Text

Submittal of 2012 Annual Radiological Environmental Operating Report
	ML13135A006
Person / Time
Site:	Monticello
Issue date:	05/10/2013
From:	Schimmel M A; Xcel Energy, Northern States Power Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	L-MT-13-042
	Download: ML13135A006 (73)
	v • d • e

jXcelEnergy May 10, 2013 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-13-042 Technical Specification

5.6.1 Monticello

Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No. DPR-22 2012 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 (NSPM), d/b/a Xcel Energy, is submitting the Annual Radiological Environmental Operating Report for the year 2012.Summary of Commitments This letter makes no new commitments and no revisions to existing Mark A. Schimmel Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company -Minnesota commitments.

Enclosure cc: Administrator, Region III, USNRC Project Manager, Monticello, USNRC Resident Inspector, Monticello, USNRC Minnesota Department of Commerce 56u~

ENCLOSURE I RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1 -DECEMBER 31, 2012 71 pages follow

)&ATI Environmental, Inc.Midwest Laboratory 700 Landwehr Road -Northbrook, 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, 2012 Prepared under Contract by ENVIRONMENTAL, Inc.Midwest Laboratory Project No. 8010 Approved: Bro ni G b, M.S.Lratbora Manager (94/17 113 1 1 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 List of Tables ..............................................................................................................

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

v

1.0 INTRODUCTION

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

1 2 .0 S U M M A R Y ..........................................................................................................................

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 Atmospheric Nuclear Detonations and Nuclear Accidents

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

7 4.2 Summary of Preoperational Data ....................................................................

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

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

12

6.0 REFERENCES

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

24 APPENDICES A Interlaboratory Comparison 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 Sampling Location Maps ...................................................................................................

D-1 E Ground Water Monitoring Well Samples .................................

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

13 Sampling Locations

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

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 Therm olum inescent dosim eters (TLDs) ........................................................................

A2-1 A-3 In-house Spiked Sam ples ........................................................................................

A3-1 A -4 In-house "Blank" S am ples .............................................................................................

A 4-1 A-5 In-house "Duplicate" Sam ples ..................................................................................

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

A6-1 A-7 Environmental Resources Associates, Crosscheck Program Results (EML study replacement)

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

A7-1 Attachment A: Acceptance criteria for spiked samples ...............................................

A2 Appendix C C-1 Appendix E E-1 E-2 E-3 E-4 Maximum Permissible Concentrations of Radioactivity in air and water above background in unrestricted areas ....................................................................

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

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

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

E-7 Results of Analyses, Ground Water Monitoring Program ...............................................

E-9 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 pling locatio ns ...........................................................................................................

D -5 0-5 Sample collection and analysis program: Radiation Environmental Monitoring Program, 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, 2012.This Program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the Plant on its surroundings.

Tabulations of the individual analyses made during the year are not included in this report. These data are included in a reference document (Environmental, Inc., Midwest Laboratory, 2012a)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 2012 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-1 37, cerium-144, beryllium-7, and potassium-40.

The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation.

Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown.

On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen as calibration monitors and should not be considered 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 Progqram

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-1 31. 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, M-16 and one control, M-17) was added to the program in 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-131 and gamma-emitting isotopes.

In addition, pasture grass and vegetation are collected from locations M-41, M-42 and M-43 (C). The samples are analyzed for iodine-131 and other gamma emitting isotopes, as substitute for dairy sampling.Vegetables, corn and potatoes are collected annually if fields are irrigated by water in which liquid radioactive effluent has been discharged.

Analysis is done 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 prevent possible groundwater contamination due to plant operations, samples from nineteen on-site monitoring wells are collected and analyzed for tritium and gamma emitting isotopes.

The Ground Water Monitoring Program is further described in Appendix E.Quarterly collections of storm water runoff were added to monitor another possible pathway to the groundwater aquifer. The samples are also 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-131, and gamma-emitting isotopes.

Quarterly composites are analyzed for tritium.The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, 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 Procqram

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

(1) Air Particulates

/ Air Iodine: M-02. Volume for the week ending January 4, 2012 was lower than expected.

A short power outage is suspected.

No air particulate sample was collected for the week ending June 27, 2012, the filter was misaligned in the holder.M-03. No air particulate

/ air iodine sample was available for the week ending May 9, 2012, the timer reading was low due to power interruption.

No air particulate sample was collected for the week ending June 27, 2012, the filter was misaligned in the holder.No air particulate

/ air iodine sample was available for the week ending July 18, 2012, low volume due to power interruption.

M-04. No air particulate

/ air iodine sample was available for the week ending May 30, 2012, the timer reading was low due to power interruption.

M-05. No air particulate

/ air iodine sample was available for the week ending May 30, 2012, the volume was low due to power interruption.

(2) Thermoluminescent Dosimeters:

The TLD for location M-01 B was missing in the field for the first quarter, 2012.The TLD for location M-08A was missing in the field for the first quarter, 2012.The TLD for location M-1 1 A was missing in the field for the fourth quarter, 2012.(3) Surface Water: Surface water was not collected at location M-08 for the weeks ending January 25 through February 15, 2012. The water was not collected due to unsafe ice conditions.

Both the January and February monthly composite samples were made up from available collections.

(4) Well Water: Well water was not collected at location MW-27 in January, 2012. The outside well was locked and the residence was vacant.(5) Milk Milk was not available from locations M-16 and M-17 for the January through March, 2012 collections.

No milk was available after November 7, 2012.(6) Invertebrates Bottom organisms were not collected in the Spring of 2012, due to high river levels..!(7) Shoreline Sediments Shoreline sediment was not collected in the Spring of 2012, due to high river levels.Deviations from the program are summarized in Table 5.3.5

3.4 Laboratory

Procedures The iodine-131 analyses in milk and drinking water were made using a sensitive radiochemical procedure which involves separation of the iodine using an ion-exchange method and solvent extraction and subsequent beta counting.Gamma-spectroscopic analyses are performed using high-purity germanium (HPGe) detectors.

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

Tritium concentrations are determined by liquid scintillation.

Analytical.

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

Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Dep't of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained.

Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2012). The QA Program includes participation in Interlaboratory Comparison (crosscheck)

Programs.

Results obtained in the crosscheck programs are presented in Appendix A.3.5 Program Modifications There were no program modifications made to the Radiological Environmental Monitoring Program (REMP) at the Monticello Nuclear Generating Plant in 2012. Additions to the Groundwater monitoring program are detailed in Appendix E.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 ft 2 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 2012 land use census was conducted between September 10 and September 14, 2012.In the SSE and NW sectors, the highest D/Q value for nearest garden increased by greater than 20%. Closer gardens were identified.

The highest D/Q locations for nearest resident and milk animal did not change from the 2011 census. The Offsite Dose Calculation Manual (ODCM) will be revised to reflect the sector changes.The location for critical receptor did not change from the 2011 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 involving significant release to the environment at nuclear reactor facilities in 2012. The Fukushima Daiichi nuclear accident occurred March 11, 2011.There were no reported atmospheric nuclear tests in 2012. The last reported test was conducted on October 16, 1980 by the People's Republic of China.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 pCi/g for Cs-137. Gross beta measured in soil averaged 51.7 pCi/g .Presentday 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 Progqram

Findings Results obtained show background levels of radioactivity in environmental samples collected outside of the Site Protected Area in 2012. 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 (16.2 and 15.5 mRem/91 days, respectively).

The mean for special interest locations was 14.1 mRem/91 days and the mean for the control locations was 15.5 mRem/91 days. Dose rates measured at the inner and outer ring locations were similar to those observed from 1997 through 2011 and are tabulated below. No plant effect on ambient gamma radiation is indicated (Figure 5-1).Year Inner Ring Outer Rin~q Dose rate (mRem/91 days)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 15.9 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 2011 14.8 14.3 2012 16.2 15.5 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 almost identical at 3 both indicator and control locations (0.032 and 0.031 pCi/m ,respectively), similar to levels observed from 1997 through 2011. The results are tabulated below.Year Indicators Control 3 Concentration (pCi/m 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 2011 0.029 0.027 2012 0.032 0.031 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 1997 through 2012.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 radiation3(Arnold and AI-Salih, 1955) was detected in all samples, with an average activity of 0.066 pCi/m for all locations.

All other gammaemitting isotopes were below their respective LLD limits.Airborne Iodine Weekly levels of airborne iodine-1 31 were below the lower limit of detection (LLD) of 0.03 pCi/m 3 in all samples.9 River Water and Drinkina Water Tritium activity measured below 500 pCi/L in all samples. Gross beta activity in Minneapolis drinking water averaged 2.4 pCi/L and was similar to average levels observed from 1997 through 2011. Gross beta averages are tabulated below.Year Gross Beta (pCi/L) Year Gross Beta (pCi/L)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 2003 3.0 2011 2.2 2004 2.7 2012 2.4 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 500 pCi/L for all samples.Gamma isotopic results were below detection limits.The data for 2012 were consistent with previous years results and no plant operational effects were indicated.

Goat Milk Iodine-131 activity measured below the detection limit of 0.5 pCi/L for all samples. No gamma-emitting isotopes, excepting naturally-occurring potassium-40, were detected.In summary, the data for 2012 showed no radiological effects of the plant operation.

Pasture Grass Pasture grass was collected in July, August and September, 2012. Iodine-131 concentrations measured below 0.044 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.10 Crops A vegetation collection was not required for 2012. No crops, within five miles of the plant, were found using irrigation water from the Mississippi River.Fish Fish were collected in May and October. Flesh was separated from the bones and analyzed by gamma spectroscopy.

Only naturally-occurring potassium-40 was found in the upstream and downstream samples (3.36 and 3.34 pCi/g wet weight, respectively).

Other gamma-emitting isotopes remained below detection limits. There was no indication of a plant effect.Invertebrates Samples were collected in September of 2012, and analyzed by gamma spectroscopy.

All gamma-emitting isotopes were below detection limits. There was no indication of any plant effect.Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment collections were made in September of 2012 and analyzed for gamma-emitting isotopes.

High water prevented a May collection.

A low level of cesium-1 37 was detected in one downstream sample (M-15), at a concentration of 0.081 pCi/g dry weight. Similar levels of activity and distribution have been observed since 1978, and are indicative of the influence of fallout deposition.

Naturally-occurring beryllium-7 and potassium-40 were also detected.

There was no indication of a plant effect.Ground Water Monitoring Program Monitoring Wells (on-site)Measurable tritium above 500 pCi/L was detected in 8 of 172 samples collected from the nineteen on-site monitoring wells. The activities ranged from 507 to 3,044 pCi/L, similar to concentrations seen in 2010 and 2011. The highest activities were observed at well MW-1 3A.Gamma isotopic measurements were below detection limits.Stormwater Run-off (on-site)Tritium activity was detected in one of the six stormwater runoff samples submitted for analysis in 2012 and measured 4,479 pCi/L. Gamma isotopic results were below detection limits.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 c Ambient radiation 40 M-01A- M-14A, M-01B -M-16B C/Q Ambient gamma (TLDs) M-01S -M-06S, M-01C -M-04C Airborne Particulates 5 M-1(C), M-2, M-3, M-4, M-5 C/W GB, GS (QC of each location)Airborne Iodine 5 M-1(C), M-2, M-3, M-4, M-5 C/W 1-131 Milk 2 M-16, M-17 (C) G/M 1-131, GS Pasture grass, Vegetation d 3 M-41, M-42, M-43(C) 3x/year GS Surface water 2 M-8(C), M-9 G/W GS(MC), H-3(QC)Drinking water 1 M-14 G/W GB(MC), 1-131(MC)GS (MC), H-3 (QC)Well water 4 M-11, M-12, M-27, M-43(C) G/Q H-3, GS On-site monitoring wells 5 M-36 to M-40 G/Q H-3, GS 19 M-33 to M-35, M-44 to M-54 G/M H-3, GS Edible cultivated crops e Leafy Vegetable 2 M-27, Available Producer (C) G/A 1-131 Corn 1 M-19 G/A GS Potatoes 1 M-21 G/A GS Fish 2 M-8(C), M-9 G/SA GS (one species, edible portion)Periphyton or invertebrates 2 M-8(C), M-9 G/SA GS Shoreline sediment 3 M-8(C), M-9, M-15 G/SA GS 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.

d 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 a Collection Site Sample Type 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-1 5 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 M-53 M-54 C Air Station M-1 Air Station M-2.Air Station M-3 Air Station M-4 Air Station M-5 C Upstream of Plant Intake Downstream of Plant Discharge C Campbell Farm City of Monticello Plant Well #1 City of Minneapolis Montissippi Park Kitzman Farm C Greninger Farm River Irrigated Corn Field River Irrigated Potato Field C Wise residence (Highest D/Q Garden) c a. Available Producer c 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 C Imholte Farm Monitoring Well #9 Monitoring Well #10 Monitoring Well #11 Monitoring Well #12A Monitoring Well #12B Monitoring Well #13A Monitoring Well #13B MonitoringWell

9B Monitoring Well #14 Monitoring Well #15A Monitoring Well #15B Storm water Runoff AP, Al AP, Al AP, Al AP, Al AP, Al SW, SS, BO, F SW, SS, BO, F WW WW WW DW SS M M VE VE VE, WW VE WW WW WW WW WW WW WW WW VE VE VE, WW WW 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 0/SE< 1000' upstream< 1000' downstream 10.6 mi @ 357°/N 3.3 mi @ 127°/SE 0.26 mi @ 252°/WSW 37.0 mi @ 132 0/SE 1.27 mi @ 114°/ESE 3.0 mi @ 165 0/SSE 7.8 mi @ 250°/WSW.0.64 mi @ 207°/SSW> 10.0 mi.593- @ 299 0/WNW 749- @ 301 /WNW 770' @ 304 0/NW 0.1 mi @ 25°/NNE 0.1 mi @ 253 0/WSW 229- @ 228 0/SW 0.2 mi @ 66°/ENE 0.3 mi @ 150 0/SSE 0.8 mi @ 151*/SSE 0.6 mi @ 134 0/SE 12.3 mi @ 313 0/NW 0.1 mi @ 310 0/NW 0.1 mi @ 292 0 1WNW 0.1 mi @ 283°/WNW 0.1 mi @ 330°/NW 0.1 mi @ 326°/NW 0.12 mi @ 316 0/NW 0.12 mi @ 316"/NW 0.1 mi @ 310°/NW 0.17 mi @ 306°/NW 751'@ 14°/NNE 750- @ 14 0/NNE 0.1 mi @ 27"/NE 14 Table 5.2. Sampling locations, Monticello Nuclear Generating Plant.Distance and Code Typea Collection Site Sample TypeD 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 1NE 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-10B 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 Type" 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°/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-01C 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 @ 226°/ 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 I-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 MOIC"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 6.3. MISSED COLLECTIONS AND ANALYSES All required samples were collected and analyzed as scheduled with the following exceptions:

Collection Reason for not Sample Analysis Location (s) Date or conducting REMP Plans for Preventing Type Period as required Recurrence AP/AI Beta, 1-131 M-2 1/4/2012 Low sample volume. Short power Power restored.outage suspected.

AP/AI Beta, 1-131 M-3 5/9/2012 Low timer reading, possible power failure Power restored.AP/AI Beta, 1-131 M-3, M-4, M-5 5/30/2012 Low timer reading, power interruption.

Power restored.AP Beta, 1-131 M-2, M-3 6/27/2012 Filters misaligned in holder, Technician training no particulate accumulation.

reviewed SW For composite M-08 1/25/2012 Water frozen. None Required SW For composite M-08 2/1, 2/8, Water frozen. None Required 2/15, 2012 SW For composite M-08 12/15/2012 Water frozen. None Required WW Gamma, H-3 M-27 1/18/2012 Outside well locked; residence vacant. None Required WW Gamma, H-3 MW-14 10/17/2012 Well not collected.

Well contents frozen.MI Gamma, 1-131 M-16, 17 1/31/2012 Milking discontinued until Spring. None Required MI Gamma, 1-131 M-16, 17 12/31/2012 Milking discontinued for the year. None Required TLD Gamma M-1B, M-8A 1st Qtr. 2012 TLD missing in field. Replaced, vandalism TLD Gamma M-11A 4th Qtr. 2012 TLD missing in field. Replaced, vandalism BO Gamma M-8, M-9 Spring High water prevented sampling.

None Required SS Gamma M-8, M-9 Spring High water prevented sampling.

None Required 17 Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.0.035 0.033 0.031 0.029 0.027 0.025 0.023 C.0.021 0.019 0.017 0.015 0) ) 0 C) C) C) C) C, C)- C) C) -(C) C:)) 0 0 0 0D 0 0: 0) a 0: 0 0 04 C( 4 04 (N 4 (N I (N j ( V ( j ( I ( N (j C14 19 Figure 5-1. Offsite Ambient Radiation (TLDs); Inner Ring versus Outer Ring locations.

20 19 18 17 16 15 Co 14 E 13 12 11 10 r- 0 0) Co C1 N CY) 'I LOl (0 1--0) M M 0) 0 CD 0 D 0 > 0 : 0 C0 0) 0)) 0) 0: 0C0 0 0 0) 0 C14 --N N N N N Nl N C) C) 0N 0 0 -.-0 0 04 0 0 18 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, 2012 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse Direct Radiation TLD (Inner Ring, Gamma 54 3.0 16.2 (54/54) M-11A, County Rd 75, 17.8 (3/3) (See Control 0 General Area at (121-19.1) 0.4 mi @ 250°/WSW (17.0-18.3) below.)Site Boundary)mRem/91 days)TLD (Outer Ring, Gamma 63 3.0 15.5 (63/63) M-09B, Weinand Farm 17.2 (4/4) (See Control 0 4-5 mi. distant) (12.1-18.3) 4.7 mi @ 180°/S (15.9-18.3) below.)mRem/91 days)TLD (Special Gamma 24 3.0 15.0 (24/24) M-06S, Mont. Pub. Wks. 17.6 (4/4) (See Control 0 Interest Areas) (11.9-17.9) 2.7 mi @ 136°/SE (17.2-17.9) below.)mRem/91 days)TLD (Control)

Gamma 16 3.0 None M-03C, Rte. 19 & Jason, 18.2 (4/4) 16.9 (16/16) 0 mRem/91 days) 11.6 mi @ 130°/SE (17.3-18.7)

(15.5-18.7)

Airborne Pathway Airborne GB 259 0.002 0.032 (206/206)

M-4, Air Station 0.033 (52/52) 0.031 (53/53) 0 Particulates (0.011-0.087) 0.8 mi @ 147°/SSE (0.013-0.087)

(0.011-0.097)(pCi/m 3)GS 20 Be-7 0.015 0.066 (16/16) M-4, Air Station 0.068 (4/4) 0.064 (4/4) 0 (0.042-0.100) 0.8 mi @ 147°/SSE (0.046-0.091)

(0.041-0.094)

Mn-54 0.0009 < LLD < LLD 0 Co-58 0.0007 < LLD < LLD 0 Co-60 0.0009 < LLD < LLD 0 Zn-65 0.0015 < LLD -< LLD 0 Zr-Nb-95 0.0013 < LLD -< LLD 0 Ru-103 0.0011 < LLD -< LLD 0 Ru-.1 06 0.0068 < LLD -< LLD 0 Cs-134 0.0008 < LLD -< LLD 0 Cs-137 0.0008 < LLD -< LLD 0 Ba-La-140 0.0022 < LLD -< LLD 0 Ce-141 0.0014 < LLD < LLD 0 Ce-144 0.0045 < LLD < LLD 0 Airborne Iodine 1-131 259 0.03 < LLD < LLD 0 (pCi/m 3)20 Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Monticello Nuclear Location of Facility Wright, Minnesota Generating Plant Docket No. 50-263 Reporting Period January-December, 2012 ( County, State )Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD b Mean (F)c Mean (F)c Mean (F)' Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse Waterborne Pathway River Water (pCi/L) H-3 8 500 < LLD < LLD 0 GS 24 Mn-54 10 < LLD < LLD 0 Fe-59 30 < LLD < LLD 0 Co-58 10 < LLD --< LLD 0 Co-60 10 < LLD --< LLD 0 Zn-65 30 < LLD --< LLD 0 Zr-Nb-95 15 < LLD --< LLD 0 Cs-134 10 < LLD --< LLD 0 Cs-137 10 < LLD --< LLD 0 Ba-La-140 15 < LLD --< LLD 0 Ce-144 31 < LLD --< LLD 0 Drinking Water GB 12 1.0 2.4 (11/12) M-14, Minneapolis 2.4 (11/12) None 0 (pCi/L) (2.0-3.1) 37.0 mi. @ 1320 /SE (2.0-3.1)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 36 < LLD --None 0 Well Water H-3 15 500 .< LLD --< LLD 0 (pCi/L) GS 15 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 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. 50-263 Reporting Period January-December, 2012 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse Waterborne Pathway Invertebrates GS 2 (pCi/g wet) Be-7 0.58 < LLD < LLD 0 K-40 1.08 < LLD -< LLD 0 Mn-54 0.051 < LLD -< LLD 0 Fe-59 0.17 < LLD -- < LLD 0 Co-58 0.072 < LLD -< LLD 0 Co-60 0.052 < LLD -< LLD 0 Zn-65 0.097 < LLD -< LLD 0 Zr-Nb-95 0.12 < LLD -< LLD 0 Ru-103 0.091 < LLD -< LLD 0 Ru-106 0.39 < LLD -< LLD 0 Cs-1 34 0.046 < LLD -< LLD 0 Cs-137 0.055 < LLD -< LLD 0 Ba-La-140 0.39 < LLD -< LLD 0 Ce-144 0.30 < LLD -< LLD 0 Shoreline GS 3 Sediments Be-7 0.18 0.71 (2/2) M-15, Montissippi Park 1.09(1/1)

< LLD 0 (pCi/g dry) (0.33-1.09) 1.27 mi @ 114°/ESE K-40 0.10 9.84(2/2)

M-15, Montissippi Park 10.82 (1/1) 10.02(1/1) 0 (8.85-10.82) 1.27 mi @ 114°/ESE Mn-54 0.020 < LLD -< LLD 0 Fe-59 0.042 < LLD -< LLD 0 Co-58 0.026 < LLD -< LLD 0 Co-60 0.016 < LLD -< LLD 0 Zn-65 0.035 < LLD --< LLD 0 Nb-95 0.032 < LLD --< LLD 0 Zr-95 0.023 < LLD --< LLD 0 Ru-103 0.027 < LLD --< LLD 0 Ru-106 0.14 < LLD --< LLD 0 Cs-134 0.014 < LLD --< LLD 0 Cs-137 0.014 0.081 (1/2) M-15, Montissippi Park 0.081 (1/1) < LLD 0 1.27 mi @ 114°/ESE Ba-La-140 0.059 < LLD -< LLD 0 Ce-144 0.12 < LLD < LLD 0 22 Table 5.4 Radiological Environmental 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, 2012 Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)A Mean (F)M Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse Ingestion Pathway Milk (pCi/L) 1-131 30 0.5 < LLD -< LLD 0 GS 30 K-40 200 1816 (15/15) M-16, Kitzman 1816 (15 /15) 1771 (15/15) 0 (1436-1982) 3.0 mi @ 165°/SSE (1436-1982)

(1512-2082)

Cs-134 5 < LLD -< LLD 0 Cs-137 5 < LLD -< LLD 0 Ba-La-140 5 < LLD -< LLD 0 Vegetation GS 9 (Pasture Grass, Mn-54 0.011 < LLD -< LLD 0 Weeds, Leaves) Fe-59 0.031 < LLD -< LLD 0 Co-58 0.010 < LLD -< LLD 0 (pCi/gwet)

Co-60 0.012 < LLD -< LLD 0 Zn-65 0.030 < LLD -< LLD 0 Nb-95 0.014 < LLD -< LLD 0 1-131 0.044 < LLD -< LLD 0 Cs-134 0.010 < LLD -< LLD 0 Cs-137 0.014 < LLD -< LLD 0 Fish GS 6 (pCi/g wet) K-40 0.10 3.34(3/3)

M-08, Upstream 3.36 (3/3) 3.36 (3/3) 0 (3.02-3.58)

< 1000' of discharge (3.24-3.51)

(3.24-3.51)

Mn-54 0.018 < LLD < LLD 0 Fe-59 0.055 < LLD -< LLD 0 Co-58 0.023 < LLD --< LLD 0 Co-60 0.013 < LLD --< LLD 0 Zn-65 0.037 < LLD --< LLD 0 Zr-Nb-95 0.027 < LLD --< LLD 0 Cs-134 0.018 < LLD --< LLD 0 Cs-137 0.015 < LLD --< LLD 0 Ba-La-140 0.043 < LLD --< LLD 0 Ce-144 0.11 < LLD --< LLD 0 GB = gross beta, GS = gamma scan.b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).d Locationsare specified:

(1) by name, and/or station code 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 2013a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2012.2001b through 2013b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -December, 2000 through 2012.1984a 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 GeneratingPlant, 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. 3, 14 November 2012.2009. 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-520/5-84-006).

__ 2009. 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 2012. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2011. Minneapolis, Minnesota.

2009 to 2012. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2011.Minneapolis, Minnesota.

25

A LTI0 Environmental, Inc.Midwest Laboratory 700 Landwehr Road .Northbrook.

IL 60062-2310 phone (847) 564-0700 -lax (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, 2012 through December, 2012 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 < 100 pCi/liter 5.0 pCi/liter> 100 pCi/liter 5% of known value Tritium < 4,000 pCi/liter

+/- Ia =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/iiter Nickel-63b

> 35 pCi/liter 15% of known value Technetium-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter> 100 pCi/liter 10% of known value Other Analyses b 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limit.A2 TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.Concentration (pCi/L)Lab Code Date Analysis Laboratory ERA Control Result b Result Limits Acceptance ERW-1783 04/09/12 Sr-89 ERW-1 783 04/09/12 Sr-90 ERW-1786 ERW-1786 ERW-1786 ERW-1 786 ERW-1786 ERW-1789 ERW-1 789 d ERW-1795 ERW-1 795 ERW-1795 04/09/12 04/09/12 04/09/12 04/09/12 04/09/12 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 04/09/12 Gr. Alpha 04/09/12 Gr. Beta 04/09/12 04/09/12 04/09/12 Ra-226 Ra-228 Uranium 62.2 +/- 6.0 33.7 +/- 2.1 75.7 +/- 4.1 71.9 +/- 4.0 70.0 +/- 4.3 151.5 +/- 6.1 108.3 +/- 89.0 55.0 +/- 2.4 76.2 +/- 1.8 6.4 +/- 0.4 5.4 +/- 1.2 56.2 +/- 2.6 16023 +/-355 41.5 +/- 4.1 19.7 +/- 1.6 82.7 +/- 4.4 77.2 +/- 3.7 74.4 +/- 1.5 183.0 +/- 6.2 211.0 +/- 9.9 82.3 72.9 74.2 155.0 105.0 62.9 44.2 5.7 4.6 61.5 58.5 37.4 46.9 -66.3 27.4 -43.1 69.1 -90.5 65.6 -82.6 60.6-81.6 140.0 -172.0 94.5 -125.0 33.0 -78.0 29.6 -51.5 4.3 -6.9 2.7 -6.3 50.0 -68.2 ERW-1798 04/09/12 H-3 ERW-6283 10/05/12 Sr-89 ERW-6283 10/05/12 Sr-90 15800 13800 -17400 Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Fail Pass ERW-6286 ERW-6286 ERW-6286 ERW-6286 ERW-6286 10/05/12 10/05/12 10/05/12 10/05/12 10/05/12 Ba-133 Co-60 Cs-134 Cs-137 Zn-65 39.1 20.1 84.8..78.3 76.6 183.0 204.0 29.7 -46.1 14.4 -23.8 71.3 -93.3 70.5 -88.5 62.6 -84.3 165.0 -203.0 184.0 -240.0 30.6 -72.9 26.0 -46.7 20.6 -29.4 11.2 -17.2 2.7 -6.2 50.8 -69.3 ERW-6288 10/05/12 Gr. Alpha 47.0 +/- 2.3 ERW-6288 10/05/12 Gr. Beta 33.4 +/- 1.2 ERW-6290 10/05/12 ERW-6295 e ERW-6295 e ERW-6295 10/05/12 10/05/12 10/05/12 1-131 Ra-226 Ra-228 Uranium 23.3 +/- 1.0 17.5 +/- 0.7 7.4 +/- 1.5 61.2 +/- 1.8 58.6 39.2 24.8 15.0 4.6 62.5 a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).b Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.

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

A new dilution was prepared and the sample reanalyzed.

Result of reanalysis, 38.3 +/- 1.3 pCi/L.e Results of reanalyses (pCi/L): Ra-226, 16.51 +/- 0.73 Ra-228, 4.85 +/- 1.11. A new test was ordered from Environmental Resources Associates, results will be updated for first quarter, 2013.Al-1 TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaSO 4: Dy Cards).mR Lab Code Date Known Lab Result Control Description Value + 2 sigma Limits Acceptance Environmental, Inc.2012-1 2012-1 2012-1 2012-1 2012-1 2012-1 2012-1 2012-1 2012-1 2012-1 2012-1 2012-1 2/7/2012 2/7/2012 2/7/2012 2/7/2012 2/7/2012 2/7/2012 2/7/2012 2/7/2012 2/7/2012 2/7/2012 2/7/2012 2/7/2012 30 cm.40 cm.50 cm.70 cm.75 cm.80 cm.90 cm.100 cm.110 cm.120 cm.150 cm.180 cm.74.87 42.12 26.95 13.75 11.98 10.53 8.32 6.74 5.57 4.68 2.99 2.08 87.22 53.70 33.04 13.26 13.38 11.27 7.79 5.91 4.63 3.96 2.41 2.02+/- 2.86+/- 4.53+/- 1.96+/- 1.15+/- 1.68+/- 0.95+/- 0.83+/- 0.25+/- 0.83+/- 1.68+/- 0.08+/- 0.25 52.41 -97.33 29.48 -54.76 18.87 -35.04 9.63 -17.88 8.39 -15.57 7.37 -13.69 5.82 -10.82 4.72 -8.76 3.90 -7.24 3.28 -6.08 2.09 -3.89 1.46 -2.70 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Environmental, Inc.2012-2 2012-2 2012-2 2012-2 2012-2 2012-2 2012-2 2012-2 2012-2 2012-2 2012-2 9/11/2012 9/11/2012 9/11/2012 9/11/2012 9/11/2012 9/11/2012 9/11/2012 9/11/2012 9/11/2012 9/11/2012 9/11/2012 40 cm.50 cm.60 cm.70 cm.80 cm.90 cm.100 cm.110 cm.120 cm.150 cm.180 cm.33.75 21.6 15 11.02 8.44 6.67 5.4 4.46 3.75 2.4 1.67 43.74 +/- 1.31 25.37 +/- 0.82 16.63 +/- 0.45 10.58 +/- 0.20 8.55 +/- 1.18 5.75 +/- 0.33 4.44 +/- 0.22 3.85 +/- 0.05 3.03 +/- 0.71 1.82 +/- 0.10 1.19 +/- 0.34 23.63 -43.88 15.12 -28.08 10.50 -19.50 7.71 -14.33 5.91 -10.97 4.67 -8.67 3.78 -7.02 3.12 -5.80 2.63 -4.88 1.68 -3.12 1.17 -2.17 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A2-1 TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPW-41824 W-22712 W-22712 SPAP-I032 SPAP-1032 SPAP-1034 SPW-1036 SPW-1036 SPW-1036 SPMI-1038 SPM1-1038 SPW-1045 SPW-1047 SPW-1049 W-31412 SPW-1520 SPW-41825 WW-1547 WW-1547 WW-1 547 W-51712 W-61112 W-61112 SPAP-4418 SPAP-4420 SPAP-4420 SPMI-4422 SPMI-4422 SPMI-4422 SPMI-4422 SPW-4424 SPW-4424 SPW-4424 SPF-4426 SPF-4426 SPW-4428 SPW-4430 SPW-4432 W-81712 SPW-5407 SPW-18022 2/15/2012 2/27/2012 2/27/2012 315/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/14/2012 3/23/2012 4/10/2012 4/16/2012 4/16/2012 4/16/2012 5/17/2012 6/11/2012 6/11/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 8/17/2012 8/29/2012 9/10/2012 Ra-228 Gr. Alpha Gr. Alpha Cs-1 34 Cs-1 37 Gr. Beta Cs-134 Cs-137 Sr-90 Cs-134 Cs-137 H-3 Ni-63 C-14 Ra-226 U-238 Ra-228 Ba-1 33 Cs-1 34 Cs-137 Ra-226 Gr. Alpha Gr. Beta Gr. Beta Cs-134 Cs-137 Co-60 Cs-1 34 Cs-1 37 Sr-90 Co-60 Cs-137 Sr-90 Cs-134 Cs-137 C-14 H-3 Ni-63 Ra-226 U-238 Ra-228 24.85.+/- 2.14 14.59 +/- 0.34 43.57 +/- 0.40 7.06 +/- 1.71 102.63 +/- 3.13 44.30 +/- 0.11 43.23 +/- 3.84 57.44 +/- 4.60 60.51 +/- 1.93 37.79 +/- 4.06 54.75 +/- 5.09 68022 +/- 746 217.10 +/- 3.64 3858.90 +/- 12.79 13.13 +/- 0.36 45.67 +/- 2.02 28.48 +/- 2.51 18.99 +/- 4.67 9.28 +/- 2.82 27.77 +/- 4.49 17.29 +/- 0.43 22.16 +/- 0.45 43.57 +/- 0.40 43.74 +/- 0.11 4.54 +/- 0.73 104.70 +/- 2.77 31.43 +/- 2.12 16.50 +/- 1.17 29.60 +/- 2.61 31.60 +/- 1.35 38.52 +/- 1.76 33.23 +/- 2.27 36.56 +/- 1..58 947.50 +/- 42.50 2692.00 +/- 62.40 4325.70 +/- 15.80 70119.40 +/- 773.40 187.20 +/- 3.85 14.94 +/- 0.40 42.95 +/- 0.11 29.03 +/- 2.80 28.75 20.00 41.70 5.26 104.24 46.88 39.42 52.12 61.52 39.42 52.12 69048 206.64 4738.80 16.70 41.70 28.35 26.70 8.68 29.70 16.70 20.00 45.20 46.50 4.60 103.30 31.62 16.15 26.64 30.47 37.95 32.01 40.60 1025.00 2480.00 4738.80 67570.00 206.80 16.70 41.70 28.21 20.13 -37.38 10.00- 30.60 20.85 -62.55 0.00 -15.26 93.82 -114.66 28.13 -65.63 29.42 -49.42 42.12 -62.12 49.22 -73.82 29.42 -49.42 42.12 -62.12 55238 -82858 144.65 -268.63 2843.28 -6634.32 11.69 -21.71 29.19 -54.21 19.85 -36.86, 16.70 -36.70 0.00 -18.68 19.70 -39.70 11.69 -21.71 10.00 -30.00 35.20 -55.20 27.90 -65.10 2.76 -6.44 92.97 -113.63 21.62 -41.62 6.15 -26.15 16.64 -36.64 24.38 -36.56 27.95 -47.95 22.01 -42.01 32.48 -48.72 922.50 -1127.50 2232.00 -2728.00 2843.28 -6634.32 54056.00 -81084.00 144.76 -268.84 11.69 -21.71 29.19 -54.21 19.75 -36.67 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 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 "Spiked" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n1l c Activity Limnits d Acceptance W-91012 W-91012 W-100312 W-100312 W-101812 ESO-7235 SPW-7753 SPW-18023 9/10/2012 Gr. Alpha 9/10/2012 Gr. Beta 10/3/2012 10/3/2012 10/18/2012 12/6/2012 12/6/2012 12/18/2012 Gr. Alpha Gr. Beta Ra-226 Sr-90 U-238 Ra-228 19.95 +/- 0.42 43.47 +/- 0.40 19.95 +/- 0.41 44.21 +/- 0.40 18.80 +/- 0.43 138.79 +/- 2.67 45.55 +/- 5.05 31.59 +/- 2.99 20.00 45.20 20.00 45.20 16.70 161.05 41.70 25.98 10.00 -30.00 35.20 -55.20 10.00 -30.00 35.20 -55.20 11.69 -21.71 128.84 -193.26 29.19 -54.21 18.19 -33.77 Pass Pass Pass Pass Pass Pass Pass Pass a Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/m 3), and solid samples (pCi/g).b Laboratory codes : W (Water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).c Results are based on single determinations.

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

Criteria (4.66 a)SPW-41814 W-22712 W-22712 SPAP-1031 SPAP-1031 SPAP-1033 SPW-1035 SPW-1035 SPW-1035 SPW-1035 SPM1-1037 SPMI-1037 SPMI-1037 SPW-1044 SPW-1046 SPW-1048 SPW-1166 W-31412 SPW-1 521 W-51712 W-61112 W-61112 SPW-41815 SPAP-4417 SPMI-4421 SPMI-4421 SPMI-4421 SPMI-4421 SPW-4423 SPW-4423 SPW-4423 SPW-4423 SPF-4425 SPF-4425 SPF-4425 SPW-4427 SPW-4431 W-81712 SPW-5408 Water Water Water Air Filter Air Filter Air Filter Water Water Water Water Milk Milk Milk Water Water Water water Water Water Water Water Water Water Air Filter Milk Milk Milk Milk Water Water Water water Fish Fish Fish Water Water Water Water 2/15/2012 2/27/2012 2/27/2012 3/5/2012 3/5/2012 3/512012 3/5/2012 3/5/2012 3/5/2012 3/5/2012.3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/5/2012 3/9/2012 3/14/2012 3/23/2012 4/24/2012 6/11/2012 6/11/2012 7/7/2011 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 7/25/2012 8/17/2012 8/29/2012 Ra-228 Gr. Alpha Gr. Beta Cs-134 Cs-137 Gr. Beta Cs-1 34 Cs-137 1-131(G)Sr-90 Cs-134 Cs-137 1-131(G)H-3 Ni-63 C-14 C-14 Ra-226 U-238 Ra-226 Gr. Alpha Gr. Beta Ra-228 Gr. Beta Co-60 Cs-134 Cs-137 Sr-90 Co-60 Cs-134 Cs-137 Sr-90 Co-60 Cs-134 Cs-137 C-14 Ni-63 Ra-226 U-238 0.65 0.42 0.74 1.89 1.16 0.003 2.40 2.88 2.35 0.60 2.85 3.73 3.24 146.10 19.07 5.70 6.79 0.034 0.10 0.04 0.47 0.71 0.77 0.001 4.29 3.58 4.60 0.45 1.88 2.38 2.80 0.45 6.74 7.47 9.62.10.93 19.00 0.038 0.039 0.49 +/- 0.36-0.04 +/- 0.29-0.54 +/- 0.50 0.013 +/- 0.003-0.11 +/- 0.26 37.10 +/- 74.40 8.30 +/- 11.79 2.99 +/- 3.04 1.11 0.043 +/- 0.027 0.09 +/- 0.11 0.04 +/- 0.03-0.14 +/- 0.32 0.29 +/- 0.51 0.52 +/- 0.42 0.021 +/- 0.003 0.53 +/- 0.27 0.08 +/- 0.22 3.54 +/- 5.84 5.50 +/- 11.70 0.035 +/- 0.030 0.015 +/- 0.057 2 1 3.2 100 100 0.01 10 10 20 1 10 10 20 200 20 200 200 1 1 1 1 3.2 2 0.01 10 10 10 I 10 10 10 1 100 100 100 200 20 1 1 A4-1 TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date Analysis' Laboratory results (4.66o) Acceptance Type LLD Activityc Criteria (4.66 a)SPW-18032 W-91012 W-91012 W-100312 W-100312 W-101812 SPW-7754 SPW-18033 Water Water Water Water Water Water Water Water 9/10/2012 9/10/2012 9/10/2012 10/3/2012 10/3/2012 10/18/2012 12/6/2012 12/18/2012 Ra-228 Gr. Alpha Gr. Beta Gr. Beta Gr. Beta Ra-226 U-238 Ra-228 0.78 0.42 0.75 0.77 0.43 0.04 0.10 0.98 0.85 +/- 0.46 0.027 +/- 0.29-0.13 +/- 0.52-0.32 +/- 0.53 0.06 +/- 0.30 0.04 +/- 0.03 0.02 +/- 0.08 0.43 +/- 0.50 2 1 3.2.3.2 3.2 1 1 2 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 P-9133, 9134 U-302, 303 S-386, 387 S-386,387 S-386, 387 S-386, 387 S-386, 387 WW-619,620 MI-702, 703 WW-892, 893 S-850, 851 S-850,851 W-1251, 1252 W-1251, 1252 W-1251, 1252 W-1251, 1252 AP-1209, 1210 XWW-1564, 1565 SG-1438, 1439 SG-1438, 1439 WW-1585, 1586 AP-2103, 2104 AP-2166, 2167 AP-1632, 1633 E-1653, 1654 E-1653, 1654 SG-1677, 1678 SG-1677, 1678 SWU-1719, 1720 W-1698, 1699 W-1698, 1699 W-1698, 1699 SG-1761, 1762 SG-1761, 1762 AP-2019, 2020 DW-2272, 2273 DW-2356, 2357 1/3/2012 1/3/2012 1/3/2012 1/3/2012 1/17/2012 1/23/2012 1/23/2012 1/23/2012 1/23/2012 1/23/2012 1/31/2012 2/6/2012 2/17/2012 2/22/2012 2/22/2012 3/6/2012 3/6/2012 3/6/2012 3/6/2012 3/8/2012 3/14/2012 3/19/2012 3/19/2012 3/19/2012 3/28/2012 3/28/2012 3/29/2012 4/2/2012 4/2/2012 4/2/2012 4/2/2012 4/3/2012 4/5/2012 4/5/2012 4/5/2012 4/10/2012 4/10/2012 4/12/2012 4/20/2012 4/24/2012 Gr. Beta K-40 Sr-90 H-3 Beta (-K40)Ac-228 Bi-214 Pb-214 TI-208 U-235 H-3 K-40 Gr. Beta Cs-134 Cs-137 Gr. Alpha Gr. Beta H-3 Tc-99 Be-7 H-3 Ac-228 Pb-214 H-3 Be-7 Be-7 Gr. Beta K-40 Ac-228 Pb-214 Gr. Beta Gr. Beta Ra-226 Ra-228 Ac-228 Pb-214 Be-7 1-131 Gr. Beta 14.50 12.88 0.01 108.86 6.84 0.77 0.80 0.74 0.21 0.05 257.20 1337.00 3.46 0.14 0.21 1.20 16.86 5235.52 19.67 0.24 308.00 6.01 4.69 3124.50+/- 0.29+/- 0.55+/- 0.01+/- 83.03+/- 2.91+/- 0.11+/- 0.07+/- 0.06+/- 0.02+/- 0.02+/- 86.00+/- 123.00+/- 0.56+/- 0.02+/- 0.03+/- 0.62+/- 1.43+/- 230.91+/- 3.60+/- 0.12+/- 88.00+/- 0.30+/- 0.49+/- 176.96 15.02 +/- 0.30.12.40 +/- 0.53 0.01 +/- 0.01 206.60 +/- 86.38 5.24 +/- 2.56 0.79 +/- 0.14 0.73 +/- 0.11 0.75 +/- 0.11 0.21 +/- 0.04 0.12 +/- 0.05 305.80 +/- 88.30 1460.40 +/- 102.00 3.77 +/- 0.59 0.13 +/- 0.02 0.22 +/- 0.03 1.27 +/- 0.92 15.14 +/- 1.34 4893.24 +/- 224.55 14.46 +/- 3.51 0.20 +/- 0.11 293.00 +/- 87.00 6.23 +/- 0.31 5.20 +/- 0.54 2982.38 +/- 173.62 0.076 +/- 0.013_ .0.Q7_1__0.01.6_

0.24 + 0.12 1.55 + 0.04 1.36 +/- 0.14 6.49 +/- 0.33 5.07 +/- 0.14 1.53 +/- 0.44 9.42 +/- 1.32 0.67 +/- 0.18 1.48 +/- 0.74 16.55 +/- 0.44 15.40 + 1.56 0.17 +/- 0.08 0.49 +/- 0.27 9.47 + 1.74 14.76 +/- 0.21 12.64 +/- 0.38 0.01 +/- 0.00 157.73 +/- 59.91 6.04 +/- 1.94 0.78 +/- 0.09 0.77 +/- 0.07 0.75 +/- 0.06 0.21 +/- 0.02 0.09 +/- 0.03 281.50 +/- 61.63 1398.70 +/- 79.90 3.61 +/- 0.41 0.14 +/- 0.01 0.22 +/- 0.02 1.24 +/- 0.55 16.00 +/- 0.98 5064.38 +/- 161.05 17.07 +/- 2.51 0.22 +/- 0.08 300.50 +/- 61.87 6.12 +/- 0.22 4.95 +/- 0.36 3053.44 +/- 123.96 0.078 +/- 0.010-.0.066-+/--0.0_1.3 0.25 +/- 0.08 1.54 +/- 0.03 1.35 +/- 0.10 6.56 +/- 0.25 4.92 +/- 0.11 1.35 +/- 0.30 10.14 +/- 1.00 0.54 +/- 0.12 1.47 +/- 0.53 16.41 +/- 0.34 14.78 +/- 1.06 0.17 +/- 0.07 0.51 +/- 0.18 11.14 +/- 1.33 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass-Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 0.080 _ 0.016____o.06_1_++/-0.02o 0.26 +/- 0.12 1.53 +/- 0.05 1.34 +/- 0.13 6.63 +/- 0.37 4.77 +/- 0.16 1.16 +/- 0.41 10.86 +/- 1.49 0.41 +/- 0.15 1.46 +/- 0.76 16.26 +/- 0.53 14.16 +/- 1.44 0.17 +/- 0.10 0.52 +/- 0.24 12.82 +/- 2.01 A5-1 TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance G-2403,2404 G-2403,2404 BS-2445, 2446 BS-2445, 2446 SWU-2550, 2551 WW-2614,2615 WW-2614, 2615 BS-2656, 2657 BS-2656, 2657 SO-2635, 2636 SO-2635, 2636 MI-2677, 2678 VE-2719, 2720 SWU-3221, 3222 SWU-3221, 3222 WW-3073, 3074 AP-2968, 2969 F-3031, 3032 F-3031, 3032 G-3094,3095 F-3412, 3413 F-3412, 3413 MI-3067, 3068 SO-3305, 3306 SO-3305, 3306 SO-3305, 3306 LW-3454, 3455 BS-3697, 3698 BS-3697, 3698 BS-3697, 3698 VE-3798, 3799 WW-4790,4791 DW-30103, 30104 DW-30103, 30104 LW-3970, 3971 DW-3949, 3950 SG-4075, 4076 SG-4075, 4076 SG-4075, 4076 AP-4390, 4391 AP-4390, 4391 AP-4012, 4013 SW-4033, 4034 5/1/2012 5/1/2012 5/1/2012 5/1/2012 5/1/2012 5/1/2012 5/1/2012 5/2/2012 5/2/2012 5/3/2012 5/3/2012 5/7/2012 5/7/2012 5/8/2012 5/8/2012 5/14/2012 5/17/2012 5/22/2012 5/22/2012 5/23/2012 5/23/2012 5/2312012 5/24/2012 5f30/2012 5/30/2012 5/30/2012 5/31/2012 6/14/2012 6/14/2012 6/14/2012 6/20/2012 6/20/2012 6/27/2012 6/27/2012 6/28/2012 6/29/2012 7/2/2012 7/2/2012 7/2/2012 7/3/2012 7/3/2012 7/5/2012 7/5/2012 Be-7 K-40 Gr. Beta K-40 Gr. Beta Gr. Beta H-3 Cs-137 K-40 Cs-137 K-40 K-40 K-40 Gr. Beta H-3 H-3 Be-7 H-3 K-40 Gr. Beta Gr. Beta K-40 K-40 Cs-137 Gr. Beta TI-208 Gr. Beta Be-7 Cs-137 K-40 K-40 H-3 Ra-226 Ra-228 Gr. Beta 1-131 Ac-228 K-40 Pb-214 Be-7 Be-7 Be-7 H-3 1.77 +/- 0.21 6.38 +/- 0.50 8.92 +/- 1.52 5.86 +/- 0.38 2.07 +/- 0.65 2.03 +/- 1.04 750.60 +/- 106.20 0.13 +/- 0.07 10.15 +/- 0.97 0.046 +/- 0.024 13.20 +/- 0.74 1415.30 +/- 131.40 4.15 +/- 0.36 1.67 +/- 0.47 236.90 +/- 101.90 339.12 +/- 145.45 0.25 +/- 0.12 11291.00 +/- 372.80 3528.90 +/- 372.80 7.89 +/- 0.16 3.46 +/- 0.10 2.40 +/- 0.38 1267.20 +/- 105.00 0.024 +/- 0.013 10.95 +/- 0.89 0.068 +/- 0.018 2.12 +/- 0.86 2.05 +/- 0.19 2.32 +/- 0.39 6.67 +/- 0.28 5.93 +/- 0.38 251.33 +/- 86.51 0.30 +/- 0.08 0.76 +/- 0.54 1.49 +/- 1.06 0.54 +/- 0.26 0.33 +/- 0.09 6.71 +/- 0.58 0.46 +/- 0.05 0.09 +/- 0.02 0.11 +/- 0.02 0.27 +/- 0.09 614.99 +/- 107.99 1.55 +/- 0.33 6.93 +/- 0.72 9.29 +/- 1.63 6.22 +/- 0.48 1.59 +/- 0.62 2.36 +/- 1.14 653.20 +/-102.30 0.07 +/- 0.04 11.13 +/- 0.90 0.05O +/- 0.027 14.01 +/- 0.67 1348.10 +/- 109.00 4.19 +/- 0.38 1.39 +/- 0.45 281.90 +/- 103.70 337.23 +/- 98.19 0.21 +/- 0.09 11167.00 +/- 315.00 3677.20 +/- 392.40 8.01 +/- 0.16 3.33 +/- 0.10 2.55 +/- 0.43 1305.70 +/- 109.80 0.030 +/- 0.015 10.86 +/- 0.89 0.062 +/- 0.017 2.27 +/- 0.77 2.27 +/- 0.38 2.26 +/- 0.66 6.64 +/- 0.42 6.03 +/- 0.37 372.48 +/- 92.27 0.42 +/- 0.09 0.78 +/- 0.54 0.72 +/- 0.53 0.25 +/- 0.26.0.34 +/- 0.06 7.20 +/- 0.32 0.49 +/- 0.03 0.09 +/- 0.01 0.10 +/- 0.01 0.29 +/- 0.16 512.31 +/- 103.83 1.66 +/- 0.20 6.66 +/- 0.44 9.11 +/- 1.11 6.04 +/- 0.31 1.83 +/- 0.45 2.20 +/- 0.77 701.90 +/- 73.73 0.10 +/- 0.04 10.64 +/- 0.66 0.048 +/- 0.018 13.61 +/- 0.50 1381.70 +/- 85.36 4.17 +/- 0.26 1.53 +/- 0.33 259.40 +/- 72.69 338.18 +/- 87.74 0.23 +/- 0.07 11229.00 +/- 244.03 3603.05 +/- 270.63 7.95.+/- 0.11 3.40 +/- 0.07 2.48 +/- 0.29 1286.45 +/- 75.96 0.027 +/- 0.010 10.91 +/- 0.63 0.065 +/- 0.012 2.20 +/- 0.58 2.16 +/- 0.21 2.29 +/- 0.38 6.66 +/- 0.25 5.98 +/- 0.26 311.90 +/- 63.24 0.36 +/- 0.06 0.77 +/- 0.38 1.11 +/- 0.59 0.40 +/- 0.18 0.34 +/- 0.05 6.96 +/- 0.33 0.48 +/- 0.03 0.09 +/- 0.01 0.11 +/- 0.01 0.28 +/- 0.09 563.65 +/- 74.91 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 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 VE-4054, 4055 VE-4222, 4223 VE-4222, 4223 DW-30113, 30114 DW-30115, 30116 DW-30124, 30125 DW-30124, 30125 DW-30126, 30127 AP-4433, 4434 SG-4475, 4476 SG-4475, 4476 WW-4685, 4686 AP-4706, 4707 SO-4748, 4749 SO-4748, 4749 SO-4748, 4749 SO-4748, 4749 VE-4832, 4833 DW-30149, 30150 DW-30149, 30150 SG-4916, 4917 SG-4916, 4917 F-5313, 5314 F-5313, 5314 F-5313, 5314 VE-5166, 5167 VE-5376, 5377 VE-5334, 5335 VE-5481, 5482 VE-5481, 5482 VE-5481, 5482 DW-30164, 30165 DW-30164, 30165 VE-5166, 5167 ME-5607, 5608 ME-5607, 5608 SW-5901, 5902 BS-6048, 6049 AP-6482, 6483 7/9/2012 7/13/2012 7/13/2012 7/13/2012 7/13/2012 7/13/2012 7/13/2012 7/13/2012 7/19/2012 7/19/2012 7/19/2012 7/24/2012 7/26/2012 7/26/2012 7/26/2012 7/26/2012 7/26/2012 8/1/2012 811/2012 8/11/2012 8/3/2012 81312012 8/9/2012 8/9/2012 8/9/2012 8/15/2012 8/22/2012 8/27/2012 8/28/2012 8/28/2012 8/28/2012 8/30/2012 8/30/2012 9/4/2012 9/4/2012 9/4/2012 9/17/2012 9/24/2012 9/27/2012 K-40 Be-7 K-40 Ra-228 Gr. Alpha Ra-226 Ra-228 Gr. Alpha Be-7 Gr. Alpha Gr. Beta H-3 Be-7 Gr. Beta Gr. Beta U-233/4 U-238 K-40 Ra-226 Ra-228 Ac-228 K-40 Cs-137 Gr. Beta K-40 K-40 Gr. Beta K-40 Be-7 K-40 Sr-90 Ra-226 Ra-228 K-40 Gr. Beta K-40 H-3 K-40 Be-7 7.28 +/- 0.56 0.16 +/- 0.08 7.20 +/- 0.30 1.93 +/- 0.66 7.46 +/- 1.21 1.16 +/- 0.15 1.38 +/- 0.56 6.23 +/- 1.16 0.17 +/- 0.09 17.03 +/- 4.17 13.23 +/- 2.61 289.00 +/- 99.00 0.28 +/- 0.14 20.45 +/- 1.04 20.45 +/- 1.04 0.11 +/-0.02 0.12 +/- 0.02 4.06 +/- 0.22 2.69 +/- 0.22 2.77 +/- 0.75 11.03 +/- 0.33 6.39 +/- 0.80 0.05 +/- 0.02 4.12 +/- 0.08 3.07 +/- 0.42*4.26 +/- 0.28 7.72 +/- 0.17 1.65 +/- 0.17 2.52 +/- 0.19 5.05 +/- 0.37 0.01 +/- 0.00 1.33 +/- 0.15 2.76 +/- 0.66 2.05 +/- 0.32 2.92 +/- 0.08 2.06 +/- 0.32 10909.00 +/- 311.00 1.24 +/- 0.20 0.09 +/- 0.02 7.42 +/- 0.63 0.22 +/- 0.09 6.60 +/- 0.30 1.03 +/- 0.53 7.02 +/- 1.14 0.90 +/- 0.12 1.72 +/- 0.60 6.75 +/- 1.29 0.21 +/- 0.10 15.56 +/- 3.96 14.36 +/- 2.47 375.00 +/- 103.00 0.24 +/- 0.14 19.22 +/- 0.94 19.22 +/- 0.94 0.10 +/- 0.01 0.11 +/- 0.01 4.08 +/- 0.24 2.79 +/- 0.22 1.61 +/- 0.57 11.08 +/- 0.44 6.98 +/- 0.88 0.05 +/- 0.02 4.10 +/- 0.08 3.14 +/- 0.40 3.66 +/- 0.47 7.61 +/- 0.16 1.72 +/- 0.15 2.65 +/- 0.21 4.79 +/- 0.39 0.01 +/- 0.01 1.59 +/- 0.17 1.54 +/- 0.56 2.53 +/- 0.36 2.89 +/- 0.08 2.53 +/- 0.36 10817.00 +/- 310.00 1.18 +/- 0.21 0.09 +/- 0.03 7.35 +/- 0.42 0.19 +/- 0.06 6.90 +/- 0.21 1.48 +/- 0.42 7.24 +/- 0.83 1.03 +/- 0.10 1.55 + 0.41 6.49 + 0.87 0.19 +/- 0.07 16.30 +/- 2.88 13.80 +/- 1.80 332.00 + 71.43 0.26 _ 0.10 19.84 +/- 0.70 19.84 +/- 0.70 0.11 +/-0.01 0.12 +/- 0.01 4.07 +/- 0.16 2.74 +/- 0.16 2.19 +/- 0.47 11.06 +/- 0.28 6.69 +/- 0.59 0.05 +/- 0.01 4.11 +/- 0.06 3.11 +/- 0.29.3.96 +/- 0.27 7.67 +/- 0.12 1.68 +/- 0.12 2.59 +/- 0.14 4.92 +/- 0.27 0.01 +/- 0.00 1.46 +/- 0.11 2.15 +/- 0.43 2.29 +/- 0.24 2.90 +/- 0.06 2.29 +/- 0.24 10863.00 +/- 219.56 1.21 +/- 0.14 0.09 +/- 0.02 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-3 TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance G-6090, 6091 G-6090, 6091 G-6090, 6091 SO-6111, 6112 SO-6111, 6112 W-6795, 6796 AP-6461, 6462 WW-6279, 6280 W-6346, 6347 VE-6503, 6504 WW-6606, 6607 WW-6606, 6607 WW-7237, 7238 F-6627, 6628 VE-6669, 6670 VE-6669, 6670 SS-6711, 6712 SS-6711, 6712 SS-6711, 6712 SS-6711, 6712 SS-6711, 6712 WW-7258, 7259 WW-7655, 7656 WW-7747, 7748 MI-6963, 6964 MI-7174, 7175 SG-7221, 7222 DW-30216, 30217 DW-30216, 30217 DW-30216, 30217 MI-7363, 7364 CF-7384, 7385 VE-7489, 7490 AP-7531, 7532 BS-7573, 7574 LW-7865, 7866 SG-8095, 8096 SG-8095, 8096 10/1/2012 10/1/2012 10/1/2012 10/1/2012 10/1/2012 10/1/2012 10/2/2012 10/3/2012 10/3/2012 10/9/2012 10/10/2012 10/10/2012 10/12/2012 10/15/2012 10/16/2012 10/16/2012 10/16/2012 10/16/2012 10/16/2012 10/16/2012 10/16/2012 10/22/2012 10/25/2012 10/25/2012 10/28/2012 11/5/2012 11/9/2012 11/9/2012 11/9/2012 11/9/2012 11/13/2012 11/13/2012 11/16/2012 11/21/2012 11/24/2012 12/5/2012 12/19/2012 12/19/2012 Be,-7 Gr. Beta K-40 Cs-137 K-40 H-3 Be-7 Gr. Beta Ra-226 K-40 Gr. Beta H-3 H-3 K-40 Be-7 K-40 Ac-228 Bi-214 Gr. Beta Pb-212 TI-208 H-3 H-3 H-3 K-40 K-40 Pb-214 Gr. Alpha Ra-226 Ra-228 K-40 K-40 K-40 Be-7 K-40 Gr. Beta Ac-228 Gamma 3.74 +/- 0.33 10.81 +/- 0.34 5.99 +/- 0.47 0.06 +/- 0.03 19.66 +/- 0.84 215.20 +/- 88.00 0.07 +/- 0.01 1.54 +/- 0.68 0.30 +/- 0.10 5.23 +/- 0.83 3.18 +/- 1.31 273.10 +/- 85.70 175.44 +/- 99.84 3.05 +/- 0.39 0.48 +/- 0.26 4.06 +/- 0.28 0.16 +/- 0.05 0.13 +/- 0.03 14.20 +/- 0.89 0.15 +/- 0.06 0.06 +/- 0.02 214.69 +/- 85.42 159.00 +/- 86.10 156.50 +/- 84.70 1384.60 +/- 111.70 1283.60 +/- 97.45 31.49 +/- 0.70 2.23 +/- 0.86 0.72 +/- 0.12 0.92 +/- 0.52 1304.40 +/- 103.30 11.75 +/- 0.52 2.22 +/- 0.23 0.19 +/- 0.10 7.21 +/- 0.41 2.16 +/- 0.56 25.15 +/- 0.73 26.98 +/- 2.72 3.54 +/- 0.30 10.72 +/- 0.33 5.45 +/- 0.44 0.04 +/- 0.02 20.09 +/- 0.80 292.80 +/- 91.60 0.07 +/- 0.02 1.67 +/- 0.75 0.36 +/- 0.10 6.00 +/- 0.45 2.42 +/- 1.27 219.80 +/- 83.10 180.75 +/- 100.03 3.23 +/- 0.37 0.50 +/- 0.13 3.68 +/- 0.26 0.17 +/- 0.06 0.16 +/- 0.03 12.67 +/- 0.88 0.13 +/- 0.02 0.04 +/- 0.02 314.60 +/- 90.25 159.00 +/- 86.10 170.20 +/- 85.30 1421.60 +/- 107.60 1293.20 +/- 91.37 30.11 +/- 0.80 2.31 +/- 0.92 0.82 +/- 0.14 1.26 +/- 0.53 1496.10 +/- 121.30 10.94 +/- 0.59 1.91 +/- 0.22 0.29 +/- 0.17 7.57 +/- 0.39 1.64 +/- 0.62 25.47 +/- 0.54 28.68 +/- 2.89 3.64 +/- 0.22 10.77 +/- 0.24 5.72 +/- 0.32 0.05 +/- 0.02 19.88 +/- 0.58 254.00 +/- 63.51 0.07 +/- 0.01 1.61 +/- 0.51 0.33 +/- 0.07 5.62 +/- 0.47 2.80 +/- 0.91 246.45 +/- 59.69 178.10 +/- 70.66 3.14 +/- 0.27 0.49 +/- 0.15 3.87 +/- 0.19 0.17 +/- 0.04 0.14 +/- 0.02 13.44 +/- 0.63 0.14 +/- 0.03 0.05 +/- 0.01 264.65 +/- 62.13 159.00 +/- 60.88 163.35 +/- 60.10 1403.10 +/- 77.55 1288.40 +/- 66.79 30.80 +/- 0.53 2.27 +/- 0.63 0.77 +/- 0.09 1.09 +/- 0.37 1400.25 +/- 79.66 11.35 +/- 0.39 2.06 +/- 0.16 0.24 +/- 0.10 7.39 +/- 0.28 1.90 +/- 0.42 25.31 +/- 0.45 27.83 +/- 1.98 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Note: Duplicate analyses are performed on every twentieth sample received in-house.

Results are not listed for those analyses with activities that measure below the LLD.a Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).A5-4 TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits C Acceptance STW-1670 02/01/12 1-129 9.31 +/- 0.31 12.29 8.60 -15.98 STSO-1766 d STSO-1 766 STSO-1 766 STSO-1766 STSO-1766 STSO-1766 STSO-1766 STSO-1 766 STSO-1766 STSO-1766 STSO-1766 STSO-1766 STSO-1 766 STSO-1 766 STSO-1 766 STAP-1772 STAP-1772 STAP-1772 STAP-1772 STAP-1772 STAP-1772 STAP-1772 STAP-1772 STAP-1772 STAP-1 772 e STAP-1 772 STAP-1 772 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 Am-241 Co-57 Co-60 Cs-134 Cs-137 K-40 Mn-54 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 U-233/4 U-238 Zn-65 Am-241 Co-57 Co-60 Cs-134 Cs-1 37 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Zn-65 88.50 +/- 8.30 1352.10 +/- 4.00 1.70 +/- 0.70 842.20 +/- 4.30 0.40 +/- 0.90 1729.60 +/- 22.20 647.60 +/- 4.20 781.50 +/- 9.70 142.40 +/- 9.70 66.10 +/- 6.40 383.20 +/- 15.30 289.60 +/- 10.90 63.20 +/- 5.40 310.80 +/- 12.10 766.70 +/- 6.70 0.062 +/- 0.02 0.010 +/- 0.01 2.40 +/- 0.08 2.33 +/- 0.13 2.07 +/- 0.10 3.77 +/- 0.14 0.003 +/- 0.004 0.098 +/- 0.017-0.010 +/- 0.060 0.016 +/- 0.006 0.11 +/- 0.02 3.67 +/- 0.20 0.51 +/- 0.05 2.75 +/- 0.10 14.57 +/- 0.28 6.45 +/- 0.23 8.39 +/- 0.29 0.01 +/- 0.09 0.03 +/- 0.08 10.31 +/- 0.67 1.68 +/- 0.09 6.33 +/- 0.10 159.00 1179.00 1.56 828.00 0.00 1491.00 558.00 862.00 136.00 65.80 392.00 374.00 68.10 329.00 642.00 0.073 0.00 2.18 2.38 1.79 3.24 0.002 0.097 0.000 0.019 0.12 2.99 111.00 -207.00 825.00 -1533.00 1.00 -2.00 580.00 -1076.00 0.00 -1.00 1044.00 -1938.00 391.00 -725.00 603.00 -1121.00 97.00 -177.00 46.10 -85.50 274.00 -510.00 262.00 -486.00 47.70 -88.50 230.00 -428.00 449.00 -835.00 0.051 -0.10 0.000 -1.00 1.53 -2.84 1.67 -3.09 1.25 -2.33 2.27 -4.21 0.000 -0.10 0.07 -0.13-0.10 -0.13 0.013 -0.024 0.09 -0.16 2.09 -3.89 Pass Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass STAP-1 773 02/01/12 Gr. Alpha STAP-1773 02/01/12 Gr. Beta STVE-1776 STVE-1 776 STVE-1776 STVE-1776 STVE-1 776 STVE-1776 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 Co-57 Co-60 Cs-134 Cs-1 37 Mn-54 Zn-65 1.20 2.40 12.00 6.05 8.43 0.00 0.00 8.90 2.14 6.36 0.40 -2.00 1.20-3.60 8.40 -15.60 4.24 -7.87 5.90 -10.96 0.00 -0.10 0.00 -0.10 6.23-11.57 0.64 -3.64 3.18 -9.54 STW-1 960 02/01/12 Gr. Alpha STW-1960 02/01/12 Gr. Beta A6-1 TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance STW-1964 STW-1 964 STW-1964 STW-1 964 STW-1964 STW-1964'STW-1964 STW-1964 STW-1964 STW-1 964 STW-1 964 STW-1964 STW-1964 STW-1964 STW-1964 STW-1964 STW-1964 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 02/01/12 Am-241 Co-57 Co-60 Cs-134 Cs-1 37 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 1.28 +/- 0.12 33.30 +/- 0.40 23.20 +/- 0.40 0.30 +/- 3.00 40.10 +/- 0.60 65.10 +/- 9.50 460.00 +/- 12.10 153.00 +/- 4.20 32.70 +/- 0.60 49.80 +/- 2.90 0.58 +/- 0.06 1.30 +/- 0.15 0.10 +/- 0.20 23.70 +/- 0.80 0.40 +/- 0.05 2.67 +/- 0.13 0.01 +/- 0.20 5.73 +/- 0.28 1.63 32.90 23.72 0.00 39.90 81.90 437.00 142.00 31.80 60.00 0.63 1.34 0.00 27.90 0.39 2.76 0.00 6.82 111.00 406.00 105.80 134.00 508.00 469.00 1316.00 531.00 939.00 1150.00 632.00 920.00 60.30 263.00 606.00 1.14 -2.12 23.00 -42.80 16.60 -30.84 0.00 -1.00 27.90 -51.90 57.30 -106.50 306.00 -568.00 99.00 -185.00 22.30 -41.30 42.00 -.78.00 0.44 -0.82 0.94-1.74 0.00 -1.00 19.50 -36.30 0.27 -0.51 1.93 -3.59 0.00 -1.00 4.77 -8.87 78.00 -144.00 284.00 -528.00 74.10 -137.50 94.00 -174.00 356.00 -660.00 328.00 -610.00 921.00 -1711.00 372.00 -690.00 657.00 -1221.00 805.00 -1495.00 442.00 -822.00 644.00 -1196.00 42.20 -78.40 184.00 -342.00 424.00 -788.00 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 STW-5391 .08/01/12 1-129 STSO-5392 STSO-5392 STSO-5392 STSO-5392 STSO-5392 STSO-5392 STSO-5394 STSO-5394 STSO-5394 STSO-5394 STSO-5394 STSO-5394 STSO-5394 STSO-5394 STSO-5394*08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 08/01/12 Am-241 Ni-63 Pu-238 Pu-239/40 Sr-90 Tc-99 Co-57 Co-60 Cs-1 34 Cs-137 K-40 Mn-54 U-233/4 U-238'Zn-65 129.30 376.20 118.70 140.70 483.52 432.50 1528.00 592.00 933.60 1319.80 737.30+/- 12.70+/- 20.60+/- 9.30+/- 9.90+/- 16.47+/- 23.10+/- 4.10+/- 3.20+/- 5.82+/- 5.50+/- 17.70 1083.20 +/- 5.20 55.80 +/- 4.20 231.20 +/- 8.60 696.10 +/- 7.00 A6-2 TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance STVE-5395 g 08/01/12 Co-57 7.44 +/- 0.17 5.66 3.96 -7.36 Fail STVE-5395 08/01/12 Co-60 5.90 +/- 0.15 5.12 3.58 -6.66 Pass STVE-5395 08/01/12 Cs-134 7.40 +/- 0.31 6.51 4.56 -8.46 Pass STVE-5395 08/01/12 Cs-137 5.45 +/- 0.18 4.38 3.07 -5.69 Pass STVE-5395 08/01/12 Mn-54 4.06 +/- 0.21 3.27 2.29 -4.25 Pass STAP-5398 08/01/12 Gr. Alpha 0.41 +/- 0.05 0.97 0.29 -1.65 Pass STAP-5398 08/01/12 Gr. Beta 2.11 +/- 0.09 1.92 0.96 -2.88 Pass STAP-5401 h 08/01/12 Am-241 0.12 +/- 0.02 0.08 0.05 -0.10 Fail STAP-5403 08/01/12 Co-57 1.96 +/- 0.05 1.91 1.34 -2.48 Pass STAP-5403 08/01/12 Co-60 1.76 +/- 0.07 1.73 1.21 -2.25 Pass STAP-5403 08/01/12 Cs-134 2.74 +/- 0.18 2.74 1.92 -3.56 Pass STAP-5403 08/01/12 Cs-137 0.00 +/- 0.03 0.00 -0.01 -0.01 Pass STAP-5403 08/01/12 Mn-54 2.52 +/- 0.10 2.36 1.65 -3.07 Pass STAP-5403 08/01/12 Pu-238 0.050 +/- 0.015 0.063 0.044 -0.081 Pass STAP-5403 08/01/12 Pu-239/40 0.001 +/- 0.004 0.00081 0.000 -0.010 Pass STAP-5403' 08/01/12 U-233/4 0.009 +/- 0.011 0.014 0.010 -0.018 Fail STAP-5403 08/01/12 U-238 0.08 +/- 0.02 0.10 0.070 -0.130 Pass STAP-5403 08/01/12 Zn-65 0.01 +/- 0.06 0.00 -0.010 -0.010 Pass STW-5445 08/01/12 Fe-55 79.80 +/- 4.10 89.30 62.50 -116.10 Pass STW-5445 08/01/12 Ni-63 74.30 +/- 3.40 66.30 46.40 -86.20 Pass STW-5445 08/01/12 U-233/4 0.46 +/- 0.05 0.45 0.32 -0.59 Pass STW-5445 08/01/12 U-238 3.14 +/- 0.14 3.33 2.33 -4.33 Pass STW-5445 J 08/01/12 Am-241 0.64 +/- 0.04 1.06 0.74 -1.38 Fail a Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

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

c 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.d Investigation was inconclusive, there was not enough sample for reanalysis.

ERA results (A-7) for the same matrix were acceptable.

e No errors found in calculation or procedure, original analysis result; 0.010 +/- 0.010 Bq/filter.

f Reanalysis results were within limits, but low. ERA results (A-7) for the same matrix were acceptable.

The efficiency factor was recalculated for the second round of MAPEP testing. Original analysis results 55.8 +/- 12.6 Bq/L.g Result of reanalysis; 6.74 +/- 0.15 Bq/sample.

Gamma emitters for the vegetation matrix exhibited a high bias, only Co-57 exceeded acceptance limits. Recounted using a geometry more closely matched to the MAPEP sample size.h Result of reanalysis; 0.070 +/- 0.013 Bq/filter.

Result of reanalysis; 0.013 +/- 0.005 pCi/filter.

A larger sample size was used to reduce the counting error.Result of reanalysis 1.07 +/- 0.06 pCi/L. The analyses of the MAPEP sample matrix resulted in recovery factors greater than 100%.A correction was made using recovery based on analysis of blank samples. A new tracer solution is on order, future samples for MAPEP testing will include batch spike and blank samples.A6-3 TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERAP-1393 ERAP-1393 ERAP-1393 ERAP-1393 ERAP-1393 ERAP-1 394 ERAP-1394 ERAP-1394 ERAP-1394 ERAP-1394 ERAP-1394 ERAP-1394 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 Co-60 Cs- 134 Cs-137 Mn-54 Zn-65 Am-241 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium ERAP-1396 03/19/12 Gr. Alpha ERAP-1396 03/19/12 Gr. Beta ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1 397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 ERSO-1397 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 Ac-228 Am-241 Bi-212 Bi-214 Co-60 Cs-134 Cs-137 K-40 Mn-54 Pb-212 Pb-214 Pu-238 Pu-239/40 Sr-90 Th-234 U-233/4 U-238 Uranium Zn-65 917.5 +/- 7.0 586.6 +/- 7.4 1255.9 +/- 9.4< 3.4 1085.2 +/- 1'8.0 86.9 +/- 2.9 70.2 +/- 3.6 66.0 +/- 1.0 112.5 +/- 15.4 43.4 +/- 0.8 44.0 +/- 1.2 89.1 +/- 2.2 81.1 +/- 1.5 68.4 +/- 0.7 1303.4 +/- 89.3 856.0 +/- 123.7 1379.2 +/- 247.2 965.2 +/- 38.4 3693.6 +/- 32.1 2257.3 +/- 45.4 9444.5 +/- 58.4 11277.0 +/- 275.1< 21.0 1208.4 +/- 26.3 1041.6 +/- 46.9 921.0 +/- 112.6 1028.0 +/- 112.6 8128.0 +/- 329.0 2711.3 +/- 253.6 1859.3 +/- 126.6 2003.3 +/- 130.3 3939.5 +/- 283.8 4200.4 +/- 65.9 880.0 656.0 1130.0 0.0 897.0 68.8 63.2 63.0 89.6 47.5 47.1 96.7 77.8 52.5 1570.0 938.0 1550.0 1100.0 3500.0 2180.0 8770.0 11600.0 0.0 1510.0 1110.0 984.0 879.0 8800.0 2000.0 1960.0 2000.0 4030.0 3650.0 681.0 -1100.0 417.0 -814.0 849.0 -1480.0 642.0 -1240.0 42.4 -93.1 43.3 -83.1 45.6 -82.4 43.8 -134.0 29.4 -71.6 30.4 -65.1 53.5 -147.0 26.1 -121.0 33.2 -76.5 1010.0 -2180.0 549.0 -1220.0 413.0 -2280.0 665.0 -1590.0 2370.0 -4820.0 1420.0 -2620.0 6720.0 -11300.0 8470.0 -15600.0 992.0 -2110.0 647.0 -1650.0 592.0 -1360.0 575.0 -1210.0 3360.0 -13900.0 632.0 -3760.0 1200.0 -2510.0 1240.0 -2540.0 2190.0 -5320.0 2910.0 -4850.0 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 Pass Pass Pass Pass Pass Pass A7-1 TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)a.Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result o Limits Acceptance ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERVE-1400 ERW-1403 ERW-1403 ERW-1403 ERW-1403 ERW-1403 ERW-1403 ERW-1403 ERW-1405 ERW-1405 ERW-1405 ERW-1405 ERW-1405 ERW-1405 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 03/19/12 Am-241 Cm-244 Co-60 Cs-134 Cs-137 K-40 Mn-54 Pu-238 Pu-239/40 Sr-90 U-233/4 U-238 Uranium Zn-65 Am-241 Fe-55 Pu-238 Pu-239/40 U-233/4 U-238 Uranium Co-60 Cs-134 Cs-137 Mn-54 Sr-90 Zn-65 4194.8 +/- 199.5 1471.2 +/- 113.1 2347.8 +/- 47.9 2847.5 +/- 64.0 1503.5 +/- 52.5 34105.7 +/- 745.3< 26.8 2509.0 +/- 213.6 2690.4 +/- 208.9 7881.5 +/- 470.8 3149.6 +/- 165.2 3203.6 +/- 166.5 6463.7 +/- 363.2 2701.9 +/- 105.5 119.9 +/-_3.2 713.7 +/- 127.4 131.9 +/- 6.4 108.9 +/- 10.2 93.1 +/- 7.9 96.9 +/- 5.5 190.0 +/- 13.8 858.7 +/- 5.6 560.4 +/- 4.4 1239.9 +/- 7.4< 7.4 944.3 +/- 26.2 786.9 +/- 20.6 85.9 +/- 3.0 45.7 +/- 1.6 9045.0 +/- 284.0 4540.0 1590.0 2210.0 2920.0 1340.0 28600.0 0.0 2350.0 2570.0 8520.0 3610.0 3580.0 7350.0 2310.0 135.0 863.0 135.0 112.0 105.0 104.0 214.0 875.0 609.0 1250.0 0.0 989.0 749.0 103.0 43.7 2780.0 -6040.0 779.0 -2480.0 1520.0 -3090.0 1880.0 -3790.0 972.0 -1860.0 20700.0 -40100.0 1400.0 -3220.0 1580.0 -3540.0 4860.0 -11300.0 2370.0 -4640.0 2390.0 -4550.0 4980.0 -9150.0 1670.0 -3240.0 91.0 -181.0 514.0 -1170.0 99.9 -168.0 86.9-141.0 78.9 -135.0 79.3 -128.0 157.0 -277.0 760.0 -1020.0 447.0 -700.0 1060.0.- 1500.0 644.0 -1310.0 624.0 -945.0 36.6 -160.0 25.0 -64.7 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass ERW-1406 03/19/12 Gr. Alpha ERW-1406 03/19/12 Gr. Beta ERW-1409 03/19/12 H-3 9150.0 6130.0 -13000.0 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).

Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCi/kg).c Unless otherwise indicated, the laboratory result is given as the mean +/- standard deviation for three determinations.

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

Control limits are not provided.A7-2 APPENDIX B DATA REPORTING CONVENTIONS B-1 Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.2.0. Single Measurements Each single measurement is reported as follows: x + s where: x = value of the measurement; s = 2a counting uncertainty (corresponding to the 95% confidence level).In cases where the activity is less than the lower limit of detection L, it is reported as: < L, where L = the lower limit of detection based on 4.66a uncertainty for a background sample.3.0. Duplicate analyses If duplicate analyses are reported, the convention is as follows.3.1 Individual results: For two analysis results; x 1 _ s 1 and x2 + s2 Reported result: x +/- s; where x = (1/2) (x 1 + x 2) and s = (1/2) S1 +3.2. Individual results: < L, < L 2 Reported result: < L, where L = lower of L 1 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 .2. xn are defined as follows:-- 1 x = Zx s= n-4.2 Values below the highest lower limit of detection are not included in the average.4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.4.5 In rounding off, the following rules are followed: 4.5.1. If the number following those to be retained is less than 5, the number is dropped, and the retained 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-I Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural a background in unrestricted areas Air (pCi/m 3)Water (pCi/L)Gross alpha Gross beta b Iodine-i 31-3 1 x 10 1-1 2.8 x 10 Strontium-89 Strontium-90 Cesium-137 Barium-140 Iodine-1 31 c Potassium-40 Gross alpha Gross beta Tritium 500 8,000 1,000 8,000 1,000 4,000 2 10 6 1 x 10 b C 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.A natural radionuclide.

C-2 APPENDIX D Sampling Location Maps D-1 Figure D-1, Sample Collection and Analysis Program: TLD locations, Inner Ring. (Table 5.2)D-2 Figure D-2, Sample Collection and Analysis Program: TLD locations, Outer Ring. (Table 5.2)D-3 w Ct Figure D-3, Sample Collection and Analysis Program: TLD locations, Controls. (Table 5.2)D-4

--"--- -..! .i --o:ei -a.t -..~-:s Rd .i '. .V.. .... , ---ru. nh... .: =--::t: ~ i~t 51 -.. ..-.-- 4.. ..* VOW.am* -* .. a' -... l" ' ' ".. .......7U-F i u e .-.. a pe.o le t o n a d A n lm Rt Mg P Mil Sapln locations. (Table D-1A: .: : ......, .: .: , ...o ..-.: : : ...i : : i i i -"O. ." :' .. '4 ' : ! 4 " i : : i ! -' , : : .' .: : .;% ' ' ' ..; " " " : ' .: : ' : -: .'- ; -; -." s., '. .; .--i , i , .... ...." ...; = : : " : ! ---....& .... .... i ..: .:." ...

-.: Jp.-O:i*f, :,. .: , 2.....4 .RT .; ...* ." : : .- ; .' ' -: ..*. .i : ., .4 ' ;.... D- , Sample Colcto an Analysi Progra : ; Raioogca Eniom na Monitorin Program,#:

..M ilk.... Sa pln locat i ons. .(Table .... I.. 1 -::--:::.: ..., '.. -5; : : .... , ..; --T Figure D-5, Sample Collection and Analysis Program: Radiological Environmental Monitoring Program, Sludge, Ground Water and Shoreline sampling locations. (Table 5.2)D-6 APPENDIX E Ground Water Monitoring 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 2012. 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, 2012") 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 2012 are summarized and discussed.

Program findings for 2012 detected low levels of tritium in monitoring wells located on the plant property.

With the exception of monitoring wells MW-9A, MW-10 and MW-13A, tritium measured at or near expected natural background levels. The 2012 sample results (excluding MW-9A, MW-10 and MW-1i3A) all measured below the required limit of 500 pCi/L. One of six storm water runoff samples collected in October from the sanitary sewer, measured 4479 pCi/L of tritium. The remaining samples measured less than 500 pCi/L. The measurements for 2012 are well below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L and present no harm to 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 SamDlina Program 3.1 Progqram 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.Sampling from the groundwater monitoring wells was conducted monthly at fourteen locations and quarterly for five locations.

3.3 Program

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

Ground water from location MW-14, October 17, 2012, was not collected as scheduled.

Additional analyses for gamma emitting isotopes were performed on samples from each of the nineteen monitoring wells. Results are summarized in Table E-3.3.4 Program Modifications Two additional on-site monitoring wells MW-15A, 15B (approx. 0.14 mi / NNE) were added to the ground water program in July, 2012. Samples are analyzed for tritium and gamma emitting isotopes.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 monitoring wells, MW-9A, MW-10 and MW-1 3A.Excluding data for wells MW-9A, MW-1 0 and MW-1 3A, the 2012 sample results are similar or slightly lower than averages seen in 2011 and 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 tritium activity detected at sites MW-9A and MW-10 ranged from a high of 770 pCi/L to <500 pCi/L. These levels were lower than measurements taken in 2011. Previous investigations concluded that the higher tritium activity was due to a 1981 spill from the Condensate Storage Tanks, that had infiltrated the surface and migrated towards MW-9.Tritium concentrations measured at location MW-13A were higher than previously measured in 2011. A spike in activity occurred in March and April, 2012, declined in May, and dropped through the rest of the year. Activity ranged from a high of 3044 to less than 500 pCi/L.No groundwater sample analyzed for gamma-emitting isotopes showed 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 29 MW-4, MW-5, MW-6, MW-7, Grab H-3 Quarterly MW-8 Ground Water 143 MW-1, MW-2, MW-3, MW-9A, Grab H-3 Monthly MW-9B, MW-10, MW-i1, MW-12A, MW-12B, MW-13A, MW-1i3B, MW-14, MW-15A, MW-I 1B, 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-9A 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 Ground Water M-53 MW-15A 0.14 14 NNE Ground Water M-54 MW- 5B 0.14 14 NNE E-6 Table E-3. Ground Water Monitoring Program Summary.Name of Facility Location of Facility Monticello Nuclear Generating Plant Wright, Minnesota Docket No.Reporting Period 50-263 January-December, 2012 ( County, State)Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLD b Mean (F) C Mean (F)c Mean (F) c Routine (Units) Analyses 8 Range -Location d Range' Range -Results Groundwater H-3 172 500 1182 (8/172) MW-13A, Onsite, 2155 (3/12) none 8 Monitoring Wells (540-2317) 0.12 mi @ 316°/NW (810-3044)(pCi/L) GS 54 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 46 < LLD --none 0 Stormwater H-3 6 500 4479 (1/6) Sewer Lift Station 4479 (1/6) none 1 Runoff On-site (pCi/L) GS 6 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 45 < LLD -none 0 GB = gross beta, GS = gamma scan.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 and (2) by distance (miles) and direction relative to reactor site.o 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 i' MIM( cc Ln... ' j= ..\ J,'Z8*'i'6 v UU MissssPPI RIVER 904.40 (September 09, 2009)Figure E-1. Sample collection and analysis program: Ground water, On-site monitoring well locations.

E-8 Table E-4. Ground water, analyses for tritium and gamma-emitting isotopes.Collection Concentration (pCi/L)Lab Code Date 3H 54Mn 5 9 Fe 5 8 Co 6 0 Co 65Zn 95ZrNb 1 34Cs 1 3 7 Cs 14°BaLa 14Ce Monitoring Well #1 (M-33)MWW- 272 01/17/12 < 152 -MWW- 897 02/21/12 < 142 -MWW- 1576 03/23/12 < 145 -MWW-2226 04/18/12 <144 <10 <30 <10 <10 <30 <15 <10 <10 <15 <16 MWW- 3121 05/22/12 < 161 --MWW- 3923 06/20/12 < 145 -- -MWW-4496.

07/19/12 <170 <10 <30 <10 <10 <30 <15 <10 <10 <15 <27 MWW- 5353 08/23/12 < 156 -- --MWW- 5974 09/18/12 < 153 -.. .MWW-6829 10/16/12 <147 <10 <30 <10 <10 <30 <15 <10 <10 <15 <26 MWW- 7630 11/21/12 178 +/- 84 -... .MWW- 8195 12/19/12 < 141 ... ..Monitorinq Well #2 (M-34)MWW- 273 01/17/12 293 +/- 87 -MWW- 898 02/21/12 246 +/- 87 -.MWW- 1577 03/23/12 182 +/- 86 -MWW- 2227 04/18/12 240 +/-97 <10 <30 <10 <10 <30 <15 <10 <10 <15 <30 MWW- 3122 05/22/12 273 +/- 96 -MWW- 3924 06/20/12 207 +/- 97 -MWW- 4498 07/19/12 235 +/-95 <10 <30 <10 <10 <30 <15 <10 <10 <15 <18 MWW- 5354 08/23/12 177 +/- 102 -MWW- 5975 09/18/12 < 153 -- .MWW- 6830 10/16/12 217 +/-84 <10 <30 <10 <10 <30 <15 <10 <10 <15 <21 MWW- 7631 11/20/12 286 +/- 89 ----------MWW- 8196 12/19/12 292 +/- 88 ----------Monitoring Well #3 (M-35)MWW- 274 01/17/12 258 +/- 85 ----------MWW- 899 02/21/12 192 +/- 84 ----------MWW- 1578 03/23/12 < 145 ----------MWW-2228 04/18/12 161 +/-94 <10 <30 <10 <10 <30 <15 <10 <10 <15 <25 MWW- 3123 05/22/12 < 161 -- --MWW- 3925 06/20/12 < 145 -- -MWW-4499 07/19/12 <170 <10 <30 <10 <10 <30 <15 <10 <10 <15 <22 MWW- 5355 08/23/12 < 156 --MWW- 5976 09/18/12 186 +/- 89 -- -MWW- 6831 10/16/12 360 +/-91 a <10 <30 <10 <10 <30 <15 <10 <10 <15 <25 MWW- 7632 11/20/12 241 +/-87 -- --MWW- 8197 12/19/12 < 141 -----Monitoringq Well #4 (M-36)MWW- 275 01/16/12 < 145 -MWW- 2229 04/18/12 <144 <10 <30 <10 <10 <30 <15 <10 <10 <15 <38 MWW-4500 07/19/12 <170 <10 <30 <10 <10 <30 <15 <10 <10 <15 <20 MWW- 5357 08/22/12 < 156 -MWW- 6832 10/16/12 <147 <10 <30 <10 <10 <30 <15 <10 <10 <15 <34 Monitoring Well #5 (M-37)MWW- 276 01/16/12 < 145 ---------MWW- 2230 04/18/12 <144 <10 <30 <10 <10 <30 <15 <10 <10 <15 <39 MWW- 4501 07/20/12.

<170 <10 <30 <10 <10 <30 <15 <10 <10 <15 <24 MWW- 6833 10/18/12 <147 <10 <30 <10 <10 <30 <15 <10 <10 <15 <46 Analysis was repeated; result of reanalysis, 336 +/- 92 pCi/L.E-9 Table E-4. Ground water, analyses for tritium and gamma-emitting isotopes (continued).

Collection Concentration (pCi/L)Lab Code Date 3H 54Mn 59Fe 5 8 Co 8 0 CO 65Zn 1 5 ZrNb 134CS 137Cs 1 4 0 BaLa 1 44Ce Monitoring Well #6 (M-38)MWW- 277 01/16/12 < 145 -----MWW-2232 04/18/12 <144 <10 <30 <10 <10 <30 <15 <10 <10 <15 <22 MWW- 4502 07/20/12 <170 <10 <30 <10 <10 <30 <15 <10 <10 <15 <17 MWW- 6834 10/18/12 < 147 <10 <30 <10 <10 <30 < 15 < 10 < 10 < 15 < 26 Monitoring Well #7 (M-39)MWW- 278 01/16/12 < 145 ----MWW- 2233 04/18/12 < 144 <10 <30 <10 <10 < 30 < 15 <10 <10 < 15 < 20 MWW-4503 07/20/12 <170 <10 <30 <10 <10 <30 <15 <10 <10 <15 <25 MWW- 6835 10/18/12 < 147 <10 <30 <10 <10 < 3.0 < 15 <10 <10 < 15 < 35 Monitoring Well #8 (M-40)MWW- 279 01/16/12 < 145 --MWW-2234 04/19/12 <144 <10 <30 <10 <10 <30 <15 <10 <10 <15 <17 MWW- 4504 07/20/12 < 170 <10 <30 <10 <10 < 30 < 15 <10 <10 < 15 < 14 MWW- 6836 10/18/12 <147 <10 <30 <10 <10 <30 <15 <10 <10 <15 <24 Monitoring Well #9A (M-44)MWW- 280 01/16/12 < 152 --MWW- 900 02/21/12 < 142 -MWW- 1579 03/23/12 < 145 --MWW- 2235 04/19/12 376 +/- 107 <10 < 30 <10 <10 < 30 <15 <10 <10 <15 < 28 MWW- 3124 05/23/12 770 +/- 114 --MWW- 3864 06/21/12 483 +/- 95 -- --MWW- 4505 07/17/12 <171 <10 <30 <10 <10 <30 <15 <10 <10 <15 <17 MWW- 5358 08/21/12 375 +/- 110 -- --MWW- 5977 09/19/12 436 +/- 100 -- -MWW- 6837 10/17/12 337 +/-90 <10 <30 <10 <10 <30 <15 <10 <10 <15 <32 MWW- 7633 11/19/12 < 144 ----------MWW- 8198 12/19/12 < 141 ----------Monitoring Well #9B (M-51)MWW- 281 01/16/12 < 152 ----------MWW- 901 02/21/12 < 142 ----------MWW- 1580 03/23/12 < 145 ----------MWW- 2236 04/19/12 <150 <10 <30 <10 <10 <30 <15 <10 <10 <15 <28 MWW- 3125 05/23/12 < 161 ----MWW- 3927 06/20/12 < 145 ---MWW-4506 07/17/12 <171 <10 <30 <10 <10 <30 <15 <10 <10 <15 <27 MWW- 5359 08/21/12 < 156 -MWW- 5978 09/19/12 < 153 -MWW- 6839 10/17/12 <147 <10 <30 <10 <10 <30 <15 <10 <10 <15 <35 MWW- 7634 11/19/12 < 150 -MWW- 8199 12/19/12 < 141 E-1 0 Table E-4. Ground water, analyses for tritium and gamma-emitting isotopes (continued).

Collection Concentration (pCi/L)Lab Code Date 3 H 54 Mn 59Fe 58Co 6 0 Co 6 5 Zn 9 5 ZrNb 1 3 4 Cs 1 3 7 Cs 1 4 0 BaLa 144Ce Monitoring Well #10 (M-45)MWW- 283 01/17/12 636 +/- 102 MWW- 902 02/21/12 544 +/- 100 --, -MWW- 1581 03/23/12 489 +/- 99 --MWW-2237 04/18/12 539+/-113 <10 <30 <10 <10 <30 <15 <10 <10 <15 <18 MWW- 3126 05/22/12 416 +/- 101 --MWW- 3928 06/20/12 244 +/- 99 ---MWW- 4507 07/19/12 290 +/-98 <10 <30 <10 <10 <30 <15 <10 <10 <15 <29 MWW- 5360 08/23/12 208 +/- 104 --MWW- 5979 09/18/12 401 +/- 99 ---MWW-6840 10/16/12 418+/-94 <10 <30 <10 <10 <30 <15 <10 <10 <15 <24 MWW- 7636 11/20/12 507 +/- 99 ---------MWW- 8200 12/19/12 373 +/- 92 --------Monitoring Well #11 (M-46)MWW- 284 01/17/12 < 145 --------MWW- 903 02/21/12 < 154 --------MWW- 1582 03/23/12 < 145 --------MWW-2238 04/18/12 <150 <10 <30 <10 <10 <30 <15 <10 <10 <15 <22 MWW- 3127 05/22/12 < 161 -MWW- 3929 06/20/12 < 145 -MWW- 4508 07/19/12 <170 <10 <30 <10 <10 <30 <15 <10 <10 <15 <20 MWW- 5361 08/23/12 < 156 -MWW- 5980 09/18/12 < 153 -MWW- 6841 10/16/12 <147 <10 <30 <10 <10 <30 <15 <10 <10 <15 <19 MWW- 7637 11/21/12 < 144 ----------MWW- 8201 12/19/12 < 141 ----------Monitoring Well #12A (M-47)MWW- 285 01/17/12 < 152 ----------MWW- 904 02/21/12 < 154 ----------MWW- 1583 03/19/12 < 145 ----------MWW-2239 04/18/12 <150 <10 <30 <10 <10 <30 <15 <10 <10 <15 <22 MWW- 3128 05/22/12 189 +/- 93 -- -MWW- 3930 06/20/12.

< 145 -- --MWW-4509 07/19/12 <170 <10 <30 <10 <10 <30 <15 <10 <10 <15 <18 MWW- 5362 08/23/12 < 156 -....MWW- 5981 09/17/12 < 153. -MWW-6842 10/17/12 <147 <10 <30 <10 <10 <30 <15 <10 <10 <15 <36 MWW- 7638 11/20/12 < 144 -MWW- 8203 12/20/12 < 141 E-11 Table E-4. Ground water, analyses for tritium and gamma-emitting isotopes (continued).

Collection Concentration (pCi/L)Lab Code Date 3H "Mn Fe 'Co 6 0 Co 6 5 Zn 9 5 ZrNb 1 3 4 cS 1 3 7 cS 1 4 0 BaLa 1440e Monitoringq Well #12B (M-48)MWW- 286 01/17/12 < 145 MWW- 905 02/21/12 < 154 -MWW- 1584 03/19/12 < 145 -MWW-2240 04/18/12 <150 <10 <30 <10 <10 <30 <15 <10 <10 <15 <26 MWW- 3129 05/22/12 < 161 -MWW- 3931 -06/20/12

< 145 MWW-4510 07/19/12 <170 <10 <30 <10 <10 <30 <15 <10 <10 <15 <19 MWW- 5363 08/23/12 < 156 -MWW- 5982 09/17/12 < 153 -MWW-6843 10/17/12 <147 <10 <30 <10 <10 <30 <15 <10 <10 <15 <45 MWW- 7639 11/20/12 < 144 --------MWW- 8204 12/20/12 < 141 -----Monitoring Well #1 3A (M-49)MWW- 287 01/17/12 < 152 -----MWW- 906 02/21/12 < 154 -----MWW- 1585 03/19/12 2612 +/- 166 a -----MWW-2080 04/17/12 3044+/-176 b <10 <30 <10 <10 <30 <15 <10 <10 <10c <10 MWW- 3130 05/22/12 810 +/- 115 -MWW- 3932 06/20/12 351 +/- 103 MWW- 4511 07/19/12 180 +/-93 <10 <30 <10 <10 <30 <15 <10 <10 <15 <23 MWW- 5364 08/22/12 206 +/- 104 MWW- 5983 09/18/12 < 153 MWW-6844 10/17/12 <147 <10 <30 <10 <10 <30 <15 <10 <10 <15 <15 MWW- 7640 11/20/12 221 +/-89 ----------MWW- 8205 12/19/12 < 141 ----------Monitorinq Well #13B (M-50)MWW- 288 01/17/12 < 152 ----------MWW- 907 02/21/12 < 154 ---------MWW- 1587 03/19/12 < 145 ----------MWW- 2241 04/17/12 162 +/-80 <10 <30 <10 <10 <30 <15 <10 <10 <15 <24 MWW- 3131 05/22/12 189 +/- 93 -- --MWW- 3933 06/20/12 294 +/- 101 -- -MWW- 4512 07/19/12 174 +/-93 <10 <30 <10 <10 <30 <15 <10 <10 <15 <17 MWW- 5365 08/22/12 219 +/- 104 -...MWW- 5984 09/18/12 167 +/- 88 -... .MWW- 6845 10/17/12 225 +/-85 <10 <30 <10 <10 <30 <15 <10 <10 <15 <10 MWW- 7641 11/20/12 301 +/-92 -. ...MWW- 8206 12/19/12 222 +/- 85 -.. .a Sample was analyzed in duplicate; result of duplicate analysis, 2283 +/- 157 pCi/L.b Analysis was repeated; result of reanalysis, 3234 +/- 181 pCi/L.' LLD for Ba-La-1 40 not reached due to delay in counting.

Value given is activity at time of counting.E-1 2 Table E-4.,Ground water, analyses for tritium and gamma-emitting isotopes (continued).

Collection Concentration (pCi/L)Lab Code Date 3 H 54Mn 59Fe 58Co 6 0 Co 65 Zn 95ZrNb 1 3 4 Cs 1 3 7 Cs 1 4 0 BaLa 1 44Ce Monitoring Well #14 (M-52)MWW- 289 01/16/12 < 145 --MWW- 908 02/21/12 < 154 --MWW- 1588 03/23/12 < 145 --MWW- 2242 04/18/12 <144 <10 <30 <10 <10 <30 <15 <10 <10 <15 <26 MWW- 3132 05/22/12 < 161 --MWW- 3934 06/20/12 < 145 --MWW- 4513 07/20/12 <170 <10 <30 <10 <10 <30 <15 <10 <10 <15 <12 MWW- 5366 08/21/12 < 156 ---MWW- 5985 09/17/12 < 153 --ND a MWW- 7642 11/20/12 160 +/- 86 c -_MWW- 8207 12/18/12 < 141 --Monitoring Well #15A (M-53) b MWW-4514 07/16/12 <171 <10 <30 <10 <10 <30 <15 <10 <10 <15 <22 MWW- 6846 10/16/12 <147 <10 <30 <10 <10 <30 <15 <10 <10 <15 <14 MWW- 7643 11/20/12 < 149 ----------MWW- 8208 12/20/12 < 141 Monitoring Well #15B (M-54) b MWW-4515 07/16/12 <171 <10 <30 <10 <10 <30 <15 <10 <10 <15 <23 MWW- 6847 10/16/12 341 +/-90 <10 <30 <10 <10 <30 <15 <10 <10 <15 <24 MWW- 7644 11/20/12 323 +/- 93 d ---------MWW- 8209 12/20/12 340 +/- 90 ---------Storm Water Run-off (SD-006)MxW- 1462 03/02/12 <142 <10 <30 <10 <10 <30 <15 <10 <10 <15 <9 MxW- 2732 05/03/12 <149 <10 <30 <10 <10 <30 <15 <10 <10 <15 <17 MxW- 2466 05/01/12 <157 e <10 <30 <10 <10 <30 <15 <10 <10 <15 <42 MxW- 4480 07/18/12 <165 <10 <30 <10 <10 <30 <15 <10 <10 <15 <26 MxW- 7035 10/25/12 4479 +/-207 <10 <30 <10 <10 <30 <15 <10 <10 <15 <18 MxW-7705 11/27/12 <152 e <10 <30 <10 <10 <30 <15 <10 <10 <15 <22 a ND = No Data; Sample not collected.

b New well added in July, 2012.0 Analysis was repeated; result of reanalysis, 153 +/- 83 pCi/L.d Analysis was repeated; result of reanalysis, 371 +/- 92 pCi/L.e Sample from the sanitary sewer.Analysis was repeated; result of reanalysis, 4306 +/- 205 pCi/L.E-13

L-MT-13-042, Submittal of 2012 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 Progqram

3.3 Procqram

3.4 Laboratory

4.0 RESULTS

4.3 Progqram

5.0 FIGURES

6.0 REFERENCES

6.0 REFERENCES

4.0. Computation

4.1 Averages

1.0 INTRODUCTION

SUMMARY

3.0 Ground

3.3 Program

3.5 Results

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L-MT-13-042, Submittal of 2012 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 Progqram

3.3 Procqram

3.4 Laboratory

4.0 RESULTS

4.3 Progqram

5.0 FIGURES

6.0 REFERENCES

6.0 REFERENCES

4.0. Computation

4.1 Averages

1.0 INTRODUCTION

SUMMARY

3.0 Ground

3.3 Program

3.5 Results

Navigation menu

Search