L-MT-03-035, Annual Radiological Environmental Operating Report

Annual Radiological Environmental Operating Report

ML031410684
Person / Time
Site:	Monticello
Issue date:	05/09/2003
From:	Denise Wilson Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-MT-03-035
Download: ML031410684 (58)

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Monticello Nuclear Generating Plant Committed to Nuclear Excel Operated by Nuclear Management Company, LLC May 9, 2003 L-MT-03-035 Technical Specification 6.7.C.1 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 2002 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT In accordance with the Monticello Technical Specification 6.7.C.1, the Nuclear Management Company, LLC is submitting the Annual Radiological Environmental Operating Report for the year 2002.

This letter contains no new NRC commitments, nor does it modify any prior commitments.

Please contact John Fields at (763) 295-1663 with any questions or comments.

David L. Wilson Site Vice President Monticello Nuclear Generating Plant - Annual Report to the United States Nuclear Regulatory Commission, Radiological Environmental Monitoring Program, January 1 to December 31, 2002 c: Regional Administrator-lIl, NRC NRR Project Manager, NRC Resident Inspector, NRC Minnesota Department of Commerce 2807 West County Road 75

• Monticello, Minnesota 55362-9637 Telephone: 763-295-5151

• Fax: 763-295-1454 <<C;S

ATTACHMENT 1 NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO NUCLEAR GENERATING PLANT DOCKET 50-263 May 9, 2003 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION, RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM, JANUARY 1 TO DECEMBER 31, 2002 1-1

- ~E1Environmental, Inc.

Midwest Laboratory an Allegheny Technologies Co.

700 Landwehr Road

• Northbrook, IL 60062-2310 ph. (847) 564-0700 *fax (847) 564-4517 XCEL ENERGY CORPORATION MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2002 Prepared under Contract by ENVIRONMENTAL, Inc.

Midwest Laboratory Project No. 8010 Approved:

M.S.

L orato anager

PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by personnel of the Monticello Nuclear Generating Plant, operated by Nuclear Management Company, LLC for XCEL Energy Corporation. This report was prepared by Environmental, Inc.,

Midwest Laboratory.

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TABLE OF CONTENTS No. Pae Preface ...................................................... ii List of Tables ...................................................... iv List of Figures ....................................................... v

1.0 INTRODUCTION

...................................................... 1 2.0

SUMMARY

....................................................... 2 3.0 RADIOLOGICAL 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 ............................ 6 3.5 Program Modifications ............................. 6 3.6 Land Use Census ............................. 6 4.0 RESULTS AND DISCUSSION ................................................. 7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents ..................................... 7 4.2 Summary of Preoperational Data ................................................. 7 4.3 Program Findings ................................................ 8 5.0 FIGURES AND TABLES ................................................ 12

6.0 REFERENCES

................................................ 24 APPENDICES A Interlaboratory Comparison Program Results ................................................ A-1 B Data Reporting Conventions ................................................ B-1 C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Area ................................... C-1 D Sampling Location Maps ................................... D-1 iii

LIST OF TABLES No. Title Paqe 5.1 Sample Collection and Analysis Program ........................................ 13 5.2 Sampling Locations ........................................ 14 5.3 Missed Collections and Analyses ........................................ 16 5.4 Radiation Environmental Monitoring Program Summary ........................................ 19 The following tables are in the Appendices:

Appendix A A-1 Interlaboratory Comparison Program Results ......................................................... Al-1 A-2 Interlaboratory Comparison Program Results, thermoluminescent dosimeters (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 Attachment A: Acceptance criteria for spiked samples ..................................................... A2 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas ......................................................... C-2 iv

LIST OF FIGURES No. Title Page 5-1 Offsite Ambient Radiation (TLDs), inner versus outer ring locations,1987-2002 ..................... 17 5-2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (M-2, 3, 4, 5) versus control location (M-1), 1987-2002.18 Appendix D D-1 Sample collection and analysis program: TLD locations, General Area of Site Boundary. D-2 D-2 Sample collection and analysis program: TLD locations, 4 to 5 miles Distant from the Plant, Control and Special Interest locations .D-3 D-3 Sample collection and analysis program: Radiological Environmental Monitoring Program, Sampling locations. D-4 v

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory for the Monticello Nuclear Generating Plant, Monticello, Minnesota, during the period January - December, 2002. This Program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the Plant on its surroundings.

Tabulation 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, 2003a) available at the Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.

Monticello Nuclear Generating Plant is a boiling water reactor with a nominal generating capacity of 620 MWe. It is located on the Mississippi River in Wright County, Minnesota, and operated by Nuclear Management Company, LLC. Initial criticality was achieved on December 10, 1970. Full power was achieved March 5, 1971 and commercial operation began on June 30,1971.

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2.0

SUMMARY

The Radiological Environmental Monitoring Program (REMP) required by the U.S.

Nuclear Regulatory Commission (NRC) Technical Specifications and the Offsite Dose Calculation Manual (ODCM) for the Monticello Nuclear Generating Plant is described.

Results for the year 2002 are summarized and discussed.

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

No effect on the environment due to the operation of the Monticello Nuclear Generating Plant is indicated.

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3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program (REMP) at the Monticello 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 (TLD's).

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 Monticello 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 environmental samples collected from the Plant site. The Plant's monitoring program includes analyses for tritium and iodine-131. Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40. The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown. On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered as radiological impact indicators.

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Program Design and Data Interpretation (continued)

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.

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

3.2 Program Description The sampling and analysis schedule for the Radiological Environmental Monitoring Program (REMP) at the Monticello Plant is summarized in Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the plant site. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Monticello Generating Plant REMP Surveillances, Current Revision). Maps of sampling locations are included in Appendix D.

To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Also, airbome iodine is collected by continuous pumping through charcoal filters at all of these locations. Filters are changed and counted weekly. Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-131. Quarterly composites of particulate filters from each location are gamma-scanned on a HPGe detector. One of the five locations is a control (M-1), and four are indicators (M-2, M-3, M-4, M-5). One of the indicators is located in the geographical sector expected to be most susceptible to any atmospheric emissions from the Plant (highest D/Q sector).

Ambient gamma radiation is monitored at forty locations, using CaSO4:Dy dosimeters with four sensitive areas at each location: fourteen in an inner ring in the general area of the site boundary, sixteen in the outer ring within 4-5 mile radius, six at special interest locations and four control locations, outside a 10 mile radius from the plant. They are replaced and measured quarterly. An emergency set of TLDs is placed in the field along side of the regular set. The emergency TLDs are returned to EIML quarterly for annealing and repackaging.

Milk samples are collected monthly from three farms (two indicator and one control).

There are currently only two milk producers within the indicator area. Milk is collected biweekly during the growing season (May - October), because the milk animals may be on pasture. All samples are analyzed for iodine-131 and gamma-emitting isotopes.

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Program Description (continued)

Leafy green vegetables (cabbage) are collected annually from the highest D/Q garden and a control location and analyzed for iodine-131. Corn and potatoes are collected annually only if the field is irrigated by water in which liquid radioactive effluent has been discharged. Analysis is for gamma-emitting isotopes.

The terrestrial environment is also monitored by the quarterly collections of well water from four locations. Samples are analyzed for tritium and gamma-emitting isotopes.

River water is collected weekly at two locations, one upstream of the plant and one downstream. Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.

Drinking water is collected weekly from the City of Minneapolis water supply, which is taken from the Mississippi River downstream of the Plant. 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, invertebrates, and shoreline sediments. Shoreline sediment is also collected semi-annually from one downstream recreational location. All samples are analyzed for gamma-emitting isotopes.

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

(1) A partial air particulate/air iodine sample was obtained from location M-1 for the week ending 06-13-02, due to an open fuse.

(2) A partial air particulate/air iodine sample was obtained from location M-3 for the week ending 06-26-02, The circuit breaker was tripped.

(3) No air particulate/air iodine sample was available from location M-1 for the week ending 10-23-02, due to an open fuse.

(4) TLD data was not available from location M-02S for the second and third quarters, 2002. The telephone pole was removed at the Klucas residence.

The TLD was relocated to the Krone residence in the fourth quarter, 2002.

(5) Milk samples were not available from M-28 (Hoglund Farm) from July 24 through October 16, 2002. Dairy operations were temporarily discontinued.

Deviations from the program are summarized in Table 5.3.

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3.4 Laboratory Procedures The iodine-131 analyses in milk and drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method and solvent extraction and subsequent beta counting.

All gamma-spectroscopic analyses were performed with an HPGe detector. Levels of iodine-131 in cabbage and natural vegetation were determined by gamma spectroscopy.

Concentrations of airborne iodine-131 in charcoal samples were also determined by gamma spectroscopy.

Tritium was determined by a 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 data obtained. Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2000 ).

The QA Program includes participation in Interlaboratory Comparison (crosscheck)

Programs. Results obtained in the crosscheck programs are presented in Appendix A.

3.5 Program Modifications There were no program modifications made during the year 2002.

3.6 Land Use Census In accordance with the Offsite Dose Calculation Manual, sec. 07.01, a land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft2 producing fresh leafy vegetables, in each of the 16 meteorological sectors within a distance of 5 miles. The census shall also identify the locations of all milk animals and all 500 ft2 or greater gardens producing broad leaf vegetation in each of the meteorological sectors within a distance of three miles. This census shall be conducted at least once per year between the dates of May 1 and October 31. New locations shall be 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. The 2002 land use census was conducted between August 6 and September 2, 2002. The highest D/Q locations did not change from the 2001 census, Detailed land use census data are contained in the Land Use Census and Critical Receptor Report, Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.

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

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

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported accidents at nuclear facilities and no atmospheric nuclear tests conducted in the year 2002. The last reported test was made by the People's Republic of China on October 16, 1980.

4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Monticello Nuclear Generating Plant during the years 1968 to 1970, 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 to make, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross beta measurements in fallout averaged 20,600 pCi/m 2 in 1969 and 12,000 pCi/m2 in 1970. These levels are reflected throughout the various media tested.

In the air environment, ambient gamma radiation (TLDs) averaged 9.1 mRem/4 weeks during preoperational studies (1970). Gross beta in air particulates in 1969 and 1970 averaged 0.20 pCi/m3 . Present day levels have stabilized at around 0.025 pCi/m 3 .

Airborne radioiodine remained below detection levels.

In the terrestrial environment of 1968 to 1970, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-137 and Sr-90 were detected. Cs-137 levels averaged 16.7 pCi/L. Soybean crop measurements in 1969 averaged 35.5 pCi/g for gross beta and 0.3 pCi/g for Cs-137. Gross beta measured in soil averaged 51.7 pCi/g . Present day measurements for cesium-137 are below detection levels in milk and agricultural crops.

The aqueous environment was monitored by testing of river water, 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 seven separate locations from 1968 to 1970, averaged 970 pCi/L. Present day environmental samples measure below detection levels. Values for gross beta, measured from 1968 to 1970, averaged 9.8 pCi/L in upstream and downstream Mississippi River water, 4.4 pCi/L for well waters, and 18.6 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In shoreline sediments, gross beta background levels in 1970 averaged 49.8 pCi/g for both upstream and downstream samples. Cs-137 activity averaged 0.10 pCi/g for both upstream and downstream samples. Low levels of Cs-137, occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta levels in 7

4.2 Summary of Preoperational Data (continued) fish flesh averaged 5.3 pCi/g in 1968 and 1969. Cs-137, measured in 1969 and 1970, averaged 0.044 pCi/g. Gross beta background levels, in 1970, for aquatic vegetation, algae, and periphyton samples measured 86.7 pCi/g, 76.5 pCi/g, and 28.1 pCi/g respectively.

4.3 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello Nuclear Generating Plant.

Ambient Radiation (TLD's)

Ambient radiation was measured in the general area of the site boundary, at an outer ring 4 - 5 mi. distant from the Plant, at special interest areas and at four control locations. The means were similar for both inner and outer rings (15.9 and 14.8 mRem/91 days, respectively). The mean for special locations was 14.6 mRem/91 days.

The mean for control locations was 14.9 mRem/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1987 through 2001 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).

Year Inner Rinq I Outer Rinq Dose rate (mRem/91 days) 1987 15.4 15.5 1988 14.8 14.7 1989 15.0 15.4 1990 16.1 16.2 1991 15.2 15.8 1992 15.1 15.1 1993 15.6 15.9 1994 14.6 14.0 1995 14.4 13.6 1996 14.0 13.5 1997 13.3 12.8 1998 15.0 14.4 1999 15.1 14.3 2000 15.1 14.5 2001 14.3 13.7 2002 15.9 14.8 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates, Inner vs. Outer Ring locations 8

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

Year Indicators Control Concentrati npCi/m3) 1987 0.026 0.026 1988 0.030 0.030 1989 0.027 0.026 1990 0.023 0.023 1991 0.024 0.024 1992 0.023 0.023 1993 0.024 0.023 1994 0.023 0.024 1995 0.024 0.025 1996 0.023 0.023 1997 0.023 0.023 1998 0.023 0.023 1999 0.023 0.025 2000 0.027 0.026 2001 0.027 0.026 2002 0.028 0.028 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 a., 1964). It was pronounced in 1981, occurred to a lesser degree in 1982, and has not occurred since 1983. The highest averages occur during the months of January and December, and the first and fourth quarters, as seen in 1987 through 2001.

Two pieces of evidence indicate conclusively that the elevated activity observed during the first and fourth quarters 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 Prairie Island Nuclear Generating Plant, about 100 miles distant from the Monticello Nuclear Generating Plant (XCEL Energy Corp., 2003b).

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih, 1955) was detected in all samples, with an average activity of 0.063 pCi/m 3 for all locations.

All other gamma-emitting isotopes were below their respective LLD limits.

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Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.07 pCi/m3 in all samples.

Milk lodine-131 activity measured below the detection limit of 1.0 pCi/L in all samples.

Cesium-137 results were below the LLD level of 15 pCi/L in all samples.

No other gamma-emitting isotopes except naturally-occurring potassium-40, were detected in milk samples. This is consistent with the finding of the National Center for Radiological Health (1968) 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.

In summary, the milk data for 2002 show no radiological effects of the plant operation.

River Water and Drinkinq Water Tritium activity measured below the LLD of 330 pCi/L in all samples. Gross beta activity in Minneapolis drinking water averaged 2.9 pCi/L and was similar to average levels observed from 1987 through 2001. Gross beta averages are tabulated below.

Year Gross Beta (pCi/L)-

1987 2.4 1988 2.7 1989 2.6 1990 2.2 1991 2.9 1992 2.1 1993 2.6 1994 2.0 1995 2.3 1996 = 2.1 1997 2.3 1998 2.4 1999 2.2 2000 2.5 2001 2.5 2002 2.9 Average annual concentrations; Gross beta in drinking water.

Comparisons with data reported by the USEPA for Minneapolis drinking water samples collected in 1975, 1976, 1977, and 1978 indicate that concentrations of these nuclides are remaining fairly constant and are consistent with drinking water levels in other parts of the country. Gamma-emitting isotopes were below detection limits in all surface water samples. There was no indication of a plant effect.

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Well Water Tritium measured below the LLD level of 330 pCi/L in all samples. All gamma isotopic results were below detection limits. There was no indication of a plant effect.

Crops Two samples of cabbage were collected in August and analyzed for iodine-131. Levels of 1-131 measured below 0.013 pCi/g wet weight in both samples. There was no indication of a plant effect. There were no crops irrigated from the Mississippi River within 5 miles of the plant in 2002; therefore, no corn or potato samples were collected for analysis from irrigated fields.

Fish Fish samples were collected in May and October. Flesh was separated from the bones and gamma-scanned. Naturally-occurring potassium-40 was found to be similar in upstream and downstream samples (2.87 and 2.82 pCi/g wet weight, respectively). All gamma-emitting isotopes were below their respective LLD levels. There was no indication of any plant effect.

Invertebrates Samples were collected in May and October. The samples were analyzed for gamma-emitting isotopes. With the exception of naturally-occurring potassium-40, all gamma-emitting isotopes were below detection limits. There was no indication of any plant effect.

Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment collections were made in May and October and analyzed for gamma-emitting isotopes.

Low levels of cesium-137 were detected in all samples collected, averaging 0.082 pCi/g dry weight in downstream samples and 0.090 pCi/g dry weight in two control samples, indicating the influence of fallout deposition. Similar levels of activities and distribution were observed in 1978-2001. The only other gamma-emitting isotopes detected were naturally-occurring beryllium-7 and potassium-40. There was no indication of a plant effect.

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5.C FIGURES AND TABLES 12

Table 5.1. Sample collection and analysis program, Monticello Nuclear Generating Plant.

Collection Analysis Location Type and Type and Medium No. Codes (and Type)r Frequency' Frequencyc Ambient radiation 40 M-01A-M-14A CrQ Ambient gamma (TLDs) M-01B - M-16B M-01S - M-06S M-01C - M-04C Airbome Particulates 5 M-1(C), M-2, M-3, M-4, M-5 C/W GB, GS (QC of each location)

Airbome Iodine 5 M-1(C), M-2, M-3, M-4, M-5 C/W 1-131 Milk 3 M-10 (C), M-24, M-28 GIMd 1-131, GS Surface water 2 M-8(C), M-9 G/W GS(MC), H-3(QC)

Drinking water 1 M-14 G/W GB(MC), 1-131(MC)

GS (MC), H-3 (QC)

Well water 4 M-10(C), M-11, M-12, M-27 GIQ H-3, GS Edible cultivated crops -

Corn' 1 M-19 GIA GS Leafy Vegetable 2 M-27, GIA 1-131 St. Cloud Farmer's Mkt. (C)

Potatoese 1 M-21 G/A GS Fish 2 M-8(C), M-9 GISA GS (one species, edible portion)

Periphyton or invertebrates 2 M-8(C), M-9 GISA GS Shoreline sediment 3 M-8(C), M-9, M-15 G/SA GS a Location codes are defined in Table 5.2. Control stations are indicated by (C). All other stations are indicators.

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

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

c Analysis type is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, 1-131 =

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

d Milk is collected biweekly during the grazing season (May - October), if milch animals are on pasture.

e Collected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields.

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Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.

Distance and Direction from Code Type' Collection Site Sample Type b Reactor M-1 C Air Station M-1 AP, Al 11.0 mi @ 307°/NW M-2 Air Station M-2 AP, Al 0.9 mi @ 137°/SE M-3 Air Station M-3 AP, Al 0.7 ml @ 104°/ESE M4 Air Station M-4 AP, Al 0.9 mi @ 146°/SSE M-5 Air Station M-5 AP, Al 2.7 mi @ 134°/SE M-8 C Upstream of Plant SW, SS, BO, F < 1000' upstream of Plant Intake M-9 Downstream of Plant SW, SS, BO, F < 1000' downstream of Plant Discharge M-10 C Goenner Farm M, WW 12.4 mi @ 322°/NW M-11 City of Monticello WW 3.4 mi @ 126°/SE M-12 Plant Well #1 WW 0.2 mi @ 232°/SW M-14 City of Minneapolis DW 37.0 mi @ 132°/SE M-15 Montissippi Park SS 1.4 mi @ 114°/ESE M-19 River Inigated Com Fieldc M-21 River Inigated Potato Fieldc M-24 Weinand Farm M 4.8 mi @ 1780/S M-27 Wise residence (Highest DIQ Garden) VE, WW 0.6 mi @ 198°/SSW

a. Available Producer VE > 10.0 mi.

M-28 Hoglund Farm M 3.6 mi @ 300°/WNW General Area of the Site Boundary M-01A Sherbume Ave. So. TLD 0.7 mi @ 01°/N M-02A Sherbume Ave. So. TLD 0.8 mi @ 31°/NNE M-03A Sherbume Ave. So. TLD 1.3 mi @ 55°/NE M-04A Biology Station Road TLD 0.6 mi @ 91°/E M-05A Biology Station Road TLD 0.6 mi @ 1181ESE M-06A Biology Station Road TLD 0.7 mi @ 130°/SE M-07A County Road 75 TLD 0.6 mi @ 148°lSSE M-08A County Road 75 TLD 0.6 mi @ 170°/S M-09A County Road 75 TLD 0.6 mi @ 192°/SSW M-1OA County Road 75 TLD 0.5 mi @ 218°/SW M-IIA County Road 75 TLD 0.4 mi ©240°/WSW M-12A County Road 75 TLD 0.4 mi @ 260°/W M-13A North Boundary Road TLD 0.8 mi @ 324°/NW M-14A North Boundary Road TLD 0.7 mi @ 340°/NNW 14

Table 5.2. Sampling locations, Monticello Nuclear Generating Plant, (continued).

Distance and Direction from Code Typea Collection Site Sample Typeb Reactor Approximately 4 to 5 miles Distant from the Plant M-01B Sherco #1 Air Station TLD 4.6 mi @ 03°lN M-02B County Road 11 TLD 4.4 mi @ 20°/NNE M-03B County Road 73 & 81 TLD 4.3 mi @ 53°/NE M-04B County Road 73 (196th St.) TLD 4.3 mi @ 68°/ENE M-05B City of Big Lake TLD 4.4 mi @ 90°/E M-06B County Road 14 and 196th St. TLD 4.4 mi @ 117°/ESE M-07B Monte Industrial Drive TLD 4.4 mi @ 136°/SE M-08B Residence, Hwy 25 & Davidson Ave. TLD 4.7 mi @ 161°/SSE M-09B Weinand Farm TLD 4.8 mi @ 178°/S M-1OB Reisewitz Farm, Acacia Ave. TLD 4.2 mi @ 204°/SSW M-11B Vanlith Farm, 97th Ave. TLD 4.0 mi @ 226°/SW M-12B Lake Maria State Park TLD 4.2 mi @ 254°/WSW M-13B Bridgewater Station TLD 4.0 mi @ 270°/W M-14B Anderson Residence, Cty Rd. 111 TLD 4.3 mi @ 2890/WNW M-15B Red Oak Wild Bird Farm TLD 4.3 mi @ 309°/NW M-16B Sand Plain Research Farm TLD 4.3 mi @ 341 °/NNW Special Interest Locations M-01S Osowski Fun Market TLD 0.6 mi @ 234°/SW M-02Sd Edgar Klucas Residence TLD 1.1 mi @ 143°/SE M-02S Krone Residence TLD 0.5 mi @ 223°/SW M-03S Big Oaks Park TLD 1.6 ml @ 102°/E M-04S Pinewood School TLD 2.4 mi @ 129°/SE M-05S Rivercrest Christian Academy TLD 3.1 mi @ 118°/ESE M-06S Monte Public Works TLD 2.7 mi @ 134°/SE M-O1C C Kirchenbauer Farm TLD 11.5 ml @ 323°/NW M-02C C County Roads 4 and 15 TLD 11.2 mi @ 47°/NE M-03C C County Rd 19 and Jason Ave. TLD 13.0 mi @ 100°/E M-04C C Maple Lake Water Tower TLD 10.3 mi @ 2260/ SW a C' denotes control location. All other locations are indicators.

b Sample Codes:

AP Airbome particulates F Fish Al Airbome Iodine M Milk BS Bottom (river) sediments RW River Water BO Bottom organisms SS Shoreline Sediments DW Drinking Water VE Vegetation / vegetables WW Well Water C Collected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields.

d Telephone pole removed at Klucas residence. TLD relocated to Krone residence in 4th quarter, 2002.

15

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

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

Collection Reason for not Sample Analysis Location Date or conducting REMP Plans for Preventing Type Period as required Recurrence AP/AI Beta, M-01 6113/2002 Open fuse, Electrician checked sampler and 1-131 Partial sample collected. replaced fuse. Power out due to electrical storm.

AP/AI Beta, M-03 6/26/2002 Tripped breaker, Breaker reset. Power out due 1-131 Partial sample collected. to electrical storm.

TLD Ambient M-02S 6/27/2002 TLD lost. The telephone TLD temporarily replaced at location Gamma pole was removed. across the road.

Mi Gamma, M-28 7/24/2002 Hoglund Dairy temporarily Hoglund will inform the MNGP 1-131 through out of dairy business. upon resumption of operation.

10/16/2002 TLD Ambient M-02S 10/2/2002 TLD not exchanged. The TLD was relocated to a new Gamma residency.

AP/AI Beta, M-01 10/23/2002 Open fuse, Electrician checked sampler and 1-131 No sample collected. replaced fuse. Power out due to electrical storm.

16

Figure 5-1. Offsite Ambient Radiation (TLDs); Inner Ring versus Outer Ring locations.

-U- Inner

-- Outer 20- _ I 19 18 _

17 16 12

_1 __ ___

11 - _ _ _

_ co 0 - C) _t to co _ co O) 0 N N co 0O co O) C) C) C) 0) 0) 0) C) ) 0) 0) 0 0)

0) 0) 0) 0) 0) C) 0) 0) C) C) C) CD ) C) 0D 0D 17

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

lU-Indicators (M-2, 3, 4 5) 1-4 11 . .

l---

Control (M-1) I 0.031 - _

0.029 -

/Ik 0.027 E

711K__

(

_X_ _~.11 I I 0.025 - I A ~~~~~~I 1 _11 E 0.023 -

.0 CL 0.021 -

0.019 - 4 4 4 4 4 4 4 4 4 4 4 4 4 4 --

0.017 - ___ 4 4 4 4 4 4 4 4 4 4 4 4 4 +

0.015 -

co co co m

co 0DC C) O

_ N a)

C CD 0)

U)

CD tD a)

I-a) 0) 0)

0) 0 0

0 0

0) a) c) 0) 0 c) 0)

0) 0)

0) 0)

0 0) o0 N ~N 0 N

18

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Perod January-December, 2002

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD' Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analyses' Rangec Locationd Rangec Rangec Resultse TLD (Inner Ring, Gamma 56 3.0 15.9 (56/56) M-03A, N. Boundary Rd. 17.4 (4 /4) (See Control 0 General Area at (12.4-23.1) 1.0 mi @ 43°/NE (14.0-23.1) below.)

Site Boundary) mRem/91 days)

TLD (Outer Ring, Gamma 64 3.0 14.8 (64/64) M-09B, Weinand Farm 16.2 (414) (See Control 0 4-5 mi. distant) (11.6-17.3) 4.7 mi @ 180°/S (15.4-17.0) below.)

mRem/91 days)

TLD (Special Gamma 22 3.0 14.6 (22/22) M-06S, Mont. Pub. Wks. 16.7 (4 /4) (See Control 0 Interest Areas) (11.4-16.9) 2.7 mi @ 136/SE (16.4-16.9) below.)

mRem/91 days)

TLD (Control) Gamma 16 3.0 None M-03C, County Rd.19 & 16.0 (4/4) 14.9 (16/16) 0 mRem/91 days) Jason, 13.0 mi. @ 100/E (15.1-17.0) ( 12.8-17.6)

Airborne GB 259 0.005 0.028 (208/208) M-5, Air Station 0.029 (52 /52) 0.028 (51/51) 0 Particulates (0.013-0.064) 2.7 mi @ 136/SE (0.013-0.064) (0.011-0.060)

(pCi/m 3)

GS 20 Be-7 0.015 0.063 (16/16) M-5, Air Station 0.066 (4/4) 0.064 (4/4) 0 (0.042-0.088) 2.7 mi @ 136/SE (0.044-0.082) (0.051-0.078)

Mn-54 0.0010 < LLD - - < LLD 0 Co-58 0.0010 < LLD - - < LLD 0 Co-60 0.0010 < LLD - - < LLD 0 Zn-65 0.0014 < LLD - - <LLD 0 Zr-Nb-95 0.0064 < LLD - - < LLD 0 Ru-103 0.0056 < LLD - < LLD 0 Ru-106 0.0051 < LLD - - < LLD 0 Cs-134 0.0036 < LLD - - < LLD 0 Cs-137 0.0038 < LLD - - < LLD 0 Ba-La-140 0.0043 < LLD - - < LLD 0 Ce-141 0.0038 < LLD - - < LLD 0 Ce-i44 0.0049 < LLD - - < LLD 0 Airbome Iodine 1-131 259 0.07 < LLD - - < LLD 0 (pCVm 3) 19

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period January-December, 2002

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysese Rangec Locationd Rangec Rangec Resultse Milk (pCi/L) 1-131 53 1.0 < LLD < LLD 0 GS 53 K-40 200 1354 (33/33) M-24, Weinand Farm 1360 (20/20) 1316 (20/20) 0 (1165-1541) 4.8 mi @ 180'/S (1165-1479) (1194-1441)

Cs-134 15 < LLD - < LLD 0 Cs-137 15 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 River Water H-3 8 330 < LLD - - <LLD 0 (pCi/L)

GS 24 Mn-54 15 < LLD - < LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 15 < LLD - < LLD 0 Co-60 15 < LLD - - < LLD 0 Zn-65 30 < LLD - - < LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 15 < LLD - - < LLD 0 Cs-137 18 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 49 < LLD - - < LLD 0 20

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 1 50-263 Location of Facility Wright, Minnesota Reporting Peod January-December. 2002 (County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analyses' Range Locationd Rangec Range Results' Drinking Water GB 12 1.0 2.9 (12112) M-14, Minneapolis 2.9 (12/12) None 0 (pCi/L) (2.3-3.8) 37.0 mi. @ 132 /SE (2.3-3.8) 1-131 12 1.0 <LLD - - None 0 H-3 4 330 <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 0 < LLD - - None 0 Well Water H-3 16 330 < LLD - - < LLD 0 (pCi/L)

GS 16 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 38 < LLD - - < LLD 0 Crops - Cabbage 1-131 2 0.013 < LLD - - < LLD 0 (pCi/gwet) 21

Table 5.4 Radiological Environmental Monitoring Program Summary I Name of Facility Monicello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota ReporUng Period January-December, 2002 (County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Range' Locatond Rangec Rangec Resultse Fish GS 4 (pCi/g wet) K-40 0.10 2.87 (2/2) M-09, Downstream 2.87 (2/2) 2.82 (2/2) 0 (2.42-3.31) 0.2 mi @ 62°/ENE (2.42-3.31) (2.48-3.15)

Mn-54 0.014 < LLD - - < LLD 0 Fe-59 0.047 < LLD - - < LLD 0 Co-58 0.012 < LLD - - < LLD 0 Co-60 0.011 < LLD - - < LLD 0 Zn-65 0.031 < LLD - - < LLD 0 Zr-Nb-95 0.028 < LLD - - < LLD 0 Cs-134 0.017 < LLD - - < LLD 0 Cs-137 0.012 < LLD - - < LLD 0 Ba-La-140 0.064 < LLD - - < LLD 0 Ce-144 0.071 < LLD - - < LLD 0 Invertebrates GS 2 (pCUg wet) K-40 3.93 < LLD - - < LLD 0 Mn-54 0.22 < LLD - < LLD 0 Fe-59 0.48 < LLD - - < LLD 0 Co-58 0.22 < LLD - - < LLD 0 Co-60 0.21  : LLD - - < LLD 0 Zn-65 0.44 < LLD - - < LLD 0 Zr-Nb-95 0.39 < LLD - - < LLD 0 Cs-134 0.21 < LLD - - < LLD 0 Cs-137 0.22 < LLD - - < LLD 0 Ba-La-140 0.57 < LLD - - < LLD 0 Ce-144 0.89 < LLD - - < LLD 0 22

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reportng Period January-December, 2002

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analyses" Range' Locationd Range' Rangec Results' Shoreline GS 6 Sediments Be-7 0.24 0.35 (114) M-15, Montissippi Park 0.35 (1/1) 0.090 (212) 0 (pCi/g dry) 1.6 mi@ 117°lESE (0.029-0.151)

K-40 0.10 10.44 (4/4) M-09, Downstream 10.49 (2/2) 10.29 (2/2) 0 (10.39-10.57) 0.2 mi @ 62°lENE (10.40-10.57) (10.03-10.54)

Mn-54 0.022 < LLD - - <LLD 0 Fe-59 0.073 < LLD - - < LLD 0 Co-58 0.029 < LLD - - < LLD 0 Co-60 0.019 < LLD - - < LLD 0 Zn-65 0.053 < LLD - - < LLD 0 Nb-95 0.034 < LLD - - < LLD 0 Zr-95 0.044 < LLD - - < LLD 0 Ru-i 03 0.021 < LLD - - < LLD 0 Ru-106 0.18 < LLD - - < LLD 0 Cs-134 0.035 < LLD - - < LLD 0 Cs-1 37 0.019 0.082 (4/4) M-08, Upstream 0.090 (212) 0.090 (2/2) 0 (0.056-0.107) 0.2 mi @ 285°/WNW (0.029-0.151) (0.029-0.151)

Ba-La-140 0.074 < LLD < LLD 0 Ce-144 0.12 < 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.

e Non-routne 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.

23

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, 276.

Environmental, Inc., Midwest Laboratory.

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

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

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

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

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

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

Hazleton Environmental Sciences Corporation.

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

1979b through 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 Helath and Data Reports, Vol. 9, Number 12, 730-746.

Northern States Power Company.

1969. Monticello Nuclear Generating Plant, Environmental Radiation Monitoring Program, Annual Report, June 18,1968 to December 31, 1968. Minneapolis, Minnesota.

1970. Monticello Nuclear Generating Plant, Environmental Radiation Surveillance, Annual Report, January 1, 1969 to December 31, 1969. Minneapolis, Minnesota.

1971. Monticello Nuclear Generating Plant, Environmental Radiation Surveillance, Annual Report, January 1, 1970 to December 31, 1970. Minneapolis, Minnesota.

24

6.0 REFERENCES

CITED (continued)

Northern States Power Company.

Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, to December 31, 1977 through 1982 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.

1984 through 2000. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1983 through 1999 (prepared by Teledyne Brown Engineering Environmental Services, Midwest Laboratory). Northbrook, Illinois Teledyne Brown Engineering Environmental Services, Midwest Laboratory.

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

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

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

U.S. Environmental Protection Agency.

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

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

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

XCEL Energy Corporation.

2002. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2000 through 2001. (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 25

-e nEnvirtna enal, Inc.

Mdwest Laboratory an Allsheoy TechndJoges Co.

7WLa,nd.erPoad NothbM,.tL 6C02 (84fl 584-0700 I (47r)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 evaluaton program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January, 2002 through December, 2002

Appendix A Interlaboratorv ComDarison 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 intemal laboratory testing is also listed.

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

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

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

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

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

Attachment A lists acceptance criteria for spiked" samples.

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

Al

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

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

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

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

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

> 100 pCi/liter 5% of known value Tritium 4,000 pCi/liter Is = (pCiliter) =

169.85 x (known) 00933

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

> 100 pCi/liter 10% of known value Othersb 20% of known value a From EPA publication, Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-60014-81-004.

b Laboratory limit.

A2

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

Concentration (pCVL)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultf Limits S1W-940 02/20/02 Sr-89 53.0 2.5 55.3 +/- 5.0 46.6 - 64.0 S1W-940 02/20/02 Sr-90 16.6 +/-0.5 15.9 +/- 5.0 7.2 - 24.6 STW-942 02/20102 Gr. Alpha 6.5 +/-0.6 8.0 +/- 5.0 0.0 - 16.7 STW-942 02/20/02 Gr. Beta 45.7 +/-3.1 48.3 +/- 5.0 39.6 - 57.0 STW-944 02/20/02 Ba-1 33 25.8 +/-1.5 28.9 +/- 5.0 20.2 - 37.6 STW-944 02/20102 Co-60 76.9 +/-2.7 73.4 +/- 5.0 64.7 - 82.1 STW-944 02120102 Cs-I 34 38.7 +/-1.6 42.1 +/- 5.0 33.4 - 50.8 STW-944 02/20/02 Cs-137 92.9 2.7 88.8 5.0 80.1 - 97.5 STW-944 02/20/02 Ra-226 15.3 +0.7 14.3 + 2.2 10.6 - 18.0 STW-944 02/20/02 Ra-228 17.5 +/-0.4 16.9 +/-4.2 9.6 - 24.2 STW-944 02/20/02 Uranium 23.8 i 1.1 28.3 +/- 3.0 23.1 - 33.5 STW-944 02/20102 Zn-65 361.0 9.2 359.0 +/- 35.9 298.0 - 420.0 STW-951 05/22/02 Gr. Alpha 23.9 +/-2.5 22.8 +/- 5.7 13.0 - 32.6 S1W-951 05/22/02 Ra-226 5.9 + 0.5 6.1 +/- 0.9 4.5 -7.7 STW-951 05/22/02 Ra-228 5.6 +/- 0.9 4.5 +/- 1.1 2.6 - 6.5 STW-951 05/22/02 Uranium 7.6 +/- 0.2 9.3 +/-3.0 4.1 - 14.5 STW-952 05/22102 Co-60 37.9 +/-0.7 39.1 +/- 5.0 30.4 - 47.8 STW-952 05/22/02 Cs-134 14.5 0.8 17.1 +/-5.0 8.4 - 25.8 STW-952 05/22102 Cs-137 50.0 +/- 2.0 52.1 +/- 5.0 43.4 - 60.8 STW-952 05/22/02 Gr. Beta 171.0 +/- 2.5 189.0 +/-28.4 140.0 - 238.0 STW-952 05/22/02 Sr-89 28.4 +/- 4.8 31.7 +/- 5.0 23.0 - 40.4 STW-952 05/22/02 Sr-90 32.4 +/- 3.1 28.3 +/- 5.0 19.6 - 37.0 STW-953 05/22/02 H-3 13900.0 +/- 100.0 17400.0 +/- 1740.0 14400.0 - 20400.0 STW-954 05/22/02 1-131 14.6 +/- 0.3 14.7 +/-2.0 11.2 - 18.2 STW-965 08/21/02 Ba-133 71.9 +/- 2.1 80.0 +/-8.0 66.4 - 93.6 STW-965 08/21/02 Co-60 23.8 +/- 1.0 23.3 +/-5.0 14.6 - 32.0 STW-965 08/21/02 Cs-134e 62.9 +/- 1.2 71.7 +/-5.0 63.0 - 80.4 STW-965 08/21/02 Cs-137 219.3 10.7 214.0 +/-10.7 195.0 - 233.0 STW-965 08/21/02 Gr. Alpha 74.4 +/- 0.6 58.8 +/- 14.7 33.5 - 84.1 STW-965 08/21/02 Gr. Beta 26.7 OA 21.9 +/- 2.2 13.2 - 30.6 STW-965 08/21/02 Ra-226 5.0 0.5 5.0 +/- 0.8 3.7 - 6.3 STW-965 08/21/02 Ra-228 6.0 +/- 0.7 4.7 +/- 1.2 2.7 - 6.7 STW-965 08/21/02 Sr-89 28.4 +/-1.5 29.0 +/-5.0 20.3 - 37.7 STW-965 08/21/02 Sr-90 36.5 +/-1.1 36.4 +/- 5.0 27.7 -45.1 STW-965 08/21/02 Uranium 4.1 +/-0.1 5.0 +/- 3.0 0.0 - 10.2 STW-965 08/21/02 Zn-65 92.4 +/- 2.2 95.7 +/- 9.6 79.4 - 112.0 STW-966 11/20/02 Gr. Alpha 9.3 +/- 0.4 12.2 +/- 5.0 3.5 - 20.9 STW-966 11/20/02 Gr. Beta 44.7 +/-1.0 47.0 +/- 5.0 38.3 - 55.7 STW-967 11/20/02 H-3 10100.0 +/- 38.7 10200.0 +/- 1020.0 8440.0 - 12000.0 STW-968 11/20/02 Ra-226 11.6 +/-0.1 12.1 +/-1.8 9.0 - 15.2 STW-968 11/20/02 Ra-228 16.0 +/-1.4 15.1 +/-3.8 8.6 - 21.6 STW-968 11/20/02 Uranium 15.5 +/- 0.5 19.2 +/- 3.0 14.0 - 24.4 STW-969 11/20/02 1-131 6.0 +/- 0.4 6.8+/- 2.0 3.3 - O.2 Al-i

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultf Limits SIW-970 11120/02 Co-50 104.0 + 7.1 104.0 i 5.2 95.0 - 113.0 STW-970 11/20/02 Cs-134 48.2 +2.3 55.5 +/-5.0 46.8 -64.2 STW-970 11120102 Cs-137 109.0 + 12.6 117.0 +/- 5.9 107.0 - 127.0 STW-970 11120/02 Gr. Beta 252.0 26.8 288.0 t 49.5 244.0 -416.0 STW-970 11120/02 Sr-89 43.2 +/- 0.7 47.6 :t 5.0 38.9 - 56.3 SlW-970 11/20/02 Sr-90 7.5 +/- 0.2 7.6 +/- 5.0 0.0 - 16.2 STW-971 11/20/02 Gr. Alpha 74.9 +/- 1.5 103.0 +/- 25.8 58.4 - 148.0 STW-971 11/20/02 Ra-226 8.9 +/- 0.0 9.1 1.4 6.7 -11.5.

STW-971 11120/02 Ra-228 15.3 +/-0.1 17.8 4.5 10.1 -25.5 STW-971. 11/20/02 Uranium 51.7 +/- 1.6 61.7 6.2 51.0 - 72.4 Results obtained by Environmental, Inc., Midwest Laboratory as a participant In the environmental samples crosscheck program operated by Environmental Resources Associates (ERA).

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

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

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

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

No problems were Identified inthe analysis.

Al-2

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

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

2001-1 CaSO4: Dy Cards 12/24/2001 Reader 1, #1 3.98 3.71 0.12 2.79 - 5.17 2001-1 CaSO4: Dy Cards 12/24/2001 Reader 1, #1 3.98 3.38 0.09 2.79 - 5.17 2001-1 CaS04: Dy Cards 12/24/2001 Reader 1, #2 7.07 7.89 +/- 0.18 4.95 - 9.19 2001-1 CaSO4: Dy Cards 12/24/2001 Reader 1, #2 7.07 7.64 +/- 0.25 4.95 - 9.19 2001-1 CaSO4: Dy Cards 12/24/2001 Reader 1,#3 15.9 18.62 +/- 0.40 11.13 - 20.67 2001-1 CaSO4: Dy Cards 12/24/2001 Reader 1, #3 15.9 19.58 +/- 0.12 11.13 - 20.67 2001-1 CaSO4: Dy Cards 12/24/2001 Reader 1, #4 63.61 78.24 +/- 1.23 44.53 - 82.69 2001-1 CaSO4: Dy Cards 12/24/2001 Reader l,#4 63.61 79.89 +/- 2.47 44.53 - 82.69 Environmental. Inc.

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

2002-2 CaSO4: Dy Cards 12/13/2002 Reader 1,30 56.73 71.61 +/- 1.79 39.71 - 73.75 2002-2 CaSO4: Dy Cards 12/13/2002 Reader 1, 45a 25.21 33.49 +/- 1.38 17.65 - 32.77 a Precision of the distance (cm) measurement can significantly increase the error. The placement of the card holder on the table could account for the higher error.

2002-2 CaSO4: Dy Cards 12/13/2002 Reader 1,60 14.18 17.37 +/- 1.24 9.93 - 18.43 2002-2 CaSO4: Dy Cards 12/13/2002 Reader 1,75 9.08 10.65 1.02 6.36 - 11.80 2002-2 CaSO4: Dy Cards 12/13/2002 Reader 1,90 6.30 6.37 +/- 0.54 4.41 - 8.19 2002-2 CaSO4: Dy Cards 12/13/2002 Reader 1,120 3.55 4.60 +/- 0.41 2.49 - 4.62 2002-2 CaSO4: Dy Cards 12/13/2002 Reader 1,135 2.80 2.51 +/- 0.23 1.96 - 3.64 2002-2 CaSO4: Dy Cards 12/13/2002 Reader 1,150 2.28 2.22 +/- 0.28 1.60 - 2.96 A2-1

TABLE A-3. In-House "Spike" Samples Concentration (pCVL)a Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n=1b Activity Limits' SPW-1 1552 Water 117/2002 Gr. Alpha 35.33 +/- 1.83 34.57 17.29 - 51.86 SPW-1 1552 Water 1/7/2002 Gr. Beta 112.62 +/-2.44 107.70 96.93 - 118.47 SPMI-595 Milk 1/3112002 Cs-134 29.63 +/- 4.98 27.10 17.10 - 37.10 SPMI-595 Milk 1/31/2002 Cs-137 51.31 +/-7.55 50.89 40.89 - 60.89 SPMI-597 Milk 1/31/2002 Co-60 44.18 +/-7.76 41.36 31.36 - 51.36 SPMI-597 Milk 1/31/2002 Cs-1 34 20.15 +/- 5.08 22.59 12.59 - 32.59 SPMI-597 Milk 1/31/2002 Cs-137 54.88 +/- 8.32 50.89 40.89 - 60.89 SPAP-594 Air Filter 216/2002 Gr. Beta 1.58 +/- 0.02 1.55 0.00 - 11.55 SPW-599 Water 2119/2002 H-3 47607 +/- 595 50189 40151 60227 SPMI-1446 Milk 3/8/2002 1-131(G) 87.84 +/- 11.47 85.20 75.20 - 95.20 SPW-1446 Water 3/8/2002 1-131 82.98 +/- 1.20 85.20 68.16 - 102.24 SPW-1446 Water 318/2002 1-131(G) 92.75 12.87 85.20 75.20 - 95.20 SPMI-1448 Milk 3/8/2002 1-131 88.00 +/- 1.13 85.20 68.16 - 102.24 SPVE-1444 Vegetation 3/11/2002 1-131 (G) 0.39 +/- 0.04 OA2 0.25 - 0.58 SPAP-2078 Air Filter 4/8/2002 Gr. Beta 1.43 +/- 0.01 1.55 0.00 - 11.55 SPW-2080 Water 4/5/2002 H-3 49121 +/- 608 46912 37530 + 56294 SPF-2082 Fish 415/2002 Cs-I 34 0.83 +/- 0.04 0.83 0.50 - 1.16 SPF-2082 Fish 4/5/2002 Cs-I 37 1.29 +/- 0.07 1.35 0.81 - 1.89 SPMI-2084 Milk 4/8/2002 Cs-134 20.93 +/- 5.82 24.69 14.69 - 34.69 SPMI-2084 Milk 418/2002 Cs-1 37 51.83 +/- 10.23 50.56 40.56 - 60.56 SPMI-2084 Milk 418/2002 1-131 87.72 +/- 1.28 88.37 70.70 - 106.04 SPMI-2084 Milk 4/812002 1-131(G) 84.08 +/- 10.75 88.37 78.37 - 98.37 SPMI-2084 Milk 4/8/2002 Sr-90 62.81 +/- 1.99 66.85 53.48 - 80.22 SPW-2115 Water 4/8/2002 1-131 82.42 +/- 1.27 88.37 70.70 - 106.04 SPW-2116 Water 4/8/2002 Co-60 32.47 +/- 5.78 33.09 23.09 - 43.09 SPW-2116 Water 4/812002 Cs-I 34 30.80 +/- 3.60 28.80 18.80 - 38.80 SPW-2116 Water 418/2002 Cs-137 53.85 +/- 7.07 50.56 40.56 - 60.56 SPW-2116 Water 4/8/2002 1-131 (G) 79.09 +/- 7.58 88.37 78.37 - 98.37 SPW-2116 Water 418/2002 Sr-90 70.35 +/- 2.32 66.85 53.48 - 80.22 SPW-2019 Water 5/3/2002 Gr. Alpha 25.89 +/- 1.71 34.57 17.29 - 51.86 SPW-2019 Water 5/3/2002 Gr. Beta 101.19 +/- 2.37 107.70 96.93 - 118A7 SPCH-3064 Charcoal 5/11/2002 1-131(G) 0.74 +/- 0.04 0.85 0.51 - 1.18 SPW-4682 Water 7/17/2002 H-3 40856 +/-548 46179 36943 +55415 SPAP-4685 Air Filter 7/17/2002 Gr. Beta 1.58 +/- 0.02 1.55 0.00 - 11.55 W-71702S Water 7/17/2002 Fe-55 10463.00 +/- 126.00 12200.60 9760.48 - 14640.72 W-71702S Water 07/17/02 H-3 45779 +/- 583 46179 36943 +/-55415 W-71702S Water 07/17/02 Ni-63 17.02 +/- 1.50 17.10 10.26 - 23.94 SPVE-4910 Vegetation 07/22102 Sr-90 10.22 +/- 0.80 9.04 0.00 - 19.04 W-72302S Water 07/23102 Sr-90 21.43 +/- 0.97 26.55 16.55 - 36.55 W-80102S Water 08/01102 Gr. Alpha 41.25 +/- 4.58 34.45 17.23 - 51.68 W-80102S Water 08/01/02 Gr. Beta 113.66 +/- 5.30 107.70 96.93 - 118.47 W-80202S Water 08/02/02 Tc-99 16.39 +/- 0.72 14.13 2.13 - 26.13 SPW-7188 Water 10/25/02 Fe-55 20396 +/- 265 22778 18222 -27334 SPW-7190 Water 10/25102 Ni-63 227.18 +/- 11.60 170.80 102.48 - 239.12 A3-1

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

Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n=l1 b Activity Limitsc SPW-7192 Water 10/25/02 H-3 96310 871 90963 72770 -109156 SPW-7194 Water 10/25/02 C-14 42938 +/- 167 49661 29796 - 69525 SPAP-7198 Air Filter 10125102 Gr. Beta 1.65 +/- 0.02 1.53 0.00 - 11.53 SPW-7335 Water 10/30/02 Co-60 39.67 +/- 7.38 37.05 27.05 -47.05 SPW-7335 Water 10/30/02 Cs-134 33.09 +/- 5.96 34.11 24.11 -44.11 SPW-7335 Water 10/30/02 Cs-I 37 46.80 +/- 10.39 49.90 39.90 - 59.90 SPMI-7336 Milk 10/30102 Cs-134 34.40 +/- 4.99 34.11 24.11 -44.11 SPMI-7336 Milk 10/30/02 Cs-i37 46.52 +/- 8.52 49.91 39.91 - 59.91 SPF-7340 Fish 10/30/02 Cs-1 34 0.66 +/- 0.03 0.68 0.41 - 0.95 SPF-7340 Fish 10130/02 Cs-1 37 1.35 +/- 0.05 1.33 0.80 - 1.86 SPS-8102 Sediment 11/01/02 Sr-90 14.69 +/- 0.67 13.45 3.45 -23A5 8 Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCilg).

bResults are based on single determinations.

' Control 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

TABLEA-4. In-House"Blank"Samples Concentration (pCi/L)a Lab Code Sample Date Analysis Laboratory results (4.66a) Acceptance Type LLD Activityb Criteria (4.66 a)

SPW-1 1551 water 11712002 Gr. Alpha 0.47 0.45 +/- 0.39 I SPW-1 1551 water 1l72002 Gr. Beta 1.37 0.55 +/- 1.03 3.2 SPAP-590 Air Filter 1/31/2002 Co-60 1.78 100 SPAP-590 Air Filter 1/31/2002 Cs-1 34 3.42 100 SPAP-590 Air Filter 1/31/2002 Cs-I 37 2.33 100 SPAP-590 Air Filter 1/3112002 Gr. Beta 0.74 -0.096

• 0.38 3.2 SPMI-596 Milk 113112002 Co-60 3.54 10 SPMI-596 Milk 1/31/2002 Cs-134 3.24 10 SPMI-596 Milk 1/3112002 Cs-1 37 3.89 10 SPMI-596 Milk 1/3112002 K-40 1472.1 101.50 0 SPW-598 water 1/31/2002 Co-60 2.30 10 SPW-598 water 1131/2002 Cs-134 3.74 10 SPW-598 water 1/31(2002 Cs-137 3.23 10 SPW-600 water 1/31/2002 H-3 138.80 -96.5 +/- 63.40 200 SPMI-1447 Milk 3/7/2002 1-131 (G) 7.63 20 SPVE-1443 Vegetation 3/8/2002 1-131 (G) 0.02 20 SPW-1445 water 318/2002 Co-60 2.76 10 SPW-1445 water 3/812002 Cs-I 34 2.87 10 SPW-1445 water 3/812002 Cs-i 37 4.34 10 SPW-1445 water 3/8/2002 1-131 0.45 0.17 +/- 0.31 0.5 SPW-1445 water 3/8/2002 1-131 (G) 6.50 20 SPMI-1447 Milk 3/812002 1-131 0.31 0.15 +/- 0.22 0.5 SPAP-2077 Air Filter 4/812002 Gr. Beta 0.32 -0.055 +/- 0.19 3.2 SPW-2079 water 41512002 H-3 134.17 16.13 +/- 67.39 200 SPF-2081 Fish 4/5/2002 Cs-134 7.67 100 SPF-2081 Fish 4/5/2002 Cs-137 9.54 100 SPMI-2083 Milk 4/8/2002 Cs-I 34 2.90 10 SPMI-2083 Milk 4/8/2002 Cs-I 37 3.03 10 SPMI-2083 Milk 4/8/2002 1-131 0.52 -0.38 +/- 0.34 0.5 SPMI-2083 Milk 4/8/2002 Sr-90 0.48 1.29 +/- 0.36 1 SPW-2115 water 418(2002 Co-60 1.49 10 SPW-2115 water 41812002 Cs-I 34 2.09 10 SPW-2115 water 4/812002 Cs-137 3.78 10 SPW-2115 water 4/8/2002 1-131 0.50 -0.16 +/- 0.33 0.5 SPW-2115 water 418/2002 1-131 (G) 3.30 20 SPW-2115 water 41812002 Sr-90 0.66 0.10 +/- 0.32 1 SPW-2018 water 4/22/2002 Gr. Alpha 0.56 -0.24 +/-0.38 1 SPW-201 8 water 4/2212002 Gr. Beta 1.38 3.19 +/- 1.03 3.2 SPch-3063 Charcoal 5/11/2002 1-131 (G) 8.27 9.6 SPW-4683 water 711712002 H-3 129.00 -62.8 +/- 60.30 200 W-71702 water 7/1712002 Fe-55 33.61 -1.72 +/- 15.63 1000 W-71702 water 7/17/2002 Ni-63 2.56 0.71 +/-1.37 20 W-71802B water 7/18/2002 Gr. Alpha 0.48 0.31 +/- 0.36 1 W-71802B water 7118/2002 Gr. Beta 1.33 0.9 +/- 0.95 3.2 A4-1

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

W-72302 water 7/2312002 Sr-90 0.27 0.027 +/-0.13 I W-80202 water 81212002 Tc-99 0.34 -0.051 +/-0.16 10 SPW-7189 water 1012512002 Fe-55 978.21 21.77 +/- 595.33 1000 SPW-7191 water 10/25/2002 Ni-63 11.74 4.47 +/- 7.24 20 SPW-7193 water 10/25/2002 H-3 146.00 -92 +/- 65.00 200 SPAP-7199 Alr Filter 10/25/2002 Gr. Beta 0.00 -0.0024 +/- 0.00 3.2 SPMI-7333 Milk 10/30/2002 Cs-134 5.30 10 SPMI-7333 Milk 10/30/2002 Cs-137 4.80 10 SPW-7334 water 10/30/2002 Co-60 3.69 10 SPW-7334 water 10/3012002 Cs-134 5.37 10 SPW-7334 water 10/30/2002 Cs-1 37 3.90 10 SPF-7339 Fish 10/30/2002 Cs-I 34 4.69 100 SPF-7339 Fish 10/3012002 Cs-I 37 11.18 100 I Uquid sample results are reported in pCLiter, air filters( pCifilter), charcoal (pCiVcharcoal canister), and solid samples (pCi/kg).

b The activity reported Is the net activity result C Low levels of Sr-90 are still detected In the environmenL A concentraUon of (1-5 pCiVL) in milk Isnot unusual.

A4-2

TABLE A-5. In-House 'Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result CF-20,21 .11212002 Be-7 0.47 0.25 0.37 0.12 0.42 +/-0.14 CF-20, 21 1/212002 Gr. Beta 7.82 +/- 0.20 7.95 + 0.21 7.89 +/- 0.14 CF-20, 21 1/2/2002 K-40 6.65 +/- 0.55 6.53 + 0.36 6.59 +/- 0.33 CF-20, 21 1/2/2002 Sr-90 0.01 +/- 0.01 0.01 0.01 0.01 +/- 0.00 AP-11804, 11805 1/2/2002 Be-7 0.054 +/- 0.011 0.049 + 0.019 0.052 +/- 0.011 AP-11825, 11826 1/2/2002 Be-7 0.053 +/- 0.013 0.043 + 0.013 0.048 +/- 0.009 AP-11846, 11847 1/212002 Be-7 0.054 +/- 0.018 0.048 +/- 0.016 0.051 +/- 0.012 WW-150, 151 1/7/2002 Gr. Beta 1.26 +/- 0.50 1.04 +/- 0.46 1.15 +/- 0.34 MI-124, 125 1/8/2002 K-40 1332.30 +/- 158.90 1271.70 +/- 151.50 1302.00 +/-109.77 W-172, 173 1/8/2002 H-3 153.00 +/- 68.00 148.00 + 68.00 150.50 +/-48.08 SW-11698, 11699 1/8/2002 Gr. Alpha 2.51 +/- 1.36 3.71 +/- 1.80 3.11 +/-1.13 SW-11698, 11699 1/8/2002 Gr. Beta 7.68 +/- 1.33 8A9 +/- 1.43 8.09 +/-0.98 U-275, 276 1/10/2002 Gr. Alpha 1.40 +/- 1.00 1.10 +/- 1.20 1.25 i0.78 LW-356, 357 1/16/2002 Gr. Beta 3.47 +/- 0.65 2.94 +/- 0.61 3.21 +/-0.45 LW-377, 378 1116/2002 Gr. Beta 2.75 +/- 0.68 2.84 +/- 0.61 2.79 +/- 0.46 SW-525, 526 1/3012002 Gr. Alpha 0.56 +/- 0.35 0.24 +/- 0.35 0.40 +/- 0.25 SW-525, 526 1130/2002 Gr. Beta 2.29 +/- 0.41 2.58 +/- 0.39 2.43 +/-0.28 DW-504, 505 1/31/2002 Gr. Alpha 2.30 +/- 1.70 3.90 +/- 1.40 3.10 +/- 1.10 MI-649, 650 2/5/2002 K-40 1319.40 +/- 176.70 1210.80 +/- 118.20 1265.10 +/-106.29 DW-697, 698 2/612002 Gr. Beta 5.10 +/-1.20 4.70 +/- 1.20 4.90 +/- 0.85 DW-927, 928 2/812002 Sr-90 0.69 +/- 0.29 0.71 +/- 0.29 0.70 +/-021 W-973, 974 2/18/2002 Fe-55 7.29 +/- 0.97 6.86 +/- 0.94 7.08 +/- 0.68 W-1 673, 1674 2/25/2002 H-3 2640.00 +/- 155.00 2908.00 +/- 161.00 2774.00 +/- 111.74 SWT-1395, 1396 2/2612002 Gr. Beta 2.96 +/-0.59 2.29 +/- 0.53 2.63 +/- 0.40 MI-1268, 1269 2/27/2002 K-40 1460.50 +/- 162.50 1573.00 +/- 168.00 1516.75 +/- 116.87 MI-1268, 1269 2/27/2002 Sr-90 0.77 +/- 0.36 0.95 +/- 0.40 0.86 +/- 0.27 MI-1332, 1333 3/5/2002 K-40 1503.00 +/- 164.00 1305.00 +/- 168.00 1404.00 +/- 117.39 MI-1332, 1333 3/5/2002 Sr-90 1.35 +/- 0.38 1.07 + 0.40 1.21 +/- 0.28 MI-1458, 1459 3/6/2002 K-40 1411.70 +/- 166.70 1390.00 +/- 172.30 1400.85 +/- 119.87 DW-10100, 10101 3/9/2002 Gr. Alpha 4.10 +/- 1.70 1.80 +/- 1.60 2.95 +/- 1.17 DW-10111, 10112 3/912002 Gr. Alpha 7.10 +/- 2.00 8.30 +/- 2.30 7.70 +/-1.52 MI-1521, 1522 3111/2002 K-40 1270.80 +/- 103.30 1369.10 +/- 121.60 1319.95 +/-79.78 MI-1521, 1522 3/11/2002 Sr-90 1.69 +/-0.46 2.46 +/- 0.49 2.07 +/- 0.34 MI-1541, 1542 3/11/2002 K-40 1562.20 +/- 122.80 1529.30 +/- 126.10 1545.75 +/- 88.01 MI-1541, 1542 3/11/2002 Sr-90 0.85 +/-0.57 1.48 +/- 0.43 1.16 +/-0.36 LW-1651, 1652 3/14/2002 Gr. Beta 2.90 +/- 0.57 2.57 +/- 0.56 2.74 +/- 0.40 DW-10134, 10135 3/1612002 Gr. Alpha 5.60 +/- 1.90 5.40 +/- 1.60 5.50 +/-1.24 WW-1694, 1695 3/18/2002 Gr. Beta 1.79 +/- 0.59 1.53 +/- 0.50 1.66 +/- 0.39 SO-1715, 1716 3/1912002 Cs-1 37 0.03 +/- 0.01 0.02 +/- 0.01 0.03 +/- 0.01 SO-1715, 1716 3/1912002 Gr. Beta 16.50 +/- 1.70 19.10 +/- 1.70 18.80 +/-1.20 DW-10302. 10303 3/20/2002 Gr. Alpha 2.30 +/-1.40 3.30 +/- 1.60 2.80 +/- 1.06 W-1758, 1759 3/25/2002 Gr. Alpha 2.50 +/- 0.70 2.30 +/- 0.60 2.40 +/-0.46 W-1758, 1759 3125/2002 Gr. Beta 4.10 +/- 1.20 2.50 +/- 1.10 3.30 +/-0.81 A5-1

TABLEA-5. In-House"Duplicate"Samples Concentration (pCiIL)a Averaged Lab Code Date Analysis First Result Second Result Result MI-1926,1927 3/26/2002 K-40 1414.00 +/- 115.00 1316.00 +/- 128.00 1365.00 +/- 86.04 MI-1926,1927 3/26/2002 Sr-90 2.30 +/- 0.70 2.40 +/- 0.70 2.35 +/- 0.49 SWU-2010, 2011 3/26/2002 Gr. Beta 2.90 +/- 0.60 2.20 +/- 0.50 2.55 +/- 0.39 DW-10376,10377 3/27/2002 Gr. Beta 10.50 1.30 10.10 +/- 1.50 10.30 +/- 0.99 AP-2479,2480 3/28/2002 Be-7 0.064 +/- 0.023 0.068 +/- 0.014 0.066 +/- 0.013 DW-10395,10396 3/29/2002 Gr. Alpha 10.20 +/- 2.10 14.60 +/- 2.40 12.40 1.59 LW-2181, 2182 3/31/2002 Gr. Beta 2.98 +/- 0.68 1.99 +/- 0.70 2.48 +/- 0.49 LW-2181, 2182 313112002 H-3 2694.43 +/- 156.53 2688.84 +/- 156.40 2691.64 +/- 110.64 CW-2437, 2438 3131/2002 Gr. Beta 1.09 +/- 0.61 1.14 +/-0.58 1.11 i0.42 CW-2437, 2438 3/31/2002 H-3 6456.70 +/- 229.20 6292.80 i226.52 6374.75 i161.12 MI-1947,1948 4/1/2002 K-40 1421.40 +/- 130.90 1256.80 +/-104.20 1339.10 i83.65 AP-2458, 2459 4/1/2002 Be-7 0.077 +/- 0.011 0.081 i0.010 0.079 +/-0.008 DW-10409,10410 4/1/2002 Gr. Alpha 39.30 +/- 4.00 35.30 i3.60 37.30 +/-2.69 MI-2052, 2053 4/3/2002 K-40 1283.70 +/- 103.20 1434.80 +/-147.90 1359.25 +/-90.17 MI-2052, 2053 413/2002 Sr-90 0.81 +/- 0.36 0.75 +/- 0.35 0.78 +/-0.25 AP-2711, 2712 4/3/2002 Be-7 0.071 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 W-938,939 4/9/2002 Ni-63 1.73 +/- 0.10 1.82 +/- 0.10 1.78 +/- 0.07 SS-2202, 2203 419/2002 Gr. Beta 5.83 +/- 1.16 5.52 +/-1.19 5.67 +/- 0.83 SS-2202, 2203 4/9/2002 K-40 5.75 +/- 0.48 6.11 +/-0.51 5.93 +/- 0.35 F-2307, 2308 4/10/2002 K-40 2.75 +/- 0.27 2.49 +/-0.32 2.62 +/- 0.21 DW-10476,10477 4/12/2002 Gr. Alpha 5.10 +/- 1.30 3.90 i1.60 4.50 +/- 1.03 W-2244,2245 4/15/2002 Gr. Beta 1.70 +/- 1.10 1.60 i1.00 1.65 +/- 0.74 DW-10509,10510 4/17/2002 Gr. Alpha 6.00 +/- 2.00 7.30 i1.80 6.65 +/- 1.35 SW-2690, 2691 4/24/2002 Gr. Beta 2.25 +/- 0.68 2.15 +/- 0.59 2.20 +/- 0.45 SO-2903, 2904 4/2412002 Be-7 1.22 +/- 0.57 0.78 +/- 0.43 1.00 +/- 0.36 SO-2903, 2904 4/2412002 Cs-137 0.13 +/- 0.05 0.09 +/- 0.05 0.11 +/-0.04 S0-2903,2904 412412002 K-40 21.06 +/- 1.48 19.91 +/-1.16 20.48 +/- 0.94 DW-10562,10563 4/24/2002 Gr. Alpha 2.17 +/- 1.13 3.25 +/-1.54 2.71 +/- 0.96 DW-10578,10579 4/2912002 Gr. Alpha 8.20 +/- 2.20 7.40 +/- 2.00 7.80 +/- 1A9 SO-2861, 2862 4/30/2002 Cs-I 37 236.40 +/- 46.00 200.70 +/-52.60 218.55 +/- 34.94 SO-2861, 2862 4130/2002 K-40 10191.00 +/- 784.60 11025.00 +/- 941.30 10608.00 +/- 612.71 SL-2819, 2820 5/112002 Be-7 805.70 +/- 301.50 860.73 +/- 164.80- 833.22 i171.80 SL-2819, 2820 5/1/2002 Gr. Beta 5566.00 +/- 124.00 5359.00 +/-122.00 5462.50 i86.98 SL-2819, 2820 5/1/2002 K-40 5524.00 +/- 632.90 5277.50 +/-431.40 5400.75 i382.97 SL-2840,2841 511/2002 Be-7 1010.00 +/-352.10 872.95 +/- 181.70 941.48 i198.11 SL-2840, 2841 5/1/2002 Gr. Beta 4399.00 +/- 221.80 4593.00 +/- 276.00 4496.00 +/-177.04 SL-2840,2841 5/1/2002 K-40 2422.80 +/- 352.10 2254.10 +/-371.40 2338.45 +/- 255.89 MI-2971, 2972 5/5/2002 K-40 1338.90 +/- 83.44 1345.80 +/-100.90 1342.35 +/- 65.47 MI-2971, 2972 5/5/2002 Sr-90 0.83 +/- 0.47 1.65 +/- 0.46 1.24 +/-0.33 DW-10603,10604 516/2002 Gr. Alpha 6.30 +/- 1.70 5.50 +/-1.60 5.90 +/-1.17 SS-3037, 3038 5/912002 K-40 11585.00 +/-749.00 11612.00 +/- 787.00 11598.50 +/- 543.22 MI-3124, 3125 5/13/2002 K-40 1329.50 103.80 1373.00 +/-107.40 1351.25 +/- 74.68 MI-3208, 3209 5/14/2002 K-40 1494.60 +/- 158.40 1462.60 +/- 182.50 1478.60 +/- 120.83 LW-3250,3251 5/15/2002 Gr. Beta 3.14 +/- 0.55 3.28 +/- 0.63 3.21 +/-0.42 A5-2

TABLE A-5. In-House 'Duplicate" Samples Concentration (pC!/L)a Averaged Lab Code Date Analysis First Result Second Result Result CF-3292,3293 5/20/2002 K-40 1.33 +/- 0.99 1.14 0.91 1.23

• 0.67 MI-3376, 3377 5/26/2002 K-40 1333.30 +/- 159.40 1090.70 +/- 143.40 1212.00 +/- 107.21 MI-3418, 3419 5/28/2002 K-40 1423.70 +/- 121.30 1443.30 +/- 164.30 1433.50 +/- 102.11 SWT-3461, 3462 5/28/2002 Gr. Beta 2.65 +/- 0.54 3.28 +/- 0.60 2.97 +/- 0.40 S0-3503, 3504 5/2912002 Cs-I 37 0.17 +/- 0.04 0.18 0.05 0.18 +/- 0.03 SO3503, 3504 5/29/2002 Gr. Beta 27.72 +/- 2.26 25.45 +/- 2.03 26.58 +/- 1.52 S0-3503, 3504 5/29/2002 K-40 20.24 +/- 1.19 20.54 +/- 1.24 20.39 +/- 0.86 SL-3545. 3546 6/3/2002 Gr. Beta 4436.00 +/- 90.00 4281.00 89.00 4358.50 +/- 63.29 SL-3545, 3546 6/3/2002 K-40 4684.20 +/- 734.40 5242.50 +/- 884.50 4963.35 +/- 574.82 DW-10754, 10755 6/6/2002 Sr-90 0.50 +/- 0.30 0.60 +/- 0.30 0.55 +/- 0.21 SW-3777, 3778 6/11/2002 Gr. Alpha 4.42 +/- 1.50 2.97 +/- 1.40 3.70 +/- 1.02 SW-3777, 3778 6111/2002 Gr. Beta 7.57 +/- 1.22 6.83 i 1.16 7.20 +/- 0.84 MI-3798, 3799 611112002 K-40 1433.40 +/- 124.20 1401.20 +/-96.96 1417.30 +/- 78.78 LW-3924, 3925 6/13/2002 Gr. Beta 3.05 +/- 0.59 3.38 +/- 0.72 3.21 +/- 0.46 MI-3966, 3967 6/1812002 K-40 1245.20 +/- 109.20 1340.20 +/- 121.90 1292.70 +/- 81.83 MI-3966, 3967 6/18/2002 Sr-90 2.38 +/- 0.51 2.63 +/- 0.52 2.51 +/- 0.36 MI-3987, 3988 6/19/2002 Sr-90 0.98 +/- 0.35 0.97 +/- 0.35 0.98 +/- 0.25 MI-4095, 4096 6/25/2002 K-40 1256.10 +/- 138.20 1199.00 i 128.30 1227.55 +/- 94.29 SWU-4221, 4222 6/2512002 Gr. Beta 6.89 +/- 1.97 5.38 1.93 6.13 +/- 1.38 LW-4179, 4180 6/27/2002 Gr. Beta 2.37 +/- 0.58 2.00 +/- 0.62 2.19 +/- 0.42 G-4329, 4330 7/1/2002 Be-7 1394.80 +/- 538.40 1098.10 +/- 437.40 1246A5 +/- 346.84 G-4329, 4330 7/112002 Gr. Beta 8.10 +/- 0.27 8.00 i 0.25 8.05 +/- 0.18 G-4329,4330 7/112002 K-40 7758.20 +/- 1100.00 8399.80 i 929.30 8079.00 +/- 720.00 SL-4337, 4338 7/1/2002 Be-7 1480.90 +/- 223.80 1726.40 +/- 552.60 1603.65 +/- 298.10 SL-4337, 4338 7/1/2002 Cs-I 37 32.30 +/- 14.70 50.97 i27.10 41.64 +/- 15.42 SL-4337, 4338 7/1/2002 Gr. Beta 5262.40 +/- 522.10 5432.40 i 540.00 5347.40 +/- 375.56 SL-4337, 4338 7/1/2002 K-40 2249.00 +/- 381.90 2989.90 i 509.60 2619.45 +/-318A1 AP-4864, 4865 7/1/2002 Be-7 0.085 +/- 0.009 0.085 +/- 0.006 0.085 +/- 0.006 MI-4359. 4360 7/2/2002 K-40 1390.10 +/- 168.30 1567.40 +/- 194.30 1478.75 +/- 128.53 AP-4569,4570 712/2002 Be-7 0.068 +/- 0.016 0.086 +/-0.018 0.077 +/- 0.012 AP-4843,4844 7/212002 8e-7 0.077 +/- 0.016 0.090 +/- 0.020 0.084 +/- 0.013 AP-4789,4790 7/3/2002 Be-7 0.080 +/- 0.013 0.078 +/- 0.015 0.079 +/- 0.010 SWU-4810, 4811 7/3/2002 Gr. Beta 2.40 +/- 0.84 2.47 +/- 0.88 2A3 +/- 0.61 MI-4548,4549 7/912002 K-40 1511.80 +/- 127.00 1446.80 +/- 101.80 1479.30 +/- 81.38 DW-4737, 4738 7/1212002 1-131 0.52 0.20 0.49 +/- 0.29 0.51 +/-0.18 MI-4632, 4633 7/1512002 K-40 1198.40 +/- 114.10 1371.30 +/- 146.90 1284.85 +/- 93.00 MI-5054, 5055 7/3012002 K-40 1428.80 +/- 105.60 1344.30 +/- 106.40 1386.55 +/- 74.95 G-5075, 5076 7/3012002 Gr. Beta 7.11 0.07 6.99 +/- 0.07 7.05 +/- 0.05 SWU-5124, 5125 7/3012002 Gr. Beta 1.75 +/- 0.84 1.90 +/- 0.78 1.82 +/- 0.57 G-5151, 5152 7/31/2002 Be-7 1.82 +/- 0.30 2.05 +/- 0.32 1.93 +/- 0.22 G-5151, 5152 7/31/2002 K-40 5.13 0.66 5.72 +/- 0.70 5.42 +/- 0.48 MI-5103, 5104 8/2/2002 K-40 1415.90 +/- 70.57 1423.80 i 129.20 1419.85 +/- 73.61 LW-5434, 5435 815/2002 Gr. Beta 2.77 +/- 0.35 2.26 +/- 0.35 2.52 +/- 0.25 MI-5215, 5216 8/7/2002 K-40 1361.10 +/- 111.90 1358.30 +/- 115.80 1359.70 +/- 80.52 A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result MI-5355, 5356 8/13/2002 K-40 1405.00 165.80 1549.30 +/- 114.40 1477.15 i 100.72 F-5413, 5414 8/15/2002 Gr. Beta 2.37 0.10 2.55 i 0.10 2.46 i 0.07 F-5413, 5414 8/15/2002 K-40 1.47 0.32 1.73 i 0.43 1.60 i 0.27 MI-5603,5604 8/26/2002 1-131 0.64 +/- 0.34 0.52 i 0.36 0.58 i 0.25 MI-5603, 5604 8/26/2002 K-40 1353.60 +/- 83.13 1261.40 +/- 117.80 1307.50 +/-72.09 MI-5578, 5579 8/27/2002 K-40 1301.50 +/- 161.70 1381.60 +/- 111.20 1341.55 98.12 VE-5682, 5683 8/28/2002 Be-7 0.29 +/- 0.10 0.25 +/- 0.11 0.27 + 0.08 VE-5682, 5683 8/28/2002 Gr. Beta 3.79 +/- 0.08 3.80 +/- 0.08 3.79 +/- 0.06 VE-5682, 5683 8/28/2002 K-40 3.06 0.29 3.31 +/- 0.42 3.18 +/-0.25 WW-6188, 6189 8/31/2002 Gr. Beta 2.70 +/- 0.57 2.30 +/- 0.57 2.50 +/- 0.41 SL-5724, 5725 9/3/2002 Be-7 0.92 +/- 0.19 1.04 +/- 0.23 0.98 +/- 0.15 SL-5724, 5725 9/3/2002 Cs-1 37 0.05 +/- 0.02 0.05 +/- 0.02 0.05 +/- 0.01 SL-5724, 5725 9/3/2002 K-40 2.09 +/- 0.31 2.28 +/- 0.48 2.19 +/- 0.29 MI-5877, 5878 9/9/2002 K-40 1340.70 +/- 165.00 1168.50 +/- 172.50 1254.60 +/- 119.35 MI-6157,-6158 9/19/2002 K-40 1372.10 115.10 1136.50 +/- 222.70 1254.30 +/- 125.34 MI-6258, 6259 9/24/2002 K-40 1328.60 +/- 201.00 1312.60 +/- 118.60 1320.60 +/- 116.69 LW-6278.6279 9/30/2002 Gr. Beta 2.15 0.51 1.70 +/- 0.50 1.93 +/- 0.36 Ml-6385, 6386 10/1/2002 K-40 1297.10 i 168.90 1310.10 +/- 128.30 1303.60 +/- 106.05 BS-6453, 6454 10/1/2002 Cs-137 0.43 +/- 0.03 0.44 +/- 0.03 0.44 + 0.02 BS-6453, 6454 10/1/2002 K-40 16.50 0.51 16.80 +/- 0.61 16.65 +/- 0.40 S0-6478, 6479 10/1/2002 Cs-I 37 0.074 0.016 0.070 +/- 0.016 0.072 +/- 0.011 SO-6478, 6479 10/112002 Gr. Alpha 8.01 +/- 4.36 7.55 +/- 4.57 7.78 +/- 3.16 S0-6478, 6479 10/1/2002 Gr. Beta 30.41 +/- 4.07 33.04 +/- 4.28 31.73 +/- 2.95 SO-6478, 6479 10/1/2002 K-40 19.82 0.53 20.39 +/- 0.58 20.10 +/- 0.39 SO-6478, 6479 10/1/2002 Sr-go 0.087 +/- 0.017 0.094 +/- 0.020 0.091 +/- 0.013 AP-6641, 6642 10/1/2002 Be-7 0.070 +/- 0.016 0.080 +/- 0.015 0.075 +/- 0.011 MI-6544,6545 10/2/2002 K-40 1331.60 +/- 125.20 1326.50 +/- 171.60 1329.05 +/- 106.21 AP-6857, 6858 10/3/2002 Be-7 0.062 +/- 0.015 0.071 +/- 0.015 0.066 +/- 0.010 AP-6857. 6858 10/3/2002 Be-7 0.062 +/- 0.015 0.071 +/- 0.015 0.066 i 0.010 AP-6857, 6858 10/3/2002 Be-7 0.062 0.015 0.071 +/-0.015 0.066 +/-0.010 BS-6620, 6621 10/712002 Co-60 0.090 +/- 0.020 0.11 i0.02 0.10 +/- 0.01 BS-6620, 6621 10/7/2002 Cs-I 37 0.62 +/- 0.04 0.63 i 0.03 0.62 +/- 0.02 BS-6620, 6621 10/7/2002 K-40 11.38 0.48 10.78 i 0.52 11.08 +/- 0.35 MI-6651. 6652 10/8/2002 K-40 1565.50 +/- 141.00 1640.60 i 189.20 1603.05 i 117.98 G-6760, 6761 10/9/2002 Be-7 2.17 +/-0.49 2.31 +/- 0.34 2.24 +/- 0.30 G-6760, 6761 10/9/2002 K-40 6.24 1.00 6.61 +/- 0.60 6.42 +/- 0.58 SWU-7054, 7055 10/10/2002 Gr. Beta 3.09 +/- 0.57 2.06 +/- 0.52 2.57 +/- 0.39 U-7126, 7127 10111/2002 Gr. Beta 2.61 +/- 1.24 2.61 +/- 1.08 2.61 +/- 0.82 XW-7768, 7769 10/14/2002 Cs-1 37 2.25 +/- 0.25 2.09 +/- 0.18 2.17 +/- 0.15 XW-7768, 7769 10/14/2002 H-3 2.63 +/- 0.10 2.64 +/- 0.10 2.64 +/- 0.07 F-7148, 7149 10/15/2002 K-40 2.57 +/- 0.28 2.98 +/- 0.44 2.77 +/- 0.26 BS-7337,7338 10/23/2002 Co-60 0.083 +/- 0.025 0.073 +/- 0.031 0.078 +/- 0.020 BS-7337, 7338 10/23/2002 Cs-I 37 0.082 +/- 0.019 0.11 +/-0.04 0.10 +/- 0.02 BS-7337, 7338 10/23/2002 Gr. Beta 12.54 +/- 2.34 12.99 +/- 2.22 12.77 +/- 1.61 SO-7407, 7408 10/29/2002 Cs-137 0.14 +/- 0.03 0.15 +/- 0.03 0.15 +/- 0.02 S0-7407, 7408 10/29/2002 Gr. Beta 16.73 +/-2.21 16.62 +/- 2.27 16.67 +/- 1.58 S0-7407, 7408 10/29/2002 K-40 12.05 +/- 0.61 12.27 +/- 0.81 12.16 +/- 0.51 A5-4

TABLE A-5. In-House "Duplicate" Samples Concehtration (pCiL) 3 Averaged Lab Code Date Analysis First Result Second Result Result MI-7428, 7429 10/2912002 K-40 1542.60 +/-213.00 1355.80 +/- 185.70 1449.20 +/- 141.29 pw-7621, 7622 10/30/2002 Gr. Beta 2.22 +/- 0.92 2.08 +/- 0.83 2.15 +/- 0.62 TD-7653, 7654 10/31/2002 H-3 11122.00 +/-387.00 11259.00 +/-390.00 11190.50 +/- 274.71 SW-7569, 7570 11/5/2002 Gr. Beta 15.90 +/- 1.25 16.24 +/- 1.27 16.07 +/-0.89 SW-7569, 7570 11/5/2002 K-40 14.79 +/- 1.48 14.79 1.48 14.79 +/- 1.05 SO-8010, 8011 1117/2002 Cs-137 0.11 +/- 0.02 0.11 +/- 0.03 0.11 +/-0.02 SO.8010,8011 11/7/2002 K-40 6.91 +/-0.54 7.21 +/-0.54 7.06 +/- 0.38 VE-7747,7748 11t11/2002 Gr. Beta 3.59 +/- 0.05 3.25 +/- 0.05 3.42 +/- 0.03 VE-7747, 7748 11111/2002 K-40 3.17 +/- 0.36 3.26 +/- 0.46 3.22 +/- 0.29 MI-7789, 7790 11/13/2002 K-40 1319.30 +/- 167.60 1301.20 +/- 140.70 1310.25 +/- 109.41 DW-8082,8083 11/29/2002 1-131 0.83 +/- 0.24 0.98 +/- 0.22 0.90 +/-0.16 SW-8054, 8055 12/2/2002 Gr. Beta 2.60 +/- 0.46 2.21 + 0.39 2.41 +/- 0.30 SW-8054, 8055 12/212002 K-40 1.44 +/- 0.14 1.43 +/- 0.14 1.44 +/- 0.10 MI-8105,8106 12/4/2002 K-40 1300.60 +/-111.30 1315.40 +/-108.90 1308.00 +/- 77.86 TD-8298, 8299 1215/2002 H-3 355.00 +/- 94.00 469.00 +/- 99.00 412.00 +/- 68.26 MI-8396, 8397 12117/2002 K-40 1409.20 +/- 117.30 1449.60 +/- 108.60 1429.40 +/- 79.93 SWT-8654, 8655 12/30/2002 Gr. Beta 1.63 +/- 0.50 1.40 +/- 0.47 1.51 +/- 0.34 AP-8783, 8784 12/31/2002 Be-7 0.044 +/- 0.009 0.042 +/- 0.008 0.043 +/- 0.006 Note: Duplicate analyses are performed on every twentieth sample received in-house. Fsesults are not listed for those analyses with activities that measure below the LLD.

a Results are reported in units of pCilL, except for air filters (pCil/Filter), food products, vegetation, soil, sediment (pCilg).

A5-5

TABLE A-6. Departrnent of Energys Mixed Analyte Performance Evaluation Program (MAPEP)a.

Concentrationb Known Control Lab Code Type Date Analysis Laboratory result Activity Limitsr STW-939 water 12/01/01 Am-241 1.25 +/- 0.0 1.19 +/- 0.0 0.83 - 1.6 STW-939 water 12101101 Co-57 138.9 +/-0.5 143 +/- 14.3 100.1 - 185.9 STW-939 water 12101/01 Co-60 139.1 +/- 0.5 141 +/-14.1 98.7 - 183.3 STW-939 water 12101/01 Cs-134 25.16 +/-0.2 28.5 +/-0.3 19.95 -37.1 STW-939 water 12101/01 Cs-137 279.96 +/- 0.9 286 + 28.6 200.2 - 371.8 STW-939d water 12/01/01 Fe-55 19.68 +/-23.2 9.2 +/-0.9 6.44 - 12.0 STW-939 water 12101/01 Mn-54 253.64 +/- 0.9 246 +/-0.2 172.2 -319.8 STW-939 water 12101/01 Ni-63 65.88 +/-1.9 88.3 +/-8.8 61.81 -114.8 STW-939e water 12101(01 Pu-238 0.060 +/-0.01 0.0 +/-0.0 STW-939 water 12/01/01 Pu-239140 2.79 +/- 0.0 2.99 +/- 0.3 2.09 - 3.9 STW-939 water 12/01/01 Sr-90 4.88 +/- 0.3 4.8 +/- 0.5 3.36 - 6.2 STW-939 water 12/01/01 U-233/4 0.89

• 0.0 0.98 +/- 0.1 0.69 - 1.3 STW-939 water 12/01/01 U-238 6.75 +/- 0.0 7.8 +/-0.8 5.46 - 10.1 STW-939 water 12101/01 Zn-65 70.6 +/- 1.1 67.3 +/- 6.7 47.11 - 87.5 STSO-955 soil 10/16/02 Am-241 40.54 +/- 2.7 43.5 +/- 4.4 30.45 -56.6 STSO-955 soil 10/16/02 Co-57 210.58 +/-2.0 246 +/- 24.6 172.2 -319.8 STSO-955 soil 10/16/02 Co-60 84.38 +/-0.9 87.5 +/-8.8 61.25-113.8 STSO-955 soil 10(16/02 Cs-134 692.6 +/- 2.1 862 +/- 86.0 603.4 - 1120.6 STSO-955 soil 10116102 Cs-137 96.98 +/-1.7 111 11.1 77.7-144.3 STSO-955 soil 10/16/02 Fe-55 1714.6+/-299.6 1870 +/-187.0 1309 -2431.0 STSO-955 soil 10/16102 Mn-54 509.74 +/- 3.4 546 +/-54.6 382.2 - 709.8 STSO-955 soil 10116/02 Ni-63 890.6 +/- 22A 1180 +/- 118.0 826 - 1534.0 STSO-955 soil 10/16/02 Pu-238 34.04 +/- 6.0 33.3 +/- 3.3 23.31 -43.3 STSO-955 soil 10/16102 Pu-239140 68.7 +/- 3.7 72.9 +/- 7.3 51.03 - 94.8 STSO-955e soil 10/16/02 Sr-90 1.5 +/-3.0 0.0 +/-0.0 STSO-955 soil 10/16/02 U-23314 166.33 +/- 3.8 229 +/- 22.9 160.3 -297.7 STSO-955 soil 10/16/02 U-238 169.76 +/- 3.8 220 +/- 22.0 154 - 286.0 STSO-955 soil 10/16/02 Zn-65 783.59 +/- 6.4 809 +/- 80.9 566.3 - 1051.7 a 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 t All results are in Bqlkg or Bq/L as requested by the Department of Energy.

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

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

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

A6-1

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

Concentrationa EML Control Lab Code Type Date Analysis Laboratory results Resultb Limitsc STW-945 Water 03/01/02 Am-241 1.68 +/- 0.14 1.47 0.79 - 1.41 STW-945 Water 03/01/02 Co-60 349.20 +/- 2.60 347.33 0.80 - 1.20 STW-945 Water 03/01/02 Cs-134 3.40 +/- 0.60 3.36 0.80 - 1.30 STW-945 Water 03/01/02 Cs-137 57.20 +/- 1.70 56.07 0.80 - 1.22 STW-945 Water 03/01/02 Pu-238 0.45 +/- 0.11 0.49 0.74 - 1.20 STW-945 Water 03/01/02 Pu-239140 4.47 +/- 0.28 4.22 0.79 - 1.20 STW-945 Water 03/01/02 Sr-90 7.40 i 1.30 7.58 0.69 - 1.34 STW-945 Water 03/01/02 Uranium 3.27 i 0.43 2.84 0.75 - 1.33 STW-946 Water 03/01/02 Gr. Alpha 265.40 i 7.70 375.00 0.58 - 1.29 STW-946 Water 03/01/02 Gr. Beta 930.60 i 12.00 1030.00 0.61 - 1.43 STW-946 Water 03/01/02 H-3 226.30 i 32.70 283.70 0.78 - 2.45 STSO-947 Soil 03/01/02 Ac-228 55.00 +/- 5.50 51.17 0.80 - 1.38 STSO-947 Soil 03/01/02 Am-241 8.30 +/- 3.30 10.93 0.65 - 2.28 STSO-947 Soil 03/01/02 Bi-212 49.20 +/- 12.40 53.43 0.50 - 1.34 STSO-947 Soil 03/01/02 Bi-214 46.60 +/- 3.10 53.93 0.78 - 1.42 STSO-947 Soil 03/01/02 Cs-I 37 1401.60 +/- 9.10 1326.67 0.80 - 1.25 STSO-947 Soil 03/01/02 K-40 613.10 +/- 28.10 621.67 0.80 - 1.32 STSO-947 Soil 03/01/02 Pb-212 51.60 +/- 2.60 51.10 0.78 - 1.32 STSO-947 Soil 03/01/02 Pb-214 52.00 +/- 3.60 54.37 0.76 - 1.46 STSO-947 Soil 03/01/02 Pu-239140 14.70 i 3.50 19.10 0.71 - 1.30 STSO-947 Soil 03101/02 Sr-90 52.10 i 6.30 53.76 0.67 - 2.90 STSO-947 Soil 03/01/02 Th-234 122.40 i6.30 89.30 0.63 - 2.35 STSO-947 Soil 03/01102 Uranium 143.40 i9.40 194.77 0.71 - 1.32 STVE-948 Vegetation 03/01102 Am-241 3.10 i2.20 2.23 0.73 - 2.02 STVE-948 Vegetation 03/01/02 Cm-244 0.90 +/- 0.80 1.32 0.61 - 1.59 STVE-948 Vegetation 03/01/02 Co-60 13.50 +/-2.10 11:23 0.80 - 1.44 STVE-948 Vegetation 03/01/02 Cs-1 37 350.40 +/- 6.30 313.67 0.80 - 1.31 STVE-948 Vegetation 03/01/02 K-40 940.80 +/- 45.60 864.33 0.79 - 1.39 STVE-948d Vegetation 03/01/02 Pu-239/40 16.90 +/- 0.70 3.54 0.69 - 1.31 STVE-948 Vegetation 03/01/02 Sr-90 543.40 +/- 24.90 586.28 0.55 - 1.21 STAP-949 Air Filter 03/01/02 Am-241 0.09 +/- 0.05 0.09 0.70 - 2.34 STAP-949 Air Filter 03/01102 Co-60 30.10 +/- 0.30 30.52 0.80 - 1.26 STAP-949 Air Filter 03/01102 Cs-1 37 29.90 +/- 0.30 28.23 0.80 - 1.32 STAP-949 Air Filter 03/01/02 Mn-54 40.40 +/- 0.40 38.53 0.80 - 1.35 STAP-949 Air Filter 03/01/02 Pu-238 0.05 +/- 0.02 0.06 0.67 - 1.33 STAP-949 Air Filter 03101102 Pu-239140 0.15 +/- 0.02 0.19 0.73 - 1.26 STAP-949 Air Filter 03/01/02 Sr-90 3.40 +/- 0.40 4.83 0.53 - 1.84 STAP-949 Air Filter 03/01/02 Uranium 0.80 +/- 0.20 0.61 0.79 - 2.10 STAP-950 Air Filter 03/01/02 Gr. Alpha 0.43 +/- 0.04 0.53 0.73 - 1.43 STAP-950 Air Filter 03/01/02 Gr. Beta 1.34 +/- 0.05 1.30 0.76 - 1.36 STW-959 Water 09/01/02 Am-241 3.00 +/- 0.10 3.04 0.79 - 1.41 STW-959 Water 09/01/02 Co-60 258.40 +/- 2.30 268.67 0.80 - 1.20 STW-959 Water 09/01/02 Cs-I 34 50.80 +/- 3.30 60.20 0.80 - 1.30 STW-959 Water 09/01/02 Cs-1 37 80.10 +/- 0.30 81.43 0.80 - 1.22 STW-959 Water 09/01/02 Cs-137 80.10 +/- 0.30 81.43 0.80 - 1.22 STW-959 Water 09/01/02 Am-241 3.00 +/-0.10 3.04 0.79 - 1.41 A7-1

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

Concentration° EML Control Lab Code Type Date Analysis Laboratory results Resultc Limitsd STW-959 Water 09101/02 Am-241 3.00 +/- 0.10 3.04 0.79 - 1.41 STW-959 Water 09/01102 Co-60 258.40 +/- 2.30 268.67 0.80 - 1.20 STW-959 Water 09/01/02 Cs-134 50.80 +/- 3.30 60.20 0.80 - 1.30 STW-959 Water 09/01/02 Cs-137 80.10 +/- 0.30 81.43 0.80 - 1.22 STW-959 Water 09/01/02 H-3 271.90 20.90 227.30 0.78 -2.45 STW-959 Water 09/01/02 Pu-238 4.40 +/- 0.20 4.33 0.74 - 1.20 STW-959 Water 09/01/02 Pu-239/40 2.10 +/- 0.10 2.07 0.79 - 1.20 STW-959 Water 09/01/02 Sr-90 9.70 +/- 0.20 8.69 0.69 - 1.34 STW-959 Water 09/01/02 Uranium 5.60 +/- 0.10 6.84 0.75 - 1.33 STW-960 Water 09/01/02 Gr. Alpha 204.90 +/- 3.20 210.00 0.58 - 1.29 STW-960 Water 09/01/02 Gr. Beta 852.00 +/- 26.50 900.00 0.61 - 1.43 STSO-961 Soil 09/01/02 Ac-228 47.60 +/- 1.90 42.30 0.80 - 1.38 STSO-961 Soil 09/01/02 Am-241 7.80 +/- 1.40 6.77 0.65 - 2.28 STSO-961 Soil 09/01/02 Bi-212 45.60 +/- 1.70 45.93 0.50 - 1.34 STSO-961e Soil 09/01102 Bi-214 48.80 +/- 4.90 33.63 0.78 - 1.42 STSO-961 Soil 09/01/02 Cs-1 37 819.60 +/- 16.60 829.33 0.80 - 1.25 STSO-961 Soil 09/01102 K-40 705.30 +/-31.40 637.67 0.80 - 1.32 STSO-961 Soil 09/01/02 Pb-212 48.60 +/- 3.40 43.43 0.78 - 1.32 STSO-961 Soil 09/01/02 Pb-214 51.10 +/- 5.10 35.20 0.76 - 1.46 STSO-961' Soil 09/01/02 Pu-239/40 20.20 +/-0.80 12.90 0.71 - 1.30 STSO-961 Soil 09/01/02 Sr-90 38.50 +/- 0.10 41.16 0.67 -2.90 STSQ.961 9 Soil 09/01/02 Uranium 58.90 +/- 0.70 87.21 0.71 - 1.32 STVE-962 Vegetation 09/01/02 Arn-241 2.10 +/- 0.30 2.25 0.73 - 2.02 STVE-962 Vegetation 09/01/02 Cm-244 1.00 +/- 0.30 1.25 0.61 - 1.59 STVE-962 Vegetation 09/01/02 Co-60 11.80 +/- 1.50 9.66 0.80 - 1.44 STVE-962 Vegetation 09/01/02 Cs-I 37 340.30 +/- 16.80 300.67 0.80 - 1.31 STVE-962 Vegetation 09/01/02 K-40 1646.00 +/- 74.40 1480.00 0.79 - 1.39 STVE-962 Vegetation 09/01/02 Pu-239/40 3.00 +/- 0.30 3.43 0.69 - 1.31 STVE-962 Vegetation 09/01/02 Sr-90 345.60 +/- 97.80 476.26 0.55 - 1.21 STAP-963" Air Filter 09/01/02 Am-241 0.20 +/- 0.01 0.19 0.70 -2.34 STAP-963 Air Filter 09/01/02 Co-60 24.90 +/- 0.60 23.00 0.80 - 1.26 STAP-963 Air Filter 09/01/02 Cs-1 37 38.00 +/- 1.30 32.50 0.80 - 1.32 STAP-963 Air Filter 09/01/02 Mn-54 60.80 +/- 1.90 52.20 0.80 - 1.35 STAP-963h Air Filter 09/01/02 Pu-238 0.11 +/- 0.02 0.12 0.67-1.33 STAP-963h Air Filter 09/01/02 Pu-239/40 0.21 +/- 0.01 0.21 0.73 - 1.26 STAP-963 Air Filter 09/01/02 Sr-90 5.20 +/- 0.20 5.56 0.53 - 1.84 STAP-963h Air Filter 09/01/02 Uranium 0.41 +/- 0.04 0.47 0.79 - 2.10 STAP-964 Air Filter 09/01/02 Gr. Alpha 0.40 +/- 0.10 0.29 0.73 - 1.43 STAP-964 Air Filter 09/01102 Gr. Beta 0.80 +/- 0.10 0.87 0.76 - 1.36 a Results are reported in BqlL with the following exceptons: Air Filters (Bq/Filter), Soil and Vegetabon (Bqlkg).

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.

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

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

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

gThe analysis was repeated induplicate; result of reanalysis, 87.05 +/- 7.64 Bq/kg.

h STAP-963, Calculations for the transuranics analyses (Am-241, Uranium, Pu-238, -239/40) were not converted to Bq/total filter.

The data listed is the result of recalculation.

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 Ume 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; x:i+/- s and x2 +/- s2 21 2 Reported result: x +/- s; where x = (1/2) (xl + x2) and s = (1/2) S2 3.2. Individual results: <L1, <L2 Reported result: <L, where L = lower of Li and L2 3.3. Individual results: x +/- s, L Reorted result: x +/- s if x 2L; <L otherwise.

4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x 1 , x2 . .. Xn are defined as follows:

- I _ _ _ _ _ _~~~X-x X= Ex s=

4.2 Values below the highest lower limit of detection are not included in the average.

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

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

4.5 In rounding off, the following rules are followed:

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

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

B-2

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

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

Air (pCiVm 3 ) Water (pCi/L)

Gross alpha 1 x 10- 3 Strontium-89 8,000 Gross beta 1 Strontium-90 500 Iodine-1 3 1 b 2.8 x 10-1 Cesium-137 1,000 Barium-1 40 8,000 Iodine-131 1,000 Potassium-40c 4,000 Gross alpha 2 Gross beta 10 Tritium 1 x 106 a Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.

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

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

c A natural radionuclide.

C-2

APPENDIX D Sampling Location Maps D-1

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