Text

Independent Spent Fuel Storage Installation, Submittal of 2009 Annual Radiological Environmental Monitoring Program Report
	ML101380302
Person / Time
Site:	Prairie Island
Issue date:	05/12/2010
From:	Schimmel M; Northern States Power Co, Xcel Energy
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
	ISFSI TS 6.2, L-PI-1 0-042, TS 5.6.2
	Download: ML101380302 (75)
	v • d • e

XcelEner 't I

MAY 1 2 2010 L-PI-1 0-042 TS 5.6.2 ISFSI TS 6.2 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 and 72-10 License Nos. DPR-42 and DPR-60 and SNM-2506 Prairie Island Independent Spent Fuel Storage Installation Docket 72-10 Materials License No. SNM-2506 2009 Annual Radiological Environmental Monitorinq Progqram (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 Prairie Island Independent Spent Fuel Storage Installation Technical Specification (ISFSI TS) 6.2, Appendix A to Materials License SNM-2506, the Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy, submits one copy of the Annual Radiological Environmental Monitoring Program report for the period January 1, 2009 through December 31, 2009 as Enclosure 1.

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

Mark A. Schimmel Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc:

Regional Administrator, USNRC, Region III Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector, Prairie Island Nuclear Generating Plant Billy Dickson, USNRC, Region III Director of NMSS, USNRC Department of Health, State of Minnesota PI Dakota Community Environmental Coordinator

~1E~

1717 Wakonade Drive East 9 Welch, Minnesota 55089-9642 Telephone: 651.388.1121 ki it5_

,ENCLOSUREI Annual Report to the United States Nuclear Regulatory Commission Radiological Environmental Monitoring Program January 1, 2009 through December 31, 2009 73 pages follow

- (

Environmental, Inc.

Midwest Laboratory 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 Radiological Environmental Monitoring Program January 1 to December 31, 2009 Docket No. 50-282 License No. DPR-42 50-306 DPR-60 ISFSI Docket No.72-10 SNM-2506 Prepared under Contract by ENVIRONMENTAL, Inc.

MIDWEST LABORATORY Project No. 8010 Approved:

Z 1

La ~r Manager

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 Northern States Power Co. -Minnesota, for XCEL Energy Corporation.

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

ii

TABLE OF CONTENTS Section Page P re fa c e............................................ *.........................................................................................................

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

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

........................... v

1.0 INTRODUCTION

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

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

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

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

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

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

6 3.5 Program Modifications...........................................................................................................

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

6 4.0 RESULTS AND DISCUSSION............................................................................................................

7 4.1 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 Comparison Program Results......................................

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

A-2 B

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

B-1 C

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

C-1 D

Sam pling Location Maps......................................................................................................................

D-1 E

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

E-1 iii

LIST OF TABLES No.

Title Paae 5.1 Sample Collection and Analysis Program................................................

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

16 5.3 Missed Collections and Analyses..............................................................................................................

19 5.4 Radiological 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..................................................

Al-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" Samples.......................................................................................................

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

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

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

E-6 E-4.2 Sampling locations..................................................................................................................................

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

E-8 E-4.4 REMP Complete Data Tables...............................................................................................................

E-9 E-4.5 Supplementary Data Tables................................................................................................................

E-12 iv

LIST OF FIGURES Title No.

Page 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator lo ca tio n s ve rsus co ntro l..............................................................................................................................

13 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6) versus control location (P-1)................................................................................

14 MAPS Appendix D Title Page TLD locations w ithin a one m ile radius.....................................................................................................

D-2 TLD locations, Controls.............................................................

............................... D-3 TLD locations, surrounding the ISFSI Area...............................................................................................

D-3 TLD locations within a five m ile radius..................................................................................................

D-4 REM P sam pling points within a one m ile radius......................................................................................

D-5 REM P sam pling points within a five m ile radius......................................................................................

D-6 REMP sampling points, Control locations..................................................

D-7 Appendix E Onsite Tritium Sam pling W ell locations...................................................................................................

E-14 v

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiological 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, 2009.

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, 2010b) 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 Northern States Power Co.-Minnesota.

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 Radiological Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Offsite Dose Calculation Manual for the Prairie Island Nuclear Generating Plant and the Independent Spent Fuel Storage Installation (ISFSI) is described.

Results for 2009 are summarized and discussed.

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

2

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

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

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

Sources of environmental radiation include the following:

(1)

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

Fallout from atmospheric nuclear detonations; (3)

Releases from nuclear power plants; (4)

Industrial and medical radioactive waste; and (5)

Fallout from nuclear accidents.

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

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

An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the plant site.

The plant's monitoring program includes analyses for tritium and iodine-1 31. Most samples are analyzed for gamma-emitting isotopes with results for the following groups quantified:

zirconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40. The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown. On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963).

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

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

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

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

60, and zinc-65, are activation products and arise from activation of corrosion products. They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.

3

3.1 Proaram Desian and Data Interpretation (continued)

Other means of distinguishing sources of environmental radiation are employed in interpreting the data.

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

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

3.2 Progqram Description The sampling and analysis schedule for the radiological 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, 2009). 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 CaSO4: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 four farms (three indicators and one control) and analyzed for iodine-131 and gamma-emitting isotopes. The milk is collected biweekly during the growing season (May - October), because the milk animals may be on pasture.

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

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

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

0 4

3.2 Proaram Description (continued)

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

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

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

3.3 Procqram 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-4 for the week ending 10/20/09. Power was down approximately 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> due to switching operations at the plant.

Deviations from the program are summarized in Table 5.3.

5

3.4 Laboratory Procedures The iodine-131 analyses in milk and drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method and solvent extraction and subsequent beta counting.

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

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

Tritium concentrations are determined by liquid scintillation.

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

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

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

Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2009). The QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs.

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

3.5 Program Modifications There were no modifications to the REMP in 2009.

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 animal, the nearest residence, and the nearest garden of greater than 500 ft2 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 radiological 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 radiological environmental monitoring program should sampling locations change within the 5 mile radius from the plant.

The Land Use Census was completed in September, 2009. There were no changes to any of the highest D/Q locations for nearest residence, milk animal or garden sites.

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 2009. The last reported test was conducted on October 16, 1980 by the People's Republic of China. There were no reported accidents involving any significant release to the environment at nuclear reactor facilities in 2009.

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 pre-3 operational 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-137 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 measure below a detection limit of approximately 160 pCi/L. 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 Prociram Findingqs 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 15.5 mRI91 days at inner ring locations to 16.2 mR/91 days at outer ring locations.

The mean at special interest locations was 15.8 mR/91 days and 16.3 mRI91 days at the control location. Dose rates measured at the inner and outer ring and the control locations were similar to those observed from 1994 through 2008. The results are tabulated below. No plant effect on ambient gamma radiation measurements was indicated(Figure 5-1).

S Year 1994 1995 1997 1998 L 2000 2001 Average (Inner and Outer Rings) 15.2 15.6 14.8 15.1 16.7 16.6 17.0 16.8 Average (Inner and Control I

Year Outer Rings)_

Control 16.0 1 1 2002 17.4 16.9 16.6 I

2003..

16.2 16.0 16.4 2004

-17.6 1 17.6 16.0 I

20516.8 16.3 17.3Y 2006 16.6 16.6

--T

-20 08

-6 9-1* T..

i 2007

17. T 17.7 17.1 20081697.

17.2 2009 15.9 i

16.3 A-II

_i,_

Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates (mRJ91 days).

ISFSI Facility Onerations Monitorina Ambient radiation was measured inside the ISFSI earth berm, outside the ISFSI earth berm and at two special locations between the plant ISFS1 and the Prairie Island Indian Community. The mean dose rates averaged 99.5 mR/91 days inside the ISFSI earth berm and 20.4 mR/91 days outside the ISFSI earth berm. One additional cask was placed on the ISFSI pad in 2009, a total of twenty-five 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 15.1 and 15.0 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 Typically, the highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 1993 through 2006, and also in 2008. The elevated activity observed in 2007 was attributed to construction activity in the area, an increase in dust and consequent heavier particulate filter loading.

Average annual gross beta concentrations in airborne particulates were identical at the indicators 3

versus control locations (0.029 pCi/m ) and similar to levels observed from 1994 through 2006 and 2008. The results are tabulated below.

IAverageof Year Indicators Control

_Concentration (pCi/m 1994 0.022 0.02 1995 0.022 0.02o 1996 j

0.023 1

0.02(

1997 0.021 0.02" 1998 0.022 0.01 1999 0.024 0.022 2000 0.025 0.021 2001 0.023 0.02:

2002 0.028 0.02:

2003 0.027 0.02_,'

2004 0.025 0.02 2005 0.027 0.021 2006 0.026 0.021 2007 0.037 0.031 2008 0.028 0.027 0.029 0.021 2

2 0

1 8

2 5

3 3

5 6

5 5

1 7

9 Average annual gross beta concentrations in airborne particulates.

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations.

Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and AI-Salih, 1955) was detected in all samples, with an average activity of 0.087 pCi/im3 for all locations. All other gamma-emitting isotopes were below their respective LLD limits.

Airborne Iodine Weekly levels of airborne iodine-1 31 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 lodine-131 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 2009 show no radiological effects of the plant operation.

Drinkingq Water In drinking water from the City of Red Wing well, tritium activity measured below the LLD level of 159 pCi/L in all samples.

Gross beta concentrations averaged 11.4 pCi/L throughout the year, ranging from 6.8-15.2 pCi/L. These concentrations are consistent with levels observed from 1994 through 2008. 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 2009 data of any effect.of plant operation.

Year 1994 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 i

2006 2007 F

2008 l

Gross Beta

.{pCilL) 5.8 3.9 6.3 5.1 5.4 5.3 10.1 8.3 9.9 13.4 11.6 11.6 11.4 i1 2009

_T_---11 Average annual concentrations; Gross beta in drinking water.

10

River Water For 2009, no measurable tritium activity was detected in river water composites, above the concentration level of 159 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 a concentration level of 161 pCi/L.

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

In summary, well water data for 2009 show no radiological effects of the plant operation.

Crops Three samples of broadleaf vegetation, cabbage leaves, were collected in August and analyzed for gamma-emitting isotopes, including iodine-131. The 1-131 level was below 0.029 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 September, 2009 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, 2009 and analyzed for gamma-emitting isotopes. All gamma-emitting isotopes were below 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, June and September, 2009 and analyzed for gamma-emitting isotopes. The only gamma-emitting isotopes detected were naturally-occurring beryllium-7 and potassium-40. 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.

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12 -

11 10 20 19 18 17 16 (n

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41 (A

0)

-4 CD C0 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-OIA - P-iOA C/Q Ambient gamma Airborne Particulates Airborne Iodine Milk River water Drinking water Well water Edible cultivated crops -

leafy green vegetables P-O01B - P-15B P-01S - P-08S P-OlIA - P-08A P-OIB - P-081B P-OIlX-P-041X, P-01C 5

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

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

P-18, P-37, P-42, P-43 (C) 2 P-5(C), P-6 P-11 5

P-6, P-8, P-9, P-24, P-43 (C) 3 P-28, P-38(C), P-45 C/W C/W G/Md G/W G/W G/Q G/A GB, GS (QC of each location) 1-131 1-131, GS GS(MC), H-3(QC)

GB(MC), 1-131(MC)

GS (MC), H-3 (QC)

H-3, GS GS (1-131)

Fish (one species, edible portion)

Periphyton or invertebrates Bottom sediment Shoreline sediment 2

2 2

1 P-19(C), P-13 P-40(C), P-6 P-20(C), P-6 P-12 G/SA G/SA G/SA G/SA GS GS GS GS

' 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.

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 Code Typea Collection Site Sample Typeb from Reactor P-1 P-2 P-3 P-4 P-5 P-6 P-8 P-9 P-1i P-12 P-13 P-18 P-19 P-20 P-24 P-28 P-37 P-38 P-40 P-42 P-43 P-45 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 Christiansen Farm C

Upstream of Plant C

Upstream of Plant Suter Residence Allyn Residence Welsch Farm C

Cain Residence C

Upstream of Plant Rother Farm C

Peterson Farm Glazier Residence AP, Al AP, Al AP, Al AP, Al RW AP, Al, RW WW, BS, BO' WW WW DW SS Fr M

Fr BS WW VE M

VE BOc M

M, WW VE 11.8 mi @ 3160/NNW 0.5 mi @ 2940/WNW 0.8 ml @ 313°/NW 0.4 mi @ 3590/N 1.8 mi @ 110/N 1.6 mi @ 129°/SE 1.0 mi @ 321e/WNW

0.3 mi @ 3060/NW 3.3 mi @ 1580/SSE 3.0 mi @ 116°/ESE 3.5 mi @1130/ESE 3.8 mi @ 880/E 1.3 mi @ O°/N 0.9 mi @ 45°/NE 0.6 mi @ 1580/SSE 1.0 mi @ 152°/SSE 4.1 mi @ 870/E 14.2 mi @ 359°/N 0.4 mi @ O°/N 4.3 mi. @ 2640/W 13.9 mi. @ 3550/N 0.6 mi. @ 3410/NNW General Area of the Site Boundary P-OIA P-02A P-03A P-04A P-05A P-06A P-07A P-OSA P-09A P-IOA 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 @ 359'/N 0.3 mi @ 100/N 0.5 mi @ 1830/S 0.4 mi @ 204°/SWW 0.4 mi @ 2250/SW 0.4 mi @ 2490/WSW 0.4 mi @ 268°/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 Code Typea Collection Site Sample Type" from Reactor Approximately 4 to 5 miles Distant from the Plant P-0113 P-02B P-03B P-04B P-05B P-06B P-07B P-08B P-09B P-10B P-111B P-12B P-13B P-1413 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 TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 4.7 mi @ 3550/N 4.8 mi @ 170/NNE 4.9 mi @ 46°/NE 4.2 mi @ 610 /ENE 4.2 mi @ 1020/ESE 4.4 mi @ 112o/ESE 4.7 ml @ 140°/SE 4.1 ml @ 1650/SSE 4.2 mi @ 1870/S 4.9 mi @ 2000/SSW 4.5 mi @ 2210/SW 4.6 mi @ 2510/WSW 4.4 mi @ 2700/W 4.9 mi @ 3060/NW 3.8 mi @ 3450/NNW 1.6 mi @ 1290/SE 0.5 mi @ 1550/SSE 2.2 ml @ 1730/S 2.0 mi @ 2020/SSW 2.0 mi @ 2700/W 2.5 mi @ 2997/WNW 0.7 mi @ 2710/W 0.7 mi @ 287°/NWW 11.1 mi @ 3310/NNW Special Interest Locations P-01S 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 17

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

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

ISFSI Area Inside Earth Berm P-011A P-021A P-031A P-041A P-051A P-061A P-071A P-081A P-011X P-021X P-031X P-041X 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 ISFSI Nuisance Fence ISFSI Nuisance Fence TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 190' @ 450/NE 360'@ 820/E 370' @ 1000/E 200'@ 1340/SE 180' @ 2190/SW 320' @ 2580/WSW 320' @ 2810 /WNW 190' @ 3180/NW 140'@ 1800/S 310' @ 2700/W 140' @ 0'/N 360' @ 900/E ISFSI Area Outside Earth Berm P-O1IB P-021B P-031B P-0411B P-051B P-061B P-071B P-081B 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'@ 3'/N 380' @ 280 /NNE 560' @ 850/E 590' @ 1650/SSE 690'@ 1860/S 720' @ 201°/SSW 610' @ 2710/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 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 Gross Beta, P-4 10/2012009 Approx. 32 hrs run-time lost.

none 1-131 Inadvertant loss of power.

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, 2009 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)0 Mean (F)c Mean (F)0 Routine (Units)

Analysesa Range' Locationd Range' Rangec Resultse TLD (Inner Ring, Gamma 40 3.0 15.5 (40/40)

P-06A 16.9 (4/4)

(See Control 0

Area at Site (10.8-17.9) 0.4 mi @ 2490 /WSW (15.5-17.9) below.)

Boundary) mR/91 days)

TLD (Outer Ring, Gamma 60 3.0 16.2 (60/60)

P-12B, R. Gergen Farm, 17.7 (4/4)

(See Control 0

4-5 mi. distant)

(12.9-19.0) 4.6 mi @ 2510 /WSW (16.5-18.4) below.)

mR-91 days)

TLD (Special Gamma 32 3.0 15.8 (32/32)

P-03S, Gustafson Farm, 18.3 (4/4)

(See Control 0

Interest Areas)

(13.3-19.4) 2.2 mi @ 1730 /S (17.4-19.4) below.)

mR/91 days)

TLD (Control)

Gamma 4

3.0 None P-01C, Robert Kinneman 16.3 (4/4) 16.3 (4/4) 0 mR/91 days) 11.1 mi @ 3310 /NNW (15.7-17.0)

(15.7-17.0)

Airborne GB 260 0.005 0.029 (208/208)

P-06, Air Station 0.029 (52 /52) 0.029 (52/52) 0 Particulates (0.007-0.075) 1.6 mi @ 1290 /SE (0.007-0.075)

(0.008-0.064)

(pCi/m 3)

GS 20 Be-7 0.015 0.087 (16/16)

P-02, Air Station 0.089(4/4) 0.088(4/4) 0 (0.051-0.112) 0.5 mi @ 2940 /WNW (0.057-0.102)

(0.057-0.102)

Mn-54 0.0007

< LLD

< LLD 0

Co-58 0.0006

< LLD

< LLD 0

Co-60 0.0007

< LLD

< LLD 0

Zn-65 0.0010

< LLD

< LLD 0

Zir-Nb-95 0.0010

< LLD

< LLD 0

Ru-103 0.0008

< LLD

< LLD 0

Ru-106 0.0057

< LLD

< LLD 0

Cs-134 0.0007

< LLD

< LLD 0

Cs-137 0.0006

< LLD

< LLD 0

Ba-La-140 0.0024

< LLD

< LLD 0

Ce-141 0.0016

< LLD LLD 0

Ce-144 0.0035

< LLD

< LLD 0

Airborne Iodine 1-131 260 0.03

< LLD

< LLD 0

(pCi/mrn) 20

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

50-282, 50-306 Reporting Period January-December, 2009

( County, State )

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

Analysesa Rangec Locationd Rangec Rangec Resultse Milk (pCi/L) 1-131 72 0.5

< LLD

< LLD 0

GS 72 K-40 200 1386 (54/54)

P-37, Welsch Farm 1416 (18/18) 1404 (18/18) 0 (1303-1540) 4.1 mi @ 87'/E (1356-1540)

(1299-1517)

Cs-134 5

< LLD

< LLD 0

Cs-137 5

< LLD

< LLD 0

Ba-La-140 5

< LLD

< LLD 0

River Water H-3 8

159

< 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 30

< LLD

< LLD 0

21

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

50-282, 50-306 Reporting Period January-December, 2009

( 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 Range' Location" Range' Rangec Resultse Drinking Water GB 12 1.0 11.4 (12/12)

P-11, Red Wing S.C.

11.4 (12/12)

None 0

(pCi/L)

(6.8-15.2) 3.3 mi @ 1580 /SSE (6.8-15.2) 1-131 12 1.0

< LLD None 0

H-3 4

159

< 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 38

< LLD None 0

Well Water H-3 20 161

< 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 46

< LLD LLD 0

Crops - Cabbage 1-131 3

0.029

< 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 Goodhue. Minnesota Docket No.

50-282, 50-306 Reporting Period January-December, 2009

( 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)

Analyses3 Rangec Locationd Rangec Rangec Resultse Fish GS 4

(pCi/g wet)

K-40 0.10 2.52 (2/2)

P-19, Upstream 3.02 (2/2) 3.02 (2/2) 0 (2.45-2.58) 1.3 mi @ 00/N (2.92-3.13)

(2.92-3.13)

Mn-54 0.018

< LLD

< LLD 0

Fe-59 0.036

< LLD

< LLD 0

Co-58 0.018

< LLD

< LLD 0

Co-60 0.017

< LLD

< LLD 0

Zn-65 0.018

< LLD

< LLD 0

Zr-Nb-95 0.029

< LLD

< LLD 0

Cs-134 0.013

< LLD

< LLD 0

Cs-137 0.016

< LLD

< LLD 0

Ba-La-140 0.034

< LLD

< LLD 0

Invertebrates GS 4

(pCi/g wet)

Be-7 1.15

< LLD

< LLD 0

K-40 1.65

< LLD LLD 0

Mn-54 0.084

< LLD

< LLD 0

Co-58 0.091

< LLD

< LLD 0

Co-60 0.073

< LLD

< LLD 0

Zn-65 0.16

< LLD

< LLD 0

Zr-Nb-95 0.12

< LLD

<LLD 0

Ru-103 0.15

< LLD

< LLD 0

Ru-106 0.54

< LLD

< LLD 0

Cs-1 34 0.068

< LLD

< LLD 0

Cs-1 37 0.066

< LLD

< LLD 0

Ba-La-140 0.46

< LLD

< LLD 0

Ce-141 0.25

< LLD

< LLD 0

Ce-144 0.46

< 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 Docket No.

50-282, 50-306 Reporting Period January-December, 2009

( 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)

Analyseso Rangec Locationd Rangec Rangec Resultse Bottom and GS 6

Shoreline Be-7 0.23

< LLD P-20, Upstream 0.23 (1/2) 0.23 (1/2) 0 Sediments 0.9 mi. @ 450 /NE (pCi/g dry)

K-40 0.10 8.93(4/4)

P-6, Lock and Dam #3 9.84 (2/2) 9.46 (2/2) 0 (8.00-10.38) 1.6 mi @ 12901SE (9.29-10.38)

(8.46-10.45)

Mn-54 0.025

< LLD

< LLD 0

Co-58 0.027

< LLD

< LLD 0

Co-60 0.023

< LLD

< LLD 0

Zn-65 0.062

< LLD

< LLD 0

Zr-Nb-95 0.031

< LLD

< LLD 0

Ru-103 0.020

< LLD

< LLD 0

Ru-106 0.21

< LLD

< LLD 0

Cs-134 0.018

< LLD

< LLD 0

Cs-137 0.026

< LLD

< LLD 0

Ba-La-140 0.029

< LLD

< LLD 0

Ce-141 0.044

< LLD

< LLD 0

Ce-144 0.14

< LLD

< LLD 0

0 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).

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

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

24

6.0 REFERENCES

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

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

Environmental, Inc., Midwest Laboratory.

2001a through 2010a.

Radiation Environmental Monitoring for Monticello Nuclear.Generating Plant, Complete Analysis Data Tables, January-December, 2000' through 2009.

2001b through 2010b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000 through 2009.

1984a to 2000a. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)

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

1984b to 2000b. (formerly Teledyne Brown Engineering Environmental Services, Midwest Laboratory)

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

1979a to 1983a. (formerly Hazleton Environmental Sciences Corporation)

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

1979b to 1983b. (formerly Hazleton Environmental Sciences Corporation)

Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -

December, 1978 through 1982.

2009.

Quality Assurance Program Manual, Rev. 2, 10 November 2009.

2009.

Quality Control Procedures Manual, Rev. 2, 08 July 2009.

2009.

Quality Control Program, Rev. 2, 12 November 2009.

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.

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 2008.

Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1978 through 2007.

Minneapolis, Minnesota.

Prairie Island Nuclear Generating Plant, 2009. Radiological Environmental Monitoring for Prairie Island Nuclear Generating Plant, Radiation Protection Implementing Procedures, 4700 series.

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

25

6.0 REFERENCES

CITED (continued)

U.S. Environmental Protection Agency.

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

1984.

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

2007.

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

Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125.

Xcel Energy Corporation.

2009 to 2010. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 and 2009. Minneapolis, Minnesota.

2009 to 2010.

Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 and 2009.

Minneapolis, Minnesota.

26

... Environmental, Inc.

Midwest Laboratory an 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 reports only.

January, 2009 through December, 2009

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.

Table A-2 lists results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internal laboratory testings Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.

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

Table A-5 lists REMP specific analytical results from the in-house "duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors.

Complete analytical data for duplicate analyses is available upon request.

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

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

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

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

Al

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

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

> 50 pCilliter 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

+ lo =

169.85 x (known)0,933

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

> 0.1 pCi/liter 15% of known value Plutonium

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

< 55 pCi/liter 6 pCi/liter Iodine-129b

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

< 35 pCi/liter 6 pCi/liter Nickel-63b

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

> 100 pCi/liter 10% of known value Other Analyses b 20% of known value 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-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.

Concentration (pCi/L)

Lab Code Date Analysis aboratory ERA Control Result Resultc Limits Acceptance STW-1181 STW-1 181 STW-1 182 STW-1182 STW-1 182 STW-1 182 STW-1 182 STW-1 183 STW-1 183 STW-1 184 STW-1185 STW-1185 STW-1185 STW-1186 STW-1 193 STW-1 193 STW-1 194 STW-1 194 STW-1 194 STW-1194 STW-1194 STW-1 195 STW-1 195 STW-1196 STW-1197 STW-1197 STW-1 197 STW-1198 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 04/06/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 10/05/09 Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 Sr-89 Sr-90 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 Gr. Alpha Gr. Beta 1-131 Ra-226 Ra-228 Uranium H-3 41.0 +/- 5.8 32.4 +/- 2.4 44.6 +/- 3.1 81.0 +/- 3.1 65.6 +/- 5.2 147.7 +/- 5.3 79.8 +/- 7.5 47.6 +/- 2.1 38.5 +/- 1.3 24.4 +/- 2.5 14.0 +/- 0.7 14.3 +/- 2.1 25.0 +/- 0.2 22819.0 +/- 453.0 53.0 +/- 6.0 31.1 +/- 2.2 82.5 +/- 3.5 116.8 +/-3.3 78.8 +/- 5.7 54.2 +/- 3.7 102.5 +/- 6.2 20.3 +/- 2.0 23.7 +/- 1.4 22.4 +/- 1.4 15.0 +/- 0.7 17.4 +/- 2.0 32.5 +/- 0.4 17228.0 +/- 694.0 48.3 31.4 52.7 88.9 72.9 168.0 84.4 54.2 43.5 26.1 15.1 13.6 25.7 20300.0 62.2 30.7 92.9 117.0 78.8 54.6 99.5 23.2 26.0 22.2 13.9 14.9 33.8 16400.0 37.8 - 55.7 22.9 - 36.4 43.4 - 58.3 80.0 - 100.0 59.5 - 80.2 151.0 - 187.0 76.0-101.0 28.3 - 67.7 29.1 - 50.8 21.7 -30.8 11.2-17.3 9.0 - 16.6 20.6 - 28.8 17800.0 - 22300.0 50.2 - 70.1 22.4 - 35.6 78.3 - 102.0 105.0 - 131.0 65.0 - 87.3 49.1 -62.9 89.6-119.0 11.6 -31.1 16.2 -33.9 18.4 - 26.5 10.4 - 16.0 10.0 - 18.0 27.3 - 37.8 14300.0 - 18000.0 Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass

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

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

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

d All gamma -emitters showed a low bias. A large plastic burr found on the base of the Marinelli kept the beaker from sitting directly on the detector. Result of recount in a different beaker, Cs-1 37, 155.33 +/- 14.55 pCi/L.

Samples were recounted and also reanalyzed. A recount of the original vials averaged 23,009 pCi/L.

Reanalysis results were acceptable, 19,170 pCi/L.

Al-1

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

mR Lab Code Date Known Lab Result Control Description Value

+ 2 sigma Limits Acceptance Environmental, Inc.

2009-1 7/6/2009 40 cm.

41.82 45.43 +/- 3.66 29.27 - 54.37 Pass 2009-1 7/6/2009 50 cm.

26.76 32.17 +/- 1.52 18.73 - 34.79 Pass 2009-1 7/6/2009 60 cm.

18.58 20.23 +/- 1.60 13.01 -24.15 Pass 2009-1 7/6/2009 70 cm.

13.65 15.28 +/- 0.79 9.56 - 17.75 Pass 2009-1 7/6/2009 90 cm.

8.26 7.97 +/- 0.40 5.78 - 10.74 Pass 2009-1 7/6/2009 90 cm.

8.26 7.37 +/- 0.49 5.78 - 10.74 Pass 2009-1 7/6/2009 100 cm.

6.69 6.16 +/- 0.64 4.68 - 8.70 Pass 2009-1 7/6/2009 110 cm.

5.53 4.38 +/- 0.24 3.87 - 7.19 Pass 2009-1 7/6/2009 120 cm.

4.65 4.34 +/- 0.23 3.26 - 6.05 Pass 2009-1 7/6/2009 150 cm.

2.97 2.92 +/- 0.25 2.08 - 3.86 Pass Environmental, Inc.

2009-2 12/27/2009 40 cm.

44.83 51.38 +/- 2.69 31.38 - 58.28 Pass 2009-2 12/27/2009 50 cm.

28.69 31.65 +/- 2.81 20.08 - 37.30 Pass 2009-2 12/27/2009 60 cm.

19.92 21.38 +/- 1.19 13.94 - 25.90 Pass 2009-2 12/27/2009 60 cm.

19.92 22.30 +/- 0.50 13.94 - 25.90 Pass 2009-2 12/27/2009 75 cm.

12.75 13.48 +/- 1.02 8.93 - 16.58 Pass 2009-2 12/27/2009 90 cm.

8.85 9.62 +/- 0.74 6.20-11.51 Pass 2009-2 12/27/2009 90 cm.

8.85 8.39 +/- 0.86 6.20 - 11.51 Pass 2009-2 12/27/2009 100 cm.

7.17 6.65 +/- 0.96 5.02 - 9.32 Pass 2009-2 12/27/2009 120 cm.

4.98 4.89 +/- 0.53 3.49 - 6.47 Pass 2009-2 12/27/2009 120 cm.

4.98 4.92 +/- 0.58 3.49 - 6.47 Pass 2009-2 12/27/2009 150 cm.

3.19 2.74 +/- 0.39 2.23 -4.15 Pass 2009-2 12/27/2009 180 cm.

2.21 1.65 +/- 0.33 1.55 -2.87 Pass 2009-2 12/27/2009 180 cm.

2.21 2.12 +/- 0.69 1.55 -2.87 Pass A2-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=l c Activity Limits d Acceptance W-1 2009 W-12009 W-12709 SPW-5553 SPW-217 SPW-539 SPW-71 8 SPMI-814 SPMI-814 SPMI-814 SPMI-815 SPMI-815 SPW-817 SPW-817 SPW-818 SPW-818 SPW-818 SPW-818 SPAP-903 SPAP-903 SPCH-916 SPVE-888 SPF-820 W-40909 W-40909 SPW-12641 SPW-1267 TWW-2124 W-42809 SPMI-2186 SPMI-2186 SPMI-2186 SPMI-2186 SPMI-2186 SPW-2497 SPW-3448 SPW-3497 SPW-3499 SPMI-3582 SPMI-3582 SPAP-3595 SPAP-3595 1/20/2009 1/27/2009 1/27/2009 1/27/2009 1/29/2009 2/24/2009 3/6/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/23/2009 3/23/2009 3/24/2009 4/1/2009 4/7/2009 4/9/2009 4/912009 4/10/2009 4/10/2009 4/21/2009 4/28/2009 5/12/2009 5/12/2009 5/12/2009 5/12/2009 5/12/2009 5/27/2009 7/14/2009 7/15/2009 7/15/2009 7/17/2009 7/17/2009 7/17/2009 7/17/2009 Ra-226 Gr. Alpha Gr. Beta Ra-228 U-238 Ni-63 C-14 Cs-1 34 Cs-137 Sr-90 1-131 1-131(G) 1-131 1-131(G)

Co-60 Cs-134 Cs-137 Sr-90 Cs-1 34 Cs-137 1-131(G) 1-131(G)

Cs-134 Gr. Alpha Gr. Beta Ra-228 U-238 H-3 Ra-226 Cs-134 Cs-137 1-131 1-131(G)

Sr-90 Fe-55 Cs-137 Ni-63 Tc-99 Cs-134 Cs-137 Cs-134 Cs-137 12.88 +/- 0.41 20.20 +/- 0.40 46.26 +/- 0.42 29.11 +/- 2.53 44.98 +/- 2.30 167.93 +/- 3.79 4893.50 +/- 21.69 34.91 +/- 3.85 59.17 +/- 6.70 40.82 +/- 1.59 70.99 +/- 0.62 63.08 +/- 7.12 62.11 +/- 0.59 64.55 +/- 8.32 50.84 +/- 4.70 33.78 +/- 3.42 61.27 +/- 7.18 47.26 +/- 1.89 13.29 +/- 2.89 103.24 +/- 7.54 0.22 +/- 0.02 0.40 +/- 0.08 0.58 +/- 0.02 19.26 +/- 0.40 48.04 +/- 0.42 40.06 +/- 2.79 41.71 +/- 2.25 7932.00 +/- 279.00 14.49 +/- 0.53 32.55 +/- 1.26 54.27 +/- 2.60 60.81 +/- 0.63 56.89 +/- 2.56 43.88 +/- 1.68 2472.37 +/- 10.76 171.06 +/- 9.21 179.99 +/- 3.06 29.61 +/- 0.81 32.86 +/- 3.72 182.49 +/- 10.54 13.01 +/- 3.00 110.63 +/- 6.58 12.69 20.08 45.60 28.66 41.70 211.00 4740.20 35.70 55.60 44.07 69.60 69.60 69.60 69.60 51.99 35.70 55.64 44.07 14.19 111.23 0.22 0.35 0.56 20.08 45.60 40.54 41.70 7063.00 16.78 33.89 55.60 52.40 52.40 52.40 2106.35 166.10 210.40 32.34 31.89 166.10 12.75 110.73 8.88 - 16.50 10.04 - 30.12 35.60 - 55.60 20.06 - 37.26 29.19 - 54.21 147.70 - 274.30 2844.12 -6636.28 25.70 - 45.70 45.60 - 65.60 35.26 - 52.88 55.68 - 83.52 59.60 - 79.60 55.68 - 83.52 59.60 - 79.60 41.99 - 61.99 25.70 - 45.70 45.64 - 65.64 35.26 - 52.88 4.19 -24.19 100.11 - 122.35 0.13 -0.31 0.21 -0.49 0.34 - 0.78 10.04 -30.12 35.60 - 55.60 28.38 - 52.70 29.19 - 54.21 5650.40 - 8475.60 11.75 -21.81 23.89 - 43.89 45.60 - 65.60 40.40 - 64.40 42.40 - 62.40 41.92 -62.88 1685.68 - 2527.62 149.49 - 182.71 147.28 - 273.52 20.34 - 44.34 21.89 - 41.89 149.49 - 182.71 2.75 - 22.75 99.66 - 121.80 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 A3-1

TABLE A-3. In-House "Spike" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 Activity Limitsc Acceptance SPF-3597 SPF-3597 SPW-3599 SPW-12643 W-80709 W-81009 W-81009 W-100109 W-102709 W-1 02709 SPW-5964 SPW-12647 SPAP-6769 SPAP-6774 SPAP-6774 SPF-6776 SPF-6776 SPW-6780 SPMI-6782 SPMI-6782 SPMI-6782 SPW-6784 SPW-6784 SPW-6784 7/17/2009 7/17/2009 7/17/2009 8/3/2009 8/7/2009 8/10/2009 8/10/2009 10/1/2009 10/27/2009 10/27/2009 10/28/2009 11/6/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12t14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 Cs-134 Cs-137 H-3 Ra-228 Ra-226 Gr. Alpha Gr. Beta Ra-226 Gr. Alpha Gr. Beta U-238 Ra-228 Gr. Beta Cs-134 Cs-137 Cs-134 Cs-137 Tc-99 Co-60 Cs-134 Cs-137 Co-60 Cs-134 Cs-137 0.53 +/- 0.03 2.43 +/- 0.05 63246.00 +/- 725.00 38.18 +/- 2.72 16.28 +/- 0.41 20.58 +/- 0.44 44.44 +/- 0.40 15.68 +/- 0.41 21.50 +/- 0.43 44.83 +/- 0.40 40.20 +/- 1.87 44.49 +/- 3.33 45.43 +/- 0.11 10.32 +/- 0.83 106.58 +/- 2.51 0.43 +/- 0.02 2.33 +/- 0.05 30.71 +/- 1.09 74.30 +/- 5.41 58.82 +/- 3.75 178.18 +/- 9.68 74.03 +/- 4.64 54.84 +/- 3.83 180.06 +/- 8.81 0.51 2.22 62495.00 40.54 16.77 20.08 45.60 16.77 20.08 45.60 41.70 40.54 49.48 11.11 109.70 0.44 2.19 32.34 72.81 55.54 164.55 72.81 55.54 164.55 0.31 - 0.71 1.33.3.10 49996.00 - 74994.00 28.38 - 52.70 11.74 -21.80 10.04 - 30.12 35.60 - 55.60 11.74 -21.80 10.04 -30.12 35.60 - 55.60 29.19 -54.21 28.38 - 52.70 29.69 - 69.27 1.11 -21.11 98.73 - 120.67 0.26 - 0.62 1.31 -3.07 20.34 - 44.34 62.81 -82.81 45.54 - 65.54 148.10 - 181.01 62.81 -82.81 45.54 - 65.54 148.10 - 181.01 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass

' Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/mr3), 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 established from the precision values listed in Attachment A of this report, adjusted to +/- 2a.

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

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

A3-2

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

Acceptance Type LLD Activityc Criteria (4.66 a)

W-12009 SPW-5554 W-12709 W-12709 SPW-218 SPW-538 SPW-717 SPMI-816 SPMI-816 SPMI-816 SPMI-816 SPMI-816 SPW-819 SPW-819 SPW-819 SPW-819 SPW-819 SPW-819 SPAP-902 SPAP-904 SPAP-904 SPW-32709 SPF-821 SPF-821 W-40909 W-40909 SPW-12651 SPW-1268 W-42809' SPMI-2186 SPMI-2187 SPMI-2187 SPMI-2187 SPMI-2187 SPW-2498 Water Water Water Water Water Water Water Milk Milk Milk Milk Milk Water Water Water Water Water Water Air Filter Air Filter Air Filter Water Fish Fish Water Water Water Water Water Milk Milk Milk Milk Milk Water 1/20/2009 1/27/2009 1/27/2009 1/27/2009 1/29/2009 2/24/2009 3/6/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/16/2009 3/23/2009 3/23/2009 3/23/2009 3/23/2009 4/7/2009 4/7/2009 4/9/2009 4/9/2009 4/10/2009 4/10/2009 4V28/2009 5/12/2009 5/12/2009 5/12/2009 5/12/2009 5/12/2009 5127/2009 Ra-226 Ra-228 Gr. Alpha Gr. Beta U-238 Ni-63 C-14 Cs-134 Cs-137 1-131 1-131(G)

Sr-90 Co-60 Cs-134 Cs-137 1-131 1-131(G)

Sr-90 Gr. Beta Cs-134 Cs-137 Ni-63 Cs-134 Cs-137 Gr. Alpha Gr. Beta Ra-228 U-238 Ra-226 Sr-90 Cs-134 Cs-137 1-131

.1-131(G)

Ni-63 0.05 0.08 0.35 0.74 0.19 7.91 7.66 3.24 3.38 0.31 3.65 0.48 3.02 2.25 2.03 0.42 3.02 1.10 0.003 1.68 2.62 2.84 3.12 3.93 0.40 0.77 0.77 0.11 0.04 0.43 3.61 3.13 0.15 3.77 1.60 0.06 +/- 0.04 0.17 +/- 0.40 0.22 +/- 0.27

-0.08 +/- 0.51

-0.06 +/- 0.09 4.96 +/- 4.93 3.03 + 4.71 0.04 +/- 0.17 0.41 + 0.27

-0.06 +/- 0.19

-0.63 +/- 0.44 0.006 +/- 0.002 1.37 +/- 1.75

-0.25 +/- 0.26

-0.30 +/- 0.53 0.77 +/- 0.45 0.24 +/- 0.17 0.09 +/- 0.04 0.52 +/- 0.26

-0.02 +/- 0.10 0.00 +/- 0.97 1

2 1

3.2 2

20 200 10 10 0.5 20 1

10 10 10 0.5 20 1

3.2 100 100 20 100 100 I

3.2 2

1

-1 1

10 10 0.5 20 20 A4-1

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

Acceptance Type LLD Activityc Criteria (4.66 Y)

SPW-3497 SPW-3500 SPMI-3589 SPAP-3594 SPAP-3594 SPF-3596 SPF-3596 SPF-3596 SPW-3598 SPW-12653 W-80709 W-81009 W-81009 W-100109 W-102709 W-102709 SPW-5965 SPW-12657 SPAP-6769 SPAP-6773 SPF-6775 SPF-6775 SPW-6777 SPW-6779 SPMI-6781 SPMI-6781 SPMI-6781 SPW-6783 SPW-6783 SPW-6783 Water Water Milk Air Filter Air Filter Fish Fish Fish Water Water Water Water Water Water Water Water Water Water Air Filter Air Filter Fish Fish Water Water Milk Milk Milk Water Water Water 7/15/2009 7/15/2009 7/17/2009 7/17/2009 7/17/2009 7/17/2009 7/17/2009 7/17/2009 7/17/2009 8/3/2009 8/7/2009 8/10/2009 8110/2009 10/1/2009 10/27/2009 10/27/2009 10/28/2009 11/6/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 12/14/2009 Ni-63 Tc-99 1-131(G)

Cs-134 Cs-137 Co-60 Cs-134 Cs-137 H-3 Ra-228 Ra-226 Gr. Alpha Gr. Beta Ra-226 Gr. Alpha Gr. Beta U-238 Ra-228 Gr. Beta Cs-137 Cs-134 Cs-137 Ni-63 Tc-99 Cs-134 Cs-137 1-131(G)

Cs-134 Cs-1 37 1-131(G) 1.55 0.90 5.75 1.14 2.47 5.00 8.00 11.50 148.40 0.76 0.04 0.44 0.75 0.04 0.38 0.81 0.15 0.86 0.003 1.31 5.70 4.18 2.29 1.16 2.62 3.29 2.65 2.18 2.90 2.30

-0.24 +/- 0.94

-1.71 +/- 0.53 0.69 +/- 73.60 1.46 +/- 0.51 0.08 +/- 0.03 0.08 +/- 0.31

-0.31 +/- 0.52 0.09 +/- 0.03 0.33 +/- 0.30

-0.59 +/- 0.55 0.09 +/- 0.13 0.80 +/- 0.50 0.010 +/- 0.002 0.25 +/- 1.38

-0.98 +/- 0.69 20 10 20 100 100 100 100.

100 200 2

1 1

3.2 1

1 3.2 1

2 3.2 100 100 100 20 10 10 10 20 10 10 20 a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

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

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

A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance AP-7464, 7465 E-20, 21 CF-67, 68 CF-67, 68 CF-67, 68 DW-90010, 90011 DW-90010, 90011 SG-198, 199 SG-198, 199 SW-308, 309 LW-330, 331 SW-308, 309 DW-375, 376 SWU-606, 607 U-651, 652 U-651, 652 SG-739,740 MI-875, 876 MI-875, 876 WW-970,971 XWW-980,981 AP-1441, 1442 SWT-1123, 1124 WW-1102, 1103 XWW-1174, 1175 AP-1462, 1463 SL-2024, 2025 SL-2024, 2025 SL-2024, 2025 SO-2045, 2046 SO-2045, 2046 SO-2045, 2046 mi-2251,2252 mi-2381, 2382 SWT-2534, 2535 G-2626, 2627 G-2626, 2627 WW-2732, 2733 1/1/2009 1/5/2009 1/5/2009 1/5/2009 1/5/2009 1/9/2009 1/9/2009 1/23/2009 1/23/2009 1/27/2009 1/27/2009 1/29/2009 2/4/2009 2/24/2009 2/27/2009 2/27/2009 3/2/2009 3/17/2009 3/17/2009 3/24/2009 3/24/2009 3/30/2009 3/31/2009 4/1/2009 4/1/2009 4/2/2009 5/4/2009 5/4/2009 5/4/2009 5/4/2009 5/4/2009 5/4/2009 5/14/2009 5/19/2009 5/26/2009 5/28/2009 5/28/2009 6/1/2009 Be-7 K-40 Be-7 Gr. Beta K-40 Ra-226 Ra-228 Gr. Alpha Gr. Beta Gr. Beta Gr. Beta Gr. Beta Gr. Beta Gr. Beta Beta-K40 H-3 Ra-226 K-40 Sr-90 Gr. Beta H-3 Be-7 Gr. Beta Gr. Beta H-3 Be-7 Be-7 Gr. Beta K-40 Gr. Alpha Gr. Beta Sr-90 K-40 K-40 Gr. Beta Gr. Beta K-40 H-3 0.063 +/- 0.012 1.34 +/- 0.21 0.34 +/- 0.12 4.34 +/- 0.11 3.16 +/- 0.26 2.97 +/- 0.22 3.13 +/- 0.71 101.90 +/- 6.50 97.80 +/- 3.50 1.43 +/- 0.58 2.09 +/- 0.58 1.51 +/- 0.56 2.72 +/- 0.65 2.66 +/- 0.68 3.90 +/- 2.30 597.00 +/- 292.00 8.20 +/- 0.20 1286.50 +/- 111.60 0.67 +/- 0.31 13.59 +/- 2.32 7143.00 +/- 262.00 0.076 +/- 0.012 1.40 +/- 0.55 2.13 +/- 1.34 2814 +/- 176 0.085 +/- 0.014 0.80 +/- 0.18 2.41 +/- 0.19 1.20 +/- 0.21 6.22 +/- 2.87 28.85 +/- 3.15 0.036 +/- 0.010 1220.60 +/- 155.10 1472.50 +/- 122.90 1.12 +/- 0.57 6.32 +/- 0. 19 4.13 +/- 0.35 240.73 +/- 93.21 0.065 +/- 0.010 1.13 +/- 0.13 0.39 +/- 0.08 4.38 +/- 0.12 3.00 +/- 0.16 2.76 +/- 0.21 3.55 +/- 0.81 101.70 +/- 6.10 94.00 +/- 3.20 1.41 +/- 0.54 2.33 +/- 0.63 1.61 +/- 0.57 3.06 +/- 0.69 2.16 +/- 0.67 1.70 +/- 2.50 507.00 +/- 288.00 8.30 +/- 0.20 1471.70 +/- 111.50 0.36 +/- 0.36 17.33 +/- 2.69 7262.00 +/- 264.00 0.075 +/- 0.014 1.86 +/- 0.62 2.30 +/- 1.32 2787 +/- 176 0.10 +/- 0.016 0.82 +/- 0.13 2.68 +/- 0.21 1.30 +/- 0.15 6.50 +/- 3.26 30.39 +/- 3.34 0.024 +/- 0.010 1455.50 +/- 118.20 1412.80 +/- 117.40 1.66 +/- 0.58 6.18 +/- 0.19 4.05 +/- 0.34 190.39 +/- 90.81 0.064 +/- 0.008 1.24 +/- 0.12 0.37 +/- 0.07 4.36 +/- 0.08 3.08 +/- 0.15 2.87 +/- 0.15 3.34 +/- 0.54 101.80 +/- 4.46 95.90 +/- 2.37 1.42 +/- 0.40 2.21 +/- 0.43 1.56 +/- 0.40 2.89 +/- 0.47 2.41 +/- 0.48 2.80 +/- 1.70 552.00 +/- 205.07 8.25 +/- 0.14 1379.10 +/- 78.88 0.52 +/- 0.24 15.46 +/- 1.78 7202.50 +/- 185.97 0.076 +/- 0.009 1.63 +/- 0.41 2.22 +/- 0.94 2801 +/- 124 0.091 +/- 0.011 0.81 +/- 0.11 2.55 +/- 0.14 1.25 +/- 0.13 6.36 +/- 2.17 29.62 +/- 2.30 0.030 +/- 0.007 1338.05 +/- 97.50 1442.65 +/- 84.98 1.39 +/- 0.41 6.25 +/- 0.13 4.09 +/- 0.24 215.56 +/- 65.07 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 SO-3141, 3142 SO-3141, 3142 SO-3141, 3142 SO-3141, 3142 SO-3141, 3142 SO-3141, 3142 SO-3141, 3142 SO-3141, 3142 SO-3141, 3142 SO-3141,3142 SO-3141, 3142 SO-3141,3142 SG-3187,3188 SG-3187, 3188 SL-3297, 3298 SL-3297, 3298 SL-3297, 3298 AP-3944, 3945 DW-90222, 90223 DW-90222, 90223 DW-90237, 90238 F-3790, 3791 DW-90250, 90251 DW-90250,90251 VE-3965, 3966 VE-4098, 4099 VE-4098, 4099 VE-4098, 4099 SO-4325,4326 SO-4325,4326 SO-4325, 4326 SG-4283, 4284 SG-4283,4284 VE-4436, 4437 SL-4589, 4590 SL-4589, 4590 AV-4882, 4883 AV-4882, 4883 6/22/2009 6/22/2009 6/22/2009 6/22/2009 6/22/2009 6/22/2009 6122/2009 6/22/2009 6/22/2009 6/22/2009 6/22/2009 6/22/2009 6/25/2009 6/25/2009 7/1/2009 7/1/2009 7/1/2009 7/1/2009 7/15/2009 7/15/2009 7/17/2009 7/21/2009 7/22/2009 7/22/2009 7/28/2009 8/3/2009 8/3/2009 8/3/2009 8/14/2009 8/14/2009 8/14/2009 8/17/2009 8/17/2009 8/25/2009 9/1/2009 9/1/2009 9/8/2009 9/8/2009 Ac-228 Be-7 Bi-212 Bi-214 Cs-1 37 Pb-212 Pb-214 Pu-239/40 Th-232 TI-208 U-233/4 U-238 Ac-228 Pb-214 Be-7 Gr. Beta K-40 Be-7 Ra-226 Ra-228 Gr. Alpha K-40 Ra-226 Ra-228 K-40 Be-7 Gr. Beta K-40 Be-7 Cs-137 K-40 Ac-228 Pb-214 K-40 Be-7 K-40 Be-7 K-40 1.07 +/- 0.06 0.55 +/- 0.14 1.16 +/- 0.17 0.96 +/- 0.03 0.72 +/- 0.07 1.00 +/- 0.02 1.01 +/- 0.03 0.022 + 0.008 0.51 _ 0.04 0.35 _ 0.02 0.16 + 0.02 0.14 +/-+0.02 11.07 +/- 0.33 26.54 +/- 0.23 1.15 +/- 0.13 3.38 +/- 0.23 1.43 +/- 0.18 0.064 +/- 0.009

- 5.36 +/- 0.60 2.91 +/- 0.73 3.54 +/- 0.99 1.10 +/- 0.35 14.58 +/- 0.39 6.71 + 1.05 1.48 +/- 0.16 0.54 + 0.16 5.15 + 0.17 4.91 +/- 0.49 0.59 _ 0.21 0.29 +/- 0.05 13.41 +/- 0.77 7.16 +/- 0.28 6.27 +/- 0.13 2.28 +/- 0.28 1.25 0 0.22 2.96 + 0.30 0.93 + 0.18 2.50 + 0.26 1.06 +/- 0.05 0.62 +/- 0.08 1.14 +/- 0.16 1.01 +/- 0.03 0.76 +/- 0.08 1.03 +/- 0.02 1.04 +/- 0.03 0.030 +/- 0.009 0.48 +/- 0.05 0.36 +/- 0.02 0.18 +/- 0.02 0.18 +/- 0.03 10.88 +/- 0.33 26.17 +/- 0.25 1.15 +/- 0.12 3.37 +/- 0.12 1.50 +/- 0.19 0.068 +/- 0.010 4.62 +/- 0.51 2.80 +/- 0.70 4.22 +/- 1.09 1.41 +/- 0.44 15.13 +/- 0.40 6.10 +/- 1.01 1.56 +/- 0.19 0.58 +/- 0.16 5.07 +/- 0.18 5.17 +/- 0.15 0.68 +/- 0.28 0.28 +/- 0.05 13.46 +/- 0.80 7.10 +/- 0.26 6.21 +/- 0.13 2.67 +/- 0.26 1.25 +/- 0.16 2.70 +/- 0.27 0.95 +/- 0.17 2.47 +/- 0.29 1.07 +/- 0.04 0.59 +/- 0.08 1.15 +/- 0.12 0.99 +/- 0.02 0.74 +/- 0.05 1.02 +/- 0.01 1.03 +/- 0.02 0.026 +/- 0.006 0.50 +/- 0.03 0.36 +/- 0.01 0.17 +/- 0.01 0.16 +/- 0.02 10.97 +/- 0.24 26.36 +/- 0.17 1.15 +/- 0.09 3.38 +/- 0.13 1.47 +/- 0.13 0.066 +/- 0.007 4.99 +/- 0.39 2.86 +/- 0.51 3.88 +/- 0.74 1.26 +/- 0.28 14.86 +/- 0.28 6.41 +/- 0.73 1.52 +/- 0.13 0.56 +/- 0.11 5.11 +/- 0.12

5.04 +/- 0.26 0.64 +/- 0.18 0.28 +/- 0.03 13.43 +/- 0.56 7.13 +/- 0.19 6.24 +/- 0.09 2.48 +/- 0.19 1.25 +/- 0.14 2.83 +/- 0.20 0.94 +/- 0.12 2.49 +/- 0.20 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 A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance WW-4721,4722 WW-4903, 4904 BS-5119, 5120 BS-5119, 5120 BS-5119, 5120 SS-5188, 5189 SS-5188, 5189 AP-3944,3945 E-5251, 5252 E-5251, 5252 G-5272, 5273 G-5272, 5273 G-5272, 5273 F-5690, 5691 F-5690, 5691 DW-90396,90397 DW-90396,90397 DW-90408,90409 DW-90408,90409 DW-90420,90421 DW-90420,90421 SG-5962,5963 SG-5962,5963 DW-90423, 90424 ME-6116, 6117 ME-6116, 6117 F-6567,6568 F-6567,6568 W-6495,6496 WW-6313, 6314 SWU-6611, 6612 DW-90446,90447 DW-90446,90447 9/9/2009 9/11/2009 9/16/2009 9/16/2009 9/16/2009 9/23/2009 9/23/2009 9/29/2009 10/1/2009 10/1/2009 10/1/2009 10/1/2009 10/1/2009 10/15/2009 10/15/2009 10/16/2009 10/16/2009 10/19/2009 10/19/2009 10/21/2009 10/21/2009 10/22/2009 10/22/2009 10/27/2009 11/3/2009 11/3/2009 11/6/2009 11/6/2009 11/8/2009 11/9/2009 11/24/2009 12/30/2009 12/30/2009 H-3 H-3 Be-7 Cs-137 K-40 Be-7 K-40 Be-7 Gr. Beta K-40 Be-7 Gr. Alpha K-40 H-3 K-40 Ra-226 Ra-228 Ra-226 Ra-228 Ra-226 Ra-228 Ac-228 Pb-214 Gr. Alpha Gr. Beta K-40 Gr. Beta Sr-90 H-3 H-3 Gr. Beta Ra-226 Ra-228 19191.00 +/- 404.00 1075.00 +/- 130.00 2067.50 +/- 327.90 86.24 +/- 35.40 16.85 +/- 0.90 1.02 +/- 0.31 10.21 +/- 0.65 0.09 +/- 0.02 2.30 +/- 0.10 1.18 +/- 0.24 3.31 +/- 0.29 19.81 +/- 0.80 16.47 +/- 0.75 8895.00 +/- 250.00 3.62 +/- 0.40 0.54 +/- 0.09 1.44 +/- 0.56 0.99 +/- 0.12 2.76 +/- 0.66 1.95 +/- 0.17 3.10 +/- 0.73 16.39 +/- 0.79 18.03 +/- 0.41 12.04 +/- 1.68 0.86 +/- 0.03 2.57 +/- 0.08 2.72 +/- 1.05 0.09 +/- 0.03 2638.00 +/- 173.00 1514.00 +/- 137.00 1.88 +/- 0.60 0.30 +/- 0.10 2.60 +/- 0.64 18677.00 + 399.00 1281.00 +/- 136.00 2225.40 +/- 371.10 145.10 +/- 31.54 17.27 +/- 0.79 1.04 +/- 0.43 9.94 +/- 0.93 0.09 +/- 0.02 2.10 +/- 0.10 1.15 +/- 0.18 3.60 +/- 0.26 21.10 +/- 0.74 17.00 +/- 0.74 9051.00 +/- 252.00 3.09 +/- 0.48 0.42 +/- 0.08 0.94 +/- 0.51 1.10 +/- 0.14 1.38 +/- 0.92 1.77 +/- 0.15 3.32 +/- 0.80 16.51 +/- 0.63 17.74 +/- 0.42 15.28 +/- 1.97 0.83 +/- 0.03 2.65 +/- 0.08 3.04 +/- 0.92 0.12 +/- 0.04 2451.00 +/- 168.00 1483.00 +/- 136.00 1.67 +/- 0.59 0.54 +/- 0.14 2.65 +/- 0.65 18934.00 +/- 283.91 1178.00 +/- 94.07 2146.45 +/- 247.61 115.67 +/- 23.71 17.06 +/- 0.60 1.03 +/- 0.26 10.07 +/- 0.57 0.09 +/- 0.01 2.20 +/- 0.07 1.17 +/- 0.15 3.46 +/- 0.19 20.46 +/- 0.54 16.74 +/- 0.53 8973.00 +/- 177.49 3.36 +/- 0.31 0.48 +/- 0.06 1.19 +/- 0.38 1.05 +/- 0.09 2.07 +/- 0.57 1.86 +/- 0.11 3.21 +/- 0.54 16.45 +/- 0.51 17.89 +/- 0.29 13.66 +/- 1.29 0.85 +/- 0.02 2.61 +/- 0.06 2.88 +/- 0.70 0.11 +/- 0.02 2544.50 +/- 120.57 1498.50 +/- 96.52 1.78 +/- 0.42 0.42 +/- 0.09 2.63 +/- 0.46 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 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).

A5-3

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

Concentration b Known Control Lab Code c Date Analysis Laboratory result Activity Limits d Acceptance STW-1 170' STW-1 170 STW-1170 STW-1170 STW-1170 STW-1170 STW-1170 STW-1 170 STW-1 170 STW-1170 STW-1170 STW-1 170 STW-1170 STW-1170 STW-1170 STW-1170 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 Am-241 Co-57 Co-60 Cs-134 Cs-137 Fe-55 H-3 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-233/4 U-238 Zn-65 STW-1171 01/01/09 Gr. Alpha STW-1171 01/01/09 Gr. Beta 1.15 +/- 0.06 19.60 +/- 0.40 16.60 +/- 0.30 20.40 +/- 0.50 0.10 +/- 0.20 51.60 +/- 20.60 359.90 +/- 33.90 15.00 +/- 0.40 50.50 +/- 3.25 1.17 +/- 0.04 0.74 +/- 0.03 7.87 +/- 1.39 12.70 +/- 0.80 2.78 +/- 0.07 2.87 +/- 0.07 14.00 +/- 0.70 0.56 +/- 0.06 1.29 +/- 0.05 0.00 +/- 0.00 458.60 +/- 7.40 652.30 +/- 3.50 636.40 +/- 9.50 346.40 +/- 3.10 28.60 +/- 2.20 0.50 +/- 0.40 180.60 +/- 12.10 152.20 +/- 4.30 154.90 +/- 4.40 268.30 +/- 4.00 2.75 +/- 0.11 0.06 +/- 0.09 3.49 +/- 0.22 1.01 +/-0.11 2.52 +/- 0.14 1.52 +/- 0.18 0.64 18.90 17.21 22.50 0.00 48.20 330.90 14.66 53.50 1.18 0.85 7.21 14.46 2.77 2.88 13.60 0.64 1.27 0.00 467.00 605.00 570.00 307.00 25.30 0.00 257.00 149.00 155.00 242.00 2.36 0.00 3.40 0.93 2.30 1.35 0.45 - 0.83 13.20 -24.60 12.05 - 22.37 15.80 -29.30 0.00 -1.00 33.70 - 62.70 231.60 -430.20 10.26 - 19.06 37.45 - 69.55 0.83 - 1.53 0.60 - 1.11 5.05 - 9.37 10.12 - 18.80 1.94 - 3.60 2.02 - 3.74 9.50 - 17.70 0.00 - 1.27 0.64 -1.91 0.00 -1.00 327.00 - 607.00 424.00 - 787.00 360.40 - 669.40 215.00 - 399.00 17.70 - 32.90 0.00 - 1.00 180.00 -334.00 104.00 - 194.00 109.00 -202.00 169.00 - 315.00 1.65 - 3.07 0.00 - 1.00 2.38 - 4.42 0.65 -1.21 1.61 -2.99

-0.95 - 1.76 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 Pass Pass Pass Pass Pass Pass STSO-1 172 e STSO-1 172 STSO-1 172 STSO-1172 STSO-1 172 STSO-1 172 STSO-1172 e STSO-1 172 STSO-1 172 STSO-1 172 STSO-1172 STVE-1 173 STVE-1173 e STVE-1173 STVE-1 173 STVE-1 173 STVE-1 173 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 Co-57 Cs-134 Cs-137 K-40 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 A6-1

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

Concentration b Known Control Lab Code C Date Analysis Laboratory result Activity Limits d Acceptance STAP-1174 '

STAP-1 174 STAP-1 174 STAP-1 174 STAP-1 174 STAP-1 174 STAP-1174 h STAP-1 174 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 01/01/09 Am-241 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 0.29 +/- 0.03 1.25 +/- 0.05 1.17 +/- 0.06 2.67 +/- 0.14 1.53 +/- 0.08 2.34 +/- 0.09 0.93 +/-+0.14 1.44 +/- 0.14 0.22 +/- 0.03 0.36 +/- 0.04 0.21 1.30 1.22 2.93 1.52 2.27 0.64 1.36 0.35 0.28 0.14 -0.27 0.91 -1.69 0.85 - 1.59 2.05 - 3.81 1.06 -1.98 1.59 -2.95 0.45 - 0.83 0.95 - 1.77 0.00 - 0.70 0.14 -0.42 STAP-1 175 01/01/09 Gr. Alpha STAP-1175 01/01/09 Gr. Beta STSO-1 188 STS1O-1188 STSO-1188 STSO-1 188 STSO-1 188 STSO-1188 STSO-1 188 STSO-1188 STSO-1188 STSO-1 188 STSO-1 188 STSO-1 188 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 Co-57 Co-60 Cs-134 Cs-137 K-40 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 STAP-1 189 07/01/09 Gr. Alpha STAP-1 189 07/01/09 Gr. Beta 674.60 +/- 9.00 356.40 +/- 6.30 0.20 +/- 1.90 767.50 +/- 12.00 433.00 +/- 37.20 931.60 +/- 14.10 53.10 +/- 9.00 107.10 +/- 12.60 310.50 +/- 12.20 188.20 +/- 11.90 197.40 +/- 12.20 1433.90 +/- 25.20 0.33 +/- 0.04 1.57 +/- 0.07 0.01 +/- 0.02 6.78 +/- 0.27 1.06 +/- 0.18 0.01 +/- 0.06 1.49 +/- 0.27 6.00 +/- 0.45 0.79 +/- 0.13 4.55 +/- 0.66 8.90 +/- 0.60 2.50 +/- 0.36 0.01 +/- 0.11 2.42 +/- 0.16 8.35 +/- 0.70 0.01 +/- 0.26 586.00 327.00 0.00 669.00 375.00 796.00 63.20 116.30 455.00 209.00 217.00 1178.00 0.66 1.32 0.00 6.48 1.03 0.00 1.40 5.49 0.84 3.93 8.00 2.57 0.00 2.43 7.90 0.00 410.00 -762.00 229.00 - 425.00 0.00 - 1.00 468.00 - 870.00 263.00 - 488.00 557.00 - 1035.00 44.20 - 82.20 81.40 - 151.20 319.00 - 592.00 146.00 - 272.00 152.00 -282.00 825.00 - 1531.00 0.00 - 1.32 0.66 -1.98 0.01 - 0.05 4.54 - 8.42 0.72 - 1.34 0.01 - 0.05 0.98 -1.82 3.84 -7.14 0.59 - 1.09 2.75 -5.11 5.60 - 10.40 1.80 -3.34 0.00 -0.10 1.70 -3.16 5.50 - 10.30 0.00 - 0.10 Fail Pass Pass Pass Pass Pass Fail 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-1 190 STAP-1 190 STAP-i 190 STAP-1 190 STAP-1 190 STAP-I 190 STAP-1 190 STAP-1 190 STVE-1 190 STVE-1 190 STVE-1 190 STVE-1 190 STVE-1 190 STVE-1 190 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 07/01/09 Am-241 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 A6-2

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

Concentration b Known Control Lab Code c Date Analysis Laboratory result Activity Limits d Acceptance STW-1 191 07/01/09 Gr. Alpha 0.88 +/- 0.07 1.05 0.00 -2.09 Pass STW-1191 07/01/09 Gr. Beta 7.29 +/- 0.10 7.53 3.77 -11.30 Pass STW-1192 07/01/09 Am-241 0.88 +/- 0.08 1.04 0.73 -1.35 Pass STW-1192 07/01/09 Co-57 37.20 +/- 1.50 36.60 25.60 - 47.60 Pass STW-1192 07/01/09 Co-60 15.10 +/- 0.90 15.40 10.80 - 20.00 Pass STW-1192 07/01/09 Cs-134 30.30 +/- 2.10 32.20 22.50 - 41.90 Pass STW-1192 07/01/09 Cs-137 41.90 +/- 1.80 41.20 28.80 - 53.60 Pass STW-1192 07/01/09 Fe-55 54.50 +/- 15.50 60.80 42.60 - 79.00 Pass STW-1 192 07/01/09 H-3 680.30 +/- 33.60 634.10 443.90 - 824.30 Pass STW-1192 e 07/01/09 Mn-54 0.01 +/- 0.26 0.00 0.00 -1.00 Pass STW-1 192 07/01/09 Ni-63 38.70 +/- 2.60 44.20 30.90 - 57.50 Pass STW-1 192 07/01/09 Pu-238 0;02 +/- 0.01 0.02 0.00 - 0.05 Pass STW-1192 07/01/09 Pu-239/40 1.70 +/- 0.10 1.64 1.15 -2.13 Pass STW-1192 07/01/09 Sr-90 12.90 +/- 1.70 12.99 9.09 - 16.89 Pass STW-1192 07/01/09 Tc-99 7.60 +/- 0.40 10.00 7.00 - 13.00 Pass STW-1192 07/01/09 Tc-99 7.60 +/- 0.40 10.00 7.00 - 13.00 Pass STW-1192 07/01/09 U-233/4 2.90 +/- 0.10 2.96 2.07 -3.85 Pass STW-1192 07/01/09 U-238 3.00 +/- 0.10 3.03 2.12 -3.94 Pass STW-1192 07/01/09 Zn-65 28.50 +/- 2.40 26.90 18.80 -35.00 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 Included in the testing series as a "false positive".

f No errors were found in procedure or calculation. There was not enough sample for a reanalysis. Americium-241 in water was included in the ERA studies (TbI. A-7) and also in the second round of MAPEP testing. Both analysis results were acceptable.

9 One determination was eliminated from the average, due to poor recovery. Average of three determinations, 0.25 +/- 0.03 pCi/filter.

No reason was determined for the initial high results. The analysis was repeated; result of reanalysis; 0.54 +/- 0.12 Bq/filter.

Incomplete separation of strontium from calcium could result in a higher recovery percentage and consequently lower reported activity. The analysis was repeated; result of reanalysis 363.3 +/- 28.6 Bq/kg.

A6-3

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

Concentration (pCi/L)

Lab Code b Date Analysis Laboratory ERA Control Result '

Result d Limits Acceptance STAP-1 176 STAP-1 176 STAP-1176 STAP-1176 STAP-1176 e STAP-1 176 STAP-1 176 STAP-1 176 STAP-1 176 STAP-1 176 STAP-1 176 STAP-1 176 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 Am-241 Co-60 Cs-134 Cs-137 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium Zn-65 47.20 +/- 3.10 543.60 +/- 8.90 941.30 +/- 30.70 850.60 +/- 19.40 0.00 +/- 0.00 64.50 +/- 3.60 88.50 +/- 4.20 93.90 +/- 10.00 50.00 +/- 2.47 50.40 +/- 2.48 101.60 +/- 5.30 237.30 +/- 23.70 76.30 +/- 3.47 98.50 +/- 3.04 55.4 490.0 865.0 724.0 0.0 57.4 78.2 95.3 53.5 53.1 109.0 185.0 32.4 - 76.0 379.0 - 612.0 563.0 - 1070.0 544.0 - 951.0 0.0 - 0.0 39.4 - 75.5 56.7 - 101.0 41.9-148.0 33.7 - 79.3 34.0 - 75.4 55.7 - 173.0 128.0 - 256.0 33.1 -96.0 49.7 -118.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STAP-1177 03/23/09

- Gr. Alpha STAP-1177 03/23/09 Gr. Beta 63.8 80.7 STSO-1 178 STSO-1 178 STSO-1178 STSO-1178 STSO-1 178 STSO-1 178 STSO-1178 STSO-1178 STSO-1 178 STSO-1 178 STSO-1 178 STSO-1 178 STSO-1178 STSO-1 178 STSO-1178 STSO-1178 STSO-1178 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03123/09 03123/09 03/23/09 03/23/09 03/23/09 Ac-228 Am-241 Bi-212 Bi-214 Co-60 Cs-134 Cs-137 K-40 Mn-54 Pb-212 Pb-214 Pu-238 Pu-239/40 Sr-90 U-233/4 Uranium Zn-65 1370.00 +/- 121.00 1853.00 +/- 185.50 1449.00 +/- 308.80 1355.00 +/- 66.20 7475.00 +/- 46.40 5073.00 +/- 74.70 5040.00 +/- 49.70 10884.00 +/- 292.70 0.00 +/- 0.00 1259.00 +/- 28.40 1464.00 +/- 56.80 1853.00 +/- 185.50 1516.50 +/- 168.30 5270.90 +/- 290.20 1452.30 +/- 114.40 3013.70 +/- 131.10 2083.00 +/- 59.00 1330.0 1660.0 1550.0 1420.0 7520.0 5170.0 4970.0 11200.0 0.0 1260.0 1510.0 1590.0 1360.0 5750.0 1600.0 3270.0 1940.0 860.0 - 1880.0 992.0 - 2130.0 406.0 -2310.0 872.0 -2050.0 5470.0 - 10100.0 3330.0 - 6220.0 3800.0 -6460.0 8060.0 - 15100.0 0.0 -20.0 820.0 - 1780.0 902.0 -2260.0 910.0 -2240.0 928.0 - 1800.0 2080.0 - 9380.0 1010.0 - 1990.0 1860.0 - 4410.0 1540.0 -2600.0 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-1 179 STVE-1 179 STVE-1179 STVE-1 179 STVE-1 179 STVE-1 179 STVE-1 179 STVE-1 179 STVE-1 179 STVE-1 179 STVE-1 179 STVE-1179 STW-1180 STW-1180 STW-1180 STW-1180 STW-1 180 STW-1180 STW-1180 STW-1180 STW-1 180 STW-1 180 STW-1 180 STW-1180 STW-1180 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 03/23/09 Am-241 Cm-244 Co-60 Cs-134 Cs-137 K-40 Mn-54 Sr-90 U-233/4 U-238 Uranium Zn-65 Am-241 Co-60 Cs-134 Cs-137 Fe-55 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium Zn-65 2849.70 +/- 237.60 808.00 +/- 85.70 1546.80 +/- 31.60 1706.00 +/- 59.20 1940.50 +/-44.80 30107.30 +/- 598.00 0.00 +/- 0.00 6604.80 +/- 440.10 1718.00 +/- 128.90 1718.30 +/- 128.80 3499.40 +/- 371.00 869.40 +/- 63.60 127.50 +/- 5.10 1174.10 +/- 11.70 742.20 +/- 18.30 887.50 +/- 14.00 323.00 +/- 362.00 0.00 +/- 0.00 96.60 +/- 2.20 89.50 +/- 2.10 763.20 +/- 12.90 95.00 +/- 1.80 97.40 +/- 1.80 195.50 +/- 3.70 653.10 +/- 24.10 3660.0 954.0 1710.0 1880.0 1800.0

.30800.0 0.0, 8860.0 2040.0 2020.0 4150.0 878.0 132.0 1230.0 790.0 913.0 492.0 0.0 108.0 86.3 834.0 96.6 95.8 197.0 631.0 2090.0 - 5030.0 470.0 - 1480.0 1160.0 - 2460.0 1080.0 - 2600.0 1320.0 - 2500.0 22300.0 - 43700.0 0.0 - 0.0 4950.0 - 11800.0 1400.0 - 2710.0 1420.0 - 2550.0 2850.0 - 5360.0 634.0 - 1200.0 90.4 - 178.0 1070.0 - 1450.0 584.0 - 907.0 776.0 - 1090.0 286.0 - 657.0 0.0 - 0.0 81.7 -134.0 66.8 - 107.0 530.0 - 1120.0 72.8 - 124.0 73.2 -119.0 142.0 - 262.0 535.0 - 786.0 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 administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

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

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

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

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

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

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

A7-2

APPENDIX B DATA REPORTING CONVENTIONS B-1

Data Reportinq 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 = 2y 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 If duplicate analyses are reported, the convention is as follows.

3.1 Individual results: For two analysis results; x1 +/- si and x2 +/- s2 Reported result:

x +/- s; where x= (1/2) (x, +x 2) ands= (1/2) 1 +'2 3.2.

Individual results:

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

Individual results:

x +/- s, < L Reported result:

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

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

1 X =n

-x sn-i 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 numbers are kept unchanged. As an example, 11.443 is rounded off to 11.44.

4.5.2.

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

B-2

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

Table C-1.

Maximum permissible concentrations of radioactivity in air and water above natural a

background in unrestricted areas Air (pCi/m 3)

Water (pCi/L)

Gross alpha Gross beta b

Iodine-1 31

-3 1 x1O 1

-1 2.8x 10 Strontium-89 Strontium-90 Cesium-137 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 a

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

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

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

c A natural radionuclide.

C-2

APPENDIX D Sampling Location Maps

TLD LOCATIONS ONE MILE RADIUS

'i PLANT AREA ENLARGED PLAN (1.00 MILE RADIUS).

[NO SCALE]

MONITORING LEGEND:

E) PRAIRIE ISLAND TLO POINTS REV, *,

D-2 TLOOL.OGN REV.

D~2 TLO0I.DGN

TLO LOCATIONS TLD LOCATIONS 2.7 PR4-__,

2J ic

--1 CONTROL POINTS PRESCOTT, WISCONSIN

[SFSI AREA TLD LOCATIONS MONITORING LEGEND:

(

PRAIRIE ISLAND ILD POINTS REV. i D-3 TL002.DGN

TLD LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:

) PRAIRIE ISLAND TLD POINTS REV. 1 D-4 TLD03.DGN REV..1 D-4 TLD03.DGN

ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS PLANT AREA ENLARGED PLAN (1.00 MILE RADIUS]

(NO SCALE]

MONITORING LEGEND MILK SAMPLING POINT IO NUMBERS P-18, P-37, P'42. P-43 A

AIR SAMPLING POINT 10 NUMBERS P-I,:P-2. P-3. P-4. P-6 WATER SAMPLING POINT 1O NUMBERS P-5, P-GP.

P-8, P-q* P-il. P-24. P-443 VEGETATION / VEGETABLES I1 NUMBERS P-28. P-38.P-45 FISH SA.MPLING POINT 10 NUMBERS 0-I3. P-14 INVERTEBRATES POINT IU NUMBERS M

P-6 S

P-4O0 LA SEDIMENT SAMPLING POINT 10 NUMBERS v*

P-E, Pwl 2. P-20 D-51

ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS N,

MONITORING LEGEND

(>

MILK SAMPLING POINT 10 NUMBERS P-lB, P-37, P-42. P-43 A

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

WATER SAMPLING POINT I1 NUMBERS P-S.

P-B.

P-8

, P-Iq. P-24, P-43

]I VEGETATION /

VEGETABLES 10 NUMBERS P-28. P-38. P-45 FISH SAMPLING POINT 10 NUMBERS P-13, P-19 INVERTEBRATES POINT 10 NUMBERS P-S. P-40 SEDIMENT SAMPLING POINT ID NUMBERS P-G, P-12, P-20

Q-6

ENVIRONMENTAL SAMPLING POINTS P-1 10 4ý p43, Peterson Farm, W10322 St Rd 29, River Falls, WI (D P-38, Cain Residence, N7395 960th St, River Falls, W%

CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND MILK SAMPLING POINT ID NUMBER8 P-18, P-37, P-41, P-42, P-43 AIR SAMPLING POINT ID NUMBERS P-1. P-2, P-3, P-4, P-6 O

WATER SAMPLING POINT ID NUMBERS P-8, P4, P.8, P-9, P1t, P-43 El VEGETATION I VEGETABLES ID NUMBERS P-28, P-38, P-45 D-7

APPENDIX E Special Well and Surface Water Samples E-1

1.0 INTRODUCTION

This appendix to the Radiological 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, 2009. This supplemental special sampling program was established in December of 1989 when higher than expected levels of tritium were detected in a nearby residence well sample.

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

E-2

2.0

SUMMARY

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

This program is described and the results for 2009 are summarized and discussed.

Program findings for 2009 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 wells P-10 and MW-8 and storm water runoff sample S-6. The 2009 sample results (except for P-10, MW-8, and S-6) ranged from <19 pCi/L to 320 pCi/L. Sample well P-10 ranged from 75 pCi/L to 686 pCi/L. Sample well MW-8 ranged from 248 pCi/L to 542 pCi/L. Storm water runoff sample S-6 ranged from 56 pCi/L to 515 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.

None of the water samples monitored for gamma-emitting isotopes showed activity greater than the LLD.

The one-time river sediment samples that were monitored for gamma-emitting isotopes showed only natural activity, beryllium-7 and potassium-40 and background levels of cesium-137.

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 E-4.1 and briefly reviewed below. Table E-4.2 defines the additional sample locations and codes for the special water sampling program.

Special well, storage tank, and surface water samples were collected quarterly at one location, monthly at six locations, semi-annually at six locations, and annually at thirty-five 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 2009 include:

sampling was not performed at station P-4 because it has been capped, it has been deleted as a sample point sampling was not performed at the STA house (SW-2) because it was dry deleted Unit 2 demineralizer header sample because it comes from the same source as the Unit 1 demineralizer header added sampling of the Septic System storage tank, S-7 Parking Lot Storm Water Runoff, and 3 additional Prairie Island Indian Community locations PIIC-20, PIIC-23, and PIIC-28 samples were taken from monitoring wells P-10 and MW-8 and from storm water runoff from the parking lot and the Old Administration Building Roof, these samples were sent to Environmental Incorporated for analysis for hard-to-detect nuclides in accordance with American Nuclear Insurers recommendations. (Table E-4.5a)

In addition, gamma analyses were conducted using a P1 plant spectrometer on 3000 mL samples from the following monitoring wells: P-2, P-3, P-5, P-6, P-7, P-10, P-11, PZ-1, PZ-2, PZ-4, PZ-5, PZ-7, PZ-8, MW-4, MW-5, MW-7, and MW-8.

A special one-time sample of surface water and river sediment was conducted in preparation for dredging near the plant intake (Table E-4.5b).

E-4

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 and MW-8 sample wells and S-6, Old Admin Building storm water runoff. Table E-4.4 provides the complete data table of results for each period and sampling location.

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

Except for sample wells P-10 and MW-8 and runoff sample S-6, the 2009 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 and MW-8 in 2009 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 terminated, the last discharge took place on 11/14/09.

None of the water samples monitored for gamma-emitting isotopes showed any activity greater than the LLD.

The one-time river sediment samples that were monitored for gamma-emitting isotopes showed only natural activity, beryllium-7 and potassium-40 and background levels of cesium-1 37.

E-5

Table E-4.1. Sample collection and analysis program for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2009.

Medium No.

Location codes and type Collection type Analysis type c a

and frequency b Well Water 30 P-2, P-3, P-5, P-6, P-7, P-8, G/A H-3 Annual P-9, P-1 1, P-26, P-30, P-6 (REMP),

PIIC-02, PIIC-20, PIIC-22, PlIC-23, PIIC-26, PIIC-28, PZ-1, PZ-2, PZ-4, PZ-5, PZ-7, PZ-8, MW-4, MW-5, MW-6, SW-2, SW-3, SW-4, SW-5 Well Water quarterly 1

P-24D GIQ H-3 Well Water monthly 5

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

MW-7, MW-8, P-10 G/M H-3 Surface Water 7

S-1, S-2, S-3, S-4, G/A d H-3 S-5, S-6, S-7 Storage Tank 4

11 CST, 21 CST, 22 CST, GIS H-3 U1 demin hdr, Storage Tank I

Septic Tank G/M H-3 a Location codes are defined in table D-4.2. Control Stations are indicated by (C). All other stations are indicators.

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

semiannually: A = annually.

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

Location S-6 and S-7 are sampled semi-annually.

I E-6

Table E-4.2. Sampling locations for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2009.

Distance and Code Collection site Type of sample a direction from reactor P-8 PI Community well

, WW 1.0 mi. @ 321°/WNW REMP P-6 Lock & Dam #3 well WW 1.6 mi. @ 1291/SE PIIC-02 2077 Other Day Road WW 1.4 mi. @ 315°/NW PIIC-20 2158 Holmquist Road WW 1.6 mi @ 300°IWNW PIIC-22 1773 Buffalo Slough Rd WW 1 mi. @ 315°/NW PIIC-23 2.7 miles NW WW 2.7 mi @315*/NW PIIC-26 1771 Buffalo Slough Rd WW 1 mi. @ 315°/NW PIIC-28 1960 Larson Lane WW 1.5 mi @ 288°/WNW P-24D Suter residence WW 0.6 mi. @ 158°/SSE P-43 Peterson Farm (Control)

WW 13.9 mi. @ 3550 /N SW-1 Hanson Farm (Control)

WW 2.2 mi. @ 315°/NW P-2 Sample well WW See map P-3 Sample well WW See map P-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-1I 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. P 315°/NW SW-5 Plant Screenhouse well WW 0.05 mi. @ 0I/N P-9

-Plant well # 2 WW 0.3 mi. @ 306°/NW S-1 Upstream Miss. River SW See map S-2 Recirc/Intake canal SW See map S-3 Cooling water canal SW See map S-4 Discharge Canal (end)

SW See map S-5 Mid Discharge Canal SW See map S-6 Roof Stormwater Runoff SW 0.05 mi. @ 0°/N S-7 Parking Lot Stormwater SW 0.3 mi @ 306°/NW 11 CST Storage Tank ST Turbine Building 21 CST Storage Tank ST Turbine Building 22 CST Storage Tank ST Turbine Building Unit 1 demin hdr Storage Tank ST Turbine Building Septic System Storage Tank ST Outside #1 Warehouse a Sample codes: WW = Well water; SW = Surface Water: ST = Storage Tank.

E-7

Table E-4.3 Radiological Environmental Monitoring Program Summary: Special well, storage tank, and surface water samples.

Name of Facility Prairie Island Nuclear Power Station Location of Facility Goodhue, Minnesota (County, State)

Docket No.

Reporting Period 50-282, 50-306 January - December 2009 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Number of Type Anlse(FLc Mean (F)c Mean (F)c Routine Rangec Location d Rangec Range Resultse Offsite Well Water H-3 13 19 38 (6/13)

P-24D 37 (4/5)

(See Control 0

(pCi/L)

(24-54)

Below)

Onsite Well Water H-3 57 19 236 (43/57)

MW-8 407 (12/12)

(See Control 14 (pCi/L)

(22-686)

(248-542)

Below)

Onsite Surface Water H-3 9

19 117 (8/9)

S-6 286 (2/2)

(See Control 0

(pCi/L)

(23-515)

(56-515)

Below)

Onsite Storage Tank H-3 16 19 107 (11/16)

Septic System 135(8/8)

(See Control 0

(pCi/L)

(23-515)

(36-320)

Below)

Control (Offsite Well Water)

H-3 34 19 None P-43 35 (6/12) 34 (8/24) 0 (pCi/L)

(21-56)

(21-56) a H-3 =tritium b

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

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

d Locations are specified by code.

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

E-8

Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2009.

SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2009 2009 2009 2009 2009 2009 2009 2009 2009 2009 2009 2009 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L OFFSITE WELLS P-8 P1 Comm. Well

<19 P-6 (REMP)

Lock & Dam- #3, Well

<19 PIIC-02 2077 Other Day Rd.

<19 PIIC-20 2158 Holmquist Rd.

<19 PIIC-22 1773 Buffalo Slough Rd.

51 PIIC-23 2.7 mi. NW of Plant

<19 PIIC-26 1771 Buffalo Slough Rd.

29 PIIC-28 1960 Larson Lane

<19 P-24D Suter residence 31 54

<19 24 38 P-43 Peterson Farm (Control)

<19 44 28

<19 27

<19 21

<19 56 36

<19

<19 SW-1 Hanson Farm (Control)

<19 36

<19

<19 24

<19

<19 E-9

Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2009, continued JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC SAMPLE DATES 2009 2009 2009 2009 2009 2009 2009 2009 2009 2009 2009 2009 SAMPLE CODE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L

.pCi/L ONSITE WELLS P-2*

Sample Well 30 P-3*

Sample Well

<19 P-5*

Sample Well 77 P-6*

Sample Well

<19 P-7*

Sample Well 59 P-10*

Sample Well 75 263 267 428 445 544 432 226 455 686 219 178 P-11 Sample Well

<19 PZ-I*

Sample Well

<19 PZ-2*

Sample Well

<19 PZ-4*

Sample Well 22 PZ-5*

Sample Well

<19 PZ-7*

Sample Well

<19 PZ-8*

Sample Well

<19 MW-4*

Sample Well

<19 MW-5*

Sample Well

<19 MW-6*

Sample Well 47 MW-7*

Sample Well 79 82

<19 39 49 47 68 68 44 76 84 94 MW-8*

Sample Well 474 501 424 542 476 453 474 438 298 287 264 248 P-26 PITC Well

<19 P-30 Env, lab Well 22 SW-3 CT pump

<19 P-9 Plant Well # 2 23 SW-4 New Admin

<19 SW-5 Pin Scrnhs 24 Gamma isotopic performed at Prairie Island Plant on 3000 mL sample, no radionuclides above LLD were detected.

E-10

Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2009, continued SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2009 2009 2009 2009 2009 2009 2009 2009 2009 2009 2009 2009 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L i

pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L ONSITE SURFACE WATER S-1 Mississippi River upstream 32 S-2 Recirculation/Intake canal 42 S-3 Cooling water canal 23 S-4 Discharge Canal (end) 34 S-5 Discharge Canal (midway)

<19 S-6 Stormwater runoff 515 56 S-7 Parking Lot runoff 48 187 ONSITE STORAGE TANKS 11 CST Storage tank

<19 31 21 CST Storage tank

<19 46 22 CST Storage tank

<19 20 U1 Demin Header Storage tank

<19

<19 U2 Demin Header Storage tank Septic System Storage tank 36 156 74 215 320 121 96 61 E-1 1

Table E-4.5a. Results of analyses for iron-55, nickel-63, strontium-90, isotopic plutonium, americium-241 and isotopic curium.

Groundwater Stormwater Runoff Location P-10 MW-8 Parking Lot Old Admin Bldg Collection Date 5/11/2009 5/11/2009 5/5/2009 5/5/2009 Lab Code PXW-2665 PXW-2666 PXW-2667 PXW-2668 Isotope Concentration (pCi/mL)

Fe-55

< 8.0 E-07

< 8.2 E-07

< 8.3 E-07

< 8.1 E-07 Ni-63

< 8.7 E-09

<8.1 E-09

< 8.0 E-09

< 8.3 E-09 Sr-90

< 2.6 E-09

< 2.7 E-09

< 2.8 E-09 Pu-238

< 1.1 E-10

< 1.4 E-10

< 2.4 E-10

< 1.1 E-10 Pu-239/240

< 1.1 E-10

< 1.4 E-10

< 1.1 E-10

< 1.1 E-10 Am-241

< 4.5 E-10

< 2.6 E-10

< 4.0 E-10

< 3.0 E-10 Cm-242

< 1.1 E-10

< 6.1 E-11

< 1.7 E-10

< 6.6 E-11 Cm-243/244

< 2.0 E-10

< 6.1 E-11

< 1.2 E-10

< 9.4 E-11 I ________

[

1 1

The error given is the probable counting error with a 95% confidence level. Less than (<), value is based on a 4.66 sigma counting error for the background sample.

E-12

Table E-4.5b. Mississippi River surface water and bottom sediment, collected 11119/2009.

Analyses prior to dredging.

Sample Isotope Activity Activity H-3***

(uCi/sample)

(uCi/g)

Activity (pCi/L)

SLUDGE*

PI Marina Be-7 9.04E-4 Cs-137 1.69E-4 4.80E-8 K-40 1.69E-2 H-3 48 Approach Canal #1 K-40 3.22E-2 H-3 91 Approach Canal #2 Be-7 1.23E-3 K-40 2.39E-2 H-3 50 Sturgeon Lake 1 K-40 2.07E-2 H-3 33 Sturgeon Lake 2 Cs-137 1.06E-4 2.52E-8 K-40 2.42E-2 H-3 43 Diamond Bluff Be-7 8.44E-4 K-40 3.59E-2 H-3 22 WATER**

PI Marina H-3 20 Approach Canal H-3 28 Sturgeon Lake H-3 42 Diamond Bluff H-3 27

_I I

1 I_

Sludge samples were counted in a 3 liter marinelli for 2000 seconds for gamma emitters at the Prairie Island Plant.

Water samples were counted in a 1 liter bottle for 2000 seconds for gamma emitters at the Prairie Island Plant.

.*. Tritium analyses were performed by the University of Waterloo Laboratory.

E-13

Su~*y by.Jch~~so..

SC~,fIrIct Noc,,be, ZI. ~mQ, Top of Riser Weo North East Pipe Elev MWV4 592238 2355090 693.02 MW-5 592201 2356566 686.83 MW-G 591642 2357597 882.33 MW-7 593885 2355714 695.54 MW-8 593944 2355654 697.47 P-10 593538 2355497 693.16 P-11 594949 2355297 698.19 P-2 594449 2354002 697.72 P-3 592998 2353997 698.19 P-S 594002 2354501 695.51 P-6 595250 2354802 699.3 P-7 594449 2355235 697.97 PZ-I 596790 2354934 682.91 P -2 596743 2352589 689.05 PZ-4 594262 2352596 696.53 PZ.-

591502 2356299 695.93 PZ-7 594489 2356158 697.85 P2-8 595471 2353662 696.52 4.dY. D--

17 Pi.7p E-14

ML101380302

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