Text

2003 Annual Radiological Environmental Operating Report
	ML041410069
Person / Time
Site:	Monticello
Issue date:	05/14/2004
From:	Thomas J. Palmisano; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-MT-04-030
	Download: ML041410069 (60)
	v • d • e

Monticello Nuclear Generating Plant Commilted toft NcarExcellen~ Operated by Nuclear Management Company, LLC May 14, 2004 L-MT-04-030 Technical Specification 6.7.C.1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 License No. DPR-22 2003 Annual Radiological Environmental Operating Report In accordance with the Monticello Nuclear Generating Plant Technical Specification 6.7.C.1, the Nuclear Management Company, LLC is submitting the Annual Radiological Environmental Operating Report for the year 2003.

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.

Thomas J. Palmisano Site Vice President, Monticello Nuclear Generating Plant Nuclear Management Company, LLC Enclosure cc: Administrator, Region IlIl, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce

, i'- z' 5 2807 West County Road 75

Monticello, Minnesota 55362-9637 L-1"'e:;

Telephone: 763-295-5151

Fax: 763-295-1454

ENCLOSURE 1 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION, RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM, JANUARY 1 TO DECEMBER 31,2003 58 pages follow

- Environmental, Inc.

Midwest Laboratory an Akyx Tedlogfes u Co.

700 Landwehr Road

Northbrook, IL 60062-2310 ph. (847) 564-07C0

fax (847) 5644517

- 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, 2003 Prepared under Contract by ENVIRONMENTAL, Inc.

Midwest Laboratory Project No. 8010 Approved:

L na M.S.

Aara a

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PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by 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. Pge 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 Iiii

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 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-I 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 .......................................... 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) .18 Appendix D D-1 Sample collection and analysis program: TLD locations, Inner Ring ....... D-2 D-2 Sample collection and analysis program: TLD locations, Outer Ring. D-3 D-3 Sample collection and analysis program: TLD locations, Controls................................................................................................................................... D-4 D-4 Sample collection and analysis program: Radiation Environmental Monitoring Program, Milk sampling locations .D-5 D-5 Sample collection and analysis program: Radiation Environmental Monitoring Program, Milk, Sludge, Ground water and Shoreline sampling locations .D-6 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, 2003.

This Program monitors the levels of radioactivity Inthe 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, 2004a) available at the Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.

The 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 2003 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-1 37, 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. The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141. These isotopes are released In small quantities by nuclear power plants, but to date their major source of Injection into the general environment has been atmospheric nuclear testing. Nuclides of the final group, manganese-54, iron-59, cobalt-58 and -60, and zinc-65, are activation products and arise from activation of corrosion products. They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.

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Program Design and Data Interpretation (continued)

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

To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Also, airborne 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 determined by gamma spectroscopy. One of the five locations is a control (M-1), and four are indicators (M-2, M-3, MA, 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.

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.

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Program Description (continued)

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-5 for the week ending 02-05-03. The timer was suspect.

(2) Surface water samples could not be collected from M-08 (upstream) for the weeks ending 02-05-03 and 02-12-03. The shoreline was frozen.

(3) No milk was available from M-10 (Goenner Farm) in April, 2003. Dairy operations were discontinued.

(4) Milk samples were not available from M-28 (Hoglund Farm) June 4th through September 9th, 2003. Dairy operations were temporarily discontinued.

(5) No air particulate/air iodine samples were available from location M-4 for the weeks ending 06-25-03 through 07-16-03. A power outage occurred during an electrical storm. A partial sample was obtained for the week ending 07-23-03, after power restoration.

(6) TLD data was not available from location M-09A for the second quarter, 2003. The TLD was missing in the field.

(7) A partial air particulate/air Iodine sample was obtained from location M-1 for the week ending 09-17-03. Power was Interrupted due to an open fuse.

(8) TLD data was not available from location M-01A for the third quarter, 2003. The TLD was missing Inthe field.

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.

Gamma-spectroscopic analysis Is performed using a high-purity germanium (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, 2003 ). The QA Program includes participation In Interlaboratory Comparison (crosscheck) Programs. Results obtained in the crosscheck programs are presented inAppendix A.

3.5 Program Modifications The Goenner Farm (M-10) discontinued dairy operations in March, 2003. The Campbell Farm was added as a replacement in May, 2003.

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 I 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 2003 land use census was conducted between August 18 and September 26, 2003.

More accurate mapping by GPS in 2003 resulted in increased D/Q values by sector (> 20%) for four of the nearest residence and five nearest garden locations. Milk animal locations remained unchanged. The Trefethen garden was Identified as the highest D/Q value garden plot. The highest DIQ locations for nearest residence and nearest milk animal did not change from the 2002 census.

Details of the land use census 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 2003. 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 pCim 2 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 pCim 3. Present day levels have stabilized at around 0.025 pCim 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 pCVL.

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 pCl/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 pCVL In upstream and downstream Mississippi River water, 4.4 pCi/L for well waters, and 18.6 pCVL 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 pCig 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 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.

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4.3 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the 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 (15.6 and 15.0 mRem/91 days, respectively). The mean for special locations was 14.6 mRem/91 days. The mean for control locations was 15.9 mRem/91 days. Dose rates measured at the Inner and outer ring locations were similar to those observed from 1988 through 2002 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).

Year Inner Rin Outer Ring Dose rate (mRemI91 days) 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 2003 15.6 15.0 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 (0.027 pCVm ) and were similar to levels observed from 1988 through 2002.

The results are tabulated below.

Year Indicators Control 3

Concentration (DCifM 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 2003 0.027 0.027 Average annual gross beta concentrations in airborne particulates.

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

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

The highest averages usually occur during the months of January and December, and the first and fourth quarters, as seen in 1988 through 2003.

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 0.060 pCim for all locations. All other gamma-emitting isotopes were below their respective LLD limits.

Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.07 pCim3 in all samples.

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Milk lodine-131 activity measured below the detection limit of 1.0 pCVL in all samples. Cesium-137 results were below the LLD level of 15 pCVL in all samples.

No other gamma-emitting Isotopes except naturally-occurring potassium-40, were detected in 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 2003 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 3.0 pCVL and was similar to average levels observed from 1988 through 2002. Gross beta averages are tabulated below.

Year Year Gross Beta (pCi/L) 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 2003 3.0 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.

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

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Crops Cabbage and broccoli were collected in September from three locations and analyzed for Iodine-131. Levels of 1-131 measured below 0.020 pCig 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 2003; 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 (3.57 and 3.50 pCig 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 0.051 pCig dry weight in downstream samples and 0.035 pCig dry weight in two control samples, indicating the influence of fallout deposition.

Similar levels of activities and distribution have been observed since 1978. The only other gamma-emitting isotopes detected were naturally-occurring beryllium-7 and potassium-40. There was no indication of a plant effect.

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5.0 FIGURES AND TABLES 12

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

Collection Analysis Location Type and Type and Medium No. Codes (and Typer Frequencyb Frequencyc Ambient radiation 40 M-01A-M-14A CIQ Ambient gamma (TLDs) M-01B - M-16B M-01S - M-06S M-01C - M-04C Airborne Particulates 5 M-1(C), M-2, M-3, MA, M-5 C/W GB, GS (QC of each location)

Airborne Iodine 5 M-1(C), M-2, M-3, M4, M-5 C/W 1-131 Milk 3 M-10 (C), M-24, M-28 G/Md 1-131, GS Surface water 2 M-8(C), M-9 GS(MC), H-3(QC)

Drinking water I M-14 GN1 GB(MC), 1-131(MC)

GS (MC), H-3 (QC)

Well water 4 M-1O(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)

Potatoes" I M-21 GIA GS Fish 2 M-8(C), M-9 G/SA 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 GISA GS 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: Cl = continuous, GI = grab. Collection frequency is coded as follows:

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

cAnalysis type Is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, 1-131 =

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

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

eCollected 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 Nuctear Generating Plant.

Distance and Direction from Code Types Collection Site Sample Typeb 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 0/SE M-3 Air Station M-3 AP, Al 0.7 mi @ 104'/ESE M-4 Air Station M4 AP, Al 0.9 mi @ 146°/SSE M-5 Air Station M-5 AP, Al 2.7 mi @ 1341/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 M10d C Goenner Farm M, WW 12.4 ml @ 322°/NW M-10 C Campbell Farm M, WW 10.6 mi @ 357/N M-11 City of Monticello WW 3.4 mi @ 1261/SE M-12 Plant Well #1 WW 0.2 ml @ 232°/SW M-14 City of Minneapolis DW 37.0 ml @ 132°/SE M-15 Montissippi Park SS 1.4 mi @ 114°/ESE M-19 River Irrigated Corn Fleldc M-21 River Irrigated Potato Fieldc M-24 Weinand Farm M 4.8 mi @ 178°/S M-27 Wise residence VE, WW 0.6 mi @ 198°/SSW

a. Available Producer VE > 10.0 mi.

M-28 Hoglund Farm M 3.6 mi @ 300I/WNW M-29 Trefethen residence (Highest DIQ Garde VE 1.1 mi @ 143/SE General Area of the Site Boundary M-01A Sherburne Ave. So. TLD 0.7 mi @ 01lN 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°1E M-05A Biology Station Road TLD 0.6 mi @ 118°/ESE M-06A Biology Station Road TLD 0.7 mi @ 130°/SE M-07A County Road 75 TLD 0.6 mi @ 148°/SSE M-08A County Road 75 TLD 0.6 mi @ 170°/S M-09A County Road 75 TLD 0.6 mi @ 192°/SSW M-10A County Road 75 TLD 0.5 mi @ 218°/SW M-1 IA County Road 75 TLD 0.4 mi @ 2401WSW 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 ADproximatelv 4 to 5 miles Distant from the Plant M-011B Sherco #1 Air Station TLD 4.6 ml @ 03°/N M-02B County Road 11 TLD 4.4 ml @ 20°/NNE M-03B County Road 73 & 81 TLD 4.3 ml @ 53°/NE M-04B County Road 73 (196th St.) TLD 4.3 ml @ 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 ml @ 136°/SE M-08B Residence, Hwy 25 & Davidson Ave. TLD 4.7 ml @ 161°lSSE M-09B Weinand Farm TLD 4.8 ml @ 178/S M-IOB3 Reisewitz Farm, Acacia Ave. TLD 4.2 ml @ 204°/SSW M-IIB3 Vanlith Farm, 97th Ave. TLD 4.0 ml @ 226°/SW M-12B Lake Maria State Park TLD 4.2 ml @ 254°NWSW M-13B Bridgewater Station TLD 4.0 ml @ 270°W M-14B Anderson Residence, Cty Rd. 111 TLD 4.3 ml @ 289°/WNW M-15B Red Oak Wild Bird Farm TLD 4.3 ml @ 309°/NW M-16B Sand Plain Research-Farm TLD. 4.3 ml @ 341°/NNW Special Interest Locations M-01S Osowski Fun Market TLD 0.6 ml @ 234/SW M-02Sd Edgar Klucas Residence TLD 1.1 ml @ 143°/SE M-02S Krone Residence TLD 0.5 ml @ 223/SW M-03S Big Oaks Park TLD 1.6 mi@ 102°/E M-04S Pinewood School TLD 2.4 ml @ 129/SE M-05S Rivercrest Christian Academy TLD 3.1 ml @ 118°/ESE M-06S Monte Public Works TLD 2.7 ml @ 134°1SE M-01C C Kirchenbauer Farm TLD 11.5 ml @ 323°/NW M-02C C County Roads 4 and 15 TLD 11.2 ml @ 47/NE M-03C C County Rd 19 and Jason Ave. TLD 13.0 ml @ 100°/E M-04C C Maple Lake Water Tower TLD 10.3 ml @ 226°/ SW

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

b Sample Codes:

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

d Goenner Farm replaced by Campbell In 2nd Qtr. of 2003.

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:

Plans for Preventing Recurrence AP/Al Beta, M-05 02-05-03 Low volume due to bad timer Replaced timer.

1-131 or Interrupted flow.

SW Gamma M-08 02-05-03 Shoreline frozen None required.

02-12-03 Ml Gamma, M-10 4/9/2003 Goenner Farm out of Replaced by Campbell Farm In 1-131 dairy business. May, 2003.

Ml Gamma, M-28 6/4/2003 Hoglund Dairy temporarily Hoglund will Inform the MNGP 1-131 through out of dairy business. upon resumption of operation.

9/9/2003 Resumed 09-24-03.

AP/AI Beta, M-04 6/25/2003 Power unavailable to sampler Collections will resume upon 1-131 through after electrical storm. restoration of power.

7/16/2003 Power restored 07-18-03.

AP/AI Beta, M-04 7/2312003 Partial sample collected. Collection resumed upon restoration 1-131 of power to the sampler site.

Power restored 07-18-03.

TLD Ambient M-09A 7/3/2003 TLD run over by tractor. Replaced TLD and TLD holder, Gamma moved further from edge of field.

AP/AI Beta, M-01 9/17/2003 Open fuse, Electrician checked sampler and 1-131 Partial sample collected. replaced fuse.

TLD Ambient M-01A 10/3/2003 TLD missing In the field due to Replaced TLD and TLD holder.

Gamma road construction.

16

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

-l- Inner Ring

-D- Outer Ring 20-19: It __ _ __ - -- _ ___ _

1 2 1 8 - __ -r - - n n z - a - -

16 -* _

S I

_ _ nN 10 - -

coco Ic0C 40 ~ - C'J 0)

Cl)

0) 0 0)

)

(

0) )

~0

0) 0) 0 0D

(

~ 0D a) 0) 0) 0) 0) 0) 0) 0) 0) 0) 0) 0) 0 0 CO 0O 17

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

- indicators (M-2, 3, 4, 5) n Aepc I -- Control (M-1)

I 0.0U3 0.033 0.031 r i . . .

I -

0.029 0.027 I I I I I 0.025 I

PL.

X 0.023 &-4 0.

CL I I I I I I 0.021 0.019 0.017 I I I I I I I I I I I I I I I 0.015 co 0 n 00 -0 0 C¢ 0 .>

0 aIf

-- t0CD 0 0 0 0 $

C0) 0- C' 8C0

_ _ _C . C_ C_

18

Table 5.4 Radiological Environmental Monitortng Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period January-December. 2003 (County. State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)e Mean (F)' Mean (F)' Routine (Units) Analyses' Range' Locationd Range' Range' Results" TLD (Inner Ring, Gamma 54 3.0 15.6 (54154) M-12A 17.6 (414) (See Control 0 General Area at (14.3-18.3) 0.7 ml @ 273'W (17.0-18.3) below.)

Site Boundary) mRem/91 days)

TLD (Outer Ring, Gamma 64 3.0 15.0 (64/64) M-09B. Weinand Farm 16.2 (4 /4) (See Control 0 4-5 ml. distant) (12.4-16.9) 4.7 ml @ 180I/S (15.9-16.4) below.)

mReml91 days)

TLD (Special Gamma 24 3.0 14.6 (24124) M-06S, Mont. Pub. Wks. 16.8 (414) (See Control 0 Interest Areas) ( 11.4-17.9) 2.7 mi @ 136/SE (16.3-17.9) below.)

mRem/91 days)

TLD (Control) Gamma 16 3.0 None M-03C, County Rd.19 & 15.9 (414) 15.0 (16/16) 0 mRem/91 days) Jason, 13.0 mi. @ 100'/E (15.0-17.0) (13.2-17.0)

Airbome GB 254 0.005 0.027 (202/202) M-4 0.028 (47147) 0.027 (52/52) 0 Particulates (0.011-0.053) 0.9 ml © 150'/SSE (0.014-0.048) (0.011-0.048)

(pCVm 3)

GS 20 Be-7 0.015 0.062 (16/16) M4 0.068 (414) 0.055 (414) 0 (0.036-0.095) 0.9 ml @ 150'/SSE (0.041-0.095) (0.036-0.071)

Mn-54 0.0011 < LLD < LLD 0 Co-58 0.0012 < LLD . < LLD 0 CoG-0 0.0010 < LLD < LLD 0 Zn-65 0.0013 < LLD < LLD 0 Zr-Nb-95 0.0068 < LLD - < LLD 0 Ru-103 0.0070 < LLD - < LLD 0 Ru-106 0.0069 < LLD - < LLD 0 Cs-134 0.0020 < LLD - < LLD 0 Cs-1 37 0.0026 < LLD < LLD 0 Ba-La-140 0.0042 < LLD < LLD 0 Ce-141 0.0061 < LLD . < LLD 0 Ce-144 0.0049 < LLD - < LLD 0 Airbome Iodine 1-131 254 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, 2003

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (Ffc Mean (FY Mean (F)' Routine (Units) Analyses' Range' Locationd Range' Range' Results" Milk (pCUIL) 1-131 48 1.0 < LLD . < LLD 0 GS 48 K-40 200 1338 (30130) M-24, Weinand Farm 1352 (19119) 1337 (18/18) 0 (1085-1489) 4.8 ml @ 180-1S (1085-1489) (1082-1537)

Cs-134 15 < LLD . < LLD 0 Cs-137 15 < LLD . < LLD 0 Ba-La-140 15 < LLD . < LLD 0 RiverWater H-3 8 330 < LLD . < LLD 0 (pCUL)

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 8a-La-140 15 < LLD - < LLD 0 Ce-144 61 < LLD - < LLD 0 20

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, 2003

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)' Mean (F)c Mean (F)' Routine (Units) Analysesa Range' Locationr Range' Range' Results Drinking Water GB 12 1.0 3.0 (12V12) M-14, Minneapolis 3.0 (12V12) None 0 (pCVL) (2.3-4.1) 37.0 mi. © 132 /SE (2.3-4.1) 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-40 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 45 < LLD None 0 Well Water H-3 16 330 < LLD < LLD 0 (pCUL)

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 49 < LLD < LLD 0 Crops - Cabbage 1-131 3 0.020 < LLD < LLD 0 (pCVgwet) 21

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, 2003 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)' Mean (F)' Mean (F)' Routine (Units) Analyses' Range' Location' Range' Range' Results Fish GS 4 (pCVg wet) K-40 0.10 3.50 (2/2) M-08, Upstream 3.57 (2/2) 3.57 (212) 0 (2.98-4.01) 0.2 mi @ 285/WNW (3.44-3.70) (3.44-3.70)

Mn-54 0.017 < LLD < LLD 0 Fe-59 0.048 < LLD < LLD 0 Co-58 0.019 < LLD - < LLD 0 Co-60 0.015 < LLD < LLD 0 Zn-65 0.042 < LLD < LLD 0 Zr-Nb-95 0.027 < LLD < LLD 0 Cs-134 0.019 < LLD < LLD 0 Cs-137 0.021 < LLD < LLD 0 Ba-La-140 0.091 < LLD < LLD 0 Ce-144 0.12 < LLD < LLD 0 Invertebrates GS 4 (pCVg wet) K-40 5.03 < LLD < LLD 0 Mn-54 0.17 < LLD < LLD 0 Fe-59 0.42 < LLD < LLD 0 Co-58 0.17 < LLD < LLD 0 Co-60 0.19 < LLD < LLD 0 Zn-65 0.40 < LLD < LLD 0 Zr-Nb-95 0.13 < LLD < LLD 0 Cs-134 0.23 < LLD < LLD 0 Cs-137 0.17 < LLD < LLD 0 Ba-La-140 0.29 < LLD <LID 0 Ce-144 0.94 < 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 Reporting Period January-December. 2003 (County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)e Mean (F)' Mean (F)' Routine (Units) Analyses _ Range' Locationd Range' Range' Results' Shoreline GS 6 Sediments Be-7 0.21 < LLD M-08, Upstream 0.35 (1/1) 0.35 (111) 0 (pC/g dry) 0.2 mi @ 285A1WNW K-40 0.10 9.75 (414) M-08, Upstream 10.14 (212) 10.14 (212) 0 (8.29-11.05) 0.2 ml @ 2851/WNW (9.99-10.28) (9.99-10.28)

Mn-54 0.025 <LLD < LLD 0 Fe-59 0.084 c LLD < LLD 0 Co-58 0.029 < LLD < LLD 0 Co-60 0.021 < LLD < LLD 0 Zn-65 0.057 < LD < LLD 0 Nb-95 0.033 <LD . < LLD 0 Zr-95 0.048 < LLD < LLD 0 Ru-103 0.042 < LLD < LLD 0 Ru-106 0.16 < LLD < LLD 0 Cs-134 0.034 < LLD < LLD 0 Cs-1 37 0.021 0.051 (3/3) M-09, Downstream 0.060 (1/1) 0.035 (2/2) 0 (0.031-0.060) 0.2 ml @ 621ENE (0.029-0.040)

Ba-La-140 0.28 < 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, andlor station code (Table 2) and (2) by distance (miles) and direction relative to reactor site.

Non-routine results are those which exceed ten times the control station value. If no control station value Is available, the result Is considered non-routine if It exceeds ten time the typical preoperational value for the medium or location.

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

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

2003. Quality Assurance Program Manual, Rev. 1, 01 October 2003.

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

2003. Quality Control Program, Rev. 1, 21 August 2003.

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

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, Intemational Atomic Energy Agency. p.125.

XCEL Energy Corporation.

2003. Prairie- Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2000 through 2003. (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 25

- % Environmental, Inc.

Mdwest Laboratory mi PJlghen Tse cgo5 Co.

70O3Lmd*trRoad *ihWcktL e0Q2

847) 5440700 ta (847) 8-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates InIntercomparison 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 InAppendix A. TLD Intercomparison results, In-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A Is updated four times a year; the complete Appendix Is Included InMarch, June, September and December monthly progress reports only.

January, 2003 through December, 2003

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

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

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

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

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

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

Table A-5 list results of the in-house 'duplicateu 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 InTable 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 ANALYSES, One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pCilliter or kg 5.0 pCi/liter

> 100 pCi/liter or kg 5% of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCi/liter

> 50 pCIlliter or kg 10% of known value Strontium-90b 2 to 30 pCilliter or kg 5.0 pCi/liter

> 30 pCi/liter or kg 10% of known value Potassium40 > 0.1 giliter or kg 5% of known value Gross alpha . 20 pCI/liter 5.0 pC/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 pCilniter Is = (pCi/liter) =

169.85 x (known) 00 9 33

> 4,000 pCi/liter 10% of known value Radium-226,-228 0.1 pCiAiter 15% of known value Plutonium 0.1 pCi/liter, gram, or sample 10% of known value lodine-131, 55 pCi/liter 6.0 pCilliter lodine-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

' From EPA publication, *Environmental Radioactivity Laboratory Inlercomparlson Studies Program, Fiscal Year. 1981-1982, EPA-60014-81-004.

b Laboratory limit.

A2

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

Concentration (pCVL)

Lab Code Date Analysis Laboratory ERA Control Resultb Result' Limits STW-973 02/17103 Sr-89 17.0

0.5 15.9 t5.0 7.2 -24.6 SIW-973 02117103 Sr-90 8.9

0.3 9.0

5.0 0.4 -17.7 S1W-974 02/17/03 Ba-133 14.5

0.9 19.5 *5.0 10.8 - 28.2 STW-974 02/17/03 Co-60 37.5

0.9 37A

5.0 28.7 - 46.1 STW-974 02/17103 Cs-134 18.2

0.6 17.8

5.0 9.1 - 26.5 STW-974 02/17103 Cs-1 37 42.7

1.0 44.2

5.0 35.5 - 52.9 STW-974 02/17103 Zn-65 56.8

2.2 60.3

6.0 49.9 -70.7 STW-975d 02/17103 Gr. Alpha 18.4 *0.3 37.6 *9.4 21.3 - 53.9 S1W-975 02/17103 Gr. Beta 11.7 +/-0.5 8.6 *5.0 0.0 -17.2 S1W-976 02/17/03 Ra-226 4.1

0.1 4.7 *0.7 3.5 - 6.0 STW-976 02/17/03 Ra-228 7.6 *0.5 6.5 +/- 1.6 3.7 -9.3 STW-976 02/17103 Uranium 52.9

1.9 53.7

5.4 44.4 - 63.0 STW-983 05/19/03 H.-3 1290.0 + 25.0 1250.0

331.0 678.0 - 1820.0 STW-984 05/19103 1-131 19.7 +/- 1.3 20.8

3.0 15.6 - 26.0 STW-985 05/19/03 Gr. Alpha 54.4

3.0 70.3

17.6 39.9 -101.0 STW-985 05/19103 Ra-226. 14.9

0.2 16.5 *2.5 12.2 - 20.8 STW-985 05/19103 Ra-228 13.1 +/-0.6 10.3 t2.6 5.8 - 14.8 STW-985 05/19/03 Uranium 14.5

0.4 15.1 *E3.0 9.9 - 20.3 STW-986 05/19103 Co-60 56.9

8.6 63.8

5.0 55.1 - 72.5 STW-986e 05/19/03 Cs-134 61.6

6.6 75.7 *k5.0 67.0 - 84A STW-986 05/19/03 Cs-137 143.0

1.2 150.0 *7.5 137.0 - 163.0 STW-986 05/19/03 Gr. Beta 309.0 *2.7 363.0

54.5 269.0 - 457.0 STW-986 05/19/03 Sr-89 33.1 i 0.2 31.3

5.0 22.6 -40.0 STW-986 05/19/03 Sr-90 28.8 *1.3 27.4

5.0 18.7 - 36.1 SIW-988 08/18/03 Ra-226 13.3

1.1 13.4 *2.0 9.9 - 16.9 STW-988 08/18/03 Ra-228 11.5

1.0 12.5

3.1 7.1 -17.9 S1W-988 08/18/03 Uranium 12.3

0.4 11A *+/-3.0 6.2 - 16.6 STW-989 08/18/03 Ba-133 18.1 *1.9 20.7

5.0 12.0 - 29.4 STW-989 08118103 Co-60 35.9 *l: 1.3 37.4 5.0 28.7 - 46.1 STW-989 08/18/03 Cs-134 32.6

1.8 32.6

5.0 23.9 -41.3 STW-989 08/18/03 Cs-137 48.3 + 0.6 44.3

5.0 35.6 - 53.0 STW-989 08/18/03 Zn-65 58.9

2.1 60.2

6.0 49.8 - 70.6 SlW-990 08/18/03 Gr. Alpha 41.8

3.4 56.2 +/-16.3 36.9 - 93.3 STW-990 I 08/18/03 Gr. Beta 51.3 + 3.0 31.6

5.0 22.9 - 40.3 STW-991 08/18/03 Sr-89 57.2 +/- 4.3 58.8

5.0 50.1 - 67.5 STW-991 08118/03 Sr-90 21.2

0.9 20.6 +/- 5.0 11.9 - 29.3 AM-1

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

Concentration (pCilL)

Lab Code Date Analysis Laboratory ERA Control Result Result! Limits STW-997 11118103 Gr.Alpha 37.0

2.0 29.5 :7.4 16.7 -42.3 STW-997 11/18/03 Gr. Beta 26.5

0.8 26.3 5.0 17.6 -35.0 STW-998 11118/03 1-131 14.8 : 0.3 16.5 +/-3.0 11.3 -21.7 STW-999 11/18/03 Ra-226 17.2

1.1 17.8 +/-2.7 13.2 -22.4 STW-999 11/1 8/03 Ra-228 6.6 +/- 0.3 6.8 +/- 1.7 3.8 - 9.7 STW-999 11/18/03 Uranium 11.7

0.3 11.7 +/- 3.0 6.5 -16.9 STW-1000 11/18/03 H-3 15900.0 + 174.0 14300.0 +/- 1430.0 11800.0 - 16800.0 STW-1001 11/18103 Gr. Alpha 32.9 +/- 0.3 54.2 i3.0 30.7 -77.7 STW-1001 11/18103 Ra-226 16.5 :t0.9 16.1 +2.4 11.9 -20.3 STW-1001 11/18/03 Ra-228 6.2 +/-0.5 5.5 +/- 1.4 3.1 -7.9 STW-1001 11/18/03 Uranium 9.7 +/- 1.5 9.3 +/- 13.6 4.1 -14.5 STW-1002 11118/03 Co-60 27.7 +/-1.9 27.7 +/-5.0 19.0 -36.4 STW-1002 11/18103 Cs-134 21.5 +/-1.1 23.4 *5.0 17.6 -29.2 STW-1002 11118103 Cs-137 66.3 :t2.8 64.2 5.0 55.5 - 72.9 STW-1002 11/18103 Gr. Beta 159.0 +/-2.5 168.0 +/-5.0 124.0 - 212.0 STW-1002 11/18/03 Sr-89 48.5 *0.4 50.4 :5.0 41.7 -59.1 STW-1002 11/18/03 Sr-90 10.1 *3.0 10.2 *25.2 1.5 -18.9 Results obtained by Environmental, Inc., Midwest Laboratory as a participant In the environmental samples crosscheck program operated by Environmental Resources Associates (ERA).

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

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

dRecount of the original sample still low. The ERA blank was spiked Inthe tab; known value of 20.1 pCY/L. measured 21.5 +/- 1.1 pCl/L No explanation for ERA test failure.

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

'Reason for deviation unknown. A recount of the original planchets averaged 43.4 pCilL.

Cs-1 37activity by gamma spectroscopy; 28.3 pCUL Result of reanalysis; 29.3 pCUL A1-2

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

mR Lab Code TLD Type Date Known Lab Result Control

Description Value +/- 2 sigma Limits Environmental, Inc.

2003-1 CaSO4: Dy Cards 8/8/2003 Reader 1, 120 4.69 4.74 +/- 0.54 3.28 - 6.10 2003-1 CaSO4: Dy Cards 81812003 Reader 1, 150 3.00 3.02 +/- 0.20 2.10 - 3.90 2003-1 CaSO4: Dy Cards 81812003 Reader1,180 2.08 1.89

0.45 1.46 - 2.70 2003-1 CaSO4: Dy Cards 8/812003 Reader 1,180 2.08 2.11

0.22 1.46 - 2.70 2003-1 CaSO4: Dy Cards 8/8/2003 Reader 1,30 75.00 84.40 +/- 4.87 52.50 - 97.50 2003-1 CaSO4: Dy Cards 8/8/2003 Reader 1,60 18.75 19.11 i +/-1.86 13.13 - 24.38 2003-1 CaSO4: Dy Cards 818/2003 Reader 1,60 18.75 22.82

5.41 13.13 - 24.38 2003-1 CaSO4: Dy Cards 8/812003 Reader 1,90 8.33 9.05 +/- 1.17 5.83 - 10.83 2003-1 CaSO4: Dy Cards 8/8/2003 Reader 1,90 8.33 7.60 +/- 1.08 5.83 - 10.83 Environmental. Inc.

2003-2 CaSO4: Dy Cards 1/12/2004 Redder 1,30 61.96 73.50 +/-2.58 43.37 - 80.55 2003-2 CaS04: Dy Cards 1/12/2004 Reader 1,60 15.49 19.70 *E0.51 10.84 - 20.14 2003-2 CaSO4: Dy Cards 1/12/2004 Reader 1, 60 15.49 16.93 i 1.37 10.84 - 20.14 2003-2 CaSO4: Dy Cards 1/1212004

Reader 1,90 6.88 8.06 + 0.60 4.82 - 8.94 2003-2 CaSO4: Dy Cards 1/1212004 Reader 1,90 6.88 6.64 i 0.58 4.82 - 8.94 2003-2 CaSO4: Dy Cards 1/1212004 Reader 1, 120 3.87 4.39 + 0.17 2.71 - 5.03 2003-2 CaSO4: Dy Cards 1/12/2004 Reader 1,150 2.48 2.34 +/-0.18 1.74 - 3.22 2003-2 CaSO4: Dy Cards 1/12/2004 Reader 1, 150 2.48 2.51

0.16 1.74 - 3.22 2003-2 CaSO4: Dy Cards 1/1212004 Reader t,180 1.72 2.01 +/-0.13 1.20 - 2.24 A2-1

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

Lab Code Sample Date Analysis Laboratory results Known Control Type . 2s. n=1 b Activity . Llmitsc SPW-356 water 1/2/2003 Sr-90 34.04 +/- 1.57 30.93 24.74 - 37.12 W-10303 water 113/2003 Gr. Beta 63.24 i 1.20 63.90 53.90 - 73.90 W-11303 water 1/13/2003 Gr. Beta 59.75 +/- 1.10 63.90 53.90 - 73.90 W-12103 water 1/2112003 Gr. Beta 61.56 +/- 1.59 63.99 53.99 - 73.99 SPAP-446 Air Filter 1/31/2003 Gr. Beta 1A9 +/- 0.02 1.52 -8.48 - 11.52 SPW-468 water 1/3112003 H-3 95982.00

865.00 89607.00 71685.60 - 107528A0 W-20703 water 217/2003 Fe-55 9095.00 +/- 114.00 10587.00 8469.60 - 12704.40 SPU-1347 Urine 311/2003 H-3 1724.00 +/- 412.00 1784.33 1101.27 - 2467.39 DW-30303 water 3/3/2003 Gr. Beta 65.44 + 0.59 63.90 53.90 - 73.90 SPCH-964 Charcoal 3/8/2003 1-131(G) 73.37 +/- 0.28 69.45 59.45 - 79.45 SPMI-1086 Milk 3/13/2003 Cs-137 57.18 *8.03 49.50 39.50 -.59.50 SPMI-1086 Milk 3113/2003 1-131 75.13 *E12.01 67.60 54.08 - 81.12 SPMI-1086 Milk 3/13/2003 1-131 (G) 65.81 +/- 1.06 67.56 57.56 - 77.56 SPW-1088 water 3113/2003 Co-60 27.16 *4.79 28.20 18.20 - 38.20 SPW-1088 water 3/13/2003 Cs-137 51.74

9.15 49.50 39.50 - 59.50 SPW-1088 water 3113/2003 1-131 (G) 68.14

12.92 67.60 57.60 - 77.60 SPW-1088 water 3113/2003 1-131 76.94

1.13 67.56 54.05 - 81.07 SPVE-1110 Vegetation 3114/2003 1-131(G) 122.80 +/- 16.80 124.00 111.60 - 136A0 SPW-1 194 water 3/21/2003 Co-60 31.09 t 6.28 28.15 18.15 - 38.15 SPW-1 194 water 3/21/2003 Cs-I 37 55.11 +/- 0.13 49.50 39.50 - 59.50 SPW-1194 water 3121J2003 1-131 (G) 66.17

9.15 67.60 57.60 - 77.60 W-32103 water 3/21/2003 C-14 5201.00 + 16.60 4966.00 2979.60 - 6952A0 SPCH-1429 Charcoal 4(112003 1-131(G) 8.83 i 0.11 9.18 -0.82 - 19.18 W-40103 water 4/11/2003 Gr. Beta 67.74

0.52 63.39 53.39 - 73.39 SPF-1407 Fish 4/212003 Cs-I 34 0.58

0.03 0.59 0.35 - 0.83 SPF-1407 Fish 4/2/2003 Cs-137 1.29

0.06 1.32 0.79 - 1.85-SPAP-1409 Air Filter 4/2/2003 Gr. Beta 1A4 0.02 1.51 -8.49 - 11.51 SPU-41203 Urine 4112/2003 H-3 1798.50 *409.30 1784.33 1101:27 -2467.39 SPU-41703 Urine 4/17/2003 H-3 1625.10 +/-401.30 1784.33 1101.27 - 2467.39 SPW-2022 water 4/25/2003 H-3 89007.00 i 798.00 88463.00 70770.40 - 106155.60 SPW-2053 water 4128/2003 Cs-137 45.70 *E9.44 49.35 39.35 - 59.35 SPW-2053 water 4128/2003 Sr-90 47.51

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

7.17 65.80 55.80 - 75.80 SPMI-2055 Milk 4128/2003 Sr-90 38.45 +/- 1.59 44.74 35.79 - 53.69 W-50603 water 516/2003 Gr. Beta 70.95 +/- 0.53 63.39 53.39 - 73.39 W-60303 water 61312003 Gr. Beta 63.00

0.51 65.73 55.73 - 75.73 SPW-3960 water 7/15/2003 H-3 88700.00

822.00 87369.00 69895.20 - 104842.80 SPMI-4019 Milk 7/1812003 Cs-137 47.17 +7.22 49.11 39.11 -59.11 SPMI-4019 Milk 711812003 Sr-89 40.95 *4.88 49.49 39A9 - 59A9 SPMI-4019 Milk 7/1812003 Sr-9o 45.30

1.73 44.24 35.39 - 53.09 SPW-4023 water 7/18/2003 Cs-137 51.92

6.24 49.11 39.11 - 59.11 SPW-4023 water 7/18/2003 Sr-89 42.49 +/- 10.23 49.49 39.49 - 59.49 SPW-4023 water 7/18/2003 Sr-90 49.69

3.04 44.24 35.39 - 53.09 SPW-4518 water 81812003 Fe-55 8176.00

107.00 9330.00 7464.00 - 11196.00 A3-1

TABLE A-3. In-House wSpikew Samples Concentration (pCilL)

Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n=rb Activity Llmits' SPW-6197 water 10/16/2003 Tc-99 540.14 +/-54.00 539.73 377.81 -701.65 SPAP-3958 Air Filter 1012812003 Gr. Beta 1.45 +/-0.02 1.50 -8.50 -11.50 SPW-6401 water 10/2812003 H-3 84867.00 +/-826.00 85984.00 68787.20 - 103180.80 SPAP-6403 Air Filter 10/28/2003 Gr. Beta 1.71 *0.02 1A9 -8.51 - 11.49 SPF-6418 Fish 10/28/2003 Cs-134 0.50

0.02 0.49 0.29 - 0.69 SPF-6418 Fish 10/28/2003 Cs-137 1.37

0.05 1.30 0.78 -1.82 SPW-6421 water 10/28/2003 Fe-55 104.18

1.26 88.18 68.18 - 108.18 SPMI-7459 Milk 12/12/2003 Cs-1 34 41.06 +/-2.45 41.88 31.88 - 51.88 SPMI-7459 Milk 1211212003 Cs-137 48.48 *4.99 48.64 38.64 - 58.64 SPMI-7459 Milk 12/12/2003 Sr-89 55.94

4.12 65.80 52.64 - 78.96 SPMI-7459 Milk 12/12/2003 Sr-90 41.86 *t1.57 43.80 35.04 - 52.56 SPW-7461 water 12/12/2003 Cs-134 44.07

1.49 41.88 31.88 - 51.88 SPW-7461 water 12/12/2003 Cs-137 50.26

2.67 48.64 38.64 - 58.64 SPW-7461 water 12/12/2003 Sr-89 56.41 +/-4.87 65.80 52.64 - 78.96 SPW-7461 water 12/1212003 Sr-90 48.44

1.84 43.80 35.04 - 52.56 cControl limits are based on Attachment A, Page A2 of this report.

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

A3-2

TABLEA-4. In-House'Blank Samples Concentration (pCVL)a Lab Code Sample Date Analysis Laboratory results (4 . 6 6cr) Acceptance Type LLD Activityb Criteria (4.66 c)

SPW-357 water

1/2/2003 Sr-90 0.50 0.12 +/-0.25 1 W-10303 water 1/312003 Gr. Beta 0.12 0.022 +/-0.10 3.2 W-11303 water 1/13/2003 Gr. Beta 0.14 0.035

0.10 3.2 W-12103 water 112112003 Gr. Beta 0.12 0.029 +/-0.09 3.2 SPAP-447 Air Filter 1/31/2003 Gr. Beta 0.00 -0.0034 +/-0.00 3.2 SPW-469 water 1/31/2003 H-3 160.20 19.3 *80.30 200 W-20103 water 21112003 Gr. Beta 0.17 0.0 +/-0.12 3.2 W-20703 water 21712003 Fe-55 802.00 149 t498.00 1000 DW-30303 313/2003 Gr. Beta 0.15 0.007 +/-0.11 3.2 SPCH-965 Charcoal Cani: 3/8/2003 1-131(G) 0.01 9.6 SPMI-1087 Milk 3/1312003 Cs-I 34 7A9 10 SPMI-1087 Milk 3/1312003 Cs-I 37 7.90 10 SPMI-1 087 Milk 3/13/2003 1-131 0.33 -0.013 +/-0.18 0.5 SPMI-1087 Milk 3113/2003 1-131(G) 7.76 20 SPW-1089 water 3/13/2003 Co-60 4.48 10 SPW-11089 water 3113/2003 Cs-134 5.60 10 SPW-1089 water 3/13/2003 Cs-1 37 4.32 10 SPW-1089 water 3/13/2003 1-131 0.29 -0.050

0.16 0.5 SPVE-1 11. Vegetation 3/1412003 1-131(G) 7.53 20 W-32103 water 3121/2003 C-14 17.50 -0.4 +/-9.200 200 SPCH-1430 Charcoal Cani:4/1/2003 1-1 31 (G) 0.01 9.6 W-40103 water 4/1/2003 Gr. Beta 0.14 -0.11 0.100 3.2 SPF-1408 Fish 4/212003 Cs-134 0.01 100 SPF-1408 Fish 412/2003 Cs-137 0.01 100 SPAP-1410 Air Filter 4/212003 Gr. Beta 0.00 -0.0029

0.002 3.2 SPU-41203 Urine 4/12/2003 H-3 653.99 542.28

364.780 200 SPU-41703 Urine 4/17/2003 H-3 648.35 100.1 +/-344.800 200 SPW-2054 water 4/28/2003 Cs-137 3.16 10 SPW-2054 water 4/2812003 Sr-89 0.55 0.45 +/-0.50 5 SPW-2054 water 4/28/2003 Sr-90 0.55 0.072 i 0.260 1 SPMI-2056 Milk. 4/2812003 Sr-90 0.77 0.66

OA30 1 SPMI-2056 Milk 412812003 Cs-137 2.74 10 SPMI-2056 Milk 4/2812003 1-131(G) 3.54 20 W-50603 - water 51612003 Gr. Beta 0.12 0

0.090 3.2 W-60303 water 613/2003 Gr. Beta 0.14 -0.035 i0.095 3.2 SPW-3960 water 7/15/2003 H-3 156.60 53.4 +/-80.200 200 SPMI-4018 Milk 7/18/2003 Cs-137 4.10 10 SPMI-4018 Milk 7118/2003 Sr-89 0.73 0.39 +/-0.880 5 SPMI-4018 Milk 7/118/2003 Sr-90 0.51 0.93 +/-0.340 1 SPW-4024 water 7/18/2003 Sr-89 0.83 0.21 t 0.730 5 SPW-4024 water 7/18/2003 Sr-90 0.62 0.09 i 0.300 1 SPW-4519 water 8/812003 Fe-55 527.00 87 +/-369.000 1000 SPW-6401 water 1012812003 H-3 163.80 -23.8 +/- 85.000 200 A4-1

TABLE A-4. In-House wBlank7 Samples Concentration (pCVL)8 Lab Code Sample Date Analysis Laboratory results (4 .66a) Acceptance Type . . LLD Activityb Criteria (4.66 a)

SPAP-6404 Air Filter 10/2812003 Gr. Beta 0.87 -0.99 +/- 0.440 3.2 SPF-641 9 Fish 10/28/2003 Cs-134 0.01 100 SPF-6419 Fish 10/28/2003 Cs-137 0.01 100 SPMI-7460 Milk 12/12/2003 Cs-134 4.52 10 SPMJ-7460 Milk 12112/2003 Cs-1 37 5.77 10 SPMI.7460c- Milk 12/12/2003 Sr-90 0.50 1.26 +/-0.370 1

' Uquid sample results are reported In pCULter, air filters( pCiffilter), charcoal (pCVcharcoal canister), and solid samples (pCIkg).

b The activity reported Is the net activity result.

' Low levels of Sr-90 are still detected In the environment A concentration of (1-5 pCVL) In milk Is not unusual.

A4-2

TABLEA-5. In-House'Duplicate"Sanmples Concentration (pCV1L)'

Averaged Lab Code Date Analysis First Result Second Result Result MI-24,25 *11212003 K-40 1362.00

117.00 1377.00

188.00 1369.50 +/- 110.72 MI-24,25 1(2/2003 Sr-90 1.45 *0.40 2.21

0.50 1.83

0.32 CF-47,48 1/2/2003 Gr. Beta 2.72 *0.10 2.84

0.10 2.78 +/- 0.07 CF-47,48 11212003 K-40 2.61 *0.31 2.32

0.12 2.47 +/- 0.17 AP-8827,8828 1/212003 Be-7 0.06 *0.01 0.05

0.02 0.05

0.01 AP-8869,8870 1/2/2003 Be-7 0.04 *0.02 0.05

0.02 0.05

0.01 MI-119, 120 1(8/2003 K-40 1351.90

116.10 1234.70

108.70 1293.30 *79.52 MI-119, 120 118/2003 Sr-90 2.22 *0.43 1.88

0.40 2.05

0.30 1/84/2003 MI-213,214 111412003 K-40 1372.30 *E104.80 1303.80

109.10 1338.05 *75.64 MI-213,214 1/14/2003 Sr-90 1.81

0.41 2.29 +/- 0.45 2.05

0.31 MI-262, 263 1215/2003 K-40 1399.20

200.70 1347.70 +/- 126.40 1373A5 +/- 118.59 S-696, 697 1/29/2003 Gr. Alpha 24.70

4.89 23.23

4.64 23.97

3.37 S-696, 697 1/29/2003 Gr. Beta 22.89

2.67 22.71 *2.73 22.80

1.91 Ml-448,449 2/3/2003 K-40 1159.70 i 157.90 1396.40 +/- 106.20 1278.05

95.15 SW-470,471 2/3/2003 Gr. Beta 13.62 *E1.23 15.21 +/-1.21 14A2

0.86 SW-470,471 2/312003 K-40 (ICP) 5.10

0.51 5.20

0.52 5.15 i 0.36 SW.470,471 213/2003 K-40 5.80

0.51 5.90

0.52 5.85

0.36 MI-517, 518 2/412003 K-40 1437.70

125.50 1357.70

188.00 1397.70

113.02 Ml-541,542 2/512003 K-40 1443.00

194.80 1385.20

190.10 1414.10

136.09 MI-620, 621 211112003 K-40 1294.70

115.10 1234.10

165.10 1264.40

100.63 DW-922,923 3/4/2003 1-131 0.67

0.16 0.79

0.16 0.73

0.11 CF-1048.1049 b 3/10/2003 K-40 3.09 00.12 2.67 +/- 0.07 2.88

0.07 LW-1152,1153 3/1312003 H-3 1147.26 *122.56 1094.42 +/- 120.92 1120.84

86.09 F-1120,1121 3/1412003 Cs-137 0.04

0.02 0.05 i 0.01 0.05

0.01 F-1120,1121 3114/2003 Gr. Beta 2.04

0.06 2.11

0.06 2.08

0.04 311412003 F-1120,1121 3/1412003 K-40 1.93

0.38 1.89 +/- 0.25 1.91 *0.23 DW-1278,1279 3125/2003 1-131 0.37

0.22 0.34 +/- 0.29 0.36

0.18 SO-1380.1381 3/25/2003 Gr. Beta 18.60

2.68 20.53 +/- 2.83 19.57 *1.95 LW-1299,1300 3/2712003 Gr. Beta 2.35 +/- 0.55 2.48 +/- 0.56 2.42

0.39 LW-1320,1321 3127/2003 H-3 487.12 i 104A3 422.00 +/- 102.00 454.56

72.99 W-1403,1404 3/31/2003 Sr-90 0.96

0.32 1.10 +/- 0.42 1.03 +/- 0.26 AP-2019, 2020 3/31/2003 Be-7 0.07

0.01 0.08 +/-0.01 0.07

0.01 MI-1422,1423 4/1/2003 K-40 1410.00 +/- 176.00 1340.00 +/- 114.00 1375.00

104.85 MI-2170,2171 4(12003 K-40 1452.30 +/- 129.10 1472.50 +/- 191.00 1462A.0 115.27 MI-1422,1423 4/2/2003 Sr-90 1.84

0.42 1.15 +/- 0.39 1.50 +/- 0.29 AP-1633,1634 4/212003 Be-7 0.05 t 0.01 0.06 +/- 0.01 0.06

0.01 AP-1871, 1872 4/2/2003 Be-7 0.07

0.01 0.07 +/- 0.01 0.07

0.01 AP-1974,1975 4(212003 Be-7 0.08

0.02 0.07

0.02 0.08 0.01 LW-1828,1829 4111/2003 Gr. Beta 2.49

0.58 3.42 +/- 0.63 2.96 0.43 S-1544,1545 4115/2003 K-40 15.84 +/-2.36 15.41 *2.02 15.63

1.55 DW-1913,1914 4115/2003 1-131 0.29

0.21 0.42 +/- 0.19 0.36

0.14 MI-1996,1997 4/21(2003 Sr-90 2.05 +/- 0.74 3.25 +/- 0.91 2.65 +/- 0.58 MI-1996,1997 4/22/2003 K-40 1580.20 +/-118.90 1602.10 +/- 120.40 1591.15 +/- 84.61 A5-1

TABLE A-5. In-House Duplicateu Saimhples Concentration (pCiIL)a Averaged Lab Code Date Analysis First Result Second Result Result LW-2063, 2064 4.2812003 Gr. Beta 2.33 i 0.66 2.68 +/- 0.60 2.51 +/- 0.45 SWU-2275, 2276 4/2812003 Gr. Beta 3.62 +/- 0.67 4.60 +/- 0.71 4.11 +/-0;49 G-2149,2150 4/30/2003 Be-7 0.71 i0.19 0.69 +/- 0.20 0.70 +/- 0.14 TD-2339, 2340 5/302003 H-3 221.00 +/-91.00 161.00 +/- 88.00 191.00 +/- 63.29 SO-2381. 2382 5/1/2003 Cs-137 0.11 i 0.03 0.10 +/- 0.02 0.10 +/- 0.02 SO-2381, 2382 5/1/2003 Gr. Alpha 11.14 +/-5.15 10.39

5.60 10.77 +/- 3.80 SO-2381, 2382 511/2003 Gr. Beta 35.18 +/-4.69 39.66 +/- 5.24 37.42 +/- 3.52 SO-2381, 2382 5/1/2003 K-40 18.29 +/-0.84 17.83 +/- 0.84 18.06 +/- 0.59 SO-2381, 2382 5/1/2003 Sr-90 0.06

0.02 0.10 +/- 0.02 0.08 +/- 0.01 DW-2317, 2318 5/1/2003 1-131 1.77 +/-0.27 1A7 +/- 0.26 - 1.62 +/- 0.19 B5-2595. 2596 5/6/2003 Cs-137 0.06

0.02 0.06 +/- 0.02 0.06 +/- 0.02 BS-2595.2596 5/6/2003 K-40 13.74 +/-0.62 14.10 +/-0.73 13.92

0.48 U-2484, 2485 5/9/2003 H-3 512.00 i 100.00 370.00 +/- 95.00 441.00

68.97 S0-2645,2646 5/14/2003 Be-7 1.18 i 0.42 1.21 +/- 0.35 1.19 0.27 SO-2645,2646 5/1412003 Cs-137 0.11 0.04 0.09 +/- 0.05 0.10

0.03 SO-2645,2646 5/14/2003 K-40 16.50 +/-1.13 15.33 +/- 1.09 15.91 +/-0.79 MI-2696,2697 5/19/2003 K-40 1320.40

124.50 1394.10 +/- 113.00 1357.25 +/-84.07 MI-2696,2697 5f1912003 Sr-90 1.49 i 0.47 2.01 +/- 0.45 1.75 +/-0.32 SO-2787, 2788 5/2812003 Cs-137 .0.27 +/-0.04 0.23 + 0.04 0.25

0.03 SO-2787, 2788 5/28/2003 Gr. Beta -i9.62+/- 1.73 20.81 + 1.72 20.21 +/- 1.22 SO-2787, 2788 5128/2003 K-40 14.77 +/-1.02 14.41

1.00 14.59 +/- 0.71 MI-2840, 2841 5/28/2003 K-40 1179.50 +/-167.80 1401.70 +/- 120.20 1290.60 +/- 103.20 SWU-2864,2865 5/28/2003 Gr. Beta 3.39

0.59 3.41 +/- 0.64 3.40 +/- 0.43 BS-2888, 2889 5/29/2003 Cs-137 0.05 +/- 0.02 0.07 +/- 0.04 0.06 +/- 0.02 5/29/2003 BS-2888, 2889 512912003 K-40 9.70 *k0.83 10.17 +/- 0.87 9.93 +/- 0.60 W-3230, 3231 5/30/2003 Gr. Beta 4.33 i 1.00 3.28 + 1.22 3.81 +/- 0.79 TD-3036,3037 61212003 H-3 529.50

100.00 585.50 +/- 102.00 557.50 +/-71.42 SL-2909,2910 b 6/3/2003 Gr. Beta 7.10 + 0.15 7.60 +/- 0.16 7.35 +/- 0.11 SL-2909, 2910 6/3/2003 K-40 3.90 +/-E0.67 3.49 +/- 0.52 3.70 +/- 0.42 SW-3080,3081 6/10/2003 Gr. Alpha 4.63 i 1.90 4.47 +/- 1.71 4.55 +/- 1.28 SW-3080. 3081 6/10/2003 Gr. Beta 9.07 +/-1.29 8.98 +/- 1.28 9.02 +/- 0.91 VE-3172, 3173 6/11/2003 K-40 2.62

0.35 3.17 +/- 0.58 2.90 +/- 0.34 F-3742, 3743 6111/2003 Gr. Beta 3.47 +/- 0.13 3.71 +/-0.14 3.59 +/- 0.10 F-3742,3743 6111/2003 K-40 2.94 +/- 0.39 2.70

0.40 2.82 +/- 0.28 SO-3325,3326 6/13/2003 Gr. Beta 20.95 +/- 1.88 19.97 *2.01 20.46 +/- 1.38 MI-3253, 3254 6/17/2003 K-40 1329.40 +/- 121.80 1417.60 t 130.90 1373.50 +/- 89.40 MI-3297, 3298 6/17/2003 Sr-90 2.14 +/- 0.57 2.27 +/- 0.50 2.21 +/- 0.38 WW-3380, 3381 6/23/2003 Gr. Beta 5.58

0.69 5.03 +/- 0.69 5.31 +/- 0.49 SWT-3403, 3404 6/24/2003 Gr. Beta 2.80 +/- 0.56 2.63

0.55 2.72 +/- 0.39 MI-3424,3425 612412003 K-40 1422.80 +/- 185.40 1216.20 +/- 170.10 1319.50 +/- 125.80 SW-3862,3863 6/24/2003 Gr. Beta 3.66 +/- 1.18 3.70 +/-1.22 3.68 +/- 0.85 G-3479.3480 6/25/2003 Be-7 1.52

0.25 1.43 +/- 0.28 1.47 +/- 0.19 G-3479, 3480 6/2512003 K-40 5.02 +/- OA5 5.10 +/- 0.48 5.06 +/- 0.33 LW-3809, 3810 6/30/2003 Gr. Beta 2.12 +/- 0.76 2.39 +/- 0.72 2.25 +/- 0.52 A5-2

TABLE A-5. In-House "Duplicate Samples Concentration (pCi/L)r Averaged Lab Code Date Analysis First Result Second Result Result LW-3809, 3810 6/30/2003 H-3 2814.09

167.99 2812.17 +/- 167.94 2813.13 +/-118.77 AP-4105,4106 6130/2003 Be-7 0.07

0.01 0.07

0.01 0.07

0.01 G-3572, 3573 7/1/2003 Be-7 0.91

0.24 0.81

0.28 0.86

0.18 G-3572, 3573 7/1/2003 Gr. Beta 6.35 *0.15 6.35

0.15 6.35

0.11 G-3572,3573 7/1/2003 K-40 5.44

0.55 5.68

0.28 5.56

0.31 G-3572,3573 7/1/2003 Sr-90 0.01

0.00 0.02

0.00 0.01

0.00 MI-3601, 3602 7/1/2003 K-40 1318.60

117A0 1435.10

117.80 1376.85

83.16 MI-3601, 3602 7/11/2003 Sr-90 0.86

0.51 1.74

0.60 1.30

0.39 AP-3933, 3934 7/1/2003 Be-7 0.07

0.01 0.07

0.01 0.07 +/- 0.01 AP-4061,4062 712/2003 Be-7 0.07 +/- 0.01 0.08

0.01 .0.08 +/- 0.01 AP-4147,4148 7/2/2003 Be-7 0.08 +/- 0.01 0.07 +/- 0.01 0.07

0.01 AP-4084,4085 7/3/2003 Be-7 0.09 TJ.02 0.08

0.02 0.08

0.01 LW-3786. 3787 7/912003 Gr. Beta 2.13

0.56 2.93

0.62 2.53

0.42 WW-4168, 4169 7/11/2003 Gr. Beta 3.79

1.87 4.48 +/- 1.98 4.14

1.36 CF-3975,3976 7114/2003 Be-7 1.64

0.81 1.66 +/- 0.57 1.65 +/- 0.50 CF-3975, 3976 7/14/2003 K-40 6.54 +/- 0.75 6.19 i 0.50 6.36

0.45 Ml-4020,4021 7116/2003 K-40 1350.90 +/- 174.90 1199.80 +/-153.20 1275.35

116.25 DW-4272,4273 7/29/2003 Gr. Beta 2.35

0.92 2.29 +/- 0.89 2.32 +/- 0.64 SWU-4461, 4462 7/30/2003 Gr. Beta 2.28

0.44 1.93 +/- 0.43 2.10 +/- 0.31 SL-4398, 4399 8/4/2003 Be-7 4.55

1.05 4.50 +/- 1.10 4.53

0.76 SL-4398,4399 b 814/2003 Gr. Beta 3.41 *0.12 3.12 +/-0.11 3.27 i 0.08 SL-4398,4399 8/4/2003 K-40 2.47

0.67 2.44 +/- 0.87 2.46 +/- 0.55 G-4419,4420 8/4/2003 Be-7 3.98 i 0.63 3.93

0.57 3.96

0.42 G-4419,4420 8/4/2003 Gr. Beta 5.38

0.14 5.35 +/- 0.16 5.37 +/- 0.11 G44191 4420 814/2003 K-40 4.42

0.66 4.32

0.74 4.37 +/- 0.50 TD-4550, 4551 8/4/2003 H-3 327.30 *95.10 390.20 +/- 92.10 358.75 +/- 66.19 MI-4482, 4483 8/6/2003 K-40 1301.40

115.20 1370.30 +/- 116.80 1335.85 +/- 82.03 MI-4482, 4483 8/612003 Sr.90 0.81

0.30 0.85 +/- 0.31 0.83 +/- 0.21 G-4526, 4527 8/612003 Be-7 1.47

0.29 1.42

0.28 1.45 +/- 0.20 G-4526, 4527 8/6/2003 K-40 5.42 +/- 0.56 5.21

0.63 5.31

0.42 SWU-4609,4610 8/6/2003 Gr. Beta 3.22

0.63 2.67

0.64 2.95

0.45 CW-4694, 4695 8/6/2003 Gr. Beta 1.48

0.34 1.09 +/- 0.34 1.29 +/- 0.24 CW-4694,4695 8/6/2003 H-3 22776.41 428.73 21831.75 +/- 420.10 22304.08

300.12 LW-4673,4674 8/13/2003 Gr. Beta 2.86

0.65 3.75 +/-0.71 3.30

0.48 MI-4735,4736 8/1912003 K40 1396.30 +/- 127.90 1410.10 +/- 120.20 1403.20 +/- 87.76 MI-4756,4757 8/1912003 Sr-90 1.66 +/- 0.47 1.53

0.44 1.60

0.32 VE-4832,4833 8/20/2003 K-40 1.96 i 0.50 1.43

0.47 1.70 +/- 0.34 Ml4860,4861 8/26/2003 K40 1312.10

191.80 1307.80

109.30 1309.95 +/- 110.38 SO-5082, 5083 8/28/2003 Cs-137 0.01

0.00 0.01

0.00 0.01

0.00 SO-5082, 5083 8/28/2003 Gr. Beta 20.02 +/- 1.84 20.92

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

0.39 1.55 +/- OA5 1.50 +/- 0.30 CW-5349, 5350 8/31/2003 H-3 24429.50

444.42 24744.25 +/-447.18 24586.88 *315.23 ME-4968, 4969 912/2003 Gr. Beta 4.90 + 0.23 5.18 +/- 0.24 5.04 +/- 0.17 ME-4968,4969 912/2003 K-40 2.46

0.41 2.68

0.37 2.57 +/- 0.28 A5-3

TABLE A-5. In-House wDuplicate" Samples Concentration (pCiIL)8 Averaged Lab Code Date Analysis First Result Second Result Result DW-4989,4990 912/2003 Gr. Beta 2.20

1.04 3.19 +/- 1.14 2.70 +/- 0.77 MI-5154, 5155 9/8/2003 K-40 1365.50

116.70 1456.70 +/- 119.10 1411.10 +/- 83.37 MI-5154, 5155 918/2003 Sr-90 1.19

0.39 1.39 +/- 0.39 1.29 *0.28 AP-6177, 6178 912912003 Be-7 0.07

0.01 0.06 +/-0.01 0.06

0.01 SWU-5773, 5774 9130/2003 Gr. Beta 2.55

0.63 2.83 +/- 0.60 2.69 0.44M AP-6102, 6103 9/30/2003 Be-7 0.07 +/- 0.01 0.05 +/- 0.01 0.06 +/- 0.01 G-5631. 5632 10/112003 Be-7 1.88 +/- 0.48 2.21 +/- 0.40 2.05 +/- 0.31 G-5631. 5632 10/1/2003 Gr. Beta 5.87 +/- 0.09 5.85 +/- 0.08 5.86 +/- 0.06 G-5631, 5632 10/1/2003 K-40 5.24 +/- 0.77 5.26 +/- 0.58 5.25 +/- 0.48 SO-5660, 5661 10/1/2003 Cs-137 0.15 +/- 0.04 0.16 +/- 0.05 0.16

0.03 S0-5660,5661 10/1/2003 Gr. Alpha 12.72 +/-3.72 14.86 i3.88 13.79 +/- 2.69 SO-5660, 5661 10/1/2003 Gr. Beta 32.42 +/- 3.09 33.60

3.04 33.01 +/-2.17 SO-5660,5661 1011/2003 K-40 18.93 +/- 0.87 18.25

1.19 18.59

0.74 SO-5660, 5661 10/1/2003 Sr-90 0.03 +/- 0.01 0.03 *0.01 0.03 +/- 0.01 AP-6334, 6335 10/1/2003 Be-7 0.06 +/- 0.01 0.06

0.01 0.06

0.01 AP-6363, 6364 10/2/2003 Be-7 0.07

0.02 0.07

0.02 0.07 +/- 0.01 MI-5794, 5795 10/6/2003 Sr-90 1.37

0.37 1.02

0.37 1.19 +/-0.26 MI-5838, 5839 1018/2003 K-40 1364.30 +/- 124.10 1414.40

1100AO 1389.35 +/-83.05 MI-5838, 5839 1018/2003 Sr-90. 0.76

0.30 1.00 +/- 0.34 0.88

0.23 BS-5938, 5939 10/8/2003 Cs-137 0.18

0.03 0.20 +/- 0.05 0.19 +/- 0.03 BS-5938,5939 10/812003 K-40 15.59 +/- 0.70 16.69

0.80 16.14 + 0.53 SS-5959, 5960 10/13/2003 K-40 7.49 +/- 0.42 7.29

0.63 7.39

0.38 Ml-6011, 6012 10/13/2003 K-40 1165.20 +/- 118.70 1191.20

99.50 1178.20 +/- 77.44 MI-6034, 6035 10/14/2003 Sr-90 0.86 t 0.33 0.90 +/- 0.34 0.88 +/- 0.24 VE-6055, 6056 10/15/2003 Gr. Beta 5.18 +/-0.18 5.33 +/- 0.18 5.25 +/- 0.13 VE-6055, 6056 10/15/2003 K-40 5.31

0.57 4.52 +/- 0.51 4.92 +/- 0.38 Mil-6291, 6292 10/21/2003 K-40 1935.60

147.70 1936.10 +/- 116.50 1935.85

94.06 MI-6291, 6292 10/21/2003 Sr-90 1.22

0.39 14A1 +/-0.37 1.31 *0.27 SS-6435, 6436 10/21/2003 Cs-l 37 0.05 + 0.02 0.05 +/- 0.03. 0.05 +/- 0.02 SS-6435, 6436 10/21/2003 K-40 14.08 +/- 0.54 14.28 +/- 0.80 14.18 *0.48 CF-6313, 6314 10/22/2003 K-40 14.56 0.45 14.70 +/- 0.95 14.63

0.53 SO-6528, 6529 10/22/2003 Cs-137 0.15 +/-0.03 0.16 +/- 0.05 0.16

0.03 SO-6528,6529 10/2212003 K-40 17.46 +/- 0.69 17.90 +/- 1.05 17.68 +/- 0.63 SO-6393,6394 10/25/2003 Cs-I 37 0.09

0.03 0.10 +/- 0.04 0.10

0.03 SO-6393, 6394 10/25/2003 Gr. Beta 23.21 +/-1.98 21.76 +/- 1.91 22.48

1.38 SO-6393,6394 10/25/2003 K-40 13.98 +/- 0.80 14.57 *0.86 14.27

0.59 SWT-6507, 6508 10/28/2003 Gr. Beta 2.64 +/- 0.52 2.63 +/- 0.53 2.63

0.37 DW-6647, 6648 10/31/2003 1-131 0.46 +/- 0.27 0.61 +/- 0.31 0.53

0.21 BS-6603, 6604 11/3/2003 Cs-137 9.03 +/- 0.82 8.60 +/- 1.13 8.82

0.70 BS-6603, 6604 11/312003 Gr. Beta 26.83 +/- 1.94 27.18 +/- 1.95 27.01

1.38 SO-6670,6671 11/5/2003 Cs-137 0.15

0.04 0.13 +/- 0.04 0.14

0.03 SO-6670, 6671 11/5/2003 K-40 12.96 +/- 0.66 12.95 +/- 0.72 12.96

0.49 S-7067, 7068 11/10/2003 Cs-I 37 021 +/- 0.05 0.19

0.08 0.20 4 0.05 MI-6818, 6819 11/11/2003 K-40 1695.50 +/- 129.80 1709.40

143.00 1702.45 i 96.56 A5-4

TABLEA-S. In-House"Duplicate"Samples Concentration (pCUL)'

Averaged Lab Code Date Analysis First Result Second Result Result MI-6818.6819 11/1112003 Sr-90 2.01 *0.41 1.59

0.39 1.80 0.28 WL-6987, 6988 11/17/2003 Fe-55 .603.49 +/- 53.32 619.65

53.97 611.57 i 37.93 SO-7156,7157 11/21/2003 Cs-137 0.74

0.08 0.77

0.07 0.76

0.06 SO-7156, 7157 11121/2003 Gr. Alpha 14.90 *4.24 19.25 *4.45 17;07 +/- 3.07 SO-7156, 7157 11/21/2003 Gr. Beta 22.97

3.12 25.51

2.98 24.24 +/-2.16 SO-7156, 7157 11/21/2003 K40 12.51

1.06 12.94

1.07 12.73 +/-0.75 S-7281, 7282 11/24/2003 Cs-137 0.82

0.15 1.16 i 0.20 0.99

0.12 SWU-7198, 7199 11/25/2003 Gr. Beta 2.60

0.53 2.54

0.55 2.57 +/- 0.38 DW-7221,7222 11/25/2003 Gr. Beta 12.32 I10 12.38 1.A3 12.35

1.00 SW-7133,7134 12V1/2003 Gr. Beta 2.10 *0.23 2A6 *0.23 2.28

0.16 SW-7133,7134 121112003 K-40 1.50

0.15 1.0 0.14 1.A5 +/-0.10 W-7519,7520 12/1/2003 Fe-55 3.03

0.65 3.12

0.64 3.08

0.46 SW-7805,7806 12/1/2003 Sr-90 0.59 *k0.32 0.56

0.33 0.58

0.23 VE-7399,7400 12/9/2003 Gr. Beta 4.99

0.15 5.24

0.15 5.11 +/-0.11 VE-7399,7400 12/9/2003 K-40 5.04

0.46 5.34 +/- 0.74 5.19 +/- 0.43 SW-7540, 7541 121912003 Gr. Alpha 2.64

1.36 2.10 +/- 1.19 2.37 +/- 0.91 SW-7540, 7541 12/9/2003 Gr. Beta 6.62 *1.22 5.89

1.35 6.25 +/- 0.91 LW-7736, 7737 12/26/2003 Gr. Beta 2.62 +/- 0.54 2.83 +/- 0.56 2.73

0.39 AP-7868, 7869 12130/2003 Be-7 0.05

0.01 0.04

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

0.01 0.04

0.01 0.04 +/- 0.01 AP-7994,7995 12131/2003 Le-7 0.05

0.02 0.05 +/- 0.01 0.05

0.01 Note: Duplicate analyses are performed on every twentieth sample received In-house. Results are not listed for those analyses with activIties that measure below the LLD.

8 Results are reported In units of pCiUL, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi~g).

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

A5-5

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

Concentrationb Known Control Lab Code Type Date Analysis Laboratory result Activity Limtse STW-972 vwater 12/01/02 Am-241 0.56 +/- 0.06 0.58

0.09 0.40 - 0.75 STW-972 water 12101102 Co-57 57.10 +/- 1.90 57.00

5.70 39.90 - 74.10 STW-972 water 12/01102 Co-60 38.30 +/-0.60 38.20

3.82 26.74 -49.66 STW-972 water 12/01/02 Cs-1 34 395.30 10.10 421.00 +/-42.10 294.70 - 547.30 S1W-972 water 12/01/02 Cs-137 316.40 *5.30 329.00

32.90 230.30 - 427.70 STW-972 water 12/01/02 Fe-55 94.90 *24.50 96.00

9.60 67.20 - 124.80 STW-972 water 12/01102 Mn-54 33AO +/-0.10 32.90

3.29 23.03 - 42.77 S1W-972 water 12/01102 Ni-63 123.80 +/-5.50 136.50 +/- 13.70 95.55 - 177.45 STW-972 water 12101/02 Pu-238 0.66 +/- 0.06 0.83

0.08 0.58 - 1.08 STW-972 water 12101/02 Pu-239/40 0.001

0.001 0.000

0.000 0.000 - 0.005 STW-972 water 12101102 Sr-90 13.80 +/- 1.00 12.31 *1.23 8.62 - 16.00 S1W-972 water 12101/02 Tc-99 128.10 +/- 3.80 132.00

13.20 92.40 - 171.60 S1W-972 water 12/01/02 U-23314 1.60 +/- 0.09 1.54 i 0.15 1.08 - 2.00 S1W-972 water 12/01/02 U-238 1.64 +/- 0.09 1.60

0.16 1.12 - 2.08 S1W-972 water 12/01/02 Zn-65 540.40

9.90 516.00

51.60 361.20 - 670.80 STSO-987 soil 01/01103 Co-57 534.36 +/- 2.61 530.00

53.00 371.00 - 689.00 STSO-987 soil 01101/03 Co-60 442.16 +/-2.31 420.00 +/- 42.00 294.00 - 546.00 STSO-987 soil 01/01/03 Cs-134 211.00 +/-2.30 238.00 +/- 23.80 166.60 - 309.40 STSO-987 soil 01101/03 Cs-137 849.50 +/- 3.30 832.00

83.20 582.40 - 1081.60 STSO-987 soil 01/01/03 K-40 716.50 +/- 12.80 652.00

65.20 456AO - 847.60 STSO-987 soil 01/01/03 Mn-54 148.76 +/- 2.84 137.00

13.70 95.90 - 178.10 STSO-987 soil 01/01103 Ni-63 597.10 +/- 23.50 770.00 +/- 77.00 539.00 - 1001.00 STSO-987 soil 01/01/03 Pu-238 67.05 +/- 3.10 66.90 +/- 6.70 46.83 - 86.97 STSO-987 soil 01/01/03 Pu-239/40 52.80

3.60 52.70

5.30 36.90 - 68.50 STSO-987 soil 01/01/03 Sr-90 609.50

9.80 714.00 i 71.40 499.80 - 928.20 STSO-987 soil 01/01/03 U-233/4 99.50 i 7.60 89.00

8.90 62.30 - 115.70 STSO-987 soil 01/01/03 U-238 508.60 +/- 42.20 421.00 +/-42.10 294.70 - 547.30 STSO-987 soil 01/01/03 Zn-65 492.70 *28.10 490.00 +/- 49.00 343.00 - 637.00

' Results obtained by Environmental, Inc. ,Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b All results are In 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, I determination) and control limits as defined by the MAPEP.

A6-1

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

Concentrations EML Control Lab Code Type Date Analysis Laboratory results Resulte Llmits' STW-977 water 03101/03 Gr. Alpha 304.30 i 53.10 377.50 0.58 -1.29 STW-977 water 03101/03 Gr. Beta. 615.80

14.70 627.50 0.61 -1.43 STW-978 water 03101103 Am-241 2.00

0.10 2.13 0.79 -1.41 STW-978 water 03101/03 Co-60 221.30 +/- 1.20 234.00 0.80 -1.20 STW-978 a water 03/01/03 Cs-134 23.30

1.10 30.50 0.80 -1.30 STW-978 water 03101103 Cs- 137 61A.0 0.60 63.80 0.80 -1.22 STW-978 e water 03101103 H-3 341.90

22.70 390.00 0.78 - 2A5 STW-978 water 03/01/03 Pu-238 3.70

0.20 3.33 0.74 -1.20 STW-978 water 03/01/03 Pu-239/40 4.40 *0.10 3.92 0.79 -1.20 STW-978 water 03/01/03 Sr-9o 4.60 +/- 0.30 4.34 0.69 - 1.34 STW-978 water 03101/03 Uranium 5.10

0.60 4.29 0.75 -1.33 STSO-979 soil 03101/03 Ac-228 55.60

2.50 57.60 0.80 - 1.38 STSO-979 soil 03101103 Am-241 12.42

0.90 15.60 0.65 -2.28 STSO-979 soil 03101103 Bi-212 57.70

3.20 60.60 0.50 -1.34 STSOi979 soil 03101103 BI-214 60A.0 3.20 67.00 0.78 - 1.42 STSO-979 soil 03/01103 Cs-137 1416.80 +/- 70.00 1450.00 0.80 - 1.25 STSO-979 soil 03101103 K-40 653.80 +/- 11.90 636.00 0.80 - 1.32 STSO-979 soil 03101/03 Pb-212 51.10 +/-520 57.90 0.78 - 1.32 STSO-979 soil 03101103 Pb-214 64.70 +/-5.10 71.10 0.76 - 1.46 STSO-979 soil 03101/03 Pu-239140 24.40 +/- 0.30 23.40 0.71 - 1.30 STSO-979 soil 03101/03 Sr-9o 54.50 +/-2.60 64.40 0.67 - 2.90 STSO-979 soil 03/01103 Uranium 245.00 +/- 1.50 249.00 0.71 - 1.32 STVE-980 Vegetation 03/01/03 Am-241 3.10 0.20 3.51 0.73 -2.02 STVE-980 Vegetation 03/01/03 Cm-244 1.40

0.50 2.01 0.61 -1.59 STVE-980 Vegetation 03/01/03 Co-60 12.60

0.40 12.10 0.80 - 1.44 STVE-980 Vegetation 03101/03 Cs-I 37 449.70 + 6.20 444.00 0.80 -1.31 STVE-980 Vegetation 03101103 K140 1159.00 +/- 38.60 1120.00 0.79 - 1.39 STVE-980 Vegetation 03/01/03 Pu-239/40 4.80 +/-0.40 5.17 0.69 -1.31 STVE-980 Vegetation 03101103 Sr-90 659.70 +/- 50.40 650.00 0.55 -1.21 STAP-981 Air Filter 03101/03 Am-241 0.27 +/- 0.10 0.34 0.70 -2.34 STAP-981 Air Filter 03/01/03 Co-60 30.20 +/- 0.30 33.50 0.80 - 1.26 STAP-981 Air Filter 03/01103 Cs-137 90.30

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

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

Concentration' EML Control Lab Code Type Date Analysis Laboratory results Result t Umits' STW-992 water 09/02103 Am-241 9.78 +/-t 0.32 8.76 0.79 -1.41 The September, 2003 results are preliminary. Control limits used were taken from the March, 2003 data.

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

STW-992 water 09/02/03 Co-so 468.30 +/-4.10 513.00 0.80 - 1.20 STW-992 water 09102103 Cs-134 53.90 +/- 0.80 63.00 0.80 - 1.30 STW-992 water 09/02/03 Cs-137 76.10 +/- 1.40 80.30 0.80 -1.22 STW-992 water 09102103 H-3 35520 +/- 12.80 446.30 0.78 - 2.45 STW-992 water 09102103 Pu-238 1.71 +/- 0.07 2.07 0.74 - 1.20 STW-992 water 09/02/03 Pu-239140 4.24 +/- 0.01 4.99 0.79 - 1.20 STW-992 water 09102103 Sr-90 6.70 +/- 0.50 7.04 0.69 - 1.34 STW-992 water 09102103 Uranium 6.03 +/- 0.14 5.69 0.75 -1.33 STW-993 water 09102103 Gr. Alpha 688.00 +/- 7.60 622.00 0.58 -1.29 STW-993 water 09/02/03 Gr. Beta 1985.00 +/- 111.00 1948.00 0.61 - 1A3 STSO-994 soil 09/02103 Am-241 19.70

1.50 18.40 0.65 - 2.28 STSO-994 soil 09102103 *Cs-137 1928.00

19.00 1973.00 0.80 -1.25 STSO-994 soil 09/02103 K-40 533.00 i 79.00 488.00 0.80 - 1.32 STSO-994 soil 09102103 Pu-238 15.30

0.80 14.60 0.59 -2.88 STSO-994 soil 09102103 Pu-239140 32.50

2.30 30.40 0.71 -1.30 STSO-994 soil 09102103 Sr-90 69.80

2.30 80.30 0.67 - 2.90 STSO-994 soil 09102103 Uranium. 228.30

17.10 259.30 0.71 -1.32 STAP-995 Air Filter 09102/03 Am-241 0.64

0.05 0.44 0.70 -2.34 STAP-995 Air Filter 09/02103 Co-60 48.50 +/-0.40 55.10 0.80 - 1.26 STAP-995 Air Filter 09102103 Cs-137 51.20 +/-1.10 54.80 0.80 -1.32 STAP-995 Air Filter 09102103 Mn-54 53.70 +/-1.10 58.00 0.80 -1.35 STAP-995 Air Filter 09102103 Pu-238 0.24 + 0.05 0.23 0.67 - 1.33 STAP-995 Air Filter 09102/03 Pu-239140 0.41

0.10 0.40 0.73 -1.26 STAP-995 Air Filter 09102103 Sr-90 1.90 +/-0.10 2.06 0.53 -1.84 STAP-995 Air Filter 09102103 Uranium 0.80

0.06 0.82 0.79 -2.10 STAP-996 Air Filter 09102103 Gr. Alpha 3.23 + 0.07 3.11 0.73 -1.43 STAP-996 Air Filter 09102/03 Gr. Beta 4.18

0.03 3.89 0.76 - 1.36

Results are reported In Bq/L with the following exceptions: Air Filters (Sq/Filter), Soil and Vegetation (Bq/lkg).

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

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

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

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

Reporting error.

A7-2

APPENDIX B DATA REPORTING CONVENTIONS B-1

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

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

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

3.0. Duplicate analyses 3.1 Individual results: For two analysis results; xj +/- sl and X2 +/- S2 Reported result: x +/-s; where x = (1/2) (xi + x2) and s = (1/2) lS1 + 52 3.2. Individual results: <L 1 , <L2 Reported result: <L, where L = lower of LI and L2 3.3. Individual results: x +/- s, <L Reported result: x +/- s if x ;L; <L otherwise.

4.0. Computation of Averaces and Standard Deviations 4.1 Averages and standard deviations listed In the tables are computed from all of the Individual measurements over the period averaged; for exampLe, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x1 , x2 ... Xn are defined as follows:

xi=n Ex \ -

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 areas8 .

Air (pCrm3 ) Water (pCiL)

Gross alpha I x10- 3 Strontium-89 8,000 Gross beta I Strontium-90 500 lodine-I 3 1 b 2.8 x 10-1 Cesium-137 1,000 Barium-140 8,000 Iodine-131 1,000 Potassium-40c 4,000 Gross alpha 2 Gross beta 10 Tritium I 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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L-MT-04-030, 2003 Annual Radiological Environmental Operating Report

Contents

Text

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

6.0 REFERENCES

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L-MT-04-030, 2003 Annual Radiological Environmental Operating Report

Text

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

6.0 REFERENCES

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