Text

2010 Annual Radiological Environmental Operating Report
	ML11133A363
Person / Time
Site:	Monticello
Issue date:	05/12/2011
From:	O'Connor T J; Northern States Power Co, Xcel Energy
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-MT-11-020
	Download: ML11133A363 (70)
	v • d • e

&XcelEnergy May 12, 2011 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 L-MT-1 1-020 Technical Specification

5.6.1 Monticello

Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 2010 Annual Radiological Environmental Operating Report In accordance with the Monticello Nuclear Generating Plant Technical Specification 5.6.1, the Northern States Power Company, a Minnesota corporation is submitting the Annual Radiological Environmental Operating Report for the year 2010.iew commitments and no revisions to existing commitments.

Timotli//.

O'Connor Site VI President, Monticello Nuclear Generating Plant Northfn States Power Company -Minnesota Enclosure cc: Administrator, Region III, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce ENCLOSURE1 Annual Report to the United States Nuclear Regulatory Commission Radiological Environmental Monitoring Program January 1, 2010 through December 31, 2010 67 pages follow Environmental, Inc.Midwest Laboratory 700 Landwehr Roed -iNorthbrook.

IL 60062-2310 phone (847) 564-0700

fax (847) 564-4517 XCEL ENERGY CORPORATION MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 LICENSE NO. DPR-22 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2010 Prepared under Contract by ENVIRONMENTAL, Inc.Midwest Laboratory Project No. 8010 L orb tory ager Approved:

PREFACE The staff of Environmental, Inc., Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by personnel of the Monticello Nuclear Generating Plant, operated by Northern States Power Co. -Minnesota for XCEL Energy Corporation.

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

ii TABLE OF CONTENTS No. Page P re fa c e ...............................................................................................................................

ii L ist o f T a b le s ......................................................................................................................

iv L ist o f F ig u re s .....................................................................................................................

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 mary of Preoperational Data ....................................................................

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

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

12

6.0 REFERENCES

..................................................................................................................

24 APPENDICES A Interlaboratory Com parison Program Results ...............................................................

A-1 B Data Reporting Conventions

........................................................................................

B-1 C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Area .......................................................

C-1 D Sam pling Location Maps ...............................................................................................

D-1 E Ground W ater Monitoring W ell Sam ples ..........................................................................

E-1 No.5.1 5.2 5.3 5.4 LIST OF TABLES Title PaQe Sample Collection and Analysis Program ...............................................................

13 S a m plin g Lo ca tio ns ........................................................................................................

14 Missed Collections and Analyses ..............................................................................

17 Radiation Environmental Monitoring Program Summary ...........................................

20 The following tables are in the Appendices:

Appendix A A-1 Interlaboratory Comparison Program Results ..........................................................

Al-1 A-2 Thermoluminescent dosimeters (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 Attachment A: Acceptance criteria for spiked samples .............................................

A2 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas ....................................................................

C-2 Appendix E E-1 Sample Collection and Analysis Program, Ground Water ..............................................

E-6 E-2 Sampling Locations for Ground Water Monitoring Wells ...............................................

E-6 E-3 Ground Water Monitoring Program Summary ................................................................

E-7 iv LIST OF FIGURES No. Title Page 5-1 Offsite Ambient Radiation (TLDs), inner versus outer ring locations

.................

18 5-2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location ........................................................................................

19 The following figures are located in the Appendices:

Appendix D D-1 Sample collection and analysis program: TLD locations, In n e r R in g ...............................................................................................................................

D -2 D-2 Sample collection and analysis program: TLD locations, O u te r R in g .............................................................................................................................

D -3 D-3 Sample collection and analysis program: TLD locations, C o n tro ls ...................................................................................................................................

D -4 D-4 Sample collection and analysis program: Radiation Environmental Monitoring Program, M ilk sa m p ling lo catio ns ...........................................................................................................

D -5 D-5 Sample collection and analysis program: Radiation Environmental Monitoring Program, Milk, Sludge, Ground water and Shoreline sampling locations

...............................................

D-6 Appendix E E-1 Sample collection and analysis program: Ground water, On-site monitoring well locations

.....................................................................

E-8 v

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory for the Monticello Nuclear Generating Plant, Monticello, Minnesota, during the period January -December, 2010.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.

Tabulation 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, 2010a)available at the Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.

The Monticello Nuclear Generating Plant is a boiling water reactor with a nominal generating capacity of 600 MWe. It is located on the Mississippi River in Wright County, Minnesota, owned by Xcel Energy Corporation and operated by Northern States Power Co.-Minnesota.

Initial criticality was achieved on December 10, 1970. Full power was achieved March 5, 1971 and commercial operation began on June 30, 1971.1 2.0

SUMMARY

The Radiological Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications and the Offsite Dose Calculation Manual (ODCM) for the Monticello Nuclear Generating Plant is described.

Results for the year 2010 are summarized and discussed.

Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Monticello 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 Monticello 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 (TLD's).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 Monticello 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 environmental samples collected from the Plant site. The Plant's monitoring program includes analyses for tritium and iodine-1 31. Most samples are also 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 4:11:0.03 (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 as 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.

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

3.2 Program

Description The sampling and analysis schedule for the Radiological Environmental Monitoring Program (REMP) at the Monticello Plant 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 plant site. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Monticello Generating Plant REMP Surveillances, Current Revision).

Maps of 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.

Also, airborne iodine is collected by continuous pumping through charcoal filters at all of these locations.

Filters are changed and counted weekly.Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-131.

Quarterly composites of particulate filters from each location are determined by gamma spectroscopy.

One of the five locations is a control (M-1), and four are indicators (M-2, M-3, M-4, M-5). One of the indicators is located in the geographical sector expected to be most susceptible to any atmospheric emissions from the Plant (highest D/Q sector).Ambient gamma radiation is monitored at forty locations, using CaSO 4:Dy dosimeters with four sensitive areas at each location:

fourteen in an inner ring in the general area of the site boundary, sixteen in the outer ring within 4-5 mile radius, six at special interest locations and four control locations, outside a 10 mile radius from the plant. They are replaced and measured quarterly.

Milk sampling from two goat farms (one indicator and one control), was added to the program in the fourth quarter of 2010. Samples are collected monthly from November through April and biweekly during the growing season (May -October), when animals may be on pasture. The samples are analyzed for iodine-1 31 and gamma-emitting isotopes.

In addition, pasture grass and vegetation are collected from locations M-41, M-42 and M-43 (C) and analyzed for iodine-1 31 and other gamma emitting isotopes, as substitute for dairy sampling.Leafy green vegetables (cabbage) are collected annually from the highest D/Q garden and a control location and analyzed for iodine-1 31. Corn and potatoes are collected annually only if the field is irrigated by water in which liquid radioactive effluent has been discharged.

Analysis is for gamma-emitting isotopes.Ground water is monitored by quarterly collections from three off-site locations (one control and two indicators) and one on-site Plant well. To check possible sources of groundwater contamination due to plant operations, samples from sixteen on-site monitoring wells are collected and analyzed for tritium and gamma emitting isotopes.

An additional on-site well was added in September, 2010.Quarterly collections of storm water runoff were added to monitor another possible pathway to the groundwater aquifer. The samples are analyzed for tritium and gamma emitting isotopes.River water is collected weekly at two locations, one upstream of the plant and one downstream.

Monthly composites are analyzed for gamma-emitting isotopes.

Quarterly composites are analyzed for tritium.Drinking water is collected weekly from the City of Minneapolis water supply, which is taken from the Mississippi River downstream of the Plant. Monthly composites are analyzed for gross beta, iodine-1 31, 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, invertebrates, and shoreline sediments.

Shoreline sediment is also collected from one downstream recreational location.

All samples are analyzed for gamma-emitting isotopes.4

3.3 Progqram

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

(1) Air Particulates

/ Air Iodine: No air particulate

/ air iodine sample was available from location M-03 for the week ending February 24, 2010. The particulate filter was not positioned correctly.

No air particulate/air iodine sample was available from location M-04 for the weeks ending July 21, 2010 and August 18, 2010. There was no power, due to an open fuse.No air particulate

/ air iodine sample was available from location M-05 for the week ending October 28, 2010. There was no power to the sampler, due to an open fuse.(2) Thermoluminescent Dosimeters:

The TLD for location M-05B was missing in the field for the second quarter, 2010.TLDs for locations M-07A, M-10A,. M-11A, M-12A and M-01S were missing in the field for the fourth quarter, 2010.(3) Surface Water: Surface water was not collected at location M-08 during the months of January, February and December, 2010, due to unsafe ice conditions.

(4) Well Water: Well water was not collected at location M-10 for the fourth quarter, 2010. The location was discontinued and replaced with a collection at M-43.Well water was collected on October 18, 2010, but the shipment was lost in transit to the laboratory.

Affected locations were MW-1, 4, 5, 8, 13A.(5) Milk Milk was not available from location M-17 for November and December, 2010 and from location M-16 in December, 2010. The dairies stopped milking for the winter.(6) Invertebrates Bottom organisms were not collected in the Spring or Fall of 2010, due to high river levels.Deviations from the program are summarized in Table 5.3.3.4 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.

5

3.4 Laboratory

Procedures (continued)

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, 2011). 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 One additional on-site monitoring well site, #14 (M-52) was added to the REMP in 2010. Samples were collected quarterly and analyzed for tritium and gamma emitting isotopes.Ground water collections were discontinued at M-10 (Campbell) in the fourth quarter of 2010, sampling was replaced with collections from M-43 (Imholte Farm) in October, 2010.Two commercial goat farms were identified during the 2010 land use census and added to the REMP. Milk sampling began in October, 2010 at M-16 (Kitzman Farm) and at the control location M-17 (Greninger Farm).3.6 Land Use Census In accordance with the MNGP Chemistry Manual, Procedure 1.05.41, "Annual Land Use Census and Critical Receptor Identification", a land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft 2 producing fresh leafy vegetables, in each of the 16 meteorological sectors within a distance of 5 miles. The census shall also identify the locations of all milk animals and all 500 ft2 or greater gardens producing broad leaf vegetation in each of the meteorological sectors within a distance of three miles. This census shall be conducted at least once per year between the dates of May 1 and October 31. New locations shall be added to the radiation environmental monitoring program within 30 days and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted.

The 2010 land use census was conducted between September 21 and October 19, 2010. There was one sector (E) in which the highest D/Q value for nearest garden increased by greater than 20%. No changes to the sampling procedures were required.Two commercial goat farms were identified during the 2010 land use census and milk sampling has been added to the REMP. The highest D/Q locations for nearest resident and garden animal did not change from the 2009 census.Details of the land use census are contained in the Land Use Census and Critical Receptor Report, Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.

6

4.0 RESULTS

AND DISCUSSION All of the scheduled collections and analyses were made except those listed in Table 5.3.All 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 accidents at nuclear facilities and no atmospheric nuclear tests conducted in the year 2000. The last reported test was made by the People's Republic of China on October 16, 1980.4.2 Summary of Preoperational Data The following constitutes a summary of preoperational studies conducted at the Monticello Nuclear Generating Plant during the years 1968 to 1970, 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 to make, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere.

Gross 2 2 beta measurements in fallout averaged 20,600 pCi/m in 1969 and 12,000 pCi/m in 1970. These levels are reflected throughout the various media tested.In the air environment, ambient gamma radiation (TLDs) averaged 9.1 mRem/4 weeks during preoperational studies (1970). Gross beta in air particulates in 1969 and 1970 averaged 0.20 3 3 pCi/m .Present day levels have stabilized at around 0.025 pCi/m .Airborne radioiodine remained below detection levels.In the terrestrial environment of 1968 to 1970, milk, agricultural crops, and soil were monitored.

In milk samples, low levels of Cs-1 37 and Sr-90 were detected.

Cs-137 levels averaged 16.7 pCi/L.Soybean crop measurements in 1969 averaged 35.5 pCi/g for gross beta and 0.3 pCilg for Cs-137. Gross beta measured in soil averaged 51.7 pCilg .Present day measurements for cesium-137 are below detection levels in milk and agricultural crops.The aqueous environment was monitored by testing of river water, 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 seven separate locations from 1968 to 1970, averaged 970 pCi/L. Present day environmental samples measure below detection levels. Values for gross beta, measured from 1968 to 1970, averaged 9.8 pCi/L in upstream and downstream Mississippi River water, 4.4 pCi/L for well waters, and 18.6 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In shoreline sediments, gross beta background levels in 1970 averaged 49.8 pCi/g for both upstream and downstream samples. Cs-137 activity averaged 0.10 pCi/g for both upstream and downstream samples. Low levels of Cs-137, occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta levels in fish flesh averaged 5.3 pCi/g in 1968 and 1969. Cs-137, measured in 1969 and 1970, averaged 0.044 pCi/g. Gross beta background levels, in 1970, for aquatic vegetation, algae, and periphyton samples measured 86.7 pCi/g, 76.5 pCi/g, and 28.1 pCi/g respectively.

7

4.3 Program

Findinqs Results obtained show background levels of radioactivity in environmental samples collected outside of the Site Protected Area in 2010. The trace levels of strontium-90 and cesium-137, still measurable in soil and sediment samples, are generally attributed to deposition of fallout from previous decades.Tritium was identified in some groundwater samples collected within the site Protected Area.Ambient Radiation (TLD's)Ambient radiation was measured in the general area of the site boundary, at an outer ring 4 -5 mi.distant from the Plant, at special interest areas and at four control locations.

The means were similar for both inner and outer rings (14.7 and 14.3 mRem/91 days, respectively).

The mean for special interest locations was 14.0 mRem/91 days and the mean for the control locations was 15.2 mRem/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1995 through 2009 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).Year Inner Rina Outer Ring Dose rate (Rem/91 days)1995 14.4 13.6 1996 14.0 13.5 1997 13.3 12.8 1998 15.0 14.4 1999 15.1 14.3 2000 15.1 14.5 2001 14.3 13.7 2002 1.5.9 14.8 2003 15.6 15.0 2004 16.0 15.4 2005 15.6 15.2 2006 16.5 15.6 2007 16.1 15.1 2008 15.2 14.6 2009 14.9 14.4 2010 14.7 14.3 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates, Inner vs. Outer Ring locations 8 Airborne Particulates The average annual gross beta concentrations in airborne particulates were identical at both 3 indicator and control locations ( 0.026 pCi/m ), similar to levels observed from 1995 through 2009. The results are tabulated below.Year Indicators Control 3 ConcentrationA(p~i/m) 1995 0.024 0.025 1996 0.023 0.023 1997 0.023 0.023 1998 0.023 0.023 1999 0.023 0.025 2000 0.027 0.026 2001 0.027 0.026 2002 0.028 0.028 2003 0.027 0.027 2004 0.024 0.024 2005 0.025 0.025 2006 0.024 0.025 2007 0.027 0.028 2008 0.028 0.029 2009 0.029 0.030 2010 0.026 0.026 Average annual gross beta concentrations in airborne particulates.

Typically, the highest average readings occur during the months of January and December, and the first and fourth quarters, as observed in 1995 through 2010.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 3(Arnold and AI-Salih, 1955) was detected in all samples, with an average activity of 0.076 pCirn for all locations.

All other gamma-emitting isotopes were below their respective LLD limits.Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.03 pCi/m 3 in all samples.9 River Water and Drinkina Water Tritium activity measured below the LLD of 500 pCi/L in all samples. Gross beta activity in Minneapolis drinking water averaged 2.9 pCi/L and was similar to average levels observed from 1995 through 2009. Gross beta averages are tabulated below.1 OOIR Gross Beta (pCi/L)Year Gross Beta (pCi/L):)n NA 9 q 11 n 1996 2.1 2004 2.7 1997 2.3 2005 2.8 1998 2.4 2006 2.1 1999 2.2 2007 2.8 2000 2.5 _ 2008 2.1 2001 2.5/ 2009 2.3 2002 2.9 -2010 2.9 Average annual concentrations; Gross beta in drinking water.Comparisons with data reported by the USEPA for Minneapolis drinking water samples collected from 1980 through 2005 indicate that concentrations of these nuclides are remaining fairly constant.

Gamma-emitting isotopes were below detection limits in all surface water samples.There was no indication of a plant effect.Well Water At the four indicator and control locations, tritium measured below the required 500 pCi/L limit in all samples. Gamma isotopic results were below detection limits. The data for 2010 were consistent with previous years results and no plant operational effects were indicated.

Monitoring Wells (on-site)Measurable tritium above 500 pCi/L was detected in 20 of 152 samples collected from fourteen on-site monitoring wells. The activities ranged from 609 to 21,127 pCi/L, almost identical to concentrations seen in 2009. The highest activities were observed at well MW-9A.Gamma isotopic results were below detection limits.Stormwater Run-off (on-site)Six stormwater runoff samples from three on-site locations, were submitted for analysis in 2010.No tritium activity above 500 pCi/L was measured in any of the samples. Gamma isotopic results were below detection limits.10 Goat Milk Milk collections restarted in October, 2010 with the addition of two new dairies to the REMP.Iodine-131 activity measured below the detection limit of 0.5 pCi/L in all samples. No gamma-emitting isotopes, excepting naturally-occurring potassium-40, were detected.In summary, the goat milk data for 2010 show no radiological effects of the plant operation.

Pasture Grass Pasture grass was collected in July, August and September, 2010. 1-131 concentrations measured below 0.051 pCi/g wet weight in all samples; With the exceptions of naturally-occurring beryllium-7 and potassium-40, no other gamma-emitting isotopes were detected. Cabbage was collected in September from two locations and analyzed for iodine-1 31. Levels of 1-131 measured below 0.028 pCi/g wet weight in both samples. With the exceptions of naturally-occurring beryllium-7 and potassium-40, no other gamma-emitting isotopes were detected.No crops within five miles of the plant, were found using irrigation water from the Mississippi River. There was no indication of any plant effect.Fish Fish samples were collected in May and October. Flesh was separated from the bones and analyzed by gamma spectroscopy.

Naturally-occurring potassium-40 was found to be similar in upstream and downstream samples (2.94 and 2.91 pCi/g wet weight, respectively).

All gamma-emitting isotopes were below their respective LLD levels. There was no indication of a plant effect.Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment collections were made in June and November of 2010 and analyzed for gamma-emitting isotopes.

Low levels of cesium-137 were detected in three of four downstream samples, averaging 0.089 pCi/g dry weight. Similar levels of activity and distribution have been observed since 1978, and are indicative of the influence of fallout deposition.

The only other 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 Table 5.1. Sample collection and analysis program, Monticello Nuclear Generating Plant.Collection Analysis Location Type and Type and Medium No. Codes (and Type) a Frequency b Frequency Ambient radiation (TLDs)Airborne Particulates 40 M-01A -M-14A, M-01B -M-16B M-01S -M-06S, M-01C -M-04C 5 M-1(C), M-2, M-3, M-4, M-5 5 M-1(C), M-2, M-3, M-4, M-5 C/Q C/W C/W Ambient gamma GB, GS (QC of each location)Airborne Iodine 1-131 Milk Pasture grass, Vegetation 0 2 3 M-16, M-17 (C)M-41, M-42, M-43(C)G/M 1-131, GS 3x/year GS Surface water Drinking water 2 M-8(C), M-9 G/W GS(MC), H-3(QC)G/W GB(MC), 1-131(MC)GS (MC), H-3 (QC)1 M-14 Well water On-site monitoring wells Edible cultivated crops -Come Leafy Vegetable Potatoes e Fish (one species, edible portion)Pedphyton or invertebrates Shoreline sediment 4 17 M-10(C), M-11, M-12, M-27, M-43(C)M-33 to M-40, M-44 to M-52 G/Q H-3, GS GS 1-131 GS 1 M-19 2 M-27, Available Producer (C)1 M-21 G/A G/A G/A 2 M-8(C), M-9 G/SA GS G/SA GS G/SA GS 2 M-8(C), M-9 3 M-8(C), M-9, M-15 a Location codes are defined in Table 5.2. 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.c Analysis type is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium, 1-131 = iodine-131.

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

d Pasture grass and vegetation collections added to supplement dairy sampling.e Collected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields.13 Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.Distance and Code Type Collection Site Sample Type b Direction from Reactor M-1 M-2 M-3 M-4 M-5 M-8 M-9 M-10 M-11 M-12 M-14 M-15 M-16 M-17 M-19 M-21 M-27 M-33 M-34 M-35 M-36 M-37 M-38 M-39 M-40 M-41 M-42 M-43 M-44 M-45 M-46 M-47 M-48 M-49 M-50 M-51 M-52 C C C C Air Station M-1 Air Station M-2 Air Station M-3 Air Station M-4 Air Station M-5 Upstream of Plant Intake Downstream of Plant Discharge Campbell Farm City of Monticello Plant Well #1 City of Minneapolis Montissippi Park Kitzman Farm Greninger Farm River Irrigated Corn Field River Irrigated Potato Field c Wise residence (Highest D/Q Garden)a. Available Producer Monitoring Well #1 Monitoring Well #2 Monitoring Well #3 Monitoring Well #4 Monitoring Well #5 Monitoring Well #6 Monitoring Well #7 Monitoring Well #8 Training Center Biology Station Road Imholte Farm Monitoring Well #9 Monitoring Well #10 Monitoring Well #11 Monitoring Well #12A Monitoring Well #12B Monitoring Well #13A Monitoring Well #13B Monitoring Well #9B Monitoring Well #14 Storm water Runoff AP, A!AP, Al AP, Al AP, Al AP, Al SW, SS, BO, F SW, SS, BO, F WW WW WW DW SS M M VE, WW VE WW WW WW WW WW WW WW WW VE VE VE, WW WW WW WW WW WW WW WW WW WW 11.0 mi @ 307°/NW 0.8 mi @ 140°/SE 0.6 mi @ 104°/ESE 0.8 mi @ 147°/SSE 2.6 mi @ 134°/SE< 1000' upstream< 1000' downstream 10.6 mi @ 357°/N 3.3 mi @ 127°/SE 0.26 mi @ 252°/WSW 37.0 mi @ 132°/SE 1.27 mi @ 114°/ESE 3.0 mi @ 165*/SSE 7.8 mi @ 250°/WSW 0.64 mi @ 207°/SSW> 10.0 mi.593' @ 299 0/WNW 749' @ 301°/WNW 770' @ 304°/NW 0.1 mi @ 25°/NNE 0.1 mi @ 253°/WSW 229' @ 228°/SW 0.2 mi @ 66°/ENE 0.3 mi @ 150°/SSE 0.8 mi @ 151°/SSE 0.6 mi @ 134 0/SE 12.3 mi @ 313*/NW 0.1 mi @ 310°/NW 0.1 mi @ 292°/WNW 0.1 mi @ 283°/WNW 0.1 mi @ 330°/NW 0.1 mi @ 326°/NW 0.12 mi @ 316°/NW 0.12 mi @ 316°/NW 0.1 mi @ 310°/NW 0.17 mi @ 306°/NW 0.1 mi @ 27°1NE C 14 Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.Distance and Code Typea Collection Site Sample Typeb Direction from Reactor General Area of the Site Boundary M-01A Sherburne Ave. So. TLD 0.75 mi @ 353°/N M-02A Sherburne Ave. So. TLD 0.79 mi @ 23°/NNE M-03A Sherburne Ave. So. TLD 1.29 mi @ 55 0/NE M-04A Biology Station Road TLD 0.5 mi @ 86°/E M-05A Biology Station Road TLD 0.48 mi @ 118°/ESE M-06A Biology Station Road TLD 0.54 mi @ 135°/SE M-07A County Road 75 TLD 0.5 mi @ 155°/SSE M-08A. County Road 75 TLD 0.48 mi @ 1720/S M-09A County Road 75 TLD 0.38 mi @ 209°/SSW M-10A County Road 75 TLD 0.38 mi @ 226°/SW M-11A County Road 75 TLD 0.4 mi @ 239°/WSW M-12A County Road 75 TLD 0.5 mi @ 262'/W M-13A North Boundary Road TLD 0.89 mi @ 324°/NW M-14A North Boundary Road TLD 0.78 mi @ 334°/NNW Approximately 4 to 5 miles Distant from the Plant M-01B Sherco #1 Air Station TLD 4.66 mi @ 02'/N M-02B County Road 11 TLD 4.4 mi @ 18°/NNE M-03B County Road 73 & 81 TLD 4.3 mi @ 51°/NE M-04B County Road 73 (196th St.) TLD 4.2 mi @ 67°/ENE M-05B City of Big Lake TLD 4.3 mi @ 89°/E M-06B County Road 14 and 196th St. TLD 4.3 mi @ 117°/ESE M-07B Monte Industrial Drive TLD 4.3 mi @ 136°/SE M-08B Residence, Hwy 25 & Davidson Ave. TLD 4.6 mi @ 162°/SSE.M-09B Weinand Farm TLD 4.7 mi @ 178°/S M-1OB Reisewitz Farm, Acacia Ave. TLD 4.2 mi @ 204°/SSW M-11B Vanlith Farm, 97th Ave. TLD 4.0 mi @ 228°/SW M-12B Lake Maria State Park TLD 4.2 mi @ 254°/WSW M-13B Bridgewater Station TLD 4.1 mi @ 270°/W M-14B Anderson Residence, Cty Rd. 111 TLD 4.3 mi @ 289°/WNW M-15B Red Oak Wild Bird Farm TLD 4.3 mi @ 309°/NW M-16B Sand Plain Research Farm TLD 4.4 mi @ 341°/NNW 15 Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.Distance and Code Typea Collection Site Sample Typeb Direction from Reactor Special Interest Locations M-01S Osowski Fun Market TLD 0.66 mi @ 242°/WSW M-02S Krone Residence TLD 0.5 mi @ 224 0/SW M-03S Big Oaks Park TLD 1.53 mi @ 102°/ESE M-04S Pinewood School TLD 2.3 mi @ 131°/SE M-05S Rivercrest Christian Academy TLD 3.0 mi @ 118°/ESE M-06S Monte Public Works TLD 2.6 mi @ 134°/SE M-0I C C Kirchenbauer Farm TLD 11.5 mi @ 323°/NW M-02C C County Roads 4 and 15 TLD 11.2 mi @ 47°/NE M-03C C County Rd 19 and Jason Ave. TLD 11.6 mi @ 130°/SE M-04C C Maple Lake Water Tower TLD 10.3 mi @ 2260/ SW Protected Area ISFSI-1 ISFSI-1 (neutron) and 1-01 (gamma) TLD NE corner of ISFSI ISFSI-2 ISFSI-2 (neutron) and 1-02 (gamma) TLD North side of ISFSI, center ISFSI-3 ISFSI-3 (neutron) and 1-03 (gamma) TLD NW corner of ISFSI ISFSI-4 ISFSI-4 (neutron) and 1-04 (gamma) TLD' West side of ISFSI, middle ISFSI-5 ISFSI-5 (neutron) and 1-05 (gamma) TLD West side of ISFSI, at center of array ISFSI-6 ISFSI-6 (neutron) and 1-06 (gamma) TLD SW corner of ISFSI ISFSI-7 ISFSI-7 (neutron) and 1-07 (gamma) TLD South side of ISFSI, center ISFSI-8 ISFSI-8 (neutron) and 1-08 (gamma) TLD SE corner of ISFSI ISFSI-9 ISFSI-9 (neutron) and 1-09 (gamma) TLD East side of ISFSI, at center of array ISFSI-10 ISFSI-10 (neutron) and 1-10 (gamma) TLD East side of ISFSI, middle ISFSI-1 1 ISFSI-1 1 (neutron) and 1-11 (gamma) TLD OCA fence south, on exit road ISFSI-12 ISFSI-12 (neutron) and 1-12 (gamma) TLD OCA fence middle, on exit road ISFSI-13 ISFSI-13 (neutron) and 1-13 (gamma) TLD OCA fence north, on exit road ISFSI-14 ISFSI-14 (neutron)

TLD Posted with TLD M12A ISFSI-15 ISFSI-15 (neutron)

TLD Posted with TLD M10A ISFSI-16 ISFSI-16 (neutron)

TLD Posted with TLD M02S Neutron Control A C TLD Posted with TLD M03C Neutron Control B C TLD Posted with TLD M04C Neutron Control C C TLD Posted with TLD M02C Neutron Control D C TLD Posted with TLD M01C a "C" denotes control location.

All other locations are indicators.

Sample Codes: AP Airborne particulates F Fish Al Airborne Iodine SW River Water BS Bottom (river) sediments SS Shoreline Sediments BO Bottom organisms TLD Thermoluminescent Dosimeter DW Drinking Water VE Vegetation

/ vegetables WW Well Water Collected only if the plant discharges radioactive effluent into the river, then only from river irrigated fields.16 Table 5.3. MISSED COLLECTIONS AND ANALYSES 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 SW Gamma M-08 January Water frozen. None Required WW Gamma M-12 1/27/2010 Well No. 1 inoperable Sampled Well No. 2, repaired Well No. 1.AP/I Beta, 1-131 M-03 02-24-10 Mispositioned particulate filter None Required SW Gamma M-08 February Water frozen. None Required BO Gamma M-08, M-09 Spring, 2010 High water levels in river. None AP/I Beta, 1-131 M-03 06-30-10 Power lost for 21 hrs. Restored power.TLD Gamma M-05B 2nd Quarter Missing in field. Replaced, vandalism AP/I Beta, 1-131 M-04 7/21/2010 Open Fuse. Fuse replaced.AP/I Beta, 1-131 M-04 8/18/2010 Open Fuse. Fuse replaced.BO Gamma M-08, M-09 Fall, 2010 High water levels in river. None WW Gamma, H-3 M-10 10/20/2010 Location discontinued.

Replaced by M-43 WW Gamma, H-3 MW-1, 4, 5, 10/18/2010 Samples lost in transit. Resampled 8,13A AP/I Beta, 1-131 M-05 10/28/2010 Open Fuse. Fuse replaced.MI Gamma, 1-131 M-17 11/24/2010 Milking finished for the year. None Required MI Gamma, 1-131 M-16 12/22/2010 Milking finished for the year. None Required SW Gamma M-008 December Water frozen. None Required TLD Gamma M-7A, 10A, 4th Quarter Missing in field. Knocked over and 11A, 12A, 1S covered by snow plow.17 Figure 5-1. Offsite Ambient Radiation (TLDs); Inner Ring versus Outer Ring locations.

Inner Ring Outer Ring 20 -1 19 I 7 18 17 _ _E 13 12 1 14[E 10 LO (D t- 0 CD CM ) LO (D P- CC) M M IM C C 0 0 C0 0 0 0D 0 0 -S C CD C3 C> CDC0 000 0 0 0 0 0 0 0-N (N i (N i C14 04 (N4 (N NI (4 (\18 Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.w --Indicators (M-2, 3, 4, 5)---a- Control (M-1)0.035 0.033 0.031 --0.029 .1 0.027 0.025 0.023 ----..-- --__-__ __ ____0.21 0.017 0.015 {---t-Un (0 1- 00 M 0 E; CN M~ to to f'- 00 M~0 0) 0) 0) 0 0 0 0 0 0 0 0 0 0 0 S ) 0) 0 4 0 0 0 0 0 0 0 0 0 0 0 19 Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Monticello Nuclear Generating Plant Docket No.Reporting Period Wright, Minnesota 50-263 January-December, 2010 ( 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 Range' Rangec Resultse TLD (Inner Ring, Gamma 52 3.0 14.7 (52/52) M-1 1A, County Rd 75, 15.9(3/3) (See Control 0 General Area at (11.1-17.0) 0.4 mi @ 250°/WSW (14.9-17.0) below.)Site Boundary)mRem/91 days)TLD (Outer Ring, Gamma 63 3.0 14.3 (63163) M-07B 15.6(4/4) (See Control 0 4-5 mi. distant) (11.1-16.5) 4.4 mi @ 135°/SE (14.9-16.2) below.)mRem/91 days)TLD (Special Gamma 23 3.0 14.0 (23/23) M-06S, Mont. Pub. Wks. 16.4(4/4) (See Control 0 Interest Areas) (10.5-16.9) 2.7 mi @ 136°/SE (15.9-16.9) below.)mRern/91 days)TLD (Control)

Gamma 16 3.0 None M-03C, Rte. 19 & Jason, 16.1 (4/4) 15.2 (16/16) 0 mRem/91 days) 11.6 mi @ 130°/SE (14.8-16.9)

(13.3-16.9)

Airborne GB 256 0.002 0.026 (204/204)

M-4, Air Station 0.027 (50 /50) 0.026 (52/52) 0 Particulates (0.005-0.061) 0.8 mi @ 147°/SSE (0.006-0.060)

(0.003-0.062)(pCi/ms)GS 20 Be-7 0.015 0.076 (16/16) M-4, Air Station 0.084 (4/4) 0.077 (4/4) 0 (0.059-0.097) 0.8 mi @ 147°/SSE (0.067-0.096)

(0.071-0.087)

Mn-54 0.0006 < LLD < LLD 0 Co-58 0.0008 < LLD < LLD 0 Co-60 0.0009 < LLD < LLD 0 Zn-65 0.0011 < LLD < LLD 0 Zr-Nb-95 0.0012 < LLD < LLD 0 Ru-103 0.0014 < LLD < LLD 0 Ru-106 0.0072 < LLD < LLD 0 Cs-134 0.0008 < LLD < LLD 0 Cs-137 0.0010 < LLD < LLD 0 Ba-La-1 40 0.0025 < LLD < LLD 0 Ce-141 0.0020 < LLD < LLD 0 Ce-144 0.0056 < LLD < LLD 0 Airborne Iodine 1-131 256 0.03 < LLD < LLD 0 (pCi/un)20 Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Monticello Nuclear Generating Plant Docket No.Reporting Period Wright, Minnesota ( County, State)50-263 January-December, 2010 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD' Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse Milk (pCi/L) 1-131 3 0.5 < LLD < LLD 0 GS 3 K-40 200 1788(1/1)

M-16, Kitzman 1788(1 /1) 1762 (2/2) a 3.0 mi. SSE (1644-1879)

Cs-134 5 < LLD c< LLD 0 Cs-137 5 < LLD < LLD 0 Ba-La-140 5 < LLD < LLD 0 River Water (pCi/L) H-3 8 500 < LLD < LLD 0 GS 21 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 40 < LLD < LLD 0 Drinking Water GB 12 1.0 2.9 (9/12) M-14, Minneapolis 2.9 (9/12) None 0 (pCi/L) (1.8-3.5) 37.0 mi. @ 1320/SE (1.8-3.5)1-131 12 1.0 < LLD None 0 H-3 4 500 < LLD None 0 GS 12 Mn-54 10 < LLD None 0 Fe-59 30 < LLD None 0 Co-58 10 < LLD None 0 Co-60 10 < LLD None 0 Zn-65 30 < LLD None 0 Zr-Nb-95 15 < LLD None 0 Cs-134 10 < LLD None 0 Cs-137 10 < LLD None 0 Ba-La-140 15 < LLD None 0 Ce-144 38 < LLD None 0 21 Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Location of Facility Monticello Nuclear Generating Plant Wright, Minnesota ( County, State)Docket No.Reporting Period 50-263 January-December, 2010 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)' Mean (F)c Mean (F)' Routine (Units) Analysesa Rangec Location" Range' Rangec Resultse Well Water H-3 16 500 < LLD < LLD 0 (pCi/L) GS 16 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 GS 2 (pCi/gwet)

Mn-54 0.006 < LLD < LLD 0 Fe-59 0.020 < LLD < LLD 0 Co-58 0.009 < LLD. < LLD 0 Co-60 0.008 < LLD < LLD 0 Zn-65 0.017 < LLD < LLD 0 Nb-95 0.007 < LLD < LLD 0 1-131 0.028 < LLD < LLD 0 Cs-134 0.010 < LLD < LLD 0 Cs-137 0.011 < LLD < LLD 0 Vegetation GS 9 (Pasture Grass, Weeds, Leaves) Mn-54 0.021 < LLD < LLD 0 Fe-59 0.039 < LLD < LLD 0 Co-58 0.025 < LLD < LLD 0 (pCi/gwet)

Co-60 0.021 < LLD < LLD 0 Zn-65 0.043 < LLD < LLD 0 Nb-95 0.028 < LLD < LLD 0 1-131 0.051 < LLD < LLD 0 Cs-134 0.020 < LLD < LLD 0 Cs-137 0.027 < LLD < LLD 0 22 Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Generating Plant Location of Facility Wright, Minnesota Docket No. 50-263 Reporting Period January-December, 2010 ( 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)' Routine (Units) Analyses' RangeC Locationd Rangec Rangec Resultse Fish GS 6 (pCi/g wet) K-40 0.10 2.91 (3/3) M-08, Upstream 2.94 (3/3) 2.94 (3/3) 0 (2.67-3.15)

< 1000' of discharge (2.69-3.09)

(2.69-3.09)

Mn-54 0.021 < LLD < LLD 0 Fe-59 0.072 < LLD < LLD 0 Co-58 0.023 < LLD < LLD 0 Co-60 0.017 < LLD < LLD 0 Zn-65 0.043 < LLD < LLD 0 Zr-Nb-95 0.029 < LLD < LLD 0 Cs-134 0.022 < LLD < LLD 0 Cs-137 0.024 < LLD < LLD 0 Ba-La-140 0.101 < LLD < LLD 0 Ce-144 0.13 < LLD < LLD 0 Shoreline GS 6 Sediments Be-7 0.25 0.48 (1/4) M-09, downstream 0.48 (1/2) 0.43 (1/2) 0 (pCi/g dry) of discharge, < 1000'K-40 0.10 10.79 (4/4) M-15, Montissippi Park 11.04 (2/2) 10.03 (2/2) 0 (9.87-11.83) 1.27 mi @ 114°/ESE (10.24-11.83)

(9.67-10.38)

Mn-54 0.026 < LLD < LLD 0 Fe-59 0.053 < LLD < LLD 0 Co-58 0.029 < LLD < LLD 0 Co-60 0.024 < LLD < LLD 0 Zn-65 0.073 < LLD < LLD 0 Nb-95 0.037 < LLD < LLD 0 Zr-95 0.049 < LLD < LLD 0 Ru-103 0.027 < LLD < LLD 0 Ru-106 0.17 < LLD < LLD 0 Cs-134 0.023 < LLD < LLD 0 Cs-137 0.031 0.089 (3/4) M-15, Montissippi Park 0.096 (1/2) < LLD 0 (0.038-0.126) 1.27 mi @ 114°/ESE Ba-La-140 0.025 < LLD < LLD 0 Ce-144 0.14 < LLD < LLD 0 8 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.23

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, 276.Environmental, Inc., Midwest Laboratory.

_ 2001a through 2011a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2010._____ 2001b through 2011 b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -December, 2000 through 2010._ _ 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, Illinois, 369-382.National Center for Radiological Health, 1968. Radiological Health and Data Reports, Vol. 9, Number 12, 730-746.Northern States Power Company._ 1969 through 1971. Monticello Nuclear Generating Plant, Environmental Radiation Monitoring Program, Annual Report, June 18, 1968 to December 31, 1968, 1969, 1970. Minneapolis, Minnesota.

_ 1978 through 2008. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1, to December 31, 1977 through 2007.24

6.0 REFERENCES

CITED (continued)

U.S. Dep't of Energy 1997 HASL-300, Edition 28, Procedures Manual, Environmental Measurements Laboratory, New York, NY.U.S. Environmental Protection Agency.___ 1980. Prescribed Procedures 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-52015-84-006).

__ 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 2011. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2010. Minneapolis, Minnesota.

___ 2009 to 2011. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2010.Minneapolis, Minnesota.

25 Environmental, Inc.Midwest Laboratory 700 Landwehr Road -Northbrook, IL 60062-2310 phone (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, 2010 through December, 2010 Appendix A Interlaboratory Comparison Proqram 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 testing.Table A-3 lists results of the analyses on in-house "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.Table A-4 lists results of the analyses on in-house "blank" samples for the past twelve months. Data for previous years available upon request.Table A-5 lists REMP specific analytical results from the in-house "duplicate" program for the past twelve 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 pCi/liter or kg 5.0 pCi/liter> 100 pCi/liter or kg 5% of known value Strontium-89b 5 to 50 pCi/liter or kg 5.0 pCi/liter> 50 pCi/liter or kg 10% of known value Strontium-90b 2 to 30 pCi/liter or kg 5.0 pCi/liter> 30 pCi/liter or kg 10% of known value Potassium-40

_> 0.1 g/liter or kg 5% of known value Gross alpha !< 20 pCi/liter 5.0 pCi/liter> 20 pCi/liter 25% of known value Gross beta 5 100 pCi/liter 5.0 pCi/liter> 100 pCi/liter 5% of known value Tritium < 4,000 pCi/liter

+ lU =169.85 x (known)0 0 9 3 3> 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 8 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)'.Concentration (pCi/L)Lab Code Date Analysis Laboratory ERA Control Resultb Result' Limits Acceptance STW-1205 STW-1205 STW-1206 STW-1206 STW-1206 04/05/10 04/05/10 04/05/10 04/05/10 04/05/10 Sr-89 Sr-90 Ba-133 Co-60 Cs-134 63.0 +/- 5.7 37.4 +/- 2.4 63.6 + 3.3 83.3 +/- 2.9 71.0 +/- 3.4 145.5 +/- 5.1 194.9 +/- 7.8 60.4 41.3 65.9 84.5 71.6 48.6 -68.2 30.4 -47.4 54.9 -72.5 76.0 -95.3 58.4 -78.8 STW-1206 04/05/10 Cs-137 STW-1206 04/05/10 Zn-65 146.0 131.0 -163.0 186.0 167.0 -219.0 STW-1207 04/05/10 Gr. Alpha 26.5 +/- 1.7 STW-1207 04/05/10 Gr. Beta 34.5 +/- 1.6 STW-1208 04/05/10 1-131 STW-1209 STW-1209 STW-1209 STW-1210 04/05/10 04/05/10 04/05/10 04/05/10 Ra-226 Ra-228 Uranium H-3 STW-1224 10/04/10 Sr-89 STW-1224 10/04/10 Sr-90 22.7 +/- 0.8 15.2 +/- 0.7 15.6 +/- 1.8 59.5 +/- 0.7 12955 +/- 332 65.3 +/- 5.7 39.9 +/- 2.3 67.2 +/- 4.3 53.2 +/- 3.3 47.3 +/- 5.1 118.0 +/-5.9 107.0 +/- 8.7 32.9 37.5 26.4 14.6 15.1 62.3 12400.0 STW-1225 STW-1225 STW-1225 STW-1225 STW-1225 10/04/10 10/04/10.10/04/10 10/04/10 10/04/10 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 68.5 43.0 68.9 53.4 43.2 123.0 102.0 42.3 36.6 16.9 -42.6 24.7 -45.0 21.9 -31.1.10.9 -16.8 10.1 -18.3 50.7 -69.1 10800 -13600 55.8 -76.7 31.7 -49.3 57.5 -75.8 48.1 -61.3 34.5 -47.5 111.0 -138.0 91.8 -122.0 21.9 -53.7 24.0 -44.2 22.9 -32.3 8.5 -13.2 6.4 -12.3 29.8 -41.0 11200 -14200 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 STW-1226 10/04/10 Gr. Alpha 30.7 +/- 2.9 STW-1226 10/04/10 Gr. Beta 32.7 +/- 0.8 STW-1227 10/04/10 1-131 STW-1228 STW-1228 STW-1228 STW-1229 10/04/10 10/04/10 10/04/10 10/04/10 Ra-226 Ra-228 Uranium H-3 28.6 +/- 1.1 11.8 +/-0.6 12.0 +/- 1.8 34.8 +/-0.4 13682 +/-352 27.5 11.4 9.9 36.8 12900.0 Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.

Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA.Al-1 TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLD, CaSO 4: Dy Cards).mR Lab Code Date Known Lab Result Control Description Value +/- 2 sigma Limits Acceptance Environmental, Inc.2010-1 61812010 30 cm. 75.07 90.78 +/- 3.60 52.55 -97.59 Pass 2010-1 6/8/2010 40 cm. 42.23 50.88 +/- 3.59 29.56 -54.90 Pass 2010-1 6/8/2010 50 cm. 27.03 32.12 +/- 1.90 18.92 -35.14 Pass 2010-1 6/812010 60 cm. 18.77 21.80 +/- 0.90 13.14 -24.40 Pass 2010-1 6/8/2010 70 cm. 13.79 15.38 +/- 1.39 9.65 -17.93 Pass 2010-1 6/8/2010 75 cm. 12.01 11.30 +/- 1.07 8.41 -15.61 Pass 2010-1 6/8/2010 80 cm. 10.56 10.90 +/- 0.61 7.39 -13.73 Pass 2010-1 6/8/2010 90 cm. 8.34 7.84 +/- 0.83 5.84 -10.84 Pass 2010-1 6/8/2010 100 cm. 6.76 6.61 +/- 0.52 4.73 -8.79 Pass 2010-1 6/8/2010 110 cm. 5.58 4.29 +/- 0.55 3.91 -7.25 Pass 2010-1 618/2010 120 cm. 4.69 3.64 +/- 0.33 3.28 -6.10 Pass 2010-1 6/8/2010 150 cm. 3.00 2.82 +/- 0.84 2.10 -3.90 Pass 2010-1 6/8/2010 180 cm. 2.09 1.55 +/- 0.23 1.46 -2.72 Pass Environmental, Inc.2010-2 12/13/2010 100 cm. 4.94 4.65 +/- 0.57 3.46 -6.42 Pass 2010-2 12/13/2010 110 cm. 4.09 3.50 +/- 0.74 2.86 -5.32 Pass 2010-2 12/13/2010 120 cm. 3.43 2.68 +/- 0.36 2.40 -4.46 Pass 2010-2 12/13/2010 150 cm. 2.2 1.75 +/- 0.42 1.54 -2.86 Pass 2010-2 12/13/2010 180 cm. 1.53 1.32 +/- 0.52 1.07 -1.99 Pass 2010-2 12/13/2010 40 cm. 30.89 38.56 +/- 2.11 21.62 -40.16 Pass 2010-2 12/13/2010 50 cm. 19.77 23.35 +/- 1.82 13.84 -25.70 Pass 2010-2 12/13/2010 60 cm. 13.73 14.53 +/- 1.24 9.61 -17.85 Pass 2010-2 12/13/2010 60 cm. 13.73 15.84 +/- 1.53 9.61 -17.85 Pass 2010-2 12/13/2010 80 cm. 7.72. 8.33 +/- 0.74 5.40-10.04 Pass 2010-2 12/13/2010 90 cm. 6.1 5.93 +/- 0.73 4.27 -7.93 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=1 C Activity Limits d Acceptance SPW-12648 SPW-279 SPW-391 W-21210 W-21710 W-21710 SPAP-669 SPAP-671 SPAP-671 SPMI-674 SPMI-674 SPMI-674 SPW-676 SPW-676 SPW-676 SPW-678 SPF-680 SPF-680 SPW-682 SPW-2871 W-40510 W-4051 0 SPW-2083 W-51310 SPW-3181 SPW-3272 SPW-3278 SPW-3280 SPAP-3270 SPAP-3270 SPW-3274 SPW-3274 SPW-3274 SPW-3274 SPMI-3276 SPMI-3276 SPMI-3276 SPMI-3276 1/20/2010 1/27/2010 2/4/2010 2/12/2010 2/17/2010 2/17/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 2/25/2010 4/5/2010 4/5/2010 4/5/2010 4/28/2010 5/13/2010 6/17/2010 6/25/2010 6/25/2010 6/25/2010 6/28/2010 6/28/2010 6/28/2010 6/28/2010 6/28/2010 6/28/2010 6/28/2010 6/28/2010 6/28/2010 6/28/2010 Ra-228 U-238 Ni-63 Ra-226 Gr. Alpha Gr. Beta Gr. Beta Cs-134 Cs-137 Co-60 Cs-134 Cs-1 37 Co-60 Cs-134 Cs-137 H-3 Cs-134 Cs-137 Tc-99 Ra-228 Gr. Alpha Gr. Beta U-238 Ra-226 Tc-99 H-3 Fe-55 C-14 Cs-134 Cs-137 Co-60 Cs-1 34 Cs-137 Sr-90 Co-60 Cs-134 Cs-1 37 Sr-90 40.04 +/- 2.99 4.52 +/- 0.22 179.70 +/- 2.96 16.05 +/- 0.39 17.54 +/- 0.37 42.47 +/- 0.39 45.78 +/- 0.11 10.56 +/- 3.15 105.36 +/- 3.15 67.38 +/- 5.65 60.61 +/- 6.28 173.80 +/- 10.30 66.13 +/- 5.22 51.54 +/- 5.97 179.30 +/- 9.95 59213.70 +/- 709.90 402.56 +/- 22.40 2267.90 +/- 75.60 29.70 +/- 1.51 33.91 +/- 2.85 20.65 +/- 0.42 44.72 +/- 0.40 4.20 +/- 0.32 17.04 +/- 0.50 29.87 +/- 1.09 5489.00 +/- 224.00 17054.00 +/- 348.00 3410.60 +/- 9.75 12.24 +/- 3.13 103.92 +/- 7.14 67.48 +/- 5.53 49.55 +/- 6.11 58.85 +/- 6.54 41.59 +/- 1.83 66.80 +/- 5.25 48.20 +/- 3.88 62.46 +/- 6.33 43.32 +/- 1.63 40.54 4.17 209.62 16.77 20.00 45.20 49.24 10.38 109.20 68.79 51.91 163.80 68.79 51.91 163.80 60407.70 415.00 2180.00 32.34 36.80 20.00 45.20 4.17 16.77 32.34 5928.00 19614.00 4738.00 10.38 109.20 65.84 46.38 54.17 42.72 65.84 46.38 54.17 42.72 28.38 -52.70 0.00 -16.17 146.73 -272.51 11.74 -21.80 10,00 -30.00 35.20 -55.20 29.54 -68.94 0.38 -20.38 98.28 -120.12 58.79 -78.79 41.91 -61.91 147.42 -180.18 58.79 -78.79 41.91 -61.91 147.42 -180.18 48326.16 -72489.24 373.50 -456.50 1962.00 -2398.00 20.34 -44.34 25.76 -47.84 10.00 -30.00 35.20 -55.20 0.00 -16.17 11.74 -21.80 20.34 -44.34 4742.40 -7113.60 15691.20 -23536.80 2842.80 -6633.20 0.38 -20.38 98.28 -120.12 55.84 -75.84 36.38 -56.38 44.17 -64.17 34.18 -51.26 55.84 -75.84 36.38 -56.38 44.17 -64.17 34.18 -51.26 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 SPW-5081 W-90910 W -90910 W-91010 SPW-2874 XWW-5302 XWW-5302 XWW-5302 XWW-5302 SPW-6035 W-120110 W-120110 W-121610 9/9/2010 9/9/2010 9/9/2010 9/10/2010 9/23/2010 10/6/2010 10/6/2010 10/6/2010 10/6/2010 10/21/2010 12/1/2010 12/1/2010 12/16/2010 Tc-99 Gr. Alpha Gr. Beta Ra-226 Ra-228 Ba-133 Co-60 Cs-134 Cs-137 U-238 Gr. Alpha Gr. Beta Ra-226 30.22 +/- 1.06 20.95 +/- 0.43 45.20 +/- 0.41 17.48 +/- 0.50 34.60 +/- 2.68 154.13 +/- 8.90 24.65 +/- 4.11 14.03 +/- 3.87 61.16 +/- 6.08 4.52 +/- 0.20 20.27 +/- 0.41 46.75 +/- 0.41 17.99 +/- 0.43 32.34 20.00 45.20 16.77 36.80 155.21 23.28 13.95 59.22 4.17 20.00 45.20 16.77 20.34 -44.34 10.00 -30.00 35.20 -55.20 11.74 -21.80 25.76 -47.84 139.69 -170.73 13.28 -33.28 3.95 -23.95 49.22 -69.22 0.00 -16.17 10.00 -30.00 35.20 -55.20 11.74 -21.80 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/M3 ), and solid samples (pCi/g).Laboratory codes as follows: W (water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish).Results are based on single determinations.

Control limits are established from the precision values listed in Attachment A of this report, adjusted to +/- 2o.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)SPW-12658-Water 1/20/2010 Ra-228 0.79 0.61 +/- 0.44 2 SPW-280 Water 1/27/2010 U-238 0.18 0.07 +/- 0.13 1 SPW-392 Water 2/412010 Ni-63 15.90 -11.80 +/- 9.40 20 W-21210 Water 2/12/2010 Ra-226 0.03 0.06 +/- 0.02 1 W-21710 Water 2/17/2010 Gr. Alpha 0.41 0.09 +/- 0.30 1 W-21710 Water 2/17/2010 Gr. Beta 0.73 0.23 +/- 0.52 3.2 SPAP-668 Air Filter 2/25/2010 Gr. Beta 0.11 0.008 +/- 0.002 3.2 SPAP-670 Air Filter 2/25/2010 Cs-134 1.87 100 SPAP-670 Air Filter 2/25/2010 Cs-137 2.31 -100 SPMI-672 Milk 2/25/2010 Cs-137 3.52 -10 SPMI-672 Milk 2/25/2010 1-131(G) 6.09 -20 SPW-675 Water 2/25/2010 Co-60 1.55 -10 SPW-675 Water 2/25/2010 Cs-137 2.69 -10 SPW-675 Water 2/25/2010 1-131(G) 5.68 -20 SPF-679 Fish 2/25/2010 Cs-134 10.94 -100 SPF-679 Fish 2/25/2010 Cs-137 18.37 -100 SPW-681 Water 2/25/2010 Tc-99 16.11 -10.75 +/- 9.53 10 SPW-2881 Water 4/5/2010 Ra-228 0.89 0.22 +/- 0.44 2 W-40510 Water 4/5/2010 Gr. Alpha 0.40 -0.20 t 0.26 1 W-40510 Water 4/5/2010 Gr. Beta 0.75 -0.09 +/- 0.52 3.2 SPW-2084 Water 4/28/2010 U-238 0.14 0.03 +/- 0.10 1 W-51310 Water 5/13/2010 Ra-226 0.03 0.06 +/- 0.02 1 SPW-3271 Water 6/25/2010 H-3 151.60 -58.10 +/- 71.90 200 SPW-3278 Water 6/25/2010 Fe-55 634.50 256.80 +/- 396.40 1000 SPW-3279 water 6/25/2010 C-14 8.57 -1.84 +/- 5.18 200 SPAP-3269 Air Filter 6/28/2010 Cs-1 34 1.71 100 SPAP-3269 Air Filter 6/28/2010 Cs-137 2.42 -100 SPW-3273 Water 6/28/2010 Co-60 1.64 -10 SPW-3273 Water 6/28/2010 Cs-134 3.89 -10 SPW-3273 Water 6/28/2010" Cs-137 4.29 -10 SPW-3273 water 6/25/2010 Sr-90 0.50 -0.04 +/- 0.22 1 SPMI-3275 Milk 6/28/2010 Cs-134 3.33 -10 SPMI-3275 Milk 6/28/2010 Csm137 3.82 -10 SPMI-3275 Milk 6/28/2010 1-131(G) 3.71 -20 SPMI-3275 Milk 6/28/2010 Sr-90 0.58 0.81 +/- 0.36 1 A4-1 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 o)SPW-5080 W-9091 0 W-9091 0 W-91010 SPW-2884 SPW-6036 W-120110 W-120110 W-121610 BKW-120610 BKW-120610 BKW-120610 BKW-120610 W-121610 Water Water Water Water Water Water Water Water Water water water water water Water 9/9/2010 9/9/2010 9/9/2010 9/10/2010 9/23/2010 10/21/2010 12/1/2010 12/1/2010 12/16/2010 12/6/2010 12/6/2010 12/6/2010 12/6/2010 12/16/2010 Tc-99 Gr. Alpha Gr. Beta Ra-226 Ra-228 U-238 Gr. Alpha Gr. Beta Ra-226 Ba-133 Co-60 Cs-134 Cs-137 Ra-226 2.15 0.39 0.78 0.04 0.71 0.11 0.43 0.75 0.03 5.66 4.49 4.41 5.33 0.03-0.71 +/- 1.29 0.10 +/- 0.28-0.09 +/- 0.55 0.07 +/- 0.03 1.14 +/- 0.46 0.07 +/- 0.10-0.05 +/- 0.29-0.08 +/- 0.53 0.04 +/- 0.02 0.04 + 0.02 10 1 3.2 1 2 1 1 3.2 1 10 10 10 10 1 8 Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).b 1-131(G);

iodine-131 as analyzed by gamma spectroscopy.

c Activity reported is a net activity result. For gamma spectroscopic analysis, activity detected below the LLD value is not reported.A4-2 TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-20, 21 CF-20, 21 CF-20, 21 CF-41, 42 CF-41, 42 CF-41, 42 MI-111, 112 DW-10010, 10011 DW-10010, 10011 WW-215, 216 DW-10022, 10023 DW-10022, 10023 WW-424,425 DW-10034, 10035 DW-10034,10035 SW-382, 383 DW-10046, 10047 DW-10046,10047 WW-693, 694 SW-782, 783 SW-782, 783 MI-946,947 W-1035,1036 W-1035,1036 SW-1285,1286 W-1103,1104 WW-1193, 1194 LW-1909,1910 LW-1909,1910 DW-10068, 10069 DW-10070, 10071 DW-10070,10071 AP-1729,1730 AP-1782, 1783 E-1392, 1393 E-1392, 1393 WW-1422,1423 SW-1464,1465 XW-1666,1667 SG-1532,1533 SG-1532,1533 1/4/2010 1/4/2010 1/4/2010 1/4/2010 1/4/2010 1/4/2010 1/12/2010 1/13/2010 1/13/2010 1/18/2010 1/21/2010 1/21/2010 1/28/2010 1/28/2010 1/28/2010 2/1/2010 2/2/2010 2/2/2010 2/23/2010 3/1/2010 3/1/2010 3/9/2010 3/17/2010 3/17/2010 3/17/2010 3/18/2010 3/18/2010 3/24/2010 3/25/2010 3/25/2010 3/29/2010 3/29/2010 3/30/2010 3/30/2010 4/1/2010 4/1/2010 4/1/2010 4/1/2010 4/1/2010 4/6/2010 4/6/2010 Gr. Beta K-40 Sr-90 Be-7 Gr. Beta K-40 K-40 Ra-226 Ra-226 H-3 Ra-226 Ra-228 H-3 Ra-226 Ra-228 Gr. Beta Ra-226 Ra-228 H-3 Gr. Beta K-40 K-40 Ra-226 Ra-228 H-3 H-3 H-3 H-3 H-3 Gr. Alpha Ra-226 Ra-228 Be-7 Be-7 Gr. Beta K-40 Gr. Beta H-3 Fe-55 Ac-228 Pb-214 10.96 +/- 0.27 8.88 +/- 0.48 0.02 +/- 0.01 0.45 +/- 0.11 3.26 +/- 0.10 2.85 +/- 0.36 1276.00 +/- 98.96 0.48 +/- 0.10 1.59 +/- 0.61 211.16 +/- 87.57 8.57 +/- 0.91 5.68 +/- 1.36 422.30 +/- 95.90 0.93 +/- 0.13 1.16 +/- 0.62 2.22 +/- 0.68 6.11 +/- 0.91 5.84 +/- 1.11 1458.00 +/- 131.00 1.05 +/- 0.42 1.50 +/- 0.15 1485.00 +/- 109.30 11.78 +/- 1.51 5.31 +/- 2.42 377.60 +/- 104.50 12690 +/-333 227.38 +/- 95.19 1529.40 +/- 144.60 2.40 +/- 0.97 1.08 +/- 1.02 1.58 +/- 0.17 1.16 +/- 0.47 0.08 +/- 0.01 0.08 +/- 0.01 1.59 +/- 0.07 902.30 +/- 179.00 22.23 +/- 1.58 262.06 +/- 98.96 7.05 +/- 0.71 19.45 +/- 1.14 12.66 +/- 0.52 11.30 +/- 0.28 8.27 +/- 0.78 0.02 +/- 0.01 0.41 +/- 0.14 3.33 +/- 0.11 3.04 +/- 0.22 1334.80 +/- 105.00 0.43 +/- 0.10 1.13 +/- 0.47 291.90 +/- 91.31 10.20 +/- 1.08 3.59 +/- 1.17 484.20 +/- 98.50 0.90 +/- 0.11 1.29 +/- 0.62 1.18 +/- 0.71 7.88 +/- 1.17 6.13 +/- 1.14 1531.00 +/- 133.00 1.60 +/- 0.43 1.52 +/- 0.15 1347.40 +/- 108.30 9.76 +/- 1.26 8.45 +/- 2.78 282.70 +/- 100.70 12679 +/-333 251.81 +/- 96.15 1404.40 +/- 140.80 1.99 +/- 1.03 1.35 +/- 1.05 1.69 +/- 0.16 1.34 +/- 0.49 0.08 +/- 0.01 0.09 +/- 0.01 1.66 +/- 0.08 1076.70 +/- 202.90 19.42 +/- 1.40 233.18 +/- 97.75 7.25 +/- 0.74 20.07 +/- 1.19 13.32 +/- 0.54 11.13 +/-0.19 8.58 +/- 0.46 0.02 +/- 0.00 0.43 +/- 0.09 3.30 +/- 0.07 2.95 +/- 0.21 1305.40 +/- 72.14 0.46 +/- 0.07 1.36 +/- 0.39 251.53 +/- 63.26 9.39 +/- 0.71 4.64 +/- 0.90 453.25 +/- 68.74 0.92 +/- 0.09 1.23 +/- 0.44 1.70 +/- 0.49 7.00 +/- 0.74 5.99 +/- 0.80 1494.50 +/- 93.34 1.33 +/- 0.30 1.51 +/- 0.11 1416.20 +/- 76.93 10.77 +/- 0.98 6.88 +/- 1.84 330.15 +/- 72.56 12685 +/- 235 239.60 +/- 67.65 1466.90 +/- 100.91 2.20 +/- 0.71 1.22 +/- 0.73 1.64 +/- 0.12 1.25 +/- 0.34 0.08 +/- 0.01 0.09 +/- 0.01 1.63 +/- 0.05 989.50 +/- 135.29 20.83 +/- 1.06 247.62 +/- 69.55 7.15 +/- 0.51 19.76 +/- 0.82 12.99 +/- 0.38 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-1 TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SG-1506,1507 SG-1506, 1507 SW-1645,1646 DW-10095,10096 DW-10095,10096 W-2013,2014 W-2013,2014 WW-2431,2432 SO-2037, 2038 W-2325,2326 AP-2149, 2150 LW-2191, 2192 G-2170,2171 G-2170,2171 G-2170,2171 SWT-2282, 2283 WW-2233,2234 WW-2233,2234 TD-2410, 2411 SG-2347, 2348 F-2463, 2464 XW-2834, 2835 WW-2597,2598 MI-2639, 2640 SL-2771, 2772 SL-2771, 2772 SW-2879, 2880 SG-2904, 2905 SO-3039, 3040 SO-3039, 3040 SO-3039, 3040 SO-3039, 3040 SO-3039, 3040 SO-3039, 3040 WW-3060, 3061 VE-3351, 3352 VE-3351, 3352 W-3469, 3470 SG-3539, 3540 SG-3539, 3540 AP-3743,3744 4/7/2010 4/7/2010 4/14/2010 4/14/2010 4/14/2010 4/16/2010 4/16/2010 4/19/2010 4/22/2010 4/26/2010 4/29/2010 4/29/2010 5/3/2010 5/3/2010 5/3/2010 5/4/2010 5/5/2010 5/5/2010 5/10/2010 5/13/2010 5/17/2010 5/20/2010 5/25/2010 5/25/2010 6/1/2010 6/1/2010 6/1/2010 6/7/2010 6/8/2010 618/2010 6/8/2010 6/8/2010 6/8/2010 6/8/2010 6/14/2010 6/21/2010 6/21/2010 6/25/2010 6/29/2010 6/29/2010 6/30/2010 Ac-228 Pb-214 H-3 Ra-226 Ra-228 Gr. Alpha Gr. Beta H-3 K-40 H-3 Be-7 Gr. Beta Be-7 Gr. Beta K-40 Gr. Beta Gr. Alpha Gr. Beta H-3 Ra-226 K-40 H-3 H-3 K-40 Gr. Beta K-40 H-3 Gamma Be-7 Cs-137 Gr. Beta K-40 U-233/4 U-238 H-3 Be-7 K-40 H-3 Ac-228 Pb-214 Be-7 1.28 +/- 0.15 1.24 +/- 0.10 312.00 +/- 100.00 4.87 +/- 0.53 2.49 +/- 0.56 33.45 +/- 3.98 14.83 +/- 0.96 400.40 +/- 98.10 2.89 +/- 0.40 399.00 +/- 92.00 0.14 + 0.08 1.16 +/- 0.56 0.91 +/- 0.32 8.73 +/- 0.22 7.24 +/- 0.44 0.73 +/- 0.52 1.56 + 1.47 2.33 +/- 1.14 431.92 _ 96.50 37.34 + 0.42 2.69 + 0.56 209.53 +/- 83.34 288.10 +/- 98.20 1428.80 +/- 110.60 5.33 +/- 0.18 4.67 +/- 0.46 335.60 +/- 92.60 5.20 +/- 0.20 0.12 +/- 0.03 0.01 +/- 0.00 22.80 +/- 2.05 11.30 +/- 1.20 0.12 +/- 0.02 0.12 +/- 0.01 199.16 +/- 95.13 1.86 +/- 0.25 6.10 +/- 0.52 573.00 +/- 110.00 14.55 +/- 0.51 15.50 +/- 1.56 0.07 +/- 0.01 1.15 +/- 0.14 1.22 +/- 0.09 352.00 +/- 102.00 5.57 +/- 0.61 2.76 +/- 0.60 39.11 +/- 4.54 16.07 +/- 0.96 377.70 +/- 97.10 2.89 +/- 0.51 429.00 +/- 94.00 0.26 +/- 0.12 0.79 +/- 0.52 0.86 +/- 0.26 9.01 +/- 0.23 7.48 +/- 0.78 1.58 +/- 0.57 2.27 +/- 1.65 4.08 +/- 1.24 403.05 +/- 95.26 37.91 +/- 0.36 2.65 +/- 0.38 263.11 +/- 85.95 155.80 +/- 93.40 1408.60 +/- 107.40 5.30 +/- 0.18 4.88 +/- 0.46 356.40 + 93.60 5.50 +/- 0.10 0.13 +/- 0.08 0.01 +/- 0.00 23.84 +/- 2.44 11.70 +/- 1.20 0.13 +/- 0.01 0.13 +/- 0.01 203.59 +/- 95.34 1 1.85 +/- 0.27 6.10 +/- 0.57 525.00 +/- 108.00 14.57 +/- 0.44 16.80 +/- 1.71 0.07 +/- 0.01 1.22 +/- 0.10 1.23 +/- 0.07 332.00 +/- 71.42 5.22 +/- 0.40 2.63 +/- 0.41 36.28 +/- 3.02 15.45 +/- 0.68 389.05 +/- 69.01 2.89 4- 0.32 414.00 +/- 65.76 0.20 +/- 0.07 0.97 +/- 0.38 0.89 +/- 0.21 8.87 +/- 0.16 7.36 +/- 0.45 1.16 +/- 0.39 1.92 +/- 1.10 3.21 +/- 0.84 417.48 +/- 67.80 37.63 +/- 0.28 2.67 +/- 0.34 236.32 +/- 59.86 221.95 +/- 67.76 1418.70 +/- 77.08 5.32 +/- 0.13 4.78 +/- 0.33 346.00 +/- 65.83 5.35 +/- 0.11 0.13 +/- 0.04 0.01 +/- 0.00 23.32 +/- 1.59 11.50 +/- 0.85 0.13 +/- 0.01 0.13 +/- 0.01 201.38 +/- 67.34 1.85 +/- 0.18 6.10 +/- 0.39 549.00 +/- 77.08 14.56 +/- 0.34 16.15 +/- 1.16 0.07 +/- 0.01 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 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 G-3427, 3428 G-3427, 3428 SW-3512, 3513 AP-3680, 3681 VE-3791,3792 WW-3934, 3935 DW-10135, 10136 DW-10135, 10136 W-4063, 4064 DW-10143, 10144 DW-10148, 10149 DW-10148, 10149 DW-10159, 10160 DW-10159, 10160 SL-4106, 4107 SL-4106, 4107 SL-4106, 4107 SG-4085, 4086 SG-4085, 4086 SWT-4304, 4305 BS-4398, 4399 BS-4398, 4399 VE-4531,4532 VE-4531,4532 VE-4531, 4532 VE-4531,4532 DW-10170, 10171 DW-10170, 10171 AP-4766, 4767 DW-10182, 10183 VE-4928, 4929 SL-4883, 4884 SL-4883, 4 8 8 4 b W-5135, 5136 SW-5071, 5072 XWW-5246, 5247 7/1/2010 7/1/2010 7/6/2010 7/8/2010 7/12/2010 7/12/2010 7/13/2010 7/13/2010 7/14/2010 7/19/2010 7/23/2010 7/23/2010 7/23/2010 7/23/2010 8/2/2010 8/2/20 10 8/2/2010 8/3/2010 8/3/2010 8/3/2010 8/10/2010 8/10/2010 8/11/2010 8/11/2010 8/11/2010 8/11/2010 8/13/2010 8/13/2010 8/26/2010 8/27/2010 9/1/2010 9/1/2010 9/1/2010 9/6/2010 9/13/2010 9/14/2010 Be-7 K-40 H-3 Be-7 K-40 H-3 Ra-226 Ra-228 H-3 Gr. Alpha Ra-226 Ra-228 Ra-226 Ra-228 Be-7 Gr. Beta K-40 Ra-226 Ra-228 Gr. Beta Cs-137 K-40 Gr. Beta K-40 U-233/4 U-238 Ra-226 Ra-228 Be-7 Ra-226 K-40 Gr. Beta K-40 H-3 H-3 H-3 1.18 + 0.29 8.79 + 0.64 441.00 + 103.00 0.16 +/- 0.08 4.37 + 0.38 3091.00 + 187.00 0.18 +/- 0.07 0.76 0 0.44 469.00 +/- 104.00 2.84 +/- 0.74 2.08 +/- 0.39 1.90 + 0.61 0.91 +/- 0.14 1.41 +0.54 2.05 + 0.20 5.06 + 0.32 1.89 +/- 0.24 20.23 +/- 2.04 15.88 +/-0.41 2.08 -1.07 78.80 +/- 33.50 13708 +/- 795 36.20 +/- 0.90 27.31 +/- 0.70 0.014 +/- 0.003 0.012 +/- 0.003 1.32 + 0.14 2.55 +/- 0.78 0.18 +/- 0.09 0.15 +/- 0.08 2.99 +/- 0.41 6.90 +/- 0.20 7.15 +/- 0.99 658.60 +/- 110.80 186.70 +/- 101.10 1990.60 -157.70 1.06 +/- 0.25 7.85 +/- 0.65 423.00 +/- 102.00 0.13 +/- 0.07 4,23 + 0.35 3242.00 +/- 191.00 0.26 +/- 0.07 0.81 +/- 0.41 351.00 +/- 99.00 2.49 +/- 0.73 2.97 +/- 0.55 2.00 +/- 0.61 0.79 +/- 0.21 1.30 +/- 0.53 2.05 +/- 0.18 4.62 +/- 0.30 1.70 +/- 0.17 21.45 +/- 2.16 16.24 +/- 0.36 2.44 +/- 0.98 94.30 +/- 51.90 12091 +/- 1110 35.80 +/- 0.90 27.58 +/- 0.62 0.014 +/- 0.003 0.010 +/- 0.002 1.26 +/- 0.14 1.76 +/- 0.71 0.25 +/- 0.13 0.11 +/- 0.07 3.18 +/- 0.28 7.10 +/- 0.20 5.07 +/- 0.51 600.90 +/- 108.50 267.30 +/- 104.40 1986.20 +/- 157.60 1.12 +/- 0.19 8.32 +/- 0.46 432.00 +/- 72.48 0.15 +/- 0.05 4.30 +/- 0.26 3166.50 +/- 133.65 0.22 +/- 0.05 0.79 +/- 0.30 410.00 +/- 71.79 2.67 +/- 0.52 2.53 +/- 0.34 1.95 +/- 0.43 0.85 +/- 0.13 1.36 +/- 0.38 2.05 +/- 0.13 4.84 +/- 0.22 1.80 +/- 0.15 20.84 +/- 1.49 16.06 +/- 0.27 2.26 +/- 0.73 86.55 +/- 30.89 12900 +/- 683 36.00 +/- 0.64 27.45 +/- 0.47 0.014 +/- 0.002 0.011 +/- 0.002 1.29 +/- 0.10 2.16 +/- 0.53 0.22 +/- 0.08 0.13 +/- 0.05 3.09 +/- 0.25 7.00 +/- 0.14 6.11 +/- 0.56 629.75 +/- 77.54 227.00 +/- 72.66 1988.40 +/- 111.48 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 Fail Pass Pass Pass A5-3 TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-5114, 5115 VE-5114, 5115 VE-5114, 5115 VE-5114, 5115 VE-5114, 5115 MI-5267, 5268 SO-5357, 5358 AP-5357, 5358 DW-10194, 10195 DW-10194,10195 WW-5442, 5443 VE-5469, 5470 BS-5886,5887 BS-5886,5887 G-5513,5514 E-5492, 5493 E-5492, 5493 G-5512, 5513 G-5512, 5513 MI-5541, 5542 MI-5541, 5542 F-6061, 6062 F-6061, 6062 VE-5740, 5741 VE-5761, 5762 VE-5761, 5762 AP-5910, 5911 WW-6294,6295 P-6038, 6039 AP-6195, 6196 WW-6366,6367 SWU-6315, 6316 SO-6336, 6337 SO-6336, 6337 SO-6336,6337 AP-6453, 6454 BS-6475,6476 F-6658, 6659 F-6565, 6566 F-6565, 6566 F-6565, 6566 SS-5761,5762 WW-7056,7057 9/9/2010 9/9/2010 9/9/2010 9/9/2010 9/9/2010 9/20/2010 9/23/2010 9/23/2010 9/23/2010 9/23/2010 9/29/2010 9/29/2010 9/29/2010 9/29/2010 10/4/2010 10/4/2010 10/4/2010 10/4/2010 10/4/2010 10/4/2010 10/4/2010 10/9/2010 10/9/2010 10/10/2010 10/12/2010 10/12/2010 10/14/2010 10/18/2010 10/19/2010 10/21/2010 10/23/2.010 10/26/2010 10/28/2010 10/28/2010 10/28/2010 10/28/2010 11/1/2010 11/3/2010 11/4/2010 11/4/2010 11/4/2010 11/16/2010 11/30/2010 Be-7 Gr. Beta H-3 K-40 U-233/4 K-40 K-40 Be-7 Ra-226 Ra-228 H-3 K-40 Cs-137 K-40 Be-7 Gr. Beta K-40 Gr. Beta K-40 K-40 Sr-90 H-3 K-40 K-40 Be-7 K-40 Be-7 H-3 H-3 Be-7 H-3 Gr. Beta Cs-1 37 Gr. Beta K-40 Be-7 Gr. Beta K-40 Cs-137 Gr. Beta K-40 K-40 Gr. Beta 1.14 +/- 0.35 34.72 +/- 1.29 79367 +/- 837 22.13 +/- 0.67 0.08 +/- 0.01 1281.10 +/- 118.90 10894.00 +/- 560.00 0.11 +/- 0.02 0.40 +/- 0.10 1.61 +/- 0.65 6706.00 +/- 252.00 2.86 +/- 0.38 83.36 +/- 23.31 13913.00 +/- 775.40 6.73 +/- 0.40 1.74 +/- 0.05 1.57 +/- 0.17 10.86 +/- 0.44 7.10 +/- 0.54 1090.60 +/- 106.70 1.44 +/- 0.38 7.64 +/- 0.23 2.81 +/- 0.40 4.92 +/- 0.53 1.05 +/- 0.29 3.45 +/- 0.45 0.23 +/- 0.09 1681.49 +/- 146.32 2131.90 +/- 159.50 0.27 +/- 0.11 477.28 +/- 102.02 1.85 +/- 1.00 0.23 +/- 0.03 26.36 +/- 1.67 13.43 +/- 0.76 0.23 +/- 0.12 13.13 +/- 1.83 2.79 +/- 0.40 0.06 +/- 0.02 3.90 +/- 0.10 2.63 +/- 0.45 15.42 +/- 1.57 2.09 +/- 0.84 1.48 +/- 0.26 33.38 +/- 1.23 79421 +/- 837 21.93 +/- 0.58 0.06 +/- 0.01 1218.60 +/- 110.80 11175.00 +/- 760.00 0.09 +/- 0.02 0.20 +/- 0.10 0.88 +/- 0.47 6510.00 +/- 249.00 2.57 +/- 0.37 58.97 +/- 21.16 13582.00 +/- 710.30 6.36 +/- 0.41 1.77 +/- 0.05 1.55 +/- 0.18 10.39 +/- 0.39 7.41 +/- 0.59 1246.10 +/- 102.60 1.11 +/- 0.35 7.49 +/- 0.23 2.56 +/- 0.50 4.61 +/- 0.34 0.69 +/- 0.15 3.34 +/- 0.29 0.30 +/- 0.12 1637.41 +/- 144.98 2212.00 +/- 161.70 0.26 +/- 0.13 529.99 +/- 104.27 1.40 +/- 0.90 0.23 +/- 0.04 24.78 +/- 1.52 13.73 +/- 0.81 0.30 +/- 0.15 12.75 +/- 1.67 2.94 +/- 0.44 0.04 +/- 0.01 4.10 +/- 0.10 2.57 +/- 0.35 15.87 +/- 1.21 2.22 +/- 0.80 1.31 +/- 0.22 34.b5 +/- 0.89 79394 +/- 592 22.03 +/- 0.44 0.07 +/- 0.01 1249.85 +/- 81.26 11034.50 +/- 472.02 0.10 +/- 0.01 0.30 +/- 0.07 1.25 +/- 0.40 6608.00 +/- 177.13 2.72 +/- 0.26 71.17 +/- 15.74 13747.50 +/- 525.78 6.55 +/- 0.29 1.76 +/- 0.04 1.56 +/- 0.12 10.63 +/- 0.29 7.26 +/- 0.40 1168.35 +/- 74.01 1.27 +/- 0.26 7.57 +/- 0.16 2.68 +/- 0.32 4.77 +/- 0.32 0.87 +/- 0.16 3.40 +/- 0.27 0.26 +/- 0.08 1659.45 +/- 102.99 2171.95 +/- 113.56 0.26 +/- 0.09 503.64 +/- 72.94 1.62 +/- 0.67 0.23 +/- 0.02 25.57 +/- 1.13 13.58 +/- 0.56 0.26 +/- 0.10 12.94 +/- 1.24 2.86 +/- 0.30 0.05 +/- 0.01 3.96 +/- 0.06 2.60 +/- 0.29 15.65 +/- 0.99.2.16 +/- 0.58 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-4 TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)5 Averaged Lab Code Date Analysis First Result Second Result Result Acceptance SO-7166, 7167 11/30/2010 Cs-137 0.12 +/- 0.04 0.11 +/- 0.03 0.11 +/- 0.03 Pass SO-7166, 7167 11/30/2010 K-40 14.93 +/- 0.88 14.49 +/- 0.86 14.71 +/- 0.61 Pass WW-7412, 7413 12/6/2010 H-3 469.78 +/- 146.32 503.57 +/- 93.96 486.68 +/- 86.94 Pass MI-7187, 7188 12/8/2010 K-40 1495.10 +/- 129.00 1398.40 +/- 109.10 1446.75 +/- 84.47 Pass MI-7187, 7188 12/8/2010 Sr-90 0.57 +/- 0.31 0.66 +/- 0.28 0.62 +/- 0.21 Pass WW-7255, 7256 12/8/2010 H-3 243.46 +/- 90.39 327.34 +/- 94.11 285.40 +/- 65.24 Pass AP-7276, 7277 12/9/2010 Be-7 0.13 +/- 0.07 0.18 +/- 0.10 0.16 +/- 0.06 Pass XWW-7297, 7298 1219/2010 H-3 686.00 +/- 102.00 764.60 +/- 105.00 725.30 +/- 73.19 Pass AP-7344, 7345 12/16/2010 Be-7 0.16 +/- 0.09 0.17 +/- 0.09 0.16 +/- 0.06 Pass SWT-7480, 7481 12/28/2010 Gr. Beta 0.90 +/- 0.40 1.03 +/- 0.41 0.97 +/- 0.29 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).b Analysis was repeated, result of reanalysis:

4.83 +/- 0.29 pCi/L.A5-5 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 STVE-1 199 STVE-1 199 STVE-1 199 STVE-1 199 STVE-1 199 STVE-1 199 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 0.01 +/- 0.03 3.39 +/- 0.12 4.74 +/- 0.15 3.32 +/- 0.17 0.01 +/- 0.05 8.03 +/- 0.33 0.40 +/- 0.05 3.03 +/- 0.07 0.00 3.27 4.39 3.06 0.00 7.10 0.68 3.09 2.29 -4.25 3.07 -5.71 2.14 -3.98 4.97 -9.23 0.00-1.35 1.55 -4.64 STW-1200 03/01/10 Gr. Alpha STW-1200 03/01/10 Gr. Beta STW-1201 STW-1 201 STW-1 201 STW-1 201 STW-1201 STW-1201 STW-1201 STW-1201 STW-1 201 STW-1 201 STW-1201 STW-1 201 STW-1201 STW-1201 STSO-1202 STSO-1202 STSO-1202 STSO-1202 STSO-1202 STSO-1202 STSO-1202 STSO-1202 STSO-1202 STSO-1202 STAP-1203 STAP-1203 STAP-1203 STAP-1203 STAP-1 203 STAP-1203 STAP-1203 STAP-1203 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 03/01/10 Am-241 Co-57 Co-60 Cs-134 Cs-1 37 Fe-55 H-3 Mn-54 Ni-63 Sr-90 Tc-99 U-233/4 U-238 Zn-65 Co-57 Co-60 Cs-134 Cs-137 K-40 Mn-54 Sr-90 U-233/4 U-238 Zn-65 Am-241 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 1.05 +/- 0.08 28.90 +/- 0.40 0.06 +/- 0.05-0.03 +/- 0.09 60.60 +/- 0.60 3.00 +/- 14.40 93.20 +/- 18.30 27.80 +/- 0.40 49.10 +/- 3.50-0.10 +/- 0.60 0.50 +/- 0.50 1.21 +/- 0.05 1.20 +/- 0.05 42.70 + 0.80 520.00 +/- 10.80 599.10 +/- 2.80 666.10 +/- 4.70 774.40 +/- 4.50 562.00 +/- 15.30 866.20 +/- 4.60 225.50 +/- 11.80 59.90 +/- 2.50 62.10 +/- 2.60-1.23 +/- 1.96 0.10 +/- 0.01 0.01 +/- 0.02 2.63 +/- 0.19 2.21 +/- 0.34 1.66 +/- 0.22 3.42 +/- 0.26 0.02 +/- 0.06-0.05 +/- 0.11 1.30 28.30 0.00 0.00 60.60 0.00 90.80 26.90 59.90 0.00 0.00 1.22 1.25 40.70 522.00 622.00 733.00 779.00 559.00 849.00 288.00 60.00 64.00 0.00 0.15 0.00 2.47 2.13 1.53 3.02 0.00 0.00 0.91 -1.69 19.80 -36.80 42.40 -78.80 63.60 -118.00 18.80 -35.00 41.90 -77.90 0.85 -1.59 0.88-1.63 28.50 -52.90 365.00 -679.00 435.00 -809.00 513.00 -953.00 545.00 -1013.00 391.00 -727.00 594.00 -1104.00 202.00 -374.00 42.00 -78.00 45.00 -83.00 0.10 -0.19 1.73 -3.22 1.49 -2.77 1.07-1.99 2.11 -3.93 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 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-1204 03101/10 Gr. Alpha STAP-1204 03/01/10 Gr. Beta 0.13 +/- 0.03 1.46 +/- 0.07 0.43 1.29 0.00 -0.85 0.65 -1.94 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW-1211 STW- 1211 STW-1211 STW-1211 STW-1211 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01110 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 Am-241 Co-57 Co-60 Cs-134 Cs-137 Fe-55 H-3 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-233/4 U-238 Zn-65 STW-1212 08/01/10 Gr. Alpha STW-1212 08/01/10 Gr. Beta 0.02 +/- 0.02 36.40 +/- 4.80 28.30 +/- 1.00 29.30 +/- 2.10 44.60 +/- 1.80 48.50 +/- 20.10 503.60 +/- 12.80 38.50 +/- 2.50 0.10 +/- 0.30 49.30 +/- 3.10 1.49 +/- 0.15 1.20 +/- 0.10 9.20 +/- 1.30 28.10 +/- 0.90 2.04 +/- 0.14 2.05 +/- 0.14 32.80 +/- 3.00 1.54 +/- 0.09 4.13 +/- 0.15 9.60 +/- 0.54 0.05 +/- 0.08 4.83 +/- 0.26 6.45 +/- 0.66 7.12 +/- 0.66 6.05 +/- 0.74 0.10 +/- 1.60 370.00 +/- 6.00 1005.00 +/- 21.00 755.00 +/- 15.00 783.00 +/- 54.00 942.00 +/- 15.00 69.20 +/- 6.20 76.50 +/- 6.20 3.50 +/- 8.00 76.50 +/- 6.20 271.40 +/- 9.00 310.00 +/- 18.00 0.00 36.00 28.30 31.40 44.20 60.20 453.40 38.90 0.00 56.10 1.81 1.35 8.30 33.60 2.01 2.07 31.00 1.92 4.39 8.27 0.00 4.79 5.88 6.29 5.39 0.00 343.00 940.00 670.00 699.00 820.00 64.00 71.00 0.00 71.00 289.00 265.00 25.20 -46.80 19.80 -36.80 22.00 -40.80 30.90 -57.50.42.10 -78.30 317.40 -589.40 27.20 -50.60 39.30 -72.90 1.27 -2.35 0.95 -1.76 5.80 -10.80 23.50 -43.70 1.41 -2.61 1.45 -2.69 21.70 -40.30 0.58 -3.26 2.20 -6.59 5.79 -10.75 3.35 -6.23 4.12 -7.64 4.40 -8.17 3.77 -7.01 240.00 -446.00 658.00 -1222.00 469.00 -871.00 489.00 -909.00 574.00 -1066.00 45.00 -83.00 50.00 -92.00 50.00 -92.00 202.00 -376.00 186.00 -345.00 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 STVE-1213 STVE-1213 STVE-1213 STVE-1213 STVE-1213 STVE-1213 STSO-1214 STSO-1214 STSO-1214 STSO-1 214 STSO-1214 STSO-1214 STSO-1214 STSO-1214 STSO-1214 STSO-1214 STSO-1214 STSO-1 214 08/01/10 08/01/10 08/01/10 08/01(10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 08/01/10 Co-57 Co-60 Cs-134 Cs- 137 Mn-54 Zn-65 Co-57 Co-60 Cs-134 Cs-1 37 K-40 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 A6-2 TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP)'.Concentration b Known Control Lab Code Date Analysis Laboratory result Activity Limits d Acceptance STAP-1215 08/01/10 Co-57 4.47 +/- 0.21 4.08 2.86 -5.30 Pass STAP-1215 08/01/10 Co-60 3.15 +/- 0.30 2.92 2.04 -3.80 Pass STAP-1215 08/01110 Cs-134 3.03 +/- 0.17 2.98 2.09 -3.87 Pass STAP-1215 08/01/10 Cs-137 0.01 +/- 0.05 0.00 -Pass STAP-1215 08/01/10 Mn-54 3.69 +/- 0.39 3.18 2.23 -4.13 Pass STAP-1215 08/01/10 Sr-90 1.00 +/- 0.12 1.01 0.71 -1.31 Pass STAP-1215 08/01/10 Zn-65 0.03 +/- 0.15 0.00 -Pass STAP-1216 08/01/10 Gr. Alpha 0.01 +/- 0.01 0.00 -Pass STAP-1216 08/01/10 Gr. Beta 0.54 +/- 0.05 0.50 0.25 -0.75 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. A known value of "zero" indicates an analysis was included in the testing series as a "false positive".

MAPEP does not provide control limits.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-1217 STAP-1217 STAP-1217 STAP-1217 STAP-1217 STAP-1217 STAP-1217 STAP-1217 STAP-1217 STAP-1217 STAP-1217 STAP-1217 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 Am-241 Co-60 Cs-134 Cs-137 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/234 U-238 Uranium Zn-65 55.6 +/- 2.9 517.1 +/-9.1 384.6 +/- 33.7 589.4 +/- 7.1 0.0 +/- 0.0 76.5 +/- 4.0 73.0 +/- 3.8 172.9 +/- 21.3 64.9 +/- 3.9 68.0 +/- 4.0 135.5 +/- 8.7 563.1 +/- 15.3 66.1 +/- 3.2 69.9 +/- 2.5 74.1 479.0 388,0 514.0 72.9 69.6 159.0 71.8 71.2 146.0 465.0 52.3 52.7 43.3 -102.0 371.0 -598.0 253.0 -480.0 386.0 -675.0 50.0 -95.8 50.5 -90.1 70.0 -247.0 45.2 -106.0 45.6 -101.0 74.6 -232.0 322.0 -644.0 27.1 -78.7 32.5 -77.0 STAP-1218 09/20/10 Gr. Alpha STAP-1218 09/20/10 Gr. Beta STSO-1219 STSO-1219 STSO-1219 STSO-1219 STSO-1219 STSO-1219 STSO-1219 STSO-1219 STSO-1219 STSO-1219 STSO-1219 STSO-1219 STSO-1219 STSO-1219 e STSO-1219 e STSO-1219 e STSO-1219 STVE-1220 STVE-1220 STVE-1220 STVE-1220 STVE-1220 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 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 U-233/234 U-238 Uranium.Zn-65 Co-60 Cs-134 Cs-137 K-40 Mn-54 1632.0 t 80.4 1063.0 t 120.9 1752.0 +/- 255.6 909.3 +/- 38.9 4852.0 +/- 153.5 2190.0 +/- 50.7 3584.0 +/- 42.5 10017.0 +/- 274.5 0.0 +/- 0.0 1573.0 +/- 28.2 999.0 +/- 39.2 1568.0 +/- 155.0 1445.0 +/- 142.9 599.4 +/- 69.4 633.8 +/- 71.3 1248.0 +/- 152.7 2447.0 +/- 60.1 1108.0 +/- 38.7 1161.0 +/- 57.3 1400.0 +/- 43.0 27400.0 +/- 683.4 0.0 +/- 0.0 1830.0 1120.0 2070.0 983.0 4780.0 2240.0 3530.0 10700.0 1640.0 969.0 1280.0 1180.0 1360.0 1340.0 2770.0 2300.0 1010.0 1040.0 1260.0 22600.0 1170.0 -2580.0 669.0 -1440.0 543.0 -3100.0 603.0 -1410.0 3480.0 -6420.0 1440.0 -2700.0 2700.0 -4580.0 7760.0 -14500.0 1060.0 -2310.0 580.0 -1440.0 733.0 -1800.0 805.0 -1570.0 862.0 -1690.0 819.0 -1700.0 1580.0 -3740.0 1820.0 -3080.0 683.0 -1450.0 595.0 -1440.0 924.0 -1750.0 16200.0 -32000.0 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 Pass Pass Fail Fail Fail 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 ' Result Limits Acceptance STVE-1220 STVE-1220 STVE-1220 STVE-1220 STVE-1220 STVE-1220 STVE-1220 STVE-1220 STVE-1220 STW-1221 STW-1221 STW-1221 STW-1221 STW-1 221 STW-1 221 STW-1221 STW-1221 STW-1221 STW-1221 STW-1221 STW-1221 STW-1221 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 09/20/10 Am-241 Cm-244 Pu-238 Pu-239/40 Sr-90 U-233/234 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-233/234 U-238 Uranium Zn-65 4185.0 +/- 180.0 2329.0 +/- 132.5 4912.0 +/- 194.0 4765.0 +/- 111.0 7706.0 +/- 583.9 3862.0 +/- 203.0 3926.0 +/- 205.3 7671.0 +/- 201.2 1443.0 +/- 81.0 127.9 +/- 4.2 697.8 +/- 10.4 437.5 +/- 13.3 612.8 +/- 11.6 936.8 +/- 508.2 0.0 +/- 0.0 148.1 +/- 6.0 154.1 +/- 6.2 872.3 +/- 13.4 99.1 +/- 4.4 103.7 +/- 4.5 206.5 +/- 9.8 489.1 +/- 16.2 110.6 +/- 3.5 134.6 +/- 2.6 23500.0 +/- 1438.0 4760.0 2740.0 4740.0 4470.0 7810.0 4010.0 3980.0 8180.0 1210.0 176.0 714.0 492.0 625.0 825.0 162.0 148.0 921.0 109.0 108.0 221.0 489.0 146.0 143.0 2710.0 -6540.0 1350.0 -4270.0 2560.0 -6940.0 2770.0 -6100.0 4360.0 -10400.0 2750.0 -5320.0 2800.0 -5030.0 5620.0 -10600.0 874.0 -1650.0 120.0 -238.0 622.0 -844.0 363.0 -565.0 531.0 -749.0 480.0 -1100.0 122.0 -201.0 114.0 -183.0 585.0 -1230.0 82.2 -140.0 82.5 -134.0 159.0 -294.0 414.0 -610.0 64.8 -216.0 83.6 -210.0 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 STW-1222 09/20/10 Gr. Alpha STW-1222 09/20/10 Gr. Beta STW-1223 09/20/10 H-3 21600.0 14100.0 -31900.0 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).

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

Results are presented as the known values, expected.

laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. A known value of "zero" indicates an analysis was included in the testing series as a "false positive".

Control limits are not provided.Analysis was repeated using total dissolution.

Results of the reanalysis, U-233/234:

1137 +/- 254 pCi/kg, U-238: 1193 +/- 116 pCi/kg, Total Uranium: 2379 +/- 254 pCi/kg.A7-2 APPENDIX B DATA REPORTING CONVENTIONS B-1 Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period, 2.0. Single Measurements Each single measurement is reported as follows: x +/- s where: x = value of the measurement; s = 2a counting uncertainty (corresponding to the 95% confidence level).In cases where the activity is less than the lower limit of detection L, it is reported as: < L, where L = the lower limit of detection based on 4.66ay 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; x, +/- sI and x2 _ s2 Reported result: x+/-s; where x= (1/2)(x +X 2)ands= (1/2) ýS+S2_3.2. Individual results: < L , < L 2 Reported result: < L, where L = lower of L, and L2 3.3. Individual results: x +/- s, < L Reported result: x + s if x >- L; < L otherwise.

4.0. 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, x 2... x are defined as follows: 1 x-x 2 x n 7x = n-4.2 Values below the highest lower limit of detection are not included in the average.4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.4.5 In rounding off, the following rules are followed: 4.5.1. If the number following those to be retained is less than 5, the number is dropped, and the retained 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 (pCilm3) Water (pCiIL)-3 Gross alpha 1 x 10 Strontium-89 8,000 Gross beta 1 Strontium-90 500 b -1 Iodine-1 31 2.8 x 10 Cesium-137 1,000 Barium-140 8,000*lodine-131 1,000 C Potassium-40 4,000 Gross alpha 2 Gross beta 10 6 Tritium 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.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 MNGP APPENDIX D Sampling Location Maps D-1 lr Figure D-1, Sample Collection and Analysis program: TLD locations, Inner ring (Table 5.2).D-2 ED CL iCI 0~1 IB IMI I t '.&000 Figure D-2. Sample Collection and Analysis program: TLD locations, Outer ring (Table 5.2).D-3 0-I I Figure D-4. Sample Collection and Analysis Program: Radiation Environmental Monitoring Program, Milk sampling locations. (Table 5.2)D-5 Doe-..- Figure D-5. Sample Collection and Analysis Program: Radiation Environmental Monitoring Program, Milk, Sludge, Ground Water and Shoreline sampling locations (Table 5-2.)D-6 APPENDIX E Ground Water Monitorina Well Samples

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 Ground Water Monitoring Program samples taken at the Monticello Nuclear Plant, Monticello, Minnesota, during the period January -December 2010. This sampling program was established in October of 2006 following the industry initiative on ground water monitoring.

Complete data tables for each period and sampling location, are provided in a reference document, (Environmental, Inc., Midwest Laboratory, "Complete Analyses Data Tables, January -December, 2010") available at the Monticello Nuclear Generating Plant, Chemistry and Radiation Protection Department.

E-2 2.0

SUMMARY

The Ground Water Sampling Program was established following industry events where tritium was discovered in ground water surrounding commercial nuclear facilities.

This program is described and the results for 2010 are summarized and discussed.

Program findings for 2010 detected low levels of tritium in monitoring wells located on the plant property at or near the expected natural background levels, with the exception of Monitoring Wells MW-9 and MW-10. The 2010 sample results (except for MW-9 and MW-10) ranged from <143 to 665 pCi/L. Storm water runoff samples ranged from 468 pCi/L to < LLD. All tritium results (with the exception of MW-9)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 samples monitored for gamma-emitting isotopes showed activity greater than the LLD.A summation of the analytical data for both ground water monitoring wells and storm water runoff samples is provided in Table E-3.E-3

3.0 Ground

Water Sampling Proaram 3.1 Program Design and Data Interpretation The purpose of this sampling program is to assess the impact of any tritium leaching into the environment (ground water system) from MNGP. For this purpose, water samples are collected and analyzed for tritium content.3.2 Program Description The sampling and analysis schedule for the Ground Water Monitoring Program is summarized in Table E-1 and briefly reviewed below. Table E-2 defines the additional sample locations and codes for the Ground Water Sampling Program.Ground Water Monitoring Well samples were collected quarterly at 5 locations and monthly at 10 locations.

In addition, Monitoring Well M-14 was installed in the fall of 2010 but only one sample has been collected due to inaccessibility of the well. This well will be sampled monthly in the future.3.3 Program Execution The Ground Water Monitoring Program was executed as described in the preceding section.3.4 Program Modifications Changes to the program include:* The addition of Monitoring Well MW-14* The creation of this Appendix" The stand pipe for MW-5 was cut off at the ground to create a parking lot* A sample of MW-9 was analyzed for hard to detect nuclides in accordance with American Nuclear Insurers recommendations E-4

3.5 Results

and Discussions Results obtained show tritium in ground water samples at or near expected natural background levels, with the exception of MW-9 and MW-1 0.Except for MW-9 and MW-10, the 2010 sample results are within the range of expected background tritium levels in groundwater 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 in MW-9 and MW-10 have been addressed in an Apparent Cause Evaluation In 1981 there was a spill from the Condensate Storage Tanks that site groundwater studies have indicated infiltrated the surface and migrated to MW-9.MW-14 was added to the program near the river bank to monitor for tritiated ground water reaching the river. All samples from MW-14 have been less than LLD.None of the water samples monitored for gamma-emitting isotopes showed any activity greater than LLD.E-5 Table E-1. Sample Collection and Analysis Program, Ground Water.Medium Number Sample Codes Collection type Analysis Type Ground Water 5 MW-4, MW-5, MW-6, MW-7, Grab H-3 Quarterly MW-8 Ground Water 12 MW-1, MW-2, MW-3, MW-9, Grab H-3 Monthly MW-9A, MW-1 0, MW-1 1, MW-12A, MW-1i2B, MW-13A, MW-13B, MW-14 Table E-2. Sampling locations for Ground Water Monitoring Wells.Sample Type Vendor Well Distance from Compass Sector Code Number Stack (miles) Heading from Stack Ground Water M-33 MW-1 0.11 299 WNW Ground Water M-34 MW-2 0.14 301 WNW Ground Water M-35 MW-3 0.15 305 NW Ground Water M-36 MW-4 0.1 25 NNE Ground Water M-37 MW-5 0.1 253 WSW Ground Water M-38 MW-6 229 Feet 228 SW Ground Water M-39 MW-7 0.2 66 ENE Ground Water M-40 MW-8 0.3 150 SSE Ground Water M-44 MW-9 0.1 310 NW Ground Water M-51 MW-9B 0.1 310 NW Ground Water M-45 MW-10 0.1 292 WNW Ground Water M-46 MW-11 0.1 283 WNW Ground Water M-47 MW-12A 0.1 330 NW Ground Water M-48 MW-12B 0.1 326 NW Ground Water M-49 MW-13A 0.12 316 NW Ground Water M-50 MW-13B 0.12 316 NW Ground Water M-52 MW-14 0.17 306 NW E-6 Table E-3. Ground Water Monitoring Program Summary.Name of Facility Location of Facility Monticello Nuclear Generating Plant Wright. Minnesota ( County, State)Docket No. 50-263 Reporting Period January-December, 2010 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)' Mean (F)0 Mean (F)0 Routine (Units) Analyses' Range' Locationd Range' Range' Results 0 Groundwater H-3 152 500 3257 (20/152) MW-9A, Onsite, 7633 (7/12) none 4 Monitoring Wells (609-21127) 0.1 mi @ 310=/NW (629-21127)(pCi/L) GS 150 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 52 < LLD none 0 Stormwater H-3 6 500 < LLD none 0 Runoff (pCi/L) GS 3 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 1-131 30 < LLD none 0 Cs-134 10 < LLD none 0 Cs-137 10 < LLD none 0 Ba-La-140 15 < LLD none 0 Ce-144 41 < LLD none 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.c Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).Locations are specified:

(1) by name, and/or station code (Table 2) and (2) by distance (miles) and direction relative to reactor site.e Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten time the typical preoperational value for the medium or location.E-7 MISSISSIPPI RIVER 904.40 (September 09, 2009)Figure E-1. Sample collection and analysis program: Ground water, On-site monitoring well locations.

E-8 QF-0212, Revision 4 (FP-SC-RSI-04)

& XcelEnergyo Page 1 of 1 SHIPPING DOCUMENT NORTHERN STATES POWER -MN Xcel Energy 2807 County Rd 75 Monticello MN 55362 Date: 5/12/11 Shipping Document Tracking Number:)) -O 01 Yý6 Ship To: USNRC One White Flint North 11555 Rockville Pike Rockville, MD 20852 Attention Of: Document Control Desk SHIPMENT,:

SHIPMENT PO NUMBER: RMA NO.: PACKAGING SHIPPING BY PleBo.... ....

Pallet, Box, Etc.Fed Ex .ORIGINAL PO NUMBER: BUYER: Town Run.Motor Freight FREIGHT TRACKING NO.' -JDErNUMBER:

Vendor UPS-- Reason for shipment:

Overnight Shipment to USNRC Other Item o.,--,t, Unit Description Catalog-I 2010 Annual Radiological Environmental Operating 1 1 Letter eo Report Shipment Requester SWIP Ma ng Shipment Victoria Blomgren Use of this form as a procedural aid does not require retention as a quality record.

L-MT-11-020, 2010 Annual Radiological Environmental Operating Report

Contents

Text

5.6.1 Monticello

1.0 INTRODUCTION

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

3.0 RADIOLOGICAL

3.2 Program

3.3 Progqram

3.4 Laboratory

4.0 RESULTS

4.3 Program

5.0 FIGURES

6.0 REFERENCES

6.0 REFERENCES

4.0. Computation

4.1 Averages

1.0 INTRODUCTION

SUMMARY

3.0 Ground

3.5 Results

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L-MT-11-020, 2010 Annual Radiological Environmental Operating Report

Text

5.6.1 Monticello

1.0 INTRODUCTION

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

3.0 RADIOLOGICAL

3.2 Program

3.3 Progqram

3.4 Laboratory

4.0 RESULTS

4.3 Program

5.0 FIGURES

6.0 REFERENCES

6.0 REFERENCES

4.0. Computation

4.1 Averages

1.0 INTRODUCTION

SUMMARY

3.0 Ground

3.5 Results

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