Text

2007 Annual Radiological Environmental Monitoring Program (REMP) Report
	ML081370083
Person / Time
Site:	Prairie Island
Issue date:	05/13/2008
From:	Wadley M; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	FOIA/PA-2010-0209, ISFSI TS 6.2, L-PI-08-033
	Download: ML081370083 (73)
	v • d • e

NOprae Committed to Nuclear Excellence Prairie Island Nuclear Generating Plant Operated by Nuclear Management Company, LLC MAY 1 3 2008 L-PI-08-033 TS 5.6.2 ISFSI TS 6.2 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282, 50-306 and 72-10 License Nos. DPR-42, DPR-60 and SNM-2506 2007 Annual Radiological Environmental Monitoring Program (REMP) Report Pursuant to Prairie Island Nuclear Generating Plant (PINGP) Technical Specification (TS) 5.6.2, Appendix A to Operating Licenses DPR-42 and DPR-60, and PINGP Independent Spent Fuel Storage Installation Technical Specification (ISFSI TS) 6.2, Appendix A to Materials License SNM-2506, the Nuclear Management Company, LLC (NMC) submits one copy of the Annual Radiological Environmental Monitoring Program report for the period January 1, 2007 through December 31, 2007.

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

Michael D. Wadley /7 Site Vice President, Prairie Isla kd Nuclear Generating Plant Nuclear Management Company, LLC Enclosure cc: Regional Administrator, USNRC, Region III Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector, Prairie Island Nuclear Generating Plant Dr. John House, USNRC, Region III Director of NMSS, USNRC Tim Donakowski, State of Minnesota PI Dakota Community Environmental Coordinator 1717 Wakonade Drive East 9 Welch, Minnesota 55089-9642 Telephone: 651.388.1121

ENCLOSURE 1 Annual Report to the United States Nuclear Regulatory Commission Radiation Environmental Monitoring Program January 1, 2007 through December 31, 2007 71 pages follow

-- *j 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 PRAIRIE ISLAND NUCLEAR GENERATING PLANT ANNUAL REPORT To the UNITED STATES NUCLEAR REGULATORY COMMISSION

.Radiation Environmental Monitoring Program January 1 to December 31, 2007 Docket No. 50-282 License No. DPR-42 50-306 DPR-60 ISFSI

-Docket No.72-10 SNM-2506 Prepared under Contract by ENVIRONMENTAL, Inc.

.MIDWEST LABORATORY Project No. 8010 Approved:

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

The report was prepared by Environmental, Inc., Midwest Laboratory.

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TABLE OF CONTENTS Section Page Preface ........................................................................................................................................................... ii List of Tables ................................................................................................................................................. iv List of Figures ................................................................................................................................................. v 1.0 INTRO DUCTIO N ............................................................................................................................................. 1 2.0 SUM MARY ...................................................................................................................................................... 2 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) ........................................................ 3 3.1 Program Design and Data Interpretation ......................................................................................... 3 3.2 Program Description ............................................................................................................................. 4 3.3 Program Execution .............................................................................................................................. 5 3.4 Laboratory Procedures ......................................................................................................................... 6 3.5 Program M odifications ....................................................................................................................... 6 3.6 Land Use Census ................................................................................................................................. 6 4.0 RESULTS AND DISCUSSIO N ........................................................................................................................ 7 4.1 Atm ospheric Nuclear Detonations and Nuclear Accidents ............................................................. 7 4.2 Sum m ary of Preoperational Data ..................................................................................................... 7 4.3 Program Findings ................................................................................................................................. 8 5.0 FIGURES AND TABLES ............................................................................................................................... 12

6.0 REFERENCES

CITED ......................................................................................................................... 25 APPENDICES A Interlaboratory Com parison Program Results .......................................................................................... A-1 Attachm ent 1, Acceptance Criteria for "Spiked" Sam ples ........................................................................ A-2 B Data Reporting Conventions ....................................................................................................................... B-1 C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas ............ * .................................................. ............

I C-1 D Sam pling Location Maps ............................................................................................................................. D-1 E Special W ell and Surface W ater Sam ples .................................................................................................. E-1 iii

LIST OF TABLES No. Title Pa_ e 5.1 Sample Collection and Analysis Program .................................................................................................... 15 5.2 Sampling Locations .......................................................................................................................................... 16 5.3 Missed Collections and Analyses ..................................................................................................................... 19 5.4 Radiation Environmental Monitoring Program Summary ............................................................................ 20 In addition, the following tables can be found in the Appendices:

Appendix A A-1 Environmental Resources Associates, Crosscheck Program Results ...................................................... A1-1 A-2 Program Results; (TLDs) .............................................................................................................................. A2-1 A-3 In-house "Spiked" Samples ..................................................................... ......................... .................. ...... A3-1 A-4 In-house "Blank" Samples ............................................................................................................................. A4-1 A-5 In-house "Duplicate" Sam ples ...................................................................................................................... A5-1 A-6 Department of Energy MAPEP comparison results .................................................................................. A6-1i A-7 Environmental Resources Associates, Crosscheck Program Results (EML study replacement) ................. A7-1 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas ........................................................................................... C-2 Appendix E E-4.1 Sample collection and analysis program ........................................................................................................ E-6 E-4.2 Sam pling locations .......................................................................................................................................... E-7 E-4.3 REMP Summary .............................................................................................................................................. E-8 E-4.4 REMP Com plete Data Table ........................................................................................................................... E-9 iv

LIST OF FIGURES No. Title Paqe 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator locations versus control ....................................................................................................................................... 13 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6) versus control location (P-i) .................. *...................................................................... 14 In addition, the following figure can be found in the Appendices:

E-1 Onsite Tritium Sampling W ell locations ...................................................................................................... E-11 v

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiation Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December, 2007. 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.

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

These data are included in a reference document (Environmental, Inc., Midwest Laboratory, 2008b) available at Prairie Island Nuclear Generating Plant.

Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, owned by Xcel Energy Corporation and operated by Nuclear Management Company, LLC. The plant has two 575 MWe pressurized water reactors. Unit 1 achieved initial criticality on 1 December 1973. Commercial operation at full power began on 16 December 1973. Unit 2 achieved initial criticality on 17 December 1974. Commercial operation at full power began on 21 December 1974.

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2.0

SUMMARY

The Radiation Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications for the Prairie Island Nuclear Generating Plant and the Independent Spent Fuel Storage Installation (ISFSI) is described.

Results for 2007 are summarized and discussed.

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

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

Sources of environmental radiation include the following:

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

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

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

An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected-from the plant site. The plant's monitoring program includes analyses for tritium and iodine-131. Most samples are analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40. The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which. they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown. On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-1 37 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope.

They were chosen as calibration monitors and should not be considered radiological impact indicators.

The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141. These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the final group, manganese-54, iron-59, cobalt-58 and -60, and zinc-65, are activation products and arise from activation of corrosion products.

They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.

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3.1 Program Design and Data Interpretation (continued)

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

3.2 Program Description The sampling and analysis schedule for the radiation environmental monitoring program at Prairie Island is 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 reactor-site or ISFSI facility, as appropriate. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Prairie Island Nuclear Generating Plant, 2007). Maps of fixed 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. Airborne iodine is collected by continuous pumping through charcoal filters at these same locations. Filters are changed and counted weekly. Particulate filters are analyzed for. gross beta activity and charcoal filters for iodine-1 31. Quarterly composites of particulate filters from each location are determined by gamma spectroscopy. One of the five locations is a control (P-i), and four are indicators (P-2, P-3, P-4, and P-6).

Offsite ambient gamma radiation is monitored at thirty-four locations, using CaSO4:Dy dosimeters with four sensitive areas at each location: ten in an inner ring in the general area of the site boundary, fifteen in the outer ring within a 4-5 mile radius, eight at special interest locations, and one control location, 11.1 miles distant from the plant. They are replaced and measured quarterly.

Ambient gamma radiation is monitored at the Independent Spent Fuel Storage Installation (ISFSI) Facility by twenty CaSO 4:Dy dosimeters. Twelve dosimeters are located inside of the earthen berm in direct line of sight from the storage casks and eight dosimeters are located outside of the earthen berm. They are replaced and measured quarterly.

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

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

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

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3.2 Prooram Descriotion (continued)

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

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

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

(1) Air Particulates / Air Iodine:

A partial sample was collected from location P-1 for the week ending 08-15-07. The sampler pump failed and was replaced.

A partial sample was collected from location P-2'for the week ending 02-21-07. The sampler pump failed and was replaced.

No air particulate sample was available for location P-6 for the week ending 04-18-07.

The filter was missing.

A partial sample was collected from location P-6 for the week ending 07-18-07. The sampler pump failed and was replaced.

(2) Milk:

The Gustafsen Dairy (P-14) sold the herd in September, 2007. No milk samples were available after September 12, 2007.

No milk was available from location P-44 for the months of January, November and December, 2007. The goats were dry for the season.

(3) Thermoluminescent Dosimeters:

The TLD for location P-07B was missing for the second quarter, 2007. The TLD was missing in the field.

Deviations from the program are summarized in Table 5.3.

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3.4 Laboratory Procedures The iodine-1 31 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-1 31 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 The Gustafsen Dairy (P-14) sold their herd in September, 2007. Dairy operations were discontinued.

3.6 Land Use Census In accordance with the Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual, H4, (ODCM) a land use census is conducted in order to identify the location of the nearest milk 2

animal, the nearest residence, and the nearest garden of greater than 500 ft producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles. This census is conducted at least once per 12 months between the dates of May 1 and October 31. If new locations yield a calculated dose or dose equivalent (via the same exposure pathway) twenty percent greater than the required locations per the ODCM, then the new locations are added to the radiation environmental monitoring program within 30 days, and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this.monitoring program after October 31 of the year in which the land use census was conducted.

This land use census insures the updating of the radiation environmental monitoring program should sampling locations change within the 5 mile radius from the plant.

The Land Use Census was completed in October, 2007. There were no changes to any of the highest D/Q locations for nearest residence, milk animal or garden sites. Although one dairy in the monitoring program has discontinued operations, the sampling program is still in compliance with the ODCM.

No downstream irrigation of corn was discovered within 5 miles of the Prairie Island Plant.

Therefore, no corn samples were collected for analysis.

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

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

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 2007 The last reported test was conducted on October 16, 1980 by the People's Republic of China. There were no reported accidents involving a release to the environment at nuclear reactor facilities in 2007.

4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Prairie Island Nuclear Power Plant during the years 1970 to 1973, to determine background levels expected in the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross beta measurements in 2 2 fallout declined yearly from a level of 12,167 pCi/m to 1,020 pCi/m , and these declining values

are reflected throughout the various media tested.

In the air environment, ambient gamma radiation (TLDs) averaged 9.4 mR/4 weeks during preoperational studies. Gross beta in air particulates declined from levels 3of 0.38 to 0.037 pCi/m.

Average present day levels have stabilized at around 0.025 pCi/m . Airborne radioiodine remained below detection levels.

In the terrestrial environment of 1970 to 1973, milk, agricultural crops, and soil were monitored.

In milk samples, low, levels of Cs-137, 1-131, and Sr-90 were detected. Cs-137 levels declined from 16.5 to 8.6 pCi/L. Present day measurements for both Cs-1 37 and 1-131 are below detection levels. Agricultural crop measurements averaged 57.7 pCi/g for gross beta and 0.47 pCi/g for Cs-137. Gross beta measured in soil averaged 52 pCi/g.

The aqueous environment was monitored by testing of river, well and lake waters, bottom sediments, fish , aquatic vegetation and periphyton. Specific location comparison of drinking, river and well water concentrations for tritium and gross beta are not possible. However, tritium background levels, measured at eight separate locations, declined steadily from an average concentration of 1020 pCi/L to 490 pCi/L. Present day environmental levels of tritium are below detection limits. Values for gross beta, measured from 1970 to 1973, averaged 9.9 pCi/L in downstream Mississippi River water, 8.2 pCi/L for well water, and 11.0 pCi/L for lake water.

Gamma emitters were below the lower limit of detection (LLD). In bottom sediments, gross beta background. levels were determined at 51.0 pCi/g. Cs-137 activity during preoperational studies in 1973 measured 0.25 pCi/g upstream and 0.21 pCi/g downstream. The lower levels occasionally observed today can still be attributed to residual activity from atmospheric fallout.

Gross beta in fish, measured in both flesh and skeletal samples, averaged 7.3 and 11.7 pCi/g, respectively. Gross beta background levels in aquatic vegetation, algae and periphyton samples measured 76.0 pCi/g , 46.0 pCi/g, and 13.6 pCi/g, respectively.

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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 Prairie Island Nuclear Generating Plant.

Ambient Radiation (TLDs)

Ambient radiation was measured in the general area of the site boundary, at the outer ring 4 - 5 mi. distant from the Plant, at special interest areas and at one control location. The means ranged from 16.8 mR/91 days at inner ring locations to 17.9 mR/91 days at outer ring locations:

The mean at special interest locations was 16.9 mR/91 days and 17.7 mR/91 days at the control location. Dose rates measured at the inner and outer ring and the control locations were similar to those observed from 1992 through 2006. The results are tabulated below. No plant effect on ambient gamma radiation measurements was indicated (Figure 5-1).

Average (Inner and Average (Inner and Year Outer Rings) Control Year Outer Rings) Control 1992 16.3 14.8 2000 17.0 17.1 1993 - 15.9 15.4 I 2001 16.8 1 17.2 1994 15.2 16.0 2002 17.4 1 16.9 1995 15.6 16.6 2003 16.2 1 16.0 1996 14.8 16.4 2004 17.6 17.6 1997 15.1 16.0 2005 16.8 1 16.3 1998 16.7 17.3 IT 2006 16.6 16.6 1999 I 16.6 17.5 2007 I 17.5 1 17.7 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates (mR/91 days).

ISFSI Facility Operations Monitoring Ambient radiation was measured inside the ISFSI earth berm, outside the ISFSI earth berm and at two special locations between the plant ISFSI and the Prairie Island Indian Community. The mean dose rates measured 105.0 mR/91 days inside the ISFSI earth berm and 21.5 mR/91 days outside the ISFSI earth berm. Two additional casks were placed on the ISFSI pad in 2007, a total of twenty-four loaded casks remain. The higher levels inside the earth berm are expected, due to the loaded spent fuel casks being in direct line-of-sight of the TLDs.

Ambient radiation levels measured outside the earth berm show a slight increase as compared to other offsite dose rates around the plant. If the dose rates outside the earth berm are an indication of gamma skyshine from the casks, they are consistent with predictions given in the ISFSI Safety Analysis Report, Table 7A-7, "Total Skyshine Dose Rate". The cumulative average of the two special Prairie Island Indian.Community TLDs measured 16.4 and 16.3 mR/91 days.

Although the skyshine neutron dose rates are not directly measured, the neutron levels measured next to the casks are below the levels predicted in the ISFSI SAR Report, Table 7A-4, "TN-40 Dose Rates at Short Distances". Therefore, the skyshine dose rates at farther distances from the casks should be at or below the calculated dose rates. No spent fuel storage effect on offsite ambient gamma radiation was indicated (Fig. 5-1).

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Airborne Particulates Average annual gross beta concentrations in airborne particulates at both indicator and control locations were higher in 2007. The results are tabulated below.

Average of Year Indicators Control 3

_Concentration (pCi/m 1992 0.023 0.021 1993 0.022 0.019 1994 0.022 0.022 1995 0.022 0.022 1996 0.023 0.020 1997 0.021 0.021 1998 0.022 0.018 1999 0.024 0.022 2000 0.025 0.025 2001 0.023 0.023 2002 0.028 0.023 2003 0.027 0.025 2004 0.025 0.026 2005 0.027 0.025 2006 0.026 0.025 2007 0.037 0.031 Average annual gross beta concentrations in airborne particulates.

Concentrations were slightly higher at the indicator locations versus the control location (0.037 pCi/m 3 and 0.031 pCi/m 3 , respectively. The pattern of differences between indicator and control locations is similar to that observed from 1992 through 2006.

Gross beta measurements could be affected by construction activity, or dryer summer months, increasing dust in the air and causing heavier loading of the particulate filters. Typically, the highest averages for gross beta occur during the months of January and December and the first and fourth quarters. This pattern was not observed in 2007, the highest beta activity was seen in the spring and summer months. The effect was local, no increase was observed at the Monticello Nuclear Generating Plant, about 100 miles distant. (Xcel Energy Corp., 2008). The highest concentrations were measured at locations P-2, P-3, and P-6. At the control and indicator location P-1 and P-4, elevated activities of similar size occurred. There is no evidence of a plant effect.

The increase in gross beta activity was matched by elevations of Be-7 concentrations, detected in the quarterly composites of air particulate filters. Gamma spectroscopic analysis yielded proportionally higher results for both indicator and control locations. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and AI-Salih, 1955) was detected at an average activity of 0.096 pCi/m3 for all locations, versus an average of 0.070 pCi/m3 in 2006. All other gamma-emitting isotopes were below their respective LLD limits.

Airborne Iodine Weekly levels .of airborne iodine-131 were below the lower limit of detection (LLD) of 0.03 pCi/m 3 in all samples. There was no indication of a plant effect.

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Milk Iodine-1 31 results were below the detection limit of 0.5 pCi/L in all samples. Cs-1 37 results were below the LLD level of 5 pCi/L in all samples. No other gamma-emitting isotopes, except naturally-occurring potassium-40, were detected in any milk samples. This is consistent with the findings of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center . for Radiological Health, 1968).

In summary, the milk data for 2007 is consistent with previous results and show no radiological effects of the plant operation.

Drinking Water In drinking water from the City of Red Wing well, tritium activity measured below the LLD level of 500 pCi/L in all samples.

Gross beta concentrations averaged .11.6 pCi/L throughout the year, ranging from 6.9-1 7.5 pCi/L. These concentrations are consistent with levels observed from 1992 through 2006. The most likely contribution is the relatively high levels of naturally-occurring radium. Gamma spectroscopy indicates the presence of lead and bismuth isotopes, which are daughters of the radium decay chain. There is no indication from the 2007 data of any effect of plant operation.

Year Gross Beta (pCi/L) 1992 7.6 1993 7.5 1994 5.8 1995 3.9 1996 6.3 1997 5.1 1998 . _ 5.4 1999 1 5.3 2000 10.1 20018.

2002 8.7 2003 9.9 2004 9.8 2005 11.5

.2006 13.4 2007 11.6 Average annual concentrations; Gross beta in drinking water.

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River Water For 2007, no measurable tritium activity was detected in river water composites, above the LLD level of 500 pCi/L.

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

Well Water At control well, P-43 (Peterson Farm) and the four indicator wells (P-8, Community Center, P-6, Lock and Dam No. 3, P-9, Plant Well No. 2 and P-24, Suter Farm ) no tritium was detected above the LLD level of 500 pCi/L.

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

In summary, well water data for 2007 show no radiological effects of the plant operation.

Crops Three samples of broadleaf vegetation, cabbage leaves, were collected in July and analyzed for gamma-emitting isotopes, including iodine-1 31. The 1-131 level was below 0.033 pCi/g wet weight in all samples. With the exception of naturally-occurring potassium-40, all other gamma-emitting isotopes were below their respective detection limits. There was no indication of a plant effect.

Field sampling personnel conducted an annual land use survey and found no river water taken for irrigation into fields within 5 miles downstream from the Prairie Island Plant. The collection and analysis of corn samples was not required.

Fish Fish were collected in May and October, 2007 and analyzed for gamma emitting isotopes. Only naturally-occurring potassium-40 was detected, and there was no significant difference between upstream and downstream results. There was no indication of a plant effect.

Aquatic Insects or Periphyton Aquatic insects (invertebrates) or periphyton were collected in May and September, 2007. With the exception of naturally occurring potassium-40, all gamma-emitting isotopes were below their respective detection limits. There was no indication of a plant effect.

Bottom and Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediments were sampled in May and September, 2007 and analyzed for gamma-emitting isotopes. With the exception of naturally occurring potassium-40, all gamma-emitting isotopes were below their respective detection limits. There was no indication of a plant effect.

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5.0 FIGURES AND TABLES 12

Figure 5-1. Offsite Ambient Radiation (TLDs); average of inner and outer ring indicator locations versus control location.

-- Indicator 20 19 18 17 16 15

" 14 13 E

12 11 10 CoC13 C

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Control (P-01C) 20 19 1 __ __ __ 1 1

__ ____ __ [ ~

18 [ ~

____ ____ ____ ____ 1* I ____ ____ ____ ____ ____ ____ ____

17 16 _ ~ iii t _ _ *iI.I iii

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

Indicators (P-2,3,4,6) 0.039 0;037 0.035 0.033 0.031 0.029

____ ____ ____ 1 ~

____ ____ ~ ____-~ ____ ____

0.027

___ ___ I ___ I 1 j ___ ~ [ I 0.025 E- 0.023 I I I

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FL 0.021 0.019

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____ t____ ____ ____ ____ ____ ____ ____ ____ ____ ____ ____ ____ ____

- - - -N N) N)j N) pN) N) N)

CO C C OO O C o 0 0 0 C0 0 . 0 0 0>

wO (0 ( (O CO to CD ED 0 0 0D 0D 0 0 0D N) w 4. (11 0) -14 CO CD -w PQ 1) .4. C-1 (D 4 I----Control (P-i) 0.039 I I I IT_ L i_ 1 1 0.037 0.035

_ _I I _ I_ _ I__

0.033 0.031 0.029

__ _ _ _ _ _ _ _ _ _ _ _ I- ! I _ _ _

0.027 0.025 a-0.023 0.021 0.019 0.017 r 11 2! __ ___i__ _______ ___

n n1n CO C0 0 0 0 0 0 0 0 0C CAO CD Co CO CO CO CD CO 0 0 0 C0 0 0 0 C0 N) &) 4 Ci' 0) -4 CO CO 0) - r) W~ -rý 01 0) -4 14

PRAIRIE ISLAND Table 5.1. Sample collection and analysis program, Prairie Island Nuclear Generating Plant.

Collection Analysis Location Type and Type and Medium No. Codes (and Type)a Frequencyb Frequencyc Ambient radiation (TLD's) 54 P-OI.A - P-IOA C/Q Ambient gamma P-0113 - P-15B P-O1S - P-08S P-OIIA - P-081A P-01113 - P-081B P-OIIX- P-041X, P-OIC Airborne Particulates P-1(C), P-2, C/W GB,GS(QCof P-3, P-4, P-6 each location)

Airborne Iodine 5 P-I(C), P-2, P-3, P-4, P-6 C/W 1-131 Milk 5 P-14, P-18, P-37, P-42, P-44, G/M d 1-131, GS P-43 (C)

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

Drinking water 1 P-11 G/W GB(MC), 1-131(MC)

GS (MC), H-3 (QC)

Well water 5 P-6, P-8, P-9, P-24, G/Q H-3, GS P-43 (C)

Edible cultivated crops - 2 P-38(C), P-24 G/A GS (I-13 1) leafy green vegetables Fish (one species, edible portion) 2 P-19(C), P-13 G/SA GS Periphyton or invertebrates 2 P-40(C), .P-6 G/SA GS Bottom sediment 2 P-20(C), P-6 G/SA GS Shoreline sediment 1 P-12 G/SA GS a Location codes are defined in Table D-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).

15

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

Distance and Direction from Code Typea Collection Site Sample Typeb Reactor P-1 C Air Station P-1 AP, Al 11.8 mi @ 3160/NNW 0

P-2 Air Station P-2 AP, Al 0.5 mi @ 294 /WNW P-3 Air Station P-3 AP, Ai 0.8 mi @ 3130 /NW 0

P-4 Air Station P-4 AP, Al 0.4 mi @ 359 /N P-5 C Upstream of Plant RW 1.8 mi @ 11 0/N P-6 Lock and Dam #3 &.Air AP, Al, RW 0

Station P-6 WW, BS, BOC 1.6 mi @ 129 /SE 0

P-8 Community Center WW 1.0 mi @ 321 /WNW 0

P-9 Plant Well #2 WW 0.3 mi @ 306 /NW P-11 Red Wing Service Center DW 3.3 mi @ 1587/SSE 0

P-12 Downstream of Plant SS 3.0 mi @ 116 /ESE P-13 Downstream of Plant Fc 3.5 mi @ 1130 /ESE P-14 Gustafson Farm M 2.3 mi @ 1730/S P-18 Christiansen Farm M 3.8 mi @ 88°/E P-19 C Upstream of Plant Fc 1.3 mi @ O°/N 0

P-20 C Upstream of Plant BS 0.9 mi @ 45 /NE 0

P-24 Suter Residence VE, WW 0.6 mi @ 158 /SSE 0

P-37 Welsch Farm M 4.1 mi @ 87 /E 0

P-38 C Cain Residence VE 14.2 mi @ 359 /N P-40 C Upstream of Plant BOC 0.4 mi @ O/N 0

P-42 Rother Farm M 4.3 mi. @ 264 /W P-43 C Peterson Farm M, WW 13.9 mi. @ 3550/N 0

P-44 Yoemans Farm M 2.0 mi. @ 214 /SW General Area of the Site Boundary 0

P-OIA Property Line TLD 0.4 mi @ 359 /N P-02A Property Line TLD 0.3 mi @ 100 /N P-03A Property Line TLD 0.5 mi @ 1830/S 0

P-04A Property Line TLD 0.4 mi @ 204 /SWW 0

P-05A Property Line TLD 0.4 mi @ 225 /SW 0

P-06A Property Line TLD 0.4 mi @ 249 /WSW 0

P-07A Property Line TLD 0.4 mi @ 268 /W 0

P-08A Property Line TLD 0.4 mi @ 291 /WNW P-09A Property Line TLD 0.7 mi @ 3170 /NW 0

P-1OA Property Line TLD 0.5 mi @ 333 /NNW 16

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

Distance and Direction from Code Type0 Collection Site Sample Typeb Reactor Approximately 4 to 5 miles Distant from the Plant 0

P-OIB Thomas Killian Residence TLD 4.7 mi @ 355 /N 0

P-02B Roy Kinneman Residence TLD 4.8 mi @ 17 /NNE 0

P-03B Wayne Anderson Farm TLD 4.9 mi @ 46 /NE 0

P-04B Nelson Drive (Road) TLD 4.2 mi @ 61 /ENE 0

P-05B County Road E and Coulee TLD 4.2 mi @ 102 /ESE 0

P-06B William Hauschiblt Residence TLD 4.4 mi @ 112 /ESE 0

P-07B Red Wing Public Works TLD 4.7 mi @ 140 /SE 0

P-08B David Wnuk Residence TLD 4.1 mi @ 165 /SSE P-09B Highway 19 South TLD 4.2 mi @ 1870/S 0

P-101 'Cannondale Farm TLD 4.9 mi @ 200 /SSW 0

P-1iB1 Wallace Weberg Farm TLD 4.5 mi @ 221 /SW 0

P-12B Ray Gergen Farm TLD 4.6 mi @ 251 /WSW 0

P-13B Thomas O'Rourke Farm TLD 4.4 mi @ 270 /W 0

P-14B David J. Anderson Farm TLD 4.9 mi @ 306 /NW 0

P-15B Hoist Farms TLD 3.8 mi @ 345 /NNW Special Interest Locations P-015S Federal Lock & Dam #3 TLD 1.6 mi @ 129 0/SE 0

P-02S Charles Suter Residence TLD 0.5 mi @ 155 /SSE P-03S Carl Gustafson Farm TLD 2.2 mi @ 1730/S 0

P-04S Richard Burt Residence TLD 2.0 mi @ 202 /SSW P-05S Kinney Store TLD 2.0 mi @ 270 0/W 0

P-06S Earl Flynn Farm TLD 2.5 mi @ 299 /WNW 0

P-07S Indian Community TLD 0.7 mi @ 271 /W 0

P-08S Indian Community TLD 0.7 mi @ 287 /NWW 0

P-01C C Robert Kinneman Farm TLD 11.1 mi @ 331 /NNW 17

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

Approximate Type of Distance and Direction Code Type" Collection Site Sampleb from ISFSI Center.

ISFSI Area Inside Earth Berm 0

P-Oi.IA ISFSI Nuisance Fence TLD 190' @ 45 /NE P-021A ISFS1 Nuisance Fence TLD 360'@ 82'/E P-031A ISFSI Nuisance Fence TLD 370' @ 100-/E 0

P-041A ISFSI Nuisance Fence TLD 200' @ 134 /SE P-051A ISFSI Nuisance Fence TLD 180' @ 219°/SW P-061A ISFSI Nuisance Fence TLD 320' @ 258°/WSW P-071A ISFSI Nuisance Fence TLD 320' @ 281"!/WNW P-OSIA ISFSI Nuisance Fence TLD 190' @ 318°/NW P-0+/-tIX ISFSI Nuisance Fence TLD 140' @ 1800/S P-021X ISFSI Nuisance Fence TLD 310'@ 270°/W P-031X ISFSI Nuisance Fence TLD 140' @ 0/N P-041X ISFSI Nuisance Fence TLD 360'@ 90-/E ISFSI Area Outside Earth Berm P-01.I1 ISFSI Berm Area TLD 340' @ 30/N P-021B ISFSI Berm Area TLD 380' @ 28°/NNE P-031B ISFSI Berm Area TLD 560'@ 85-/E P-0411B ISFSI Berm Area TLD 590' @ 165"/SSE P-051B ISFSI Berm Area TLD 690'@ 1860/S P-061B ISFSI Berm Area TLD 720' @ 201"/SSW P-0711B ISFSI Berm Area TLD 610' @ 271'/W P-08113 ISFSI Berm Area TLD 360' @ 332°/NNW a "C" denotes control location. All other locations are indicators.

b Sample Codes:

AP Airborne particulates F Fish Al Airborne Iodine M Milk BS Bottom (river) sediments SS Shoreline Sediments BO Bottom organisms SW Surface Water (periphyton or macroinvertebrates) VE Vegetation/vegetables DW Drinking water WW Well water c Distance and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location.

18

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

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

Collection Reason for not Sample Analysis Location Date or conducting REMP Plans for Preventing Type Period as required Recurrence AP/AI Beta, P-02 2/21/2007 Sampler pump failure. Sampler pump was replaced with 1-131 a calibrated spare.

AP Beta, P-06 4/18/2007 Filter not installed. None required.

TLD Ambient P-07B 2nd. Qtr. TLD missing in field. None required.

Gamma 2007 AP/AI Beta, P-06 7/18/2007 Only 86 hours9.953704e-4 days 0.0239 hours 1.421958e-4 weeks 3.2723e-5 months Sampler pumpwas replaced with 1-131 run-time logged, a calibrated spare.

AP/AI Beta, P-01 8/;15/2007 Only 66 hours7.638889e-4 days 0.0183 hours 1.09127e-4 weeks 2.5113e-5 months Sampler pump was replaced with 1-131 run-time logged. a calibrated spare.

Ml Gamma, P-14 Sept. 12 - Dec. 31, Dairy discontinued None, requirements 1-131 2007 operations, of the ODCM are still met.

Ml Gamma, P-44 Jan., Nov., Dec., Goats were dry. The goat milk is available during 1-131 2007 the grazing season.

19

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2007

( 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 Results' TLD (Inner Ring, Gamma 40 3.0 16.8 (40/40) P-06A 18.2 (4/4) (See Control 0 Area at Site (13.5-19.0) 0.4 mi @ 249° /WSW (17.5-19.0) below.)

Boundary) mR/91 days)

TLD (Outer Ring, Gamma 59 3.0 17.9 (59/59) P-02B, Roy Kinneman, 19.8 (4/4) (See Control 0 4-5 mi. distant) (14.5-20.9) 4.8 mi @ 170 /NNE (18.9-20.9) below.)

mRR91 days)

TLD (Special Gamma 32 3.0 16.9 (32/32) P-03S, Gustafson Farm, .19.4 (4/4) (See Control 0 Interest Areas) (14.1-20.9) 2.2 mi @ 1730/S (18.4-20.4) below.)

mRI91 days)

TLD (Control) Gamma 4 3.0 None P-01C, R. Kinneman, 17.7 (4/4) 17.7 (4/4) 0 mRa91 days) 11.1 mi @ 331 /NNW (16.2-19.5) (16.2-19.5)

Airborne GB 259 0.005 0.037 (207/207) P-03, Air Station 0.041 (52 /52) 0.031 (52/52) 0 Particulates (0.005-0.081) 0.8 mi @ 3130 /NW (0.019-0.081) (0.015-0.069)

(pCi/m 3)

GS 20 Be-7 0.015 0.102 (16/16) P-03, Air Station 0.114 (4/4) 0.073 (4/4) 0 (0.046-0.182) 0.8 mi @ 3130/NW (0.066-0.179) (0.052-0.099)

Mn-54 0.0007 < LLD - < LLD 0 Co-58 0.0007 < LLD - < LLD 0 Co-60 0.0009 < LLD - < LLD 0 Zn-65 0.0008 < LLD - < LLD 0 Zr-Nb-95 0.0010 < LLD < LLD 0 Ru-103 0.0008 < LLD - < LLD 0 Ru-106 0.0066 < LLD - < LLD 0 Cs-134 0.0006 < LLD - - < LLD 0 Cs-137 0.0008 < LLD - - < LLD 0 Ba-La-140 0.0038 < LLD - - < LLD 0 Ce-141 0.0017 < LLD - - < LLD 0 Ce-144 0.0043 < LLD < LLD 0

,Airborne Iodine 1-131 259 0.03 < LLD < LLD 0 (pCi/m 3) 20

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2007 I

( 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 Milk (pCi/L) 1-131 100 0.5 < LLD < LLD 0 GS 100 K-40 200 1468 (82/82) P-44, Yoemans Farm 1819 (15 /15) 1441 (18/18) 0 (1190-2152) 2.0 mi @ 214°/SW (1231-2152) (1351-1571)

Cs-134 5 < LLD < LLD 0 Cs-137 5 < LLD < LLD 0 Ba-La-140 5 < LLD < LLD 0 River Water H-3 8 500 < LLD < LLD 0 (pCi/L)

GS 24 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 43 < LLD < LLD 0 21

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2007

( 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 d Rangec Rangec Resultse Drinking Water GB 12 1.0 11.6 (12/12) P-11, Red Wing S.C. 11.6 (12/12) None 0 (pCi/L) (6.9-17.5) 3.3 mi @ 1580 /SSE (6.9-17.5) 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 51 < LLD None 0 Well Water H-3 20 500 < LLD < LLD 0 (pCi/L)

GS 20 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 42 < LLD - < LLD 0 Crops - Cabbage 1-131 3 0.033 < LLD - < LLD 0 (pCi/gwet) 22

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2007

( 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 3.17 (2/2) P-19, Upstream 3.44(2/2) 3.44 (2/2) 0 (2.85-3.49) 1.3 mi @ 0°/N (3.40-3.47) (3.40-3.47)

Mn-54 0.014 < LLD < LLD 0 Fe-59 0.091 < LLD < LLD 0 Co-58 0.022 < LLD < LLD 0 Co-60 0.023 < LLD < LLD 0 Zn-65 0.021 < LLD < LLD 0 Zr-Nb-95 0.029 < LLD < LLD 0 Cs-134 0.020 < LLD < LLD 0 Cs-137 0.024 < LLD < LLD 0 Ba-La-140 0.12 < LLD < LLD 0 Invertebrates GS 4 (pCi/g wet) .Be-7 0.69 < LLD < LLD 0 K-40 0.74 < LLD < LLD 0 Mn-54 0.035 < LLD < LLD 0 Co-58 0.060 < LLD < LLD 0 Co-60 0.036 < LLD < LLD 0 Zn-65 0.062 < LLD < LLD 0 Zr-Nb-95 0.18 < LLD < LLD 0 Ru-103 0.13 < LLD < LLD 0 Ru-106 0.31 < LLD - < LLD 0 Cs-1 34 0.032 < LLD - < LLD 0 Cs-137 0.030 < LLD - < LLD 0 Ba-La-140 2.36 < LLD - < LLD 0 Ce-141 0.30 < LLD - < LLD .0 Ce-144 0.19 < LLD - < LLD 0 23

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2007

( County, State)

Indicator Location with Highest Control Number Sample Type and - Locations Annual Mean . Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analyses' Rangec Locationd Rangec Rangec Resultse Bottom and GS 6 Shoreline Be-7 0.33 < LLD < LLD 0 Sediments (pCi/g dry) K-40 0.10 7.83 (4/4) P-20, Upstream 9.11 (2/2) 9.11 (2/2) 0 (6.93-8.85) 0.9 mi. @ 45°/NE (9.00-9.21) (9.00-9.21)

Mn-54 0.028 < LLD - < LLD 0 Co-58 0.034 < LLD - < LLD 0 Co-60 0.021 < LLD - < LLD 0 Zn-65 0.068 < LLD <- LLD 0 Zr-Nb-95 0.067 < LLD <- LLD 0 Ru-103 0.040 < LLD - < LLD 0 Ru-106 0.14 < LLD - < LLD 0 Cs-134 0.029 < LLD <- LLD 0 Cs-1 37 0.022 < LLD <- LLD 0 Ba-La-140 0.39 < LLD < LLD 0 Ce-141 0.13 < LLD < LLD 0 Ce-144 0.17 < LLD < LLD 0 a GB = gross beta, GS = gamma scan.

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

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

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.

24

6.0 REFERENCES

CITED Arnold, J. R. and H. A. Al-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.

Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275 and 276.

Environmental, Inc., Midwest Laboratory

__ 2001a through 2008a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2007.

2001b through 2008b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000-2007.

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

2005. Quality Control Procedures Manual, Rev. 1, 17.September 2005.

2003. Quality Control Program, Rev. 0, 21 August 2003.

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

Hazleton Environmental Sciences Corporation.

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

1979b to 1983b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete. Analysis Data Tables, January - December 1978 through 1982.

Hohenemser, C. M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel. 1986. "Chernobyl," Chemtech, October 1986, pp. 596-605.

National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, No. 12,730-746.

Northern States Power Company.

1972 through 1974. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1, 1971 to December 31, 1971, 1972, 1973. Minneapolis, Minnesota.

1979 to 2006. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1978 through 2005.

Minneapolis, Minnesota.

Prairie Island Nuclear Generating Plant, 2007. Radiological Environmental Monitoring for Prairie Island Nuclear Generating Plant, Radiation Protection Implementing Procedures, 4700 series.

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

- December, 1983 through 1999.

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

25

6.0 REFERENCES

CITED (continued)

U.S. Dep't of Energy 1997 ý.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. 2008. Monticello Nuclear Generating Plant, Annual Radiation Environmental-Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2005-2007 (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 26

- Environmental, Inc.

Midwest Laboratory n Allegheny Technologies Co.

700 Landwehr Road - Northbrook, IL 60062-2310 ph. (847) 564-0700 - fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte 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 reportsonly.

January through December, 2007

. 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 month,,

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 acceptance criteria for "spiked" samples.

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

Al

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

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

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

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

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

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

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

> 100 pCi/liter 10% of known value Othersb 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies

. Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limit.

A2

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1 121 04/09/07 Sr-89 30.7 +/- 4.3 35.4 26.7 - 44.1 Pass STW-1 121 04/09/07 Sr-90 39.3 +/- 1.8 42.1 33.4 - 50.8 Pass STW-1 122 04/09/07 Ba-1 33 30.0 +/- 2.4 29.3 20.6 - 38.0 Pass STW-1 122 04/09/07 Co-60 118.5 +/-3.9 119.0 109.0 - 129.0 Pass STW-1 122 04/09/07 Cs-1 34 52.6 +/- 2.3 54.3 45.6 - 63.0 Pass STW-1 122 04/09/07 Cs-1 37 49.5.+/- 3.8 50.3 41.6 - 59.0 Pass STW-1 122 04/09/07 Zn-65 91.7 +/- 6.3 88.6 73.3 - 104.0 Pass STW-1 123 ,.04/09/07 Gr. Alpha 33.8 +/- 3.5 56.5 32.0 - 81.0 Pass STW-1 123 04/09/07 Gr. Beta 24.2 +/- 2.3 25.3 16.6 - 34.0 Pass STW-1 124 04/09/07 1-131 19.2 +/- 1.2 18.9 13.7 -24.1 Pass STW-1125 04/09/07 H-3 7540.0 +/- 255.0 8060.0 6660.0 - 9450.0 Pass STW-1 125 04/09/07 Ra-226 13.0 +/- 0.6 13.4 9.9 - 16.9 Pass STW-1 125 04/09/07 Ra-228 19.9 +/- 2.7 18.2 10.3 - 26.1 Pass STW-1 125 04/09/07 Uranium 4.5 +/- 0.2 4.6 0.0 - 9.8 Pass STW-1 127 07/09/07 Sr-89 51.7 +/- 5.0 58.2 49.5 - 66.9 Pass STW-1127 07/09/07 Sr-90 21.4 +/- 2.3 19.0 10.3 -27.7 Pass STW-1 128 07/09/07 Ba-1 33 19.4 +/- 2.2 19.4 10.7 -28.1 Pass STW-1 128 07/09/07 Co-60 32.8 +/- 2.0 33.5 24.8 - 42.2 Pass STW-1 128 07/09/07 Cs-134 67.0 +/- 2.9 68.9 60.2 -77.6 Pass.

STW-1 128 07/09/07 Cs-1 37 61.6 +/-3.8 61.3 52.6 - 70.0 Pass STW-1 128 07/09/07 Zn-65 55.6 +/- 7.5 54.6 45.2 -64.0 Pass STW-1 129 07/09/07 Gr. Alpha 19.2 +/- 1.6 27.1 15.4 -38.8 Pass STW-1 129 07/09/07 Gr. Beta 9.1 +/-0.9 11.5 2.8 - 20.2 Pass STW-1 130 07/09/07 Ra-226 7.0 +/- 0.5 7.7 5.7 - 9.7 Pass STW-1 130 07/09/07 Ra-228 9.2 +/- 2.3 9.1 5.2 - 13.1 Pass STW-1 130 07/09/07 Uranium 23.9 +/- 1.1 25.1 19.9 - 30.3 Pass STW-1 131 10/05/07 Sr-89 27.3 +/- 3.3 27.4 19.3 -33.9 Pass STW-1 131 10/05/07 Sr-90 17.7 +/- 1.2 18.2 12.9 -21.6 Pass STW-1 132 10/05/07 Ba-133 12.2 +/- 3.3 12.6 8.6 - 15.5 Pass STW-1 132 10/05/07 Co-60 23.8 +/- 1.4 23.2 19.9 -28.3 Pass STW-1 132 10/05/07 Cs-134 70.5 +/- 4.2 71.1 58.0 - 78.2 Pass STW-1 132 10/05/07 Cs-137 178.2 +/- 3.3 180.0 162.0 -200.0 Pass STW-1 132 10/05/07 Zn-65 263.9 +/- 6.9 251.0 226.0 - 294.0 Pass STW-1133 10/05/07 Gr. Alpha 54.7 +/- 2.1 58.6 30.6 - 72.9 Pass STW-1 133 10/05/07 Gr. Beta 11.9 +/--0.9 9.7 4.3 - 18.2 Pass STW-1 134 10/05/07 1-131 33.0 +/- 1.5 28.9 24.0 - 33.8 Pass STW-1 135 10/05/07 H-3 9965.0 +/- 250.0 9700.0 8430.0 - 10700.0 Pass STW-1 135 10/05/07 Ra-226 12.7 +/- 0.2 12.9 9.6 - 14.9 Pass STW-1 135 10/05/07 Ra-228 19.6 +/-2.4 17.9 12.0 -21.5 Pass STW-1 135 10/05/07 Uranium 27.3 - 1.1 27.5 22.1 -30.8 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

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

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

Al-1

TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry,, (TLD, CaSO 4 : Dy Cards).

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

2007-1 7/13/2007 30 cm. 54.25 60.56 +/- 5.54 37.98 - 70.53 Pass 2007-1 7/13/2007 40 cm. 30.51. 34.23 +/- 0.96 21.36 -39.66 Pass 2007-1 7/13/2007 50 cm. 19.53 17.95 +/- 1.86 13.67 - 25.39 Pass 2007-1 7/13/2007 60 cm. 13.56 16.61 +/- 0.60 9.49 - 17.63 Pass 2007-1 7/13/2007 70 cm. 9.96 9.72 +/- 0.90 6.97 - 12.95 Pass 2007-1 7/13/2007 80 cm. 7.63 7.79 +/- 0.33 5.34 - 9.92 Pass 2007-1 7/13/2007 90 cm. 6.03 5.53 +/- 0.72 4.22 - 7.84 Pass 2007-1 7/13/2007 100 cm. 4.88 5.32 .+/- 0.17 3.42 - 6.34 Pass 2007-1 7/13/2007 110 cm. 4.03 3.49 +/- 0.14 2.82 - 5.24 Pass 2007-1 7/13/2007 120 cm. 3.39 2.64 +/- 0.14 2.37 - 4.41 Pass 2007-1 7/13/2007 150 cm. 2.17 2.13+/- 0.87 1.52 -2.82 Pass Environmental, Inc.

2007-2 11/12/2007 30 cm. 54.37 65.47 +/- 5.25 38.06 - 70.68 Pass 2007-2 11/12/2007 40 cm. 30.59 37.43 +/- 2.18 21.41 -39.77 Pass 2007-2 11/12/2007 60 cm. .13.59 15.18 +/- 0.50 9.51 - 17.67 Pass 2007-2 11/12/2007 70 cm. 9.99 12.18 +/- 0.46 6.99 -12.99 Pass 2007-2 11/12/2007 80 cm. 7.65 8.74 +/- 0.39 5.36 - 9.95 Pass 2007-2 11/12/2007 90 cm. 6.04 5.89 +/- 0.25 4.23 - 7.85 Pass 2007-2 11/12/2007 110 cm. 4.04 4.13 +/- 0.41 2.83 - 5.25 Pass 2007 11/12/2007 120 cm. 3.4 2.92 +/- 0.13 2.38 - 4.42 Pass 2007-2 11/12/2007 120 cm. 3.4 2.91 +/- 0.31 2.38 - 4.42 Pass 2007-2 11/12/2007 150 cm. 2.17 1.95 +/- 0.72 1.52 -2.82 Pass 2007-2 11/12/2007 180 cm. 1.51 1.38 +/- 0.05 1.06-1.96 Pass A2-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Codue b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance W-30707 3/7/2007 Gr. Alpha 19.51 +/- 0.40 20.08 10.04 - 30.12 Pass W-30707 3/7/2007 Gr. Beta 67.45 +/- 0.49 65.73 55.73 - 75.73 Pass SPAP-i 566 3/23/2007 Cs-134 25.35 +/- 1.31 27.82 17.82 -37.82 Pass S PAP- 1566 3/23/2007 Cs-137 107.52 +/- 3.02 116.48 104.83 - 128.13 Pass SPW-1568 3/23/2007 H-3 65595.00 +/- 672.00 71118.00 56894.40 -85341.60 Pass SPW-1678 3/28/2007 Tc-99 28.44 +/- 1.12 32.35 20.35 -44.35 Pass SPW-1 595. 4/5/2007 Cs-134 54.48 +/- 2.12 54.99 44.99 - 64.99 Pass SPW-1595 4/5/2007 Cs-1 37 59.03 +/- 2.94 58.19 48.19 - 68.19 Pass SPW-1 595 4/5/2007 1-131(G) 83.11 +/- 3.51 82.07 72.07 - 92.07 Pass SPW-1595A 4/512007 1-131 78.40 +/- 1.10 82.07 65.66 - 98.48 Pass SPW-1595B 4/5/2007 1-131 78.97 +/- 1.10 82.07 65.66 - 98.48 Pass SPMI-1 597 4/5/2007 Cs-1 34 54.03 +/- 2.15 54.99

44.99 - 64.99 Pass SPM1-1597 4/5/2007 Cs-137 59.81 +/- 4.75 58.19 48.19 - 68.19 Pass SPM1-1597 4/5/2007 1-131(G) 83.97 +/- 4.07 82.07 72.07 - 92.07 Pass SPMI-1597A 4/5/2007 1-131 79.53 +/- 1.03 82.07 65.66 - 98.48 Pass SPMI-1597B 4/5/2007 1-131 83.51 +/- 1.05 82.07 65.66 - 98.48 *Pass SPCH-2839 5/17/2007 1-131(G) 78.70 +/- 7.36 70.40 60.40 - 80.40 Pass SPW-2847 5/17/2007 Cs-134 55.43 +/- 1.68 52.85 42.85 - 62.85 Pass SPW-2847 5/17/2007 Cs-137 59.86 +/- 2.71 58.03 .48.03 - 68.03 Pass SPW-2847 5/17/2007 1-131(G) 63.95 +/- 2.69 70.87 60.87 - 80.87 Pass SPMI-2849 5/17/2007 Cs-134 51.37 +/- 1.65 52.85 42.85 - 62.85 Pass SPMI-2849 5/17/2007 Cs-1 37 60.42 +/- 4.31 58.03 48.03 - 68.03 Pass SPMI-2849 5/17/2007 1-131(G) 62.44 +/- 3.14 70.87 60.87 - 80.87 Pass SPCH-2922 5/17/2007 1-131(G) 80.00 +/- 6.40 70.40 41.60 - 99.20 Pass SPW-2847 5/18/2007 1-131 60.14 +/- 0.89 70.87 56.70 - 85.04 Pass SPW-2847 5/18/2007 Sr-89 104.93 +/- 6.64 121.90 97.52 - 146.28 Pass SPW-2847 5/18/2007 Sr-89 46.72 +/- 1.97 46.08. 36.08 - 56.08 Pass SPMI-2849 5/18/2007 1-131 67.97 +/- 0.88 70.87 56.70 - 85.04 Pass SPW-2909 e 5/22/2007 Fe-55 11137.00 +/- 316.00 14271.50 11417.20 - 17125.80 Fail SPW-2911 5/22/2007 H-3 65023.00 +/- 679.00 70485.00 56388:00 - 84582.00 Pass SPAP-2913 5/22/2007 Gr. Beta 55.27 +/- 8.51 52.65 42.12 -73.71 Pass SPAP-2915 5/22/2007 Cs-134 22.53 +/- 1.12 26.42 16.42 - 36.42 Pass SPAP-2915 5/22/2007 Cs-1 37 111.14 +/- 3.57 116.06 .104.45 - 127.67 Pass SPF-2922 5/22/2007 Cs-134 0.52 +/- 0.03 0.53 0.32 - 0.74 Pass SPF-2922 5/22/2007 Cs-137 2.58 +/- 0.07 2.32 1.39 - 3.25 Pass SPW-3223 5/24/2007 Ni-63 2233.10 +/- 10.32 2135.90 1281.54 -2990.26 Pass W-60507 6/5/2007 Gr. Alpha 20.93 +/- 0.42 20.08 10.04 - 30.12 Pass W-60507 6/5/2007 Gr. Beta 60.50 +/- 0.46 65.73 55.73 - 75.73 Pass SPW-4327 7/18/2007 Tc-99 25.58 +/- 1.11 32.35 20.35 - 44.35 Pass SPW-5476 8/17/2007 Ni-63 1925.18 +/- 9.62 2135.90 1281.54 -2990.26 Pass W-92107 9/21/2007 Gr. Alpha 23.02 +/- 0.44 20.08 10.04 -30.12 Pass W-92107 9121/2007 Gr. Beta 61.48 +/- 0.47 65.73 55.73 - 75.73 Pass A3-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)8 Lab Code Date Analysis Laboratory results Known Control 2s, n=1b Activity Limitsc Acceptance SPW-6880 10/1012007 Tc-99 30.97 + 1.21 32.35 20.35 - 44.35 Pass w-111007 11/10/2007 Gr. Alpha 22.43 +/- 0.42 20.08 10.04 - 30.12 Pass w-1 11007 11/10/2007 Gr. Beta 64.49 +/- 0.48 65.73 55.73 - 75.73 Pass SPAP-7742 11/13/2007 Cs-1 34 21.18 +/- 1.29 22.41 12.41 -32.41 Pass SPAP-7742 11/13/2007 Cs-1 37 113.61 +/- 3.16 114.76 103.28 - 126.24 Pass SPAP-7744 11/13/2007 Gr. Beta 53.41 +/- 0.13 52.03 41.62 -72.84 Pass SPMI-7746 11/13/2007 Cs-1 34 42.20 +/- 1.48 44.83 34.83 - 54.83 Pass SPMI-7746 11/13/2007 Cs-137 56.05 +/- 2.83 57.40 47.40 - 67.40 Pass SPMI-7746 11/13/2007 Sr-90 41.02 +/- 1.61 45.54 36.43 - 54.65 Pass SPW-7748 11/13/2007 Cs-134 43.11 +/- 1.52 44.80 34.80 - 54.80 Pass SPW-7748 11/13/2007 Cs-137- 59.28 +/- 3.50 57.40 47.40 - 67.40 Pass SPW-7748 11/13/2007 Sr-90 37.23 +/- 1.51 45.54 36.43 - 54.65 Pass SPW-7752 11/13/2007 Fe-55 12935.10 +/- 357.00 12640.50 10112.40 -15168.60 Pass SPW-7758 11/13/2007 H-3 65405.00 +/- 712.50 68618.00 54894.40 - 82341.60 Pass SPF-7760 11/13/2007 Cs-134 0.45 +/-0.02 0.45 0.27 - 0.63 Pass SPF-7760 11/13/2007 Cs-1 37 2.45 +/- 0.07 2.29 1.37 -3.21 Pass SPW-8034 11/13/2007 Ni-63 2194.06 +/- 10.77 2129.03 1277.42 - 2980.64 Pass a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/m 3), 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).

cResults are based on single determinations.

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

'Sample recount: 12557 +/- 335.

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 (4.667) Acceptance Type LLD Activityc Criteria (4.66 a)

W-30707 water 3/7/2007 Gr. Alpha 0.40 0.01' +/- 0.28 .2 W-30707 water 3/7/2007 Gr. Beta 0.75 0.06 +/- 0.53 4 SPAP-1 567 Air Filter 3/23/2007 Cs-1 34 0.79 100 SPW-1567 Air Filter 3/23/2007 Cs-137 1.01 100 SPW-1568 water 3/23/2007 H-3 176.10 -26.16 +/- 91.62 200 SPW-1596 water 4/5/2007 Cs-1 34 3.28 10 SPW-1596 water 4/5/2007 Cs-137 3.45 10 SPW-1 596 water 4/5/2007 1-131 0.27 0.02 +/- 0.18 0.5 SPW-1596 water 4/5/2007 1-131(G) 2.91 20 SPM1-1598 Milk 4/5/2007 Cs-1 34 3.30 10 SPMI-1598 Milk 4/5/2007 Cs-137 5.08 10 SPMI-1598 Milk 4/5/2007 1-131 0.26 -0.10 +/- 0.17 0.5 SPMI-1598 Milk 4/5/2007 1-131(G) 4.10 20 SPCH-2839 Charcoal Canister 5/17/2007 1-131(G) 2.24 9.6 SPW-2848 water 5/17/2007 Cs-134 3.14 10 SPW-2848 water 5/17/2007 *.Cs-137 1.37 10 SPW-2848 water 5/17/2007 1-131(G). 5.34 20 SPMI-2850 Milk 5/17/2007 Cs-1 34 3.32 10 SPMI-2850 Milk 5/17/2007 Cs-1 37 2.60 10 SPMI-2850 Milk 5/17/2007 1-131(G) 4.77 20 SPW-2848 water 5/18/2007 1-131 0.34 -0.06 +/- 0.19 0.5 SPW-2848 water 5/18/2007 Sr-89 0.81 -0.02 +/- 0.65 5 SPW-2848 water 5/18/2007 Sr-90 0.53 0.01 +/- 0.25 1 SPMI-2850 Milk 5/18/2007 1-131 0.45 .0.20 +/- 0.26 0.5 SPMI-2850 Milk 5/18/2007 Sr-89 0.96 -0.73 +/- 1.02 5 SPMI-2850d Milk 5/18/2007 Sr-90 0.58 0.96 +/- 0.38 1 SPAP-2914 Air Filter *5/22/2007 Gr. Beta 0.004 -0.002 +/- 0.002 0.01 SPAP-2916 Air Filter 5/22/2007 Cs-1 34 2.84 100 SPAP-2916 Air Filter 5/22/2007 Cs-137 2.24 100 SPF-2923 Fish 5/22/2007 Cs-134 8.71 100 SPF-2923 Fish 5/22/2007 Cs-137 8.35 100 SPW-3224 water 5/24/2007 Ni-63 1.61 -0.30 +/- 0.84 20 W-60507 water 6/5/2007 Gr. Alpha 0.43 -0.01 +/- 0.30 2 W-60507 water 6/5/2007 Gr. Beta 0.77 0.01 +/- 0.54 4 SPW-4328 water 7/18/2007 Tc-99 6.41 -3.12 +/- 3.84 10 SPW-5477 water 8/17/2007 Ni-63 1.48 4.38 +/- 1.01 20 W.92107 water 9/21/2007 Gr. Alpha 0.41 0.09 + 0.29 2 W-92107 water 9/21/2007 Gr. Beta 0.75 -0.26 + 0.51 4 A4-1

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

SPW-6881 water 10/10/2007 Tc-99 6.82 -6.58 +/- 4.04 10 SPAP-7743 Air Filter 11/13/2007 Gr. Beta 0.003 -0.002 +/- 0.002 0.01 SPMI-7745 Milk 11/13/2007 Cs-1 34 2.16 10 SPMI-7745 Milk 11/13/2007 Cs-137 3.46 10 SPMI-7745 Milk 11/13/2007 1-131(G) 5.89 20 SPMI-7745 Milk 11/13/2007 Sr-90 0.59 0.73 +/- 0.35 1 SPW-7.747 water 11/13/2007 Cs-1 34 2.39 10 SPW-7747 water 11/13/2007 Cs-1 37 3.53 10 SPW-7747 water 11/13/2007 1-131(G) 12.51 20 SPW-7747 water 11/13/2007 Sr-90 0.71 -0.04 +/- 0.32 1 SPW-7751 water 11/13/2007 Fe-55 15.50 -4.18 +/- 9.20 1000 SPW-7757 water 11/13/2007 H-3 151.35 -14.98 +/- 78.85 200 SPF-7759 Fish 11/13/2007 Cs-134 5.50 100 SPF-7759 Fish 11/13/2007 Cs-137 5.10 100 SPW-8033 water 11/13/2007 Ni-63 1.45 -0.19 +/- 0.87 20 W-120607 water 12/6/2007 Gr. Alpha 0.40 0.02 +/- 0.28 2 W-1 20607 water 12/6/2007 Gr. Beta 0.77 -0.70 +/- 0.51 4 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.

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

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

A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration .(pCi/L)a Averaged Lab Code* Date Analysis. First. Result Second Result Result Acceptance E-20, 21 1/2/2007 Gr. Beta 1.76 +/- 0.07 1.70+/- 0.06 1.73 +/- 0.05 Pass E-20, 21 1/2/2007 K-40 1.49 +/- 0.24 1.57 +/- 0.27 1.53 +/- 0.18 Pass CF-41, 42 1/2/2007 Gr. Beta 18.02 +/- 0.41 18.81 +/- 0.42 18.42 +/- 0.29 Pass CF-41, 42 1/2/2007 K-40 11.68 +/- 1.12 12.67- +/- 0.97 12.18 +/- 0.74 Pass CF-41,42 .1/2/2007 Sr-90 0.039 +/- 0.011 0.026 +/- 0.010 .0.033 +/- 0.007 Pass P-9516, 9517 1/3/2007 H-3 270.78 +/- 91.74 301.18 +/- 92.99 285.98 +/- 65.31 \ Pass LW-9579, 9580 1/4/2007 Gr. Beta 0.91 +/- 0.31 0.93 +/- 0.30 0.92 +/- 0.22 Pass DW-70085, 70086 1/9/2007 Gr. Alpha 7.95 +/- 1.20 7.92 +/- 1.42 7.94 +/- 0.93 Pass DW-70037, 70038 1/11/2007 Gr. Alpha 55.47 +/- 3.99 52.87 +/- 4.02 54.17 +/- 2.83 Pass DW-70054, 70055 1/18/2007 Gr. Alpha 2.68 +/- 0.88 1.88 +/- 0.78 2.28 +/- 0.59 Pass DW-70122, 70123 1/18/2007 Gr. Alpha 4.30 +/- 1.14 6.25 +/- 1.16 5.28 +/- 0.81 Pass DW-70122, 70123 1/18/2007 Gr. Beta 4.22 +/- 0.70 5.33 +/- 0;75 4.78 +/- 0.51 Pass DW-70098, 70099 1/25/2007 Gr. Alpha 3.27 +/- 0.90 1.97 +/- 0.92 2.62 +/- 0.64 Pass DW-70110, 70111 1/25/2007 Gr. Alpha 2.19 +/- 0.92 1.69 +/- 0.79 1.94 +/- 0.61 Pass SWU-676, 677 1/30/2007 Gr. Beta 1.77 +/- 0.39 2.11 +/- 0.39 1.94 +/- 0.28 Pass DW-70148, 70149 1/30/2007 Gr. Alpha 4.65 +/- 1.37 *5.20+/- 1.81 4.93 +/- 1.14 Pass SW-600,601 2/1/2007 K-40 1.24 +/- 0.12 1.20 +/- 0.12 1.22 +/- 0.08 Pass SW-601,602 - 2/1/2007 Gr. Beta 0.89 + 0.37 1.02 +/- 0.25 0.96 +/- 0.22 Pass DW-1138, 1139 2/9/2007 H-3 2707.00 +/- 161.00 2700.00 +/- 161.00 2703.50 +/- 113.84 Pass MI-721, 722 2/13/2007 K-40 1330.40 +/- 117.60 1316A0 +/- 116.50 1323.40 +/- 82.77 Pass SW-847, 848 2/13/2007 Gr. Alpha 3.82 +/- 1.67 2.61 +/- 1.24 3.22 +/-1.04 Pass SW-847, 848 2/13/2007 Gr. Beta 7.33 +/- 1.37 5.89 +/- 0.90 6.61 +/- 0.82 Pass DW-70175, 70176 2/14/2007 Gr. Alpha 11.72 +/- 1.68 8.84 +/- 1.32 10.28 +/- 1.07 Pass DW-70187, 70188 2/14/2007 Gr. Alpha 6.79 +/- 1.18 6.47 +/- 1.08 6.63 +/- 0.80 Pass SWU-1162,1163 2/27/2007 Gr. Beta 3.63 +/- 0.69 2.61 +/- 0,44 3.12 _0.41 Pass DW-70205, 70206 2/28/2007 Gr. Alpha 0.88 +/- 0.80 1.31 +/- 0.79 1.10 +/- 0.56 Pass PW-1117, 1118 3/1/2007 Gr. Alpha 3.79 +/- 1.91 3.62 +/- 2.09 3.71 - 1.42 Pass PW-1i17, 1118 3/1/2007 Gr. Beta. 7.12 +/- 1.40 7.20 +/- 1.39 7.16 +/- 0.99 Pass W-2122,2123 3/5/2007 .Gr. Alpha 6.10 +/- 4.16 3.80 +/- 4.30 4.95 +/- 2.99 Pass W-2122,2123 3/5/2007 Gr. Beta 10.65 +/- 2.15 13.11 +/- 2.42 11.88 +/-1.62 Pass W-2085,2086 3/6/2007 Gr. Alpha 2.51 +/- 2.29 1.10 +/- 2.78 1.81 +/- 1.80 Pass W-2085,2086 3/612007 Gr. Beta 11.02 +/- 1.85 9.50 +/- 2.01 10.26 +/- 1.37 Pass DW-70232, 70233 3/8/2007 Gr. Alpha 4.75 +/- 1.28 5.98 +/- 1.31 5.37 +/- 0.92 Pass WW-1477,1478 3/12/2007 Gr. Beta 6.41 +/- 1.48 4.10 +/-_1.25 5.26 00.97 Pass WW-1498,1499 3/15/2007 Gr. Beta 0.83 +/- 0.31 0.97 +/- 0.33 0.90 +/- 0.22 Pass W-2140,2141 3/19/2007 Gr. Alpha 2.31 +/- 1.57 1.33 +/- 1.64 1.82 +/- 1.14 Pass W-2140,2141 3/19/2007 Gr. Beta 4.26 +/- 1.00 5.58 +/- 1.02 4.92 +/- 0.71 Pass DW-1626,1627 3/21/2007 H-3 4973.00 +/- 209.00 5190.00 +/- 213.00 5081.50 +/- 149.21 Pass MI-1647, 1648 3/21/2007 K-40 1448.80 +/- 120.20 1439.30 +/- 126.00 1444.05 +/- 87.07 Pass DW-70248, 70249 3/21/2007 Gr.Alpha 11.10 +/- 1.18 9.90 +/- 1.16 10.50 +/- 0.83 Pass W-2150, 2151 3/26/2007 Gr, Alpha 3.56 +/- 2.20 3.30 +/- 1.81 3.43 +/- 1.42 Pass W-2150,2151 3/26/2007 Gr. Beta 9.26 +/- 1.00 10.17 +/- 1.90 9.72 +/- 1.07 Pass LW-1941, 1942 3/31/2007 Gr. Beta 1.35 +/- 0.43 1.36 +/- 0.41 1.36 +/- 0.30 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*

MI-1824, 1825 4/2/2007 K-40 1316.10 +/- 110.60 1229.80 +/- 110.50 .1272.95 +/- 78.17 Pass MI-1824, 1825 4/2/2007 Sr-90 1.20 +/- 0.50 1.10 +/- 0.36 1.15 +/- 0.31 Pass AP-21.70, 2171 4/2/2007 Be-7 0.08 +/-+0.01 0.08 +/- 0.01 0.08 +/- 0.01 Pass WW-1850, 1851

4/3/2007 H-3 -5.83 +/- 102.29 150.05 +/- 80:14 72.11 +/- 64.97 Pass AP-2198, 2199 4/3/2007 Be-7 0.08 + 0.01 0.08 +/- 0.01 0.08 +/- 0.01 Pass AP-2370, 2371 4/3/2007 Be-7 0.07 +/- 0.01 0.07 _ 0.01 0.07 +/- 0.01 Pass DW-70300, 70301 4/4/2007 Gr. Alpha 3.78 00.89 3.66 +/- 0.96 3.72 +/- 0.65 Pass DW-70300, 70301 4/4/2007 Gr. Beta 2.93 +/- 0.61 2.91 +/- 0.64 2.92 +/- 0.44 Pass DW-70335, 70336 4/5/2007 Gr. Alpha 24.37 +/- 2.89 22.72 +/- 2.91 23.55 +/- 2.05 Pass DW-70335, 70336 4/5/2007 Gr. Beta .20.26 1.37 18.33 +/- 1.34 19.30 +/- 0.96 Pass SW-1898, 1899 4/10/2007 Gr. Alpha 3.86 +/- 1.40 4.78 +/- 1.51 4.32 +/- 1.03 Pass SW-1 898, 1899 4/10/2007 Gr. Beta 6.31 +/- 1.36 7.03 +/- 1.42 6.67 +/- 0.98 Pass SW- 898, 1899 4/10/2007 H-3 241.99 +/- 93.35 318.10 +/- 96.48 280.04 +/- 67.12 Pass DW-70346, 70347 4/11/2007 Gr. Alpha 1.83 +1.08 2.54 +/- 1.04 2.19 +/- 0.75 Pass DW-70346, 70347 4/11/2007 Gr. Beta 4.62 +/- 0:72 4.01 +/- 0.71 4.32 +/- 0.51 Pass DW-70376, 70377 4/11/2007 Gr. Alpha 1.81 +/- 0.80 1.66 +/- 0.86 1.74 +/- 0.59 Pass DW-70376, 70377 4/11/2007 Gr. Beta 1.84 +/- 0.62 2.24 +/- 0.61 2.04 +/- 0.44 Pass DW-70311, 70312 4/12/2007 Gr. Alpha 10.82 +/-1.50 13.20 +/- 1.56 12.01 +/- 1.08 Pass WW-2349, 2350 4/17/2007 Gr. Alpha 0.71 +/- 0.56 0.62 +/- 0.52 0.66 +/- 0.38 Pass WW-2461, 2462 4/25/2007 H-3 190.30 +/- 100.31 115.95 +/- 97.65 153.13 +/- 70.00 Pass LW-2437,2438 4/26/2007 Gr. Beta 2.71 +/- 0.50 2.15 +/- 0.45 2.43 +/- 0.34 Pass LW-2917, 2918 4/30/2007 Gr. Beta 1.97 +/- 0.79 2.78 +/- 0.81 2.38 +/- 0.57 Pass SO-2583, 2584 5/1/2007 Be-7 544.99 +/- 247.70 601.13 +/- 192.20 573.06 +/- 156.76 Pass SO-2583,2584 5/1/2007 Cs-1 37 119.22 +/- 36.61 87.46 +/- 23.97 103.34 +/- 21.88 Pass SO-2583, 2584 5/1/2007 K-40 17825.00 +/- 749.90 17672.00 +/- 724.30 17748.50 +/- 521.29 Pass SO-2583, 2584 5/1/2007 Gr. Alpha 11.49 +/- 3.96 8.04 +/- 3.88 9.7.7 +/- 2.77 Pass SO-2583,2584 5/1/2007 Gr. Beta 31.02 +/- 3.74 26.10 +/- 3.40 28.56 +/- 2.53 Pass SO-2583,2584 5/1/2007 Sr-90 0.086 +/- 0.024 0.068 +/- 0.025 0.077 +/- 0.017 Pass S-2620, 2621 5/2/2007 H-3 277.90 +/- 126.70 304.40 +/- 101.00 291.15 +/- 81.02 Pass MI-2610, 2611 5/3/2007 K-40 1549.20 +/- 184.20 1388.80 +/- 128.20 1469.00 +/- 112.21 Pass W-4469,4470 5/7/2007 Gr. Beta 10.60 +/- 1.90 11.10 +/- 1.80 10.85 +/- 1.31 Pass SS-2697, 2698 5/8/2007 Cs-137 0.06 +/- 0.02 0.05 +/- 0.03 0.05 +/- 0.02 Pass SS-2697, 2698 5/8/2007 K-40 8.03 +/- 0.57 7.36 +/- 0.68 7.70 +/- 0.44 Pass MI-2790, 2791 5/14/2007 K-40 1694.30 +/- 126.20 1627.60 +/- 128.80 1660.95 +/- 90.16 Pass W-4505,4506 5/14/2007 Gr. Beta 3.30 +/- 1.70 3.90 +/- 1.50 3.60 +/- 1.13 Pass DW-3219, 3220 5/26/2007 1-131 0.62 +/- 0.32 .0.69 +/- 0.31 0.66 +/- 0.22 Pass SO-3416, 3417 5/31/2007 Cs-1 37 0.15 +/- 0.03 0.15 +/- 0.03 0.15 +/- 0.02 Pass SO-3416, 3417 5/31/2007 Gr. Beta 22.88 +/- 2.33 22.46 +/- 2.37 22.67 +/- 1.66 Pass SO-3416, 3417 5/31/2007 K-40 12.26 +/- 0.80 12.36 +/- 0.65 12.31 +/- 0.52 Pass F-3561, 3562 5/31/2007 K-40 3.06 +/- 0.39 3.37 +/- 0.45 3.21 +/- 0.30 Pass SL-3311, 3312 6/4/2007 Be-7 0.61 +/- 0.29 0.55 +/- 0.25 0.58 +/- 0.19 Pass SL-3311, 3312 6/4/2007 K-40 5.78 +/- 0.67 4.87 +/- 0.25 5.33 +/- 0.36 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 SL-3992, 3993 6/4/2007 Be-7 0.75 +/- 0.19 0.74 +/- 0.32 0.75 +/- 0.19 Pass SL-3992, 3993 6/4/2007 Gr. Beta 13.61 +/- 1.12 14.06 +/- 1.08 13.84 +/- 0.78 Pass

-SL-3992, 3993 6/4/2007 K-40 2.43 +/- 0.36 2.29 +/- 0.40 2.36 +/- 0.27 Pass W-5087, 5088 .6/11/2007 Gr. Beta 8.70 +/- 1.90 7.70 +/-_1.90 8.20 +/- 1.34 Pass SW-3710, 3711 6/14/2007 H-3 9571.51 +/- 287.22 9879.21 +/- 291.42 9725.36 +/- 204.59 Pass W-4062, 4063 6/28/2007 Gr. Alpha 0.76 +/- 0.63 0.32 +/- 0.66 0.54 +/- 0.45 Pass W-4062, 4063 6/28/2007 Gr. Beta 0.97 +/- 0.53 0.58 +/- 0.57 0.78 +/- 0.39 Pass AP-4448, 4449 6/28/2007 Be-7 0.10 +/- 0.02 0.09 +/- 0.02 0.10 +/- 0.01 Pass SG-3735, 3736 6/30/2007 Be-7 0.84 +/- 0.12 0.82 +/- 0.18 0.83 +/- 0.11 Pass SG-3735, 3736 6/30/2007 Cs-137 0.07 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 Pass SG-3735, 3736 6/30/2007 Gr. Beta 29.51 +/- 2.22 30.81 +/- 2.22 30.16 +/- 1.57 Pass SG-3735, 3736 6/30/2007 K-40 9.41 +/- 0.31 8.90 +/- 0.48 9.16 +/- 0.29 Pass LW-4175, 4176 6/30/2007 Gr. Beta 2.18 +/- 0.60 1.93 +/- 0.68 2.06 +/- 0.45 Pass SG-5422, 5423 7/2/2007 Gr. Alpha 10.31 +/- 1.98 10.57 +/- 1.99 10.44 +/- 1.40 Pass SG-5422, 5423 7/2/2007 Gr. Beta 18.59 +/- 1.46 20.97 +/- 1.49 19.78 +/- 1.04 Pass AP-4656, 4657 7/3/2007 Be-7 0.09 +/- 0.02 0.10 +/- 0.02 0.10 +/- 0.01 Pass AP-4763, 4764 7/3/2007 Be-7 0.11 +/- 0.02 0.10 +/- 0.02 0.11 +/- 0.01 Pass SG-5430, 5431 7/11/2007 Be-7 10.17 +/- 0.48 10.06 +/- 0.51 10.12 +/- 0.35 Pass SG-5430, .5431 7/11/2007 Cs-137 0.050 +/- 0.010 0.059 +/- 0.011 0.055 +/- 0.007 Pass SG-5430, 5431 7/11/2007 Gr. Alpha 17.86 +/- 2.78 15.74 +/- 2.70 16.80 +/- 1.94 Pass SG-5430, 5431 7/11/2007 Gr. Beta 26.19 +/- 1.74 25.04 +/- 1.86 25.62 +/- 1.27 Pass SG-5430, 5431 7/11/2007 K-40 7.69 +/- 0.30 7.65 +/- 0.28 7.67 +/- 0.21 Pass WW-4298, 4299 7/12/2007 Gr. Beta 1.74 +/- 0.74 2.22 +/- 0.80 1.98 +/- 0.55 Pass DW-70612, 70613 7/23/2007 Gr. Alpha 4.54 +/- 1.11 4.19 +/- 0.97 4.37 +/- 0.74 Pass WW-4918, 4919 7/25/2007 H-3 240.43 +/- 111.12 216.68 +/- 110.27 228.56 +/- 78.27 Pass MI-4742, 4743 7/26/2007 K-40 1820.30 +/- 134.10 1802.90 +/- 199.50 1811.60 +/- 120.19 Pass VE-4939, 4940 8/1/2007 Be-7 0.39 +/- 0.21 0.45 +/- 0.20 0.42 +/- 0.15 Pass VE-4939, 4940 8/1/2007 Gr. Beta 5.50 +/- 0.14. 5.76 +/- 0.13 5.63 +/- 0.10 Pass VE-4939, 4940 8/1/2007 K-40 3.36 +/- 0.45 3.36 +/- 0.21 3.36 +/- 0.25 Pass SG-6274, 6275 8/6/2007 Gr. Alpha 16.68 +/- 3.29 19.26 +/- 3.39 17.97 +/- 2.36 Pass SG-6274, 6275 8/6/2007 Gr. Beta 40.93 +/- 2.74 42.42 +/- 2.66 41.68 +/- 1.91 Pass SW-5218, 5219 8/7/2007 1-131 1.31 +/- 0.24 1.42 +/- 0.24 1.37 +/- 0.17 Pass SG-6284, 6285 8/8/2007 Cs-1 37 0.043 +/- 0.006 0.051 +/- 0.007 0.047 +/- 0.005 Pass SG-6284, 6285 8/8/2007 Gr. Alpha 9.38 +/- 2.93 13.61 -+/- 3.38 .11.50 +/- 2.24 Pass SG-6284, 6285 8/8/2007 Gr. Beta 33.46 +/- 2.84. 32.87 +/- 2.93 33.17 +/- 2.04 Pass SG-6284, 6285 8/8/2007 K-40 16.15 +/- 0.24 16.23 +/- 0.25 16.19 +/- 0.17 Pass WW-5310, 5311 8/9/2007 H-3 644.00 +/- 106.00 831.00 +/- 113.00 737.50 +/- 77.47 Pass SW-5393, 5394 8/14/2007 Gr. Beta 2.32 +/- 1.31 1.71 +/- 1.27 2.02 +/- 0.92 Pass SW-5393, 5394 8/14/2007 H-3 190.06 +/- 86.80 69.05 +/- 80.88 129.55 +/- 59.32 Pass W-5468, 5469 8/15/2007 H-3 262.58 +/- 108.43 346.53 +/- 111.42 304.55 +/- 77.74 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 VE-5553, 5554 8/22/2007 K-40 1.89 +/- 0.33 1.89 +/- 0.22 1.89 +/- 0.20 Pass WW-5643, 5644 8/22/2007. H-3 259.00 +/- 110.00 266.00 +/- 110.00 .262.50 +/- 77.78 Pass SWU-5799, 5800 8/28/2007 Gr. Beta 2.64 +/- 1.18 3.62 +/-.1.06 3.13 +/- 0.79 Pass DW-70752, 70753 8/31/2007 Gr. Alpha 14.41 + 1.48 12.90 +/- 1.50

13.66 +/- 1.05 Pass VE-5917, 5918 9/4/2007 Be-7 0.94 +/- 0.17 0.83 +/- 0.20 0.89 +/- 0.13 Pass VE-5917, 5918 9/4/2007 K-40 3.73 0.37 3.58 +/- 0.36 3.66 +/- 0.26 Pass VE-5917, 5918 9/4/2007 Gr. Beta 2.71 + 0.10 2.69 +/- 0.10 2.70 +/- 0.07 Pass MI-6009, 6010 9/11/2007 K-40 1348.90 +/-113.40 1388.10 +/- 116.40 1368.50 +/- 81.25 Pass MI-6030, 6031 9/12/2007 K-40 1242.70 + 118.00 1475.60 +/- 119.60 1359.15 +/- 84.01 Pass MI-6030, 6031 9/12/2007 Sr-90 1.00 +/- 0.38 0.90 +/- 0.34 0.95 +/-0.26 Pass DW-70718, 70719 9/12/2007 Gr. Alpha 23.04 +/- 3.71 23.22 +/- 3.61 23.13 - 2.59 Pass DW-70718, 70719 9/12/2007 Gr. Beta 16.13 +/- 1.59 17.36 +/- 1.69 16.75 +/- 1.16 Pass SO-6156, 6157 9/14/2007 H-3 181.99 +/- 90.67 232.19 +/- 92.95 207.09 - 64.92 Pass SO-6484, 6485 9/17/2007 Cs-1 37 0.01 +/- 0.00 0.01 + 0.00 0.01 + 0.00 Pass SO-6484, 6485 9/17/2007 Gr. Beta 24.20 +/- 2.60 23.30 +/- 2.30 23.75 - 1.74 Pass SO-6484, 6485 9/17/2007 K-40 11.52 +/- 1.16 10.89 +/- 1.10 11.20 +/- 0.80 Pass WW-6469, 6470 9/21/2007 Gr. Beta 27.19 +/- 2.51 24.23 + 2.29 25.71 - 1.70 Pass E-6647, 6648 10/1/2007 Gr. Beta 1.82 +/- 0.10 1.93 +0.11 1.88 +/- 0.07 Pass E-6647, 6648 10/1/2007 K-40 1.48 +/- 0.24 1.31 +/- 0.23 1.40 +/- 0.17 Pass WW-6656, 6657 10/1/2007 Gr. Beta 2.80 +/- 0.97 1.95 - 0.87 2.38 +/- 0.65 Pass TD-7080, 7081 10/2/2007 H-3 332.00 +/- 229.00 383.00 - 191.00 357.50 +/- 149.10 Pass SG-6891, 6892 10/3/2007 Gr. Alpha 12.93 +/- 2.12 13.52 +/- 2.07 13.23 +/- 1.48 Pass SG-6891, 6892 10/3/2007 Gr. Beta 18.08 +/-+1.41 18.27 +/- 1.36 18.18 +/- 0.98 Pass AP-7191, 7192 10/3/2007 Be-7 0.09 +/- 0.01 0.09 0.01 0.09 +/- 0.01 Pass WW-6786, 6787 10/8/2007 H-3 13333 +/- 322 13532 +/-324 13433 +/-228 Pass WW-6786, 6787 10/8/2007 H-3 13188 +/- 322 13556 +/- 326 13372 +/-229 Pass VE-6828, 6829 10/8/2007 Gr. Alpha 0.06 +/- 0.04 0.06 +/- 0.05 0.06 +/- 0.03 Pass VE-6828, 6829 10/8/2007 Gr. Beta 5.55 +/- 0.21 .5.20 +/- 0.22 5.38 +/- 0.10 Pass VE-6828, 6829 10/8/2007 K-40 5.45 +/- 0.43 5.20 +/- 0.49 5.32 +/- 0.33 Pass SS-6870, 6871 10/9/2007 Gr. Beta 18.10 +/- 2.08 21.71 +/- 2.19 19.90 +/- 1.51 Pass SS-6870, 6871 10/9/2007 K-40 10.19 +/- 0.66 9.72 +/- 0.68 9.95 +/- 0.47 Pass LW-7507, 7508 10/11/2007 Gr. Beta 1.40 +/- 0.56 1.44 +/- 0.54 1.42 +/- 0.39 Pass MI-6933, 6934 10/16/2007 K-40 :1386.60 +/- 104.70 1331.20 +/- 106.70 1358.90 +/- 74.74 Pass MI-6933, 6934 10/16/2007 Sr-90 1.73 + 0.52 2.17 +/- 0.57 1.95 + 0.39 Pass MI-7059, 7060 10/17/2007 K-40 1424.80 + 106.60 1448.60 +/- 115:30 1436.70 +/- 78.51 Pass F-7213, 7214 10/24/2007 H-3 6.83 + 0.22 7.24 +/- 0.22 7.03 +/- 0.16 Pass F-7213, 7214 10/24/2007 K-40 3.13 + 0.51 3.16 +/- 0.48 3.15 + 0.35 Pass WW-7408, 7409 10/24/2007 H-3 340.71 +/- 90.45 346.22 +/- 90.67 343.46 + 64.03 Pass DW-70856, 70857 10/24/2007 Gr. Alpha 11.03 +/- 1.66 10.71 +/- 1.34 10.87 +/- 1.07 Pass SO-7508, 7509 10/26/2007 Cs-1 37 0.30 + 0.04 0.29 +/- 0.05 0.29 +/- 0.03 Pass SO-7508, 7509 10/26/2007 Gr. Beta 34.43 +/-2.72 37.25 +/- 3.07 35.84 +/- 2.05 Pass SO-7508, 7509 10/26/2007 K-40 16.84 _ 0.84 17.43 +/- 1.05 17.14 + 0.67 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 SS-7529, 7530 10/29/2007 Cs-1 37 0.12 +/- 0.03 0.12 +/- 0.02 0.12 +/- 0.02 Pass SS-7529,7530 10/29/2007 K-40 11.85 +/-+0.68 11.75 +/- 0.58 11.80 +/- 0.45 Pass SW-7589, 7590 10/30/2007 Gr. Beta 1.75 +/- 0.29 1.24 +/- 0.26 1.50 +/- 0.19 Pass SWU-7733, 7734 10/30/2007 Gr. Beta 1.66 +/- 1.01 2.43 +/- 1.13 2.05 +/- 0.76 Pass MI-7618, 7619 10/31/2007 K-40 1376.80 +/- 114.30 1426.70 +/- 128.80 1401.75 +/- 86.10 Pass VE-7666, 7667 11/5/2007 Gr. Alpha 0.07 +/- 0.04 0.16 +/- 0.05 -0.11 +/- 0.03 Pass VE-7666, 7667 11/5/2007 Gr. Beta 6.03 +/- 0.15 6.13 +/- 0.15 6.08 +/- 0.10 Pass VE-7666, 7667 11/5/2007 K-40 5.82 +/- 0.36 5.74 +/- 0.36 5.78 +/- 0.25 Pass DW-7853, 7854 11/9/2007 1-131 1.61 +/- 0.40 1.08 +/- 0.39 1.35 +/- 0.28 Pass MI-7874, 7875 11/14/2007 K-40 1407.70 +/- 101.30 1362.60 +/- 114.50 1385.15 +/- 76.44 Pass WW-8142,8143 11/28/2007 Gr. Beta 9.51 +/- 2.21 7.86 +/- 2.01 8.68 +/- 1.49 Pass DW-8094, 8095 11/29/2007 Gr. Beta 1.60 +/- 0.58 1.25 +/- 0.54 1.43 +/- 0.40 Pass F-8328, 8329 12/11/2007 Gr. Beta 3.97 +/- 0.08 4.00 +/- 0.08 3.99 +/- 0.05 Pass WW-8378,8379 12/11/2007 H-3 296.00 +/- 103.00 407.00 +/- 107.00 351.50 +/- 74.26 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

TABLEA-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-1110 01/01/07 Gr. Alpha 0.45 +/- 0.08 0.33 0.00 -0.65 Pass STW-1110 01/01/07 Gr. Beta 0.90 +/- 0.14 0.85 0.43-1.28 Pass STW-1111 01/01/07 Am-241 .2 80 +/- 0.21 1.71 1.20 -2.22 Fail STW-i1111 01/01/07 Co-57 151.60 +/- 10.00 143.70 100,60 - 186.80 Pass STW-1111 01/01/07 Cs-134 79.20 +/- 8.00 83.50 58.50 - 108.60 Pass STVV-1111 01/01/07 Cs-137 168.70 +/- 12.10 163.00 114.10 -211.90 Pass STW-1111 01/01/07 Fe-55 130.30 +/- 19.90 129.30 90.50 -168.10 Pass STW-1111 01/01/07 H-3 262.20 +/-.9.10 283.00 198.10 - 367.90 Pass STW-I-111i 01/01/07 Mn-54 130.60 +/- 11.50 123.80 86.70 - 160.90 Pass STW-1111 01/01/07 Ni-63 127.80 +/- 3.60 130.40 91.30 - 169.50 Pass STW-1111 01/01/07 Ni-63 127.80 +/- 3.60 130.40 91.30 - 169.50 Pass STW-1111 01/01/07 Pu-238 2.03 + 0.17 2.25 1.58 -2.93 Pass STWV-1111 01/01/07 Pu-239/40 2.27 +/- 0.17 2.22 1.55 -2.89 Pass STW-1111 01/01/07 Sr-90 9.60 +/-1.40 8.87 621 - 11.53 Pass STW-1111 01/01/07 Tc-99 8.80 +/- 1.50 88.00 7.40 - 13.70 Pass STW-1111 01/01/07 U-233/4 2.44 +/- 0.21 2.49 1.74 -3.24 Pass STW-1111 .01/01/07 U-238 2.44 +/- 0.21 2.48 1.74 -3.22 Pass STW-1111 01/01/07 Zn-65 123.70 +/- 17.00 114.80 80.40 -149.20 Pass STSO-1112 01/01/07 Am-241 46.40 _ 9.00 34.80 24.40 -45.20 Fail STSO-1 112 01/01/07 Co-57 501.20 +/- 2.90 471.20 329.80 -612.60 Pass STSO-1 112 01/01/07 Co-60 285.90 +/- 2.10 274.70 192.30 -357.10 Pass STSO-1 112 01/01/07 Cs-1 34 325.90 +/- 7.40 327.40 229.20 -425.60 Pass STSO-1 112 01/01/07 Cs-i 37 855.70 +/- 4.60 799.70 559.80 - 1039.60 Pass STSO-1 112 01/01/07 Mn-54 750.90 +/- 4.70 685.20 479.60 -890.80 Pass STAP-1 113 01/01/07 Gr. Alpha 0.27 +/- 0.04 0.60 0.00- 1.20 Pass STAP-1 113 01/01/07 -Gr. Beta 0.57 +/- 0.05 0.44 0.22 - 0.66 Pass STAP-1 114 01/01/07 Am-241 0.10 +/- 0.03 0.10 0.07 -0.13 Pass STAP-1 114 01/01/07 Co-57 3.51 +/- 0.07 2.89 2.02 - 3.75 Pass STAP-1 114 01/01/07 Co-60 2.98 +/- 0.10 2.91 2.03 - 3.78 Pass STAP-1 114 01/01/07 Cs-1 34 4.02 +/- 0.16 4.20 2.94 - 5.45 Pass STAP-1 114 01/01/07 Cs-I37 2.75 +/- 0.12 2.57 1.80 -3.34 Pass STAP-1 114 01/01/07 Mn-54 3.94 +/- 0.12 3.52 2.46 -4.57 Pass STAP-1 114 01/01/07 Pu-238 0.07+/- 0.01 0.07 0.05 - 0.09 Pass STAP-1 114 01/01/07 Pu-239/40 0.08 +/- 0.01 0.08 0.06 -0.11 Pass STAP-1 114 01/01/07 Sr-90 0.58 +/- 0.18 0.61 0.43 - 0.79 Pass STAP-1 114 01/01/07 U-233/4 0.09 +/- 0.01 0.10 0.07 - 0.13 Pass STAP-1 114 01/01/07 U-238 0.09 +/- 0.01 0.10 0.07 -0.13 Pass STAP-1 114 01/01/07 Zn-65 2.70 +/- 0.10 2.68 1.88 - 3.49 Pass A6-1

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

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STVE-1 115 01/01/07 Co-57 8.90 +/- 0.20 8.19 5.73 - 10.64 Pass STVE-1115 01/01/07 Co-60 6.50 +/- 0.20 5.82 4.08 - 7.57 Pass STVE-1115 01/01/07 Cs-1 34 6.90 +/- 0.30 6.21 4.35 - 8.07 Pass STVE-1 115 01/01/07 Cs-137 8.20 +/- 0.30 6.99 4.90 - 9.09 Pass STVE-1 115 01/01/07 Mn-54 10.10 +/-0.30 8.46 5.91- 10.98 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 Result of reanalysis, 2.08 +/- 0.13 pCi/L.

f The test samples were recounted on lower background detectors. Result of the recounts: 41.4 +/- 6.3 Bq/kg.

A6-2

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

Concentration (pCi/L)

Lab Code b Date Analysis Laboratory ERA Control Result c Result a Limits Acceptance STAP-1 116 03/19/07 Gr. Alpha 34.64+/- 2.56 25.8 12.4 -39 Pass STAP-1116 03/19/07 Gr. Beta 93.41 +/- 3.20 79.5 48.8 -116 Pass STAP-1l117 03/19/07 Am-241 *56.04 +/- 3.90 57.5 33.1 -80 Pass STAP-1 117 03/19/07 Co-60 1610.00 +/- 8.40 1300.0 1010.0 -1620 Pass STAP-1 117 03/19/07 Cs-1 34 1340.40 +/- 48.84 1120.0 732.0 -1380 Pass STAP-1117e 03/19/07 Cs-137 345.30 +/- 8.20 255.0 192.0 -336 Fail STAP-1117' 03/19/07 Fe-55 < 134.0 0.0 Pass STAP-1117' 03/19/07 Mn-54 < 5.0 0.0 Pass STAP-1 117 03/19/07 Pu-238 43.32 +/- 2.28 37.4 25.7-49 Pass STAP-l 117 03/19/07 Pu-239/40 35.23 +/- 2.24 31.6 22.9 -41 Pass STAP-l 117 03/19/07 Sr-90 156.10 +/- 6.60 156.0 66.6 - 246 Pass STAP-1 117 03/19/07 U-233/4 42.22 +/- 1.84 47.8 30.1 -71 Pass STAP-i 117 03/19/07 U-238 42.00 +/- 1.84 *47.4. 30.2 - 68 Pass STAP-1 117 03/19/07 Uranium 85.79 +/- 3.60 97.3 49.5 - 155 Pass STAP-1 117 03/19/07 Zn-65 363.80 +/- 11.90 245.0 208.0 -412 Pass STSO-1 1 18 03/19/07 Ac-228 3097.77 +/- 94.96 2790.0 1790.0 -3930 Pass STSO-1 118 03/19/07 Am-241 1000.70 +/- 156.10 927.0 548.0 -1200 Pass STSO-1 118 03/19/07 Bi-212 2467.87 +/- 114.33 2500.0 658.0 -3730 Pass STSO-1 118 03/19/07 Co-60 7847.40 +/- 86.60 7330.0 5340.0 -9820 Pass STSO-1 118 03/19/07 Cs-1 34 7910.60 +/- 356.88 7560.0 4850.0 -9070 Pass STSO-1 118 03/19/07 Cs-1 37 4635.00 +/- 99.10 4300.0 3290.0 -5580 Pass STSO-1118 03/19/07 K-40 12201.60 +/- 423.20 11100.0 8050.0 -15000 Pass STSO-1118 f 03/19/07 Mn-54 < 34.0 0.0 Pass STSO-1 118 ,03/19/07 Pb-212 2046.80 +/- 127.20 1730.0 .1120.0 -2430 Pass STSO-1 118 03/19/07 Pb-214 4142.80 +/- 110.40 3330.0 1980.0 -4980 Pass STSO-1118 03/19/07 Pu-238 1099.20 +/- 73.10 857.0 490.0 -1200 Pass STSO-1 118 03/19/07 Pu-239/40 1586.10 +/- 82.00 1360.0 928.0 -1810 Pass STSO-1 118 03/19/07 Sr-90 6163.30 +/- 791.60 7500.0 2610.0 -12400 Pass STSO-1 118 03/19/07 Th-234 4329.40 +/- 569.10 3590.0 2190.0 -4560 Pass STSO-1 118 03/19/07 U-233/4 3236.70 +/- 106.00 3620.0 2280.0 -4520 Pass STSO-1 118 03/19/07 U-238 3425.20 +/- 134.00 3590.0 2190.0 -4560 Pass STSO-1 118 03/19/07 Uranium 6787.80 +/- 240.00 7380.0 4210.0 -9930 Pass STSO-1 118 03/19/07 Uranium 6787.80 +/- 240.00 7380.0 4210.0 -9930 Pass STSO-1118' 03/19/07 Zn-65 0.00 +/- 0.00 0.0 0.0 -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 c Result d Limits Acceptance STVE-1 119 .03/19/07 Am-241 3249.60 +/- 150.30 3550.0 2020.0 -4890 Pass STVE-1119 03/19/07 Cm-244 1860.70 +/- 91.50 1840.0 905.0 -2870 Pass STVE-1 119 03119/07 Co-60 2827.90 +/- 62.40 2600.0 1760.0 -3720 Pass STVE-1119 03/19/07 Cs-1 34 654.80 +/- 48.40 579.0 308.0 -822 Pass, SSTVE-1119 03/19/07 Cs-137 3307.30 +/- 58.80 2920.0 2150.0 -4060 Pass STVE-1 119 03/19/07 K-40 40814.20 +/- 618.80 37900.0 27200.0 -53600 Pass SIVE-1i119 03/19/07 Mn-54 < 27.6 0.0 Pass STVE-1 119 03/19/07 Pu-238 2762.00 +/- 251.10 2430.0 1250.0 -3600 Pass STVE-1 119 03/19/07 Pu-239/40 2156.60 +/- 83.40 1900.0 1180.0 -2600 Pass STVE-1119 03/19/07 Sr-90 8999.70 +/- 580.90 8890.0. 4900.0 -11800 Pass STVE-1 119 03/19/07 U-233/4 2821.90 +/- 73.50 2940.0 1930.0 -3920 Pass STVE-1 119 03/19/07 U-238 2896.10 +/- 50.70 2910.0 2090.0 -3610 Pass STVE-1119 03/19/07 Uranium 5718.00 +/- 124.15 5980.0 4110.0 -7770 Pass STVE-1 119 03/19/07 Zn-65 474.30 +/- 45.70 366.0 267.0 -500 Pass STW-1 120 03/19/07 Am-241 133.50 +/- 10.60 179.0 -123.0 -243 Pass STW-1 120 03/19/07 Co-60 541.40 +/- 9.00 536.0 467.0 -631 Pass STW-1 120 03/19/07 Cs-1 34 1623.80 +/- 66.10 1750.0 1290.0 -2020 Pass STW-1 120 03/19/07 Cs-1 37 1839.10 +/- 17.90 1850.0 1570.0 -2220 Pass STW-1 120 03/19/07 Fe-55 829.50 +/- 226.80 671.0 392.0 -896 Pass STW-1 120' 03/19/07 Mn-54 <8.1 0.0 Pass STW-1 120 03/19/07 Pu-238 123.30 +/- 4.30 116.0 87.6 -144 Pass STW-1 120 03/19/07 Pu-239/40 95.10 +/- 3.80 90.9 70.3-113 Pass STW-1 120 03/19/07 Sr-90 949.40 +/- 16.70 989.0 630.0 -1320 Pass STW-1 120 03/19/07 U-233/4 164.20 +/- 6.58 192.0 145.0 -247 Pass STW-1 120 03/19/07 U-238 169.20 +/- 8.22 190.0 145.0 -236 Pass STW-1 120 03/19/07 Uranium 339.60 +/- 10.66 391.0 282.0 -521 Pass STW-1120 03/19/07 Zn-65 2009.00 +/- 36.40 1910.0 1600.0 -2410 Pass 8 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 previouslyby the Environmental Measurements Laboratory Quality Assessment Program (EML).

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

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 A high bias (- 20%) was observed in gamma results for air filters. A composite filter geometry was used in the calculations vs. a single filter geometry. Result of recalculation. Cs-137, 305.8 +/- 6.0 pCi/filter.

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

A7-2

APPENDIX B DATA REPORTING CONVENTIONS B-1

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

2.0. Single Measurements.

Each single measurement is reported as follows: x +s where: x= value of the measurement; s = 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 1 and x2 +s 2 Reported result: x _s; where x= (1/2) (x,+x 2)ands (1/2)2S2 +S 2 3.2. Individual results: < L1 , < L2 Reported result: < L, where L = lower of Li and L2 3.3. Individual results: x +/- s, < L Reported result: x +/- s if x > L; < L otherwise.

4.0. Computation of Averaqes and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x1 , x 2 . . . xn are defined as follows:

x =n Zx n-1 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-i. Maximum permissible concentrations of radioativity in air and water above natura.

background in unrestricted areas a Air (pci/m 3) Water (pCi/L)

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

Iodine-1 31 2.8x 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 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.

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

C IA natural radionuclide.

C-2

APPENDIX D Sampling Location Maps

TLD LOCAT.IONS ONE MILE RADIUS E

PLANT AREA ENLARGED PLAN 11.00 MILE RADIUS]

[NO SCALE)

MONITORING LEGEND:

0 PRAIRIE ISLAND TLD POINTS REV. I D*2' TLD0I'.DGN r

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

0 PRAIRIE. ISLAND TLD POINTS REV, I D-3 TLD02.DGN REV. 1 D-3 TLD~2.OGN

TLD. LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:

PRAIRIE ISLAND TLD POINTS

.REV, .1 D.-4 TLD03.DGN REV. .1 D4 TLD~3.DON

ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS

.E PLANT AtREA~ ENLA~RGED PLAN [1.0 MILE RADIUS3 (NO :SCALE]

MONITORING: LEGEND

( MILK SAMPLING POINT 10 NUMBERS FISH SAMPLING POINT ID NUMBERS P-14. Pý.-l, P-37,.RP.42. P-43, p-44 P-13, P-14 A AIR SAMPLING POINT ID NUMBERS P-I.IP-4 P-3,. P-4. P-6

.INVERTEBRATES POINT iD NUMBERS P-6, P-40

- WATER SAMPLING. POINT ID NUMBERS .SEDIMENT SAMPLING: POINT ID NUMBERS OP-S. P-6.,P-B. P-9. P-Il. P-24. P-43. P4*. P*'12, Fý20 El VEGETATION / VEGETABLES 10 NUMBERS P-24,. P-38, P-45 REV. I D-5 SAMPOLDGN 0-5 S~MP01.DGN

ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS MONITORING LEGEND MILK SAMPLING POINT 10 NUMBERS FISH SAMPLING POINT ID NUMBERS P.I4,.P-"I, P-37. P-42, P-43, P;-44 :P-13. P-Iq AIR SAMPLING POINT 10 NUMBERS INVERTEBRATES POINT i1 NUMBERS P- Z.

P-2.Pý3, P-4, P-6 P-G, P-40 G p-5. P-G,SAMPLING WATER P P-ý, P-'q,POINT ID NUMBERS P:-11. P-214, P;43 SEDIMENT SAMPLING POINT 10 NUMBERS P-G..P-I2, P-20 VEGETATION I VEGETABLES ID. NUMBERS

.,,24,P-38P-45 REV; 1: SAMP03,DON REV, 1 o~6

ENVIRONMENTAL SAMPLING POINTS P-"

-P41, Huppert Farm, W10430 St Rd 29, River Falls, WI P-43, Paterson Farm, W10322 St Rd 29, River Falls, WI 8 P-38, Cain Residence, N7395 950th St, River Falls, WI CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND

< MILK SAMPPUNG POINT ID NUMBERS P-14, P-18, P-37, P-41, P.42, P-43, P44 A AIR SAMPLING POINT ID NUMBERS P-1, P-2, P-A, P4 P-WATER SAMPLING POINT IDNUMBERS

P-4, P-4, P-8, P-4, P1I, P-43 8 VEGETATION I VEGETABLES IDNUMBERS P-24, P-38, P45 0-7

APPENDIX E Special Well and Surface Water Samples E-1

1.0 INTRODUCTION

This appendix to the Radiation Environmental Monitoring Program Annual Report to the United States Nuclear Regulatory Commission summarizes and interprets results of the special well and surface water samples taken at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December, 2007. This supplemental special sampling program was established in December of 1989 when higher than expected levels of tritium were detected in a nearby residence well sample.

Tabulations of the special sampling program individual analyses made during the year are included in this appendix. A summary table of tritium analyses is also included in this appendix.

E-2

2.0

SUMMARY

This special sampling program was established following the detection of tritium in a residenc6 well water sample south of the PINGP during 1989. This program is described and the results for 2007 are summarized and discussed.

Program findings for 2007 detect low levels of tritium in nearby residence wells and ground water surface samples at or near the expected natural background levels with the exception of sample well P-10. The 2007 sample results (except for P-10) ranged from <19 pCi/L to 513 pCi/L and sample well P-10 ranged from 390 pCi/L to 2258 pCi/L. All tritium results are far below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L and present no harm to any members of the public.

E-3

3.0 Special Tritium Sampling Program 3.1 Program Design and Data Interpretation The purpose of this sampling program is to assess the impact of any tritium leaching into the environment (ground water system) from the PINGP. For this purpose, special water samples are collected and analyzed for tritium content.

3.2 Program Description The sampling and analysis schedule for the special water sampling program is summarized in Table 4.1 and briefly reviewed below. Table 4.2 defines the additional sample locations and codes for the special water sampling program.

Special well and surface water samples were collected quarterly at one location and monthly at five locations, and annually at thirty-two locations. The Peterson (P-43) and Hanson (SW-1) farm wells are used as control locations for these special samples.

To detect low levels of tritium at or below natural background levels, analyses of the samples have been contracted to a laboratory (University of Waterloo Laboratories) capable of detecting tritium concentrations down to 19 pCi/L. Waterloo Laboratories report tritium analyses results in Tritium Units (1 TU = 3.2 pCi/L). The tritium results in this report are indicated in pCi/L.

3.3 Program Execution The special water sampling was executed as described in the preceding section.

3.4 Program Modifications Changes to the program in 2007 include:

e the addition of monitoring wells MW-7 and MW-8 in the vicinity of well P-10 to assess the higher levels previously noted in P-10

the addition of the New Administration Building well

the addition of the Plant Screenhouse well

the addition of a stormwater runoff sample

sampling was not performed at station P-3 because it was inaccessible

sampling was not performed at the STA house (SW-2) because it was dry 3.5 Results and Discussion Results obtained show tritium in well water and ground water samples at or near expected natural background levels except the P-10, MW-7, amd MW-8 sample wells. Table 4.4 provides the complete data table of results for each period and sampling location.

E-4

Results and Discussion (continued)

The tritium level annual averages have shown a downward trend since the special sampling begun in 1989.

Except for sample wells P-10, MW-7, and MW-8, the 2007 sample results are within the range of expected background tritium levels, in shallow ground water and surface water due to tritium concentrations measured in precipitation. Sampling points in:North America have shown tritium concentrations in precipitation ranging from 5 pCi/L to 157 pCi/L (Environmental Isotope Data No.

10; World Survey of Isotope Concentration in Precipitation (1988-1991)).

The higher level results at the Suter residence and Birch Lake in 1989 were possibly due to seepage from the PINGP discharge canal water into the ground water. This is thought to occur due to the elevation difference between the Vermillion River.and the discharge canal. The Suter residence is located between the discharge canal and Birch Lake, which connects to the Vermillion River. The PINGP discharge canal piping was lengthened during 1991, so that. liquid discharges from the plant are released near the end of the discharge canal, diffused and discharged to the Mississippi River. In 1992, the underground liquid discharge pipe from the plant to the discharge canal piping was replaced with a double walled leak detectable piping system. This year's sample results continue to indicate that these modifications have eliminated the suspected radioactive effluent flow into the local ground water.

The elevated tritium levels in sample wells P-10, MW-7, and MW-8 in 2007 may be due to prior leakage from the PINGP liquid radwaste discharge pipe or discharge of turbine building sump water into the landlocked area. The liquid radwaste discharge pipe was replaced in 1992 and the discharge to the landlocked area has been minimized by administrative controls.

E-5

Table E-4.1. Sample collection and analysis program, Special well and surface water samples, Prairie Island Nuclear Generating Plant, 2007.

Medium No. Location codes Collection type Analysis type and type and frequency P-8, REMP P-6, PIIC-02, PIIC-22, PIIC-26, P-2, P-3, P-4, P-5, P-6, Well water, 28P-7, P-11, 28 PZ-1, PZ-2, PZ-3, PZ-4, PZ-5, G/A H-3 Annual PZ-7, PZ-8, MW-4, MW-5, MW-6, P-9, P-26, P-30, SW-2, SW-3, SW-4, SW-5 Well water, quarterly 1 P-24D G/Q H-3 Well water, monthly 5 P-43(C), SW-1(C), G/Md H-3 MW-7, MW-8, P-10 Surface water S-1, S-2, S-3, S-4, 6 S-5, S-6 G/A H-3 Location codes are defined in table D-4.2. Control Stations are indicated by (C). All other stations are indicators.

Stations MW-7, MW-8, SW-4, SW-5, and S-6 were added in 2007.

b Collection type is codes as follows: G/ = grab. Collection frequency is coded as follows: M monthly; Q quarterly; A annually.

C Analysis type is coded as follows: H-3 = tritium.

Wells MW-7 and MW-8 were added in September 2007 and monthly sampling was begun in October 2007.

E-6

Table E-4.2. Sampling locations for special well and surface water samples, Prairie Island Nuclear Generating Plant, 2007.

Code Collection site Type of sample b Distance and

..... _ _ Direction from reactor P-8 P1 Community well WW 1.0 mi. @ 321 /WNW REMP P-6 Lock & Dam #3 well WW 1.6 mi. @ 129°/SE PIIC-02 2077 Other Day Road WW 1.4 mi. @ 315°/NW PIIC-22 1773 Buffalo Slough Rd WW 1 mi. @ 315°/NW PIIC-26 1771 Buffalo Slough Rd WW 1 mi. @ 315°/NW P-24D Suter residence WW 0.6 mi. @ 158°/SSE P-43 Peterson Farm (Control) WW 13.9 mi. @ 355°/N SW-1 Hanson Farm (Control) WW 2.2 mi. @ 315°/NW P-2 Sample well WW See map P-3 Sample well WW See map P4 Sample well . WW See map P-5 Sample well WW See map P-6 Sample well WW See map P-7 Sample well. WW See map P-10 Sample well WW See map P-11 Sample well WW See map PZ-1 Sample well WW See map PZ-2. Sample well WW See map PZ-4 Sample well WW See map PZ-5 Sample well WW See map PZ-7 Sample well WW See map PZ-8 Sample well WW See map MW-4 Sample well WW See map MW-5 Sample well WW See map MW-6 Sample well WW See map MW-7 Sample well WW See map MW-8 Sample well WW See map P-26 PITC well WW 0.4 mi. @ 258°/WSW P-30 Environ lab well WW 0.2 mi. @ 32°/NNE SW-2 STA House WW See map SW-3 Cooling Tower pump WW See map SW-4 New Admin Bldg WW 0.05 mi. @ 315°/NW SW-5 Plant Screenhouse well WW 0.05 mi. @ 0°IN P-9 Plant well # 2 WW 0.3 mi. @ 306°/NW S-1 Mississippi River upstream SW See map S-2 Recirculation/Intake canal SW See map S-3 Cooling water canal SW See map S-4 Discharge Canal (end) SW See map S-5 Discharge Canal (midway) SW See map S-6 Stormwater Runoff SW 0.05 mi. @ 0ON Sample codes: WW = Well water; SW = Surface Water.

E-7

Table E-4.3

Radiation Environmental Monitoring Program Summary: Special well and surface water samples.

Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January - December 2007 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number Tpa of b Routine (Units) Analyses LLD Mean (F)c Locationd Mean (F) Mean(F) Results C C C Range Range Range Offsite H-3 36 19 45(9/12) PIIC-22 65(1/1) 29(3/24) 0 Well Water (23-65) (65) (25-32)

(pCi/L)

Onsite H-3 63 19 367(36/39) P-10 908 (12/12) 29 (3/24) 15 Well Water (24-2258) (390-2258) (25-32)

(pCi/L)

Onsite H-3 30 19 94 (5/6) S-6 285 (1/1) 29 (3/24) 0 Surface Water (35-285) (285) (25-32)

(pCi/L) a H-3 = tritium b

LLD Nominal lower limit of detection based on 4.66 sigma error for background sample. Value shown is lowest for the period.

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 code (Table 2) and (2) by distance, direction and sector relative to reactor site.

e Non-routine results are those which exceed ten times the control station value.

E-8

Table E-4.4 Radiological Environmental Monitoring Program-, Complete Data Table, 2007, continued.

SAMPLE DATES JAN FEB MAR APR MAY JUN . JUL AUG SEP OCT NOV DEC 2007 2007 2007 2007 2007 2007 2007 2007 2007 2007 2007 2007 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L ONSITE WELLS P-2 Sample well 66 P-4 Sample well <19 P-5 Sample well 109 P-6 Sample well 45 P-7 Sample well 95 P-10 Sample well 1289 390 453 967 835 784 482 544 486 1724. 2258 678 P-1 1 Sample well 65 PZ-1 Sample well <19 PZ-2 Sample well 71 PZ-4 Sample well 40 PZ-5 Sample well 47 PZ-7 Sample well _ _52 PZ-8 Sample well 54 MW-4 Sample well 46 MW-5 Sample well 35 MW-6 Sample well 44 MW-7 Sample well 341 73 54 MW-8 Sample well 43 325 513 P-26 PITC well 31 P-30 Env. lab well <19 SW-3 Cooling Tower pump 37 P-9 Plant well # 2 24 SW-4 New Admin 65 SW-5 Pin Scrnhs 32 E-9

Table E-4.4 Radiological Environmental Monitoring Program , Complete Data Table, 2007, continued.

SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2007 2007 2007 2007 2007 2007 2007 2007 2007 2007 2007 2007 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L ONSITE SURFACE WATER S-1 Mississippi River upstream 57 S-2 Recirculation/Intake canal 56 S-3 Cooling water canal < 19 S-4 Discharge Canal (end) 36 S-5 Discharge Canal (midway) 35 S-6 Stormwater runoff 285 OFFSITE WELLS P-8 PI Community Well ____

<19 REMP P-6 Lock & Dam #3 well <19 PIIC-02 2077 Other Day Rd. <19 PI1C-22 1773 Buffalo Slough Rd. .65 PIIC-26 1771 Buffalo Slough Rd. 62 P-24D Suter"residence..... 63 47 35 25 23 46 36 P-43 Peterson Farm (Control) <19 25 <19 <19 <19 <19 <19 29 < 19 <19 <19 <19 3

SW1 Hno am(oto) 32 < 19 < 19 < 19 < 19 < 19 < 19 < 19 1< 19 < 19 < 19 < 19 E-10

Sý'."Y by Joh-0s &.9roFIld InC No gbc

ý 2fl07 Top of Riser Well North East ipe Elev MW-4 592236 2355090 693.02

MW, 5902201, .2356566 686.83 MW-6 591642 2357597 682.33 MW-7 593685 2355714 695.54 MW-8 593944 ,2355654 697.47

P-1O 593538 .2355497 693.16 P -I 594949 2355297 :698.19 P-2 594449 2354002 697.72 P-3 592998 2353997 :698.19 P-5 594002 2354501 695.51 P-6 595250 2354802 699.3 P-7 594449 2355235 697.97 PZ-1 598790 2354934 ,682-91 PZ-2 596743 2352589 .689.05 PZ-4. 594262 2352598 696.53 PZ-5 591502 2356299 695.93 PZ-7 594469 2356158 697.85.

PZ-8 595471 2353662 696.52 iV6nccy. Dncenb- 17, 2OG7 E-1 1

L-PI-08-033, 2007 Annual Radiological Environmental Monitoring Program (REMP) Report

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L-PI-08-033, 2007 Annual Radiological Environmental Monitoring Program (REMP) Report

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1.0 INTRODUCTION

SUMMARY

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