L-MT-09-036, Annual Report for the NRC, Radiological Environmental Monitoring Program, January 1 - December 31, 2008

Annual Report for the NRC, Radiological Environmental Monitoring Program, January 1 - December 31, 2008

ML091330644
Person / Time
Site:	Monticello
Issue date:	12/31/2008
From:	Grob B Environmental
To:	Office of Nuclear Reactor Regulation, Xcel Energy
References
8010, FOIA/PA-2010-0209, L-MT-09-036
Download: ML091330644 (59)

Text

Environmental, Inc.

Midwest Laboratory S 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, 2008 Prepared under Contract by ENVIRONMENTAL, Inc.

Midwest Laboratory Project No. 8010 Approved: (~J)

La orat*v Aanager

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 Northern States Power Co. -Minnesota for XCEL Energy Corporation. This report was prepared by Environmental, Inc., Midwest Laboratory.

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TABLE OF CONTENTS No. Page P re fac e ............................................................................................................................... ii Lis t of T a b le s ...................................................................................................................... iv List of Figu res ..................................................................................................................... v

1.0 INTRODUCTION

................................................................................................................. 1 2 .0 S UMMAR Y .......................................................................................................................... 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 Sum mary of Preoperational Data .................................................................... 7 4.3 Program Findings ............................................................................................. 8 5.0 FIGURES AND TABLES ............................................................................................... 12

6.0 REFERENCES

.................................................................................................................. 24 APPENDICES A Interlaboratory Com parison 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 Sam pling Location Maps ............................................................................................. D-1

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

Appendix A A-1 Interlaboratory Comparison Program Results ......................................................... Al-1 A-2 Thermoluminescent dosimeters (TLDs) ........................................................................ A2-1 A-3 In-house Spiked Samples .............................................................................................. A3-1 A-4 In-house "Blank" Samples ............................................................................................. A4-1 A-5 In-house "Duplicate" Samples .................................................................................. A5-1 A-6 Department of Energy MAPEP comparison results ...................................................... A6-1 A-7 Environmental Resources Associates, Crosscheck Program Results (EML study replacement) .................................................................................. A7-1 Attachment A: Acceptance criteria for spiked samples ............................................... A2 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas ........................................................................ C-2 iv

LIST OF FIGURES No. Title PaqE 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 versus control location ......................................................................................... 18 Appendix D D-1 Sample collection and analysis program: TLD locations, In n er R in g ............................................................................................................................... D-2 D-2 Sample collection and analysis program: TLD locations, O u te r R in g ............................................................................................................................. D-3 D-3 Sample collection and analysis program: TLD locations, C o n tro ls ................................................................................................................................... D -4 D-4 Sample collection and analysis program: Radiation Environmental Monitoring Program, Milk sa m p ling loca tion s ........................................................................................................... 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, 2008.

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, 2009a) 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, owned by Xcel Energy Corporation and operated by Northern States Power Co.-Minnesota. 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 2008 are summarized and discussed.

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

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

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

Sources of environmental radiation include the following:

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

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

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

An additional interpretive technique involves analyses for specific radionuclides present in environmental samples collected from the Plant site. The Plant's monitoring program includes analyses for tritium and iodine-131. Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-1 37, cerium-1 44, 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 Desian 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 Proqram 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-1 31. 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.

Milk samples are collected monthly from two farms (one indicator and one control). Milk is collected biweekly during the growing season (May - October), because the animals may be on pasture. 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-1 31. 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.

Ground water is monitored by quarterly collections from three off-site locations (one control and two indicators) and one on-site Plant well. The samples are analyzed for tritium and gamma-emitting isotopes.

Twelve on-site monitoring wells were added to the program and sampled for tritium and gamma isotopic analyses. Four of the wells (M-29 to M-32) are deep water drinking wells and were only sampled until the shallow monitoring wells (M-36 to M-40) could be completed The four deep drinking wells were not sampled after the first quarter, 2008.

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 DescriDtion (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-1 31, 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 Progqram Execution The Program was executed as described in the preceding section with the following exceptions:

(1) Air Particulates / Air Iodine:

No air particulate / air iodine samples were available from location M-2 for the week ending May 28, 2008. The sampler pump failed, due to an open fuse.

No air particulate / air iodine samples were available from location M-5 for the week ending July 9, 2008. The sample was missed due to air sampler pump head leakage.

(2) Milk:

Milk samples were not available from M-28 (Hoglund Farm) after the April 9, 2008 collection. The herd was sold and the farm has gone out of the dairy business.

(3) Thermoluminescent Dosimeters:

The TLD for location M-01 B was missing in the field for the first quarter, 2008.

The TLD for location M-01S was missing in the field for the second quarter, 2008.

The TLD for location M-1 1A was missing in the field for the fourth quarter, 2008.

(4) Surface Water:

Surface water was not collected at location M-08 for the months of January, February and March, 2008, due to unsafe ice conditions. Three of five weekly collections in December, 2008 could not be collected due to unsafe ice.

(5) Bottom Organisms:

The October, 2008 samples could not be collected at both upstream and downstream locations, due to unsafe river conditions.

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 analyses are performed using high-purity germanium (HPGe) detectors.

Levels of iodine-131 in cabbage and natural vegetation and concentrations of airborne iodine-131 in charcoal samples were determined by gamma spectroscopy.

Tritium concentrations are determined by liquid scintillation.

Analytical Procedures used by Environmental, Inc. are on file and are available for inspection.

Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Dep't of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.

Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2003 ). The QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs. Results obtained in the crosscheck programs are presented in Appendix A.

3.5 Progqram Modifications M-28 (Hoglund Farm) discontinued dairy operations after April, 2008.

In September of 2008, triannual collections of pasture grass and vegetation were added to the program. Samples from locations M-41, M-42 and M-43 (C) were analyzed for iodine-131 and other gamma emitting isotopes, as substitute for dairy sampling.

3.6 Land Use Census In accordance with the MNGP Chemistry Manual, Procedure 1.05.41, "Annual Land Use Census and Critical Receptor Identification", 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 ft 2 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 1 and October 31. New locations shall be added to the radiation environmental monitoring program within 30 days and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted.

The 2008 land use census was conducted between September 15 and September 20, 2008.

There were two sectors (WNW, NW) in which the highest D/Q value increased by greater than 20%. No changes to the sampling procedures are required.

In summary, the highest D/Q locations for nearest resident, garden and nearest milk animal did not change from the 2007 census.

Details of the land use census are contained in the Land Use Census and Critical Receptor Report, Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.

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

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

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported accidents at nuclear facilities and no atmospheric nuclear tests conducted in the year 2008. 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-1 37, 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 (15.2 and 14.6 mRem/91 days, respectively). The mean for special interest locations was 14.3 mRem/91 days and the mean for the control locations was 15.4 mRem/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1993 through 2007 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).

Year Inner Ring Outer Ring Dose rate (mRem/91 days) 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 2006 16.5 15.6 2007 16.1 15.1 2008 15.2 14.6 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 almost identical at 3

indicator and control locations (0.028 and 0.029 pCi/m , respectively) and similar to levels observed from 1993 through 2007. The results are tabulated below.

Year Indicators Control 3

Concentration (pCi/m 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 2006 0.024 0.025 2007 0.027 0.028 2008 0.028 0.029 Average annual gross beta concentrations in airborne particulates.

Typically, the Ihighest average readings occur during the months of January and December, and the first and fourth quarters, as observed in 1993 through 2008.

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 3(Arnold and AI-Salih, 1955) was detected in all samples, with an average activity of 0.075 pCi/m for all locations. All other gamma-emitting isotopes were below their respective LLD limits.

Airborne Iodine 3

Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.03 pCi/m in all samples.

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Milk Iodine-1 31 activity measured below the detection limit of 0.5 pCi/L in all samples.

No gamma-emitting isotopes, excepting naturally-occurring potassium-40, were detected. This is consistent with the findings 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 2008 show no radiological effects of the plant operation.

Pasture Grass Three new locations for the sampling of grass and vegetation were established, as substitute for unavailable dairy farms. Pasture grass was collected twice in September, 2008. 1-131 concentrations measured below 0.045 pCi/g wet weight in all samples. With the exceptions of naturally-occurring beryllium-7 and potassium-40, no other gamma-emitting isotopes were detected.

River Water and Drinkina Water Tritium activity measured below the LLD of 500 pCi/L in all samples. Gross beta activity in Minneapolis drinking water averaged 2.1 pCi/L and was similar to average levels observed from 1993 through 2007. Gross beta averages are tabulated below.

Year Gross Beta (pCi/L) Year Gross Beta (pCi/L 1993 2.6 2001 2.5 1994 2.0 2002 2.9 1995 2.3 2003 3.0 1996 2.1 2004 2.7 1997 2.3 2005 2.8 1998 2.4 2006 2.1 1999 2.2 2007 2.8 2000 2.5 2008 2.1 Average annual concentrations; Gross beta in drinking water.

Comparisons with data reported by the USEPA for Minneapolis drinking water samples collected from 1980 through 2005 indicate that concentrations of these nuclides are remaining fairly constant. 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 At the four indicator and control locations, tritium measured below the LLD level of 500 pCi/L in all samples. Gamma isotopic results were below detection limits. The data for 2008 were consistent with previous years results and no plant operational effects were indicated.

In one sample, from location M-35, of one hundred monitoring well samples tested, tritium was detected at 520 pCi/L, above the concentration limit level of 500 pCi/L.

No gamma-emitting isotopes attributable to plant operation were detected.

Crops Cabbage was collected in September from two locations and analyzed for iodine-131. Levels of 1-131 measured below 0.018 pCi/g wet weight in both samples. With the exceptions of naturally-occurring beryllium-7 and potassium-40, no other gamma-emitting isotopes were detected.

No crops within five miles of the plant, were found using irrigation water from the Mississippi River. There was no indication of any plant effect.

Fish Fish samples were collected in May and October. Flesh was separated from the bones and analyzed by gamma spectroscopy. Naturally-occurring potassium-40 was found to be similar in upstream and downstream samples (3.21 and 3.05 pCi/g wet weight, respectively). All gamma-emitting isotopes were below their respective LLD levels. There was no indication of a plant effect.

Invertebrates Samples were collected in the third quarter of 2008, and analyzed by gamma spectroscopy. All gamma-emitting isotopes were below detection limits. There was no indication of a 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 the four downstream samples, averaging, 0.071 pCi/g dry weight, and 0.037 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 isotopes detected were naturally-occurring beryllium-7 and potassium-40. There was no indication of a plant effect.

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5.0 FIGURES AND TABLES 12

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

Collection Analysis Location Type and Type and Medium No. Codes (and Type)a Frequencyb Frequencyc Ambient radiation 40 M-01A - M-14A, M-01B - M-16B C/Q Ambient gamma (TLDs) M-01S - M-06S, M-01C - 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-28 G/Md 1-131, GS Pasture grass, Vegetation 3 M-41, M-42, M-43(C) 3x/year 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 G/Q H-3, GS On-site monitoring wells 12 M M-40 Edible cultivated crops -

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

Potatoese 1 M-21 G/A 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.

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

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

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 Pasture grass and vegetation collections added to supplement dairy sampling.

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 Code Typea Collection Site Sample Typeb Direction from Reactor M-1 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 @ 147°/SSE M-5 Air Station M-5 AP, Al 2.6 mi @ 134°/SE M-8 Upstream of Plant Intake SW, SS, BO, F < 1000' upstream M-9 Downstream of Plant Discharge SW, SS, BO, F < 1000' downstream M-10 Campbell Farm M, WW 10.6 mi @ 357°/N M-11 City of Monticello WW 3.3 mi @ 127°/SE M-12 Plant Well #1 WW 0.26 mi @ 252°/SW M-14 City of Minneapolis DW 37.0 mi @ 132°/SE M-15 Montissippi Park SS 1.27 mi @ 114°/ESE M-19 River Irrigated Corn FieldC M-21 River Irrigated Potato Fieldc M-24 Weinand Farm M 4.7 mi @ 180'/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 M-29 Warehouse #5 WW 276' @ 32°/NNE M-30 Receiving Warehouse WW 0.27 mi @ 156°/SSE M-31 Site Administration Building WW 424- @ 192°/SSW M-32 Shooting Range WW 0.33 mi @ 111°/ESE M-33 Monitoring Well #1 WW 593' @ 299/VWNW M-34 Monitoring Well #2 WW 749' @ 301 0 /WNW M-35 Monitoring Well #3 WW 770' @ 304°/NW M-36 Monitoring Well #4 WW 0.1 mi @ 335°/NNW M-37 Monitoring Well #5 WW 0.1 mi @ 253°/WSW M-38 Monitoring Well #6 WW 229' @ 228°/SW M-39 Monitoring Well #7 WW 0.2 mi @ 66 0 /ENE M-40 Monitoring Well #8 WW 0.3 mi @ 150°/SSE M-41 Training Center VE 0.8 mi @ 151 0 /SSE M-42 Biology Station Road VE 0.6 mi @ 134 0 /SE M-43 , Imholte Farm VE 12.3 mi @ 313°/NW General Area of the Site Boundary M-01A Sherburne Ave. So. TLD 0.75 mi @ 3531/N 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 @ 172°/S M-09A County Road 75 TLD 0.38 mi @ 209°/SSW M-10A County Road 75 TLD 0.38 mi @ 226°/SW M-11A County Road 75 TLD 0.4 mi @ 239°/WSW M-12A County Road 75 TLD 0.5 mi @ 262°1W 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.

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 mi @ 18°/NNE M-03B County Road 73 &81 TLD 4.3 mi @ 57°/NE M-04B County Road 73 (196th St.) TLD 4.2 mi @ 67°/ENE M-05B City of Big Lake TLD 4.3 mi @ 89'/E M-06B County Road 14 and 196th St. TLD 4.3 mi a 117°/ESE 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 @ 1780/S M-10B Reisewitz Farm, Acacia Ave. TLD 4.2 mi @ 204°/SSW M-11B Vanlith Farm, 97th Ave. TLD 4.0 mi @ 228°/SW M-12B Lake Maria State Park TLD 4.2 mi @ 254°/WSW M-13B Bridgewater Station TLD 4.1 mi @ 270'/W M-14B Anderson Residence, Cty Rd. 111 TLD 4.3 mi @ 289°/WNW M-1 5B Red Oak Wild Bird Farm TLD 4.3 mi @ 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 mi @ 242°/WSW M-02S Krone Residence TLD 0.5 mi @ 224°/SW M-03S Big Oaks Park TLD 1.53 mi @ 102°/ESE M-04S Pinewood School TLD 2.3 mi @ 131°/SE M-05S Rivercrest Christian Academy TLD 3.0 mi @ 118°/ESE M-06S Monte Public Works TLD 2.6 mi @ 134°/SE M-01C C Kirchenbauer Farm TLD 11.5 mi @ 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°/SE M-04C C Maple Lake Water Tower TLD 10.3 mi @ 2260/ SW a "C"denotes control location. All other locations are indicators.

b Sample Codes:

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

15

Table 5.3 MISSED COLLECTIONS AND ANALYSES All required samples were collected and analyzed as scheduled with the following exceptions:

Collection Reason for not Sample Analysis Location Date or conducting REMP Plans for Preventing Type Period as required Recurrence -

AP/AI Beta, M-02 5/28/2008 Sampler pump failure, Sampler pump was 1-131 open fuse. replaced.

AP/AI Beta, M-05 7/9/2008 Sampler pump failure, Sampler pump was 1-131 sampler head leakage. replaced.

MI Gamma, M-28 4/9/2008- Hoglund Farm no longer Pasture grass collections 1-131 12/31/2008 in the dairy business, were initiated at locations M-41, M-42, M-43 in Sept. 2008 TLD Ambient M-01B 1st. Qtr. Missing in the field None required.

Gamma 2008 TLD Ambient M-01S 2nd. Qtr. Missing in the field None required.

Gamma 2008 TLD Ambient M-11A 4th. Qtr. Missing in the field None required.

Gamma 2008 BO Gamma M-08, Oct., 2008 Collection missed due to None required.

M-09 unsafe river conditions.

SW Surface Water M-08 Jan, Feb, Mar, Missed due to unsafe ice. None required.

Gamma 2008 M-08 Dec, 2008 Three of five weekly samples None required.

missed due to unsafe ice.

16

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

Inner Ring Ring 20 Outer 19 18 17 16 __ __ __

(U

-Ou 14-__

E 13 12 _

11 10_

Cto O (0 f- Co 0D 0 ClJ M~ It W) (D r-- 00 C)0) 0) 0) C) 0) C) 0 0 0) 0 C0 0C0 0 C) C) 0 C) 0 C) C) 0 C) C C)0 C\

R, e'Ji cj C14 C'i C'.4 CNt C'j C'j 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) 0.035 0.033 0.031 0.029 0.027 0.025 0.023

). 0.021 0.019 0.017 0.015 MLO (0 -- 00 0 C> C14 CY) 'T LO (0 r- 00 M) 0) M) 0) 0) 0) 0) 0 0 0 0 0 0 0 0 0

0) 0) 0) 0) 0) 0) 0) 0 0 0 0 0 0 0 0 0 C1 (N C, (

04 N 04 N 04 (C1 (04 C(4 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, 2008

( 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)0 Mean (F)0 Routine (Units) Analyses' Rangec Locationd Rangec Rangec Resultse TLD (Inner Ring, Gamma 55 3.0 15.2 (55/55) M-11A 17.5(3/3) (See Control 0 General Area at (12.1-19.2) 0.4 mi @ 250°/WSW (15.5-19.2) below.)

Site Boundary) mRem/91 days)

TLD (Outer Ring, Gamma 59 3.0 14.6 (59/59) M-09B, Weinand Farm 16.2 (4/4) (See Control 0 4-5 mi. distant) (11.1-18.5) 4.7 mi @ 180'/S (13.1-17.8) below.)

mRem/91 days)

TLD (Special Gamma 23 3.0 14.3 (23/23) M-06S, Mont. Pub. Wks. 16.8 (4/4) (See Control 0 Interest Areas) (10.2-18.4) 2.7 mi @ 136 0/SE (15.1-18.4) below.)

mRem/91 days)

TLD (Control) Gamma 16 3.0 None M-03C, County Rd.19 & 15.4(4/4) 15.4 (16/16) 0 mRem/91 days) Jason, 11.6 mi. @ 130°/SE (13.9-18.7) (11.8-18.7)

Airborne GB 258 0.003 0.028 (206/206) M-1 (C) 0.029 (51 /52) 0.029 (51/52) 0 Particulates (0.004-0.087) 11.0 mi @ 307°/NW (0.009-0.065) (0.009-0.065)

(pCi/m 3)

GS 20 Be-7 0.015 0.075 (16/16) M-3 0.079 (4/4) 0.077(4/4) 0 (0.059-0.106) 0.6 mi @ 104°/ESE (0.070-0.086) (0.062-0.089)

Mn-54 0.0008 < LLD - < LLD 0 Co-58 0.0007 < LLD - < LLD 0 Co-60 0.0009 < LLD -. < LLD 0 Zn-65 0.0016 < LLD - < LLD 0 Zr-Nb-95 0.0010 < LLD - < LLD 0 Ru-103 0.0011 < LLD - < LLD 0 Ru-106 0.0066 < LLD - < LLD 0 Cs-134 0.0009 < LLD - < LLD 0 Cs-1 37 0.0009 < LLD - < LLD 0 Ba-La-140 0.0022 < LLD - - < LLD 0 Ce-141 0.0013 < LLD - - < LLD 0 Ce-144 0.0047 < LLD - - < LLD 0 Airborne Iodine 1-131 258 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, 2008 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine Analysesa Rangec Locationd Rangec Rangec Resultse (Units)

Milk (pCi/L) 1-131 24 0.5 < LLD < LLD 0 GS 24 K-40 200 1357 (4/4) M-10 (C), Campbell 1371 (20/20) 1371 (20/20) 0 (1279-1422) 10.6 mi @ 357°/N (1275-1537) (1275-1537)

Cs-134 5 < LLD < LLD 0 Cs-137 5 < LLD - < LLD 0 Ba-La-140 5 < LLD - - < LLD 0 River Water H-3 7 500 < LLD - - < LLD 0 (pCi/L)

GS 21 Mn-54 10 < LLD - - < LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 10 < LLD - -< LLD 0 Co-60 10 < LLD - - < LLD 0 Zn-65 30 < LLD - - < LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD - - < LLD 0 Cs-137 10 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 53 < 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, 2008

( County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Location" Rangec Rangec Resultse Drinking Water GB 12 1.0 2.1 (12/12) M-14, Minneapolis 2.1 (12/12) None 0 (pCi/L) (1.3-4.4) 37.0 mi. @ 132' /SE (1.3-4.4) 1-131 12 1.0 < LLD - None 0 H-3 4 500 < LLD - None 0 GS 12 Mn-54 10 < LLD - None 0 Fe-59 30 < LLD - None 0 Co-58 10 < LLD - None 0 Co-60 10 < LLD - None 0 Zn-65 30 < LLD - None 0 Zr-Nb-95 15 < LLD - None 0 Cs-134 10 < LLD - None 0 Cs-137 10 < LLD - None 0 Ba-La-140 15 < LLD - - None 0 Ce-144 50 < LLD - - None 0 Well Water H-3 116 500 520(1/112) Monitoring Well #3 520(1/12) < LLD 0 (pCi/L) 770' @304' /NW GS 116 Mn-54 10 < LLD < LLD 0 Fe-59 30 < LLD < LLD 0 Co-58 10 < LLD - < LLD 0 Co-60 10 < LLD - < LLD 0 Zn-65 30 < LLD - - < LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD - - < LLD 0 Cs-137 10 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 48 < LLD - - < LLD 0 Broadleaf GS 8 Vegetation 1-131 0.045 < LLD < LLD 0 (pCi/gwet) Cs-1 34 0.016 < LLD < LLD 0 Cs-1 37 0.019 < LLD < 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, 2008

( County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine Analysesa Rangec Locationd Rangec Rangec Resultse (Units)

Fish GS 4 (pCi/g wet) K-40 0.10 3.05 (2/2) M-08, Upstream 3.21 (2/2) 3.21 (2/2) 0 (2.52-3.57) < 1000' of discharge (2.97-3.44) (2.97-3.44)

Mn-54 0.024 < LLD -< LLD 0 Fe-59 0.040 < LLD < LLD 0 Co-58 0.020 < LLD < LLD 0 Co-60 0.020 < LLD < LLD 0 Zn-65 0.028 < LLD < LLD 0 Zr-Nb-95 0.023 < LLD < LLD 0 Cs-134 0.016 < LLD < LLD 0 Cs-137 0.017 < LLD < LLD 0 Ba-La-140 0.031 < LLD < LLD 0 Ce-144 0.10 < LLD - < LLD 0 Invertebrates GS 2 (pCi/g wet) Be-7 0.63 < LLD - < LLD 0 K-40 1.61 < LLD - < LLD 0 Mn-54 0.066 < LLD - - < LLD 0 Fe-59 0.15 < LLD - - < LLD 0 Co-58 0.040 < LLD - - < LLD 0 Co-60 0.069 < LLD - - < LLD 0 Zn-65 0.10 < LLD - - < LLD 0 Zr-Nb-95 0.06 < LLD - - < LLD 0 Ru-103 0.06 < LLD - - < LLD 0 Ru-106 0.65 < LLD - - < LLD 0 Cs-134 0.046 < LLD - - < LLD 0 Cs-137 0.056 < LLD - - < LLD 0 Ba-La-140 0.10 < LLD - - < LLD 0 Ce-144 0.38 < 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, 2008

( County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse Shoreline GS 6 Sediments Be-7 0.20 0.44 (3/4) M-09, Downstream 0.60 (1/2) 0.45 (1/2) 0 (pCi/g dry) (0.29-0.60) < 1000' of discharge K-40 0.10 10.87 (4/4) M-09, Downstream 11.06 (2/2) 10.00 (2/2) 0 (10.56-11.51) < 1000' of discharge (10.62-11.51) (9.68-10.32)

Mn-54 0.019 < LLD - - < LLD 0 Fe-59 0.052 < LLD - - < LLD 0 Co-58 0.019 < LLD - - < LLD 0 Co-60 0.017 < LLD - - < LLD 0 Zn-65 0.043 < LLD - - < LLD 0 Nb-95 0.031 < LLD - - < LLD 0 Zr-95 0.030 < LLD - - < LLD 0 Ru-103 0.023 < LLD - - < LLD 0 Ru-106 0.12 < LLD - - < LLD 0 Cs-134 0.016 < LLD - - < LLD 0 Cs-137 0.015 0.071 (4/4) M-09, Downstream 0.078 (2/2) 0.037 (1/2) 0 (0.058-0.081) < 1000' of discharge Ba-La-140 0.081 < LLD < LLD 0 Ce-144 0.099 < LLD < LLD 0 a GB = gross beta, GS = gamma scan.

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

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

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

e Non-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. AI-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 2009a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2008.

___ 2001b through 2009b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000 through 2008.

__ 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 through 1971. Monticello Nuclear Generating Plant, Environmental Radiation Monitoring Program, Annual Report, June 18, 1968 to December 31, 1968, 1969, 1970. Minneapolis, Minnesota.

Northern States Power Company.

Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S.

Nuclear Regulatory Commission, January 1, to December 31, 1977 through 1982 (prepared by Hazleton Environmental Sciences). Minneapolis, Minnesota.

1984 through 2000. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1983 through 1999 (prepared by Teledyne Brown Engineering Environmental Services, Midwest Laboratory). Northbrook, Illinois 24

6.0 REFERENCES

CITED (continued)

Teledyne Brown Engineering Environmental Services, Midwest Laboratory.

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

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

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

U.S. Environmental Protection Agency.

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

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

__ 2007. RadNet, formerly Environmental Radiation Ambient Monitoring System, Gross Beta in Air, Gross Beta in Drinking Water (MN) 1981- 2005.

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.

___ 2009. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2000 through 2008. (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 25

- (.. Environmental, Inc.

Midwest Laboratory S an Allegheny Technologies Co.

700 Landwehr Road

• Northbrook, IL60062-2310 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 performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January, 2008 through December, 2008

Appendix A Interlaboratory 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 lists REMP specific analytical results from 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.

Complete analytical data for duplicate analyses is available upon request.

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

Results in Table A-7 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 Environmental Measurement Laboratory Quality Assessment Program (EML).

Attachment A lists the laboratory precision at the 1 sigma level for various analyses. The acceptance criteria in Table A-3 is set at +/- 2 sigma.

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

Al

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

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

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

> 30 pCi/liter or kg 10% of known value Potassium-40 > 0.1 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 5 100 pCi/liter 5.0 pCi/liter

> 100 pCi/liter 5% of known value Tritium < 4,000 pCi/liter +/-1o =

0 0 933 169.85 x (known) °

> 4,000 pCi/liter 10% of known value Radium-226,-228  ? 0.1 pCi/liter 15% of known value Plutonium ->0.1 pCi/liter, gram, or sample 10% of known value Iodine-131, < 55 pCi/liter 6 pCi/liter Iodine-1 2 9 b > 55 pCi/liter 10% of known value Uranium-238, 5 35 pCi/liter 6 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 Other Analyses b 20% of known value 8 From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limit.

A2

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1 148 03/24/08 Sr-89 50.6 +/- 2.4 60.4 48.6 - 68.2 Pass STW-1 148 03/24/08 Sr-90 42.4 +/- 1.4 39.2 28.8 - 45.1 Pass STW-1149 03/24/08 Ba-133 56.9 +/- 5.4 58.3 48.3 - 64.3 Pass STW-1149 03/24/08 Co-60 73.9 +/- 1.6 76.6 68.9 - 86.7 Pass STW-1 149 03/24/08 Cs-134 50.2 +/- 1.9 46.6 37.4 -51.3 Pass STW-1 149 03/24/08 Cs-137 97.7 +/- 2.2 102.0 91.8-115.0 Pass STW-1 149 03/24/08 Zn-65 109.9 +/- 5.8 106.0 95.4 - 126.0 Pass STW-1150 03/24/08 Gr. Alpha 43.7 +/- 7.5 50.8 26.5 - 63.7 Pass STW-1150 03/24/08 Gr. Beta 36.4 +/- 1.8 51.4 35.0 - 58.4 Pass STW-1 151 03/24/08 1-131 29.3 +/- 1.4 28.7 23.9 - 33.6 Pass STW-1152 03/24/08 Ra-226 15.0 +/- 1.1 15.3 11.4-17.6 Pass STW-1152 03/24/08 Ra-228 18.4 +/- 1.8 17.0 11.4 -20.4 Pass STW-1152 03/24/08 Uranium 23.4 +/- 1.3 24.6 19.8 -27.6 Pass STW-1 153 03/24/08 H-3 12551.0 +/- 207.0 12000.0 10400.0 - 13200.0 Pass STW-1154 07/07/08 Sr-89 24.9 + 3.5 28.7 20.4 - 35.3 Pass STW-1 154 07/07/08 Sr-90 39.7 + 0.5 40.0 29.4 - 46.0 Pass STW-1 155 07/07/08 Ba-133 45.0 +/- 1.2 46.6 38.1 -51.8 Pass STW-1155 07/07/08 Co-60 24.9 + 3.0 25,7 22.3 - 31.0 Pass STW-1155 07/07/08 Cs-134 90.4 + 5.3 93,2 76.6 - 102.0 Pass STW-1 155 07/07/08 Cs-137 57.1 + 2.8 54.6 49.1 -62.9 Pass STW-1155 07/07/08 Zn-65 102.9 +/- 7.3 98.8 88.9-118.0 Pass STW-1156 07/07/08 Gr. Alpha ,24.8 + 1.6 30.7 15.7 -40.0 Pass STW-1156 07/07/08 Gr. Beta 23.9 +/- 0.9 25.8 16.1 -33.7 Pass STW-1 157 07/07/08 Ra-226 8.0 + 0.6 8.1 6.1 -9.5 Pass STW-1157 07/07/08 Ra-228 7.7 + 0.8 7.4 4.7 - 9.5 Pass STW-1157 07/07/08 Uranium 11.2 + 0.3 11.3 8.9 - 13.0 Pass STW-1 164 10/06/08 Sr-89 42.2 + 3.2 48.7 38.2 -56.1 Pass STW-1164 10/06/08 Sr-90 35.4 +/- 1.2 33.6 24.6 - 38.8 Pass STW-1 165 10/06/08 Ba-133 56.9 +/- 1.0 63.5 52.8 - 69.9 Pass STW-1 165 10/06/08 Co-60 47.6 +/- 1.3 49.1 44.2 - 56.6 Pass STW-1165 10/06/08 Cs-134 26.4 + 4.0 25.6 19.7 -28.4 Pass STW-1 165 10/06/08 Cs-137 24.3 +0.7 25.6 21.6 -31.2 Pass STW-1 165 10/06/08 Zn-65 72.0 +/- 2.9 68.6 61.2 -83.0 Pass STW-1166 10/06/08 Gr. Alpha 24.2 +/- 4.8 26.9 13.6 -35.5 Pass STW-1 166 10/06/08 Gr. Beta 32.6 +/- 1.0 38.0 25.1 - 45.5 Pass STW-1 167 10/06/08 1-131 29.0 +/- 0.3 28.1 23.4 - 33.0 Pass STW-1168 10/06/08 Ra-226 15.0 +/- 1.0 16.1 12.0 - 18.4 Pass STW-1 168 10/06/08 Ra-228 16.0 +/- 1.0 14.1 9.4 - 17.1 Pass STW-1168 10/06/08 Uranium 47.8 +/- 2.0 50.3 40.8 - 55.9 Pass STW-1 169 10/06/08 H-3 2357.0 +/- 66.0 2220.0 1830.0 -2460.0 Pass 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.

Al-1

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.

2008-1 6/16/2008 40 cm. 30.23 33.87 +/- 1.17 21.16 - 39.30 Pass 2008-1 6/16/2008 50 cm. 19.35 23.13 +/- 0.57 13.55 -25.16 Pass 2008-1 6/16/2008 60 cm. 13.44 16.25 +/- 1.10 9.41 - 17.47 Pass 2008-1 6/16/2008 70 cm. 9.87 10.39 +/- 0.52 6.91 - 12.83 Pass 2008-1 6/16/2008 80 cm. 7.56 7.44 +/- 0.51 5.29 - 9.83 Pass 2008-1 6/16/2008 90 cm. 5.97 5.80 +/- 1.04 4.18 -7.76 Pass 2008-1 6/16/2008 100 cm. 4.84 4.32 +/- 0.43 3.39 - 6.29 Pass 2008-1 6/16/2008 120 cm. 3.36 2.69 +/- 0.15 2.35 - 4.37 Pass 2008-1 6/16/2008 150 cm. 2.15 2.05 +/- 0.69 1.51 -2.80 Pass 2008-1 6/16/2008 180 cm. 1.49 1.23 +/- 0.80 1.04 -1.94 Pass Environmental, Inc.

2008-2 11/17/2008 30 cm. 63.05 73.10 +/- 1.84 44.14 -81.97 Pass 2008-2 11/17/2008 40 cm. 35.46 40.80 +/- 2.30 24.82 -46.10 Pass 2008-2 11/17/2008 50 cm. 22.7 24.10 +/- 0.58 15.89 - 29.51 Pass 2008-2 11/17/2008 60 cm. 15.76 15.98 +/- 0.55 11.03 -20.49 Pass 2008-2 11/17/2008 60 cm. 15.76 19.49 +/- 0.93 11.03 -20.49 Pass 2008-2 11/17/2008 70 cm. 11.58 11.97 +/- 0.54 8.11 -15.05 Pass 2008-2 11/17/2008 75 cm. 10.09 9.45 +/- 0.28 7.06 - 13.12 Pass 2008-2 11/17/2008 80 cm. 8.87 9.30 +/- 0.18 6.21 -11.53 Pass 2008-2 11/17/2008 90 cm. 7.01 7.19 +/- 0.43 4.91 - 9.11 Pass 2008-2 11/17/2008 90 cm. 7.01 6.84 +/- 0.42 4.91 -9.11 Pass 2008-2 11/17/2008 100 cm. 5.67 5.47 +/- 0.19 3.97 - 7.37 Pass 2008-2 11/17/2008 110 cm. 4.69 3.98 +/- 0.27 3.28 - 6.10 Pass 2008-2 11/17/2008 120 cm. 3.94 3.09 +/- 0.21 2.76 - 5.12 Pass 2008-2 11/17/2008 120 cm. 3.94 3.12 +/- 0.34 2.76 - 5.12 Pass 2008-2 11/17/2008 150 cm. 2.52 2.55 +/- 0.12 1.76 - 3.28 Pass 2008-2 11/17/2008 150 cm. 2.52 2.24 +/- 0.08 1.76 -3.28 Pass 2008-2 11/17/2008 180 cm. 1.75 1.36 +/- 0.08 1.23 -2.28 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 SPW-111 1/14/2008 Tc-99 32.20 +/- 0.85 32.34 20.34 - 44.34 Pass SPW-298 1/31/2008 Ni-63 213.55 +/- 3.07 212.58 148.81 -276.35 Pass W-11708 1/17/2008 Ra-226 11.34 +/- 0.43 12.69 8.88 - 16.50 Pass SPW-711 2/25/2008 U-238 33.56 +/- 1.74 41.70 29.19 - 54.21 Pass SPAP-881 3/11/2008 Cs-134 19.29 +/- 1.53 20.09 10.09 -30.09 Pass SPAP-881 3/11/2008 Cs-137 114.04 +/- 3.03 113.90 102.51 - 125.29 Pass SPAP-883 3/11/2008 Gr. Beta e 54.56 +/- 0.12 51.64 30.98 - 72.30 Pass SPMI-885 3/11/2008 Sr-90 45.93 +/- 1.60 45.13 36.10 -54.16 Pass SPW-887 3/11/2008 Sr-90 38.82 +/- 1.60 45.13 36.10 - 54.16 Pass SPW-889 3/11/2008 H-3 67325.00 +/- 725.00 67384.00 53907.20 - 80860.80 Pass W-31808 3/18/2008 Gr. Alpha 19.51 +/- 0.40 20.08 10.04 -30.12 Pass W-31808 3/18/2008 Gr. Beta 47.20 +/- 0.42 45.67 35.67 - 55.67 Pass SPMI-885 3/24/2008 Cs-134 40.93 +/- 1.55 39.69 29.69 - 49.69 Pass SPMI-885 3/24/2008 Cs-137 61.36 +/- 2.82 56.91 46.91 -66.91 Pass SPW-887 3/24/2008 Cs-134 40.68 +/- 1.44 39.69 29.69 - 49.69 Pass SPW-887 3/24/2008 Cs-137 58.52 +/- 2.93 56.91 46.91 - 66.91 Pass SPW-1282 4/2/2008 U-238 41.30 +/- 1.78 41.70 29.19 - 54.21 Pass W-40308 4/3/2008 Ra-226 15.17 +/- 0.50 12.69 8.88 - 16.50 Pass SPW-5580 4/7/2008 H-3 211.02 +/- 7.71 240.00 0.00 - 806.46 Pass SPW-1562 4/8/2008 Ra-228 28.93 +/- 2.09 30.51 21.36 -39.66 Pass SPW-1560 4/10/2008 Tc-99 29.74 +/- 0.84 32.34 20.34 - 44.34 Pass SPW-1621 4/16/2008 Fe-55 27205.80 +/- 982.90 28370.00 22696.00 - 34044.00 Pass W-51508 5/15/2008 Gr. Alpha 24.01 +/- 0.41 20.08 10.04 -30.12 Pass W-51508 5/15/2008 Gr. Beta 47.97 +/- 0.41 45.68 35.68 - 55.68 Pass SPAP-2673 6/2/2008 Cs-1 34 17.39 +/- 1.32 18.60 8.60 - 28.60 Pass SPAP-2673 6/2/2008 Cs-137 106.82 +/- 3.42 113.30 101.97 - 124.63 Pass SPAP-2674 6/2/2008 Gr. Beta e 53.57 +/- 0.13 51.40 30.84 -71.96 Pass SPF-2745 6/2/2008 Cs-134 0.34 +/- 0.02 0.37 0.22 - 0.52 Pass SPF-2745 6/2/2008 Cs-137 2.06 +/- 0.04 2.27 1.36 -3.18 Pass SPMI-2677 6/3/2008 Cs-1 37 53.99 +/- 6.15 56.66 46.66 - 66.66 Pass SPMI-2677A 6/3/2008 1-131 26.64 +/- 0.59 28.58 16.58 - 40.58 Pass SPW-2677 6/3/2008 Cs-1 34 40.30 +/- 3.35 37.21 27.21 -47.21 Pass SPW-2677 6/3/2008 1-131(G) 25.92 +/- 4.48 28.58 18.58 -38.58 Pass SPMI-2679 6/3/2008 Cs-134 35.02 +/- 2.93 37.21 27.21 - 47.21 Pass SPMI-2679 6/3/2008 Cs-1 37 58.49 +/- 6.05 56.66 46.66 - 66.66 Pass SPMI-2679 6/3/2008 1-131(G) 25.30 +/- 4.97 28.58 18.58 - 38.58 Pass SPMI-2679A 6/3/2008 1-131 30.37 +/- 0.50 28.58 16.58 -40.58 Pass SPVE-2681 6/3/2008 1-131(G) 1.11 +/- 0.06 0.95 0.57 -1.33 Pass SPW-2683 6/2/2008 Ni-63 2151.70 +/- 10.22 2119.30 1483.51 - 2755.09 Pass SPW-2685 6/2/2008 H-3 64927.20 +/- 704.80 66540.80 53232.64 - 79848.96 Pass SPW-2689 6/2/2008 C-14 4405.40 +/- 15.21 4742.00 2845.20 - 6638.80 Pass A3-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 Activity Limitsc Acceptance W-81408 8/14/2008 Ra-226 12.98 +/- 0.35 12.69 8.88 - 16.50 Pass SPW-1562 8/1412008 Ra-228 29.09 +/- 2.46 30.51 21.36 - 39.66 Pass SPW-81808 8/18/2008 U-238 42.59 +/- 1.96 41.70 29.19 - 54.21 Pass W-81808 8/18/2008 Gr. Alpha 21.36 +/- 0.42 20.08 10.04 - 30.12 Pass W-81808 8/18/2008 Gr. Beta 49.33 +/- 1.01 45.68 35.68 - 55.68 Pass W-112008 11/20/2008 Gr. Alpha 20.13 +/- 0.40 20.08 10.04 - 30.12 Pass W-1 12008 11/20/2008 Gr. Beta 48.28 +/- 0.42 45.60 35.60 - 55.60 Pass SPAP-6839 12/5/2008 Cs-134 15.39 +/- 2.72 15.68 5.68 - 25.68 Pass SPAP-6839 12/5/2008 Cs-137 111.45 +/- 9.85 112.00 100.80 - 123.20 Pass SPAP-6841 12/5/2008 Gr. Beta e 49.26 +/- 0.12 50.72 30.43 - 71.01 Pass SPW-6843 12/5/2008 C-14 19377.50 +/- 55.27 23708.00 14224.80 -33191.20 Pass SPW-6845 12/5/2008 Fe-55 7068.30 +/- 692.30 6028.00 4822.40 - 7233.60 Pass SPW-6847 12/5/2008 Tc-99 37.71 +/- 1.33 32.34 20.34 - 44.34 Pass SPW-6849 12/5/2008 Ni-63 232.56 +/- 3.26 211.34 147.94 - 274.74 Pass SPW-6851 12/5/2008 H-3 63664.00 +/- 8745.00 64674.00 51739.20 - 77608.80 Pass SPF-6859 12/5/2008 Cs-134 0.63 +/- 0.02 0.63 0.38 - 0.88 Pass SPF-6859 12/5/2008 Cs-137 2.35 +/- 0.01 2.24 1.34-3.14 Pass SPW-7059 12/19/2008 Sr-90 49.19 +/- 2.62 44.33 35.46 - 53.20 Pass SPMI-7061 12/19/2008 Sr-90 39.39 +/- 2.19 44.33 35.46 - 53.20 Pass 3

a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/m ), and solid samples (pCi/g).

b Laboratory 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 established from the precision values listed in Attachment A of this report, adjusted to +/- 2a.

e Control limits based on the laboratory limit, Attachment A ("Other Analyses").

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

A3-2

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

SPW-17 Water 1/3/2008 U-238 0.09 0.01 +/- 0.07 1 SPW-1 12 Water 1/14/2008 Tc-99 4.70 -0.06 +/- 2.85 10 W-11408 Water 1/14/2008 Ra-226 0.05 0.05 +/- 0.04 1 SPAP-880 Air Filter 3/11/2008 Cs-134 0.91 100 SPAP-880 Air Filter 3/11/2008 Cs-137 1.13 100 SPW-888 Water 3/11/2008 H-3 159.99 -78.90 +/- 80.40 200 W-31808 Water 3/18/2008 Gr. Alpha 0.42 -0.05 +/- 0.29 1 W-31808 Water 3/18/2008 Gr. Beta 0.72 0.09 +/- 0.51 3.2 SPMI-884 Milk 3/24/2008 Cs-134 2.79 10 SPMI-884 Milk 3/24/2008 Cs-137 3.36 10 W-40308 Water 4/3/2008 Ra-226 0.04 0.05 +/- 0.03 1 SPW-1563 Water 4/8/2008 Ra-228 0.57 0.31 +/- 0.30 2 SPW-1561 Water 4/10/2008 Tc-99 4.77 -3.42 +/- 2.85 10 SPW-1621 Water 4/16/2008 Fe-55 668.50 -170.70 +/- 397.20 1000 SPW-2451 Water 5/22/2008 U-238 0.21 0.35 +/- 0.24 1 SPW-2676 Water 6/2/2008 Cs-134 2.03 10 SPW-2676 Water 6/2/2008 Cs-134 3.60 10 SPW-2676 Water 6/2/2008 Cs-137 2.38 10 SPW-2677 Water 6/2/2008 Cs-134 2.78 10 SPW-2677 Water 6/2/2008 1-131(G) 3.49 20 SPW-2677 Water 6/2/2008 1-131(G) 5.25 20 SPF-2744 Fish 6/2/2008 Cs-134 5.48 100 SPF-2744 Fish 6/2/2008 Cs-137 4.83 100 SPW-2676 Water 6/3/2008 1-131 0.18 0.01 +/- 0.11 0.5 SPMI-2678 Milk 6/3/2008 1-131 0.22 0.12 +/- 0.15 0.5 SPVE-2680 Vegetation 6/3/2008 1-131(G) 0.01 20 SPW-3581 Water 7/14/2008 U-238 0.10 0.13 +/-+0.12 1 W-80708 Water 8/7/2008 Gr. Alpha 0.63 -0.02 +/- 0.44 1 W-80708 Water 8/7/2008 Gr. Beta 1.43 -0.47 +/- 0.99 3.2 W-81408 Water 8/14/2008 Ra-226 0.06 0.14 +/- 0.04 1 SPW-1563 Water 8/14/2008 Ra-228 0.79 0.89 +/- 0.47 2 SPW-81808 Water 8/1812008 U-238 0.18 0.04 +/- 0.13 1 A4-1

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

W-1 12008 Water 11/20/2008 Gr. Alpha 0.40 0.02 +/- 0.28 1 W-1 12008 Water 11/20/2008 Gr. Beta 0.75 -0.16 +/- 0.52 3.2 SPAP-6838 Air Filter 12/5/2008 Cs-134 1.01 100 SPAP-6838 Air Filter 12/5/2008 Cs-137 0.95 100 SPAP-6840 Air Filter 12/5/2008 Gr. Beta 0.96 2.69 +/- 0.64 3.2 SPW-6842 Water 12/5/2008 C-14 7.79 -3.04 +/- 4.05 200 SPW-6844 Water 12/5/2008 Fe-55 715.10 21.70 +/- 435.10 1000 SPW-6846 Water 12/5/2008 Tc-99 1.36 -0.47 +/- 0.82 10 SPW-6848 Water 12/5/2008 Ni-63 1.94 3.08 +/- 1.23 20 SPF-6858 Fish 12/5/2008 Cs-134 1.53 100 SPF-6858 Fish 12/5/2008 Cs-137 3.92 100 SPW-7058 Water 12/19/2008 Cs-134 2.62 10 SPW-7058 Water 12/19/2008 Cs-137 2.39 10 SPW-7058 Water 12/19/2008 Sr-90 0.65 -0.28 +/- 0.26 1 SPMI-7060 Milk 12/19/2008 Cs-134 2.18 10 SPMI-7060 Milk 12/19/2008 Cs-137 3.87 10 SPMI-7060 Milk 12/19/2008 1-131(G) 2.80 20 SPMI-7060 d Milk 12/19/2008 Sr-90 0.53 0.76 +/- 0.34 1 a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

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

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

d Low levels of St-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)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance AP-8809, 8810 1/2/2008 Be-7 0.06 +/- 0.02 0.06 +/- 0.01 0.06 +/- 0.01 Pass CF-42, 43 1/2/2008 Gr. Beta 8.88 +/- 0.19 8.99 +/- 0.19 8.94 +/- 0.13 Pass CF-42, 43 1/2/2008 K-40 5.08 +/- 0.29 5.19 +/- 0.30 5.14 +/- 0.21 Pass DW-80020, 80021 1/7/2008 Gr. Alpha 2.28 +/- 0.84 1.98 +/- 0.86 2.13 +/- 0.60 Pass U-169, 170 1/10/2008 Beta-K40 7.50 +/- 5.50 11.70 +/- 5.10 9.60 +/- 3.75 Pass SO-8836, 8837 1/14/2008 Cs-137 0.80 +/- 0.05 0.75 +/- 0.05 0.77 +/- 0.03 Pass SO-8836, 8837 1/14/2008 Gr. Alpha 13.30 +/- 4.31 15.58 +/- 4.10 14.44 +/- 2.98 Pass SO-8836, 8837 1/14/2008 Gr. Alpha 33.68 +/- 3.73 29.21 +/- 3.10 31.45 +/- 2.43 Pass SO-8836, 8837 1/14/2008 K-40 12.31 +/- 0.74 12.96 +/- 0.73 12.64 +/- 0.52 Pass DW-80045, 80046 1/15/2008 Gr. Alpha 2.94 +/- 1.13 3.41 +/- 1.04 3.17 +/- 0.77 Pass DW-80045, 80046 1/15/2008 Gr. Beta 1.86 +/- 0.66 1.36 +/- 0.63 1.61 +/- 0.45 Pass MI-138, 139 1/15/2008 K-40 1262.40 +/- 81.70 1396.20 +/- 154.20 1329.30 +/- 87.25 Pass LW-190,191 1/16/2008 Gr. Beta 2.85 +/- 1.07 1.64 +/- 1.02 2.24 +/- 0.74 Pass DW-8008, 8009 1/16/2008 Ra-226 2.77 +/- 0.20 3.11 +/- 0.22 2.94 +/- 0.15 Pass DW-8008, 8009 1/16/2008 Ra-228 3.95 +/- 0.74 3.96 +/- 0.77 3.96 +/- 0.53 Pass DW-80057, 80058 1/21/2008 Gr. Alpha 6.77 +/- 0.66 7.91 +/- 1.73 7.34 +/- 0.92 Pass DW-80057, 80058 1/21/2008 Gr. Beta 13.83 +/- 0.97 14.78 +/- 1.01 14.31 +/- 0.70 Pass SWU-479,480 1/29/2008 Gr. Beta 4.49 +/- 1.13 3.13 +/- 1.14 3.81 +/- 0.80 Pass W-920, 921 2/4/2008 Gr. Beta 4.20 +/- 1.30 3.30 +/- 1.30 3.75 +/- 0.92 Pass SW-540, 541 2/12/2008 Gr. Alpha 2.75 +/- 1.16 4.01 +/- 1.18 3.38 +/- 0.83 Pass SW-540, 541 2/12/2008 Gr. Beta 6.46 +/- 1.11 6.71 +/- 1.03 6.59 +/- 0.76 Pass DW-80155, 80156 2/12/2008 Ra-226 2.55 +/- 0.22 2.01 +/- 0.16 2.28 +/- 0.14 Fail DW-80155, 80156 2/12/2008 Ra-228 1.86 +/- 0.70 1.53 +/- 0.67 1.70 +/- 0.48 Pass DW-80165, 80166 2/20/2008 Gr. Alpha 1.51 +/- 0.90 0.80 +/- 1.05 1.16 +/- 0.69 Pass DW-80166, 80167 2/20/2008 Ra-226 0.40 +/- 0.09 0.46 +/- 0.09 0.43 +/- 0.06 Pass DW-80166, 80167 2/20/2008 Ra-228 1.44 +/- 0.52 1.42 +/- 0.57 1.43 +/- 0.39 Pass DW-80166, 80167 2/20/2008 Uranium 0.69 +/- 0.25 0.69 +/- 0.26 0.69 +/- 0.18 Pass W-1413,1414 3/3/2008 Gr. Beta 7.50 +/- 3.00 3.70 +/- 2.60 5.60 +/- 1.98 Pass DW-80189, 80190 3/11/2008 Ra-226 4.41 +/- 0.30 4.09 +/- 0.25 4.25 +/- 0.20 Pass DW-80189, 80190 3/11/2008 Ra-228 1.99 +/- 0.65 2.17 +/- 0.66 2.08 +/- 0.46 Pass MI-1006, 1007 3/12/2008 K-40 1451.90 +/- 112.80 1409.50 +/- 111.40 1430.70 +/- 79.27 Pass MI-1006, 1007 3/12/2008 Sr-90 0.48 +/- 0.31 0.97 +/- 0.38 0.72 +/- 0.24 Pass DW-80205, 80206 3/14/2008 Gr. Alpha 3.64 +/- 0.80 3.39 +/- 0.82 3.52 +/- 0.57 Pass DW-80202, 80203 3/14/2008 Ra-226 3.16 +/- 0.21 3.00 +/- 0.19 3.08 +/- 0.14 Pass DW-80202, 80203 3/14/2008 Ra-228 2.40 +/- 1.00 2.07 +/- 0.69 2.24 +/- 0.61 Pass DW-80208, 80209 3/14/2008 U-233/4 1.32 +/- 0.25 1.29 +/- 0.36 1.31 +/- 0.22 Pass SG-1080, 1081 3/18/2008 Pb-214 3.99 +/- 0.30 4.15 +/- 0.29 4.07 +/- 0.21 Pass SO-1195, 1196 3/18/2008 U-233/4 0.14 +/- 0.02 0.14 +/- 0.02 0.14 +/- 0.01 Pass SO-1195, 1196 3/18/2008 U-238 0.13 +/- 0.02 0.13 +/- 0.02 0.13 +/- 0.01 Pass WW-1242,1243 3/24/2008 Gr. Beta 10.36 +/- 1.63 9.06 +/- 1.55 9.71 +/- 1.13 Pass AP-1519, 1520 4/2/2008 Be-7 0.07 +/- 0.01 0.08 +/- 0.01 0.08 +/- 0.01 Pass W-1565,1566 4/2/2008 Gr. Alpha 0.82 +/- 0.64 1.58 +/- 0.72 1.20 +/- 0.48 Pass W-1565,1566 4/2/2008 Gr. Beta 3.73 +/- 0.86 5.51 +/- 1.09 4.62 +/- 0.69 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 DW-80255, 80256 4/8/2008 Ra-226 0.19 +/- 0.08 0.28 +/- 0.11 0.24 +/- 0.07 Pass DW-80255, 80256 4/8/2008 Ra-228 1.79 +/- 0.57 1.32 +/- 0.55 1.56 +/- 0.40 Pass DW-80259, 80260 4/8/2008 Gr. Alpha 3.39 +/- 0.82 3.62 +/- 0.82 3.51 +/- 0.58 Pass DW-80301, 80302 4/11/2008 Ra-226 0.47 +/- 0.09 0.47 +/- 0.09 0.47 +/- 0.06 Pass DW-80301, 80302 4/11/2008 Ra-228 1.02 +/- 0.42 0.82 +/- 0.45 0.92 +/- 0.31 Pass SO-1913,1914 4/15/2008 K-40 12.79 +/- 0.73 13.88 +/- 0.85 13.34 +/- 0.56 Pass DW-80313, 80314 4/16/2008 Ra-226 3.39 +/- 0.22 3.28 +/- 0.21 3.34 +/- 0.15 Pass DW-80313, 80314 4/16/2008 Ra-228 4.27 +/- 0.72 5.14 +/- 0.77 4.71 +/- 0.53 Pass SWU-2087, 2088 4/29/2008 Gr. Beta 2.20 +/- 0.60 3.50 +/- 0.90 2.85 +/- 0.54 Pass LW-2297, 2298 4/30/2008 Gr. Beta 1.41 +/- 0.43 1.02 +/- 0.40 1.22 +/- 0.30 Pass LW-2321, 2322 4/30/2008 Gr. Beta 1.33 +/- 0.54 1.23 +/- 0.54 1.28 +/- 0.38 Pass BS-2063,2064 5/1/2008 Gr. Beta 13.71 +/- 2.06 17.60 +/- 2.49 15.66 +/- 1.62 Pass SG-2229, 2230 5/5/2008 Ac-228 26.25 +/- 2.70 24.90 +/- 2.55 25.58 +/- 1.86 Pass W-2792,2793 5/5/2008 Gr. Beta 7.20 +/- 2.30 7.00 +/- 2.50 7.10 +/- 1.70 Pass SG-2229, 2230 5/5/2008 Pb-214 23.28 +/- 0.30 23.54 +/- 0.33 23.41 +/- 0.22 Pass F-2850, 2851 5/7/2008 Cs-137 3.37 +/- 0.21 3.16 +/- 0.19 3.27 +/- 0.14 Pass DW-80376, 80377 5/9/2008 Ra-226 0.94 +/- 0.13 1.07 +/- 0.13 1.01 +/- 0.09 Pass DW-80376, 80377 5/9/2008 Ra-228 2.05 +/- 0.57 1.40 +/- 0.51 1.73 +/- 0.38 Pass MI-2363, 2364 5/14/2008 K-40 1335.40 +/- 111.20 1510.70 +/- 124.30 1423.05 +/- 83.39 Pass SG-2752, 2753 5/14/2008 Be-7 264.60 +/- 83.90 222.80 +/- 93.10 243.70 +/- 62.66 Pass SG-2752, 2753 5/14/2008 Cs-1 37 64.80 +/- 6.00 68.90 +/- 5.80 66.85 +/- 4.17 Pass SG-2752, 2753 5/14/2008 Gr. Alpha 19.35 +/- 3.48 22.88 +/- 4.04 21.12 +/- 2.67 Pass SG-2752, 2753 5/14/2008 Gr. Beta 30.53 +/- 2.40 33.31 +/- 2.71 31.92 +/- 1.81 Pass SG-2752, 2753 5/14/2008 K-40 9121.90 +/- 191.80 9183.70 +/- 194.20 9152.80 +/- 136.47 Pass DW-80389, 80390 5/14/2008 Ra-226 2.99 +/- 0.36 2.58 +/- 0.31 2.79 +/- 0.24 Pass DW-80389, 80390 5/14/2008 Ra-228 2.87 +/- 0.68 1.73 +/- 0.57 2.30 +/- 0.44 Pass DW-80392, 80393 5/14/2008 Gr. Alpha 19.94 +/- 1.30 17.89 +/- 1.26 18.92 +/- 0.91 Pass DW-80394, 80395 5/14/2008 U-233/4 2.03 +/- 0.27 2.54 +/- 0.39 2.29 +/- 0.24 Pass BS-2490, 2491 5/16/2008 Cs-137 6.81 +/- 1.20 6.76 +/- 1.23 6.78 +/- 0.86 Pass WW-2462,2463 5/19/2008 H-3 158.61 +/- 80.90 205.63 +/- 83.06 182.12 +/- 57.97 Pass W-2826,2827 5/27/2008 Gr. Alpha 3.47 +/- 2.23 4.22 +/- 2.20 3.84 +/- 1.57 Pass W-2826,2827 5/27/2008 Gr. Beta 10.67 +/- 1.92 9.43 +/- 1.76 10.05 +/- 1.30 Pass SG-3378, 3379 6/2/2008 Gr. Alpha 6.51 +/- 1.15 7.83 +/- 1.32 7.17 +/- 0.88 Pass SG-3378, 3379 6/2/2008 Gr. Beta 16.23 +/- 0.95 15.76 +/- 1.06 16.00 +/- 0.71 Pass SG-3393, 3394 6/4/2008 Be-7 0.82 +/- 0.23 0.66 +/- 0.33 0.74 +/- 0.20 Pass SG-3393, 3394 6/4/2008 Cs-137 0.07 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 Pass SG-3393, 3394 6/4/2008 Gr. Alpha 18.96 +/- 3.49 16.96 +/- 3.34 17.96 +/- 2.42 Pass SG-3393, 3394 6/4/2008 Gr. Beta 30.01 +/- 2.49 30.17 +/- 2.56 30.09 +/- 1.79 Pass SG-3393,3394 6/4/2008 K-40 9.78 +/- 0.30 10.00 +/- 0.28 9.89 +/- 0.21 Pass LW-2939, 2940 6/1212008 Gr. Beta 1.46 +/- 0.59 1.74 +/- 0.59 1.60 +/- 0.42 Pass WW-3053, 3054 6/17/2008 Gr. Beta 4.28 +/- 0.83 5.27 +/- 0.91 4.77 +/- 0.61 Pass SW-3154, 3155 6/24/2008 Gr. Beta 2.15 +/- 1.01 2.79 +/- 0.97 2.47 +/- 0.70 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 BS-3245, 3246 6/27/2008 Co-60 108.84 +/- 44.14 91.10 +/- 22.32 99.97 +/- 24.73 Pass BS-3245,3246 6/27/2008 Cs-137 952.18 +/- 52.78 941.56 +/- 13.61 946.87 +/- 27.25 Pass XW-1080,1081 6/30/2008 Fe-55 2.96 +/- 0.32 2.71 +/- 0.30 2.84 +/- 0.22 Pass XW-3786, 3787 6/30/2008 Fe-55 2.96 +/- 0.32 2.71 +/- 0.30 2.84 +/- 0.22 Pass G-3274,3275 7/1/2008 Gr. Beta 7.65 +/- 0.24 7.44 +/- 0.24 7.55 +/- 0.17 Pass SL-3295, 3296 7/1/2008 Gr. Beta 3.76 +/- 0.24 3.64 +/- 0.24 3.70 +/- 0.17 Pass AP-3531, 3532 7/1/2008 Be-7 0.10 +/- 0.01 0.08 +/- 0.01 0.09 +/- 0.01 Pass AP-3663, 3664 7/2/2008 Be-7 0.08 +/- 0.01 0.08 +/- 0.02 0.08 +/- 0.01 Pass AP-3690, 3691 7/2/2008 Be-7 0.07 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 Pass W-4333,4334 7/7/2008 Gr. Beta 7.20 +/- 1.90 7.70 +/- 1.70 7.45 +/- 1.27 Pass W-4840,4841 7/7/2008 Gr. Beta 6.70 +/- 1.60 6.70 +/- 1.80 6.70 +/- 1.20 Pass DW-80415, 80416 7/7/2008 Ra-226 2.81 +/- 0.47 2.00 +/- 0.34 2.41 +/- 0.29 Pass SG-3964,3965 7/9/2008 Be-7 1.35 + 0.23 1.51 +/- 0.22 1.43 +/- 0.16 Pass SG-3964,3965 7/9/2008 Cs-137 0.04 + 0.01 0.04 +/- 0.01 0.04 +/- 0.00 Pass SG-3964, 3965 7/9/2008 Gr. Alpha 23.17 + 3.39 18.76 +/- 3.24 20.97 +/- 2.34 Pass SG-3964,3965 7/9/2008 Gr. Beta 28.99 + 2.12 29.25 +/- 2.31 29.12 +/- 1.57 Pass SG-3964,3965 7/9/2008 K-40 6.86 +/- 0.19 6.84 +/- 0.17 6.85 +/- 0.13 Pass DW-80427, 80428 7/9/2008 Ra-226 3.25 +/- 0.24 3.27 +/- 0.20 3.26 +/- 0.16 Pass DW-80427, 80428 7/9/2008 Ra-228 2.65 +/- 0.67 3.25 +/- 0.72 2.95 +/- 0.49 Pass DW-80451, 80452 7/15/2008 Ra-226 1.02 +/- 0.10 0.96 +/- 0.12 0.99 +/- 0.08 Pass DW-80451, 80452 7/15/2008 Ra-228 1.09 +/- 0.62 1.14 +/- 0.60 1.12 +/- 0.43 Pass DW-80481, 80482 7/16/2008 Ra-226 1.20 +/- 0.13 1.40 +/- 0.14 1.30 +/- 0.10 Pass DW-80481, 80482 7/16/2008 Ra-228 1.69 +/- 0.68 1.65 +/- 0.77 1.67 +/- 0.51 Pass MI-3842, 3843 7/21/2008 K-40 1282.60 +/- 108.30 1379.00 +/- 111.40 1330.80 +/- 77.68 Pass MI-3892, 3893 7/28/2008 K-40 1371.50 +/- 102.90 1501.20 +/- 111.80 1436.35 +/- 75.97 Pass DW-4067, 4068 7/29/2008 Gr. Beta 10.46 +/- 2.37 14.25 +/- 2.78 12.36 +/- 1.83 Pass SWT-4158, 4159 7/29/2008 Gr. Beta 1.58 +/- 0.45 1.80 +/- 0.47 1.69 +/- 0.33 Pass LW-4221, 4222 7/31/2008 Gr. Beta 1.35 +/- 0.56 0.91 +/- 0.52 1.13 +/- 0.38 Pass LW-4242, 4243 7/31/2008 Gr. Beta 1.36 +/- 0.56 1.18 +/- 0.53 1.27 +/- 0.38 Pass VE-4046, 4047 8/4/2008 Be-7 0.77 +/- 0.13 0.82 +/- 0.19 0.80 +/- 0.12 Pass VE-4046, 4047 8/4/2008 Gr. Beta 8.81 +/- 0.36 8.34 +/- 0.31 8.58 +/- 0.24 Pass VE-4046, 4047 8/4/2008 K-40. 5.17 +/- 0.34 5.33 +/- 0.42 5.25 +/- 0.27 Pass W-4821, 4822 8/4/2008 Gr. Alpha 1.70 +/- 0.80 1.70 +/- 0.90 1.70 +/- 0.60 Pass W-4821, 4822 8/4/2008 Gr. Beta 3.90 +/- 0.80 3.70 +/- 0.90 3.80 +/- 0.60 Pass W-4801, 4802 8/5/2008 Gr. Alpha 4.40 + 2.40 4.80 +/- 2.30 4.60 +/- 1.66 Pass W-4801, 4802 8/5/2008 Gr. Beta 13.20 +/- 1.30 14.50 +/- 1.40 13.85 +/- 0.96 Pass DW-80522, 80523 8/5/2008 Ra-226 0.50 +/- 0.12 0.28 +/- 0.12 0.39 +/- 0.08 Pass DW-80522, 80523 8/5/2008 Ra-228 1.23 +/- 0.60 1.09 +/- 0.57 1.16 +/- 0.41 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 DW-80531, 80532 8/5/2008 Gr. Alpha 18.90 +/- 1.86 17.80 +/- 1.96 18.35 +/- 1.35 Pass DW-80534, 80535 8/5/2008 Ra-226 3.01 + 0.18 3.33 +/- 0.18 3.17 +/-0.13 Pass DW-80534, 80535 8/5/2008 Ra-228 2.24 +/- 0.59 2.12 +/- 0.59 2.18 +/- 0.42 Pass SG-4584, 4585 8/6/2008 Be-7 7.11 +0.20 7.44 +/- 0.37 7.27 +/- 0.21 Pass SG-4584, 4585 8/6/2008 Cs-137 0.05 +/- 0.01 0.04 +/- 0.01 0.04 +/- 0.00 Pass SG-4584, 4585 8/6/2008 K-40 7.88 +/- 10.18 8.02 +/- 0.21 7.95 +/- 5.09 Pass SG-4584, 4585 8/6/2008 Ra-226 3.94 +/- 0.18 3.74 +/- 0.22 3.84 +/- 0.14 Pass SG-4573, 4574 8/13/2008 Gr. Alpha 240.72 +/- 8.74 251.53 +/- 9.56 246.13 +/- 6.48 Pass SG-4573, 4574 8/13/2008 Gr. Beta 201.60 +/- 4.28 206.88 +/- 4.71 204.24 +/- 3.18 Pass SG-4584, 4585 8/13/2008 Gr. Alpha 14.07 +/- 3.10 12.97 +/- 3.04 13.52 +/- 2.17 Pass SG-4584, 4585 8/13/2008 Gr. Beta 22.08 +/- 2.36 23.02 +/- 2.34 22.55 +/- 1.66 Pass DW-80547, 80548 8/13/2008 Gr. Alpha 3.33 +/- 1.11 3.88 +/- 1.07 3.61 +/- 0.77 Pass DW-80551, 80552 8/13/2008 U-233/4 2.57 +/- 0.48 2.13 +/- 0.46 2.35 +/- 0.33 Pass DW-80553, 80554 8/13/2008 Ra-226 0.92 +/- 0.14 1.21 +/- 0.17 1.07 +/- 0.11 Pass DW-80553, 80554 8/13/2008 Ra-228 2.20 +/- 0.61 1.64 +/- 0.56 1.92 +/- 0.41 Pass DW-80566, 80567 8/20/2008 Ra-226 1.10 +/- 0.11 1.10 +/- 0.10 1.10 +/- 0.07 Pass DW-80566, 80567 8/20/2008 Ra-228 2.01 +/- 0.58 1.74 +/- 0.58 1.88 +/- 0.41 Pass VE-4647, 4648 8/27/2008 K-40 1.97 +/- 0.17 2.00 +/- 0.21 1.99 +/- 0.14 Pass SL-4690, 4691 9/2/2008 Gr. Beta 2.28 +/- 0.25 2.35 +/- 0.24 2.32 +/-0.17 Pass ME-4732, 4733 9/2/2008 Gr. Beta 2.86 +/- 0.09 2.70 +/- 0.09 2.78 +/- 0.06 Pass ME-4732, 4733 9/2/2008 K-40 2.44 +/- 0.37 2.82 +/- 0.51 2.63 +/- 0.32 Pass SG-5180, 5181 9/3/2008 Be-7 15.50 +/- 0.43 15.54 +/- 0.38 15.52 +/- 0.29 Pass SG-5180, 5181 9/3/2008 Cs-137 0.07 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 Pass SG-5180, 5181 9/3/2008 Gr. Alpha 18.74 +/- 3.33 17.61 +/- 3.15 18.18 +/- 2.29 Pass SG-5180, 5181 9/3/2008 Gr. Beta 29.19 +/- 2.10 28.49 +/- 2.15 28.84 +/- 1.50 Pass SG-5180, 5181 9/3/2008 K-40 8.55 +/- 0.32 8.11 +/- 0.27 8.33 +/- 0.21 Pass SG-5187, 5188 9/3/2008 Be-7 6.18 +/- 0.54 5.90 +/- 0.77 6.04 +/- 0.47 Pass SG-5187, 5188 9/3/2008 K-40 7.16 +/- 0.60 7.29 +/- 0.60 7.23 +/- 0.42 Pass SG-5193, 5194 9/3/2008 Gr. Alpha 5.80 +/- 1.30 7.00 +/- 1.50 6.40 +/- 0.99 Pass SG-5193, 5194 9/3/2008 Gr. Beta 15.60 +/- 1.10 15.60 +/- 1.10 15.60 +/- 0.78 Pass DW-4871, 4872 9/5/2008 1-131 1.15 +/- 0.27 1.16 +/- 0.31 1.16 +/- 0.21 Pass VE-5022, 5023 9/10/2008 K-40 1.27 +/- 0.14 1.11 +/- 0.06 1.19 +/- 0.08 Pass DW-5337, 5338 9/10/2008 Gr. Beta 3.00 +/- 1.07 2.19 +/- 1.05 2.60 +/- 0.75 Pass WW-4977,4978 9/17/2008 Gr. Beta 3.71 +/- 1.10 2.32 +/- 1.11 3.01 +/- 0.78 Pass BS-5088, 5089 9/19/2008 K-40 10493 +/- 607 10299 +/-470 10396 +/- 384 Pass DW-80584, 80585 9/19/2008 U-233/4 3.01 +/- 0.52 2.44 +/- 0.47 2.73 +/- 0.35 Pass DW-80584, 80585 9/19/2008 U-238 0.70 +/- 0.25 0.27 +/- 0.18 0.49 +/- 0.15 Pass DW-80579, 80580 9/25/2008 Gr. Alpha 10.69 +/- 1.31 12.84 +/- 1.51 11.77 +/- 1.00 Pass DW-80579, 80580 9/25/2008 Ra-226 3.13 +/- 0.22 2.89 +/- 0.21 3.01 +/- 0.15 Pass DW-80579, 80580 9/25/2008 Ra-228 3.03 +/- 0.73 1.98 +/- 0.69 2.51 +/- 0.50 Pass G-5389,5390 10/1/2008 Be-7 1.49 +/- 0.32 1.36 +/- 0.28 1.43 +/- 0.21 Pass G-5389,5390 10/1/2008 Gr. Beta 10.86 +/- 0.24 11.18 +/- 0.25 11.02 +/- 0.17 Pass G-5389,5390 10/1/2008 K-40 7.42 +/- 0.67 8.06 +/- 0.63 7.74 +/- 0.46 Pass A5-4

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance AP-5814, 5815 10/1/2008 Be-7 0.08 +/- 0.01 0.08 +/- 0.01 0.08 +/- 0.01 Pass SG-6111, 6112 10/6/2008 Gr. Alpha 9.34 +/- 1.82 8.95 +/- 1.67 9.15 +/- 1.24 Pass SG-6111, 6112 10/6/2008 Gr. Beta 17.46 +/- 1.46 18.86 +/- 1.35 18.16 +/- 0.99 Pass DW-80592, 80593 10/7/2008 Gr. Alpha 2.30 +/- 1.14 1.57 +/- 0.88 1.94 +/- 0.72 Pass DW-80594, 80595 10/7/2008 Ra-228 1.41 +/- 0.55 1.22 +/- 0.50 1.32 +/- 0.37 Pass DW-80650, 80651 10/8/2008 Gr. Alpha 1.30 +/- 0.86 0.12 +/- 0.79 0.71 +/- 0.58 Pass DW-80650, 80651 10/8/2008 Gr. Beta 2.92 +/- 0.69 3.03 +/- 0.64 2.98 +/- 0.47 Pass DW-80629, 80630 10/13/2008 Ra-226 3.12 +/- 0.18 2.87 +/- 0.17 3.00 +/- 0.12 Pass DW-80629, 80630 10/13/2008 Ra-228 2.71 +/- 0.80 3.28 +/- 0.81 3.00 +/- 0.57 Pass DW-80663, 80664 10/13/2008 Gr. Alpha 5.91 +/- 1.70 3.14 +/- 1.44 4.53 +/- 1.11 Pass MI-5572, 5573 10/14/2008 K-40 1391.00 +/- 97.39 1443.90 +/- 110.60 1417.45 +/- 73.68 Pass MI-5603, 5604 10/14/2008 K-40 1412.80 +/- 109.30 1413.80 +/- 110.50 1413.30 +/- 77.71 Pass DW-80676, 80677 10/20/2008 Gr. Alpha 12.20 +/- 1.48 11.87 +/- 1.54 12.04 +/- 1.07 Pass DW-80676, 80677 10/20/2008 Ra-226 5.04 +/- 0.25 5.10 +/- 0.25 5.07 +/- 0.18 Pass DW-80676, 80677 10/20/2008 Ra-228 5.87 +/- 0.86 6.98 +/- 0.95 6.43 +/- 0.64 Pass SW-80687, 80688 10/22/2008 Gr. Alpha 3.42 +/- 1.03 2.98 +/- 1.01 3.20 +/- 0.72 Pass DW-80729, 80730 10/30/2008 Gr. Alpha 8.40 +/- 1.45 7.76 +/- 2.00 8.08 +/- 1.24 Pass DW-80729, 80730 10/30/2008 Gr. Beta 16.94 +/- 1.45 15.41 +/- 1.37 16.18 +/- 1.00 Pass DW-80738, 80739 10/31/2008 U-233/4 2.94 +/- 0.50 3.06 +/- 0.63 3.00 +/- 0.40 Pass DW-80747, 80748 10/31/2008 Ra-226 0.60 +/- 0.09 0.50 +/- 0.08 0.55 +/- 0.06 Pass DW-80747, 80748 10/31/2008 Ra-228 1.33 +/- 0.59 1.38 +/- 0.60 1.36 +/- 0.42 Pass BS-6271, 6272 11/3/2008 Gr. Beta 12.26 +/- 1.69 13.78 +/- 1.84 13.02 +/- 1.25 Pass SS-6593,6594 11/19/2008 K-40 12.35 +/- 0.57 13.10 +/- 0.76 12.73 +/- 0.48 Pass MI-7046, 7047 12/16/2008 K-40 1380.10 +/- 109.80 1477.30 +/- 98.32 1428.70 +/- 73.69 Pass DW-80698, 80699 12/23/2008 Ra-226 3.13 +/- 0.22 3.21 +/- 0.23 3.17 +/- 0.16 Pass DW-80698,80699 12/2312008 Ra-228 5.48 +/- 0.91 5.86 +/- 0.93 5.67 +/- 0.65 Pass SW-7281, 7282 12/30/2008 Gr. Beta 0.87 +/- 0.54 1.35 +/- 0.54 1.11 +/- 0.38 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).

A5-5

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-1137 01/01/08 Am-241 1.27 +/- 0.06 1.23 0.86 -1.60 Pass STW-1137 01/01/08 Co-57 23.80 +/- 0.60 22.80 16.00 - 29.60 Pass STW-1 137 01/01/08 Co-60 8.60 +/- 0.50 8.40 5.88 - 10.92 Pass STW-1137 01/01/08 Cs-1 34 -0.02 +/- 0.10 0.00 -1.00 - 1.00 Pass STW-1137 01/01/08 Cs-137 0.00 +/- 0.10 0.00 -1.00 - 1.00 Pass STW-1137 01/01/08 Fe-55 32.60 +/- 11.60 36.50 25.60 - 47.50 Pass STW-1 137 01/01/08 H-3 515.10 +/- 12.70 472.00 330.00 - 614.00 Pass STW-1137 01/01/08 Mn-54 12.90 +/- 0.80 12.10 8.50 - 15.70 Pass STW-1137 01/01/08 Ni-63 29.50 +/- 2.30 30.70 21.50 - 39.90 Pass STW-1137 01/01108 Pu-238 0.60 +/- 0.06 0.73 0,51 -0.95 Pass STW-1137 01/01/08 Pu-239/40 0.019 +/- U015 0.01 0.00 -1.00 Pass STW-1137 01/01/08 Sr-90 12,00 +/- 1.50 ,11,40 7.98 - 14.82 Pass STW-1137 01/01/08 Tc-99 9.40 +/- 1.70 11.20 7.80 - 14.60 Pass STW-1137 01/01/08 U-233/4 3.37 +/- 0.20 3.63 2.54 - 4.72 Pass STW-1137 01/01/08 U-238 3.63 +/- 0.21 3.74 2.62 - 4.86 Pass STW-1137 01/01/08 Zn-65 16.90 +/- 1.40 16.30 11.40 - 21.20 Pass STW-1138 01/01/08 Gr. Alpha 0.96 +/- 0.14 1.40 0,00 -2.80 Pass STW-1138 01/01/08 Gr. Beta 2.30 +/- 0.15 2.43 1.22 - 3.65 Pass STAP-1139 01/01/08 Co-57 3.90 +/- 0.07 3.55 2.49 -4.62 Pass STAP-1 139 01/01/08 Co-60 1.43 +/- 0.07 1.31 0.92-1.70 Pass STAP-1 139 01/01/08 Cs-134 2.59 +/- 0.16 2.52 1.76 - 3.28 Pass STAP-1 139 01/01/08 Cs-137 3.05 +/- 0.12 2.70 1.89 - 3.51 Pass STAP-1 139 01/01/08 Mn-54 0.43 +/- 0.58 0.00 0.00 - 1.00 Pass STAP-1139 01/01/08 Pu-238 0.080 +/- 0.016 0.11 0.07 -0.14 Pass STAP-1 139 01/01/08 Pu-239/40 0.12 +/- 0.02 0.11 0.08 -0.15 Pass STAP-1 139 01/01/08 Sr-90 1.30 +/- 0.27 1.55 1.08 -2.01 Pass STAP- 1139e 01101/08 U-233/4 0.43 +/- 0.03 0.22 .0.15 -0.28 Fail STAP-1 139e 01/01/08 U-238 0.44 + 0.03 0.23 0.16 -0.29 Fail STAP-1 139 01/01/06 Zn-65 2.36 +/- 0.18 2.04 1.43 -2.65 Pass STAP-1 140 01/01/08 Gr. Alpha 0.11 +/- 0.03 0.35 0.00 - 0.70 Pass STAP-1 140 01/0,1108 Gr. Beta 0.34 +/- 0.04 0.29 0.14 -0.43 Pass STVE-1 141 01/01/08 Co-57 8.30 +/- 0.18 6.89 4.82 - 8.96 Pass STVE-1 141 01/01/08 Co-60 3,03 +/- 0.13 2.77 1.94 - 3.60 Pass STVE-1 141 01/01/08 Cs-134 6.53 + 0.29 6.28 4.40 - 8.16 Pass STVE-1 141 01/01/08 Cs-137 3.90 - 0.19 3.41 2.39 - 4.43 Pass STVE-1 141 01/01/08 Mn-54 5.43 + 0.21 4.74 3.32 -6.16 Pass STVE-1 141 01/01/08 Zn-65 0.033 +/- 0.10 0.00 0.00 - 1.00 Pass A6-1

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

b Concentration Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STSO-1 142 01/01/08 Co-57 483.00 +/- 3.00 421.00 295.00 - 547.00 Pass STSO-l 142 01/01/08 Co-60 3.00 +/- 0.80 2.90 0.00 -5.00 Pass STSO-1 142 01/01/08 Cs-134 896.50 +/- 7.40 854.00 598.00 -1110.00 Pass STSO-1 142 01/01/08 Cs-137 624.40 +/- 4.10 545.00 382.00 -709.00 Pass STSO-1 142 01101/08 Mn-54 667.20 +/- 3.80 570.00 399.00 -741.00 Pass STSO-1 142 01/01/08 Ni-63 536.00 +/- 15.50 640.00 448.00 -832.00 Pass STSO-1 142 01/01/08 Pu-238 78.60 +/- 4.80 72.80 51.00 -94.60 Pass STSO-1 142 01/01/08 Pu-239/40 89.10 +/- 4.50 90.10 63.10 - 117.10 Pass STSO-1 142 01/01/08 U-233/4 134.41 +/- 5.40 142.00 99.00 -185.00 Pass STSO-1 142 01/01/08 U-238 139.00 +/- 5.50 148.00 104.00 -192.00 Pass STSO-1 142 01/01/08 Zn-65 0.093 +/- 0.91 0.00 0.00 -1.00 Pass STSO-1 158 08/01/08 Am-241 57.73 +/- 4.78 69.10 48.40 - 89.80 Pass STSO-1158 08/01/08 Co-57 353.02 +/- 2.01 333.00 233.00 -433.00 Pass STSO-1 158 08/01/08 Co-60 151.99 +/- 1.58 145.00 102.00 -189.00 Pass STSO-1 158 08/01/08 Cs-134 499.72 +/- 2.65 581.00 407.00 -755.00 Pass STSO-1 158 08/01/08 Cs-137 2.54 +/- 0.25 2.80 0.00 -5.00 Pass STSO-1 158 08/01/08 K-40 643.94 +/- 15.50 570.00 399.00 -741.00 Pass STSO-1 158 08/01/08 Mn-54 452.14 +/- 2.96 415.00 291.00 -540.00 Pass STSO-1 158 08/01/08 Ni-63 803.09 +/- 17.01 760.00 532.00 - 988.00 Pass STSO-1 158 08/01/08 Pu-238 0.12 +/- 0.54 0.00 0.00 -5.00 Pass STSO-1158 08/01/08 Pu-239/40 60.88 +/- 5.89 55.60 38.90 -72.30 Pass STSO-1 158 08/01/08 Sr-90 1.95 +/- 2.04 0.00 0.00 -5.00 Pass STSO-1 158' 08/01/08 Tc-99 337.00 +/- 17.30 335.00 235.00 - 436.00 Pass STSO-1 158 08/01/08 U-238 315.67 +/- 11.29 303.00 212.00 -394.00 Pass STSO-1158 08/01/08 Zn-65 0.10 +/- 2.04 0.00 0.00 - 5.00 Pass STVE-1 159 08/01/08 Co-57 8.52 +/- 0.23 7.10 5.00 - 9.20 Pass STVE-1159 08/01/08 Co-60 5.08 +/- 0.19 4.70 3.30 -6.10 Pass STVE-1159 08/01/08 Cs-134 5.26 +/- 0.18 5.50 3.90 - 7.20 Pass STVE-1 159 08/01/08 Cs-137 0.01 +/- 0.14 0.00 0.00-1.00 Pass STVE-1159 08/01/08 Mn-54 6.39 +/- 0.28 5.80 4.10 -7.50 Pass STVE-1159 08/01/08 Zn-65 7.73 +/- 0.45 6.90 4.80 - 9.00 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 STW-1162 08/01/08 Am-241 0.20 +/- 0.06 0.00 0.00-0.10 Fail STW-1 162 08/01/08 Co-57 0.03 +/- 0.16 0.00 0.00 - 5.00 Pass STW-1162 08/01/08 Co-60 11.27 +/- 0.23 11.60 8.10 -15.10 Pass STW-1162 08/01/08 Cs-134 17.93 +/- 0.52 19.50 13.70 - 25.40 Pass STW-1162 08/01/08 Cs-137 23.72 +/- 0.43 23.60 16.50 - 30.70 Pass STW-1 162 08/01/08 Fe-55 43.36 +/- 16.81 46.20 32.30 - 60.10 Pass STW-1162 08/01/08 H-3 385.15 +/- 8.93 341.00 239.00 - 443.00 Pass STW-1162 08/01/08 Mn-54 13.87 +/- 0.37 13.70 9.60-17.80 Pass STW-1162 h 08/01/08 Ni-63 10.77 +/- 2.01 0.00 0.00 -5.00 Fail STW-1162' 08/01/08 Pu-238 0.33 +/- 0.06 0.50 0.40 -0.70 Fail STW-1162 08/01/08 Pu-239/40 0.14 +/- 0.15 0.00 0.00 -0.20 Pass STW-1162 08/01/08 Sr-90 6.49 +/- 1.12 6.45 4.52 -8.39 Pass STW-1162 J 08/01/08 Tc-99 1.80 +/- 0.62 3.76 2.63 -4.89 Fail STW-1162 08/01/08 U-233/4 3.33 +/- 0.18 3.44 2.41 -4.47 Pass STW-1162 08/01/08 U-238 3.38 +/- 0.18 3.55 2.49 -4.62 Pass STW-1162 08/01/08 Zn-65 17.64 +/- 0.61 17.10 12.00 - 22.20 Pass STW-1163 08/01/08 Gr. Alpha 0.08 +/- 0.04 0.00 0.00 -0.56 Pass STW-1163 08/01/08 Gr. Beta 0.12 +/- 0.05 0.00 0.00-1.85 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 b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

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

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

e The results of a repeat analysis were still unacceptable. A spiked air filter was prepared (known activity 4.17 pCi/filter) to verify the methodology; results of the spike analysis were acceptable, 4.64 pCi/filter.

f Corrected result. An error in calculation was found.

9 Included in the testing series as a "false positive". Result of reanalysis, 0.04 +/- 0.01 Bq/L.

hIncluded in the testing series as a "false positive". Result of reanalysis, 3.78 +/- 2.03 Bq/L.

'The reason for the deviation is unknown. Result of the original sample recount: 0.47 +/- 0.07 Bq/L.

The analysis was then repeated from the beginning. Result of reanalysis: 0.51 +/- 0.07 Bq/L.

'The lower result was due to a higher than average background count used in the calculation. Average background result:, 4.11 +/- 0.6 A6-3

TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration (pCi/L)

Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance STAP-1 143 03/24/08 Am-241 60.48 +/- 3.52 50.1 29.3 - 68.7 Pass STAP-1 143 03/24/08 Co-60 650.72 +/- 3.00 730.0 565.0 - 912.0 Pass STAP-1 143 03/24/08 Cs-134 467.50 +/- 5.53 523.0 341.0 -647.0 Pass STAP-1143 03/24/08 Cs-137 1375.90 +/- 25.41 1450.0 1090.0 -1900.0 Pass STAP-1 143 03/24/08 Fe-55 145.60 +/- 28.94 241.0 106.0 -375.0 Pass STAP-1 143 03/24/08 Mn-54 0.00 +/- 0.00 0.0 0.0 - 10.0 Pass STAP-1 143 03/24/08 Pu-238 53.65 +/- 1.54 46.8 32.1 -61.5 Pass STAP-1 143 03/24/08 Pu-239/40 70.44 +/- 3.11 64.1 46.5 - 83.0 Pass STAP-1 143 03/24/08 Sr-90 157.60 +/- 7.70 152.0 66.9 -236.0 Pass STAP-1 143 03/24/08 U-233/4 62.15 +/- 3.41 66.7 42.0 - 98.8 Pass STAP-1 143 03/24/08 U-238 64.11 +/- 3.29 66.2 42.4 - 94.0 Pass STAP-1143 03124/08 Uranium 128.40 +/- 3.29 136.0 69.5 -216.0 Pass STAP-1 143 03/24/08 Zn-65 889.90 +/- 15.90 872.0 604.0 - 1210.0 Pass STAP-1 144 03/24/08 Gr. Alpha 13.08 +/- 1.09 8.8 4.56 - 13.2 Pass STAP-1 144 03/24/08 Gr. Beta 99.90 +/- 3.09 92.2 56.80 -135.0 Pass STSO-1 145 03/24/08 Ac-228 1269.02 +/- 36.81 1180.0 757.0 -1660.0 Pass STSO-1 145 03/24/08 Am-241 1268.50 +/- 85.80 1230.0 735.0 -1580.0 Pass STSO-1 145 03/24/08 Bi-212 1407.10 +/- 56.64 1360.0 357.0 -2030.0 Pass STSO-1 145 03/24/08 Bi-214 2145.50 +/- 305.63 1790.0 1100.0 -2570.0 Pass STSO-1145 03/24/08 Co-60 5219.70 +/- 90.30 5130.0 3730.0 -6890.0 Pass STSO-1 145 03/24/08 Cs-1 34 5427.30 +/- 102.94 5640.0 3630.0 -6790.0 Pass STSO-1 145 03/24/08 Cs-137 6346.60 +/- 201.80 6010.0 4600.0 -7810.0 Pass STSO-1 145 03/24/08 K-40 11052.70 +/- 181.80 11000.0 7980.0 -14900.0 Pass STSO-1 145 03/24/08 Mn-54 0.00 +/- 0.00 0.0 0.0 -10.0 Pass STSO-1 145 03/24/08 Pb-212 1198.20 +/- 96.58 1080.0 697.0 -1520.0 Pass STSO-1 145 03/24/08 Pb-214 2253.30 +/- 291.60 2020.0 1210.0 -3010.0 Pass STSO-1 145 03/24/08 Sr-90 6407.00 +/- 277.00 5360.0 1940.0 -8750.0 Pass STSO-1 145 03/24/08 Th-234 2421.80 +/- 321.00 2030.0 644.0 -3870.0 Pass STSO-1 145 03/24/08 U-233/4 1227.93 +/- 91.52 2050.0 1240.0 -2580.0 Fail STSO-1145 03/24/08 U-238 1319.90 +/- 48.81 2030.0 1240.0 -2580.0 Pass STSO-1 145 03/24/08 Uranium 2592.00 +/- 140.50 4180.0 2380.0 -5640.0 Pass STSO-1 145 03/24/08 Zn-65 2936.20 +/- 73.50 2660.0 2110.0 -3570.0 Pass A7-1

TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration (pCi/L)

Lab Code b Date Analysis Laboratory ERA Control Result 0 Result d Limits Acceptance STVE-1 146 03/24/08 Am-241 1261.50 +/- 73.90 1260.0 718.0 - 1730.0 Pass STVE-1 146 03/24/08 Cm-244 1152.50 +/- 57.44 1200.0 591.0 - 1870.0 Pass STVE-1 146 03/24/08 Co-60 912.41 +/- 13.59 888.0 600.0 - 1280.0 Pass STVE-1 146 03/24/08 Cs- 134 1547.70 +/- 38.81 1540.0 882.0 - 2130.0 Pass STVE-1 146 03/24/08 Cs-137 1163.80 +/- 20.62 1100.0 807.0 - 1530.0 Pass STVE-1 146 03/24/08 K-40 22186.00 +/- 339.40 24600.0 17700.0 - 34800.0 Pass STVE-1 146 e 03/24/08 Mn-54 0.00 +/- 0.00 0.0 0.0 - 10.0 Pass STVE-1 146 03/24/08 Sr-90 3825.90 +/- 140.66 4130.0 2310.0 - 5480.0 Pass STVE-1 146 03/24/08 U-233/4 2753.30 +/- 227.90 3070.0 2110.0 -4070.0 Pass STVE-1146 03/24/08 U-238 2697.10 +/- 143.20 3050.0 2140.0 - 3850.0 Pass STVE-1 146 03/24/08 Uranium 5586.10 +/- 455.20 6260.0 4300.0 - 8080.0 Pass STVE-1 146 03/24/08 Zn-65 1676.80 +/- 43.00 1430.0 1030.0 - 1960.0 Pass STW-1 147 03/24/08 Am-241 97.56 +/- 1.02 90.9 62.0 - 124.0 Pass STW-1 147 03/24/08 Co-60 1430.00 +/- 33.33 1420.0 1240.0 - 1680.0 Pass STW-1 147 03/24/08 Cs- 134 730.18 +/- 33.39 751.0 555.0 - 862.0 Pass STW-1 147 03/24/08 Cs-137 1947.80 +/- 13.80 1990.0 1690.0 -2380.0 Pass STW-1 147 03/24/08 Fe-55 1422.70 +/- 172.16 2080.0 1210.0 -2780.0 Pass STW-1147 e 03/24/08 Mn-54 0.00 +/- 0.00 0.0 0.0 - 10.0 Pass STW-1 147 03/24/08 Pu-238 144.16 +/- 4.54 135.0 102.0 - 168.0 Pass STW-1147 03/24/08 Pu-239/40 82.16 +/- 2.50 80.7 62.4 - 99.8 Pass STW-1 147 03/24/08 Sr-90 512.03 +/- 43.37 512.0 325.0 - 684.0 Pass STW-1 147 03/24/08 U-233/4 74.40 +/- 1.20 81.0 61.0 -104.0 Pass STW-1 147 03/24/08 U-238 75.10 +/- 1.35 80.3 61.3 - 99.5 Pass STW-1147 03/24/08 Uranium 152.10 +/- 2.55 165.0 119.0 - 220.0 Pass STW-1 147 03/24/08 Zn-65 708.90 +/- 29.00 694.0 588.0 - 865.0 Pass STW-1 120 03/19/07 Uranium 339.60 +/- 10.66 391.0 282.0 - 521.0 Pass STW-1 120 03/19/07 Zn-65 2009.00 +/- 36.40 1910.0 1600.0 - 2410.0 Pass a Results obtained by- Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

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

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

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

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

f The analysis was repeated by leaching and total dissolution methods. Total dissolution yielded results within expected range.

Results of the reanalysis: U-233,4, 1655 +/- 95 pCi/kg. U-238 1805 +/- 97 pCi/kg.

A7-2

APPENDIX B DATA REPORTING CONVENTIONS B-1

Data Reportingq 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: xt 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; x, +/- s, and x2 +/-S2 Reported result: x +/- s; where x = (1/2) (x1 + x2) and s = (1/2) S+ 2 3.2. Individual results: < L1 , < L2 Reported result: < L, where L = lower of L1 and L2 3.3. Individual results: x +/- s, < L Reported result: x +/- s if x > 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 x, x2 . . . x are defined as follows:

x nx S= n-4.2 Values below the highest lower limit of detection are not included in the average.

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

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

4.5 In rounding off, the following rules are followed:

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

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

B-2

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

Table C-1. Maximum permissible concentrations a of radioactivity in air and water above natural background in unrestricted areas Air (pCi/m 3) Water (pCi/L)

-3 Gross alpha 1 x10 Strontium-89 8,000 Gross beta 1 Strontium-90 500 b -1 Iodine-I131 2.8 x 10 Cesium-1 37 1,000 Barium-140 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.

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

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

C A natural radionuclide.

C-2

MNGP APPENDIX D Sampling Location Maps D-1

i ~i jill 0000 Figure D-1, Sample Collection and Analysis program: TLD locations, Inner ring (Table 5.2).

D-2

101 MM, 4 II

(

rli M p-i I

&I.

I QGQO Figure D-2. Sample Collection and Analysis program: TLD locations, Outer ring (Table 6.2).

D-3

Coc Figure D-3. Sample Collection and Analysis program: TLD locations, Controls (Table 5.2).

D-4

CI Figure D-4. Sample Collection and Analysis Program: Radiation Environmental Monitoring Program, Milk sampling locations. (Table 5.2)

D-5

ii

• 00 Figure D-5. Sample Collection and Analysis Program: Radiation Environmental Monitoring Program, Milk, Sludge, Ground Water and Shoreline sampling locations (Table 5-2.)

D-6