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

{{Adams
| number = ML092870173
| issue date = 10/07/2009
| title = Corrections to the 2007 Annual Radiological Environmental Monitoring Program (REMP) Report and the 2007 Annual Radioactive Effluent Report
| author name = Schimmel M
| author affiliation = Northern States Power Co, Xcel Energy
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NMSS, NRC/NRR
| docket = 05000282, 05000306, 07200010
| license number = DPR-042, DPR-060, SNM-2506
| contact person = 
| case reference number = L-PI-09-103
| document type = Environmental Monitoring Report, Letter type:L
| page count = 102
}}

=Text=
{{#Wiki_filter:&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 &deg; 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.
1

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.
11

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  C&#xfd;)      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        C&#xfd;   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&deg;/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&deg;/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&deg;/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&deg;/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&deg;/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&deg;/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&deg;/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&deg;/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&deg;/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&deg;/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 hours        Sampler pump was replaced with 1-131                                    run-time logged. a calibrated spare.
AP/Al        Beta,       P-01        8/15/2007         Only 66 hours        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&deg; /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&deg; /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&deg;/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&deg;/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) &deg;'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.-.-     -^., --. , "--" &#xfd; j        -  -  &#xfd;..        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&deg;/SE PIIC-02                 2077 Other Day Road          WW               1.4 mi. f 315&deg;/NW PIIC-22                1773 Buffalo Slough Rd        WW                 1 mi. @ 315*/NW PIIC-26                1771 Buffalo Slough Rd        WW                 1 mi. @ 315&deg;/NW P-24D                     Suter residence           WW               0.6 mi. @ 158&deg;/SSE P-43                Peterson Farm (Control)        WW                13.9 mi. @ 355&deg;/N SW-1                  Hanson Farm (Control)         WW               2.2 mi. @ 315&deg;/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&deg;/WSW P-30                     Environ lab well           WW               0.2 mi._@ 32&deg;/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&deg;/NW SW-5                  Plant Screenhouse well         Ww                 0.05 mi. @ 0ON P-9                        Plant well # 2           WW               0.3 mi. @ 306&deg;/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&deg;&#xfd;7N 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&sect;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
1&#xfd;T   - -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&#xf7;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     &deg;Rs-  0&deg;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&#xf7; 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&deg;+00
                                         &deg;.&deg;O&deg;+00    &deg;.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
                                                                                                                                           &sect;  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.&deg;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"              &#xfd;*0&#xfd;4                  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&#xf7;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.}}