Text

2005 Annual Radiological Environmental Operating Report
	ML061280617
Person / Time
Site:	Monticello
Issue date:	05/04/2006
From:	Conway J; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	FOIA/PA-2010-0209 L-MT-06-031
	Download: ML061280617 (59)
	v • d • e

tNuc 3 Committed to Nuclear flence Monticello Nuclear Generating Plant Operated by Nuclear Management Company, LLC May 4, 2006 L-MT-06-031 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 2005 Annual Radiolocical Environmental Operatina 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 2005.

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

1'-X T. Conway Site Vice President. Monticello N lear eneratina Plant Nuclear Management Company, Enclosure cc: Administrator, Region ll, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce

~42S 2807 West County Road 75

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

Fax: 763-295-1454

ENCLOSURE I ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION, RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM, JANUARY 1 TO DECEMBER 31, 2005 57 pages follow

Environmental, Inc.

Midwest Laboratory an Allegheny Technologies Co.

700 Landwehr Road

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

fax (847) 564-4517 XCEL ENERGY CORPORATION MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2005 Prepared under Contract by ENVIRONMENTAL, Inc.

Midwest Laboratory Project No. 8010 Approved:

Lb MnaerM.S.

Xby Manager

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. Page Preface ...................................................... ii List of Tables ...................................................... iv List of Figures ........................................................ v

1.0 INTRODUCTION

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

SUMMARY

....................................................... 2 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) ....................... 3 3.1 Program Design and Data Interpretation ............................. 3 3.2 Program Description. ................ ......... . 4 3.3 Program Execution ............................. 5 3.4 Laboratory Procedures ............................. 6 3,5 Program Modifications ............................. 6 3.6 Land Use Census ............................. 6 4.0 RESULTS AND DISCUSSION ................................................. 7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents .................................... 7 4.2 Summary of Preoperational Data ............. ................................... 7 4.3 Program Findings ................................................ 8 5.0 FIGURES AND TABLES ................................................ 12

6.0 REFERENCES

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

LIST OF TABLES No. Title Pace 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:

Aopendix A A-1 Interlaboratory Comparison Program Results . .................................................... A1-1 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 Attachment A: Acceptance criteria for spiked samples ................................................... A2 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas ............. ...................................... C-2 iv

LIST OF FIGURES No. Title Page 5-1 Offsite Ambient Radiation (TLDs), inner versus outer ring locations ......................................... 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 ADpendix 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: TLLD 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, 2005.

This Program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the Plant on its surroundings.

Tabulation of the individual analyses made during the year are not included in this report.

These data are included in a reference document (Environmental, Inc., Midwest Laboratory, 2006a) 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 2005 are summarized and discussed.

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

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

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3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program (REMP) at the Monticello Nuclear Generating Plant is to assess the impact of the Plant on its environment. For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLD's).

Sources of environmental radiation include the following:

(1) Natural background radiation arising from cosmic rays and primordial radionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; (4) Industrial and medical radioactive waste; and (5) Fallout from nuclear accidents.

In interpreting the data, effects due to the Plant must be distinguished from those due to other sources.

A major interpretive aid in assessment of these effects is the design of the monitoring program at the Monticello Plant which is based on the indicator-control concept. Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream). A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.

An additional interpretive technique involves analyses for specific radionuclides present in environmental samples collected from the Plant site. The Plant's monitoring program includes analyses for tritium and iodine-131. Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40. The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation.

Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown. On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered as radiological impact indicators. 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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Proaram Desion and Data Interpretation (continued)

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

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

To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Also, 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, M-4, M-5). One of the indicators is located in the geographical sector expected to be most susceptible to any atmospheric emissions from the Plant (highest D/Q sector).

Ambient gamma radiation is monitored at forty locations, using CaSO 4 :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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Proaram 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 Prociram Execution The Program was executed as described in the preceding section with the following exceptions:

(1) Surface water samples could not be collected from M-08 (upstream) for the weeks ending 01-05-05 through 03-16-05. The shoreline was frozen.

(2) No air particulate / air iodine sample was available from location M-2 for the week ending 05-11-05. The sampler pump failed.

(3) No air particulate / air iodine sample was available from location M-5 for the week ending 05-18-05. Power was interrupted due to an open fuse.

(4) Milk samples were not available from M-28 (Hoglund Farm) June 29th through October 5th, 2005. Dairy operations were temporarily discontinued. Collections were resumed on 10-20-05.

(5) No air particulate / air iodine sample was available from location M-4 for the week ending 09-14-05. The breaker was tripped due to lightning.

(6) The timer reading for air particulate I air iodine sampling from location M-3, for the week ending 09-28-05, showed a deficiency of approximately 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months .

(7) Bottom organisms from the upstream location M-8 were not available for the collection of 10-27-05.

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-1 31 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 controllquality 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 in Appendix A.

3.5 Program Modifications There were no new program modifications in 2005.

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 ft 2 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 2005 land use census was conducted between August 29 and September 7, 2005.

An increased DIQ value (> 20%) was calculated for one nearest resident in the WNW sector. The change resulted from greater accuracy in measurement through the use of GPS location identification.

In summary, the highest D/Q locations for nearest garden, nearest residence and nearest milk animal did not change from the 2004 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 5A4 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 2005. 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 2 2 beta measurements in fallout averaged 20,600 pCi/M in 1969 and 12,000 pCi/M 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 3 3 pCi/M . Present day levels have stabilized at around 0.025 pCi/M . 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-1 37 and Sr-90 were detected. Cs-137 levels averaged 16.7 pCi/L.

Soybean crop measurements in 1969 averaged 35.5 pCi/g for gross beta and 0.3 pCi/g for Cs-137. Gross beta measured in soil averaged 51.7 pCi/g . Present day measurements for cesium-137 are below detection levels in milk and agricultural crops.

The aqueous environment was monitored by testing of river water, bottom sediments, fish, aquatic vegetation, and periphyton. Specific location comparison of drinking, river, and well water concentrations for tritium and gross beta are not possible. However, tritium background levels, measured at seven separate locations from 1968 to 1970, averaged 970 pCi/L. Present day environmental samples measure below detection levels. Values for gross beta, measured from 1968 to 1970, averaged 9.8 pCi/L in upstream and downstream Mississippi River water, 4.4 pCi/L for well waters, and 18.6 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In shoreline sediments, gross beta background levels in 1970 averaged 49.8 pCi/g for both upstream and downstream samples. Cs-137 activity averaged 0.10 pCi/g for both upstream and downstream samples. Low levels of Cs-137, occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta levels in 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 15.2 mRemf91 days, respectively). The mean for special locations was 15.0 mRemI91 days. The mean for control locations was 15.1 mRem/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1990 through 2004 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).

Year Inner Rin Outer Ring Dose rate (mRemf91 days) 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 2004 16.0 15.4 2005 15.6 15.2 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 3

and control locations (0.025 pCi/M ) and were similar to levels observed from 1990 through 2004.

The results are tabulated below.

Year Indicators l Control 3

Concentration (pCi/m) 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 2004 0.024 0.024 2005 0.025 0.025 Average annual gross beta concentrations in airborne particulates.

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

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

The highest averages usually occur during the months of January and December, and the first and fourth quarters, as seen in 1990 through 2005.

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., 2005b).

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 0.057 pCi/m 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 0.03 pCi/M 3 in all samples.

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Milk lodine-131 activity measured below the detection limit of 0.5 pCi/L in all samples.

One milk sample from location M-28 tested positive for Cs-137, at a concentration of 10.1 pCi/L.

Low levels of cesium-137 are still detected in soil, and are generally attributed to fallout deposition. Ingestion of soil due to low grazing on pasture is the most likely source of Cs-137 activity in milk.

No other gamma-emitting isotopes except naturally-occurring potassium-40, were detected. 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. Common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine.

In summary, the milk data for 2005 show no radiological effects of the plant operation.

River Water and Drinking Water Tritium activity measured below the LLD of 500 pCi/L in all samples. Gross beta activity in Minneapolis drinking water averaged 2.8 pCi/L and was similar to average levels observed from 1990 through 2004. Gross beta averages are tabulated below.

Year l Gross Beta 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 2004 2.7 2005 2.8 Average annual concentrations; Gross beta in drinking water.

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

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Well Water Tritium measured below the LLD level of 500 pCi/L in all samples. All gamma isotopic results were below detection limits. There was no indication of a plant effect.

Crovs Cabbage and broccoli were collected in September from three locations and analyzed for iodine-131. Levels of 1-131 measured below 0.031 pCi/g wet weight in both samples. Other gamma-emitting isotopes were below respective LLD levels. There was no indication of a plant effect.

There were no crops irrigated from the Mississippi River within 5 miles of the plant in 2005; 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 (3.07 and 3.11 pCi/g wet weight, respectively). All gamma-emitting isotopes were below their respective LLD levels. There was no indication of any plant effect.

Invertebrates Samples were collected in May and October. The samples were analyzed for gamma-emitting isotopes. 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 three of four downstream samples, averaging 0.14 pCi/g dry weight, and 0.029 pCi/g dry weight in one of two control samples. Similar levels of activity and distribution have been observed since 1978, and are indicative of the influence of fallout deposition The only other gamma-emitting isotope detected was naturally-occurring potassium-40. There was no indication of a plant effect.

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5.0 FIGURES AND TABLES 12

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

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

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

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

GS (MC), H-3 (QC)

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

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

Potatoes' 1 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 G/SA GS Shoreline sediment 3 M-8(C), M-9, M-15 G/SA GS a Location codes are defined in Table 5.2, Control stations are indicated by (C). All other stations are indicators.

bCollection type is coded as follows: Cl = continuous, GJ = grab. Collection frequency is coded as follows:

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

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

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

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

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

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Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.

Distance and Direction from Code Typea 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 0.8 mi @ 140'/SE M-3 Air Station M-3 AP, Al 0.6 mi @ 104'/ESE M-4 Air Station M-4 AP, Al 0.8 mi @ 1461lSSE M-5 Air Station M-5 AP, Al 2.6 mi @ 1340/SE M-8 C Upstream of Plant SW, SS, BO, F < 1000' upstream of Plant Intake M-9 Downstream of Plant SW, SS, BO, F < 1000' downstream of Plant Discharge M-1 0 C Campbell Farm M, WW 10.6 mi @ 357°/N M-11 City of Monticello WW 3.3 mi @ 127w/SE M-12 Plant Well #1 WW 0.26 mi @ 2520/SW M-14 City of Minneapolis DW 37.0 mi @ 132 0/SE M-15 Montissippi Park SS 1.27 ml @ 114'/ESE M-19 River Irrigated Corn Fieldc M-21 River Irrigated Potato Fieldc M-24 Weinand Farm M 4.7 mi @ 1800/S M-27 Wise residence (Highest D/Q Garden) VE, WW 0.64 mi @ 207°/SSW

a. Available Producer VE > 10.0 mi.

M-28 Hoglund Farm M 3.8 mi @ 300°/WNW General Area of the Site Boundary M-O1A Sherburne Ave. So. TLD 0.75 mi @ 353°lN M-02A Sherburne Ave. So. TLD 0.79 mi @ 23°/NNE M-03A Sherburne Ave. So. TLD 1.29 mi @ 55°/NE M-04A Biology Station Road TLD 0.5 mi @ 86°/E M-05A Biology Station Road TLD 0.48 mi @ 118°/ESE M-06A Biology Station Road TLD 0.54 mi @ 135°/SE M-07A County Road 75 TLD 0.5 mi @ 155°/SSE M-08A County Road 75 TLD 0.48 mi @ 1720/S M-09A County Road 75 TLD 0.38 mi @ 209°/SSW M-1OA County Road 75 TLD 0.38 mi @ 226°/SW M-11A County Road 75 TLD 0.4 mi @ 239°lWSW 0

M-12A County Road 75 TLD 0.5 mi @ 262 °W M-13A North Boundary Road TLD 0.89 mi @ 324°/NW M-14A North Boundary Road TLD 0.78 mi @ 334°/NNW 14

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

Distance and Direction from Code Typea Collection Site Sample Typeb Reactor Approximately 4 to 5 miles Distant from the Plant M-01B Sherco #1 Air Station TLD 4.66 mi @ 02°/N M-02B County Road 11 TLD 4.4 ml @ 180/NNE M-03B County Road 73 & 81 TLD 4.3 ml @ 51°/NE M-04B County Road 73 (196th St.) TLD 4.2 mi @ 67°/ENE M-05B City of Big Lake TLD 4.3 ml @ 89°/E M-06B County Road 14 and 196th St. TLD 4.3 mi @ 117 01ESE M-07B Monte Industrial Drive TLD 4.3 mi @ 136°/SE M-08B Residence, Hwy 25 & Davidson Ave. TLD 4.6 mi @ 162°/SSE M-09B Weinand Farm TLD 4.7 mi @ 178°/S M-10B Reisewitz Farm, Acacia Ave. TLD 4.2 ml @ 204°/SSW M-11B Vanlith Farm, 97th Ave. TLD 4.0 ml @ 228'/SW M-12B Lake Maria State Park TLD 4.2 mi @ 254°/WSW M-13B Bridgewater Station TLD 4.1 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 4.4 mi @ 341°/NNW Special Interest Locations M-01S Osowski Fun Market TLD 0.66 ml @ 2421VWSW M-02S Krone Residence TLD 0.5 ml @ 224°/SW M-03S Big Oaks Park TLD 1.53 ml @ 102°/ESE M-04S Pinewood School TLD 2.3 ml @ 131°/SE M-05S Rivercrest Christian Academy TLD 3.0 ml @ 118°/ESE M-06S Monte Public Works TLD 2.6 ml @ 134°/SE M-01C C Kirchenbauer Farm TLD 11.5 ml @ 323°/NW M-02C C County Roads 4 and 15 TLD 11.2 mi @ 47°/NE M-03C C County Rd 19 and Jason Ave. TLD 11.6 mi @ 130°1SE M-04C C Maple Lake Water Tower TLD 10.3 ml @ 226°/ SW a "C" denotes control location. All other locations are indicators.

b Sample Codes:

AP Airborne particulates M Milk Al Airborne 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 c Collected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields.

15

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

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

Collection Reason for not Sample Analysis Location Date or conducting REMP Plans for Preventing Type Period as required Recurrence SW Gamma M-08 01-05-05 Shoreline frozen None required.

through 03-16-05 AP/AI Beta, M-02 5/11/2005 Air sampler malfunction. Sampler pump replaced.

1-131 AP/AI Beta, M-05 5/18/2005 Air sampler failure due Electrician checked sampler and 1-131 to open fuse. replaced fuse.

Ml Gamma, M-28 6/29/2005 Hoglund Dairy temporarily out Hoglund will inform the MNGP 1-131 through of business for the summer. upon resumption of operation.

10/5/2005 Operation resumed 10/20/05.

AP/AI Beta, M-04 9/14/2005 Breaker tripped during storm. Reset breaker.

1-131 AP/AI Beta, M-03 9/28/2005 Air sampler timer deficient Replaced timer.

1-131 by 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months .

BO Gamma M-08 10/27/2005 No sample available. None required.

16

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

I-Inner 2-- Outer 20l------ - __ _ _--- __ X_ __ _ _

18 -

17 - _ _ _ _

11 _ _ _ _ 1 i_

10 l .k o CN M '1 LO (D 1- 00 0) 0 Of M I )

0) a) a) C) C M M M C) a8 0 0 0

0) C C 0 0 0

- - - _ - - T CN4 N CN N (N E 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)

I i0.035

! 0,033 ]< _

0.031 f __ _

K 1 0.029 - --. -- - ___ _-

0.027 0.021 0L

_ - f _ - _ L --

0.015 _--- -- u ! ! . . LJ O N C\') ) CD t- M 0 0 N O- C) r UL

0) 0) 0) 0) CT) 0) ) 0) CY) 0 0 0 0 0 0 0 0) 0) 0) 0) C) 0) 0) 0) 0) 0 0 0 0 0 0

_N _N N N N Control (M-1) 0.035 0.033 0.031 0.029 0.027 0.025 E 0.023 0 0.021 0.019 0.017 0.015 O r_ C')

e U) (O C-. >) 0) 0 - N C' U7 C

01 0 0 cV) C) 0 ? o Zs o o

0) 0) i) 0 0 0) a0 0) 0) C) o 0 0 0 0 o

_ _ __ - N N CON N N CON 18

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Docket No. 50-263 Location of Facility Wright, Minnesota Reporting Period January-December, 2005

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD' Mean (F)0 Mean (F)f Mean (F)0 Routine (Units) Analysesa Rangec Locationd Range' Rangec Results' TLD (Inner Ring, Gamma 56 3.0 15.6 (56/56) M-12A, County Rd. 75, 17.4 (4 /4) (See Control 0 General Area at (12.5-18.4) 0.5 mi @ 262°/W (15.2-18.4) below.)

Site Boundary) mRem/91 days)

TLD (Outer Ring, Gamma 64 3.0 15.2 (64/64) M-09B, Weinand Farm 16.5 (4 /4) (See Control 0 4-5 mi. distant) (12.3-17.7) 4.7 mi @ 178'/S (14.6-17.7) below.)

mRem/91 days)

TLD (Special Gamma 24 3.0 15.0 (24/24) M-06S, Mont. Pub. Wks. 16.9 (4 /4) (See Control 0 Interest Areas) (11.3-17.7) 2.6 mi @ 134°/SE (15.5-17.7) below.)

mRem/91 days)

TLD (Control) Gamma 16 3.0 None M-03C, County and 16.1 (4 /4) 15.1 (16/16) 0 mRem/91 days) Jason, 11.6 mi @ 130°/SE (15.5-17.3) ( 13.7-17.3)

Airborne GB 256 0.005 0.025 (204/204) M-5, Air Station 0.026 (51 /51) 0.025 (52/52) 0 Particulates (0.007-0.064) 2.6 mi @ 134°/SE (0.009-0.058) (0.010-0.066)

(pCi/m 3 )

GS 20 Be-7 0.015 0.063 (16/16) M-2, Air Station 0.071 (4/4) 0.064 (4/4) 0 (0.037-0.100) 0.8 mi @ 140°/SE (0.052-0.100) (0.040-0.086)

Mn-54 0.0007 < LLD < LLD 0 Co-58 0.0008 < LLD < LLD 0 Co-60 0.0010 < LLD < LLD 0 Zn-65 0.0016 < LLD < LLD 0 Zr-Nb-95 0.0012 < LLD < LLD 0 Ru-103 0.0011 < LLD . < LLD 0 Ru-106 0.0079 < LLD < LLD 0 Cs-134 0.0009 < LLD < LLD 0 Cs-137 0.0008 < LLD < LLD 0 Ba-La-140 0.0030 < LLD < LLD 0 Ce-141 0.0020 < LLD < LLD 0 Ce-144 0.0055 < LLD < LLD 0 Airborne Iodine 1-131 256 0.03 < LLD < LLD 0 (pCi/m 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, 2005

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD' Mean (F)c Mean (F)' Mean (F)' Routine (Units) Analysesa Rangec Locationd Range' Range' Resultse Milk (pCi/L) 1-131 49 0.5 < LLD <-LLD 0 GS 49 K-40 200 1305 (30130) M-28 1331 (11 /11) 1285 (19119) 0 (1180-1430) Hoglund Farm (1235-1430) (1174-1395)

Cs-134 5 < LLD < LLD 0 Cs-1 37 5 10.1 (1130) M-28 10.1 (1/11) < LLD 0 Hoglund Farm Ba-La-140 5 < LLD < LLD 0 River Water H-3 8 330 < LLD _ _ < LLD 0 (pCi/L)

GS 16 Mn-54 15 < LLD - < LLD 0 Fe-59 30 < LLD "<LLD 0 Co-58 15 < LLD - < LLD 0 Co-60 15 < LLD - < LLD 0 Zn-65 30 < LLD - < LLD 0 Zr-Nb-95 15 < LLD - < LLD 0 Cs-134 15 < LLD - < LLD 0 Cs-137 18 < LLD - < LLD 0 Ba-La-140 15 < LLD - < LLD 0 Ce-144 46 < 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, 2005

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)' Routine (Units) Analysesa Rangec Locationd Rangec Range0 Results' Drinking Water GB 10 1.6 2.8 (10112) M-14, Minneapolis 2.8 (10/12) None 0 (pCUL) (2.1-4.6) 37.0 mi. @ 132° /SE (2.1-4.6) 1-131 10 1.0 < LLD - None 0 H-3 4 500 < LLD - None 0 GS 10 Mn-54 15 < LLD - None 0 Fe-59 30 < LLD - None 0 Co-58 15 < LLD - None 0 Co-60 15 < LLD - None 0 Zn-65 30 < LLD - None 0 Zr-Nb-95 15 < LLD - None 0 Cs-134 10 < LLD - None 0 Cs-137 18 < LLD - None 0 Ba-La-140 15 < LLD - None 0 Ce-144 51 < LLD . None 0 Well Water H-3 16 500 < LLD . < LLD 0 (pCi/L)

GS 16 Mn-54 15 < LLD . cLLD

< 0 Fe-59 30 < LLD . cLLD

< 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 c- 0 Cs-137 18 < LLD c-

<LLD 0 Ba-La-140 15 < LLD c-LLD 0 Ce-144 56 < LLD <LLD c- 0 Crops -Cabbage GS 2 (pCi/gwet) 1-131 0.031 < LLD <LLD c- 0 Cs-134 0.008 < LLD < LLD 0 Cs-137 0.019 < LLD c LLD 0 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, 2005

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)0 Mean (F)c Mean (F)c Routine (Units) Analysesa Range' Locationd Range0 Range' Resultse Fish GS 4 (pCi/g wet) K-40 0.10 3.11 (2/2) 2 3.11 (2/2) 3.07 (2/2) 0 (3.05-3.17) M-09 (3.05-3.17) (2.82-3.32)

Mn-54 0.024 < LLD < LLD 0 Fe-59 0.048 < LLD < LLD 0 Co-58 0.031 < LLD < LLD 0 Co-60 0.025 < LLD < LLD 0 Zn-65 0.045 < LLD < LLD 0 Zr-Nb-95 0.053 < LLD < LLD 0 Cs-134 0.017 < LLD < LLD 0 Cs-137 0.020 < LLD < LLD 0 Ba-La-140 0.15 < LLD < LLD 0 Ce-144 0.09 < LLD < LLD 0 Invertebrates GS 4 (pCi/g wet) Be-7 0.74 < LLD < LLD 0 K140 1.27 < LLD < LLD 0 Mn-54 0.05 < LLD < LLD 0 Fe-59 0.16 < LLD < LLD 0 Co-58 0.07 < LLD c LLD 0 Co-60 0.06 < LLD < LLD 0 Zn-65 0.13 < LLD < LLD 0 Zr-Nb-95 0.13 < LLD < LLD 0 Ru-103 0.12 < LLD < LLD 0 Ru-106 0.53 < LLD < LLD 0 Cs-134 0.06 < LLD < LLD 0 Cs-137 0.05 < LLD < LLD 0 Ba-La-140 0.51 < LLD < LLD 0 Ce-144 0.42 < 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, 2005

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F) Routine (Units) Analyseso Rangec Locationd Range' Range 0 Resultse Shoreline GS 6 Sediments Be-7 0.34 < LLD - < LLD 0 (pCi/g dry)

K-40 0.10 11.46 (4/4) M-09, Downstream 12.14 (2/2) 10.81 (2/2) 0 (9.77-12.23) 0.2 mi @ 62 0/ENE (12.04-12.23) (10.31-11.31)

Mn-54 0.026 < LLD < LLD 0 Fe-59 0.135 < LLD < LLD 0 Co-58 0.033 < LLD < LLD 0 Co-60 0.025 < LLD < LLD 0 Zn-65 0.075 < LLD < LLD 0 Nb-95 0.073 < LLD - < LLD 0 Zr-95 0.072 < LLD - < LLD 0 Ru-103 0.050 < LLD - < LLD 0 Ru-106 0.25 < LLD - < LLD 0 Cs-1 34 0.036 < LLD - < LLD 0 Cs-137 0.025 0.14 (3/4) M-09, Downstream 0.15 (2/2) 0.029 (112) 0 (0.11-0.20) 0.2 mi @ 62 0/ENE (0.11-0.20) -

Ba-La-140 0.37 < LLD < LLD 0 Ce-144 0.15 < 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.

Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).

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

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

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 2006a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2005.

2001b through 2006b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000 through 2005.

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

2005. Quality Control Procedures Manual, Rev. 0, 17 September 2005.

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. "Chernobyl,"

Chemtech, October 1986, pp. 596-605.

National Center for Radiological Health, 1968. Radiological Helath and Data Reports, Vol. 9, Number 12, 730-746.

Northern States Power Company.

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

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

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

24

6.0 REFERENCES

CITED (continued)

Northern States Power Company.

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

1984 through 2000. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January I 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.

11984b to 2000b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.

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

U.S. Environmental Protection Agency.

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

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

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

XCEL Energy Corporation.

2006. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2000 through 2005. (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 25

- Environmental, Inc.

Midwest Laboratory X/ an Allegheny Technologies Co.

700 Landwehr Road. Northbrook, IL 60062-2310 ph. (847) 564 0700, fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte perfon-nance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January, 2005 through December, 2005

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

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

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

The results in Table A-2 list results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internal laboratory testing.

Table A-3 lists results of the analyses on in-house '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.

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

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

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 pCi/liter or kg 5.0 pCi/liter

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

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

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

20 pCi/liter 5.0 pCi/liter

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

100 pCi/liter 5.0 pCi/liter

> 100 pCi/liter 5% of known value Tritium

4,000 pCi/liter l ao= (pCi/liter) =

169.85 x (known)0093 3

> 4,000 pCi/liter 10% of known value Radium-226,-228 2 0.1 pCi/liter 15% of known value Plutonium Ž 0.1 pCi/liter, gram, or sample 10% of known value lodine-131,

55 pCi/liter 6.0 pCi/liter Iodine-129b > 55 pCi/liter 10% of known value Uranium-238, 5 35 pCi/liter 6.0 pCi/liter Nickel-63b > 35 pCi/liter 15% of known value Technetium-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter

> 100 pCi/liter 10% of known value Othersb_ 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limit.

A2

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resuitb Resultc Limits Acceptance STW-1051 02/1 5/05 Sr-89 28.0 +/- 1.2 29.4 20.7 - 38.1 Pass STW-1051 02/15/05 Sr-90 25.1 +/- 0.7 24.4 15.7 - 33.1 Pass STW-1052 02/15/05 Ba-133 52.9 +/- 2.8 53.4 44.2 - 62.6 Pass STW-1052 02/15/05 Co-60 54.4 +/- 0.4 56.6 47.9 - 65.3 Pass STW-1 052 02/15/05 Cs-1 34 67.7 +/- 1.8 64.9 56.2 - 73.6 Pass STW-1052 02/15/05 Cs-137 39.6 +/- 1.8 40.2 31.5 - 48.9 Pass STW-1052 02/15/05 Zn-65 159.7 +/-3.0 161.0 133.0 - 189.0 Pass STW-1053 02/15/05 Gr. Alpha 55.1 +/-1.8 67.9 38.5 - 97.3 Pass STW-1 053 02/15/05 Gr. Beta 46.8 +/- 1.3 51.1 38.5 - 97.3 Pass STW-1054 02/15/05 Ra-226 13.7 +/- 1.5 14.1 10.4 - 17.8 Pass STW-1054 02/15/05 Ra-228 13.3 +/- 0.6 13.7 7.8 - 19.6 Pass STW-1054 02/15/05 Uranium 5.1 +/-0.2 5.0 0.0 - 10.2 Pass STW-1055 05/17/05 Sr-89 45.1 +/- 4.1 41.3 32.6 - 50.0 Pass STW-1055 05/17/05 Sr-90 7.5 +/- 0.9 5.9 0.0 - 14.6 Pass STW-1 056 05/17/05 Ba-i 33 87.1 +/- 2.0 88.4 73.1 - 104.0 Pass STW-1 056 05/17/05 Co-60 38.4 +/- 0.8 37.0 28.3 - 45.7 Pass STW-1056 05/17/05 Cs-i 34 75.3 +/- 0.7 78.6 69.9 - 87.3 Pass STW-1 056 05/17/05 Cs-137 201.0 +/- 8.4 194.0 184.0 - 218.0 Pass STW-1 056 05/17/05 Zn-65 130.0 +/- 6.7 118.0 97.6 - 138.0 Pass STW-1 057 05/17/05 Gr. Alpha 42.7 +/- 2.9 37.0 21.0 - 53.0 Pass STW-1057 05/17/05 Gr. Beta 34.0 +/- 0.4 34.2 25.5 - 42.9 Pass STW-1058 05/17/05 1-131 14.7 +/- 0.5 15.5 10.3 - 20.7 Pass STW-1 059 05/17/05 Ra-226 6.6 +/- 0.1 7.6 5.6 - 9.5 Pass STW-1 059 05/17/05 Ra-228 19.3 +/- 0.7 18.9 10.7 - 27.1 Pass STW-1059 05/17/05 Uranium 9.6 +/-0.1 10.1 4.9 - 15.3 Pass STW-1 060 05/17/05 H-3 24100.0 +/- 109.0 24400.0 20200.0 - 28600.0 Pass STW-1 067 08/16/05 Sr-89 29.1 +/- 3.0 28.0 19.3 - 36.7 Pass STW-1067 08/16/05 Sr-90 36.0 +/- 0.6 33.8 25.1 - 42.5 Pass STW-1068 08/16/05 Ba-133 107.0 +/- 1.7 106.0 87.7 - 124.0 Pass STW-1068 08/16/05 Co-60 15.2 +/- 0.2 13.5 4.8 - 22.2 Pass STW-1 068 08/16/05 Cs-134 89.1 +/- 0.3 92.1 83.4 - 101.0 Pass STW-1 068 08/16/05 Cs-1 37 72.1 +/- 1.0 72.7 64.0 - 81.4 Pass STW-1 068 08/16/05 Zn-65 67.4 +/- 1.4 65.7 54.3 - 77.1 Pass STW-1 069 08/16/05 Gr. Alpha 44.3 +/- 1.5 55.7 31.6 - 79.8 Pass STW-1069 08/16/05 Gr. Beta 58.4 +/-2.1 61.3 44.0 - 78.6 Pass STW-1 070 08/16/05 Ra-226 16.6 +/- 1.5 16.6 12.3 - 20.9 Pass STW-1070 08/16/05 Ra-228 6.2 +/- 0.3 6.2 3.5 - 8.9 Pass STW-1 070 08/16/05 Uranium 4.5 +/- 0.1 4.5 0.0 - 9.7 Pass A1-1

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1 072 1/1 15/05 Sr-89 20.6 +/- 0.4 19.0 10.3 - 27.7 Pass STW-1 072 11/15/05 Sr-90 15.0 +/- 0.3 16.0 7.3 - 24.7 Pass STW-1 073 11/15/05 Ba-1 33 31.8 +/- 1.8 31.2 22.5 - 39.9 Pass STW-1 073 11/15/05 Co-60 85.0 +/- 1.4 84.1 75.4 - 92.8 Pass STW-1 073 11/15/05 Cs-1 34 37.2 +/- 2.1 33.9 25.2 - 42.6 Pass STW-I 073 11/15/05 Cs-1 37 27.8 +/- 0.7 28.3 19.6 - 37.0 Pass STW-1 073 11/15/05 Zn-65 109.0 +/- 1.0 105.0 86.8 - 123.0 Pass STW-1 074 d 11/15/05 Gr. Alpha 41.1 +/- 1.2 23.3 13.2 - 33.4 Fail STW-1 074 11/15/05 Gr. Beta 42.7 +/- 0.5 39.1 30.4 - 47.8 Pass STW-1 075 11/15/05 1-131 20.5 +/- 0.6 17.4 12.2 - 22.6 Pass STW-1 076 11/15/05 Ra-226 7.8 +/- 0.6 8.3 6.2 - 10.5 Pass STW-1076 e 11/15/05 Ra-228 5.5 +/- 0.6 3.5 2.0 - 5.0 Fail STW-1 076 11/15/05 Uranium 15.5 +/- 0,3 16.1 10.9 - 21.3 Pass STW-1 077 11/15/05 H-3 12500.0 +/- 238.0 12200.0 10100.0 - 14300.0 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

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

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

d The original samples were calculated using an Am-241 efficiency. The samples were spiked with Th-232. Samples were recounted and calculated using the Th-232 efficiency. Results of the recount: 27.01 +/- 2.35 pCi/L.

e Decay of short-lived radium daughters contributed to a higher counting rate. Delay of counting for 100 minutes provided better results.

The reported result was the average of the first cycle of 100 minutes, the average of the second cycle counts was 4.01 pCi/L A1-2

TABLE A-2, Crosscheck program results; Thermoluminescent Dosimetry, (TLD, CaSO4: Dy Cards).

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

2005-1 4/4/2005 30 cm 55.01 64.02 +/- 2.86 38.51 - 71.51 Pass 2005-1 4/4/2005 60 cm 13.75 15.43 +/- 1.02 9.63 - 17.88 Pass 2005-1 4/4/2005 60 cm 13.75 14.98 +/- 0.80 9.63 - 17.88 Pass 2005-1 4/4/2005 90 cm 6.11 6.24 +/- 0.16 4.28 - 7.94 Pass 2005-1 4/4/2005 90 cm 6.11 5.45 +/- 0.48 4.28 - 7.94 Pass 2005-1 4/4/2005 120 cm 3.44 3.50 +/- 0.35 2.41 - 4.47 Pass 2005-1 4/4/2005 120 cm 3.44 3.15 +/- 0.18 2.41 - 4.47 Pass 2005-1 4/4/2005 150 cm 2,2 2.31 +/- 0.25 1.54 - 2.86 Pass 2005-1 4/4/2005 180 cm 1.53 1.65 +/- 0.41 1.07 - 1.99 Pass Environmental, Inc.

2005-2 9/12/2005 30 cm 54.84 59.30 +/- 2.66 38.39 - 71.29 Pass 2005-2 9/12/2005 60 cm 13.71 17.55 +/- 1.30 9.60 - 17.82 Pass 2005-2 9/12/2005 75 cm 8.77 8.24 +/- 0.38 6.14 - 11.40 Pass 2005-2 9/12/2005 90 cm 6.09 5.94 +/- 0.49 4.26 - 7.92 Pass 2005-2 9/12/2005 90 cm 6.09 5.93 +/- 0.37 4.26 - 7.92 Pass 2005-2 9/12/2005 120 cm 3.43 3.42 +/- 0.18 2.40 - 4.46 Pass 2005-2 9/12/2005 150 cm 2.19 1.71 +/- 0.14 1.53 - 2.85 Pass 2005-2 9/12/2005 150 cm 2.19 1.87 +/- 0.27 1.53 - 2.85 Pass 2005-2 9/12/2005 180 cm 1.52 1.58 +/- 0.99 1.06 - 1.98 Pass A2-1

TABLE A-3. In-House 'Spike" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 C Activity Limits d Acceptance W-11105 1/11/2005 Gr. Alpha 24.05 +/- 1.01 20.08 10.04 - 30.12 Pass W-11105 1/11/2005 Gr. Beta 61.59 +/- 1.11 65.70 55.70 - 75.70 Pass SPW-764 2/18/2005 H-3 77595.00 i 764,00 80543.00 64434.40 - 96651.60 Pass SPAP-766 2/18/2005 Gr. Beta 416.08 +/- 5.52 463.00 370.40 - 509.30 Pass STW-2887 2/28/2005 Tc-99 32.91 +/- 1.23 32.98 20.98 - 44.98 Pass W-30105 3/1/2005 Gr. Alpha 25.22 +/- 0.45 20.08 10.04 - 30.12 Pass W-30105 3/1/2005 Gr. Beta 62.27 +/- 0.48 65.73 55.73 - 75.73 Pass SPW-1836 4/15/2005 1-131 109.79 +/- 0.94 106.30 85.04 - 127.56 Pass SPW-1836 4/15/2005 1-131 (G) 110.25 +/- 9.68 106.30 95.67 - 116.93 Pass SPMI-1 838 4/15/2005 Cs-134 25.94 +/- 1.28 26.60 16.60 - 36.60 Pass SPMI-1838 4/15/2005 Cs-137 59.31 +/- 3.66 60.90 50.90 - 70.90 Pass SPMI-1838 4/15/2005 1-131 97.71 +/-0.81 106.30 85.04 - 127.56 Pass SPMI-1838 4/15/2005 1-131(G) 109.45 +/- 3.06 106.30 95.67 - 116.93 Pass SPMI-1838 4/15/2005 Sr-89 104.44 +/- 2.89 108.20 86.56 - 129.84 Pass SPMI-1838 4/15/2005 Sr-90 8.97 +/- 0.79 7.53 0.00 - 17.53 Pass SPVE-1932 4/18/2005 1-131 (G) 1.00 +/- 0.04 0.73 0.44 - 1.02 Pass SPCH-1935 4/18/2005 I-131 382.40 +/- 14.95 328.64 262.91 - 394.37 Pass SPAP-1966 4/18/2005 Cs-134 52.10 +/- 7.27 53.35 43.35 - 63.35 Pass SPAP-1966 4/18/2005 Cs-134 57.28 +/- 13,47 53.35 43.35 - 63.35 Pass SPAP-1966 4/18/2005 Cs-1 37 124.68 +/- 18.41 121.77 109.59 - 133.95 Pass SPAP-1968 4/18/2005 Cs-134 52.10 +/- 7.27 53.35 43.35 - 63.35 Pass SPAP-1968 4/18/2005 Cs-137 116.79 +/- 14.00 121.77 109.59 - 133.95 Pass SPW-2098 4/26/2005 Fe-55 2565.20 +/- 63.66 3017.60 2414.08 - 3621.12 Pass SPW-2922 5/31/2005 Cs-1 34 27.01 +/- 1.09 25.54 15.54 - 35.54 Pass SPW-2922 5/31/2005 Cs-134 65.38 +/- 2.92 60.71 50.71 - 70.71 Pass SPW-2922 5/31/2005 Sr-89 107.90 +/- 3.60 113.90 91.12 - 136.68 Pass SPW-2922 5/31/2005 Sr-90 11.11 +/- 1.13 6.90 0.00 - 16.90 Pass SPAP-2892 6/1/2005 Gr. Beta 420.32 +/- 5.55 448.00 358.40 - 492.80 Pass SPW-2895 6/1/2005 H-3 75271.00 +/- 724.00 78676.00 62940.80 - 94411.20 Pass w-60105 6/1/2005 Gr. Alpha 23.69 +/- 0.52 20.08 10.04 - 30.12 Pass w-60105 6/1/2005 Gr. Beta 60.08 +/- 0.57 65.73 55.73 - 75.73 Pass SPF-3089 6/7/2005 Cs-134 1.08 +/- 0.05 1.02 0.61 - 1.43 Pass SPF-3089 6/7/2005 Cs-137 2.54 +/- 0.10 2.43 1.46 - 3.40 Pass SPW- 7/1/2005 Ni-63 20.57 +/- 1.10 16.75 10.05 - 23.45 Pass SPW-47731 8/24/2005 C-1 4 2112.30 +/- 9.13 2370.80 1422.48 - 3319.12 Pass SPW-47732 8/24/2005 C-1 4 2294.10 +/- 10.37 2370.80 1422.48 - 3319.12 Pass SPW-4775 8/24/2005 Fe-55 2633.50 +/- 62.40 2777.50 2222.00 - 3333.00 Pass SPMI-4834 8/30/2005 Cs-1 34 49.27 +/- 4.68 47.02 37.02 - 57.02 Pass SPMI-4834 8/30/2005 Cs-1 37 58.17 +/- 8.18 60.37 50.37 - 70.37 Pass SPMI-4834 8/30/2005 Sr-89 66.39 +/- 3.13 65.90 52.72 - 79.08 Pass SPMI-4834 8/30/2005 Sr-90 11.15 +/- 1.13 9.60 0.00 - 19.60 Pass A3-1

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

Lab Code Date Analysis Laboratory results Known Control 2s, n=1b Activity Limitsc Acceptance SPW-4836 8/30/2005 Cs-134 47.35 +/- 5.19 47.02 37.02 - 57.02 Pass SPW-4836 8/30/2005 Cs-1 37 62.91 +/- 9.08 60.37 50.37 - 70.37 Pass SPW-4836 8/30/2005 Sr-89 11.04 +/- 0.98 9.60 0.00 - 19.60 Pass SPW-4836 8/30/2005 Sr-90 65.89 +/- 2.79 65.90 52.72 - 79.08 Pass SPW-5014 8/3012005 H-3 77518.20 +/- 753.80 77602.52 62082.02 - 93123.02 Pass W-90705 9/7/2005 Gr. Alpha 24.61 +/- 0.48 20.08 10.04 - 30.12 Pass W-90705 9/7/2005 Gr. Beta 58.35 +/- 0.49 65.73 55.73 - 75.73 Pass SPW-5237 9/22/2005 C-14 2387.40 +/- 11.00 2370.80 1422.48 - 3319.12 Pass SPW-5508 9/2612005 Ni-63 20.64 +/- 1.23 16.70 10.02 - 23.38 Pass SPW-6019 10/24/2005 Tc-99 547.99 +/- 6.69 539.22 377.45 - 700.99 Pass SPF-6293 11/4/2005 Cs-1 34 941.30 +/-44.10 886.00 797.40 - 974.60 Pass SPF-6293 11/4/2005 Cs-137 2570.40 +/- 105,30 2400.00 2160.00 - 2640.00 Pass SPAP-6309 11/7/2005 Cs-134 41.24 i 1.91 44.03 34.03 - 54.03 Pass SPAP-6309 11/7/2005 Cs-137 114.03 +/- 5.01 120.24 108.22 - 132.26 Pass SPAP-6311 11/7/2005 Gr. Beta 1.58 +/- 0.02 1.42 1.14 - 11.42 Pass SPW-6451 11/10/2005 H-3 77126.00 +/- 747.00 76749.00 61399,20 - 92098.80 Pass W-1 20105 121112005 Gr. Alpha 25.16 + 0.45 20.08 10.04 - 30.12 Pass W-1 20105 12/112005 Gr. Beta 74.58 + 0.81 65.73 55.73 - 75.73 Pass SPW-7440 12/30/2005 Cs-1 34 42.67 i 4.22 42.03 32.03 - 52.03 Pass SPW-7440 12/30/2005 Cs-1 37 61.19 i7.20 59.91 49.91 - 69.91 Pass SPMI-7442 12/31/2005 Cs-134 40.41 i 5.66 42.03 32.03 - 52.03 Pass SPMI-7442 12/31/2005 Cs-137 60.05 +/- 7.80 59.91 49.91 - 69.91 Pass a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/i 3), and solid samples (pCilg).

bLaboratory codes as follows: W (water), MI (milk), AP (air filter), SO (soil), VE (vegetation),

CH (charcoal canister), F (fish).

' Results are based on single determinations.

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

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

A3-2

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

W-11105 water 1/11/2005 Gr. Alpha 0.055 0.00 i 0.038 W-11105 water 1/11/2005 Gr. Beta 0.15 -0.016 +/- 0.10 3.2 SPW-765 water 2/18/2005 H-3 165.8 7.4 +/- 82.5 200 SPAP-766 Air Filter 2/1812005 Gr. Beta 0.72 0.29 +/- 0.48 3.2 STW-2888 water 2/28/2005 Tc-99 1.32 0.45 +/- 0.81 10 W-30105 water 3/1/2005 Gr. Alpha 0.067 -0.007 +/- 0.043 1 W-30105 water 3/1/2005 Gr. Beta 0.18 -0.04 +/- 0.11 3.2 SPW-1837 water 4/15/2005 Cs-134 4.66 10 SPW-1837

water 4/15/2005 Cs-137 5.38 10 SPW-1 837 water 4/15/2005 1-131 0.30 -0.13 +/- 0.16 0.5 SPW-1 837 water 4/15/2005 I-1 31 (G) 6.56 20 SPMI-1839 Milk 4/15/2005 1-131 0.26 -0.083 +/- 0.14 0.5 SPMI-1839 Milk 4/15/2005 Sr-89 0.54 -0.069 +/- 0.56 5 SPMI-1839 Milk 4/15/2005 Sr-90 0.53 0.88 +/- 0.34 SPCH-1934 Charcoal 4/18/2005 1-131(G) 2.34 9.6 SPW-2097 water 4/26/2005 Fe-55 859.0 96.1 +/- 528.4 1000 SPW-2923 water 5/31/2005 Cs-134 3.29 10 SPW-2923 water 5/31/2005 Cs-137 3.87 10 SPW-2896 water 6/1/2005 H-3 138.30 48.1 +/- 85.9 200 w-60105 water 6/1/2005 Gr. Alpha 0.061 0.002 +/- 0.043 1 w-60105 water 6/1/2005 Gr, Beta 0.16 0.056 +/- 0.11 3.2 SPF-3090 Fish 6/7/2005 Cs-1 34 15.69 100 SPF-3090 Fish 6/7/2005 Cs-137 11.71 100 SPW- water 7/1/2005 Ni-63 1.60 0.79 +/- 0.99 20 SPW-4774 water 8/2412005 C-14 12.18 2.84 +/- 6.45 200 SPW-4776 water 8/24/2005 Fe-55 833 275 +/- 525 1000 SPMI-4835 Milk 8/30/2005 Co-60 4.42 10 SPMI-4835 Milk 8/30/2005 Cs-134 4.18 10 SPMI-4835 Milk 8/30/2005 Cs-1 37 6.25 10 SPMI-4835 Milk 8/30/2005 1-131(G) 5.37 20 SPMI-4835 Milk 8/30/2005 Sr-89 0.66 -0.23 +/- 0.65 5 SPMI-4835 d Milk 8/3012005 Sr-90 0.66 1.02 +/- 0.41 SPW-4837 water 8/30/2005 Co-60 2.48 10 SPW-4837 water 8/30/2005 Cs-134 3.85 10 SPW-4837 water 8/30/2005 Cs-137 3.00 10 SPW-4837 water 8/30/2005 Sr-89 0.63 0.25 +/- 0.53 5 SPW-4837 water 8/30/2005 Sr-90 0.63 -0.035 +/- 0.29 1 SPW-5015 water 8/30/2005 H-3 142.8 168 +/- 93 200 SPW-5238 water 9/22/2005 C-1 4 17.10 3.02 +/- 9.04 200 A4-1

TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)8 Lab Code Sample Date Analysis Laboratory results (4.66a) Acceptance Type LLD Activityb Criteria (4.66 a)

W-90705 water 9/7/2005 Gr. Alpha 0.056 0.034 +/- 0.04 W-90705 water 917/2005 Gr. Beta 0.16 0.082 +/- 0.11 3.2 SPW-5238 water 9/22/2005 C-14 17.10 3.02 +/- 9.04 200 SPW-5509 water 9/2612005 Ni-63 1.25 1.23 +/- 0.79 20 SPW-6020 water 10124/2005 Tc-99 4.81 -1.75 +/- 2.90 10 SPF-6294 Fish 11/4/2005 Cs-1 34 18.60 100 SPF-6294 Fish 11/4/2005 Cs-1 37 12.99 100 SPAP-6310 Air Filter 11/7/2005 Cs-1 34 3.23 100 SPAP-631 0 Air Filter 11/7/2005 Cs-137 3.86 100 SPAP-6312 Air Filter 11/7/2005 Gr. Beta 1.22 -0.64 +/- 0.64 3.2 W-1 20105 water 12/11/2005 Gr. Alpha 0.05 0.033 +/- 0.04 1 W-1 20105 water 12/11/2005 Gr. Beta 0.15 -0.043 +/- 0.11 3.2 SPMI-741 9 Milk 12/22/2005 Co-60 7.24 10 SPMI-741 9 Milk 12122/2005 Cs-1 37 5.61 10 SPMI-7419 Milk 12/22/2005 1-131(G) 10.96 20 SPW-742 1 water 12/22/2005 Co-60 2.43 10 SPW-7421 water 12/22/2005 Cs-1 37 3.12 10 SPW-7441 water 12/30/2005 Cs-1 34 4.25 10 SPW-744 1 water 12/30/2005 Cs-1 37 1.63 10 SPMI-7443 Milk 12/30/2005 Cs-1 34 4.74 10 SPMI-7443 Milk 12/30/2005 Cs-137 8.53 10 a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/g).

b Activity reported is a net activity result. For gamma spectroscopic analysis, activity detected below the LLD value is not reported c 1-131 (G); iodine-1 31 as analyzed by gamma spectroscopy.

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

A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)8 Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SW-62, 63 1/3/2005 Gr. Beta 3.01 +/- 0.57 2.39 +/- 0.58 2.70 +/- 0.41 Pass SW-62, 63 1/3/2005 K-40 2.00 +/- 0.20 2.10 +/- 0.20 2.05 +/- 0.14 Pass CF-95, 96 1/3/2005 Gr. Beta 6.26 +/- 0.23 6.28 +/- 0.23 6.27 +/- 0.16 Pass CF-95, 96 1/3/2005 K-40 5.68 +/- 0.59 5.37 +/- 0.48 5.53 +/- 0.38 Pass AP-791, 792 1/14/2005 Be-7 0.057 +/- 0.017 0.07 +/- 0.04 0.06 +/- 0.02 Pass WW-353, 354 1/19/2005 Gr. Beta 8.37 +/- 1.21 10.28 +/- 1.34 9.32 +/- 0.90 Pass SO-383, 384 1/19/2005 H-3 453.50 +/- 107.20 417.90 +/- 106.00 435.70 +/- 75.38 Pass LW-431, 432 1/27/2005 Gr. Beta 2.45 +/- 0.54 2.20 +/- 0.54 2.33 +/- 0.38 Pass MI-486, 487 2/1/2005 K-40 1319.40 +/- 163.60 1177.20 +/- 179.70 1248.30 +/- 121.51 Pass SW-511, 512 2/1/2005 1-131 0.37 +/- 0.22 0.44 +/- 0.23 0.40 +/- 0.16 Pass TD-628, 629 2/112005 H-3 489663 +/- 1918 491225 +/- 1915 490444 +/- 1355 Pass DW-538, 539 21312005 Gr. Beta 3.93 +/- 1.18 3.62 +/- 1.10 3.78 +/- 0.81 Pass MI-564, 565 2/8/2005 K-40 1316.20 +/- 171.10 1292.60 +/- 154.40 1304.40 +/- 115.23 Pass DW-50134, 5 2/11/2005 Gr. Beta 18.41 +/- 0.98 16.76 i 0.98 17.59 +/- 0.69 Pass SWU-893, 894 2/22/2005 Gr. Beta 4.00 +/- 0,96 4.20 i 0.72 4.10 +/- 0.60 Pass SW-925, 926 2/25/2005 Gr. Beta 5.97 +/- 1.51 6.14 +/- 1.55 6.06 +/- 1.08 Pass SW-950, 951 3/1/2005 Gr. Beta 0.92 +/- 0.27 1.21 +/- 0.27 1.07 +/- 0.19 Pass SW-950, 951 3/1/2005 Gr. Beta 2.06 +/- 0.40 2.29 +/- 0.44 2.18 +/- 0.30 Pass SW-973, 974 3/1/2005 1-1 31 1.08 +/- 0.19 0.92 +/- 0.18 1.00 +/- 0.13 Pass DW-50248, 9 3/16/2005 Gr. Alpha 5.27 i 1.06 4.17 +/- 0.90 4.72 +/- 0.70 Pass DW-1264, 1265 3/19/2005 1-131 0.54 +/- 0.21 0.73 +/- 0.20 0.63 +/- 0.15 Pass AP-1955, 1956 3/28/2005 Be-7 0.071 +/- 0.009 0.071 +/- 0.009 0.071 +/- 0.006 Pass AP-1 890, 1891 3/29/2005 Be-7 0.060 +/- 0.013 0.069 +/- 0.013 0.065 +/- 0.009 Pass AP-2025, 2026 3/29/2005 Be-7 0.063 +/- 0.012 0.071 +/- 0.011 0.067 +/- 0.008 Pass MI-1346, 1347 3/30/2005 K-40 1252.80 +/- 120.50 1334.10 +/- 106.60 1293.45 +/- 80.44 Pass AP-2048, 2049 3/30/2005 Be-7 0.075 +/- 0.018 0.071 i0.015 0.073 +/- 0.012 Pass AP-2081, 2082 3/30/2005 Be-7 0.073 +/- 0.016 0.061 +/- 0.018 0.067 +/- 0.012 Pass SWU-1521, 1522 3/31/2005 Gr. Beta 2.83 +/- 1.16 3.46 +/- 1.23 3.14 +/- 0.85 Pass WW-1738,1739 4/5/2005 Gr. Beta 11.44 +/- 1.17 11.14 +/- 1.62 11.29 +/- 1.00 Pass SW-1857,1858 4/13/2005 Gr. Beta 7.04 +/- 1.71 9.96 +/- 1.65 8.50 +/- 1.19 Pass LW-1911, 1912 4/14/2005 Gr. Beta 2.50 +/- 0.63 3.23 +/- 0.67 2.86 +/- 0.46 Pass F-1976,1977 4/18/2005 K-40 3.09 +/- 0.60 3.33 +/- 0.40 3.21 +/- 0.36 Pass Ml-2111, 2112 4/26/2005 K-40 1291.50 +/- 177.90 1323.70 +/- 108.80 1307.60 +/- 104.27 Pass SWU-2158, 2159 4/26/2005 Gr. Beta 3.69 +/- 0.74 3,54 +/- 0.66 3.62 +/- 0.50 Pass DW-2349, 2350 4/29/2005 1-131 0.58 +/- 0.27 0.49 +/- 0.27 0.53 +/- 0.19 Pass S0-2305, 2306 5/2/2005 Cs-1 37 0.11 +/- 0.05 0.11 +/- 0.04 0.11 +/- 0.03 Pass SO-2305, 2306 5/2/2005 Gr. Alpha 7.55 +/- 2.88 12.41 +/- 3.38 9.98 +/- 2.22 Pass SO-2305, 2306 5/2/2005 Gr. Beta 28.74 +/- 2.57 28.17 +/- 2.52 28.46 +/- 1.80 Pass SO-2305, 2306 5/2/2005 K-40 21.51 +/- 1.22 21.42 +/- 1.24 21.47 +/- 0.87 Pass SO-2305, 2306 5/2/2005 Sr-90 32.90 +/- 9.90 29.60 +/- 13.90 31.25 +/- 8.53 Pass MI-2260, 2261 5/3/2005 K-40 1028.10 +/- 99.36 1206.70 +/- 118.50 1117.40 +/- 77.32 Pass F-2630, 2631 5/5/2005 K-40 3.08 +/- 0.46 3.04 +/- 0.51 3.06 +/- 0.34 Pass VE-2502, 2503 5/10/2005 Gr. Alpha 0.06 +/- 0.03 0.07 +/- 0.04 0.07 +/- 0.03 Pass A5-1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-2502, 2503 5/10/2005 Gr. Beta 3.81 +/- 0.10 3.86 +/-0.10 3.83 +/- 0.07 Pass VE-2502, 2503 5/10/2005 K-40 3.79 +/- 0.40 4.30 +/- 0.59 4.04 +/- 0.36 Pass G-2546, 2547 5/11/2005 Be-7 0.81 +/- 0.39 1.25 +/- 0.38 1.03 +/- 0.27 Pass G-2546, 2547 5/11/2005 K-40 9.43 +/- 1.00 7.96 +/- 0.85 8.70 +/- 0.66 Pass SS-2787, 2788 5/18/2005 Cs-137 0.13 +/- 0.04 0.14 + 0.05 0.13 +/- 0.03 Pass SS-2787, 2788 5/18/2005 K-40 12.44 +/- 0.76 13.33 +/- 0.83 12.88 +/- 0.56 Pass SO-3056, 3057 5/19/2005 Cs-137 0.18 +/- 0.04 0.17 +/- 0.01 0.18 +/- 0.02 Pass SO-3056, 3057 b 5/19/2005 K-40 20.06 +/- 1.10 21.73 +/- 0.36 20.90 +/- 0.58 Fail SS-3175, 3176 5/23/2005 K-40 6.06 +/- 0.44 5.96 +/- 0.61 6.01 +/- 0.38 Pass SO-2865, 2866 5/25/2005 Cs-137 0.18 +/- 0.04 0.18 +/- 0.03 0.18 +/- 0.02 Pass SO-2865, 2866 5/25/2005 Gr. Beta 32.95 +/- 2.48 33.88 +/- 2.36 33.41 +/- 1.71 Pass S0-2865, 2866 5/25/2005 K-40 21.93 +/- 0.97 22.32 +/- 0.98 22.13 +/- 0.69 Pass DW-2935, 2936 5/27/2005 1-1 31 0.51 +/- 0.34 0.56 +/- 0.30 0.53 +/- 0.23 Pass SWU-3103, 3104 6/1/2005 Gr. Beta 3.29 +/- 0.49 3.75 +/- 0.66 3.52 +/- 0.41 Pass G-2958, 2959 6/1/2005 Be-7 1.06 +/- 0.40 1.21 +/- 0.28 1.14 +/- 0.24 Pass G-2958, 2959 b 6/1/2005 Gr. Beta 8.06 +/- 0.07 7.79 +/- 0.07 7.93 +/- 0.05 Fail G-2958, 2959 6/1/2005 K-40 5.93 +/- 0.73 6.05 +/- 0.28 5.99 +/- 0.39 Pass BS-4089, 4090 6/3/2005 Co-60 0.11 +/- 0.02 0.10 +/- 0.02 0.11 +/- 0.02 Pass BS-4089, 4090 6/3/2005 Cs-1 37 0.60 +/- 0.05 0.62 +/- 0.05 0.61 +/- 0.04 Pass DW-50527, 8 6/8/2005 Gr. Alpha 11.58 +/- 1.31 13.52 +/- 1.43 12.55 +/- 0.97 Pass VE-3278, 3279 6/13/2005 K-40 6.34 +/- 0.59 7.29 +/- 0.68 6.81 +/- 0.45 Pass MI-3299, 3300 6/15/2005 K-40 1215.40 +/- 110.20 1250.70 +/- 106.70 1233.05 i 76.70 Pass BS-3348, 3349 6/17/2005 Co-60 0.20 +/- 0.04 0.22 +/- 0.04 0.21 +/- 0.03 Pass BS-3348, 3349 6/17/2005 Cs-1 37 2.59 +/- 0.10 2.51 +/- 0.07 2.55 +/- 0.06 Pass BS-3348, 3349 6/17/2005 K-40 11.57 +/- 0.81 11.82 +/- 0.76 11.69 i 0.56 Pass DW-3486, 3487 6/28/2005 Gr. Beta 0.97 +/- 0.54 1.67 +/- 0.58 1.32 i 0.40 Pass SWT-3631, 3632 6/28/2005 Gr. Beta 2.12 +/- 0.53 1.62 +/- 0.56 1.87 +/- 0.39 Pass W-3507, 3508 6/29/2005 H-3 38717 +/- 382 38017 +/- 535 38367 +/- 329 Pass VE-3555, 3556 6/29/2005 Gr. Beta 7.53 +/- 0.18 7.56 +/- 0.18 7.55 +/- 0.13 Pass VE-3555, 3556 6/29/2005 K-40 5.70 +/- 0.52 5.64 +/- 0.53 5.67 +/- 0.37 Pass AP-3781, 3782 6/29/2005 Be-7 0.09 +/- 0.02 0.08 +/- 0.02 0.09 +/- 0.01 Pass LW-3610, 3611 6/30/2005 Gr. Beta 1.37 +/- 0.35 1.40 +/- 0.36 1.39 +/- 0.25 Pass SW-3760, 3761 6/30/2005 Gr. Beta 9.70 +/- 1.63 9,77 +/- 1.61 9.73 +/- 1.15 Pass E-3654, 3655 7/5/2005 Gr. Beta 1.76 +/- 0.07 1.69 +/- 0.07 1.72 +/- 0.05 Pass E-3654, 3655 7/5/2005 K-40 1.49 +/- 0.25 1.05 +/- 0.21 1.27 +/- 0.16 Pass MI-3676, 3677 7/5/2005 K-40 1383.90 +/- 116.20 1428.20 +/- 125.40 1406.05 +/- 85.48 Pass DW-3739, 3740 715/2005 1-131 1.93 +/- 0.24 2.18 +/- 0.23 2.05 +/- 0.17 Pass W-3808,3809 7/6/2005 H-3 4189.61 +/- 196.68 4438.33 +/- 201.39 4313.97 +/- 140.75 Pass DW-3938, 3939 7/812005 1-131 1.11 +/- 0.30 1.26 +/- 0.31 1.18 +/- 0.22 Pass VE-3896, 3897 7/12/2005 K-40 3.44 +/- 0.62 3.60 +/- 0.36 3.52 +/- 0.36 Pass MI-3963, 3964 7/13/2005 K-40 1438.70 +/- 102.80 1351.80 +/- 100.80 1395.25 +/- 71.99 Pass DW-4068, 4069 7/15/2005 1-131 0.64 +/- 0.27 0.91 +/- 0.28 0.78 +/- 0.20 Pass A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-4290, 4291 7/26/2005 Gr. Alpha 0.11 +/- 0.04 0.05 +/- 0.03 0.08 +/- 0.03 Pass VE-4290, 4291 7/26/2005 Gr. Beta 4.55 +/- 0.13 4.69 +/- 0.14 4.62 +/- 0.09 Pass SWU-4311, 4312 7/26/2005 Gr. Beta 2.62 +/- 0.64 1.67 +/- 0.37 2.15 +/- 0.37 Pass SWU-4311, 4312 7/26/2005 H-3 192.30 +/- 92.90 304,60 +/- 97.40 248.45 +/- 67.30 Pass G-4383, 4384 8/1/2005 Be-7 2.06 +/- 0.49 1.76 +/- 0.29 1.91 +/- 0.28 Pass G-4383, 4384 8/1/2005 Gr. Beta 8.76 +/- 0.22 8.40 +/- 0.20 8.58 +/- 0.15 Pass G-4383,4384 8/1/2005 K-40 6.74 +/- 0,64 6.88 +/- 0.92 6.81 +/- 0.56 Pass MI-4425,4426 8/1/2005 K-40 1358.10 +/- 169.20 1267.90 +/- 164.40 1313.00 +/- 117.96 Pass TD-4446, 4447 8/1/2005 H-3 563.00 +/- 252.00 529.00 +/- 251.00 546.00 +/- 177.84 Pass SL-4473, 4474 8/4/2005 Gr. Beta 5.44 +/- 0.48 4.57 +/- 0.42 5.00 +/- 0.32 Pass SL-4473, 4474 8/4/2005 K-40 2.91 +/- 0.83 2.74 +/- 0.54 2.82 +/- 0.49 Pass VE-4532, 4533 8/5/2005 Gr. Beta 31.20 +/- 1.20 31.70 +/- 1.20 31.45 +/- 0.85 Pass VE-4618, 4619 8/9/2005 Gr. Alpha 0.09 +/- 0.05 0.09 +/- 0.04 0.09 +/- 0.03 Pass VE-4618, 4619 8/9/2005 Gr. Beta 4.60 +/- 0.13 4.54 +/- 0.12 4.57 +/- 0.09 Pass VE-4618, 4619 8/9/2005 K-40 4.19 +/- 0.46 4.34 +/- 0.47 4.27 +/- 0.33 Pass F-4639, 4640 8/11/2005 Cs-137 0.05 +/- 0.02 0,05 +/- 0.02 0.05 +/- 0.02 Pass F-4639, 4640 8/11/2005 Gr. Beta 3.33 +/- 0.11 3.37 +/- 0.10 3.35 +/- 0.07 Pass F-4639, 4640 8/11/2005 K-40 2.62 +/- 0.57 2.58 +/- 0.59 2.60 +/- 0.41 Pass DW-4730, 4731 8/12/2005 1-131 0.82 i 0.23 0.83 +/- 0.25 0.83 +/- 0.17 Pass Ml-485S,4856 8/28/2005 K-40 1341.50 i 107.70 1340.00 +/- 114.70 1340.75 +/- 78.67 Pass MI-4855, 4856 8/28/2005 Sr-90 0.77 i 0.37 0.87 +/- 0.37 0.82 +/- 0.26 Pass MI-4945, 4946 8/31/2005 K-40 1388.90 i 158.90 1307.50 +/- 165.20 1348.20 +/- 114.61 Pass MI-4945, 4946 8/31/2005 Sr-90 0.67 +/- 0.34 0.82 +/- 0.36 0.75 +/- 0.25 Pass TD4921, 4922 9/1/2005 H-3 5737.00 +/- 266.00 5860.00 +/- 269.00 5798.50 +/- 189.15 Pass VE-4900, 4901 9/2/2005 Gr. Beta 3.40 +/- 0.06 3.51 +/- 0.06 3.45 +/- 0.04 Pass VE-4900, 4901 9/2/2005 K-40 2.15 +/-0.27 2.27 +/- 0.24 2.21 +/- 0.18 Pass DW-50769, 50770 9/2/2005 Gr. Alpha 6.17 +/- 1.42 6.08 +/- 1.46 6.13 +/- 1.02 Pass VE-4990, 4991 9/6/2005 K-40 18.81 +/- 1.12 19.52 +/- 0.86 19.17 +/- 0.71 Pass MI-5011, 5012 9/8/2005 K-40 1584.00 +/- 194.00 1707.60 +/- 173.00 1645.80 +/- 129.97 Pass VE-5119, 5120 9/12/2005 Gr. Alpha 0.10 +/- 0.06 0.09 +/- 0.05 0.10 +/- 0.04 Pass VE-5119, 5120 9/12/2005 Gr. Beta 6.05 +/- 0.18 5.92 +/- 0.17 5.98 +/- 0.12 Pass VE-5119, 5120 9/12/2005 K-40 4.61 +/- 0.46 4.74 +/- 0.69 4.68 +/- 0.41 Pass LW-5361, 5362 9/12/2005 Gr. Beta 1.09 +/- 0.33 1.18 +/- 0,34 1.13 +/- 0.24 Pass SW-5098, 5099 9/13/2005 1-131 0.44 +/- 0.22 0.31 +/- 0.20 0.38 +/- 0.15 Pass LW-5178, 5179 9/14/2005 Gr. Beta 2.92 +/- 0.56 2.95 +/- 0.59 2.93 +/- 0.41 Pass DW-5239, 5240 9/16/2005 1-131 0.45 +/- 0.27 0.55 +/- 0.29 0.50 +/- 0.20 Pass CF-5432, 5433 9/19/2005 Be-7 0.91 +/- 0.40 0.64 +/- 0.30 0.78 +/- 0.25 Pass CF-5432, 5433 9/19/2005 K-40 1.43 +/- 0.34 1.38 +/- 0.43 1.41 +/- 0.27 Pass MI-5292, 5293 9/21/2005 K40 1228.80 +/- 78.13 1297.00 +/- 81.03 1262.90 +/- 56.28 Pass BS-5340, 5341 9/23/2005 Be-7 1286.10 +/- 550.80 1222.90 +/- 394.40 1254.50 +/- 338.72 Pass BS-5340, 5341 9/23/2005 Cs-1 37 726.97 +/- 76.24 677.49 +/- 70.03 702.23 +/- 51.76 Pass A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance BS-5340, 5341 9/23/2005 K-40 12404 +/- 1154 13033 +/- 983 12719 +/- 758 Pass DW-5382, 5383 9/2312005 1-131 0.79 +/- 0.31 0.53 +/- 0.31 0.66 +/- 0.22 Pass MI-5405, 5406 9/27/2005 K-40 1324.80 +/- 112.20 1366.80 +/- 99.44 1345.80 +/- 74.96 Pass AP-5769, 5770 9/27/2005 Be-7 0.08 +/- 0.01 0.09 +/- 0.02 0.08 +/- 0.01 Pass AP-5983, 5984 9/27/2005 Be-7 0.08 +/- 0.01 0.08 +/- 0.01 0.08 +/- 0.01 Pass AP-5878, 5879 9/29/2005 Be-7 0.06 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 Pass G-5526, 5527 10/3/2005 Be-7 4.03 +/- 0.62 4.07 +/- 0.80 4.05 +/- 0.51 Pass G-5526, 5527 10/3/2005 Gr. Beta 8.10 +/- 0.30 8.80 +/- 0.40 8.41 +/- 0.24 Pass G-5526, 5527 10/3/2005 K-40 4.93 +/- 0.67 6.00 +/- 0.72 5.47 +/- 0.49 Pass VE-5721, 5722 10/10/2005 Gr. Alpha 0.07 + 0.05 0.08 +/- 0.06 0.08 +/- 0.04 Pass VE-5721, 5722 10/10/2005 Gr. Beta 5.09 +/- 0.15 5.00 +/- 0.16 5.05 +/-0.11 Pass VE-5721, 5722 10/10/2005 K-40 4.27 + 0.43 4.20 +/- 0.34 4.23 +/- 0.27 Pass CF-5695, 5696 10/11/2005 Be-7 2.70 + 0.37 2.80 +/- 0.34 2.75 +/- 0.25 Pass CF-5695, 5696 10/11/2005 K-40 11.79 +/- 0.86 13.11 +/- 0.68 12.45 +/- 0.55 Pass LW-6129, 6130 10/11/2005 Gr. Beta 1.34 +/- 0.25 1.85 +/- 0.29 1.59 +/- 0.19 Pass LW-6129, 6130 10/11/2005 H-3 304.35 +/- 95.31 369.23 +/- 97.88 336.79 +/- 68.31 Pass DW-50844, 5 10/11/2005 Gr. Beta 5.30 +/- 1.50 4.20 +/- 1.40 4.75 +/- 1.03 Pass LW-5748, 5749 10/12/2005 Gr. Beta 1.09 +/- 0.25 1.89 +/- 0.28 1.49 +/- 0.19 Fail AP-6485, 6486 10/20/2005 Be-7 0.10 +/- 0.03 0.09 +/- 0.03 0.09 +/- 0.02 Pass SWU-6156, 6157 10/25/2005 Gr. Beta 4.69 +/- 1.34 4.18 +/- 1.34 4.44 +/- 0.95 Pass VE-6186, 6187 10/26/2005 K-40 2.90 +/- 0.49 2.83 +/- 0.51 2.87 +/- 0.35 Pass LW-6203, 6204 10/27/2005 Gr. Beta 2.92 +/- 0.62 3.09 +/- 0.66 3.01 +/- 0.45 Pass SO-6270, 6271 10/28/2005 Cs-1 37 0.33 +/- 0.03 0.34 +/- 0.04 0.33 +/- 0.03 Pass SO-6270, 6271 10/2812005 Gr. Beta 26.85 +/- 2.78 22.25 +/- 2.41 24.55 +/- 1.84 Pass SO-6270, 6271 10/28/2005 K-40 13.67 +/- 0.74 14.02 +/- 0.76 13.85 +/- 0.53 Pass TD-6320, 6321 11/1/2005 H-3 444202 +/- 1770 446633 +/- 1775 445418 +/- 1253 Pass SO-6605, 6606 11/11/2005 Gr. Beta 18.22 +/- 2.23 18.47 +/- 2.22 18.35 +/- 1.57 Pass CF-6509, 6510 11/14/2005 K-40 0.85 +/- 0.14 0.99 +/- 0.22 0.92 +/- 0.13 Pass SW-6638, 6639 11/22/2005 1-131 0.95 +/- 0.35 0.67 +/- 0.31 0.81 +/- 0.23 Pass SO-6887, 6888 11/22/2005 Gr. Alpha 6.80 +/- 2.92 10.27 +/- 3.26 8.53 +/- 2.19 Pass SO-6887, 6888 11/22/2005 Gr. Beta 19.27 +/-2.16 18.43 +/- 2.21 18.85 +/- 1.54 Pass SO-6887, 6888 11/22/2005 K-40 14.29 1.11 13.78 +/- 0.78 14.03 +/- 0.68 Pass SWT-6721, 6722 11/29/2005 Gr. Beta 0.98 i 0.31 0.87 +/- 0.31 0.93 +/- 0.22 Pass VE-6775, 6776 11/29/2005 Gr. Beta 12.75 i 0.28 13.16 +/- 0.21 12.96 +/- 0.18 Pass LW-6743, 6744 11/30/2005 Gr. Beta 3.19 i 0.47 2,50 +/- 0.44 2.85 +/- 0.32 Pass DW-51023, 4 12/2/2005 Gr. Alpha 0.55 i 1.40 2.21 +/- 1.31 1.38 +/- 0.96 Pass SWT-7282, 7283 12/27/2005 Gr. Beta 1.62 +/- 0.37 1.85 +/- 0.38 1.74 +/- 0.27 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.

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

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

c Recount of W-5748, 2.38 +/- 0.85 pCi/L Averaged result; 2.14 +/- 0.45 pCi/L A5-4

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

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STW-1 045 01/01/05 Gr. Alpha 0.45 +/- 0.10 0.53 0.00 - 1.05 Pass STW-1 045 01/01/05 Gr. Beta 1.90 +/- 0.10 1.67 0.84 - 2.51 Pass STW-1046 01/01/05 Am-241 1.62 +/- 0.12 1.72 1.20 - 2.24 Pass STW-1 046 01/01/05 Co-57 239.40 +/- 1.20 227.00 158.90 - 295.10 Pass STW-1 046 01/01/05 Co-60 248.70 +/- 1.00 251.00 175.70 - 326.30 Pass STW-1 046 01/01/05 Cs-134 115.50 +/- 1.80 127.00 88.90 - 165.10 Pass STW-1 046 01/01/05 Cs-137 328.50 +/- 1.70 332.00 232.40 - 431.60 Pass STW-1 046 01/01/05 Fe-55 64.90 +/- 7.00 75.90 53.13 - 98.67 Pass STW-1046 01101/05 H-3 304.00 +/- 9.70 280.00 196.00 - 364.00 Pass STW-I 046 01/01/05 Mn-54 334.80 +/- 1.90 331.00 231.70 - 430.30 Pass STW-1046 01/01/05 Ni-63 7.10 +/- 1,60 9.00 0.00 - 20.00 Pass STW-1 046 01/01/05 Pu-238 0.01 +/- 0.02 0.02 0.00 - 1.00 Pass STW-1 046 01/01/05 Pu-239/40 2.50 +/- 0.14 2.40 1.68 - 3.12 Pass STW-1 046 01/01/05 Sr-90 0.70 +/- 0.80 0.00 0.00 - 5.00 Pass STW-1046 01/01/05 Tc-99 43.20 +/- 1.40 42.90 30.03 - 55.77 Pass STW-1 046 01/01105 U-23314 3.31 +/- 0.20 3.24 2.27 - 4.21 Pass STW-1 046 01/01/05 U-238 3.38 +/- 0.20 3.33 2.33 - 4.33 Pass STW-1 046 01/01/05 Zn-65 538.40 +/- 3.80 496.00 347.20 - 644.80 Pass STVE-1 047 01/01/05 Co-57 10.60 +/- 0.20 9.88 6.92 - 12.84 Pass STVE-1 047 01/01/05 Co-60 3.00 +/- 0.20 3.15 2.21 - 4.10 Pass STVE-1 047 01/01/05 Cs-1 34 4.80 +/- 0.40 5.00 3.50 - 6.50 Pass STVE-1 047 01/01/05 Cs-1 37 4.10 +/- 0.30 4.11 2.88 - 5.34 Pass STVE-1 047 01/01/05 Mn-54 5.10 +/- 0.30 5.18 3.63 - 6.73 Pass STVE-1 047 01/01/05 Zn-65 6.20 +/- 0.50 6.29 4.40 - 8.18 Pass STSO-1 048 01/01/05 Am-241 96.60 +/- 10.00 109.00 76.30 - 141.70 Pass STSO-1048 01/01/05 Co-57 264.00 +/- 2.00 242.00 169.40 - 314.60 Pass STSO-1048 01/01/05 Co-60 226.50 +/- 2.20 212.00 148.40 - 275.60 Pass STSO-1048 01/01/05 Cs-134 760.60 +/- 3.70 759.00 531.30 - 986.70 Pass STSO-1048 01/01/05 Cs-1 37 336.20 +/- 3.60 315.00 220.50 - 409.50 Pass STSO-1048 01/01/05 K-40 663.70 +/- 18.00 604.00 422.80 - 785.20 Pass STSO-1048 01/01/05 Mn-54 541.30 +/- 3.90 485.00 339.50 - 630.50 Pass STSO-1048 01/01/05 Ni-63 924.30 +/- 17.20 1220.00 854.00 - 1586.00 Pass STSO-1048 01/01/05 Pu-238 0.60 +/- 0.80 0.48 0.00 - 1.00 Pass STSO-1048 01/01/05 Pu-239/40 78.00 +/- 4.80 89.50 62.65 - 116.35 Pass STSO-1 048 01/01/05 Sr-90 514.60 +/- 18.70 640.00 448.00 - 832.00 Pass STSO-1 048 01/01/05 U-233/4 47.90 +/- 4.00 62.50 43.75 - 81.25 Pass STSO-1 048 01/01/05 U-238 226.30 +/- 8.60 249.00 174.30 - 323.70 Pass STSO-1 048 01/01/05 Zn-65 851.30 +/- 7.30 810.00 567.00 - 1053.00 Pass STAP-1050 01/01/05 Gr. Alpha 0.11 +/- 0.03 0.23 0.00 - 0.46 Pass STAP-1050 01/01/05 Gr. Beta 0.38 +/- 0.05 0.30 0.15 - 0.45 Pass A6-1

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

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STAP-1 049 01/01/05 Am-241 0.10 +/- 0.04 0.10 0.07 - 0.13 Pass STAP-1 049 01/01/05 Co-57 4.76 +/- 0.64 4.92 3.44 - 6.40 Pass STAP-1 049 01/01/05 Co-60 2.84 +/- 0.22 3.03 2.12 - 3.94 Pass STAP-1 049 01/01/05 Cs-1 34 3.54 +/- 0.37 3.51 2.46 - 4.56 Pass STAP-1 049 01/01/05 Cs-1 37 2.20 +/- 0.27 2.26 1.58 - 2.94 Pass STAP-1 049 01/01/05 Mn-54 3.15 +/- 0.21 3.33 2.33 - 4.33 Pass STAP-1 049 01/01/05 Pu-238 0.16 +/- 0.04 0.20 0.14 - 0.25 Pass STAP-1 049 01/01/05 Pu-239/40 0.17 +/-0.02 0.17 0.14 - 0.25 Pass STAP-1 049 e 01/01/05 Sr-90 2.24 +/- 0.34 1.35 0.95 - 1.76 Fail STAP-1 049 01/01/05 U-233/4 0.34 +/- 0.02 0.34 0.24 - 0.44 Pass STAP-1 049 01/01/05 U-238 0.35 +/- 0.02 0.35 0.25 - 0.46 Pass STAP-1 049 01/01/05 Zn-65 3.12 +/- 0.15 3.14 2.20 - 4.08 Pass STW-1061 07/01/05 Am-241 2.21 +/- 0.13 2.23 1.56 - 2.90 Pass STW-1061 07/01/05 Co-57 293.20 +/- 7.30 272.00 190.40 - 353.60 Pass STW-1 061 07/01/05 Co-60 275.70 +/- 1.30 261.00 182.70 - 339.30 Pass STW-1061 07/01/05 Cs-1 34 171.80 +/- 4.00 167.00 116.90 - 217.10 Pass STW-1 061 07/01/05 Cs-1 37 342.10 +/- 2.20 333.00 233.10 - 432.90 Pass STW-1 061 07/01/05 Fe-55 167.80 +/- 9.30 196.00 137.20 - 254.80 Pass STW-1 061 07/01/05 H-3 514.20 +/- 12.60 527.00 368.90 - 685.10 Pass STW-1 061 07/01/05 Mn-54 437.00 +/- 2.50 418.00 292.60 - 543.40 Pass STW-1 061 07/01/05 Ni-63 105.10 +/- 3.60 100.00 70.00 - 130.00 Pass STW-1 061 07/01/05 Pu-238 1.64 +/- 0.12 1.91 1.34 - 2.48 Pass STW-1061 07/01/05 Pu -239/40 2.32 +/- 0.13 2.75 1.93 - 3.58 Pass STW-1061 07/01/05 Sr-90 9.20 +/- 1.30 8.98 6.29 - 11.67 Pass STW-1 061 07/01/05 Tc-99 72.30 +/- 2.30 66.50 46.55 - 86.45 Pass STW-1 061 07/01/05 U-233/4 4.11 +/- 0.18 4.10 2.87 - 5.33 Pass STW-1 061 07/01/05 U-238 4.14 +/- 0.18 4.26 2.98 - 5.54 Pass STW-1 061 07/0 1/05 Zn-65 364.60 +/- 4.90 330.00 231.00 - 429.00 Pass STW-1 062 07/01/05 Gr. Alpha 0.57 +/- 0.05 0.79 0.21 - 1.38 Pass STW-1 062 07/01/05 Gr. Beta 1.36 +/- 0.05 1.35 0.85 - 1.92 Pass STSO-1 063 07/01/05 Am-241 48.40 +/- 3.90 81.10 56.77 - 105.43 Fail STSO-1 063 07/0 1/05 Co-57 608.30 +/- 2.80 524.00 366.80 - 681.20 Pass STSO-1 063 07/01/05 Co-60 322.70 +/- 2.40 287.00 200.90 - 373.10 Pass STSO-1 063 07/01/05 Cs-134 632.10 +/- 5.20 568.00 397.60 - 738.40 Pass STSO-1 063 07/01/05 Cs-1 37 512.40 +/- 4.20 439.00 307.30 - 570.70 Pass STSO-1 063 07/01/05 K-40 720.50 +/- 19.00 604.00 422.80 - 785.20 Pass STSO-1 063 07/01/05 Mn-54 516.80 +/- 5.10 439.00 307.30 - 570.70 Pass STSO-1 063 07/01/05 Ni-63 366.50 +/- 13.30 445.00 311.50 - 578.50 Pass STSO-1 063 07/01/05 Pu-238 68.80 +/- 15.00 60.80 42.56 - 79.04 Pass STSO-1 063 07/01/05 Pu-239/40 0.00 +/- 0.00 0.00 0.00 - 0.00 STSO-1 063 07/01/05 Sr-90 602.90 +/- 17.20 757.00 529.90 - 984.10 Pass STSO-1 063 07/0 1/05 U-233/4 61.50 +/- 1.00 52.50 36.75 - 68.25 Pass STSO-1 063 07/01/05 U-238 164.50 +/- 16.70 168.00 117.60 - 218.40 Pass STSO-1 063 07/01/05 Zn-65 874.70 +/- 8.40 823.00 576.10 - 1070.00 Pass A6-2

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

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STVE-1064 07/01/05 Am-241 0.18 +/- 0.03 0.23 0.16 - 0.30 Pass STVE-1064 07/01/05 Co-57 15.90 +/- 0,20 13.30 9.31 - 17.29 Pass STVE-1064 07/01/05 Co-60 4.80 +/- 0.10 4.43 3.10 -5.76 Pass STVE-1064 07/01/05 Cs-1 34 4.60 +/- 0.20 4.09 2.86 - 5.32 Pass STVE-1064 07/01/05 Cs-1 37 5.90 +/- 0.30 5.43 3.80 - 7.06 Pass STVE-1064 07/01/05 Mn-54 7.20 +/- 0.20 6.57 4.60 - 8.54 Pass STVE-1064 07/01/05 Pu-238 0.04 +/- 0.02 0.00 0.00 - 1.00 Pass STVE-1 064 07/01/05 Pu-239/40 0.13 +/- 0.02 0.16 0.11 -0.21 Pass STVE-1064 07/01/05 Sr-90 2.80 +/- 0.30 2.42 1.69 -3.15 Pass STVE-1064 07/01/05 U-233/4 0.28 +/- 0.03 0.33 0.23 - 0.43 Pass STVE-1 064 07/01/05 U-238 0.33 +/- 0.04 0.35 0.24 - 0.45 Pass STVE-1 064 07101/05 Zn-65 11.00 +/- 0.50 10.20 7.14 -13.26 Pass STAP-1 065 07/01/05 Gr, Alpha 0.30 +/- 0.04 0.48 0.00 - 0.80 Pass STAP-1 065 07/01/05 Gr. Beta 0.97 +/- 0.06 0.83 0.55 - 1.22 Pass STAP-1 066 07/01/05 Am-241 0.14 +/- 0.03 0.16 0.11 - 0.21 Pass STAP-1 066 07/01/05 Co-57 5.81 +/- 0.17 6.20 4.34 - 8.06 Pass STAP-1 066 07/01/05 Co-60 2.79 +/- 0.14 2.85 2.00 - 3.71 Pass STAP-1 066 07/01/05 Cs-1 34 3.67 +/- 0.12 3.85 2.70 - 5.01 Pass STAP-1 066 07/01/05 Cs-1 37 2.93 +/- 0.23 3.23 2.26 - 4.20 Pass STAP-1 066 07/01/05 Mn-54 4.11 +/- 0.26 4.37 3.06 - 5.68 Pass STAP-1 066 07/01/05 Pu-238 0.11 +/- 0.02 0.10 0.07 - 0.13 Pass STAP-1066 07/01/05 Pu-239/40 0.10 +/- 0.01 0.09 0.06 - 0.12 Pass STAP-1 066 07/01/05 Sr-90 2.25 +/- 0.29 2.25 1.58 - 2.93 Pass STAP-1 066 07/01/05 U-233/4 0.28 +/- 0.02 0.27 0.19 - 0.35 Pass STAP-1066 07/01/05 U-238 0.28 +/- 0.02 0.28 0.20 - 0.37 Pass STAP-1 066 07/01/05 Zn-65 4.11 +/- 0.26 4.33 3.06 - 5.68 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho bResults are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation) as requested by the Department of Energy.

c Laboratory codes as follows: STW (water), STAP (air filter), STSO (soil), STVE (vegetation).

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

@The strontium carbonate precipitates were redissolved and processed. The average of the three analyses was 1.34 1 although the recovery was only 30%. The result of a new analysis was 1.56 pCi/L.

Incorrect sample weight used in calculation. Result of recalculation: 97.0 +/- 7.8 Bq/kg.

A6-3

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 = 2a 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 4.66a uncertainty for a background sample.

3.0. Duplicate analyses 3.1 Individual results: For two analysis results; x1 +/-s1 and x2 s+/-

2 Reported result: x +/- s; where x = (1/2) (x + x2) and s = (1/2) +S 3.2. Individual results: < L ,. < L2 Reported result: < L, where L = lower of Li and L2 3.3. Individual results: x +/- s, < L Reported result: x +/- s if x 2 L; <L otherwise.

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

x nT YnEx X8 s= n-i 4.2 Values below the highest lower limit of detection are not included in the average.

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

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

4.5 In rounding off, the following rules are followed:

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

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

B-2

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

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

background in unrestricted areas Air (pCi/m3 ) Water (pCi/L)

-3 Gross alpha 1 x 10 Strontium-89 8,000 Gross beta 1 Strontium-90 500 b

Iodine-i131 2.8 x 101 Cesium-1 37 1,000 Barium-1 40 8,000 Iodine-1 31 1,000 Potassium-40 4,000 Gross alpha 2 Gross beta 10 6

Tritium 1 x 10 a

Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.

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

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

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ML061280617

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1.0 INTRODUCTION

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