Text

Corrections to the 2007 Annual Radiological Environmental Monitoring Program (REMP) Report and the 2007 Annual Radioactive Effluent Report
	ML092870173
Person / Time
Site:	Prairie Island
Issue date:	10/07/2009
From:	Schimmel M; Northern States Power Co, Xcel Energy
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	L-PI-09-103
	Download: ML092870173 (102)
	v • d • e

&XcelEnergyo OCT 0 72009 L-PI-09-103 4/

TS 5.5.1.c TS 5.6.2 ISFSI TS 6.2 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 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 Corrections to the 2007 Annual Radiological Environmental Monitorinq Program (REMP) Report and the 2007 Annual Radioactive Effluent Report

References:

1. Nuclear Management Company, LLC (NMC) letter to US Nuclear Regulatory Commission (NRC), 2007 Annual Radiological Environmental Monitoring Program (REMP) Report, dated May 13, 2008 (ADAMS Accession Number ML081370083)

2. NMC letter to NRC, 2007 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual (ODCM), dated May 13, 2008 (ADAMS Accession Number ML081370317)

In references 1 and 2, Nuclear Management Company, LLC (NMC) 1 submitted the 2007 Annual REMP and 2007 Annual Radioactive Effluent Report and ODCM for the Prairie Island Nuclear Generating Plant (PINGP). Minor errors were later identified in both annual reports, therefore Northern States Power Company, a Minnesota Corporation (NSPM) is resubmitting the two reports in their entirety, with the exception of the ODCM which was not affected by these changes. The corrections are described in detail below.

2007 Annual REMP Report The contractor that produces the REMP report for PINGP discovered an error in Table A-3, In-House "Spike" Samples, dealing with in-house laboratory quality assurance checks. In the report, a footnote indicated that the acceptance ranges are the known sample quantities plus or minus 1 sigma. The actual ranges listed in the report are the known sample quantities plus or minus 2 sigmas. The 2 sigma values are the correct values to use. Footnote "d" on page A3-2 was corrected to state "Control limits are established from the precision values listed in Attachment A of this report, adjusted to + 2 a." The two affected pages, A3-1 and A3-2, are noted in the header information as "Corrected Page".

1 On September 22, 2008, NMC transferred its operating license authority to Northern States Power Company, Minnesota (NSPM), doing business as Xcel Energy. By letter dated September 3, 2008, NSPM assumed responsibility for actions and commitments previously submitted by NMC.

1717 Wakonade Drive East ° Welch, Minnesota 55089-9642 jTWc9 Telephone: 651.388.1121

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Document Control Desk Page 2 2007 Annual Radioactive Effluent Report Two minor discrepancies were noted by PINGP staff, neither which constitute an error in the official reported dose.

1) Enclosure 1, Off-Site Radiation Dose Assessment, January 01, 2007 - December 31, 2008 This correction replaces page 2 of 6, which contained errors in the gamma and beta dose values in the Corrective Action section of a Leak in Waste Gas System. The officialreported dose in Table 1, page 5 of 6, of Enclosure 1 was determined to be correct.

2) Enclosure 4, Attachment to the 2007 Annual Effluent Report This correction replaces page 1 of 1, which contained a minor error in the Background section that reported "approximately 150 gallons of secondary steam condensate leaked to the ground outside the northeast side of the turbine building...". This page was corrected to indicate that "approximately 150 gallons of secondary steam condensate leaked to the ground outside the west side of the turbine building...".

The two affected pages have also been noted in the header information as "Corrected Page".

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

Mark A. Schimmel Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Attachments (2) cc: Regional Administrator, USNRC, Region III Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector, Prairie Island Nuclear Generating Plant Desiree Smith, USNRC, Region III Director of NMSS, USNRC Department of Health, State of Minnesota PI Dakota Community Environmental Coordinator

ATTACHMENT I Annual Report to the United States Nuclear Regulatory Commission Radiological Environmental Monitoring Program (REMP) Report Resubmitted with Corrected Pages January 1, 2007 through December 31, 2007 71 pages follow

- - Environmental, Inc.

Midwest Laboratory an Allegheny Tedcnologles 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:

A

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 Modifications .......................................................................................................................... 6 3.6 Land Use Census ................................................................................................................................. 6 4.0 RESULTS AND DISCUSSION ........................................................................................................................ 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 ........................................ I......................................................................................... 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 ............................................................................. 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 Page 5.1 Sample Collection and Analysis Program ................................................................................................... 15 5.2 Sampling Locations .................................................................................... ;...................................................... 16 5.3 Missed Collections and Analyses .......................................................................... ............................................ 19 5.4 Radiation Environm ental 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 .......................................................... Al-I A-2 Program Results; (TLDs) .............................................................................................................................. A2-1 A-3 hA3-1 "Spiked" Sam ples ..........................................................................................................................

In-house A-4 In-house "Blank" Sam ples ............................................................................................................................. A4-1 A-5 In-house "Duplicate" Sam ples ...................................................................................................................... A5-1 A-6 Department of Energy MAPEP comparison results ...................................................................................... A6-1 A-7 Environmental Resources Associates, Crosscheck Program Results (EML study replacement) ................. A7-1 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 Sampling locations .......................................................................................................................................... E-7 E-4.3 REMP Sum mary .............................................................................................................................................. E-8 E-4.4 REMP Com plete Data Table ........................................................................................................................... E-9 iv

LIST OF FIGURES No. Title Paae 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-1) .......................................................................................... 14 In addition, the following figure can be found in the Appendices:

E-1 Onsite Tritium Sampling Well locations ................................................ E-1 1 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 Progqram 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-1 31. 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-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope.

They were chosen as calibration monitors and should not be considered 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 CaSO 4: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 at two 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 Program Description (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 Program 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 a'nd 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-131 analyses in milk and drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method and solvent extraction and subsequent beta counting.

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

Levels of iodine-1 31 in cabbage and natural vegetation and concentrations of airborne iodine-131 in charcoal samples were determined by gamma spectroscopy.

Tritium concentrations are determined by liquid scintillation.

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

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

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

3.5 Program 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 durin3q preoperational studies. Gross beta in air particulates declined from levels of 0.38 to 0.037 pCi/m .

3 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 mRI91 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 mRI91 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 Rinqs) Control i Year Outer Rings) Control 1992 16.3 14.8 2000 17.0 r 17.1 1993 15.9 15.4 2001 16.8 1 17.2 1994 15.2 16.0 2002 7.4 16.9 1995 15.6 16.6 2003 16.2 16.0 1996 14.8 16.4 2004 17.6 17.6 1997 15.1 16.0 2005 16.8 16.3 1998 j 16.7 17.3 2006 16.6 16.6 1999 I 16.6 17.5 2007 17.5 17.7 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates (mR/91 days).

ISFSI Facility Operations Monitorinq 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 mRI91 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.

Year i Average of Indicators Contro 3

1 Concentration (,Ci/m _

1992 0.023 0.021 1993 j 0.022 0.019 1994 0.022 0.022 1995 _ 0.022 1 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 1 0.023 2003 0.027 0.025 2004 0.025 0.026 2005 0.027 0.025 2006 2007 T 0.026 0.037

]i 0.025 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 PA, 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.

Drinkinq 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 6.9-17.5 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 f 5.4 1999 I 5.3 2000 1 10.1 2001 i _ 8.3 2002 j = 8.7 2003 [ 9.9 2004 I 9.8 2005 11.5 2006 I 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.

L----Indicator 20 19 18 17 16 15

-o14 13 12 11 10

.W to (0 CO CO CO CO 0 CD 0 0 0 0 0 r.) wo A. oC CD Co D C , 0 .- 0 w 0 0 0) -4

Control (P-01C) 20 19 I 162 - _ _ _

15 I

" 14

" 13 '__

E 12 12 " II 11 _______

10 I Co Co Co Co Co Co C Co 0J 0D 0 0) 0 0 0 0)

C0 Co CO Co Co Co Co DCo 0 Q 0 0D<D C 0 0D N) w Cý) Cn(7 0) -4 OD CD Q - N) w~ .4 CA 0M -4 13

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

I -* Indicators (P-2,3,4,6) I T

0.039 _ _ -------

0.037 _ _ _;_

I I _ __ I i ('

0.035 ----------

0.0331 I " . !

0.031" 0.029 0.027 , "- "

oo:0.021* '

0.019 0.017 0.015

-. -~ Nw) toN)

CD -

w)

C -

D -.(D CD -~ CD CD C ) 0 0 0 0 0 0 CD (D to CO (D CD CD 0 0 0 0 0 0 0 w) w Cý CA 0 -4 OD O C, K) w .1 CA 0) -J

--*--Control (P-i) 0.039, 0.037. ' , I 0.035! I I 0.033 J I 0.0311 0.029 '

0.027 E 0.025 . 1 .

0.021 0.019 I'___

0.017 1.. Ii____

0.015 I ,I I - ___ - -

&D 5 CS CD CD C5 CD 8 C":D131 0 C 0D C>

0 0 0 0 w CD CO CD CM CD C C 0 0 0 0 0 0 0 w) w 4,* C.) 0) -,4 C O 0 po N w 46 Ml IM -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)e Frequencyb Frequency' Ambient radiation (TLD's) 54 P-OlA - P-IOA C/Q Ambient gamma P-OIB - P-15B P-01S - P-08S P-OllA - P-OBIA P-OIB - P-O8IB P-OblX- P-041X, P-01C Airborne Particulates 5 P-I(C), P-2, C/W GB, GS (QC of P-3, P-4, P-6 each location)

Airborne Iodine 5 P-I(C), P-2, P-3, P-4, P-6 C/W 1-1.31 Milk 5 P-14, P-18, P-37, P-42, P-44, G/Md 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), 1-1.3(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 (1-131) 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.

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.

Milk is collected biweekly during the grazing season (May - October).

15

PRA/IRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant.

Distance and Direction from Code Typea Collection Site Sample Type" Reactor P-1 C Air Station P-1 AP, Al 11.8 mi @ 316*/NNW P-2 Air Station P-2 AP, Al 0.5 mi @ 294*/WNW P-3 Air Station P-3 AP, Al 0.8 ml @ 313'/NW P-4 Air Station P-4 AP, Al 0.4 ml @ 3590/N P-5 C Upstream of Plant RW 1.8 ml @ 110/N P-6 Lock and Dam #3 & Air AP, Al. RW Station P-6 WW, BS, BO0 1.6 mi @ 129*/SE P-8 Community Center WW 1.0 mi @ 321°/WNW P-9 Plant Well #2 WW 0.3 mi @ 3060/NW P-11 Red Wing Service Center DW 3.3 mi @ 158 0/SSE P-12 Downstream of Plant SS 3.0 ml @ 116°/ESE P-13 Downstream of Plant Fr 3.5 mi @ 1130/ESE P-14 Gustafson Farm M 2.3 mi @ 1730/S P-18 Christiansen Farm M 3.8 mi @ 880/E P-19 C Upstream of Plant Fc 1.3 mi @ O/N P-20 C Upstream of Plant BS 0.9 mi @ 450/NE P-24 Suter Residence VE, WW 0.6 mi @ 158°/SSE P-37 Welsch Farm M 4.1 mi @ 870/E P-38 C Cain Residence VE 14.2 mi @ 3590/N P-40 C Upstream of Plant 10c 0.4 mi @ O°/N P-42 Rother Farm M 4.3 mi. @ 264*/W P-43 C Peterson Farm M, WW 13.9 mi. @ 3550/N P-44 Yoemans Farm M 2.0 mi. @ 214*/SW General Area of the Site Boundary P-OIA Property Line TLD 0.4 mi @ 3590/N P-02A Property Line TLD 0.3 mi @ 1O./N P-03A Property Line TLD 0.5 mi @ 1830/S P-04A Property Line TLD 0.4 mi @ 2040/SWW P-05A Property Line TLD 0.4 mi @ 2250/SW P-06A Property Line TLD 0.4 mi @ 2490/WSW P-07A Property Line TLD 0.4 mi @ 2680/W P-08A Property Line TLD 0.4 mi @ 291e/WNW P-09A Property Line TLD 0.7 mi @ 317°/NW P-IOA Property Line TLD 0.5 mi @ 3330/NNW 16

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

Distance and Direction from Code Type" Collection Site Sample Typeb Reactor Approximately 4 to 5 miles Distant from the Plant P-0113 Thomas Killian Residence TLD 4.7 mi @ 3550/N P-02B Roy Kinneman Residence TLD 4.8 mi @ 17 0/NNE P-03B Wayne Anderson Farm TLD 4.9 ml @ 460/NE P-04B Nelson Drive (Road) TLD 4.2 mi @ 610 /ENE County Road E and Coulee TLD 4.2 mi @ 102 0/ESE P-068 William Hauschlblt Residence TLD 4.4 ml @ 1120/ESE P-07B Red Wing Public Works TLD 4.7 mi @ 1400/SE P-0813 David Wnuk Residence TLD 4.1 mi @ 1650/SSE P-09B Highway 19 South TLD 4.2 ml @ 1870/S P-10B Cannondale Farm TLD 4.9 mi @ 2000/SSW P-118 Wallace Weberg Farm TLD 4.5 mi @ 221V/SW P42B Ray Gergen Farm TLD 4.6 mi @ 2510/WSW

.P-138 Thomas O'Rourke Farm TLD 4.4 ml @ 270 0/W P-14B David J. Anderson Farm TLD 4.9 mi @ 3060/NW 0

P-15B Hoist Farms TLD 3.8 mi @ 345 /NNW Special.Interest Locations P.0:15 Federal Lock & Dam #3 TLD 1.6 mi @ 1290/SE P-02S Charles Suter Residence TLD 0.5 mi @ 1550 /SSE P-03S Carl Gustafson Farm TLD 2.2 ml @ 1730/S P-04S Richard Burt Residence TLD 2.0 mi @ 202°/SSW P-05S Kinney Store TLD 2.0 mi @ 2700/W P-06S Earl Flynn Farm TLD 2.5 ml @ 2990/WNW P-07S Indian Community TLD 0.7 mi @ 271*/W P-085 Indian Community TLD 0.7 mi @ 2870/NWW P-oic C Robert Kinneman Farm TLD 11.1 mi @ 331o/NNW 17

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

Approximate Type of Distance and Direction Code Type3 Collection Site Sampleb from ISFSI Center.

ISFSI Area Inside Earth Berm P-011A ISFSI Nuisance Fence TLD 190'@ 450 /NE P-021A ISFSI Nuisance Fence TLD 360' @ 82 0/E P-031A ISFSI Nuisance Fence TLD 370' @ 1000/E 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-01IX ISFSI Nuisance Fence TLD 140' 0 180"/S P-021X ISFSI Nuisance Fence TLD 310' @ 270'/W P-031X ISFSI Nuisance Fence TLD 140' @ O/N P-041X ISFSI Nuisance Fence TLD 360' @ 90-/E ISFSI Area Outside Earth Berm P-011IB ISFSI Berm Area TLD 340' @ 30/N P-021B ISFSI Berm Area TLD 380' @ 280/NNE P-031B ISFSI Berm Area TLD 560' @ 850/E P-041B ISFSI Berm Area TLD 590' 0 165°/SSE P-051B ISFSI Berm Area TLD 690' @ 1860/S P-061B ISFSI Berm Area TLD 720'@ 201"/SSW P-0 71B ISFSI Berm Area TLD 610'@ 2710/W P-0818 ISFSI Berm Area TLD 360' @ 332°/NNW 0 "C" denotes control location. All other locations are indicators.

0 "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 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 pump was replaced with 1-131 run-time logged. a calibrated spare.

AP/Al 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.

MI 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)' Mean (F)c Routine (Units) Analyses' Range' Locationd Range' Rangec Resultse 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) mRI91 days)

TLD (Outer Ring, Gamma 59 3.0 17.9 (59/59) P-028, 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.)

mR/91 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.)

mR/91 days)

TLD (Control) Gamma 4 3.0 None P-01C, R. Kinneman, 17.7 (4/4) 17.7 (4/4) 0 mR/91 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/m3)

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 @ 313° /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

( 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 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 Rangec Locationa Rangec Rangec Resultse (Units) Analysesa 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 (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 (Units) Analyses' Rangec Location" Rangec Range' Resultse 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 @ 00 /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 4nvertebrates 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-134 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)t Routine t

(Units) Analyses' Range' Location" Range' Range 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-1 34 0.029 < LLD - < LLD 0 Cs-137 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).

o 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. AI-Salih. 1955. Beryllium-7 Produced by Cosmic Rays. Science 121: 451-453.

Eisenbud, M. 1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp. 213, 275 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 HASL-300, Edition 28, Procedures Manual, Environmental Measurements Laboratory, New York, NY.

U.S. Environmental Protection Agency.

1980. Prescribed Procedures forMeasurement 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

-~ an Allegheny Tedchologies CD.

700 Landwehr Road

Norfttbwk IL 60062-2310 ph. (847) 564-0700

fax (847) 564517 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 Intercompadson results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January 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 ANALYSES 8 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 5.0 pCi/liter Strontium-90b 2 to 30 pCi/liter or kg

> 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 +1G =

0 33 169.85 x (known) °'9

> 4,000 pCi/liter 10% of known value Radium-226,-228 - 0.1 pCi/liter 15% of known value Plutonium a 0.1 pCi/liter, gram, or sample 10% of known value 4odine-131, 5 55 pCi/liter 6.0 pCi/liter Iodine-I 2 9 b > 55 pCi/liter 10% of known value Uranium-238, < 35 pCi/liter 6.0 pCi/liter Nickei-63b > 35 pCi/liter 15% of known value Techneti UM~99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter

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

b Laboratory limit.

A2

TABLE A-1. Intedaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)8 .

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-133 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-1 125 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-1125 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-t 127 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 07/09107 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-137 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-1 33 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-1 34 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-1 133 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-i 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 8 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.

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

Al-1

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

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

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 7/1312007 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 2007-2 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 11/1212007 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 CORRECTED PAGE Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 C Activity' Limitsd 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-1566 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-1595 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-1595 4/5/2007 1-131(G) 83.11 +/- 3.51 82.07 72.07 - 92.07 Pass SPW-1595A 4/5/2007 1-131 78.40 +/- 1.10 82.07 65.66 - 98.48 Pass SPW-1 595B 4/5/2007 1-131 78.97 +/- 1.10 82.07 65.66 - 98.48 Pass SPMI-1 597 4/5/2007 Cs-134 54.03 +/- 2.15 54.99 44.99 - 64.99 Pass SPMI-1597 4/5/2007 Cs-137 59.81 +/- 4.75 58.19 48.19 - 68.19 Pass SPMI-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 5/18/2007 Cs-134 55.43 +/- 1.68 52.85 42.85 - 62.85 Pass SPW-2847 5/18/2007 Cs-137 59.86 +/- 2.71 58.03 48.03 - 68.03 Pass SPW-2847 5/18/2007 1-131 60.14 +/- 0.89 70.87 56.70 - 85.04 Pass SPW-2847 5/18/2007 1-131(G) 63,95 +/- 2.69 70.87 60.87 - 80.87 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-90 46.72 t 1.97 46.08 36.86 - 55.29 Pass SPMI-2849 5/18/2007 Cs-134 51.37 +/- 1.65 52.85 42.85 - 62.85 Pass SPMI-2849 5/18/2007 Cs-137 60.42 +/- 4.31 58.03 48.03 - 68.03 Pass SPMI-2849 5/18/2007 1-131 67.97 +/- 0.88 70.87 56.70 - 85.04 Pass SPMI-2849 5/18/2007 1-131(G) 62.44 +/- 3.14 70.87 60.87 - 80.87 Pass SPMI-2849 5/18/2007 Sr-89 102.04 +/- 8.03 121.90 97.52 - 146.28 Pass SPMI-2849 5/18/2007 Sr-90 44.80 +/- 2.37 46.08 36.86 - 55.30 Pass SPW-2909e 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-137 111.14 +/- 3.57 116.06 104.45 - 127.67 Pass SPF-2922 5/22/2007 Cs-1 34 0.52 +/- 0.03 0.53 0.32 - 0.74 Pass SPF-2922 5/22/2007 Cs-1 37 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 9/21/2007 Gr. Beta 61.48 +/- 0.47 65.73 55.73 - 75.73 Pass A3-1

TABLE A-3. In-House "Spike" Samples CORRECTED PAGE Concentration (pCi/L)f Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limitsd Acceptance SPW-6880 10/10/2007 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-111007 11/10/2007 Gr. Beta 64.49 +/- 0.48 65.73 55.73 - 75.73 Pass SPAP-7742 11/13/2007 Cs-134 21.18 +/- 1.29 22.41 12.41 -32.41 Pass SPAP-7742 11/13/2007 Cs-137 113.61 +/- 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-134 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-7750 11/13/2007 C-14 4479.20 +/- 15.67 4742.00 2845.20 - 6638.80 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-1 34 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/mi3), 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).

v Results are based on single determinations.

d Control limits are established from the precision values listed in Attachment A of this report, adjusted to +/- 2o.

e 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 (4.66a) 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-134 0.79 100 SPW-1567 Air Filter 3123/2007 Cs-137 1.01 100 SPW-1568 water 3/23/2007 H-3 176.10 -26.16 + 91.62 200 SPW-1 596 water 4/5/2007 Cs-134 3.28 10 SPW-1 596 water 4/5/2007 Cs-137 3.45 10 SPW-1596 water 4/5/2007 1-131 0.27 0.02 +/- 0.18 0.5 SPW-1t596 water 4/5/2007 1-131(G) 2.91 20 SPMI-1598 Milk 4/5/2007 Cs-134 3.30 10 SPM I-1598 Milk 4/5/2007 Cs-137 5.08 10 SPMI-1598 Milk 4/512007 1-131 0.26 -0.10 +/- 0.17 0.5 SPMI-1598 Milk 4/512007 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-134 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-2850 d 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-134 2.84 100 SPAP-2916 Air Filter 5/22/2007 Cs-1 37 2.24 100 SPF-2923 Fish 5/22/2007 Cs-134 8.71 100 SPF-2923 Fish 5/2212007 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)8 Lab Code Sample Date Analysisb Laboratory results (4.66a) 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-134 2.16 10 SPMI-7745 Milk 11/13/2007 Cs-1 37 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-7747 water 11/13/2007 Cs-134 2.39 10 SPW-7747 water 11/1312007 Cs-1 37 3.53 10 SPW-7747 water 11/13/2007 1-131(G) 12.51 20 SPW-7747 water 11/1312007 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-1 34 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-1 31 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)8 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 1130/2007 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 2/112007 K-40 1.24 +/- 0.12 1.20 +/- 0.12 1.22 +/- 0.08 Pass SW-601, 602 2/112007 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 1316.40 +/- 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-1117, 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 1.81 +/- 1.80 Pass 2.51 +/- 2.29 1.10 +/- 2.78 W-2085, 2086 31612007 Gr. Beta 11.02 +/- 1.85 9.50 +/- 2.01 10.26 +/- 1.37 Pass 3/6/2007 3/8/2007 DW-70232, 70233 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 +/- 0.97 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 3126/2007 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)"

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance MI-1824, 1825 412/2007 K-40 1316.10 +/- 110.60 1229.80 +/- 110.50 1272.95 +/- 78.17 Pass MI-1824, 1825 4/212007 Sr-90 1.20 +/- 0.50 1.10 +/- 0.36 1.15 +/- 0.31 Pass AP-2170, 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 413/2007 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 +/- 0.89 3.66 +/- 0.96 3.72 +/- 0.65 Pass

,DW-70300, 70301 414/2007 Gr. Beta 2.93 +/- 0.61 2.91 +/- 0.64 2.92 +/- 0.44 Pass OVW-70335, 70336 4/5/2007 Gr. Alpha 24.37 +/- 2.89 22.72 +/- 2.91 23.55 +/- 2.05 Pass DW-70335, 70336 41512007 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- 898, 1899 4/10/2007 Gr. Beta 6.31 +/- 1.36 7.03 +/- 1.42 6.67 +/- 0.98 Pass SW-1898, 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 OW-7'0376, 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 t 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-137 119.22 + 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 9.77 +/- 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-1 37 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-137 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 6/412007 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 M4-4742, 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-137 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)8 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 9t12/2007 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-137 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 1011/2007 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 10/812007 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 :t 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)"

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SS-7529, 7530 10/29/2007 Cs-137 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, 76-19 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 :t 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 t 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-81 42, 8143 11/28/2007 Gr. Beta 9.51 t 2.21 7.86 +/- 2.01 8.68 +/- 1.49 Pass DW-8094, 8095 11/2912007 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.

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

A5-5

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

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-1l110 01/01/07 Gr. Beta 0.90 +/- 0.14 0.85 0.43-1.28 Pass STrW-1III e 01/01/07 Am-241 2.80 +/- 0.21 1.71 1.20 -2.22 Fail STW-1111 01/01/07 Co-57 151.60 +/- 10.00 143.70 100.60 - 186.80 Pass STW-1111 01/01/07 Cs-1 34 79.20 +/- 8.00 83.50 58.50 - 108.60 Pass STW-1111 01/01/07 Cs-1 37 168.70 +/- 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-1111 01/01/07 Mn-54 130.60 +/- 11.50 123.80 86.70 - 160.90 Pass "STW-111I 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 STVV-1111 01/01/07 Pu-238 2.03 +/- 0.17 2.25 1.58 -2.93 Pass STW-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 6.21 -11.53 Pass STW-1 l,1i 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 t 01/01107 Am-241 46.40 +/- 9.00 34.80 24.40 - 45.20 Fail STSO-1112 01/01/07 Co-57 501.20 +/- 2.90 471.20 329.80 - 612.60 Pass STSO-1 112 01/01107 Co-60 285.90 +/- 2.10 274.70 192.30 - 357.10 Pass STSO-11t2 01/01/07 Cs-134 325.90 +/- 7.40 327.40 229.20 - 425.60 Pass STSO-1112 01/01/07 Cs-137 855.70 +/- 4.60 799.70 559.80 - 1039.60 Pass STSO-1112 01/01/07 Mn-54 750.90 +/- 4.70 685.20 479.60 - 890.80 Pass STAP-1113 01/01/07 Gr. Alpha 0.27 +/- 0.04 0.60 0.00-1.20 Pass STAP-1113 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-1 37 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 ' Acceptance STVE-1 115 01/01/07 Co-57 8.90 +/- 0.20 8.19 5.73 - 10.64 Pass STVE-1115 01/01107 Co-60 6.50 +/- 0.20 5.82 4.08 - 7.57 Pass STVE-1 115 01/01/07 Cs-1 34 6.90 :1:0.30 6.21 4.35 - 8.07 Pass STVE-1 115 01/01/07 Cs-1 37 8.20 t 0.30 6.99 4.90 -9.09 Pass STVE-1115 01/01/07 Mn-54 10.10 +/- 0.30 8.46 5.91 - 10.98 Pass

(

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 Bqfkg (soil), BqIL (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-1116 03/19/07 Gr. Alpha 34.64 +/- 2.56 25.8 12.4 -39 Pass STAP-1 116 03/19/07 Gr. Beta 93.41 +/- 3.20 79.5 48.8-116 Pass STAP- 117 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-1117 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-1 117 *03/19/07 Pu-239/40 35.23 +/- 2.24 31.6 22.9 -41 Pass STAP-i 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-1 117 03/19/07 U-238 42.00 +/- 1.84 47.4 30.2 - 68 Pass STAP-1 117 03/19107 Uranium 85.79 +/- 3,60 97.3 49.5 -155 Pass STAP- 117 03/19/07 zn-65 363.80 +/- 11.90 245.0 208.0 -412 Pass STSO-1 118 03/19/07 Ac-228 3097.77 +/- 94.96 2790.0 1790.0 - 3930 Pass STSO-1118 03/19/07 Am-241 1000.70 +/- 156.10 927.0 548.0 - 1200 Pass STSO-1118 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-134 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-1 118 03/19/07 K-40 12201.60 +/- 423.20 11100.0 8050.0 - 15000 Pass STSO-I 11183 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-1118 03/19/07 Pb-214 4142.80 +/- 110.40 3330.0 1980.0 -4980 Pass STSO-1 118 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-1118 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. Intedaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)".

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-1 119 03/19/07 Cm-244 1860.70 +/- 91.50 1840.0 905.0 - 2870 Pass STVE-1 119 03/19/07 Co-60 2827.90 +/- 62.40 2600.0 1760.0 -.3720 Pass STVE-1 119 03/19/07 Cs-1 34 654.80 +/- 48.40 579.0 308.0 - 822 Pass STVE-1 119 03/19/07 Cs-1 37 3307.30 +/- 58.80 2920.0 2150.0 - 4060 Pass STVE-1119 03/19/07 K-40 40814.20 +/- 618.80 37900.0 27200.0 - 53600 Pass STVE-1119 f 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-1 11i9 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-1120 03/19/07 Cs-137 1839.10 +/- 17.90 1850.0 1570.0 - 2220 Pass STW-1120 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-1120 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 Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

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

' 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.

'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.

flncluded 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 = 2o 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 4.66cr uncertainty for a background sample.

3.0. Duplicate analyses 3.1 Individual results: For two analysis results; x 1 + s 1 and x2 +/- s 2 Reported result: xs; where x= (1/2)(x 1 +x)ands= (1/2) 1 +S2 3.2. -Individual results: < L1 , < L2 Reported result: < L, where L = lower of L, and L2 3.3. Individual results: x +/- s, < L Reported result: x +/- s if x > L; < L otherwise.

4.0. Comnutation 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 x 1, x 2 . . .x are defined as follows:

n2: jx1-x 2_

x -s n=-

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

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

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

4.5 In rounding off, the following rules are followed:

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

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

B-2

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

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

-3 Gross alpha 1 x 10 Strontium-89 8,000 Gross beta 1 Strontium-90 500 b -1 Iodine-131 2.8 x 10 Cesium-1 37 1,000 Barium-140 8,000 Iodine-131 1,000 C

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.

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

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

C A natural radionuclide.

C-2

APPENDIX D Sampling Location Maps

TLO LOCATIONS ONE MILE RADIUS J

PLANT AREA ENLARGED PLAN [1.E0 MILE RADIUS)

[NO SCALE]

MONITORING LEGEND:

() PRAIRIE ISLAND TLD POINTS I

. - - - . - - -,'A . I-- -I - -. , - ,

TLD LOCATIONS CONTROL POINTS PRESCOTT, WISCONSIN ISFS.I .REA TLD LOCATIONS MONITORING LEGEND:

(2 PRAIRIE ISLAND TLD POINTS REV. 1 D-3 TLD02.DGN

J REV. 1 0~~-3TL2.N

TLD LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:

(2) PRAIRIE ISLAND TLD POINTS

.REV..1 D-4: TL003.DGN REV. 1 D4 TLO~3.DGN

ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS N

PLANT AREA ENLARGED PLAN [1.00 MILE RADIUS)

ENO SCALE]

MONITORING: LEGEND

(> MILK SAMPLING POINT TO NUMBERS FISH SAMPLING POINT ID NUMBERS P-I4aP-l. P-37, P-42..P-43. P144 P-13. P-i*

A AIR SAMPLING POINT .10 NUMBERS P-I. P-2. P-3. P-4. P-6

.INVERTEBRATES POINT. T0 NUMBERS P-6, P-40 O WATER SAMPLING POINT 10 NUMBERS SEDIMENT SAMPLING POINT TO NUMBERS P.5.P-8, P- P-.M-I.I P-74.

9. p -43 P-ig, P-12, Pv2M

']J VEGETATION / VEGETABLES TO NUMBERS P-24. P-38.P-45 IFPt:v. I 'SAMP-01.GN b-5 REVi 0-5 SAMPOI .DGN

I ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS i

.2 MONITORING LEGEND MILK SAMPLING POINT 10 NUMBERS FISH SAMPLING POINT ID NUMBERS PKE 4, P-18. P-37. P-4Z. P-43. P-44 :P-13,.P'l9 AIR SAMPLING POINT 10 NUMBERS INVERTEBRATES POINT 10 NUMBERS P-1. P'Z..P'3, P-74, PmG- P-6. P-40 O WATER SAMPLING POINT 10 NUMBERS P-5, P4e, P-'GPq, P-11. P-24. P-43 SEDIMENT SAMPLING POINT 10 NIA-ERS

P-S. P-12. P-20 j]J VEGETATION / VEGETABLES 10 NUMBERS P-24. P-38, P-45

.REV; 1 D-6 .SAMP03.DGN IREV

-- ^II- 1.-.- -^., --. , "--" ý j - - ý.. D-6 SAMP03.DGN

ENVIRONMENTAL SAMPLING POINTS CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND

MILK SAMPLING POINT ID NUMBER8 P-14, P-18, P.37, P-41, P,42. P,43, P44 A AR SAMPLING POINT ID NUMBERS P-1, P-, PA PA4, P4 WATER SAMPLING POINT ID NUMBERS

. P4, P4, P4, P4, P11. P-43

9. VEGETATION I VEGETABLES 1DNUMBERS P-24. P42, P48 D-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 residence 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 Samoling Proaram 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:

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-1 0

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 pCiIL to 157 pCiIL (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 typec a

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, 2P-7, P-1 1, Annual 28 PZ-1, PZ-2, PZ-3, PZ-4, PZ-5, G/A H-3 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 I P-24D G/Q H-3 Well water, monthly 5 P-43(C), SW-1(C), d H-3 MW-7, MW-B, P-10 GIM 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). Al other stations are indicators.

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

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

annually.

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 PI 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. f 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 P-4 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. @ 0ON 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. @ 0°ý7N 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 Annual Mean Locations Non-Sampie Type and Locations Type Number ofa b C Routine (Units) Analyses LLD Mean (F) Location Mean (F) Mean (Fe) Results

.... _Range _ Range Range Offsite H-3 36 19 45(9/12) P11C-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 b H-3 = tritium 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 d

indicated in parentheses (F).

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 pC!/L pCi/L pCi/L pCi/L ONSITE WELLS

. il 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-1I1 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 34_1' 73 54 MW-7 Sample well Sample well ..

3125 4

43 513 MW-8 P-26 PITC well 31 P-30 Env. lab well 7 _ <19 SW-3 Cooling Tower pump 437 P-9 Plant well #2 - 242 SW-4 New Admin 65 SW-5 Pin Scmhs - 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 iL PCiIL i/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

<19 P-8 PI Cormmunity Well REMP P-6 Lock & Dam #3 well <19 PIIC-02 2077 Other Day Rd. <19 65 PIIC-22 1773 Buffalo Slough Rd. 65 62 PIIC-26 1771 Buffalo Slough Rd. 62 P-24D 63 47 35 25 23 46 36 Suter residence

<19 25 < 19 <19 <19 <19 < 19 29 < 19 < 19 < 19 P-43 Peterson Farm (Control), I _____ .~ 1 .1

< 19

<19

.~ -~ I.

<19 <19 <19 1 <19 < 19 <19 <19 < 19 <19 <19 Sw--1 Hanson Farm (Control)_ 11 .... ....

E-1 0

S~.t-.y by JohnS0n L Seo~feld onc Nonbe,- 21, 2OO7 Top of RMser Well Nort East P ..Eav VI4 59228 23556090 69a,02 MW-S 692201 2356M 088 8.0 WeS 91642 2387591 382.3, MWT m 2355714 M9.54 M aS 593 I 235M,64 697.47 593538 2356497 693.16

-I ,449 2355-91 698.19 P-2 594449 2354M2 607.72 P-3 592998 23539917 ,69.'1 P-5 5§40W2 23561 895.51

. 89"260 2354W02 699.3 P 594449

,7 235235 87.97 PZ-1 5s9e 0 2". 2.91 PZ-2 598743 23S2589 G.0 PZ-4 594202 235621598 65.53

!Z-8 591 2356299 695.93 PZ_7 94= 2358158 607.85 P2- S 595471 1 2 ,. 0',52 E-1I

ATTACHMENT 2 2007 Annual Radioactive Effluent Report Resubmitted with Corrected Pages January 01, 2007 - December 31, 2007 - Off-site Radiation Dose Assessment - Annual Radioactive Effluent Report, Supplemental Information, - Effluent and Waste Disposal Annual Report, Solid Waste and Irradiated Fuel Shipments - Attachment to the 2007 Effluent Report 27 pages follow

ENCLOSURE 1 OFF-SITE RADIATION DOSE ASSESSMENT January 01, 2007 - December 31, 2007 6 pages follow

PRAIRIE ISLANI) NUCLEAR GENERATING PLANT OFF-SITE RADIATION DOSE ASSESSMENT FOR January through December 2007 An Assessment of the radiation dose due to releases fi'om Prairie Island Nucikar Generating Plant during 2007 was performed in accordance with the Olfsite Dose Calculation Manual as required by Technical Specifications. Computed doses were well below the 40 CFR Part 190 Standards and 10 CFR Part 50 Appendix I Guidelines.

Off-site dose calculation formulas and meteorological data from the Off-site Dose Calculation Manual were used in making this assessment. Source terms were obtained from the Annual Radioactive Effluent and Waste Disposal Report prepared for NRC review for the year of 2007.

Off-site Doses from Gaseous Release Computed doses due to gaseous releases are reported in Table 1. Critical receptor location and pathways for organ doses are reported in Table 2. Gaseous release doses are a small percentage of Appendix I Guidelines.

Off-site Doses from Liquid Release Computed doses due to liquid releases are reported in Table 1. Critical receptor information is reported in Table 2. Liquid release doses, both whole body and organ, are a small percentage of Appendix I Guideline-s*. -~--- --- -~-

Doses to Individuals Due to Activities Inside the Site Boundary Occasionally sportsmen enter the Prairie Island site for recreational activities. These individuals are not expected to spend more than a few hours per year within the site boundary. Commercial and recreational river traffic exists through this area.

For purposes of estimating the dose due to recreational and river water transportation activities within the site boundary, it is assumed that the limiting dose within the site boundary would be received by an individual who spends a total of seven days per year on the river just off-shore from the plant buildings (ESE at 0.2.miles). The gamma dose from noble gas releases and the whole body and organ doses from the inhalation pathway due to Iodine 131, Iodine-133, tritium and long-lived particulates were calculated for this location and occupancy time. These doses are reported in Table 1.

Critical Receptor location and pathways for organ doses are reported in Table 2.

CORRECTED PAGE ABNORMAL RELEASES There were a total of two (2) abnormal releases for 2007. The 2007 abnormal releases are summarized below:

Leak in Waste Gas System On 10/16/07 during data review, operations noted a negative trend in total volume for the routine Waste Gas System inventory. Further investigation determined that a Waste Gas Decay Tank Release had not occurred for an atypical length of time. Ventilation monitor trend plots and weekly gas grabs were reviewed and indicated no activity. It was determined that a very small leak had been present for as much as 6 months. Engineering determined that approximately 3,000 cubic feet of waste gas was lost.

Cause: Leakage was identified at the Gas Analyzer Panel pump. The Gas Analyzer was isolated until repairs could be performed. Leakage stopped. From this location all release would have exited through Unit One Auxiliary Building Ventilation.

Corrective Action: 129 Waste Gas Decay Tank (WGDT), the inservice tank, was sampled for nuclide mix.

The identified mix was used in the release calculations but, activity levels were determined to be unrepresentatively low, due to the extended time period of release.

Activity levels of the identified mix were extrapolated to the level of the sample taken for a last WGDT release performed prior to the leak:

Nuclide uCi Released Gamma Beta Dose (mrad) Dose (mrad)

Ar-41 1.08E+02 1.08E-06 3.80E-07 Kr-85 9.50E+04 1.77E-06 1.98E-04 Kr-85M 7.62E+01 1.OOE-07 1.61E-07 Xe-133 2.44E+03 9.23E-07 2.75E-06 Xe-135 1.32E+03 2.72E-06 3.48E-06 TOTAL 6.59E-06 2.05E-04 H3 1.26E+03 uCi 2.16E-06 mfirem Activity was applied to abnormal release file RACO 193, as a Unit One Auxiliary Building Release. Release duration was conservatively set at 1 week and total dose was applied to the month of October, the 4h Quarter.

Event was captured in the site's Action Request System: CAP-01 115005.

Repairs were accomplished and the Gas Analyzer was returned to service.

Result: The dose from the activity released represented a small percentage of the total dose and was a very small percentage of limits. The dose did not impose upon the health and safety of the public.

The event was reported to the NRC Region 3 Radiation Protection (RP) Inspector, at the time of the event.

2. Leaking I1 Steam Generator Relief On 6/17/07, while pertorming a surveillance procedure on I I Steam Generator Safety Relief, CV-31084 did not completely reseat. Discharge piping temperatures increased. Ihe isolation was shut and the valve was stroked in an attempt to reset. It was determined that CV-31084 did reseat as evidenced by decreasing downstream temperatures.

Cause: CV-31084 did not fully reseat during performance of surveillance procedure. When the valve was unisolated, following performance of the SP, it leaked.

Corrective Action: CV-31084 was reisolated and stroked. Leakage ended. Work Request #25903 was issued.

Engineering provided a volume released. Based on this volume it was determined that a one second release with the valve full open would conservatively represent the release volume.

The Steam Generators were sampled and a release file was created to document the release.

The dose consequences were determined to be:

H3 1.53E+01 uCi 2.6E-09 mrem Activity was applied to abnormal release file RAB0060, as an 11 Steam Generator Steam Release.

Event was captured in the site's Action Request System: CAP-01097198.

Result: The dose from the activity released represented a small percentage of the total dose and was a very small percentage of limits. The dose did not impose upon the health and safety of the public.

The event was reported to the NRC Region 3 Radiation Protection (RP) Inspector, at the time of the event.

40CFR190 COMPLIANCE The calculated dose from the release of radioactive materials in liquid or gaseous effluents did not exceed twice the limits of IOCFR50, Appendix 1,therefore compliance with 40CFRI 90 is not required to be assessed, in this report.

SAMPLING, ANALYSIS AND LLD REQUIREMENTS The minimum sampling frequency, minimum analysis frequency and lower limit of detection (LII))

requirements, as specified in ODCM Tables 2.1 and 3.1 were not exceeded in 2007.

MONITORING INSTRUMENTATION There were no occurrences when less than the minimum required radioactive liquid and/or gaseous effluent monitoring instrumentation channels were operable as required by ODCM Tables 2.2 and 3.2.

Doses to Individuals Due to Effluent Releases from the Independent Spent Fuel Storage Facility (ISFSI)

Two (2) fuel casks were loaded and placed in the storage facility during the 2007 calendar year. The total number of casks in the ISFSI is twenty-four (24). There has been no release of radioactive effluents from the ISFSI.

CURRENT ODCM REVISION The Offsite Dose Calculation Manual was revised in 2007. The current revision is 21. The revision date is July 25, 2007. A copy is submitted with this year's report.

PROCESS CONTROL PROGRAM There were no changes made to the Process Control Program in 2007. Current manual is revision 8, August 25, 1999.

Table 1 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND PERIOD: JANUARY throuqh DECEMBER 2007 10 CFR Part 50 Appendix I Guidelines for a 2-unit site per year Gasegus Releases Maximum Site Boundry Gamma Air Dose (mrad) 6.57E-06 20 Maximum Site Boundry Beta Air Dose (mrad) 2. 05E-04 40 Maximum Off-site Dose to any organ (mrem)* 3.26E-02 30 Offshore Location Gamma Dose (mrad) 4. 86E-07 Total Body (mrem)* 1.28E-03 Organ (mrad)* 1.28E-03 30 Liquid Releases Maximum Off-site Dose Total Body (mrem) 1. 72E-03 6 Maximum Off-site Dose Organ - GI TRACT (mrem) 2.50E-03 20 Limiting Organ Dose Organ - TOTAL BODY (mrem) 1.72E-03 6

Long-Lived Particulate, 1-131, 1-133 and Tritium

Tablc 2 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND SUPPLEMENTAL INFORMATION PERIOD: JANUARY through DECEMBER 2007 Gaseous Releases Maximum Site Boundary Dose Location (From Building Vents)

Sector WNW Distance (miles) 0.4 Offshore Location Within Site Boundary Sector ESE Distance (miles) 0.2 Pathway Inhalation Maximum Off-site Sector SSE Distance (miles) 0.6 Pathways Plume, Ground, Inhalation, Vegetables Age Group Child Liquid Releases Maximum Off-site Dose Location Downstream Pathway Fish

ENCLOSURE2 ANNUAL RADIOACTIVE EFFLUENT REPORT SUPPLEMENTAL INFORMATION January 01, 2007 - December 31, 2007 9 pages follow

2007' Annual Radioactive Effluent Report REV. 0 Pad. 1 of 9 Re.'ntPe0ntion: Lifetime ANNUAL RADIOACTIVE EFFLUENT REPORT 01-JAN-07 THROUGH 31-DEC-07.;

SUPPLEMENTAL INFORMATION Prairie Island Nuclear Generating Plant Licensee: Northern States Power Company Lic#,flse Numbers: DPR-42 & DPR-60 A. Reqqulatory Limits

1. Liquid Effluents:

i. :The dosb or dose commitment to an individual from radioactive materials in liquid effluents released from the site shall be limited to:

for the-quarter 3.0 mrem to the total body 10.0 mrem to any organ for the year 6.0 mrem to the total body 20.0 mrem to any organ

2. Gaseous Effluents:

a. The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to:

noble gases S500 mrem/year total body

<3000 mrem/year skin 1-131, 1-133, H-3, LLP <1500 mrem/year to any organ

b. The dose due to radioactive gaseous effluents released from the site shall be limited to:

noble gases <10 mrad/quarter gamma

<20 mrad/quarter beta

<20 mrad/year gamma

<40 mrad/year beta 1-131,'1-133, H-3, LLP <15 mrem/quarter to any organ

<30 mrem/year to any organ

2007 Annual Radioactive Effluent Report Rev. 0 PACE2 B. Water Effluent Concentration

1. Fission and activation gases in gaseous releases:

10 CFR 20, Appendix B, Table 2, Column 1

2. Iodine and particulates with half lives greater than 8 days in gaseous releases:

!Q CFR 20, Appendix B, Table 2., Column I

3. Liquid effluents for radionuclides other than dissolved or entrained gases:

10 CFR 20, Appendix B, Table 2, Column 2

4. Liquid effluent dissolved and entrained gases:

2.OE-04 uCi/ml Total Activity C. Average Energy Not applicable to Prairie Island regulatory limits.

D. Measurements and approximations of total activity

1. Fission and activation gases Total Gem +/-25%

in gaseous releases: Nuclide Gem

2. Iodines in gaseous releases: Total Gem +/-25%

Nuclide Gem

3. Particulates in gaseous releases: Total Gem +/-25%

Nuclide Gem

4. Liquid effluents Total Gem +/-25%

Nuclide Gem E. Manual Revisions

1. Offsite Dose Calculations Manual latest Revision number: 41 Revision date: 7 /., 0 (

2007 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAC-S 3 1.0 BATCH RELEASES (LIQUID)

QTR: 01 QTR: 02 QTR: 03 QTR: 04 1.1 NUMBER OF BATCH RELEASES 4.10E+01 3.803E01 2.00E+01 5.20E301 1.2 TOTAL :TIME PERIOD (HRS) 7.36E+01 6.63E +01 3.66E+01 9.18E+01 1.3 MAXIMUM TIME PERIOD (HRS) 2.92E+00 2.30E+00 2.253+00 2.22E+00 1.4 AVERAGE TIME PERIOD (HRS) 1.80E+00 1.74E+00 1.83E+00 1.773+00 1.5 MINIMUM TIME PERIOD (HRS) 1.48E+00 9.83S-01 1.523+00 1.48E300 1.6 AVERAGE MISSISSIPPI RIVER FLOW (CPS) 1.21E+04 2.90E+04 7.24E+03 1.86EDO4 2.0 BATCH RELEASES (AIRBORNE)

QTR- 01. QTR: 02 QTR: 03 1 QTR: .04 2.1 NUMBER OF BATCH RELEASES 8.003+00 1.103+01 0.003+00 0.00E+00 2.2 TOTAL TIME PERIOD (HRS) 3.18R+01 1.423+02 0.00E+00 0.00E400 2.3 MAXIMUM TIME PERIOD (HRS) 1.143+01 2.48E+01 0.00E+00 0.00E+00 2'.4 AVERAGE TIME PERIOD (HRS) 3.983+00 1.29B+01 0.003+00 0.002*00 2.5 MINIMUM TIME PERIOD (HRS) .1.433-01: 3.33B-04 0.0-0E+00 0.00Es000 3.0 ABNOR.MAL RELEASES (LIQUID) 3.1 NUMBER OF BATCH RELEASES 3.2 TOTAL ACTIVITY RELEASED (CI) 3.3 TOTAL TRITIUM RELEASED (CI) 4.0 ABNORMAL RELEASES (AIRBORNE)

41. NUMaER OF BATCH RELEASES 4.2. TOTAL- ACTIVITY RELEASED (CI)

2007 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE 4 TABLE IA GASEOUS EFFLUENTS - SUNKATION OF ALL RELEASES QTR: 01 QTR: '02 QTR:-03 ITR ~4 5.0 FISSION AND ACTIVATION GASES 5.1 TOTAL RELEASE (CI) 0.00E+04 0.009+00 0.008+00 9'.89E402 5.2 AVERAGE RELEASE RATE (UCI/SEC). 0.003+00 0.003+0-0 0.003+00 1.268-i02 5,.3 GAMMA DOSE (MRAD) 0.O0E+00- 0.00E+00 0.003+00 6.S79106 5.4 BETA DOSE (MRAD) 0.009+00.. 0.003+00 o .ooE+00 12.05E-j04 0.OOE+00 1.00E+00 0.000+00 6.579-05 5.5 PERCENT OF GAMMA TECH SPEC (M) 5.6 PERCENT OF BETA TECH SPEC (%) 0.003+00 0.00R+0.0 0.00a+00 1.039-03 6.0 IODINES 6.. TOTAL 1-131 (CI). 0.00E+00 0.00R+00 0.00E+00

.0.004,o00 6.2 AVERAGE RELEASE RATE (UCI/SEC) 0.00.+00. 0.003+00 0.003+00 L0.00+i00 7.0 PARTICULATES 7.1 TOTAL RELEASE (CI) 4.17E-06 0.00E+00 0.003+00 0.00E+00 7.2 AVERAGE RELEASE RATE (UCI/SEC) 5.31E-07 0.003+00 0.003+00 0.003+.00 4

8.0 TRITIUM' 3.33E+00!: 3.35E+00 2.73E+0 2.38H+0 8.1 TOTAL RELEASE (CI)

.8.2 AVERAGE RELEASE RATE (UCI/SEC) 4.23E-01 4.263-011 3.473-01 3.022-01 9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCI/SEC)

LLP, AND TRITIUM (MREM) 4.

1.42E-0 9.223--03 SI. 48803 f-1 3. 4 2-1 2-3 10.0 DOSE FROM4 IODINE, 9.50RI-02 6.153-02 .2513-02 2.83-92 11.0 PERCENT OF TECH SPEC (%)

r.o o00oI0.003+0 0 . oo0+0oo 0.00 0 12.0 GROSS ALPHA.(CI)

2007 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 TABLE IC PAGE 5 GASNOUS REFLURNTS - GROUND LEVEL RELEASES (CI) 13.0 FISSION AND ACTIVATION GASNS CONTINUOUS MODE I. BATCH MODE NUCLDE NITS QTR: 01

QTR. 02 I QTR:

w 03 I QTR :

i 04 f

1ýT - -ij QTR: 02 1QTR: 03 *;j QTR: 04 AR-41 CI

_ 1.08E-04 KR-85 CI 9.50E-02

I 7.62E-05 KR-85M CI XE-133 CI 2.44E-03 XE-135 CI 1.32E-03 'I "-'

TOTALS CI 0.00E÷00 0.OOE+00 0.OOE+00 9.89E-02 0.00E+00 0.005E00 0.00E+00 0.OOE+00 14.0 IODINES CONTINUOUS MODE BATCH MODE NUCLIDE I UNITS T iOTL I QTR: 01 TQoUR: 02 1 QTR: 03 oTR" Q 04 QTUR: 01 °Rs- 0°2 QTR: 03 i, i .. , i i 1 QTR: 04 J 0.0oE+00 0.OOE+00 0.00E+00 0.00+E00 0.O +00÷ 1 0.00sE00 0.008+00 *I o.oo0+00

2007 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 01 PAGE 6 TABLE IC GASEOUS EFFLUEHTS - GROUIND LEVEL RELEASES (CONTIMUED) 15.0 PARTICULATES CONTINUOUS MODE BATCH MODE I. DE ITS TR: 01 QTR: 02 QTR: 03 QTR: 04 I-.

QT~t .01. QTR: 02 QT~i-. 03 QTR: 04 II *"

4.17E-06 TOTALS cl O.0E+00 0.00°+00

°.°O°+00 °.OOE4 00 j4.173-06 0.00E+00 0.003+00 0.00m+00

2007 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 PAGE '7 TABLE IA LIQUID EFFLUENTS - SUKKATION OF ALL RELEASES QTR, 01 02-QT1R QT 0 L QTR: 4 16.0 VOLUME OF WASTE PRIOR TO DILUTION (LITERS) L.81E+0o 2.95E+-07 2.17E-+07 4

2.32E -07

.. +

17.0 VOLUME OF DILUTION WATER (LITERS&4 18.0 FISSION AND ACTIVATION PRODUCTS 18.1 TOTAL RELEASES W/O H-3, RADGAS, ALPHA (CI) 4.84E-02 1.24E-02 4.08E-03 4.90E-"02 18.2 AVERAGE DILUTION CONCENTRATION (UCI/ML) 2.63E-10 1.18E-1O 1.59E--I 2.20E-10 19.0 TRITIUM 19.1 TOTAL RELEASE (CI) 1.47E+02 ( 2.53E+02 8.42E+01 2

.36Ei02 19.2 AVERAGE DILUTION CONCENTRATION (UCI/ML) 8.01E-07 2.41E-06 3.28E-07 1.06Et06 20.0 DISSOLVED AND ENTRAINED GASES 20.1 TOTAL RELEASE (CI) 3.51E-06 4.005-05 0.00E+00 8.73E-04 20.2 AVERAGE DILUTION CONCENTRATION .(UCI/ML) 1.91E-14 3.809-13 0.00E+00 3.93E-12 21.0 GROSS ALPHA (CI) 0.00E+00 0.008+00 0.00E+00 0.00EOOz'O 22.0 TOTAL TRITIUM, FISSION & ACTIVATION PRODUCTS (UCI/ML) 8.015-0 ).1-6 3.289-07 1.06E-wn6 23.0 TOTAL BODY DOSE (MREM) 24.0 CRITICAL ORGAN 4.16E-04' 5.77E-04 1.89E-04 5.35E-,04 24.1 DOSE (MREM)

.24.2 .ORGAN TOT BODY. TOT BODY TOT BODY TOT BO'DY LIMIT (%) 1"39E-02 1.92E-02 6.31E-03 1.78E-02 25.0 PERCENT OF TECHNICAL SPECIFICATIONS

(%) 1.39E-02 1.92E-02 6.31E-03 J_1.785-02 26.0 PERCENT OF CRITICAL ORGAN TECH-SPEC LIMIT

2007 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 TABLz 2A PAGE 8 LIQUID EFFLUENTS - SUMATION OF ALL RULEASRS (CI) 27.0 INDIVIDUAL LIQUID UFFLUBUT CONTINUOUS ;MODE BATCH MODE NULD NT. QTR: 01 QTR: 02, QTR: 03 QTR., 04 QTR: 01 QTR: 02 QTR: 03 QTR: 04 IAG-108M CI 4.17E AG-1IOM CI" 8.01E-03 4.16E-03 1.503-03 1.88E-03 BA-139* CI j _ _7.58E-06 1.04S-05 CE-13.9 CI 1.303-06 1.894-06 CO-57 CI

.1.533-06 CO-58 CO-60&

CI CI 1 4.37E-03 1.55E-03 1.213-04

§ 1.00E-06 2.32E-04 1.703-03 CR-51 4 C1 4 ...... 4 _1. 87E--03 4.853-04 7.98E-05 1.463-04 1.283-05_

4.25E-04 1.893-04 FE-55 CI 1.87 CS-137 CI 4-5______1_____

6.1819-07 FE-55 CI1______.1.27B-02

3. 8 5E-03 1.443-03 4 .7 5E- 03 FE-59 CI _

3.038-04 2.403-05 LA-140-MN-54 CI CI j I_ 8.30E-06 6.783-05 4.623-06 _1.85E306 1NA-2, CI

7.14-05 49.°293-07 N 62 7 .9-06 S85 CI 3.233-07 N ED- 7 CI9.567E-05 TL*:201 CI 4.573-05 2.323-05 2.139-05 TE-123M cCI I.3305 5.630 SN-113M CI 3.037-03 5.52E-03 TE12 CI 2.193-06 TL-1201 CI 3.05 z-O3-052 -0 (CONTINUED)

2007 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. 0 TABLE 2A PAGE 9 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (CONT INUED) 27.0 INDIVIDUAL LIQUID EFFLUENT CONTINUOUS MODE BATCH MODE NUCLDE UNII QTR:

01 *T.QTR-:0QTR:

TRT2 o T" ý*0ý4 QTR'0*02 02 TT:03. T:0 04 QTR:

i I ZR-95 CI 1i.74E-04 ZR-97 CI 13.64E-06 5.96E-06 2.20E-06 4.60E-06 ITOTALS CI 4.84E-02 1.24E-02 4.08E-03, 4.90E-02 28.0 DISSOLVED AND ENTRAINED GASES CONTINUOUS MODE BATCH MODE UNITS QTR: 01 QR 02 QTR, 03 QTR: 04 QTR: 01 I I I i I QTR -02: 1~.QT-R z- -03TR QTR: 04 KR-85 j CI _ 7.46E-04 XE-133 CI 3.51E-06 3.71E-05 1.27E-04 XE-135 CI 2.88E-06 TOTALS CI 3.51E-06 4.OOE-05 O.OOE÷00 8.73E-04

ENCLOSURE3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS January 01, 2007 - December 31, 2007 7 pages follow

PINGP 753, Rev. 7 Page 1 of 7 Retention: Life PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01/01/07-12/31/07 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

Solid Waste Total Volumes and Total Curie Quantities:

-CONTAINER rA,L DISPOSAL~

% VOL (ft3)

0) (LIST) m3 o 1.02E+01 179.4 ft 3.59E+02 Ci 5.59E-01 2.50E+01 m3 B. Dry-Compacted ft3 Ci C. Non-Compacted ft 3 2.90E+02 1280 1.02E+04 Ci 3

8.08E-01 2.50E+01 D. Filter Media m 3

Wf Ci 3

S. Other (furnish description) m 7.25E+01 1280 Combined DAW/Charcoal/Grit ft3 2.56E+03 Ci 6.35E-02 2.50E+01 The solid waste information provided in this report is the volume and activity of the low-level waste leaving the Prairie Island site.

No allowance is made for off-site volume reduction prior to disposal.

Document2

PINGP 753, Rev. 7 Page 2 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-07/12-31-07 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) [continued]

2. Principal Radionuclide Composition by Type of Waste:

(Bold letter designation from Page 1)

TYPE Percent %

Abundance Nuclide (0.00E0)

Fe-55 6.35E+01 C

Co-58 8.85E+00 Co-60 8.07E+00

NI-63 1.19E+01 Zr-95 2.01E+00 Nb-95 1.59E+00 1% cutoff S *Fe-55 2.77E+01 Co-58 4.40E+00 Co-60 4.96E+00 Nb-95 1.16E+00 Zr-95 1.03E+00

C-14 7.85E+00

Ni-63 1.58E+01

H-3 3.50E+01 1% cutoff

= Inferred - Not Measured on Site

PINGP 753, Rev. 7 Page 3 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-07/12-31-07 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) [continued]

2. Principal Radionuclide Composition by Type of Waste (Continuation):

(Bold letter designation from Page 1)

TYPE Percent %

Abundance Nuclide (O.OOEO)

H-3 1.18E+00 A *Fe-55 3.48E+01

Ni-63 3.53E+01 Co-60 1.33E+01 Co-58 1.14E+00 Cs-137 3.83E+00 C-14 3.51 E+00 Sb-125 5.61 E+00 1% cutoff

= Inferred - Not Measured on Site

PINGP 753, Rev. 7 Page 4 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-07/12-31-07 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) [continued]

3. Solid Waste Disposition:

Number of Shipments Mode Destination 5 StudsvikLogistics StudsvikRACE, LLC 2 Hittman Transport Studsvik Processing Facility, Services LLC

PINGP 753, Rev. 7 Page 5 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-07t12-31-07 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) [continued]

4. Shipping Container and Solidification Method:

Disposal No. Volume Activity Type of Container Solidif.

(Ft 3/m3) (Ci) Waste Code Code 07-004 2560/72.5 0.390 C L N/A 07-005 2560/72.5 0.141 C L N/A 07-006 2560/72.5 0.226 C L N/A 07-011 179.4/5.1 0.296 A L N/A 07-012 179.4/5.1 0.263 A L N/A 07-018 2560/72.5 0.065 C L N/A 07-019 2560/72.5 0.049 C L N/A I

TOTAL 7 13200/373 1.43 S

CONTAINER CODES: L = LSA (Shipment type) .A = Type A B = Type B Q = Highway Route Controlled Quantity SOLIDIFICATION CODES: C = Cement TYPES OF WASTES: A = Resins B = Dry Compacted C = Non-Compacted D = Filter Media S = Other

PINGP 753, Rev. 7 Page 6 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-07/12-31-07 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)

Number of Shipments Mode Destination 0

PINGP 753, Rev. 7 Page 7 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 01-01-07/12-31-07 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS C. PROCESS CONTROL PROGRAM CHANGES TITLE: Process Control for Solidification/Dewatering of Radioactive Waste from Liquid Systems Current Revision Number: 8 Effective Date: 8/25/1999 If the effective date of the PCP is within the period covered by this report, NOrE: then a description and justification of the changes to the PCP is required (T.S.6.5.D) (S5 Attach the sidelined pages to this report.

Changes/Justification: N/A

ENCLOSURE4 ATTACHMENT TO THE 2007 EFFLUENT REPORT Description and Dose Assessment of Quarter I of 2007 Leak Communicated per ODCM (H4, Section 8.4) Industry Initiative on Groundwater Protection 1 page follows

CORRECTED PAGE ATTACHMENT TO THE 2007 ANNUAL EFFLUENT REPORT Amended Liquid Pathway Dose Calculation Quarter 1, 2007 Summary This calculation did not change the total liquid dose to the critical receptor for the first quarter of 2007.

Background

On March 21, 2007, approximately 150 gallons of secondary steam condensate leaked to the ground outside the west side of the turbine building during transfer of turbine building sump water to the landlocked canal. This water had a tritium concentration of 5,150 pCi/L.

The transfer of water was secured and no further leakage to the environment occurred.

This release occurred from a monitored release path.

ODCM Considerations Since the release occurred via a monitored release path, the dose calculations were performed per the ODCM. The released effluent did not flow to the normal landlocked location but was absorbed into the ground closer to the turbine building. At this location, the water has farther to travel to the receptor and is subject to greater dispersion than the normal release location. The ODCM dose calculations over-estimate the dose from this release. Corrective actions have been taken to prevent a similar spill in the future.

Dose Calculation Assumptions The dose calculation was performed per the ODCM for the annual effluent report. This dose over-estimates the dose under the conditions of this release. No revision to the ODCM dose calculation is warranted.

Discussion The critical receptor is located 0.6 miles to the SSE of the Prairie Island site. The leaked water would have to travel in the groundwater under the recycle canal and discharge canal to reach the critical receptor. This assumed water flow maximizes the dose because the normal groundwater flow is towards the Vermillion River which would not carry the tritium toward the critical receptor.

L-PI-09-103, Corrections to the 2007 Annual Radiological Environmental Monitoring Program (REMP) Report and the 2007 Annual Radioactive Effluent Report

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