Text

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

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

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

Michael D. Wadley

/7 Site Vice President, Prairie Isla kd Nuclear Generating Plant Nuclear Management Company, LLC Enclosure cc:

Regional Administrator, USNRC, Region III Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector, Prairie Island Nuclear Generating Plant Dr. John House, USNRC, Region III Director of NMSS, USNRC Tim Donakowski, State of Minnesota PI Dakota Community Environmental Coordinator 1717 Wakonade Drive East 9 Welch, Minnesota 55089-9642 Telephone: 651.388.1121

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

j Environmental, Inc..

Midwest Laboratory' S

an Allegheny Technologies Co.

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

fax (847) 564-4517 XCEL ENERGY CORPORATION PRAIRIE ISLAND NUCLEAR GENERATING PLANT ANNUAL REPORT To the UNITED STATES NUCLEAR REGULATORY COMMISSION

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

-Docket No.72-10 License No. DPR-42 DPR-60 SNM-2506 Prepared under Contract by ENVIRONMENTAL, Inc.

.MIDWEST LABORATORY Project No. 8010 Approved:

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

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

ii

TABLE OF CONTENTS Section Page Preface...........................................................................................................................................................

ii List of Tables.................................................................................................................................................

iv List of Figures.................................................................................................................................................

v 1.0 INTRO DUCTIO N.............................................................................................................................................

1 2.0 SUM MARY......................................................................................................................................................

2 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP)........................................................

3 3.1 Program Design and Data Interpretation.........................................................................................

3 3.2 Program Description.............................................................................................................................

4 3.3 Program Execution..............................................................................................................................

5 3.4 Laboratory Procedures.........................................................................................................................

6 3.5 Program M odifications.......................................................................................................................

6 3.6 Land Use Census.................................................................................................................................

6 4.0 RESULTS AND DISCUSSIO N........................................................................................................................

7 4.1 Atm ospheric Nuclear Detonations and Nuclear Accidents.............................................................

7 4.2 Sum m ary of Preoperational Data.....................................................................................................

7 4.3 Program Findings.................................................................................................................................

8 5.0 FIGURES AND TABLES...............................................................................................................................

12

6.0 REFERENCES

CITED.........................................................................................................................

25 APPENDICES A

Interlaboratory Com parison Program Results..........................................................................................

A-1 Attachm ent 1, Acceptance Criteria for "Spiked" Sam ples........................................................................

A-2 B

Data Reporting Conventions.......................................................................................................................

B-1 C

Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas............ *..................................................

I

............ C-1 D

Sam pling Location M aps.............................................................................................................................

D-1 E

Special W ell and Surface W ater Sam ples..................................................................................................

E-1 iii

LIST OF TABLES No.

Title Pa_ e 5.1 Sample Collection and Analysis Program....................................................................................................

15 5.2 Sampling Locations..........................................................................................................................................

16 5.3 M issed Collections and Analyses.....................................................................................................................

19 5.4 Radiation Environmental Monitoring Program Summary............................................................................

20 In addition, the following tables can be found in the Appendices:

Appendix A A-1 Environmental Resources Associates, Crosscheck Program Results......................................................

A1-1 A-2 Program Results; (TLDs)..............................................................................................................................

A2-1 A-3 In-house "Spiked" Samples.....................................................................

...... A3-1 A-4 In-house "Blank" Samples.............................................................................................................................

A4-1 A-5 In-house "Duplicate" Sam ples......................................................................................................................

A5-1 A-6 Department of Energy MAPEP comparison results..................................................................................

A6-1i A-7 Environmental Resources Associates, Crosscheck Program Results (EML study replacement)................. A7-1 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas...........................................................................................

C-2 Appendix E E-4.1 Sample collection and analysis program........................................................................................................

E-6 E-4.2 Sam pling locations..........................................................................................................................................

E-7 E-4.3 REMP Summary..............................................................................................................................................

E-8 E-4.4 REMP Com plete Data Table...........................................................................................................................

E-9 iv

LIST OF FIGURES No.

Title Paqe 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator locations versus control.......................................................................................................................................

13 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6) versus control location (P-i).................. *......................................................................

14 In addition, the following figure can be found in the Appendices:

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

E-11 v

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiation Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December, 2007. This program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the plant on its surroundings.

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

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

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

Unit 2 achieved initial criticality on 17 December 1974.

Commercial operation at full power began on 21 December 1974.

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.

2

3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation The purpose of the Radiation Environmental Monitoring Program (REMP) at the Prairie Island Nuclear Generating Plant is to assess the impact of the plant on its environment.

For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content.

In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs).

Sources of environmental radiation include the following:

(1)

Natural background radiation arising from cosmic rays and primordial radionuclides; (2)

Fallout from atmospheric nuclear detonations; (3)

Releases from nuclear power plants; (4)

Industrial and medical radioactive waste; and (5)

Fallout from nuclear accidents.

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

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

An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected-from the plant site. The plant's monitoring program includes analyses for tritium and iodine-131. Most samples are analyzed for gamma-emitting isotopes with results for the following groups quantified:

zirconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40. The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which. they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor:

each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown. On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-1 37 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963).

Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope.

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

The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141.

These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the final group, manganese-54, iron-59, cobalt-58 and -60, and zinc-65, are activation products and arise from activation of corrosion products.

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

3

3.1 Program Design and Data Interpretation (continued)

Other means of distinguishing sources of environmental radiation are employed in interpreting the data. Current radiation levels are compared with previous levels, including those measured before the Plant became operational. Results of the plant's monitoring program can be related to those obtained in other parts of the world.

Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g., atmospheric nuclear detonations.

3.2 Program Description The sampling and analysis schedule for the radiation environmental monitoring program at Prairie Island is summarized in Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the reactor-site or ISFSI facility, as appropriate. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Prairie Island Nuclear Generating Plant, 2007). Maps of fixed sampling locations are included in Appendix D.

To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Airborne iodine is collected by continuous pumping through charcoal filters at these same locations. Filters are changed and counted weekly. Particulate filters are analyzed for. gross beta activity and charcoal filters for iodine-1 31. Quarterly composites of particulate filters from each location are determined by gamma spectroscopy.

One of the five locations is a control (P-i), and four are indicators (P-2, P-3, P-4, and P-6).

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

They are replaced and measured quarterly.

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

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

For additional monitoring of the terrestrial environment, green leafy vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (P-38), and analyzed for gamma-emitting isotopes, including iodine-131.

Corn is collected annually only if fields are irrigated with river water and analyzed for gamma-emitting isotopes. Well water and ground water are collected quarterly from four locations near the plant and analyzed for tritium and gamma-emitting isotopes.

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

4

3.2 Prooram Descriotion (continued)

Drinking water is collected weekly from the City of Red Wing well.

Monthly.composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.

The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, periphyton or invertebrates, and bottom sediments. Shoreline sediment is collected semi-annually from one location.

All samples are analyzed for gamma-emitting isotopes.

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

(1)

Air Particulates / Air Iodine:

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

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

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

The filter was missing.

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

(2)

Milk:

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

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

(3)

Thermoluminescent Dosimeters:

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

Deviations from the program are summarized in Table 5.3.

5

3.4 Laboratory Procedures The iodine-1 31 analyses in milk and drinking water were made using a. sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method and solvent extraction and subsequent beta counting.

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

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

Tritium concentrations are determined by liquid scintillation.

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

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

EERF, Radiochemical Procedures Manual, 1984.

Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained.

Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2003 ). The QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs.

Results obtained in the crosscheck programs are presented in Appendix A.

3.5 'Progqram Modifications The Gustafsen Dairy (P-14) sold their herd in September, 2007. Dairy operations were discontinued.

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

animal, the nearest residence, and the nearest garden of greater than 500 ft producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles.

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

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

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

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

Therefore, no corn samples were collected for analysis.

6

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

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

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

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

2 fallout declined yearly from a level of 12,167 pCi/m to 1,020 pCi/m, and these declining values

are reflected throughout the various media tested.

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

7

4.3 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant.

Ambient Radiation (TLDs)

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

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

Average (Inner and Average (Inner and Year Outer Rings)

Control Year Outer Rings)

Control 1992 16.3 14.8 2000 17.0 17.1 1993 -

15.9 15.4 I

2001 16.8 1

17.2 1994 15.2 16.0 2002 17.4 1

16.9 1995 15.6 16.6 2003 16.2 1

16.0 1996 14.8 16.4 2004 17.6 17.6 1997 15.1 16.0 2005 16.8 1

16.3 1998 16.7 17.3 IT 2006 16.6 16.6 1999 I

16.6 17.5 2007 I

17.5 1

17.7 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates (mR/91 days).

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

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

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

8

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

Average of Year Indicators Control 3

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

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

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

The increase in gross beta activity was matched by elevations of Be-7 concentrations, detected in the quarterly composites of air particulate filters. Gamma spectroscopic analysis yielded proportionally higher results for both indicator and control locations.

Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and AI-Salih, 1955) was detected at an average activity of 0.096 pCi/m3 for all locations, versus an average of 0.070 pCi/m3 in 2006. All other gamma-emitting isotopes were below their respective LLD limits.

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

9

Milk Iodine-1 31 results were below the detection limit of 0.5 pCi/L in all samples. Cs-1 37 results were below the LLD level of 5 pCi/L in all samples.

No other gamma-emitting isotopes, except naturally-occurring potassium-40, were detected in any milk samples. This is consistent with the findings of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center. for Radiological Health, 1968).

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

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

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

Year Gross Beta (pCi/L) 1992 7.6 1993 7.5 1994 5.8 1995 3.9 1996 6.3 1997 5.1 1998.

5.4 1999 1

5.3 2000 10.1 20018.

2002 8.7 2003 9.9 2004 9.8 2005 11.5

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

10

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.

Indicator 20 19 18 17 16 15 14 13 E

12 11 10

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

Indicators (P-2,3,4,6) 0.039 0;037 0.035 0.033 0.031 0.029 0.027 0.025 E- 0.023 0.021 0.019 0.017 A AIR

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____-~

___ I

___ I 1 j

~

___ [

I I

__ I

~__

11:1 I

_____ I

_____ ~

_____ F

_____ K

______ F

______ F-

__ t F

__ L

____ t 0015

-N N)

N)j N) pN)

N)

CO C O

C O

O C

o 0

0 0

C0 0

. 0 0

0>

wO (0

(

(O CO to CD ED 0

0 0D 0D 0

0 0D N) w

4.

(11

0)

-14 CO CD PQ

-w

1).4.

C-1 (D

4 0.039 0.037 0.035 0.033 0.031 0.029 0.027 0.025 a-0.023 0.021 0.019 0.017 n n1n I----Control (P-i)

I

_ I I

_ I T_

L i_

_ 1

_ _I I_

I I__

I- ! I r 1 1 __ 2!

___i__

CO C0 0

0 0

C 0

CAO CD Co CO CO CO CD CO 0

0 0

C0 0

0 0

C0 N)

&)

4 Ci'

0)

-4 CO CO

0) r)

W~

-rý 01

0)

-4 14

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

Collection Analysis Location Type and Type and Medium No.

Codes (and Type)a Frequencyb Frequencyc Ambient radiation (TLD's) 54 P-OI.A - P-IOA P-0113 - P-15B P-O1S - P-08S P-OIIA - P-081A P-01113 - P-081B P-OIIX-P-041X, P-OIC C/Q Ambient gamma Airborne Particulates P-1(C), P-2, P-3, P-4, P-6 Airborne Iodine 5

P-I(C), P-2, P-3, P-4, P-6 5

P-14, P-18, P-37, P-42, P-44, P-43 (C)

Milk River water Drinking water 2

P-5(C), P-6 C/W C/W G/M d G/W G/W G/Q G/A 1-131 1-131, GS GB,GS(QCof each location) 1 P-11 GS(MC), H-3(QC)

GB(MC), 1-131(MC)

GS (MC), H-3 (QC)

H-3, GS Well water 5

P-6, P-8, P-9, P-24, P-43 (C)

Edible cultivated crops -

leafy green vegetables Fish (one species, edible portion)

Periphyton or invertebrates Bottom sediment Shoreline sediment 2

P-38(C), P-24 2

P-19(C), P-13 2

P-40(C),.P-6 2

P-20(C), P-6 1

P-12 G/SA G/SA G/SA G/SA GS (I-13 1)

GS GS GS GS a Location codes are defined in Table D-2. Control stations are indicated by (C). All other stations are indicators.

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

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

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

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

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

15

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

Distance and Direction from Code Typea Collection Site Sample Typeb Reactor P-1 P-2 P-3 P-4 P-5 P-6 P-8 P-9 P-11 P-12 P-13 P-14 P-18 P-19 P-20 P-24 P-37 P-38 P-40 P-42 P-43 P-44 C

Air Station P-1 Air Station P-2 Air Station P-3 Air Station P-4 C

Upstream of Plant Lock and Dam #3 &.Air Station P-6 Community Center Plant Well #2 Red Wing Service Center Downstream of Plant Downstream of Plant Gustafson Farm Christiansen Farm C

Upstream of Plant C

Upstream of Plant Suter Residence Welsch Farm C

Cain Residence C

Upstream of Plant Rother Farm C

Peterson Farm Yoemans Farm AP, Al AP, Al AP, Ai AP, Al RW AP, Al, RW WW, BS, BOC WW WW DW SS Fc M

M Fc BS VE, WW M

VE BOC M

M, WW M

11.8 mi @ 3160/NNW 0.5 mi @ 2940/WNW 0.8 mi @ 3130/NW 0.4 mi @ 3590/N 1.8 mi @ 11 0/N 1.6 mi @ 1290/SE 1.0 mi @ 3210/WNW 0.3 mi @ 3060/NW 3.3 mi @ 1587/SSE 3.0 mi @ 1160/ESE 3.5 mi @ 1130/ESE 2.3 mi @ 1730/S 3.8 mi @ 88°/E 1.3 mi @ O°/N 0.9 mi @ 450/NE 0.6 mi @ 1580/SSE 4.1 mi @ 870/E 14.2 mi @ 3590/N 0.4 mi @ O/N 4.3 mi. @ 2640/W 13.9 mi. @ 3550/N 2.0 mi. @ 2140/SW General Area of the Site Boundary P-OIA P-02A P-03A P-04A P-05A P-06A P-07A P-08A P-09A P-1OA Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 0.4 mi @ 3590/N 0.3 mi @ 100/N 0.5 mi @ 1830/S 0.4 mi @ 2040/SWW 0.4 mi @ 2250/SW 0.4 mi @ 2490/WSW 0.4 mi @ 2680/W 0.4 mi @ 2910/WNW 0.7 mi @ 3170/NW 0.5 mi @ 3330/NNW 16

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

Distance and Direction from Code Type0 Collection Site Sample Typeb Reactor Approximately 4 to 5 miles Distant from the Plant P-OIB P-02B P-03B P-04B P-05B P-06B P-07B P-08B P-09B P-101 P-1iB1 P-12B P-13B P-14B P-15B Thomas Killian Residence Roy Kinneman Residence Wayne Anderson Farm Nelson Drive (Road)

County Road E and Coulee William Hauschiblt Residence Red Wing Public Works David Wnuk Residence Highway 19 South

'Cannondale Farm Wallace Weberg Farm Ray Gergen Farm Thomas O'Rourke Farm David J. Anderson Farm Hoist Farms TLD 4.7 mi @ 3550/N TLD 4.8 mi @ 170/NNE TLD 4.9 mi @ 460/NE TLD 4.2 mi @ 610 /ENE TLD 4.2 mi @ 1020/ESE TLD 4.4 mi @ 1120/ESE TLD 4.7 mi @ 1400/SE TLD 4.1 mi @ 1650/SSE TLD 4.2 mi @ 1870/S TLD 4.9 mi @ 2000/SSW TLD 4.5 mi @ 2210/SW TLD 4.6 mi @ 2510/WSW TLD 4.4 mi @ 2700/W TLD 4.9 mi @ 3060/NW TLD 3.8 mi @ 3450/NNW Special Interest Locations P-015S P-02S P-03S P-04S P-05S P-06S P-07S P-08S P-01C Federal Lock & Dam #3 Charles Suter Residence Carl Gustafson Farm Richard Burt Residence Kinney Store Earl Flynn Farm Indian Community Indian Community C

Robert Kinneman Farm TLD TLD TLD TLD TLD TLD TLD TLD TLD 1.6 mi @ 1290/SE 0.5 mi @ 155 0/SSE 2.2 mi @ 1730/S 2.0 mi @ 2020/SSW 2.0 mi @ 2700/W 2.5 mi @ 2990/WNW 0.7 mi @ 2710/W 0.7 mi @ 2870/NWW 11.1 mi @ 3310/NNW 17

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

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

ISFSI Area Inside Earth Berm P-Oi.IA P-021A P-031A P-041A P-051A P-061A P-071A P-OSIA P-0+/-tIX P-021X P-031X P-041X ISFSI Nuisance Fence ISFS1 Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence ISFSI Nuisance Fence TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 190' @ 450/NE 360'@ 82'/E 370' @ 100-/E 200' @ 1340 /SE 180' @ 219°/SW 320' @ 258°/WSW 320' @ 281"!/WNW 190' @ 318°/NW 140' @ 1800/S 310'@ 270°/W 140' @ 0/N 360'@ 90-/E ISFSI Area Outside Earth Berm P-01.I1 P-021B P-031B P-0411B P-051B P-061B P-0711B P-08113 ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area ISFSI Berm Area TLD TLD TLD TLD TLD TLD TLD TLD 340' @ 30/N 380' @ 28°/NNE 560'@ 85-/E 590' @ 165"/SSE 690'@ 1860/S 720' @ 201"/SSW 610' @ 271'/W 360' @ 332°/NNW a "C" denotes control location. All other locations are indicators.

b Sample Codes:

AP Airborne particulates F

Fish Al Airborne Iodine M

Milk BS Bottom (river) sediments SS Shoreline Sediments BO Bottom organisms SW Surface Water (periphyton or macroinvertebrates)

VE Vegetation/vegetables DW Drinking water WW Well water c Distance and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location.

18

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

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

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

Beta, P-02 2/21/2007 Sampler pump failure.

Sampler pump was replaced with 1-131 a calibrated spare.

AP

Beta, P-06 4/18/2007 Filter not installed.

None required.

TLD Ambient P-07B 2nd. Qtr.

TLD missing in field.

None required.

Gamma 2007 AP/AI

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

AP/AI

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

a calibrated spare.

Ml

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

Ml

Gamma, P-44 Jan., Nov., Dec.,

Goats were dry.

The goat milk is available during 1-131 2007 the grazing season.

19

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota

( County, State Docket No.

50-282, 50-306 Reporting Period January-December, 2007 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units)

Analysesa Rangec Locationd Rangec Rangec Results' TLD (Inner Ring, Gamma 40 3.0 16.8 (40/40)

P-06A 18.2 (4/4)

(See Control 0

Area at Site (13.5-19.0) 0.4 mi @ 249° /WSW (17.5-19.0) below.)

Boundary) mR/91 days)

TLD (Outer Ring, Gamma 59 3.0 17.9 (59/59)

P-02B, Roy Kinneman, 19.8 (4/4)

(See Control 0

4-5 mi. distant)

(14.5-20.9) 4.8 mi @ 170 /NNE (18.9-20.9) below.)

mRR91 days)

TLD (Special Gamma 32 3.0 16.9 (32/32)

P-03S, Gustafson Farm,

.19.4 (4/4)

(See Control 0

Interest Areas)

(14.1-20.9) 2.2 mi @ 1730/S (18.4-20.4) below.)

mRI91 days)

TLD (Control)

Gamma 4

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

(16.2-19.5)

Airborne GB 259 0.005 0.037 (207/207)

P-03, Air Station 0.041 (52 /52) 0.031 (52/52) 0 Particulates (0.005-0.081) 0.8 mi @ 3130 /NW (0.019-0.081)

(0.015-0.069)

(pCi/m 3)

GS 20 Be-7 0.015 0.102 (16/16)

P-03, Air Station 0.114 (4/4) 0.073 (4/4) 0 (0.046-0.182) 0.8 mi @ 3130/NW (0.066-0.179)

(0.052-0.099)

Mn-54 0.0007

< LLD

< LLD 0

Co-58 0.0007

< LLD

< LLD 0

Co-60 0.0009

< LLD

< LLD 0

Zn-65 0.0008

< LLD

< LLD 0

Zr-Nb-95 0.0010

< LLD

< LLD 0

Ru-103 0.0008

< LLD

< LLD 0

Ru-106 0.0066

< LLD

< LLD 0

Cs-134 0.0006

< LLD

< LLD 0

Cs-137 0.0008

< LLD

< LLD 0

Ba-La-140 0.0038

< LLD

< LLD 0

Ce-141 0.0017

< LLD

< LLD 0

Ce-144 0.0043

< LLD

< LLD 0

,Airborne Iodine 1-131 259 0.03

< LLD

< LLD 0

(pCi/m 3) 20

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility I

Prairie Island Nuclear Power Station Goodhue, Minnesota

( County, State)

Docket No.

Reporting Period 50-282, 50-306 January-December, 2007 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units)

Analysesa Rangec Locationd Rangec Rangec Resultse Milk (pCi/L) 1-131 100 0.5

< LLD

< LLD 0

GS 100 K-40 200 1468 (82/82)

P-44, Yoemans Farm 1819 (15 /15) 1441 (18/18) 0 (1190-2152) 2.0 mi @ 214°/SW (1231-2152)

(1351-1571)

Cs-134 5

< LLD

< LLD 0

Cs-137 5

< LLD

< LLD 0

Ba-La-140 5

< LLD

< LLD 0

River Water H-3 8

500

< LLD

< LLD 0

(pCi/L)

GS 24 Mn-54 10

< LLD

< LLD 0

Fe-59 30

< LLD

< LLD 0

Co-58 10

< LLD

< LLD 0

Co-60 10

< LLD

< LLD 0

Zn-65 30

< LLD

< LLD 0

Zr-Nb-95 15

< LLD

< LLD 0

Cs-134 10

< LLD

< LLD 0

Cs-137 10

< LLD

< LLD 0

Ba-La-140 15

< LLD

< LLD 0

Ce-144 43

< LLD

< LLD 0

21

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota

( County, State)

Docket No.

50-282, 50-306 Reporting Period January-December, 2007 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units)

Analysesa Rangec Location d Rangec Rangec Resultse Drinking Water GB 12 1.0 11.6 (12/12)

P-11, Red Wing S.C.

11.6 (12/12)

None 0

(pCi/L)

(6.9-17.5) 3.3 mi @ 1580 /SSE (6.9-17.5) 1-131 12 1.0

< LLD None 0

H-3 4

500

< LLD None 0

GS 12 Mn-54

10.

< LLD None 0

Fe-59 30

< LLD None 0

Co-58 10

< LLD None 0

Co-60 10

< LLD None 0

Zn-65 30

< LLD None 0

Zr-Nb-95 15

< LLD None 0

Cs-134 10

< LLD None 0

Cs-137 10

< LLD None 0

Ba-La-140 15

< LLD None 0

Ce-144 51

< LLD None 0

Well Water H-3 20 500

< LLD

< LLD 0

(pCi/L)

GS 20 Mn-54 10

< LLD

< LLD 0

Fe-59 30

< LLD

< LLD 0

Co-58 10

< LLD

< LLD 0

Co-60 10

< LLD

< LLD 0

Zn-65 30

< LLD

<- LLD 0

Zr-Nb-95 15

< LLD

< LLD 0

Cs-134 10

< LLD

< LLD 0

Cs-137 10

< LLD

< LLD 0

Ba-La-140 15

< LLD

< LLD 0

Ce-144 42

< LLD

< LLD 0

Crops - Cabbage 1-131 3

0.033

< LLD

< LLD 0

(pCi/gwet) 22

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Docket No.

50-282, 50-306 Reporting Period January-December, 2007 Goodhue, Minnesota

( County, State )

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

Analysesa Rangec Locationd Rangec Rangec Resultse Fish GS 4

,(pCi/g wet)

K-40 0.10 3.17 (2/2)

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

(3.40-3.47)

Mn-54 0.014

< LLD

< LLD 0

Fe-59 0.091

< LLD

< LLD 0

Co-58 0.022

< LLD

< LLD 0

Co-60 0.023

< LLD

< LLD 0

Zn-65 0.021

< LLD

< LLD 0

Zr-Nb-95 0.029

< LLD

< LLD 0

Cs-134 0.020

< LLD

< LLD 0

Cs-137 0.024

< LLD

< LLD 0

Ba-La-140 0.12

< LLD

< LLD 0

Invertebrates GS 4

(pCi/g wet)

.Be-7 0.69

< LLD

< LLD 0

K-40 0.74

< LLD

< LLD 0

Mn-54 0.035

< LLD

< LLD 0

Co-58 0.060

< LLD

< LLD 0

Co-60 0.036

< LLD

< LLD 0

Zn-65 0.062

< LLD

< LLD 0

Zr-Nb-95 0.18

< LLD

< LLD 0

Ru-103 0.13

< LLD

< LLD 0

Ru-106 0.31

< LLD

< LLD 0

Cs-1 34 0.032

< LLD

< LLD 0

Cs-137 0.030

< LLD

< LLD 0

Ba-La-140 2.36

< LLD

< LLD 0

Ce-141 0.30

< LLD

.0 Ce-144 0.19

< LLD

< LLD 0

23

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Prairie Island Nuclear Power Station Goodhue, Minnesota

( County, State)

Docket No.

50-282, 50-306 Reporting Period January-December, 2007 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units)

Analyses' Rangec Locationd Rangec Rangec Resultse Bottom and GS 6

Shoreline Be-7 0.33

< LLD

< LLD 0

Sediments (pCi/g dry)

K-40 0.10 7.83 (4/4)

P-20, Upstream 9.11 (2/2) 9.11 (2/2) 0 (6.93-8.85) 0.9 mi. @ 45°/NE (9.00-9.21)

(9.00-9.21)

Mn-54 0.028

< LLD

< LLD 0

Co-58 0.034

< LLD

< LLD 0

Co-60 0.021

< LLD

< LLD 0

Zn-65 0.068

< LLD

<- LLD 0

Zr-Nb-95 0.067

< LLD

<- LLD 0

Ru-103 0.040

< LLD

< LLD 0

Ru-106 0.14

< LLD

< LLD 0

Cs-134 0.029

< LLD

<- LLD 0

Cs-1 37 0.022

< LLD

<- LLD 0

Ba-La-140 0.39

< LLD

< LLD 0

Ce-141 0.13

< LLD

< LLD 0

Ce-144 0.17

< LLD

< LLD 0

a GB = gross beta, GS = gamma scan.

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

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

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

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

24

6.0 REFERENCES

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

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

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

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

2003.

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

2005.

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

2003.

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

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

Hazleton Environmental Sciences Corporation.

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

1979b to 1983b.

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

Hohenemser, C. M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel.

1986.

"Chernobyl," Chemtech, October 1986, pp. 596-605.

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

Northern States Power Company.

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

1979 to 2006.

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

Minneapolis, Minnesota.

Prairie Island Nuclear Generating Plant, 2007.

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

Teledyne Brown Engineering Environmental Services, Midwest Laboratory.

1984a to 2000a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January

- December, 1983 through 1999.

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

25

6.0 REFERENCES

CITED (continued)

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

U.S. Environmental Protection Agency.

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

1984.

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

2007.

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

Wilson,- D. W., G. M. Ward and J. E. Johnson.

1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125.

Xcel Energy Corporation. 2008. Monticello Nuclear Generating Plant, Annual Radiation Environmental-Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2005-2007 (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 26

Environmental, Inc.

Midwest Laboratory n Allegheny Technologies Co.

700 Landwehr Road - Northbrook, IL 60062-2310 ph. (847) 564-0700 - fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE:

Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reportsonly.

January through December, 2007

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

Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits.

Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.

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

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

Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.

Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.

Table A-5 lists REMP specific analytical results from the in-house "duplicate" program for the past twelve month,,

Acceptance is~based on the difference of the results being less than the sum of the errors.

Complete analytical data for duplicate analyses is available upon request.

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

Results in Table A-7 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).

Attachment A lists acceptance criteria for "spiked" samples.

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

Al

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

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

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

> 30 pCi/liter or kg 10% of known value Potassium-40

> 0.1 g/liter or kg 5% of known value Gross alpha

< 20 pCi/liter 5.0 pCi/liter

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

< 100 pCi/liter 5.0 pCi/liter

> 100 pCi/liter 5% of known value Tritium

< 4,000 pCi/liter

+/- l=

169.85 x (known)00933

> 4,000 pCi/liter 10% of known value Radium-226,-228

> 0.1 pCi/liter 15% of known value Plutonium

> 0.1 pCi/liter, gram, or sample 10%-of known value Iodine-131,

< 55.pCi/liter 6.0 pCi/liter Iodine-129b

> 55 pCi/liter 10% of known value Uranium-238,

< 35 pCi/liter 6.0 pCi/liter Nickel-63b

> 35 pCi/liter 15% of known value Technetium-99 b Iron-55b 50 to 100 pCi/liter 10 pCi/liter

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

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

b Laboratory limit.

A2

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits Acceptance STW-1 121 STW-1 121 STW-1 122 STW-1 122 STW-1 122 STW-1 122 STW-1 122 STW-1 123 STW-1 123 STW-1 124 STW-1125 STW-1 125 STW-1 125 STW-1 125 STW-1 127 STW-1127 STW-1 128 STW-1 128 STW-1 128 STW-1 128 STW-1 128 STW-1 129 STW-1 129 STW-1 130 STW-1 130 STW-1 130 STW-1 131 STW-1 131 STW-1 132 STW-1 132 STW-1 132 STW-1 132 STW-1 132 STW-1133 STW-1 133 STW-1 134 STW-1 135 STW-1 135 STW-1 135 STW-1 135 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07

,.04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 04/09/07 07/09/07 07/09/07 07/09/07 07/09/07 07/09/07 07/09/07 07/09/07 07/09/07 07/09/07 07/09/07 07/09/07 07/09/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 10/05/07 Sr-89 Sr-90 Ba-1 33 Co-60 Cs-1 34 Cs-1 37 Zn-65 Gr. Alpha Gr. Beta 1-131 H-3 Ra-226 Ra-228 Uranium Sr-89 Sr-90 Ba-1 33 Co-60 Cs-134 Cs-1 37 Zn-65 Gr. Alpha Gr. Beta Ra-226 Ra-228 Uranium Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 H-3 Ra-226 Ra-228 Uranium 30.7 +/- 4.3 39.3 +/- 1.8 30.0 +/- 2.4 118.5 +/-3.9 52.6 +/- 2.3 49.5.+/- 3.8 91.7 +/- 6.3 33.8 +/- 3.5 24.2 +/- 2.3 19.2 +/- 1.2 7540.0 +/- 255.0 13.0 +/- 0.6 19.9 +/- 2.7 4.5 +/- 0.2 51.7 +/- 5.0 21.4 +/- 2.3 19.4 +/- 2.2 32.8 +/- 2.0 67.0 +/- 2.9 61.6 +/-3.8 55.6 +/- 7.5 19.2 +/- 1.6 9.1 +/-0.9 7.0 +/- 0.5 9.2 +/- 2.3 23.9 +/- 1.1 27.3 +/- 3.3 17.7 +/- 1.2 12.2 +/- 3.3 23.8 +/- 1.4 70.5 +/- 4.2 178.2 +/- 3.3 263.9 +/- 6.9 54.7 +/- 2.1 11.9 +/--0.9 33.0 +/- 1.5 9965.0 +/- 250.0 12.7 +/- 0.2 19.6 +/-2.4 27.3 - 1.1 35.4 42.1 29.3 119.0 54.3 50.3 88.6 56.5 25.3 18.9 8060.0 13.4 18.2 4.6 58.2 19.0 19.4 33.5 68.9 61.3 54.6 27.1 11.5 7.7 9.1 25.1 27.4 18.2 12.6 23.2 71.1 180.0 251.0 58.6 9.7 28.9 9700.0 12.9 17.9 27.5 26.7 - 44.1 33.4 - 50.8 20.6 - 38.0 109.0 - 129.0 45.6 - 63.0 41.6 - 59.0 73.3 - 104.0 32.0 - 81.0 16.6 - 34.0 13.7 -24.1 6660.0 - 9450.0 9.9 - 16.9 10.3 - 26.1 0.0 - 9.8 49.5 - 66.9 10.3 -27.7 10.7 -28.1 24.8 - 42.2 60.2 -77.6 52.6 - 70.0 45.2 -64.0 15.4 -38.8 2.8 - 20.2 5.7 - 9.7 5.2 - 13.1 19.9 - 30.3 19.3 -33.9 12.9 -21.6 8.6 - 15.5 19.9 -28.3 58.0 - 78.2 162.0 -200.0 226.0 - 294.0 30.6 - 72.9 4.3 - 18.2 24.0 - 33.8 8430.0 - 10700.0 9.6 - 14.9 12.0 -21.5 22.1 -30.8 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass.

Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

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

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

Al-1

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

mR Lab Code Date Known Lab Result Control Description Value

+ 2 sigma Limits Acceptance Environmental, Inc.

2007-1 2007-1 2007-1 2007-1 2007-1 2007-1 2007-1 2007-1 2007-1 2007-1 2007-1 7/13/2007 7/13/2007 7/13/2007 7/13/2007 7/13/2007 7/13/2007 7/13/2007 7/13/2007 7/13/2007 7/13/2007 7/13/2007 30 cm.

40 cm.

50 cm.

60 cm.

70 cm.

80 cm.

90 cm.

100 cm.

110 cm.

120 cm.

150 cm.

30 cm.

40 cm.

60 cm.

70 cm.

80 cm.

90 cm.

110 cm.

120 cm.

150 cm.

180 cm.

54.25 30.51.

19.53 13.56 9.96 7.63 6.03 4.88 4.03 3.39 2.17 54.37 30.59

.13.59 9.99 7.65 6.04 4.04 3.4 3.4 2.17 1.51 60.56 +/- 5.54 34.23 +/- 0.96 17.95 +/- 1.86 16.61 +/- 0.60 9.72 +/- 0.90 7.79 +/- 0.33 5.53 +/- 0.72 5.32.+/- 0.17 3.49 +/- 0.14 2.64 +/- 0.14 2.13+/- 0.87 65.47 +/- 5.25 37.43 +/- 2.18 15.18 +/- 0.50 12.18 +/- 0.46 8.74 +/- 0.39 5.89 +/- 0.25 4.13 +/- 0.41 2.92 +/- 0.13 2.91 +/- 0.31 1.95 +/- 0.72 1.38 +/- 0.05 37.98 - 70.53 21.36 -39.66 13.67 - 25.39 9.49 - 17.63 6.97 - 12.95 5.34 - 9.92 4.22 - 7.84 3.42 - 6.34 2.82 - 5.24 2.37 - 4.41 1.52 -2.82 38.06 - 70.68 21.41 -39.77 9.51 - 17.67 6.99 -12.99 5.36 - 9.95 4.23 - 7.85 2.83 - 5.25 2.38 - 4.42 2.38 - 4.42 1.52 -2.82 1.06-1.96 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Environmental, Inc.

2007-2 11/12/2007 2007-2 11/12/2007 2007-2 11/12/2007 2007-2 11/12/2007 2007-2 11/12/2007 2007-2 11/12/2007 2007-2 11/12/2007 2007 11/12/2007 2007-2 11/12/2007 2007-2 11/12/2007 2007-2 11/12/2007 A2-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Codue b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance W-30707 W-30707 SPAP-i 566 S PAP-1566 SPW-1568 SPW-1678 SPW-1 595.

SPW-1595 SPW-1 595 SPW-1595A SPW-1595B SPMI-1 597 SPM1-1597 SPM1-1597 SPMI-1597A SPMI-1597B SPCH-2839 SPW-2847 SPW-2847 SPW-2847 SPMI-2849 SPMI-2849 SPMI-2849 SPCH-2922 SPW-2847 SPW-2847 SPW-2847 SPMI-2849 SPW-2909 e SPW-2911 SPAP-2913 SPAP-2915 SPAP-2915 SPF-2922 SPF-2922 SPW-3223 W-60507 W-60507 SPW-4327 SPW-5476 W-92107 W-92107 3/7/2007 3/7/2007 3/23/2007 3/23/2007 3/23/2007 3/28/2007 4/5/2007 4/5/2007 4/5/2007 4/512007 4/5/2007 4/5/2007 4/5/2007 4/5/2007 4/5/2007 4/5/2007 5/17/2007 5/17/2007 5/17/2007 5/17/2007 5/17/2007 5/17/2007 5/17/2007 5/17/2007 5/18/2007 5/18/2007 5/18/2007 5/18/2007 5/22/2007 5/22/2007 5/22/2007 5/22/2007 5/22/2007 5/22/2007 5/22/2007 5/24/2007 6/5/2007 6/5/2007 7/18/2007 8/17/2007 9/21/2007 9121/2007 Gr. Alpha Gr. Beta Cs-134 Cs-137 H-3 Tc-99 Cs-134 Cs-1 37 1-131(G) 1-131 1-131 Cs-1 34 Cs-137 1-131(G) 1-131 1-131 1-131(G)

Cs-134 Cs-137 1-131(G)

Cs-134 Cs-1 37 1-131(G) 1-131(G) 1-131 Sr-89 Sr-89 1-131 Fe-55 H-3 Gr. Beta Cs-134 Cs-1 37 Cs-134 Cs-137 Ni-63 Gr. Alpha Gr. Beta Tc-99 Ni-63 Gr. Alpha Gr. Beta 19.51 +/- 0.40 67.45 +/- 0.49 25.35 +/- 1.31 107.52 +/- 3.02 65595.00 +/- 672.00 28.44 +/- 1.12 54.48 +/- 2.12 59.03 +/- 2.94 83.11 +/- 3.51 78.40 +/- 1.10 78.97 +/- 1.10 54.03 +/- 2.15 59.81 +/- 4.75 83.97 +/- 4.07 79.53 +/- 1.03 83.51 +/- 1.05 78.70 +/- 7.36 55.43 +/- 1.68 59.86 +/- 2.71 63.95 +/- 2.69 51.37 +/- 1.65 60.42 +/- 4.31 62.44 +/- 3.14 80.00 +/- 6.40 60.14 +/- 0.89 104.93 +/- 6.64 46.72 +/- 1.97 67.97 +/- 0.88 11137.00 +/- 316.00 65023.00 +/- 679.00 55.27 +/- 8.51 22.53 +/- 1.12 111.14 +/- 3.57 0.52 +/- 0.03 2.58 +/- 0.07 2233.10 +/- 10.32 20.93 +/- 0.42 60.50 +/- 0.46 25.58 +/- 1.11 1925.18 +/- 9.62 23.02 +/- 0.44 61.48 +/- 0.47 20.08 65.73 27.82 116.48 71118.00 32.35 54.99 58.19 82.07 82.07 82.07 54.99 58.19 82.07 82.07 82.07 70.40 52.85 58.03 70.87 52.85 58.03 70.87 70.40 70.87 121.90 46.08.

70.87 14271.50 70485.00 52.65 26.42 116.06 0.53 2.32 2135.90 20.08 65.73 32.35 2135.90 20.08 65.73 10.04 - 30.12 55.73 - 75.73 17.82 -37.82 104.83 - 128.13 56894.40 -85341.60 20.35 -44.35 44.99 - 64.99 48.19 - 68.19 72.07 - 92.07 65.66 - 98.48 65.66 - 98.48

44.99 - 64.99 48.19 - 68.19 72.07 - 92.07 65.66 - 98.48 65.66 - 98.48 60.40 - 80.40 42.85 - 62.85

.48.03 - 68.03 60.87 - 80.87 42.85 - 62.85 48.03 - 68.03 60.87 - 80.87 41.60 - 99.20 56.70 - 85.04 97.52 - 146.28 36.08 - 56.08 56.70 - 85.04 11417.20 - 17125.80 56388:00 - 84582.00 42.12 -73.71 16.42 - 36.42

.104.45 - 127.67 0.32 - 0.74 1.39 - 3.25 1281.54 -2990.26 10.04 - 30.12 55.73 - 75.73 20.35 - 44.35 1281.54 -2990.26 10.04 -30.12 55.73 - 75.73 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass

Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A3-1

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

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

CH (charcoal canister), F (fish).

c Results are based on single determinations.

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

'Sample recount: 12557 +/- 335.

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

A3-2

TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysisb Laboratory results (4.667)

Acceptance Type LLD Activityc Criteria (4.66 a)

W-30707 W-30707 SPAP-1 567 SPW-1567 SPW-1568 SPW-1596 SPW-1596 SPW-1 596 SPW-1596 SPM1-1598 SPMI-1598 SPMI-1598 SPMI-1598 SPCH-2839 SPW-2848 SPW-2848 SPW-2848 SPMI-2850 SPMI-2850 SPMI-2850 SPW-2848 SPW-2848 SPW-2848 SPMI-2850 SPMI-2850 SPMI-2850d SPAP-2914 SPAP-2916 SPAP-2916 SPF-2923 SPF-2923 SPW-3224 W-60507 W-60507 SPW-4328 SPW-5477 W.92107 W-92107 water water Air Filter Air Filter water water water water water Milk Milk Milk Milk Charcoal water water water Milk Milk Milk water water water Milk Milk Milk Air Filter Air Filter Air Filter Fish Fish water water water 3/7/2007 3/7/2007 3/23/2007 3/23/2007 3/23/2007 4/5/2007 4/5/2007 4/5/2007 4/5/2007 4/5/2007 4/5/2007 4/5/2007 4/5/2007 Canister 5/17/2007 5/17/2007 5/17/2007 5/17/2007 5/17/2007 5/17/2007 5/17/2007 5/18/2007 5/18/2007 5/18/2007 5/18/2007 5/18/2007 5/18/2007

5/22/2007 5/22/2007 5/22/2007 5/22/2007 5/22/2007 5/24/2007 6/5/2007 6/5/2007 Gr. Alpha Gr. Beta Cs-1 34 Cs-137 H-3 Cs-1 34 Cs-137 1-131 1-131(G)

Cs-1 34 Cs-137 1-131 1-131(G) 1-131(G)

Cs-134

.Cs-137 1-131(G).

Cs-1 34 Cs-1 37 1-131(G) 1-131 Sr-89 Sr-90 1-131 Sr-89 Sr-90 Gr. Beta Cs-1 34 Cs-137 Cs-134 Cs-137 Ni-63 Gr. Alpha Gr. Beta Tc-99 Ni-63 Gr. Alpha Gr. Beta 0.40 0.75 0.79 1.01 176.10 3.28 3.45 0.27 2.91 3.30 5.08 0.26 4.10 2.24 3.14 1.37 5.34 3.32 2.60 4.77 0.34 0.81 0.53 0.45 0.96 0.58 0.004 2.84 2.24 8.71 8.35 1.61 0.43 0.77 0.01' +/- 0.28 0.06 +/- 0.53

-26.16 +/- 91.62 0.02 +/- 0.18

-0.10 +/- 0.17

-0.06 +/- 0.19

-0.02 +/- 0.65 0.01 +/- 0.25

.0.20 +/- 0.26

-0.73 +/- 1.02 0.96 +/- 0.38

-0.002 +/- 0.002

-0.30 +/- 0.84

-0.01 +/- 0.30 0.01 +/- 0.54

-3.12 +/- 3.84 4.38 +/- 1.01 0.09 + 0.29

-0.26 + 0.51

.2 4

100 100 200 10 10 0.5 20 10 10 0.5 20 9.6 10 10 20 10 10 20 0.5 5

1 0.5 5

1 0.01 100 100 100 100 20 2

4 water water water water 7/18/2007 8/17/2007 9/21/2007 9/21/2007 6.41 1.48 0.41 0.75 10 20 2

4 A4-1

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

Acceptance Type LLD Activityc Criteria (4.66 a)

SPW-6881 SPAP-7743 SPMI-7745 SPMI-7745 SPMI-7745 SPMI-7745 SPW-7.747 SPW-7747 SPW-7747 SPW-7747 SPW-7751 SPW-7757 SPF-7759 SPF-7759 SPW-8033 W-120607 W-1 20607 water Air Filter Milk Milk Milk Milk water water water water water water Fish Fish water water water 10/10/2007 11/13/2007 11/13/2007 11/13/2007 11/13/2007 11/13/2007 11/13/2007 11/13/2007 11/13/2007 11/13/2007 11/13/2007 11/13/2007 11/13/2007 11/13/2007 11/13/2007 12/6/2007 12/6/2007 Tc-99 Gr. Beta Cs-1 34 Cs-137 1-131(G)

Sr-90 Cs-1 34 Cs-1 37 1-131(G)

Sr-90 Fe-55 H-3 Cs-134 Cs-137 Ni-63 Gr. Alpha Gr. Beta 6.82 0.003 2.16 3.46 5.89 0.59 2.39 3.53 12.51 0.71 15.50 151.35 5.50 5.10 1.45 0.40 0.77

-6.58 +/- 4.04

-0.002 +/- 0.002 0.73 +/- 0.35

-0.04 +/- 0.32

-4.18 +/- 9.20

-14.98 +/- 78.85

-0.19 +/- 0.87 0.02 +/- 0.28

-0.70 +/- 0.51 10 0.01 10 10 20 1

10 10 20 1

1000 200 100 100 20 2

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

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

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

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

A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration.(pCi/L)a Averaged Lab Code*

Date Analysis.

First. Result Second Result Result Acceptance E-20, 21 E-20, 21 CF-41, 42 CF-41, 42 CF-41,42 P-9516, 9517 LW-9579, 9580 DW-70085, 70086 DW-70037, 70038 DW-70054, 70055 DW-70122, 70123 DW-70122, 70123 DW-70098, 70099 DW-70110, 70111 SWU-676, 677 DW-70148, 70149 SW-600,601 SW-601,602 DW-1138, 1139 MI-721, 722 SW-847, 848 SW-847, 848 DW-70175, 70176 DW-70187, 70188 SWU-1162,1163 DW-70205, 70206 PW-1117, 1118 PW-1i17, 1118 W-2122,2123 W-2122,2123 W-2085,2086 W-2085,2086 DW-70232, 70233 WW-1477,1478 WW-1498,1499 W-2140,2141 W-2140,2141 DW-1626,1627 MI-1647, 1648 DW-70248, 70249 W-2150, 2151 W-2150,2151 LW-1941, 1942 1/2/2007 1/2/2007 1/2/2007 1/2/2007

.1/2/2007 1/3/2007 1/4/2007 1/9/2007 1/11/2007 1/18/2007 1/18/2007 1/18/2007 1/25/2007 1/25/2007 1/30/2007 1/30/2007 2/1/2007 2/1/2007 2/9/2007 2/13/2007 2/13/2007 2/13/2007 2/14/2007 2/14/2007 2/27/2007 2/28/2007 3/1/2007 3/1/2007 3/5/2007 3/5/2007 3/6/2007 3/612007 3/8/2007 3/12/2007 3/15/2007 3/19/2007 3/19/2007 3/21/2007 3/21/2007 3/21/2007 3/26/2007 3/26/2007 3/31/2007 Gr. Beta K-40 Gr. Beta K-40 Sr-90 H-3 Gr. Beta Gr. Alpha Gr. Alpha Gr. Alpha Gr. Alpha Gr. Beta Gr. Alpha Gr. Alpha Gr. Beta Gr. Alpha K-40 Gr. Beta H-3 K-40 Gr. Alpha Gr. Beta Gr. Alpha Gr. Alpha Gr. Beta Gr. Alpha Gr. Alpha Gr. Beta.

.Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Gr. Beta Gr. Alpha Gr. Beta H-3 K-40 Gr. Alpha Gr, Alpha Gr. Beta Gr. Beta 1.76 +/- 0.07 1.49 +/- 0.24 18.02 +/- 0.41 11.68 +/- 1.12 0.039 +/- 0.011 270.78 +/- 91.74 0.91 +/- 0.31 7.95 +/- 1.20 55.47 +/- 3.99 2.68 +/- 0.88 4.30 +/- 1.14 4.22 +/- 0.70 3.27 +/- 0.90 2.19 +/- 0.92 1.77 +/- 0.39 4.65 +/- 1.37 1.24 +/- 0.12 0.89 + 0.37 2707.00 +/- 161.00 1330.40 +/- 117.60 3.82 +/- 1.67 7.33 +/- 1.37 11.72 +/- 1.68 6.79 +/- 1.18 3.63 +/- 0.69 0.88 +/- 0.80 3.79 +/- 1.91 7.12 +/- 1.40 6.10 +/- 4.16 10.65 +/- 2.15 2.51 +/- 2.29 11.02 +/- 1.85 4.75 +/- 1.28 6.41 +/- 1.48 0.83 +/- 0.31 2.31 +/- 1.57 4.26 +/- 1.00 4973.00 +/- 209.00 1448.80 +/- 120.20 11.10 +/- 1.18 3.56 +/- 2.20 9.26 +/- 1.00 1.35 +/- 0.43 1.70+/- 0.06 1.57 +/- 0.27 18.81 +/- 0.42 12.67- +/- 0.97 0.026 +/- 0.010 301.18 +/- 92.99 0.93 +/- 0.30 7.92 +/- 1.42 52.87 +/- 4.02 1.88 +/- 0.78 6.25 +/- 1.16 5.33 +/- 0;75 1.97 +/- 0.92 1.69 +/- 0.79 2.11 +/- 0.39

5.20+/- 1.81 1.20 +/- 0.12 1.02 +/- 0.25 2700.00 +/- 161.00 1316A0 +/- 116.50 2.61 +/- 1.24 5.89 +/- 0.90 8.84 +/- 1.32 6.47 +/- 1.08 2.61 +/- 0,44 1.31 +/- 0.79 3.62 +/- 2.09 7.20 +/- 1.39 3.80 +/- 4.30 13.11 +/- 2.42 1.10 +/- 2.78 9.50 +/- 2.01 5.98 +/- 1.31 4.10 +/-_1.25 0.97 +/- 0.33 1.33 +/- 1.64 5.58 +/- 1.02 5190.00 +/- 213.00 1439.30 +/- 126.00 9.90 +/- 1.16 3.30 +/- 1.81 10.17 +/- 1.90 1.36 +/- 0.41 1.73 +/- 0.05 1.53 +/- 0.18 18.42 +/- 0.29 12.18 +/- 0.74

.0.033 +/- 0.007 285.98 +/- 65.31 0.92 +/- 0.22 7.94 +/- 0.93 54.17 +/- 2.83 2.28 +/- 0.59 5.28 +/- 0.81 4.78 +/- 0.51 2.62 +/- 0.64 1.94 +/- 0.61 1.94 +/- 0.28 4.93 +/- 1.14 1.22 +/- 0.08 0.96 +/- 0.22 2703.50 +/- 113.84 1323.40 +/- 82.77 3.22 +/-1.04 6.61 +/- 0.82 10.28 +/- 1.07 6.63 +/- 0.80 3.12 _0.41 1.10 +/- 0.56 3.71 - 1.42 7.16 +/- 0.99 4.95 +/- 2.99 11.88 +/-1.62 1.81 +/- 1.80 10.26 +/- 1.37 5.37 +/- 0.92 5.26 0 0.97 0.90 +/- 0.22 1.82 +/- 1.14 4.92 +/- 0.71 5081.50 +/- 149.21 1444.05 +/- 87.07 10.50 +/- 0.83 3.43 +/- 1.42 9.72 +/- 1.07 1.36 +/- 0.30 Pass Pass Pass Pass Pass

\\

Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result

'Acceptance*

MI-1824, 1825 MI-1824, 1825 AP-21.70, 2171 WW-1850, 1851 AP-2198, 2199 AP-2370, 2371 DW-70300, 70301 DW-70300, 70301 DW-70335, 70336 DW-70335, 70336 SW-1898, 1899 SW-1 898, 1899 SW-898, 1899 DW-70346, 70347 DW-70346, 70347 DW-70376, 70377 DW-70376, 70377 DW-70311, 70312 WW-2349, 2350 WW-2461, 2462 LW-2437,2438 LW-2917, 2918 SO-2583, 2584 SO-2583,2584 SO-2583, 2584 SO-2583, 2584 SO-2583,2584 SO-2583,2584 S-2620, 2621 MI-2610, 2611 W-4469,4470 SS-2697, 2698 SS-2697, 2698 MI-2790, 2791 W-4505,4506 DW-3219, 3220 SO-3416, 3417 SO-3416, 3417 SO-3416, 3417 F-3561, 3562 SL-3311, 3312 SL-3311, 3312 4/2/2007 4/2/2007 4/2/2007

4/3/2007 4/3/2007 4/3/2007 4/4/2007 4/4/2007 4/5/2007 4/5/2007 4/10/2007 4/10/2007 4/10/2007 4/11/2007 4/11/2007 4/11/2007 4/11/2007 4/12/2007 4/17/2007 4/25/2007 4/26/2007 4/30/2007 5/1/2007 5/1/2007 5/1/2007 5/1/2007 5/1/2007 5/1/2007 5/2/2007 5/3/2007 5/7/2007 5/8/2007 5/8/2007 5/14/2007 5/14/2007 5/26/2007 5/31/2007 5/31/2007 5/31/2007 5/31/2007 6/4/2007 6/4/2007 K-40 Sr-90 Be-7 H-3 Be-7 Be-7 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta H-3 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Gr. Alpha Gr. Alpha H-3 Gr. Beta Gr. Beta Be-7 Cs-1 37 K-40 Gr. Alpha Gr. Beta Sr-90 H-3 K-40 Gr. Beta Cs-137 K-40 K-40 Gr. Beta 1-131 Cs-1 37 Gr. Beta K-40 K-40 Be-7 K-40 1316.10 +/- 110.60 1.20 +/- 0.50 0.08 +/-+0.01

-5.83 +/- 102.29 0.08 + 0.01 0.07 +/- 0.01 3.78 0 0.89 2.93 +/- 0.61 24.37 +/- 2.89

.20.26 1.37 3.86 +/- 1.40 6.31 +/- 1.36 241.99 +/- 93.35 1.83 +1.08 4.62 +/- 0:72 1.81 +/- 0.80 1.84 +/- 0.62 10.82 +/-1.50 0.71 +/- 0.56 190.30 +/- 100.31 2.71 +/- 0.50 1.97 +/- 0.79 544.99 +/- 247.70 119.22 +/- 36.61 17825.00 +/- 749.90 11.49 +/- 3.96 31.02 +/- 3.74 0.086 +/- 0.024 277.90 +/- 126.70 1549.20 +/- 184.20 1229.80 +/- 110.50 1.10 +/- 0.36 0.08 +/- 0.01 150.05 +/- 80:14 0.08 +/- 0.01 0.07 _ 0.01 3.66 +/- 0.96 2.91 +/- 0.64 22.72 +/- 2.91 18.33 +/- 1.34 4.78 +/- 1.51 7.03 +/- 1.42 318.10 +/- 96.48 2.54 +/- 1.04 4.01 +/- 0.71 1.66 +/- 0.86 2.24 +/- 0.61 13.20 +/- 1.56 0.62 +/- 0.52 115.95 +/- 97.65 2.15 +/- 0.45 2.78 +/- 0.81 601.13 +/- 192.20 87.46 +/- 23.97 17672.00 +/- 724.30 8.04 +/- 3.88 26.10 +/- 3.40 0.068 +/- 0.025 304.40 +/- 101.00 1388.80 +/- 128.20 11.10 +/- 1.80 0.05 +/- 0.03 7.36 +/- 0.68 1627.60 +/- 128.80 3.90 +/- 1.50

.0.69 +/- 0.31 0.15 +/- 0.03 22.46 +/- 2.37 12.36 +/- 0.65 3.37 +/- 0.45 0.55 +/- 0.25 4.87 +/- 0.25

.1272.95 +/- 78.17 1.15 +/- 0.31 0.08 +/- 0.01 72.11 +/- 64.97 0.08 +/- 0.01 0.07 +/- 0.01 3.72 +/- 0.65 2.92 +/- 0.44 23.55 +/- 2.05 19.30 +/- 0.96 4.32 +/- 1.03 6.67 +/- 0.98 280.04 +/- 67.12 2.19 +/- 0.75 4.32 +/- 0.51 1.74 +/- 0.59 2.04 +/- 0.44 12.01 +/- 1.08 0.66 +/- 0.38 153.13 +/- 70.00 2.43 +/- 0.34 2.38 +/- 0.57 573.06 +/- 156.76 103.34 +/- 21.88 17748.50 +/- 521.29 9.7.7 +/- 2.77 28.56 +/- 2.53 0.077 +/- 0.017 291.15 +/- 81.02 1469.00 +/- 112.21 10.85 +/- 1.31 0.05 +/- 0.02 7.70 +/- 0.44 1660.95 +/- 90.16 3.60 +/- 1.13 0.66 +/- 0.22 0.15 +/- 0.02 22.67 +/- 1.66 12.31 +/- 0.52 3.21 +/- 0.30 0.58 +/- 0.19 5.33 +/- 0.36 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 10.60 0.06 8.03 1694.30 3.30 0.62 0.15

+/- 1.90

+/- 0.02

+/- 0.57

+/- 126.20

+/- 1.70

+/- 0.32

+/- 0.03 22.88 +/- 2.33 12.26 +/- 0.80 3.06 +/- 0.39 0.61 +/- 0.29 5.78 +/- 0.67 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 SL-3992, 3993

-SL-3992, 3993 W-5087, 5088 SW-3710, 3711 W-4062, 4063 W-4062, 4063 AP-4448, 4449 SG-3735, 3736 SG-3735, 3736 SG-3735, 3736 SG-3735, 3736 LW-4175, 4176 SG-5422, 5423 SG-5422, 5423 AP-4656, 4657 AP-4763, 4764 SG-5430, 5431 SG-5430,.5431 SG-5430, 5431 SG-5430, 5431 SG-5430, 5431 WW-4298, 4299 DW-70612, 70613 WW-4918, 4919 MI-4742, 4743 VE-4939, 4940 VE-4939, 4940 VE-4939, 4940 SG-6274, 6275 SG-6274, 6275 SW-5218, 5219 SG-6284, 6285 SG-6284, 6285 SG-6284, 6285 SG-6284, 6285 WW-5310, 5311 SW-5393, 5394 SW-5393, 5394 W-5468, 5469 6/4/2007 6/4/2007 6/4/2007

.6/11/2007 6/14/2007 6/28/2007 6/28/2007 6/28/2007 6/30/2007 6/30/2007 6/30/2007 6/30/2007 6/30/2007 7/2/2007 7/2/2007 7/3/2007 7/3/2007 7/11/2007 7/11/2007 7/11/2007 7/11/2007 7/11/2007 7/12/2007 7/23/2007 7/25/2007 7/26/2007 8/1/2007 8/1/2007 8/1/2007 8/6/2007 8/6/2007 8/7/2007 8/8/2007 8/8/2007 8/8/2007 8/8/2007 8/9/2007 8/14/2007 8/14/2007 8/15/2007 Be-7 Gr. Beta K-40 Gr. Beta H-3 Gr. Alpha Gr. Beta Be-7 Be-7 Cs-137 Gr. Beta K-40 Gr. Beta Gr. Alpha Gr. Beta Be-7 Be-7 Be-7 Cs-137 Gr. Alpha Gr. Beta K-40 Gr. Beta Gr. Alpha H-3 K-40 Be-7 Gr. Beta K-40 Gr. Alpha Gr. Beta 1-131 Cs-1 37 Gr. Alpha Gr. Beta K-40 H-3 Gr. Beta H-3 H-3 0.75 +/- 0.19 13.61 +/- 1.12 2.43 +/- 0.36 8.70 +/- 1.90 9571.51 +/- 287.22 0.76 +/- 0.63 0.97 +/- 0.53 0.10 +/- 0.02 0.84 +/- 0.12 0.07 +/- 0.01 29.51 +/- 2.22 9.41 +/- 0.31 2.18 +/- 0.60 10.31 +/- 1.98 18.59 +/- 1.46 0.09 +/- 0.02 0.11 +/- 0.02 10.17 +/- 0.48 0.050 +/- 0.010 17.86 +/- 2.78 26.19 +/- 1.74 7.69 +/- 0.30 1.74 +/- 0.74 4.54 +/- 1.11 240.43 +/- 111.12 1820.30 +/- 134.10 0.39 +/- 0.21 5.50 +/- 0.14.

3.36 +/- 0.45 16.68 +/- 3.29 40.93 +/- 2.74 1.31 +/- 0.24 0.043 +/- 0.006 9.38 +/- 2.93 33.46 +/- 2.84.

16.15 +/- 0.24 644.00 +/- 106.00 2.32 +/- 1.31 190.06 +/- 86.80 262.58 +/- 108.43 0.74 +/- 0.32 14.06 +/- 1.08 2.29 +/- 0.40 7.70 +/-_ 1.90 9879.21 +/- 291.42 0.32 +/- 0.66 0.58 +/- 0.57 0.09 +/- 0.02 0.82 +/- 0.18 0.07 +/- 0.01 30.81 +/- 2.22 8.90 +/- 0.48 1.93 +/- 0.68 10.57 +/- 1.99 20.97 +/- 1.49 0.10 +/- 0.02 0.10 +/- 0.02 10.06 +/- 0.51 0.059 +/- 0.011 15.74 +/- 2.70 25.04 +/- 1.86 7.65 +/- 0.28 2.22 +/- 0.80 4.19 +/- 0.97 216.68 +/- 110.27 1802.90 +/- 199.50 0.45 +/- 0.20 5.76 +/- 0.13 3.36 +/- 0.21 19.26 +/- 3.39 42.42 +/- 2.66 1.42 +/- 0.24 0.051 +/- 0.007 13.61 -+/- 3.38 32.87 +/- 2.93 16.23 +/- 0.25 831.00 +/- 113.00 1.71 +/- 1.27 69.05 +/- 80.88 346.53 +/- 111.42 0.75 13.84 2.36 8.20 9725.36 0.54 0.78 0.10 0.83 0.07 30.16 9.16 2.06

+/- 0.19

+/- 0.78

+/- 0.27

+/- 1.34

+/- 204.59

+/- 0.45

+/- 0.39

+/- 0.01

+/- 0.11

+/- 0.01

+/- 1.57

+/- 0.29

+/- 0.45 10.44 +/- 1.40 19.78 +/- 1.04 0.10 +/- 0.01 0.11 +/- 0.01 10.12 +/- 0.35 0.055 +/- 0.007 16.80 +/- 1.94 25.62 +/- 1.27 7.67 +/- 0.21 1.98 +/- 0.55 4.37 +/- 0.74 228.56 +/- 78.27 1811.60 +/- 120.19 0.42 +/- 0.15 5.63 +/- 0.10 3.36 +/- 0.25 17.97 +/- 2.36 41.68 +/- 1.91 1.37 +/- 0.17 0.047 +/- 0.005

.11.50 +/- 2.24 33.17 +/- 2.04 16.19 +/- 0.17 737.50 +/- 77.47 2.02 +/- 0.92 129.55 +/- 59.32 304.55 +/- 77.74 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-5553, 5554 WW-5643, 5644 SWU-5799, 5800 DW-70752, 70753 VE-5917, 5918 VE-5917, 5918 VE-5917, 5918 MI-6009, 6010 MI-6030, 6031 MI-6030, 6031 DW-70718, 70719 DW-70718, 70719 SO-6156, 6157 SO-6484, 6485 SO-6484, 6485 SO-6484, 6485 WW-6469, 6470 E-6647, 6648 E-6647, 6648 WW-6656, 6657 TD-7080, 7081 SG-6891, 6892 SG-6891, 6892 AP-7191, 7192 WW-6786, 6787 WW-6786, 6787 VE-6828, 6829 VE-6828, 6829 VE-6828, 6829 SS-6870, 6871 SS-6870, 6871 LW-7507, 7508 MI-6933, 6934 MI-6933, 6934 MI-7059, 7060 F-7213, 7214 F-7213, 7214 WW-7408, 7409 DW-70856, 70857 SO-7508, 7509 SO-7508, 7509 SO-7508, 7509 8/22/2007 8/22/2007.

8/28/2007 8/31/2007 9/4/2007 9/4/2007 9/4/2007 9/11/2007 9/12/2007 9/12/2007 9/12/2007 9/12/2007 9/14/2007 9/17/2007 9/17/2007 9/17/2007 9/21/2007 10/1/2007 10/1/2007 10/1/2007 10/2/2007 10/3/2007 10/3/2007 10/3/2007 10/8/2007 10/8/2007 10/8/2007 10/8/2007 10/8/2007 10/9/2007 10/9/2007 10/11/2007 10/16/2007 10/16/2007 10/17/2007 10/24/2007 10/24/2007 10/24/2007 10/24/2007 10/26/2007 10/26/2007 10/26/2007 K-40 H-3 Gr. Beta Gr. Alpha Be-7 K-40 Gr. Beta K-40 K-40 Sr-90 Gr. Alpha Gr. Beta H-3 Cs-1 37 Gr. Beta K-40 Gr. Beta Gr. Beta K-40 Gr. Beta H-3 Gr. Alpha Gr. Beta Be-7 H-3 H-3 Gr. Alpha Gr. Beta K-40 Gr. Beta K-40 Gr. Beta K-40 Sr-90 K-40 H-3 K-40 H-3 Gr. Alpha Cs-1 37 Gr. Beta K-40 1.89 +/- 0.33 259.00 +/- 110.00 2.64 +/- 1.18 14.41 + 1.48 0.94 +/- 0.17 3.73 0.37 2.71 + 0.10 1348.90 +/-113.40 1242.70 + 118.00 1.00 +/- 0.38 23.04 +/- 3.71 16.13 +/- 1.59 181.99 +/- 90.67 0.01 +/- 0.00 24.20 +/- 2.60 11.52 +/- 1.16 27.19 +/- 2.51 1.82 +/- 0.10 1.48 +/- 0.24 2.80 +/- 0.97 332.00 +/- 229.00 12.93 +/- 2.12 18.08 +/-+1.41 0.09 +/- 0.01 13333 +/- 322 13188 +/- 322 0.06 +/- 0.04 5.55 +/- 0.21 5.45 +/- 0.43 18.10 +/- 2.08 10.19 +/- 0.66 1.40 +/- 0.56

1386.60 +/- 104.70 1.73 + 0.52 1424.80 + 106.60 6.83 + 0.22 3.13 + 0.51 340.71 +/- 90.45 11.03 +/- 1.66 0.30 + 0.04 34.43 +/-2.72 16.84 _ 0.84 1.89 +/- 0.22 266.00 +/- 110.00 3.62 +/-.1.06 12.90 +/- 1.50 0.83 +/- 0.20 3.58 2.69 1388.10 1475.60 0.90 23.22 17.36 232.19 0.01 23.30 10.89 24.23 1.93 1.31

+/- 0.36

+/- 0.10

+/- 116.40

+/- 119.60

+/- 0.34

+/- 3.61

+/- 1.69

+/- 92.95

+ 0.00

+/- 2.30

+/- 1.10

+ 2.29

+0.11

+/- 0.23 1.89 +/- 0.20

.262.50 +/- 77.78 3.13 +/- 0.79

13.66 +/- 1.05 0.89 +/- 0.13 3.66 +/- 0.26 2.70 +/- 0.07 1368.50 +/- 81.25 1359.15 +/- 84.01 0.95 +/-0.26 23.13 - 2.59 16.75 +/- 1.16 207.09 - 64.92 0.01 + 0.00 23.75 - 1.74 11.20 +/- 0.80 25.71 - 1.70 1.88 +/- 0.07 1.40 +/- 0.17 2.38 +/- 0.65 357.50 +/- 149.10 13.23 +/- 1.48 18.18 +/- 0.98 0.09 +/- 0.01 13433 +/-228 13372 +/-229 0.06 +/- 0.03 5.38 +/- 0.10 5.32 +/- 0.33 19.90 +/- 1.51 9.95 +/- 0.47 1.42 +/- 0.39 1358.90 +/- 74.74 1.95 - 0.87 383.00 - 191.00 13.52 +/- 2.07 18.27 +/- 1.36 0.09 0.01 13532 +/-324 13556 +/- 326 0.06 +/- 0.05

.5.20 +/- 0.22 5.20 +/- 0.49 21.71 +/- 2.19 9.72 +/- 0.68 1.44 +/- 0.54 1331.20 +/- 106.70 2.17 +/- 0.57 1448.60 +/- 115:30 7.24 +/- 0.22 3.16 +/- 0.48 346.22 +/- 90.67 10.71 +/- 1.34 0.29 +/- 0.05 37.25 +/- 3.07 17.43 +/- 1.05 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 1.95 1436.70 7.03 3.15 343.46 10.87 0.29 35.84 17.14

+ 0.39

+/- 78.51

+/- 0.16

+ 0.35

+ 64.03

+/- 1.07

+/- 0.03

+/- 2.05

+ 0.67 A5-4

TABLE A-5. In-House "Duplicate"Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SS-7529, 7530 SS-7529,7530 SW-7589, 7590 SWU-7733, 7734 MI-7618, 7619 VE-7666, 7667 VE-7666, 7667 VE-7666, 7667 DW-7853, 7854 MI-7874, 7875 WW-8142,8143 DW-8094, 8095 F-8328, 8329 WW-8378,8379 10/29/2007 10/29/2007 10/30/2007 10/30/2007 10/31/2007 11/5/2007 11/5/2007 11/5/2007 11/9/2007 11/14/2007 11/28/2007 11/29/2007 12/11/2007 12/11/2007 Cs-1 37 K-40 Gr. Beta Gr. Beta K-40 Gr. Alpha Gr. Beta K-40 1-131 K-40 Gr. Beta Gr. Beta Gr. Beta H-3 0.12 +/- 0.03 11.85 +/-+0.68 1.75 +/- 0.29 1.66 +/- 1.01 1376.80 +/- 114.30 0.07 +/- 0.04 6.03 +/- 0.15 5.82 +/- 0.36 1.61 +/- 0.40 1407.70 +/- 101.30 9.51 +/- 2.21 1.60 +/- 0.58 3.97 +/- 0.08 296.00 +/- 103.00 0.12 +/- 0.02 11.75 +/- 0.58 1.24 +/- 0.26 2.43 +/- 1.13 1426.70 +/- 128.80 0.16 +/- 0.05 6.13 +/- 0.15 5.74 +/- 0.36 1.08 +/- 0.39 1362.60 +/- 114.50 7.86 +/- 2.01 1.25 +/- 0.54 4.00 +/- 0.08 407.00 +/- 107.00 0.12 +/- 0.02 11.80 +/- 0.45 1.50 +/- 0.19 2.05 +/- 0.76 1401.75 +/- 86.10

-0.11 +/- 0.03 6.08 +/- 0.10 5.78 +/- 0.25 1.35 +/- 0.28 1385.15 +/- 76.44 8.68 +/- 1.49 1.43 +/- 0.40 3.99 +/- 0.05 351.50 +/- 74.26 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.

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

A5-5

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

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STW-1110 01/01/07 Gr. Alpha STW-1110 01/01/07 Gr. Beta 0.45 +/- 0.08 0.90 +/- 0.14 0.33 0.85 0.00 -0.65 0.43-1.28 STW-1111 01/01/07 Am-241 STW-i1111 01/01/07 Co-57 STW-1111 01/01/07 Cs-134 STVV-1111 01/01/07 Cs-137 STW-1111 01/01/07 Fe-55 STW-1111 01/01/07 H-3 STW-I-111i 01/01/07 Mn-54 STW-1111 01/01/07 Ni-63 STW-1111 01/01/07 Ni-63 STW-1111 01/01/07 Pu-238 STWV-1111 01/01/07 Pu-239/40 STW-1111 01/01/07 Sr-90 STW-1111 01/01/07 Tc-99 STW-1111 01/01/07 U-233/4 STW-1111

.01/01/07 U-238 STW-1111 01/01/07 Zn-65

.2 80 +/- 0.21 151.60 +/- 10.00 79.20 +/- 8.00 168.70 +/- 12.10 130.30 +/- 19.90 262.20 +/-.9.10 130.60 +/- 11.50 127.80 +/- 3.60 127.80 +/- 3.60 2.03 + 0.17 2.27 +/- 0.17 9.60 +/-1.40 8.80 +/- 1.50 2.44 +/- 0.21 2.44 +/- 0.21 123.70 +/- 17.00 46.40 _ 9.00 501.20 +/- 2.90 285.90 +/- 2.10 325.90 +/- 7.40 855.70 +/- 4.60 750.90 +/- 4.70 1.71 143.70 83.50 163.00 129.30 283.00 123.80 130.40 130.40 2.25 2.22 8.87 88.00 2.49 2.48 114.80 34.80 471.20 274.70 327.40 799.70 685.20 1.20 -2.22 100,60 - 186.80 58.50 - 108.60 114.10 -211.90 90.50 -168.10 198.10 - 367.90 86.70 - 160.90 91.30 - 169.50 91.30 - 169.50 1.58 -2.93 1.55 -2.89 621 - 11.53 7.40 - 13.70 1.74 -3.24 1.74 -3.22 80.40 -149.20 24.40 -45.20 329.80 -612.60 192.30 -357.10 229.20 -425.60 559.80 - 1039.60 479.60 -890.80 STSO-1112 STSO-1 112 STSO-1 112 STSO-1 112 STSO-1 112 STSO-1 112 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 Am-241 Co-57 Co-60 Cs-1 34 Cs-i 37 Mn-54 Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STAP-1 113 01/01/07 Gr. Alpha STAP-1 113 01/01/07

-Gr. Beta STAP-1 114 STAP-1 114 STAP-1 114 STAP-1 114 STAP-1 114 STAP-1 114 STAP-1 114 STAP-1 114 STAP-1 114 STAP-1 114 STAP-1 114 STAP-1 114 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 Am-241 Co-57 Co-60 Cs-1 34 Cs-I37 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 0.27 +/- 0.04 0.57 +/- 0.05 0.10 +/- 0.03 3.51 +/- 0.07 2.98 +/- 0.10 4.02 +/- 0.16 2.75 +/- 0.12 3.94 +/- 0.12 0.07+/- 0.01 0.08 +/- 0.01 0.58 +/- 0.18 0.09 +/- 0.01 0.09 +/- 0.01 2.70 +/- 0.10 0.60 0.44 0.10 2.89 2.91 4.20 2.57 3.52 0.07 0.08 0.61 0.10 0.10 2.68 0.00- 1.20 0.22 - 0.66 0.07 -0.13 2.02 - 3.75 2.03 - 3.78 2.94 - 5.45 1.80 -3.34 2.46 -4.57 0.05 - 0.09 0.06 -0.11 0.43 - 0.79 0.07 - 0.13 0.07 -0.13 1.88 - 3.49 A6-1

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

Concentration b Known Control Lab Codec Date Analysis Laboratory result Activity Limits d Acceptance STVE-1 115 STVE-1115 STVE-1115 STVE-1 115 STVE-1 115 01/01/07 01/01/07 01/01/07 01/01/07 01/01/07 Co-57 Co-60 Cs-1 34 Cs-137 Mn-54 8.90 +/- 0.20 6.50 +/- 0.20 6.90 +/- 0.30 8.20 +/- 0.30 10.10 +/-0.30 8.19 5.82 6.21 6.99 8.46 5.73 - 10.64 4.08 - 7.57 4.35 - 8.07 4.90 - 9.09 5.91-10.98 Pass Pass Pass Pass Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

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

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

e Result of reanalysis, 2.08 +/- 0.13 pCi/L.

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

A6-2

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

Concentration (pCi/L)

Lab Code b Date Analysis Laboratory ERA Control Result c Result a Limits Acceptance STAP-1 116 03/19/07 Gr. Alpha STAP-1116 03/19/07 Gr. Beta 34.64+/- 2.56 93.41 +/- 3.20 25.8 79.5 12.4 -39 48.8 -116 Pass Pass STAP-1l117 STAP-1 117 STAP-1 117 STAP-1117e STAP-1117' STAP-1117' STAP-1 117 STAP-l 117 STAP-l 117 STAP-1 117 STAP-i 117 STAP-1 117 STAP-1 117 STSO-1 1 18 STSO-1 118 STSO-1 118 STSO-1 118 STSO-1 118 STSO-1 118 STSO-1118 STSO-1118 f STSO-1 118 STSO-1 118 STSO-1118 STSO-1 118 STSO-1 118 STSO-1 118 STSO-1 118 STSO-1 118 STSO-1 118 STSO-1 118 STSO-1118' 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07

,03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 Am-241 Co-60 Cs-1 34 Cs-137 Fe-55 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium Zn-65 Ac-228 Am-241 Bi-212 Co-60 Cs-1 34 Cs-1 37 K-40 Mn-54 Pb-212 Pb-214 Pu-238 Pu-239/40 Sr-90 Th-234 U-233/4 U-238 Uranium Uranium Zn-65

56.04 +/- 3.90 1610.00 +/- 8.40 1340.40 +/- 48.84 345.30 +/- 8.20

< 134.0

< 5.0 43.32 +/- 2.28 35.23 +/- 2.24 156.10 +/- 6.60 42.22 +/- 1.84 42.00 +/- 1.84 85.79 +/- 3.60 363.80 +/- 11.90 3097.77 +/- 94.96 1000.70 +/- 156.10 2467.87 +/- 114.33 7847.40 +/- 86.60 7910.60 +/- 356.88 4635.00 +/- 99.10 12201.60 +/- 423.20

< 34.0 2046.80 +/- 127.20 4142.80 +/- 110.40 1099.20 +/- 73.10 1586.10 +/- 82.00 6163.30 +/- 791.60 4329.40 +/- 569.10 3236.70 +/- 106.00 3425.20 +/- 134.00 6787.80 +/- 240.00 6787.80 +/- 240.00 0.00 +/- 0.00 57.5 1300.0 1120.0 255.0 0.0 0.0 37.4 31.6 156.0 47.8

47.4.

97.3 245.0 2790.0 927.0 2500.0 7330.0 7560.0 4300.0 11100.0 0.0 1730.0 3330.0 857.0 1360.0 7500.0 3590.0 3620.0 3590.0 7380.0 7380.0 0.0 33.1 -80 1010.0 -1620 732.0 -1380 192.0 -336 25.7-49 22.9 -41 66.6 - 246 30.1 -71 30.2 - 68 49.5 - 155 208.0 -412 1790.0 -3930 548.0 -1200 658.0 -3730 5340.0 -9820 4850.0 -9070 3290.0 -5580 8050.0 -15000

.1120.0 -2430 1980.0 -4980 490.0 -1200 928.0 -1810 2610.0 -12400 2190.0 -4560 2280.0 -4520 2190.0 -4560 4210.0 -9930 4210.0 -9930 0.0 -0 Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass.

A7-1

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

Concentration (pCi/L)

Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance STVE-1 119 STVE-1119 STVE-1 119 STVE-1119 SSTVE-1119 STVE-1 119 SIVE-1i119 STVE-1 119 STVE-1 119 STVE-1119 STVE-1 119 STVE-1 119 STVE-1119 STVE-1 119 STW-1 120 STW-1 120 STW-1 120 STW-1 120 STW-1 120 STW-1 120' STW-1 120 STW-1 120 STW-1 120 STW-1 120 STW-1 120 STW-1 120 STW-1120

.03/19/07 03/19/07 03119/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 03/19/07 Am-241 Cm-244 Co-60 Cs-1 34 Cs-137 K-40 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium Zn-65 Am-241 Co-60 Cs-1 34 Cs-1 37 Fe-55 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium Zn-65 3249.60 +/- 150.30 1860.70 +/- 91.50 2827.90 +/- 62.40 654.80 +/- 48.40 3307.30 +/- 58.80 40814.20 +/- 618.80

< 27.6 2762.00 +/- 251.10 2156.60 +/- 83.40 8999.70 +/- 580.90 2821.90 2896.10 5718.00 474.30 133.50 541.40 1623.80 1839.10 829.50 123.30 95.10 949.40 164.20 169.20

+/- 73.50

+/- 50.70

+/- 124.15

+/- 45.70

+/- 10.60

+/- 9.00

+/- 66.10

+/- 17.90

+/- 226.80

<8.1

+/- 4.30

+/- 3.80

+/- 16.70

+/- 6.58

+/- 8.22 3550.0 1840.0 2600.0 579.0 2920.0 37900.0 0.0 2430.0 1900.0 8890.0.

2940.0 2910.0 5980.0 366.0 179.0 536.0 1750.0 1850.0 671.0 0.0 116.0 90.9 989.0 192.0 190.0 391.0 1910.0 2020.0 -4890 905.0 -2870 1760.0 -3720 308.0 -822 2150.0 -4060 27200.0 -53600 1250.0 -3600 1180.0 -2600 4900.0 -11800 1930.0 -3920 2090.0 -3610 4110.0 -7770 267.0 -500

-123.0 -243 467.0 -631 1290.0 -2020 1570.0 -2220 392.0 -896 87.6 -144 70.3-113 630.0 -1320 145.0 -247 145.0 -236 282.0 -521 1600.0 -2410 Pass Pass Pass

Pass, Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 339.60 +/- 10.66 2009.00 +/- 36.40 8 Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previouslyby the Environmental Measurements Laboratory Quality Assessment Program (EML).

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

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

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

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

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

A7-2

APPENDIX B DATA REPORTING CONVENTIONS B-1

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

2.0. Single Measurements.

Each single measurement is reported as follows:

x + s where:

x= value of the measurement; s = 2a counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is less than the lower limit of detection L, it is reported as: <L, where L = the lower limit of detection based on 4.66a uncertainty for a background sample.

3.0. Duplicate analyses 3.1 Individual results: For two analysis results;.x +s 1 and x2 +s 2 Reported result:

x _s; where x= (1/2) (x,+x 2)ands (1/2)2S2 +S 2

3.2.

Individual results:

< L1, < L2 Reported result: < L, where L = lower of Li and L2 3.3.

Individual results:

x +/- s, < L Reported result:

x +/- s if x > L; < L otherwise.

4.0. Computation of Averaqes and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation s of a set of n numbers x1, x2.

. xn are defined as follows:

x =n Zx n-1 4.2 Values below the highest lower limit of detection are not included in the average.

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

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

4.5 In rounding off, the following rules are followed:

4.5.1.

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

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

B-2

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

Table C-i.

Maximum permissible concentrations of radioativity in air and water above natura.

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

Water (pCi/L)

Gross alpha Gross beta b

Iodine-1 31

-3 1 x 10 1

2.8x 10 Strontium-89 Strontium-90 Cesium-1 37 Barium-140 Iodine-1 31 Potassium-40 Gross alpha Gross beta Tritium 8,000 500 1,000 8,000 1,000 4,000 2

10 6

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

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

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

CIA natural radionuclide.

C-2

APPENDIX D Sampling Location Maps

TLD LOCAT.IONS ONE MILE RADIUS E

PLANT AREA ENLARGED PLAN 11.00 MILE RADIUS]

[NO SCALE)

MONITORING LEGEND:

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

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

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

TLD. LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:

PRAIRIE ISLAND TLD POINTS

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

ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS

.E PLANT AtREA~ ENLA~RGED PLAN

[1.0 MILE R ADIUS3 (NO :SCALE]

MONITORING: LEGEND

(

MILK SAMPLING POINT 10 NUMBERS P-14. Pý.-l, P-37,.RP.42. P-43, p-44 A

AIR SAMPLING POINT ID NUMBERS P-I.IP-4 P-3,. P-4. P-6 WATER SAMPLING. POINT ID NUMBERS O P-S. P-6.,P-B. P-9. P-Il. P-24. P-43.

El VEGETATION / VEGETABLES 10 NUMBERS P-24,. P-38, P-45 REV. I FISH SAMPLING POINT ID NUMBERS P-13, P-14

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

.SEDIMENT SAMPLING: POINT ID NUMBERS P4*. P*'12, Fý20 D-5 SAMPOLDGN 0-5 S~MP01.DGN

ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS MONITORING LEGEND MILK SAMPLING POINT 10 NUMBERS P.I4,.P-"I, P-37. P-42, P-43, P;-44 AIR SAMPLING POINT 10 NUMBERS P-Z.

P-2.Pý3, P-4, P-6 G

WATER SAMPLING POINT ID NUMBERS P

p-5. P-G, P-ý, P-'q, P:-11. P-214, P;43 VEGETATION I VEGETABLES ID. NUMBERS

.,,24,P-38P-45 FISH SAMPLING POINT ID NUMBERS

P-13. P-Iq INVERTEBRATES POINT i1 NUMBERS P-G, P-40 SEDIMENT SAMPLING POINT 10 NUMBERS P-G..P-I2, P-20 SAMP03,DON REV; 1:

REV, 1 o~6

ENVIRONMENTAL SAMPLING POINTS P-"

-P41, Huppert Farm, W10430 St Rd 29, River Falls, WI P-43, Paterson Farm, W10322 St Rd 29, River Falls, WI 8 P-38, Cain Residence, N7395 950th St, River Falls, WI CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND MILK SAMPPUNG POINT ID NUMBERS P-14, P-18, P-37, P-41, P.42, P-43, P44 A

AIR SAMPLING POINT ID NUMBERS P-1, P-2, P-A, P4 P-WATER SAMPLING POINT ID NUMBERS

P-4, P-4, P-8, P-4, P1I, P-43 8

VEGETATION I VEGETABLES ID NUMBERS P-24, P-38, P45 0-7

APPENDIX E Special Well and Surface Water Samples E-1

1.0 INTRODUCTION

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

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

E-2

2.0

SUMMARY

This special sampling program was established following the detection of tritium in a residenc6 well water sample south of the PINGP during 1989.

This program is described and the results for 2007 are summarized and discussed.

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

E-3

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

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

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

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

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

3.4 Program Modifications Changes to the program in 2007 include:

e the addition of monitoring wells MW-7 and MW-8 in the vicinity of well P-10 to assess the higher levels previously noted in P-10 the addition of the New Administration Building well the addition of the Plant Screenhouse well the addition of a stormwater runoff sample sampling was not performed at station P-3 because it was inaccessible sampling was not performed at the STA house (SW-2) because it was dry 3.5 Results and Discussion Results obtained show tritium in well water and ground water samples at or near expected natural background levels except the P-10, MW-7, amd MW-8 sample wells. Table 4.4 provides the complete data table of results for each period and sampling location.

E-4

Results and Discussion (continued)

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

Except for sample wells P-10, MW-7, and MW-8, the 2007 sample results are within the range of expected background tritium levels, in shallow ground water and surface water due to tritium concentrations measured in precipitation.

Sampling points in:North America have shown tritium concentrations in precipitation ranging from 5 pCi/L to 157 pCi/L (Environmental Isotope Data No.

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

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

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

The liquid radwaste discharge pipe was replaced in 1992 and the discharge to the landlocked area has been minimized by administrative controls.

E-5

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

Medium No.

Location codes Collection type Analysis type and type and frequency P-8, REMP P-6, PIIC-02, PIIC-22, PIIC-26, P-2, P-3, P-4, P-5, P-6, Well water, 28P-7, P-11, 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 1

P-24D G/Q H-3 Well water, monthly 5

P-43(C), SW-1(C),

G/Md H-3 MW-7, MW-8, P-10 Surface water S-1, S-2, S-3, S-4, 6

S-5, S-6 G/A H-3 Location codes are defined in table D-4.2. Control Stations are indicated by (C).

All other stations are indicators.

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

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

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

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

E-6

Table E-4.2.

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

Code Collection site Type of sample b Distance and Direction from reactor P-8 P1 Community well WW 1.0 mi. @ 321 /WNW REMP P-6 Lock & Dam #3 well WW 1.6 mi. @ 129°/SE PIIC-02 2077 Other Day Road WW 1.4 mi. @ 315°/NW PIIC-22 1773 Buffalo Slough Rd WW 1 mi. @ 315°/NW PIIC-26 1771 Buffalo Slough Rd WW 1 mi. @ 315°/NW P-24D Suter residence WW 0.6 mi. @ 158°/SSE P-43 Peterson Farm (Control)

WW 13.9 mi. @ 355°/N SW-1 Hanson Farm (Control)

WW 2.2 mi. @ 315°/NW P-2 Sample well WW See map P-3 Sample well WW See map P4 Sample well

. WW See map P-5 Sample well WW See map P-6 Sample well WW See map P-7 Sample well.

WW See map P-10 Sample well WW See map P-11 Sample well WW See map PZ-1 Sample well WW See map PZ-2.

Sample well WW See map PZ-4 Sample well WW See map PZ-5 Sample well WW See map PZ-7 Sample well WW See map PZ-8 Sample well WW See map MW-4 Sample well WW See map MW-5 Sample well WW See map MW-6 Sample well WW See map MW-7 Sample well WW See map MW-8 Sample well WW See map P-26 PITC well WW 0.4 mi. @ 258°/WSW P-30 Environ lab well WW 0.2 mi. @ 32°/NNE SW-2 STA House WW See map SW-3 Cooling Tower pump WW See map SW-4 New Admin Bldg WW 0.05 mi. @ 315°/NW SW-5 Plant Screenhouse well WW 0.05 mi. @ 0°IN P-9 Plant well # 2 WW 0.3 mi. @ 306°/NW S-1 Mississippi River upstream SW See map S-2 Recirculation/Intake canal SW See map S-3 Cooling water canal SW See map S-4 Discharge Canal (end)

SW See map S-5 Discharge Canal (midway)

SW See map S-6 Stormwater Runoff SW 0.05 mi. @ 0ON Sample codes: WW = Well water; SW = Surface Water.

E-7

Table E-4.3

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

Name of Facility Prairie Island Nuclear Location of Facility Goodhue, Minnesota Power Station Docket No.

Reporting Period 50-282, 50-306 January - December 2007 (County, State)

Indicator Location with Highest Control Number Locations Annual Mean Locations Non-Sample Type and Type Number of Tpa b

Routine (Units)

Analyses LLD Mean (F)c Locationd Mean (F)

Mean(F)

Results C

C C

Range Range Range Offsite H-3 36 19 45(9/12)

PIIC-22 65(1/1) 29(3/24) 0 Well Water (23-65)

(65)

(25-32)

(pCi/L)

Onsite H-3 63 19 367(36/39)

P-10 908 (12/12) 29 (3/24) 15 Well Water (24-2258)

(390-2258)

(25-32)

(pCi/L)

Onsite H-3 30 19 94 (5/6)

S-6 285 (1/1) 29 (3/24) 0 Surface Water (35-285)

(285)

(25-32)

(pCi/L) a b

C d

e 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.

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

Locations are specified: (1) by name, and code (Table 2) and (2) by distance, direction and sector relative to reactor site.

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

E-8

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

SAMPLE DATES JAN FEB MAR APR MAY JUN

. JUL AUG SEP OCT NOV DEC 2007 2007 2007 2007 2007 2007 2007 2007 2007 2007 2007 2007 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L ONSITE WELLS P-2 Sample well 66 P-4 Sample well

<19 P-5 Sample well 109 P-6 Sample well 45 P-7 Sample well 95 P-10 Sample well 1289 390 453 967 835 784 482 544 486 1724.

2258 678 P-1 1 Sample well 65 PZ-1 Sample well

<19 PZ-2 Sample well 71 PZ-4 Sample well 40 PZ-5 Sample well 47 PZ-7 Sample well

_52 PZ-8 Sample well 54 MW-4 Sample well 46 MW-5 Sample well 35 MW-6 Sample well 44 MW-7 Sample well 341 73 54 MW-8 Sample well 43 325 513 P-26 PITC well 31 P-30 Env. lab well

<19 SW-3 Cooling Tower pump 37 P-9 Plant well # 2 24 SW-4 New Admin 65 SW-5 Pin Scrnhs 32 E-9

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

SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2007 2007 2007 2007 2007 2007 2007 2007 2007 2007 2007 2007 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L ONSITE SURFACE WATER S-1 Mississippi River upstream 57 S-2 Recirculation/Intake canal 56 S-3 Cooling water canal

< 19 S-4 Discharge Canal (end) 36 S-5 Discharge Canal (midway) 35 S-6 Stormwater runoff 285 OFFSITE WELLS

<19 P-8 PI Community Well REMP P-6 Lock & Dam #3 well

<19 PIIC-02 2077 Other Day Rd.

<19 PI1C-22 1773 Buffalo Slough Rd.

.65 PIIC-26 1771 Buffalo Slough Rd.

62 63 47 35 25 23 46 36 P-24D Suter" residence.....

<19 25

<19

<19 29

< 19

<19

<19 P-43 Peterson Farm (Control) 3 SW1 Hno am(oto) 32

< 19

< 19 1< 19

< 19

< 19 E-10

Sý'."Y by Joh-0s &. 9roFIld InC No gbc

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

MW,

5902201,

.2356566 686.83 MW-6 591642 2357597 682.33 MW-7 593685 2355714 695.54 MW-8 593944

,2355654 697.47

P-1O 593538

.2355497 693.16 P -I 594949 2355297

698.19 P-2 594449 2354002 697.72 P-3 592998 2353997

698.19 P-5 594002 2354501 695.51 P-6 595250 2354802 699.3 P-7 594449 2355235 697.97 PZ-1 598790 2354934

,682-91 PZ-2 596743 2352589.689.05 PZ-4.

594262 2352598 696.53 PZ-5 591502 2356299 695.93 PZ-7 594469 2356158 697.85.

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

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

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

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6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

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1.0 INTRODUCTION

SUMMARY

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