Text

ISFSI - Transmittal of 2015 Annual Radiological Environmental Monitoring Program Report
	ML16126A283
Person / Time
Site:	Prairie Island
Issue date:	05/05/2016
From:	Northard S; Northern States Power Co, Xcel Energy
To:	; Document Control Desk, Office of New Reactors
References
	L-PI-16-038
	Download: ML16126A283 (77)
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Xcel Energy L-PI-16-038 MAY 0 5 2016 TS 5.6.2 ISFSI TS 5.2 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Prairie Island Independent Spent Units 1 and 2 Fuel Storage Installation Docket Nos. 50-282 and 50-306 Docket 72-10 Renewed Facility Operating License Materials License No. SNM-2506 Nos. DPR-42 and DPR-60 2015 Annual Radiological Environmental Monitoring Program Report Pursuant to Prairie Island Nuclear Generating Plant Technical Specification (TS) 5.6.2, Appendix A, to Renewed Operating Licenses DPR-42 and DPR-60, and Prairie Island Independent Spent Fuel Storage Installation Technical Specification (ISFSI TS) 5.2, Appendix A, to Materials License SNM-2506, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), submits one copy of the annual Radiological Environmental Monitoring Program report for the period January 1, 2015, through December 31, 2015, as Enclosure 1.

Summary of Commitments

~;;;;_o new commitment and no revision to any existing commitment.

Scott Northard Acting Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc: Regional Administrator, USNRC, Region Ill Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector, Prairie Island Nuclear Generating Plant Billy Dickson, USNRC, Region Ill Director of NMSS, USNRC Department of Health, State of Minnesota PI Dakota Community Environmental Coordinator 1717 Wakonade Drive East

Welch, Minnesota 55089-9642 Telephone: 651.388.1121

ENCLOSURE 1 Annual Report to the United States Nuclear Regulatory Commission Radiological Environmental Monitoring Program January 1 to December 31,2015 75 pages follow

Environmental, Inc.

I Midwest Laboratory 700 Landwehr Road. Northbrook,IL 60062*2310 phone (617) 564.0700 oiax (647) 564-4517 XCEL ENERGY CORPORATION PRAIRIE ISLAND NUCLEAR GENERATING PLANT ANNUAL REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2015 Docket No. 50-282 License No. DPR-42 50-306 DPR-60 ISFSI Docket No.72-10 SNM-2506 Prepared under Contract by ENVIRONMENTAL, Inc.

MIDWEST LABORATORY Project No. 8010 Approved:

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

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

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TABLE OF CONTENTS Preface .................................................................................................................................................... ii List of Tables .......................................................................................................................................... iv List of Figures .......................................................................................................................................... v

1.0 INTRODUCTION

..................................................................................................................................... 1 2.0

SUMMARY

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

CITED .......................................................................................................................... 24 APPENDICES A Interlaboratory Comparison Program Results ..................................................................................... A-1 Attachment A, Acceptance Criteria for "Spiked" Samples ................................................................ A-2 B Data Reporting Conventions ............................................................................................................... 8-1 C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas ........................................................................................ C-1 D Sampling Location Maps ..................................................................................................................... D-1 E Special Well and Surface Water Samples .......................................................................................... E-1 iii

LIST OF TABLES No.

5.1 Sample Collection and Analysis Program ................................................................................................. 15 5.2 Sampling Locations ................................................................................................................................... 16 5.3 Missed Collections and Analyses ............................................................................................................. 19 5.4 Radiological Environmental Monitoring Program Summary ...................................................................... 20 In addition, the following tables can be found in the Appendices:

Appendix A A-1 Environmental Resources Associates, Crosscheck Program Results .................................................. A1-1 A-2 Program Results; (TLDs) ...................................................................................................................... A2-1 A-3 In-house "Spiked" Samples .................................................................................................................. A3-1 A-4 In-house "Blank" Samples ..................................................................................................................... A4-1 A-5 In-house "Duplicate" Samples........................................................................................................ A5-1 A-6 Department of Energy MAPEP comparison results....................................................................... A6-1 A-7 Environmental Resources Associates, Crosscheck Program Results (EML study replacement) ......... A7-1 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas .................................................................................. C-2 Appendix E E-4.1 Sample collection and analysis program ................................................................................................ E-5 E-4.2 Sampling locations ................................................................................................................................. E-6 E-4.3 REMP Summary ..................................................................................................................................... E-8 E-4.4 REMP Complete Data Tables ................................................................................................................. E-9 E-4.5 Supplementary Data Tables ................................................................................................................... E-13 iv

LIST OF FIGURES 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator locations versus control .............................................................................................................................. 13 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6,7) versus control location (P-1) .................................................................................. 14 Appendix D Title Page TLD locations within a one mile radius ..................................................................................................... D-2 TLD locations, Controls .............................................................................................................................. D-3 TLD locations, surrounding the ISFSI Area ................................................................................................ D-3 TLD locations within a five mile radius ..................................................................................................... D-4 REMP sampling points within a one mile radius ...................................................................................... D-5 REMP sampling points within a five mile radius ....................................................................................... D-6 REMP sampling points, Control locations ............................................................................................... D-7 Appendix E Groundwater Monitoring Well locations .................................................................................................. E-16 v

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December, 2015. 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, 2015 available at Prairie Island Nuclear Generating Plant.

Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, owned by Xcel Energy Corporation and operated by Northern States Power Co.-Minnesota. The plant has two 575 MWe pressurized water reactors. Unit 1 achieved initial criticality on 1 December 1973. Commercial operation at full power began on 16 December 1973. Unit 2 achieved initial criticality on 17 December 1974. Commercial operation at full power began on 21 December 1974.

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2.0

SUMMARY

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

Results for 2015 are summarized and discussed.

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

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3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation The purpose of the Radiological Environmental Monitoring Program (REMP) at the Prairie Island Nuclear Generating Plant is to assess the impact of the plant on its environment. For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs).

Sources of environmental radiation include the following:

(1) Natural background radiation arising from cosmic rays and primordial radionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; (4) Industrial and medical radioactive waste; and (5) Fallout from nuclear accidents.

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

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

An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the plant site. The plant's monitoring program includes analyses for tritium and iodine"131. Most samples are analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-137, cerium-144, beryllium-?,

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

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

The other group quantified consists of niobium-95, ruthenium-1 03 and -106, cesium-134, barium-lanthanum-140, and cerium-141. These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the final group, manganese-54, iron-59, cobalt-58 and -

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

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3.1 Program Design and Data Interpretation (continued)

Other means of distinguishing sources of environmental radiation are employed in interpreting the data. Current radiation levels are compared with previous levels, including those measured before the Plant became operational. Results of the plant's monitoring program can be related to those obtained in other parts of the world. Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g., atmospheric nuclear detonations.

3.2 Program Description The sampling and analysis schedule for the radiological environmental monitoring program at Prairie Island is summarized in Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the reactor site or ISFSI facility, as appropriate. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Prairie Island Nuclear Generating Plant, 2013). Maps of fixed sampling locations are included in Appendix D.

To monitor the airborne environment, air is sampled by continuous pumping at six stations, four site boundary indicators (P-2, P-3, P-4 and P-7), located in the highest calculated D/Q sectors, one community indicator (P-6), and one control (P-1). The particulates are collected on membrane filters, airborne iodine is trapped by activated charcoal canisters. Particulate filters are analyzed for gross beta activity and charcoal canisters for iodine-131. Quarterly composites of particulate filters from each location are analyzed for gamma emitting isotopes.

Offsite ambient gamma radiation is monitored at thirty-four locations, using CaS0 4 :Dy dosimeters with four sensitive areas at each location: ten in an inner ring in the general area of the site boundary, fifteen in the outer ring within a 4-5 mile radius, eight at special interest locations, and one control location, 11.1 miles distant from the plant. They are replaced and measured quarterly.

Ambient gamma radiation is monitored at the Independent Spent Fuel Storage Installation (ISFSI)

Facility by twenty CaS0 4 :Dy dosimeters. Twelve dosimeters are located inside of the earthen berm in direct line of sight from the storage casks and eight dosimeters are located outside of the earthen berm. They are replaced and measured quarterly.

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

For additional monitoring of the terrestrial environment, green leafy vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (P-38), and analyzed for gamma-emitting isotopes, including iodine-131. Corn is collected annually only if fields are irrigated with river water and analyzed for gamma-emitting isotopes. Well water and ground water are collected quarterly from four locations near the plant and analyzed for tritium and gamma-emitting isotopes.

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

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3.2 Program Description (continued)

Drinking water is collected weekly from the City of Red Wing well. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.

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

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

(1) Milk:

There was no milk collected 1/13/15, 2/11/15 or 3/4/15 at location P-37. The farm had temporarily suspended milking operations.

(2) Airborne Particulate I Airborne Iodine Partial samples were collected from location P-2 for the weeks ending on 2/25/15, 6/2/15, 7/29/15, 9/9/15, and 12/22/15. Power was lost to the sampler due to various issues with the temporary power source at this location. Sampler runtimes for the respective dates were 146, 122, 131, 124, and 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months . A partial sample was collected from P-7 for the week ending on 7/23/15 due to a tripped breaker. Sampler runtime was 193 hours0.00223 days 0.0536 hours 3.191138e-4 weeks 7.34365e-5 months . No sample was collected from P-1 for the week ending on 12/29/15 due to a sampler malfunction (3) Leafy Vegetables No leafy vegetables (cabbage) were collected from location P-45 due to health issues of the garden owner.

(4) TLD The TLD at location 031A (ISFSI east inside berm) had a reading of -5.5 mR and was considered to be missing data.

Deviations from the program are summarized in Table 5.3.

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

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

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

Tritium concentrations are determined by liquid scintillation.

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

Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Dep't 5

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 None.

3.6 Land Use Census In accordance with the Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual, H4, (ODCM) a land use census is conducted in order to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 fe producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles. This census is conducted at least once per 12 months between the dates of May 1 and October 31. If new locations yield a calculated dose or dose equivalent (via the same exposure pathway) twenty percent greater than the required locations per the ODCM, then the new locations are added to the radiological environmental monitoring program within 30 days, and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted.

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

The Land Use Census was completed in October, 2015. There were no changes to any of the highest D/Q locations for garden sites, or nearest residence. However, samples were not taken from the garden with the highest D/Q due to the garden owner's health issues. Samples were instead taken from the next closest garden plus a control site.

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

Therefore, no corn samples were collected for analysis.

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

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

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported accidents involving significant release to the environment at nuclear reactor facilities in 2015. The Fukushima Daiichi nuclear accident occurred March 11, 2011.

There were no reported atmospheric nuclear tests in 2015. 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 Prairie Island Nuclear Power Plant during the years 1970 to 1973, to determine background levels expected in the environment, and provided, where applicable, as a means for comparison with present day levels. Strict comparisons, however, are difficult, since background levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross beta measurements in 3 3 fallout declined yearly from a level of 12,167 pCi/ m to 1,020 pCi/ m , and these declining values are reflected throughout the various media tested.

In the air environment, ambient gamma radiation (TLDs) averaged 9.4 mR/4 weeks during pre- 3 operational studies. Gross beta in air particulates declined from levels of3 0.38 to 0.037 pCi/m .

Average present day levels have stabilized at around 0.025 pCi/m . Airborne radioiodine remained below detection levels.

In the terrestrial environment of 1970 to 1973, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-137, 1-131, and Sr-90 were detected. Cs-1371evels declined from 16.5 to 8.6 pCi/L. Present day measurements for both Cs-137 and 1-131 are below detection levels. Agricultural crop measurements averaged 57.7 pCi/g for gross beta and 0.47 pCilg for Cs-137. Gross beta measured in soil averaged 52 pCi/g.

The aqueous environment was monitored by testing of river, well and lake waters, bottom sediments, fish, aquatic vegetation and periphyton. Specific location comparison of drinking, river and well water concentrations for tritium and gross beta are not possible. However, tritium background levels, measured at eight separate locations, declined steadily from an average concentration of 1020 pCi/L to 490 pCi/L. Present day environmental levels of tritium measure below a detection limit of approximately 160 pCi/L. Values for gross beta, measured from 1970 to 1973, averaged 9.9 pCi/L in downstream Mississippi River water, 8.2 pCi/L for well water, and 11.0 pCi/L for lake water. Gamma emitters were below the lower limit of detection (LLD). In bottom sediments, gross beta background levels were determined at 51.0 pCi/g. Cs-137 activity during preoperational studies in 1973 measured 0.25 pCi/g upstream and 0.21 pCi/g downstream. The lower levels occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta in fish, measured in both flesh and skeletal samples, averaged 7.3 and 11.7 pCi!g, respectively. Gross beta background levels in aquatic vegetation, algae and periphyton samples measured 76.0 pCi/g , 46.0 pCi/g, and 13.6 pCi/g, respectively.

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

Ambient Radiation (TLDs)

Ambient radiation was measured in the general area of the site boundary, at the outer ring 4 - 5 mi. distant from the Plant, at special interest areas and at one control location. The means ranged from 15.4 mR/91 days at inner ring locations to 16.4 mR/91 days at outer ring locations.

The mean at special interest locations was 14.9 mR/91 days and 17.4 mR/91 days at the control location. Dose rates measured at the inner and outer ring and the control locations were comparable to 2014 dose rates and consistent with results from previous years. The results are tabulated below. No plant effect on ambient gamma radiation measurements was indicated (Figure 5-1).

Average (Inner and Average (Inner and Year Outer Rinas) Control Year Outer Rinas) Control 1999 16.6 17.5 2008 16.9 17.1 2000 17.0 17.1 2009 15.9 16.3 2001 16.8 17.2 2010 16.0 16.0 2002 17.4 16.9 2011 15.7 15.7 2003 16.2 16.0 2012 16.5 16.2 2004 17.6 17.6 2013 15.1 16.0 2005 16.8 16.3 2014 15.3 16.2 2006 16.6 16.6 2015 16.0 17.4 2007 17.5 17.7 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates (mR/91 days).

ISFSI Facility Operations Monitoring Ambient radiation was measured inside the ISFSI earth berm, outside the ISFSI earth berm and at two special locations between the plant ISFSI and the Prairie Island Indian Community. The mean dose rates averaged 154.6 mR/91 days inside the ISFSI earth berm and 22.1 mR/91 days outside the ISFSI earth berm. Two additional casks were placed on the ISFSI pad in 2015, a total of forty loaded casks remain. The higher levels inside the earth berm are expected, due to the loaded spent fuel casks being in direct line-of-sight of the TLDs.

Ambient radiation levels measured outside the earth berm show a slight increase as compared to other offsite dose rates around the plant. The cumulative average of the two special Prairie Island Indian Community TLDs measured 14.9 and 15.3 mR/91 days. Although the skyshine neutron dose rates are not directly measured, the neutron levels measured next to the casks are below the levels predicted in the ISFSI SAR Report, Table ?A-4, "TN-40 Dose Rates at Short Distances". Therefore, the skyshine dose rates at farther distances from the casks should be at or below the calculated dose rates. No spent fuel storage effect on offsite ambient gamma radiation was indicated (Fig. 5-1).

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Airborne Particulates Typically, the highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 1996 through 2006, and also in 2008 through 2010. The elevated activity observed in 2007 was attributed to construction activity in the area, an increase in dust and consequent heavier particulate filter loading.

3 Average annual gross beta concentrations in airborne particulates were 0.029 pCi/m for both the indicators and the control location and similar to levels observed from 1999 through 2006 and 2008 to 2015. The results are tabulated below.

Average of Year Indicators Control 3

Concentration (oCi/ m )

1999 0.024 0.022 2000 0.025 0.025 2001 0.023 0.023 2002 0.028 0.023 2003 0.027 0.025 2004 0.025 0.026 2005 0.027 0.025 2006 0.026 0.025 2007 0.037 0.031 2008 0.028 0.027 2009 0.029 0.029 2010 0.025 0.025 2011 0.026 0.027 2012 0.031 0.032 2013 0.027 0.028 2014 0.026 0.026 2015 0.029 0.029 Average annual gross beta concentrations in airborne particulates.

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-?, which is produced continuously in the upper atmosphere by cosmic radiation ~Arnold and AI-Salih, 1955) was detected 3in all samples, with an average activity of 0.071 pCi/m for indicator locations and 0.070 pCi/m at the control locations. All other isotopes were below the lower limit of detection.

There was no indication of a plant effect.

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

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lodine-131 results were below a detection limit of 0.5 pCi/L in all samples.

Cs-137 results were below 5 pCi/L in all samples. No other gamma-emitting isotopes, except naturally occurring potassium-40, were detected in any milk sample.

In summary, the data for 2015 show no radiological effects of the plant operation.

Drinking Water In drinking water from the City of Red Wing well, tritium activity measured below a detection limit of 152 pCi/L for all samples.

Gross beta concentrations averaged 11.4 pCi/L throughout the year, ranging from 4.8-15.5 pCi/L.

These concentrations are consistent with levels observed from 1998 through 2014. The most likely contribution is the relatively high levels of naturally-occurring radium. Gamma spectroscopy indicates the presence of lead and bismuth isotopes, which are daughters of the radium decay chain. There is no indication from the 2015 data of any effect of plant operation.

Year Gross Beta (pCi/L) 1999 5.3 2000 10.1 2001 8.3 2002 8.7 2003 9.9 2004 9.8 2005 11.5 2006 13.4 2007 11.6 2008 11.6 2009 11.4 2010 11.7 2011 12.4 2012 11.8 2013 12.2 2014 11.5 2015 11.4 Average annual concentrations; Gross beta in drinking water.

River Water All river water samples measured below an LLD level of 152 pCi/L.

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

In summary, the data for 2015 show no radiological effects from the plant operation.

Well Water Water samples tested from the control well, P-43 (Peterson Farm) and from four indicator wells (P-8, Community Center, P-6, Lock and Dam No. 3, P-9, Plant Well No. 2 and P-24, Suter Farm )

showed no tritium detected above a detection limit of 153 pCi/L. Gamma-emitting isotopes were below detection limits in all samples.

In summary, well water data for 2015 show no radiological effects of the plant operation.

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Crops Two samples of broadleaf vegetation, cabbage leaves, were collected in August, 2015 and analyzed for gamma-emitting isotopes, including iodine-131. The 1-131 level was below 0.021 pCi/g wet weight in all samples. With exceptions for naturally-occurring beryllium-? and potassium-40, all other gamma-emitting isotopes were below their respective detection limits.

There was no indication of a plant effect.

Field sampling personnel conducted an annual land use survey and found no river water taken for irrigation into fields within 5 miles downstream from the Prairie Island Plant. The collection and analysis of corn samples was not required.

Fish were collected in May, June and September, 2015 and analyzed for gamma emitting isotopes. Only naturally-occurring potassium-40 was detected, and there was no significant difference between upstream and downstream results. There was no indication of a plant effect.

Aquatic Insects or Periphyton Aquatic insects (invertebrates) or periphyton were collected in June and September, 2015 and analyzed for gamma-emitting isotopes. All gamma-emitting isotopes measured below detection limits. There was no indication of any plant effect.

Bottom and Shoreline Sediments Upstream and downstream bottom sediments and downstream recreational area shoreline sediments were sampled in May and September, 2015 and analyzed for gamma-emitting isotopes. The only gamma-emitting isotope detected was naturally-occurring potassium-40.

There was no indication of a plant effect.

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5.0 FIGURES AND TABLES 12

Figure 5-1. Offsite Ambient Radiation (TLDs); average of inner and outer ring indicator locations versus control location.

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

-+-Indicators (P-2,3,4,6,7)

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0.039 0.037 ~Elevated due to construction activity 0.035 tl\ !"'--..

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-+--Control (P-1) 0.039 0.037 0.035 0.033 I\

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0 w ()) --1 (X) CD 0 N (11 CD 0 (11 14

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

Collection Analysis Location Type and Type and Medium No. Codes (and Type)" Frequencyb Frequency" Ambient radiation (TLD's) 54 P-01A

P-10A C/Q Ambient gamma P-018 - P-158 P-015

P-085 P-011A

P-081A P-0118

P-0818 P-011X* P-041X, P-01C Airborne Particulates 5 P*1(C}, P-2, C/W GB, GS (QC of P-3, P-4, P-6, P-7 each location)

Airborne Iodine 5 P-1(C}, P-2, P-3, P-4, P-6, P* 7 C/W 1-131 Milk 4 P-37, P-43 (C) G/Md 1-131, GS River water 2 P-5(C}, P-6 G/W GS(MC}, H-3(QC)

Drinking water 1 P-11 G/W GB(MC}, I-131(MC)

GS (MC}, H-3 (QC)

Well water 5 P-6, P-8, P-9, P-24, G/Q H-3, GS P-43 (C)

Edible cultivated crops- 3 P-28, P-38(C}, P-45 G/A GS (1-131) leafy green vegetables Fish (one species, edible portion) 2 P-19(C}, P-13 G/SA GS Periphyton or invertebrates 2 P-40(C}, P-6 G/SA GS Bottom sediment 2 P-20(C}, P-6 G/SA GS Shoreline sediment 1 P-12 G/SA GS

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.

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

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

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

15

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

Distance and Direction 0

Code Type" Collection Site Sample Type from Reactor P-1 c Air Station P-1 AP,AI 11.8 mi@ 316°/NNW P-2 Air Station P-2 AP,AI 0.5 mi@ 294°/WNW P-3 Air Station P-3 AP,AI 0.8 mi@ 313°/NW P-4 Air Station P-4 AP,AI 0.4 mi @ 359°/N P-5 c Upstream of Plant RW 1.8 mi@ 11°/N P-6 Lock and Dam #3 & Air Station P-6 AP,AI,RW ww, BS, BOe 1.6 mi@ 129°/SE P-7 Air Station P-7 AP,AI 0.5 mi@ 271°/W P-8 Community Center ww 1.0 mi@ 321°/WNW P-9 Plant Well #2 ww 0.3 mi@ 306°/NW P-11 Red Wing Service Center DW 3.3 mi@ 158°/SSE P-12 Downstream of Plant ss 3.0 mi @ 116°/ESE P-13 Downstream of Plant Fe 3.5 mi @ 113°/ESE P-18 Christiansen Farm M 3.8 mi@ 88°/E P-19 c Upstream of Plant Fe 1.3 mi@0°/N P-20 c Upstream of Plant BS 0.9 mi@ 45°/NE P-24 Suter Residence ww 0.6 mi @ 158°/SSE P-28 Allyn Residence VE 1.0 mi @ 152°/SSE P-37 Welsch Farm M 4.1 mi@ 87°/E P-38 c Cain Residence VE 14.2 mi@ 359°/N P-40 c Upstream of Plant BOe 0.4 mi@0°/N P-43 c Peterson Farm M,WW 13.9 mi.@ 355°/N P-45 Glazier Residence VE 0.6 mi.@ 341°/NNW General Area of the Site Boundary P-01A Property Line TLD 0.4 mi@ 359°/N P-02A Property Line TLD 0.3 mi@ 10°/N P-03A Property Line TLD 0.5 mi @ 183°/S P-04A Property Line TLD 0.4 mi@ 204°/SWW P-05A Property Line TLD 0.4 mi @ 225°/SW P-06A Property Line TLD 0.4 mi @ 249°/WSW P-07A Property Line TLD 0.4 mi@ 268°/W P-08A Property Line TLD 0.4 mi@ 291°/WNW P-09A Property Line TLD 0.7 mi@317°/NW P-10A Property Line TLD 0.5 mi @ 333°/NNW 16

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

Distance and Direction Code Type" Collection Site Sample Typeb from Reactor Approximately 4 to 5 miles Distant from the Plant P-018 Thomas Killian Residence TLD 4.7 mi@ 355°/N P-028 Roy Kinneman Residence TLD 4.8 mi@ 17°/NNE P-038 Wayne Anderson Farm TLD 4.9 mi@ 46°/NE P-048 Nelson Drive (Road) TLD 4.2 mi@ 61°/ENE P-058 County Road E and Coulee TLD 4.2 mi @ 102°/ESE P-068 William Hauschildt Residence TLD 4.4 mi@ 112°/ESE P-078 Red Wing Public Works TLD 4.7 mi@ 140°/SE P-088 David Wnuk Residence TLD 4.1 mi@ 165°/SSE P-098 Highway 19 South TLD 4.2 mi@ 187°/S P-108 Cannondale Farm TLD 4.9 mi@ 200°/SSW P-118 Wallace Weberg Farm TLD 4.5 mi@ 221°/SW P-128 Ray Gergen Farm TLD 4.6 mi@ 251°/WSW P-138 Thomas O'Rourke Farm TLD 4.4 mi@ 270°/W P-148 David J. Anderson Farm TLD 4.9 mi@ 306°/NW P-158 Holst Farms TLD 3.8 mi @ 345°/NNW Special Interest Locations P-01S Federal Lock & Dam #3 TLD 1.6 mi@ 129°/SE P-02S Charles Suter Residence TLD 0.5 mi@ 155°/SSE P-03S Carl Gustafson Farm TLD 2.2 mi@ 173°/5 P-04S Richard Burt Residence TLD 2.0 mi @ 202°/SSW P-05S Kinney Store TLD 2.0 mi@ 270°/W P-06S Earl Flynn Farm TLD 2.5 mi@ 299°/WNW P-07S Indian Community TLD 0.7 mi@ 271°/W P-08S Indian Community TLD 0.7 mi@ 287°/WNW P-01C c Robert Kinneman Farm TLD 11.1 mi@ 331°/NNW 17

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

Distance and Direction 0

Code Type" Collection Site Sample Type from ISFSI Center.

ISFSI Area Inside Earth Berm P-011A ISFSI Nuisance Fence TLD 190'@ 45°/NE P-021A ISFSI Nuisance Fence TLD 360' @82°/E P-031A ISFSI Nuisance Fence TLD 370'@ 100°/E P-041A ISFSI Nuisance Fence TLD 200'@ 134°/SE P-051A ISFSI Nuisance Fence TLD 180'@ 219°/SW P-061A ISFSI Nuisance Fence TLD 320'@ 258°/WSW P-071A ISFSI Nuisance Fence TLD 320'@ 281°/WNW P-081A ISFSI Nuisance Fence TLD 190' @318°/NW P-011X ISFSI Nuisance Fence TLD 140'@ 180°/S P-021X ISFSI Nuisance Fence TLD 310' @ 270°/W P-031X ISFSI Nuisance Fence TLD 140' @0°/N P-041X ISFSI Nuisance Fence TLD 360' @90°/E ISFSI Area Outside Earth Berm P-011B ISFSI Berm Area TLD 340'@3°/N P-021B ISFSI Berm Area TLD 380'@ 28°/NNE P-031B ISFSI Berm Area TLD 560'@85°/E P-041B ISFSI Berm Area TLD 590'@ 165°/SSE P-051B ISFSI Berm Area TLD 690'@ 186°/S P-061B ISFSI Berm Area TLD 720'@ 201°/SSW P-071B ISFSI Berm Area TLD 610'@ 271°/W P-081B ISFSI Berm Area TLD 360' @332°/NNW

"C" denotes control location. All other locations are indicators.

b Sample Codes:

AP Airborne particulates F Fish AI Airborne Iodine M Milk BS Bottom (river) sediments SS Shoreline Sediments BO Bottom organisms SW Surface Water (periphyton or macroinvertebrates) VE Vegetation/vegetables DW Drinking water WW Well water "Distance and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location.

18

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

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

Collection Reason for not Sample Analysis Location Date or conducting REMP Plans for Preventing Type Period as required Recurrence Ml Gamma, 1-131 P-37 1/13/2015 Welsch Farm has temporarily None required.

2/11/2015 suspended milking operations 3/4/2015 AP/AI Beta, 1-131 P-2 2/25/2015 Lost temporary power for Permanent power greater than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to be installed.

AP/AI Beta, 1-131 P-2 6/2/2015 Lost temporary power for Permanent power greater than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to be installed.

APIA I Beta, 1-131 P-7 7/23/2015 Lost temporary power for Permanent power greater than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to be installed.

APIA I Beta, 1-131 P-2 7/29/2015 Lost temporary power for Permanent power greater than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to be installed.

LV Gamma, 1-131 P-45 8/18/2015 Garden owner had health None required.

issues.

AP/AI Beta, 1-131 P-2 9/9/2015 Lost temporary power for Permanent power greater than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to be installed.

AP/AI Beta, 1-131 P-2 12/22/2015 Lost temporary power for Permanent power greater than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to be installed.

AP/AI Beta, 1-131 P-1 12/29/2015 Sample pump malfunction. Sampler was replaced.

TLD Gamma 031A 10/1/15- TLD reading was unacceptable Replaced TLD 12/31/2015 19

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282' 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2015 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-0 0 0 Type Number of LLDb Mean (F) Mean (F) Mean (F) Routine 0 0 0 (Units) Analyses* Range Locationd Range Range Results*

Direct Radiation TLD (Inner Ring, Gamma 40 3.0 15.4 (40/40) P-05A 17.3 (4/4) (See Control 0 Area at Site ( 12.3-20.9) 0.4 mi @ 225° /SW (15.4-19.7) below.)

Boundary) mR/91 days)

TLD (Outer Ring, Gamma 60 3.0 16.4 (60/60) P-038 18.3 (4/4) (See Control 0 4-5 mi. distant) ( 12.0-20.9) 4.9 mi@ 46°/NE (15.8-19.7) below.)

mR/91 days)

TLD (Special Gamma 32 3.0 14.9 (32/32) P-03S, Gustafson Farm, 16.4 (4/4) (See Control 0 Interest Areas) (12.3-19.0) 2.2 mi@ 173° /S (14.4-18) below.)

mR/91 days)

TLD (Control) Gamma 4 3.0 None P-01C, Robert Kinneman 17.4 (4/4) 17.4 (4/4) 0 mR/91 days) 11.1 mi@ 331° /NNW (15.6-18.8) (15.6-18.8)

Airborne Pathway Airborne GB 312 0.005 0.029 (260/260) P-02, Air Station 0.030 (52 /52) 0.029 (51/51) 0 Particulates (0.01 0-0.072) 0.5 mi @ 294° /WNW (0.010-0.071) (0.012-0.057) 3 (pCi/m )

GS 24 Be-7 0.015 0.071 (20/20) P-06, Air Station 0.076 (4/4) 0.070 (4/4) 0 (0.048-0.094) 1.6 mi @ 259° /SE (0.057-0.087) (0.042-0.083)

Mn-54 0.0008 < LLD - - < LLD 0 Co-58 0.0008 < LLD - - < LLD 0 Co-60 0.0007 < LLD - - < LLD 0 Zn-65 0.0015 < LLD - - < LLD 0 Zr-Nb-95 0.0009 < LLD - - < LLD 0 Ru-103 0.0013 < LLD - - < LLD 0 Ru-106 0.0072 < LLD - - < LLD 0 Cs-134 0.0008 < LLD - - < LLD 0 Cs-137 0.0007 < LLD - - < LLD 0 Ba-La-140 0.0035 < LLD - - < LLD 0 Ce-141 0.0018 < LLD - - < LLD 0 Ce-144 0.0046 < LLD - - < LLD 0 Airborne Iodine 1-131 312 0.030 < LLD - - < LLD 0 3

(pCi/m )

20

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2015 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-0 Type Number of LLDb Mean (F)" Mean (F) 0 Mean (F) Routine (Units) Analyses* Range 0

Locationd Range 0 Range0 Results*

Terrestrial Pathway Milk (pCi/L) 1-131 33 0.5 < LLD - - < LLD 0 GS 33 K-40 200 1458 (15/15) P-37, Welsch Farm 1458 (15/15) 1436 (18/18) 0 (1364-1548) 4.1 mi@ ar /E (1364-1548) (1333-1503)

Cs-134 5 < LLD - - < LLD 0 Cs-137 5 < LLD - - < LLD 0 Ba-La-140 5 < LLD - - < LLD 0 Crops - Cabbage 1-131 2 0.021 < LLD - - < LLD 0 (pCilgwet)

Well Water H-3 20 153 < LLD - - < LLD 0 (pCi/L)

GS 20 Mn-54 10 < LLD - - < LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 10 < LLD - - < LLD 0 Co-60 10 < LLD - - < LLD 0 Zn-65 30 < LLD - - < LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD - - < LLD 0 Cs-137 10 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 41 < LLD - - < LLD 0 21

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2015 (County, State)

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

Number of Analyses* Range 0 Locationd I Range0 Range 0 Results" Waterborne Pathway Drinking Water GB 12 1.0 11.4 (11/12) P-11, Red Wing S.C. 11.4 (11/12) None 0 (pCi!L) (4.8-15.5) 3.3 mi@ 158° /SSE (4.8-15.5) 1-131 12 1.0 < LLD - - None 0 H-3 4 152 < 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 River Water H-3 8 152 < LLD - - < LLD 0 (pCi/L) -

GS 24 Mn-54 10 < LLD - - < LLD 0 Fe-59 30 < LLD - - < LLD 0 Co-58 10 < LLD - - < LLD 0 Co-60 10 < LLD - - < LLD 0 Zn-65 30 < LLD - - < LLD 0 Zr-Nb-95 15 < LLD - - < LLD 0 Cs-134 10 < LLD - - < LLD 0 Cs-137 10 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 46 < LLD - - < LLD 0 Fish GS 6 (pCi/g wet) K-40 0.10 2.98 (6/6) P-19, Upstream 3.41 (6/6) 3.41 (6/6) 0 (2.74-3.24) 1.3 mi@ 0°/N (3.04-3.67) (3.04-3.67)

Mn-54 0.024 < LLD - - < LLD 0 Fe-59 0.093 < LLD - - < LLD 0 Co-58 0.025 < LLD - - < LLD 0 Co-60 0.021 < LLD - - < LLD 0 Zn-65 0.050 < LLD - - < LLD 0 Zr-Nb-95 0.069 < LLD - - < LLD 0 Cs-134 0.025 < LLD - - < LLD 0 Cs-137 0.026 < LLD - - < LLD 0 Ba-La-140 0.420 < LLD - - < LLD 0 22

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282' 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2015

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F) 0 Mean (F)" Mean (F)" Routine (Units) Analyses" Range 0 Locationd Range0 Range0 Results*

Waterborne Pathway Invertebrates GS 4 (pCi/g wet) Be-7 0.79 < LLD - - < LLD 0 K-40 1.87 1.87 (1/1) P-40 Upstream 1.87 (1/1) 1.87 (1/1) 0 (1.87) 0.4 mi@ 0° IN (1.87) (1.87)

Mn-54 0.075 < LLD - - < LLD 0 Co-58 0.076 < LLD - - < LLD 0 Co-60 0.066 < LLD - - < LLD 0 Zn-65 0.12 < LLD - - < LLD 0 Zr-Nb-95 0.14 < LLD - - < LLD 0 Ru-103 0.13 < LLD - - < LLD 0 Ru-106 0.43 < LLD - - < LLD 0 Cs-134 0.060 <LLD - - < LLD 0 Cs-137 0.065 < LLD - - < LLD 0 Ba-La-140 0.36 < LLD - - < LLD 0 Ce-141 0.16 < LLD - - < LLD 0 Ce-144 0.24 < LLD - - < LLD 0 Bottom and GS 6 Shoreline Be-7 0.19 < LLD P-20 Upstream (C) - 0.48 (1/2) 0 Sediments 0.9 mi @ 45° I NE (0.48)

(pCi/g dry) K-40 0.10 7.69 (4/4) P-26, Lock & Dam No. 3 8.00 (2/2) 9.81 (2/2) 0 (6.22-9.32) 1.6 mi@ 129°/SE (6.68-9.32) (9.61-10.00)

Mn-54 0.016 < LLD - - < LLD 0 Co-58 0.025 < LLD - - < LLD 0 Co-60 0.015 < LLD - - < LLD 0 Zn-65 0.046 < LLD - - < LLD 0 Zr-Nb-95 0.034 < LLD - - < LLD 0 Ru-103 0.024 < LLD - - < LLD 0 Ru-106 0.14 < LLD - - < LLD 0 Cs-134 0.015 < LLD - - < LLD 0 Cs-137 0.019 < LLD - - < LLD 0 Ba-La-140 0.07 < LLD - - < LLD 0 Ce-141 O.D7 < LLD - - < LLD 0 Ce-144 0.12 < LLD - - < LLD 0 a GB = gross beta, GS =gamma scan.

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

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

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

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 times the typical preoperational value for the medium or location.

23

6.0 REFERENCES

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

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

Environmental, Inc., Midwest Laboratory.

____ 2001a through 2014a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2014.

, 2001b through 2014b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January- December, 2000 through 2014.

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

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

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

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

= 1979a to 1983a. (formerly Hazleton Environmental Sciences Corporation) Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1978 through 1982.

: 1979b to 1983b. (formerly Hazleton Environmental Sciences Corporation) Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January -

December, 1978 through 1982.

_ _ _ _ 2012. 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, Chicago, Illinois, 369-382.

Northern States Power Company.

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

= 1979 to 2008. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1978 through 2007.

Minneapolis, Minnesota.

Prairie Island Nuclear Generating Plant, 2013. Radiological Environmental Monitoring for Prairie Island Nuclear Generating Plant, Radiation Protection Implementing Procedures, 4700 series.

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

24

6.0 REFERENCES

CITED (continued)

U.S. Environmental Protection Agency.

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

---~ 1984. Eastern Environmental Radiation Facility, Radiochemistry Procedures Manual, Montgomery, Alabama (EPA-520/5-84-006).

---~ 2012. RadNet, formerly Environmental Radiation Ambie.nt Monitoring System, Gross Beta in Air, Gross Beta in Drinking Water (MN) 1981-2009.

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 2015. Monticello Nuclear Generating Plant, Annual Radiological Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2014.

Minneapolis, Minnesota.

- - - - : 2009 to 2015. Prairie Island Nuclear Generating Plant, Annual Radiological Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2014.

Minneapolis, Minnesota.

25

~*' All Environmental, Inc.

~+ll.l"\1 Midwest Laboratory 700 Landwehr Road

Northbrook, /L 60062-2310 phone (847) 564-0700

fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD lntercomparison 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, 2015 through December, 2015

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

Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.

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

Table A-2 lists results for thermoluminescent dosimeters (TLDs), via internal laboratory testing and by irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Labor.atory at the University of Wisconsin Medical Radiation Research Center.

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.

A1

Attachment A ACCEPTANCE CRITERIA FOR "SPIKED" SAMPLES 8

LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pCilliter 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-9Gb 2 to 30 pCi/liter or kg 5.0 pCi/liter

> 30 pCi/liter or kg 10%.of known value Potassium-40 2 0.1 g/liter or kg 5% of known value Gross alpha :5 20 pCilliter 5.0 pCi/liter

> 20 pCilliter 25% of known value Gross beta :5 100 pCi/liter 5.0 pCi/liter

> 100 pCi/liter 5% of known value Tritium :5 4,000 pCilliter +/- 1o =

0933 169.85 x (known) 0*

> 4,000 pCi/liter 10% of known value Radium-226,-228 2 0.1 pCilliter 15% of known value Plutonium 2 0.1 pCilliter, gram, or sample 10% of known value lodine-131, :5 55 pCilliter 6 pCi/liter lodine-129b > 55 pCi/liter 10% of known value Uranium-238, :5 35 pCi/liter 6 pCi/liter Nickel-63b > 35 pCi/liter 15% of known value Technetium-99b lron-55b 50 to 100 pCi/liter 10 pCi/liter

> 100 pCilliter 10% of known value Other Analyses b 20% of known value a From EPA publication, "Environmental Radioactivity Laboratory lntercomparison Studies Program, Fiscal Year, 1981-1982, EPA-600/4-81-004.

b Laboratory limit.

A2

8 TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1444 4/6/2015 Sr-89 59.71 +/- 5.44 63.20 51.10 -71.20 Pass ERW-1444 4/6/2015 Sr-90 43.41 +/- 2.43 41.90 30.80 - 48.10 Pass ERW-1448 4/6/2015 Ba-133 77.75 +/- 4.69 82.50 69.30 - 90.80 Pass ERW-1448 4/6/2015 Cs-134 68.82 +/- 3.08 75.70 61.80 - 83.30 Pass ERW-1448 4/6/2015 Cs-137 191.9 +/-5.9 189.0 170.0 - 210.0 Pass ERW-1448 4/6/2015 Co-60 85.05 +/- 4.59 84.50 76.00 - 95.30 Pass ERW-1448 4/6/2015 Zn-65 196.0 +/- 12.0 203.0 183.0 - 238.0 Pass ERW-1450 4/6/2015 Gr. Alpha 34.05 +/- 1.90 42.60 22.10 - 54.00 Pass ERW-1450 4/6/2015 G. Beta 26.93 +/- 1.12 32.90 21.30-40.60 Pass ERW-1453 4/6/2015 1-131 22.47 +/- 0.83 23.80 19.70-28.30 Pass ERW-1456 4/6/2015 Ra-226 8.20 +/- 0.56 8.43 6.33-9.90 Pass ERW-1456 4/6/2015 Ra-228 5.00 +/- 0.67 4.39 2.56- 6.01. Pass ERW-1456 4/6/2015 Uranium 5.98 +/- 0.31 6.59 4.99 - 7.83 Pass ERW-1461 4/6/2015 H-3 3,254 +/- 180 3280 2,770 - 3,620 Pass ERW-5528 10/5/2015 Sr-89 34.76 +/- 0.06 35.70 26.70 - 42.50 Pass ERW-5528 10/5/2015 Sr-90 29.23 +/- 0.06 31.10 22.70-36.10 Pass ERW-5531 10/5/2015 Ba-133 30.91 +/- 0.53 32.50 25.90 - 36.70 Pass ERW-5531 10/5/2015 Cs-134 57.40 +/- 2.57 62.30 50.69 - 68.50 Pass ERW-5531 10/5/2015 Cs-137 163.1 +/- 4.8 157.0 141.0 -175.0 Pass ERW-5531 10/5/2015 Co-60 73.41 +/-1.72 71.10 64.00 - 80.70 Pass ERW-5531 10/5/2015 Zn-65 138.9 +/- 5.7 126.0 113.0 - 149.0 Pass ERW-5534 10/5/2015 Gr. Alpha 29.99 +/- 0.08 51.60 26.90 - 64.70 Pass ERW-5534 10/5/2015 G. Beta 27.52 +/- 0.04 36.60 24.10 - 44.20 Pass ERW-5537 10/5/2015 1-131 25.54 +/- 0.60 26.30 21.90 - 31.00 Pass ERW-5540 10/5/2015 Ra-226 7.32 +/- 0.37 7.29 5.49-8.63 Pass ERW-5540d 10/5/2015 Ra-228 7.80 +/- 0.02 4.25 2.46-5.85 Fail 9

ERW-5540 10/5/2015 Ra-228 4.45 +/- 0.96 4.25 2.46-5.85 Pass ERW-5540 10/5/2015 Uranium 53.30 +/- 0.55 56.20 45.70 -62.40 Pass ERW-5543 10/5/2015 H-3 21,260 +/- 351 21,300 18,700 -23,400 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

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

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

d Ra-228 spike was at a level close to the detection level. The high result was likely caused by interference from short-lived Rn-222 daughters.

The result of reanalysis (Compare to original result, footnoted "e" above).

A1-1

a TABLE A-2.1. Thermoluminescent Dosimetry, (TLD, CaS0 4: Dy Cards).

mR Lab Code Irradiation Known Lab Control Date Description Value Result Limits Acceptance Environmental, Inc.

2015-1 6/24/2015 30 em. 98.81 103.67 +/- 6.05 69.20 - 128.50 Pass 2015-1 6/24/2015 30 em. 98.81 111.32 +/- 15.97 69.20 - 128.50 Pass 2015-1 6/24/2015 60 em. 24.70 27.23 +/- 1.33 17.30-32.10 Pass 2015-1 6/24/2015 60 em. 24.70 26.98 +/- 4.98 17.30-32.10 Pass 2015-1 6/24/2015 120 em. 6.18 6.71 +/- 1.77 4.30-8.00 Pass 2015-1 6/24/2015 120 em. 6.18 6.78 +/- 0.38 4.30-8.00 Pass 2015-1 6/24/2015 120 em. 6.18 6.43 +/- 2.00 4.30-8.00 Pass 2015-1 6/24/2015 150 em. 3.95 4.13 +/- 0.72 2.80-5.10 Pass 2015-1 6/24/2015 150 em. 3.95 4.12 +/- 1.36 2.80-5.10 Pass 2015-1 6/24/2015 150 em. 3.95 4.50 +/- 1.51 2.80-5.10 Pass 2015-1 6/24/2015 180 em. 2.74 3.27 +/- 0.28 1.90-3.60 Pass 2015-1 6/24/2015 180 em. 2.74 3.05+/-1.11 1.90-3.60 Pass 2015-1 6/24/2015 180 em. 2.74 3.14 +/- 0.18 1.90-3.60 Pass A2-1

TABLE A-2.2 Thermoluminescent Dosimetry, (TLD, CaS0 4 : Dy Cards). b mrem Lab Code Irradiation Delivered Reported Performance c Date Description Dose Dose Quotient (P) Acceptance d Environmental, Inc.

2015-2 12/15/2015 Spike 1 138.0 118.5 +/-2.1 -0.14 Pass 2015-2 12/15/2015 Spike 2 138.0 120.0 +/- 1.6 -0.13 Pass 2015-2 12/15/2015 Spike 3 138.0 121.9 +/- 1.9 -0.12 Pass 2015-2 12/15/2015 Spike 4 138.0 124.5 +/- 3.3 -0.10 Pass 2015-2 12/15/2015 Spike 5 138.0 126.5 +/- 3.2 -0.08 Pass 2015-2 12/15/2015 Spike 6 138.0 140.0 +/- 4.2 0.01 Pass 2015-2 12/15/2015 Spike 7 138.0 128.2 +/- 1.2 -0.07 Pass 2015-2 12/15/2015 Spike 8 138.0 128.0 +/- 4.0 -0.07 Pass 2015-2 12/15/2015 Spike 9 138.0 124.9 +/- 5.1 -0.09 Pass 2015-2 12/15/2015 Spike 10 138.0 122.9 +/- 3.0 -0.11 Pass 2015-2 12/15/2015 Spike 11 138.0 123.3 +/- 3.0 -0.11 Pass 2015-2 12/15/2015 Spike 12 138.0 119.0 +/- 3.4 -0.14 Pass 2015-2 12/15/2015 Spike 13 138.0 123.0 +/- 2.7 -0.11 Pass 2015-2 12/15/2015 Spike 14 138.0 125.4 +/- 2.0 -0.09 Pass 2015-2 12/15/2015 Spike 15 138.0 122.0+/-3.1 -0.12 Pass 2015-2 12/15/2015 Spike 16 138.0 120.8 +/- 2.0 -0.12 Pass 2015-2 12/15/2015 Spike 17 138.0 118.8 +/- 1.1 -0.14 Pass 2015-2 12/15/2015 Spike 18 138.0 117.0 +/-2.3 -0.15 Pass 2015-2 12/15/2015 Spike 19 138.0 120.8 +/- 2.6 -0.12 Pass 2015-2 12/15/2015 Spike 20 138.0 122.6 +/- 3.0 -0.11 Pass Mean (Spike 1-20) 123.4 0.11 Pass Standard Deviation (Spike 1-20) 5.0 0.04 Pass

TLD's were irradiated at Environmental Inc. Midwest Laboratory. (Table A-2.1) b TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.(Table A-2.2) c Performance Quotient (P) is calculated as ((reported dose- conventially true value) + conventially true value) where the conventially true value is the delivered dose.

d Acceptance is achieved when neither the absolute value of mean of the P values, nor the standard deviation of the P values exceed 0.15.

e Tables A2.1 and A2.2 assume 1 roentgen = 1 rem (per NRC -Health Physics Positions Based on 10 CFR Part 20- Question 96 -Page Last Reviewed/Updated Thursday, October 01, 2015).

A2-2

TABLE A-3. In-House "Spiked" Samples 8

Concentration (pCi/L)

Lab Code b Date Analysis Laboratory results Known Control 2s, n=1° Activity Limits ct Acceptance W-020315 2/3/2015 Ra-226 16.19 +/- 0.42 16.70 13.36 - 20.04 Pass W-021215 2/12/2015 Gr. Alpha 18.38 +/- 0.39 20.10 16.08-24.12 Pass W-021215 2/12/2015 Gr. Beta 27.98 +/- 0.32 30.90 24.72 - 37.08 Pass SPW-687 2/27/2015 Ni-63 239.6 +/- 3.5 202.4 161.9-242.9 Pass SPAP-689 3/2/2015 Gr. Beta 42.37 +/- 3.50 43.61 34.89 - 52.33 Pass SPAP-691 3/2/2015 Cs-134 1.77 +/- 0.61 1.90 1.52-2.28 Pass SPAP-691 3/2/2015 Cs-137 83.02 +/- 2.60 97.20 77.76 - 116.64 Pass SPW-693 3/2/2015 Cs-134 44.30 +/- 2.53 53.40 42.72 - 64.08 Pass SPW-693 3/2/2015 Cs-137 74.82 +/- 3.50 73.80 59.04 - 88.56 Pass SPW-693 3/2/2015 Sr-89 87.45 +/- 3.62 87.48 69.98 - 104.98 Pass SPW-693 3/25/2015 Sr-90 37.22 +/- 1.55 38.10 30.48 - 45.72 Pass SPMI-697 3/2/2015 Cs-134 96.67 +/- 7.74 107.00 85.60 - 128.40 Pass SPMI-697 3/2/2015 Cs-137 78.51 +/- 7.02 73.84 59.07 - 88.61 Pass SPMI-697 3/2/2015 Sr-89 72.98 +/- 4.86 87.48 69.98 - 104.98 Pass SPMI-697 3/2/2015 Sr-90 39.17+/-1.51 38.10 30.48 -45.72 Pass SPW-699 3/2/2015 H-3 59,592 +/- 703 58,445 46,756 -70,134 Pass W-031115 3/11/2015 Ra-226 13.73 +/- 0.35 16.70 13.36 -20.04 Pass W-030215 3/2/2015 Ra-228 32.79 +/- 2.31 31.44 25.15-37.73 Pass SPF-1040 3/16/2015 Cs-134 787.5 +/- 9.2 840.0 672.0 - 1,008.0 Pass SPF-1040 3/16/2015 Cs-137 2,599 +/- 24 2,360 1,888 - 2,832 Pass SPW-1036 3/25/2015 Fe-55 1,792 +/- 63 1961 1,569 - 2,353 Pass SPW-1374 4/6/2015 U-238 46.03 +/- 2.25 41.70 25.02 - 58.38 Pass W-040815 4/8/2015 Gr. Alpha 20.18 +/-0.42 20.10 16.08-24.12 Pass W-040815 4/8/2015 Gr. Beta 29.70 +/- 0.33 30.90 24.72 - 37.08 Pass SPW-1038 4/13/2015 C-14 3,497 +/-9 4,734 2,840 - 6,628 Pass W-2165 4/20/2015 H-3 5550 +/- 226 5,780 3,468 - 8,092 Pass W-2165 4/20/2015 Sr-89 90.70 +/- 8.20 108.70 65.22 -152.18 Pass W-2165 4/20/2015 Sr-90 76.80 +/- 2.00 75.90 45.54 - 106.26 Pass W-2165 4/20/2015 Cs-134 62.40 +/- 6.40 57.30 34.38 - 80.22 Pass W-2165 4/20/2015 Cs-137 91.30 +/- 7.70 84.00 50.40 -117.60 Pass W-2392 4/13/2015 H-3 5032 +/- 214 5780 3468-8092 Pass W-2392 4/13/2015 Ni-63 222.4 +/- 3.8 202.0 121.2 - 282.8 Pass W-2392 4/13/2015 Cs-134 53.26 +/- 5.01 57.30 34.38 - 80.22 Pass W-2392 4/13/2015 Cs-137 91.90 +/- 7.76 84.20 50.52 - 117.88 Pass W-042415 4/24/2015 Ra-226 12.52 +/- 0.39 16.70 10.02 - 23.38 Pass W-050715 5/7/2015 Gr. Alpha 19.05 +/- 0.41 20.10 12.06-28.14 Pass W-050715 5/7/2015 Gr. Beta 27.30 +/- 0.32 30.90 18.54 - 43.26 Pass W-061215 6/12/2015 Gr. Alpha 20.72 +/- 0.44 20.10 12.06 -28.14 Pass W-061215 6/12/2015 Gr. Beta 28.51 +/- 0.33 30.90 18.54 - 43.26 Pass U-2982 6/9/2015 Gr. Beta 500.1 +/- 5.1 604.0 362.4 - 845.6 Pass U-3200 6/9/2015 H-3 2229 +/- 424 2346 1408-3284 Pass W-70915 7/9/2015 Gr. Alpha 18.76 +/- 0.40 20.10 12.1-28.1 Pass W-70915 7/9/2015 Gr. Beta 29.71 +/- 0.33 30.90 18.5-43.3 Pass SPAP-3859 7/21/2015 Gr. Beta 41.59 +/- 0.12 43.61 26.17-61.05 Pass SPAP-3861 7/21/2015 Cs-134 1.69 +/- 0.60 1.69 1.0 -2.4 Pass A3-1

TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)"

Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPAP-3861 7/21/2015 Cs-137 93.71 +/- 2.64 96.45 57.87- 135.03 Pass SPMI-3863 7/21/2015 Cs-134 38.21 +/-5.12 47.02 28.21 -65.83 Pass SPMI-3863 7/21/2015 Cs-137 78.65 +/- 7.94 73.18 43.91 - 102.45 Pass SPMI-3863 7/21/2015 Sr-90 41.05 +/- 1.62 37.78 22.67 - 52.89 Pass SPW-3871 7/21/2015 Cs-134 45.59 +/- 6.39 47.02 28.21 - 65.83 Pass SPW-3871 7/21/2015 Cs-137 78.73 +/- 7.03 73.18 43.91 - 102.45 Pass SPW-3871 7/21/2015 Sr-90 38.36 +/- 1.58 37.78 22.67 - 52.89 Pass SPW-3873 7/21/2015 H-3 60,034 +/- 671 57,199 34,319-80,079 Pass SPW-3875 7/21/2015 Ni-63 451.3 +/- 3.3 403.7 242.2 - 565.2 Pass SPW-3877 7/21/2015 Tc-99 483.0 +/- 8.3 539.1 323.5 - 754.7 Pass SPMI-3879 7/21/2015 C-14 4,921 +/- 19 4,736 2,842 - 6,630 Pass SPS0-4037 7/21/2015 Ni-63 42,458 +/- 309 40,370 24,222-56,518 Pass SPW-072515 7/17/2015 Ra-228 35.48 +/-3 31.44 18.86-44.02 Pass SPF-4104 7/29/2015 Cs-134 661.5 +/- 115.9 740.0 444.0 -1036.0 Pass SPF-4104 7/29/2015 Cs-137 2,469 +/-59 2,340 1,404 - 3,276 Pass SPW-81015 8/10/2015 Gr. Alpha 21.59 +/- 0.46 20.10 12.06-28.14 Pass SPW-81015 8/10/2015 Gr. Beta 27.58 +/- 0.32 30.90 18.54-43.26 Pass SPW-81315 8/13/2015 Ra-226 15.05 +/- 0.36 16.70 10.02-23.38 Pass SPW-90615 9/6/2015 Gr. Alpha 18.32 +/- 0.40 20.10 12.06 - 28.14 Pass SPW-90615 9/6/2015 Gr. Beta 29.43 +/- 0.33 30.90 18.54 - 43.26 Pass W-091415 9/14/2015 Gr. Alpha 19.35 +/- 0.51 20.10 12.06 - 28.14 Pass W-091415 9/14/2015 Gr. Beta 31.53 +/- 0.35 30.90 18.54 - 43.26 Pass W-100815 10/8/2015 Ra-228 12.27 +/- 0.33 16.70 10.02-23.38 Pass W-100615 10/6/2015 Gr. Alpha 20.62 +/- 0.43 20.10 12.06-28.14 Pass W-100615 10/6/2015 Gr. Beta 29.35 +/- 0.33 30.90 18.54-43.26 Pass W-5277 10/16/2015 H-3 5,224 +/- 218 5,466 3,280 - 7,652 Pass W-5277 10/16/2015 Cs-134 99.40 +/- 6.64 99.20 59.52- 138.88 Pass W-5277 10/16/2015 Cs-137 89.60 +/- 6.64 83.20 49.92 - 116.48 Pass W-110415 11/4/2015 Ra-226 12.27 +/- 0.33 16.70 10.02-23.38 Pass W-111115 11/11/2015 Ra-228 31.78 +/-2.48 31.44 18.86-44.02 Pass W-6086,6087 11/18/2015 H-3 10,882 +/- 309 11,231 6,738- 15,723 Pass W-6086,6087 11/18/2015 Cs-134 92.98 +/- 7.29 96.25 57.75 - 134.75 Pass W-6086,6087 11/18/2015 Cs-137 76.65 +/- 7.81 82.94 49.76-116.12 Pass W-112515 11/25/2015 Gr. Alpha 20.91 +/- 0.52 20.10 12.06-28.14 Pass W-112515 11/25/2015 Gr. Beta 31.59 +/- 0.35 30.90 18.54-43.26 Pass W-120715 12/7/2015 Fe-55 2,431 +/- 97 2,319 1,391 - 3,247 Pass W-120815 12/8/2015 Gr. Alpha 20.72 +/- 0.43 20.10 12.06-28.14 Pass W-120815 12/8/2015 Gr. Beta 29.50 +/- 0.33 30.90 18.54 - 43.26 Pass W-121515 12/15/2015 Ra-226 14.77 +/- 0.42 16.70 10.02-23.38 Pass

Liquid sample results are reported in pCi/Liter, air filters( pCi/m3}, charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

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+/- 2s.

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 (4.66cr) Acceptance Type LLD Activity" Criteria (4.66 cr)

W-020315 Water 2/3/2015 Ra-226 0.03 0.03 +/- 0.02 W-021215 Water 2/12/2015 Gr. Alpha 0.47 -0.37 +/- 0.30 2 W-021215 Water 2/12/2015 Gr. Beta 0.76 -0.62 +/- 0.51 4 SPW-686 Water 2/27/2015 Ni-63 2.36 -0.74 +/- 1.42 20 SPAP-688 Air Particulate 3/2/2015 Gr. Beta 0.003 -0.001 +/- 0.002 0.01 SPAP-690 Air Particulate 3/2/2015 Cs-134 0.006 0.428 +/- 0.927 0.05 SPAP-690 Air Particulate 3/2/2015 Cs-137 0.006 -0.785 +/- 1.146 0.05 W-030215 Water 3/2/2015 Ra-228 0.76 0.22 +/- 0.38 2 SPW-692 Water 3/2/2015 Cs-134 6.70 -1.57 +/- 3.55 10 SPW-692 Water 3/2/2015 Cs-137 6.18 -0.15 +/-3.20 10 SPW-692 Water 3/2/2015 Sr-89 0.61 -0.51 +/- 0.51 5 SPW-692 Water 3/2/2015 Sr-90 0.60 0.38 +/- 0.33 1 SPMI-696 Milk 3/2/2015 Cs-134 3.75 -0.25 +/- 2.24 10 SPMI-696 Milk 3/2/2015 Cs-137 4.36 -0.25 +/- 2.24 10 SPMI-696 Milk 3/2/2015 Sr-89 0.80 -0.40 +/- 0.84 5 SPMI-696 Milk 3/2/2015 Sr-90 0.49 0.98 +/- 0.32 1 SPW-698 Water 3/2/2015 H-3 144.0 28.6 +/- 88.9 200 SPW-1035 Water 3/16/2015 Fe-55 599.7 72.6 +/- 368.1 1000 SPW-1037 Water 3/16/2015 C-14 8.94 2.16 +/-5.47 200 SPF-1039 Fish 3/16/2015 Cs-134 13.54 -1.00 +/- 6.80 100 SPF-1039 Fish 3/16/2015 Cs-137 9.80 4.87 +/- 7.00 100 W-040615 Water 4/6/2015 Ra-226 0.04 0.01 +/- 0.03 2 W-1373 Water 4/6/2015 U-238 0.08 0.01 +/- 0.01 W-1375 Water 4/6/2015 Pu-238 0.03 0.00 +/- 0.01 W-050715 Water 5/7/2015 Gr. Alpha 0.38 -0.10 +/-0.25 2 W-050715 Water 5/7/2015 Gr. Beta 0.74 -0.14 +/- 0.51 4 W-061215 Water 6/12/2015 Gr. Alpha 0.42 -0.10 +/- 0.29 2 W-061215 Water 6/12/2015 Gr. Beta 0.75 -0.04 +/- 0.53 4 SPW-3858 Water 7/21/2015 Gr. Beta 0.003 0.004 +/- 0.002 2 SPAP-3860 Air Particulate 7/21/2015 Cs-134 0.011 0.010 +/- 0.005 0.05 SPAP-3860 Air Particulate 7/21/2015 Cs-137 0.009 0.000 +/- 0.005 0.05 SPMI-3862 Milk 7/21/2015 Cs-134 3.13 1.56 +/- 1.74 10 SPMI-3862 Milk 7/21/2015 Cs-137 3.20 1.69 +/- 1.89 10 SPMI-3862 Milk 7/21/2015 Sr-89 2.17 -1.30 +/- 2.05 5 SPMI-3862 Milk 7/21/2015 Sr-90 0.90 0.74 +/- 0.50 1 SPW-3870 Water 7/21/2015 Cs-134 3.01 0.71 +/- 1.66 10 SPW-3870 Water 7/21/2015 Cs-137 3.94 0.81 +/- 1.86 10 SPW-3870 Water 7/21/2015 Sr-89 2.28 -0.42 +/- 1.80 5 SPW-3870 Water 7/21/2015 Sr-90 0.84 0.25 +/- 0.42 1 A4-1

TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)"

Lab Code Sample Date Analysisb Laboratory results (4.66cr) Acceptance 0

Type LLD Activity Criteria (4.66 cr)

SPW-3872 Water 7/21/2015 H-3 142.6 82.7 +/- 79.4 200 SPW-3874 Water 7/21/2015 Ni-63 2.98 0.77 +/- 1.82 20 SPW-3876 Water 7/21/2015 Tc-99 5.49 -3.81 +/- 3.26 10 SPW-3878 Water 7/21/2015 C-14 17.06 8.52 +/- 10.54 200 SPS0-4036 Soil 7/21/2015 Ni-63 135.7 51.3 +/- 83.0 1000 SPF-4103 Fish 7/29/2015 Cs-134 14.17 -37.70 +/- 9.67 100 SPF-4103 Fish 7/29/2015 Cs-137 12.39 1.13 +/- 8.06 100 W-081015 Water 8/10/2015 Gr. Alpha 0.48 -0.10 +/- 0.33 2 W-081015 Water 8/10/2015 Gr. Beta 0.78 -0.18 +/- 0.54 4 W-081815 Water 8/18/2015 Ra-226 0.03 0.03 +/- 0.02 2 W-090615 Water 9/6/2015 Gr. Alpha 0.40 0.00 +/- 0.28 2 W-090615 Water 9/6/2015 Gr. Beta 0.77 0.22 +/- 0.54 4 W-091415 Water 9/14/2015 Gr. Alpha 0.41 0.10 +/- 0.30 2 W-091415 Water 9/14/2015 Gr. Beta 0.77 0.04 +/- 0.54 4 W-100615 Water 10/6/2015 Gr. Alpha 0.41 -0.15 +/- 0.27 2 W-100615 Water 10/6/2015 Gr. Beta 0.75 -0.12 +/-0.52 4 W-112515 Water 11/25/2015 Gr. Alpha 0.42 0.05 +/- 0.30 2 W-112515 Water 11/25/2015 Gr. Beta 0.78 -0.31 +/- 0.54 4 W-120815 Water 12/8/2015 Gr. Alpha 0.42 -0.08 +/- 0.29 2 W-120815 Water 12/8/2015 Gr. Beta 0.76 0.17 +/- 0.54 4 W-121515 Water 12/15/2015 Ra-226 0.01 0.01 +/- 0.01 2

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

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

c Activity reported is a net activity result.

A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)"

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-62,63 1/7/2015 Gr. Beta 5.72 +/-0.12 5.78 +/- 0.12 5.75 +/- 0.42 Pass CF-62,63 1/7/2015 Be-7 0.915 +/- 0.135 0.919 +/- 0.102 0.917 +/- 0.15 Pass CF-62,63 1/7/2015 K-40 3.97 +/- 0.28 3.88 +/- 0.23 3.92 +/- 0.33 Pass CF-62,63 1/7/2015 Sr-90 0.017 +/- 0.006 0.011 +/- 0.006 0.014 +/- 0.004 Pass SG-83,84 1/12/2015 K-40 10.11 +/- 1.42 9.69 +/- 1.20 9.90+/-1.16 Pass SG-83,84 1/12/2015 Tl-208 0.57 +/- 0.07 0.56 +/- 0.06 0.57 +/- 0.05 Pass SG-83,84 1/12/2015 Pb-212 1.73 +/- 0.10 1.58 +/- 0.09 1.65 +/-0.13 Pass SG-83,84 1/12/2015 Pb-214 13.33 +/- 0.33 13.88 +/- 0.28 13.61 +/- 0.22 Pass SG-83,84 1/12/2015 Bi-214 13.48 +/- 0.39 13.45 +/- 0.29 13.47 +/- 0.24 Pass SG-83,84 1/12/2015 Ra-226 25.68 +/- 2.19 26.22 +/- 1.53 25.95 +/- 1.34 Pass SG-83,84 1/12/2015 Ac-228 13.33 +/- 0.59 12.86 +/- 0.43 13.09 +/- 0.36 Pass AP-011215A/B 1/12/2015 Gr. Beta 0.025 +/- 0.004 0.023 +/- 0.004 0.024 +/- 0.003 Pass WW-315,316 1/27/2015 H-3 1,961 +/-178 1,868 +/- 174 1,915 +/- 124 Pass DW-60010,60011 1/28/2015 Ra-226 1.25 +/-0.14 1.40 +/- 0.15 1.33 +/- 0.10 Pass DW-60010,60011 1/28/2015 Ra-228 2.00 +/- 0.66 1.39 +/- 0.60 1.70 +/- 0.45 Pass SG-336,337 1/30/2015 Bi-214 6.63 +/- 0.20 6.45 +/- 0.45 6.54 +/- 0.21 Pass SG-336,337 1/30/2015 Pb-214 6.45 +/- 0.19 6.45 +/- 0.37 6.45 +/- 0.21 Pass SG-336,337 1/30/2015 Ac-228 4.43 +/- 0.24 4.20 +/- 0.58 4.32 +/- 0.31 Pass AP-020415A/B 2/4/2015 Gr. Beta 0.021 +/- 0.004 0.019 +/- 0.035 0.035 +/- 0.020 Pass AP-021115A/B 2/11/2015 Gr. Beta 0.034 +/- 0.004 0.040 +/- 0.047 0.037 +/- 0.003 Pass DW-60023,60024 2/26/2015 Ra-226 1.52 +/- 0.15 1.51 +/- 0.15 1.52+/-0.11 Pass DW-60023,60024 2/26/2015 Ra-228 0.97 +/- 0.48 1.66 +/- 0.58 1.32 +/- 0.38 Pass S-799,800 2/26/2015 K-40 11.96 +/-0.98 11.49 +/- 0.82 11.72 +/- 0.64 Pass S-799,800 2/26/2015 Tl-208 0.36 +/- 0.04 0.31 +/- 0.04 0.34 +/- 0.03 Pass S-799,800 2/26/2015 Pb-212 0.92 +/- 0.06 0.91 +/- 0.06 0.91 +/- 0.05 Pass S-799,800 2/26/2015 Bi-212 1.26 +/- 0.45 1.50 +/- 0.40 1.38 +/- 0.30 Pass S-799,800 2/26/2015 Ac-228 1.35 +/- 0.22 1.23 +/- 0.17 1.29 +/- 0.14 Pass SG-834,835 2/2/2015 Gr. Alpha 113.3 +/- 6.3 117.2 +/- 2.8 115.2 +/- 3.4 Pass SG-834,835 2/2/2015 Gr. Beta 82.27 +/- 2.79 84.33 +/- 2.74 83.30 +/- 1.96 Pass DW-60031 ,60032 3/4/2015 Gr. Alpha 185.4 +/-7.4 177.0 +/- 7.2 181.2 +/- 5.2 Pass DW-60036,60037 3/4/2015 Ra-226 6.89 +/- 0.34 6.88 +/- 0.32 6.89 +/- 0.23 Pass DW-60036,60037 3/4/2015 Ra-228 4.43 +/- 0.73 4.41 +/- 0.72 4.42 +/- 0.51 Pass DW-60048,60049 3/4/2015 Ra-226 0.84 +/-0.10 0.94+/-0.11 0.89 +/- 0.07 Pass DW-60048,60049 3/4/2015 Ra-228 0.68 +/- 0.41 1.42 +/- 0.58 1.05 +/- 0.36 Pass AP-1169,1170 3/19/2015 Be-7 0.20 +/- 0.02 0.24 +/- 0.10 0.22 +/- 0.07 Pass DW-60069,60070 4/8/2015 Gr. Alpha 3.58 +/- 0.88 3.92 +/- 0.88 3.75 +/- 0.62 Pass AP-040915 4/9/2015 Gr. Beta 0.027 +/- 0.005 0.023 +/- 0.005 0.025 +/- 0.003 Pass WW-2394,2395 4/13/2015 H-3 1,628 +/- 139 1,695+/-141 1,662 +/- 99 Pass SG-1847, 1848 4/20/2015 K-40 3.24 +/- 1.18 1.99 +/- 0.76 2.62 +/- 0.70 Pass SG-1847, 1848 4/20/2015 Pb-214 5.80 +/- 0.22 6.23 +/- 0.76 6.02 +/- 0.40 Pass SG-1847,1848 4/20/2015 Ac-228 5.26 +/- 0.51 5.00 +/- 0.42 5.13 +/- 0.33 Pass XWW-2267,2268 4/23/2015 H-3 6,584 +/- 244 6,164 +/- 237 6,374 +/- 170 Pass XWW-2078,2079 4/27/2015 H-3 359.0 +/- 89.6 418.7 +/- 92.3 388.9 +/- 64.3 Pass A5-1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)"

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance XWW-2162,2163 4/28/2015 H-3 4,408 +/- 201 4,242 +/- 198 4,325 +/-141 Pass SG-1868, 1869 4/28/2015 Gr. Alpha 47.57 +/- 3.63 43.61 +/- 3.58 45.59 +/- 2.55 Pass SG-1868, 1869 4/28/2015 Gr. Beta 50.90 +/- 1.94 51.90 +/- 2.02 51.40 +/- 1.40 Pass SG-1868,1869 4/28/2015 Pb-214 13.80 +/- 0.52 13.54 +/- 0.62 13.67 +/- 0.40 Pass SG-1868, 1869 4/28/2015 Ra-228 20.10 +/- 0.92 22.10 +/- 1.29 21.10 +/-0.79 Pass AP-042915 4/29/2015 Gr. Beta 0.014 +/- 0.003 0.014 +/- 0.003 0.014 +/- 0.002 Pass DW-60076,60077 5/4/2015 Ra-228 2.89 +/- 0.61 2.45 +/- 0.57 2.67 +/- 0.42 Pass AP-050515 5/5/2015 Gr. Beta 0.026 +/- 0.004 0.025 +/- 0.004 0.026 +/- 0.003 Pass AP-051115 5/11/2015 Gr. Beta 0.006 +/- 0.005 0.010 +/- 0.005 0.008 +/- 0.004 Pass DW-60087,60088 5/14/2015 Ra-226 1.58+/-0.17 1.52 +/- 0.17 1.55 +/- 0.12 Pass DW-60087 ,60088 5/14/2015 Ra-228 0.94 +/- 0.50 0.94 +/- 0.50 0.94 +/- 0.35 Pass SG-2436,2437 5/15/2015 Pb-214 22.90 +/- 2.31 24.10+/-2.43 23.50 +/- 1.68 Pass SG-2436,2437 5/15/2015 Ra-228 47.95 +/- 0.61 47.80 +/- 0.71 47.88 +/- 0.47 Pass SG-2436,2437 5/15/2015 Gr. Alpha 267.8 +/- 7.9 254.6 +/- 7.6 261.2 +/- 5.5 Pass SG-2458,2459 5/19/2015 Pb-214 75.00 +/- 1.66 77.70 +/- 1.75 76.35 +/- 1.21 Pass SG-2458,2459 5/19/2015 Ra-228 41.10 +/- 0.92 40.80 +/- 0.83 40.95 +/- 0.62 Pass DW-60095,60096 5/26/2015 Gr. Alpha 1.34 +/- 0.69 0.91 +/- 0.62 1.13+/-0.46 Pass AP-052715 5/27/2015 Gr. Beta 0.010 +/- 0.003 0.010 +/- 0.003 0.010 +/- 0.002 Pass S-2627,2628 5/29/2015 Pb-214 0.85 +/- 0.07 0.85 +/- 0.07 0.85 +/- 0.05 Pass S-2627,2628 5/29/2015 Ac-228 0.85 +/- 0.14 1.08 +/- 0.12 0.97 +/- 0.09 Pass S-2627,2628 5/29/2015 Cs-137 0.07 +/- 0.02 0.07 +/- 0.02 0.07 +/- 0.01 Pass S-2605,2606 6/1/2015 Ac-228 0.42 +/- 0.06 0.38 +/- 0.07 0.40 +/- 0.05 Pass S-2605,2606 6/1/2015 Ra-226 0.44 +/- 0.03 0.49 +/- 0.03 0.47 +/- 0.02 Pass S-2605,2606 6/1/2015 K-40 10.89 +/- 0.51 11.40 +/- 0.48 11.15 +/- 0.35 Pass S-2605,2606 6/1/2015 Cs-137 0.05 +/- 0.01 0.05 +/- 0.01 0.05 +/- 0.01 Pass S-2858,2859 6/2/2015 Cs-137 34.30 +/- 16.05 40.66 +/- 17.79 37.48 +/- 11.98 Pass S-2858,2859 6/2/2015 Be-7 1501 +/- 264 1171 +/-214 1336 +/- 170 Pass 6/2/2015 K-40 22,122 +/-658 20,987 +/- 600 21,555 +/- 445 Pass S-2858,2859 AP-060315 6/3/2015 Gr. Beta 0.022 +/- 0.004 0.021 +/- 0.004 0.022 +/- 0.003 Pass DW-301 07,30108 6/8/2015 Gr. Alpha 1.34 +/- 0.82 1.47 +/- 0.85 1.41+/-0.59 Pass SG-2900,2901 6/9/2015 Ac-228 10.22 +/- 1.36 8.32 +/- 1.07 9.27 +/- 0.87 Pass SG-2900,2901 6/9/2015 Pb-214 7.55 +/- 0.43 7.27 +/- 0.41 7.41 +/-0.30 Pass AP-061515 6/15/2015 Gr. Beta 0.022 +/- 0.004 0.021 +/- 0.004 0.022 +/- 0.003 Pass XWW-3173,3174 6/18/2015 H-3 841.9 +/- 123.6 799.3 +/- 122.4 820.6 +/- 87.0 Pass AP-062215 6/22/2015 Gr. Beta 0.023 +/- 0.004 0.018 +/- 0.004 0.020 +/- 0.003 Pass S-3216,3217 6/24/2015 K-40 10.38 +/- 0.51 10.51 +/- 0.53 10.45 +/- 0.37 Pass S-3216,3217 6/24/2015 Be-7 3.65 +/- 0.24 3.38 +/- 0.27 3.52 +/- 0.18 Pass VE-3300,3301 6/24/2015 Be-7 0.78 +/- 0.15 0.83 +/- 0.23 0.81 +/- 0.14 Pass VE-3300,3301 6/24/2015 K-40 29.12 +/-0.62 29.36 +/- 0.64 29.24 +/- 0.45 Pass AP-062915 6/29/2015 Gr. Beta 0.023 +/- 0.005 0.023 +/- 0.005 0.023 +/- 0.003 Pass WW-3632,3633 6/30/2015 H-3 5,169 +/- 225 5,058 +/- 223 5,114 +/- 158 Pass A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)"

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance AP-3822, 3823 7/1/2015 Be-7 0.075 +/- 0.011 0.068 +/- 0.012 0.072 +/- 0.008 Pass AP-3969, 3970 7/1/2015 Be-7 0.063 +/- 0.008 0.064 +/- 0.010 0.063 +/- 0.006 Pass WW-3632, 3633 7/6/2015 H-3 5,169 +/- 225 5,058 +/- 223 5,114 +/- 159 Pass W-4368, 4369 7/6/2015 Gr. Alpha 26.70 +/- 4.00 24.10 +/- 3.90 25.40 +/- 2.79 Pass W-4368, 4369 7/6/2015 Gr. Beta 34.62 +/- 2.10 33.30 +/- 2.02 33.96 +/- 1.46 Pass DW-60138, 60139 7/7/2015 Ra-226 0.07 +/- 0.04 0.11 +/- 0.05 0.09 +/- 0.03 Pass DW-60138, 60139 7/7/2015 Ra-228 1.04+/-0.41 1.15 +/- 0.47 1.10+/-0.31 Pass WW-4158, 4159 7/9/2015 H-3 138.8 +/- 82.4 174.0 +/-84.1 156.4 +/- 58.9 Pass Ml-2902, 2903 7/10/2015 K-40 1271 +/- 118 1308 +/- 115 1289 +/- 82 Pass SG-3533, 3534 7/10/2015 Gr. Alpha 238.0 +/- 8.2 249.5 +/- 8.5 243.8 +/- 5.9 Pass DW-60150, 60151 7/10/2015 Ra-226 1.53+/-0.16 1.49 +/- 0.12 1.51 +/- 0.10 Pass DW-60150, 60151 7/10/2015 Ra-228 2.68 +/- 0.68 1.89 +/- 0.62 2.29 +/- 0.46 Pass VE-3716, 3717 7/14/2015 K-40 3.85 +/- 0.33 3.71 +/- 0.31 3.78 +/- 0.23 Pass Ml-3759, 3760 7/15/2015 K-40 1819 +/- 127 1764 +/- 140 1791 +/- 94 Pass Ml-3759, 3760 7/15/2015 Sr-90 1.00 +/- 0.36 0.61 +/- 0.32 0.80 +/- 0.24 Pass AP-072115 7/21/2015 Gr. Beta 0.022 +/- 0.004 0.027 +/- 0.004 0.024 +/- 0.003 Pass VE-4053, 4054 7/21/2015 Be-7 0.52 +/- 0.15 0.49 +/- 0.11 0.50 +/- 0.09 Pass VE-4053, 4054 7/21/2015 K-40 8.00 +/- 0.42 7.61 +/- 0.31 7.81 +/- 0.26 Pass AP-4200, 4201 7/29/2015 Be-7 1.06+/-0.12 0.96 +/- 0.11 1.01 +/- 0.08 Pass AP-4200, 4201 7/29/2015 K-40 5.03 +/- 0.24 4.96 +/- 0.23 4.99 +/- 0.16 Pass W-4137, 4138 7/31/2015 Ra-226 0.58 +/- 0.13 0.45 +/- 0.14 0.52 +/- 0.10 Pass XWW-4431, 4432 8/5/2015 H-3 4,773 +/- 213 4,915 +/-216 4,844 +/- 152 Pass SG-4305, 4306 8/6/2015 Ra-228 10.34 +/- 0.58 11.46 +/- 0.62 10.90 +/- 0.42 Pass AP-081015 8/10/2015 Gr. Beta 0.038 +/- 0.005 0.039 +/- 0.005 0.039 0.004 Pass AP-081115 8/11/2015 Gr. Beta 0.024 +/- 0.004 0.020 +/- 0.004 0.022 0.003 Pass VE-4452, 4453 8/11/2015 K-40 3.77 +/- 0.29 3.78 +/- 0.26 3.77 +/- 0.20 Pass AP-081715 8/17/2015 Gr. Beta 0.030 +/- 0.005 0.030 +/- 0.005 0.030 +/- 0.003 Pass DW-60195, 60196 8/17/2015 Ra-226 0.39 +/- 0.10 0.37 +/- 0.10 0.38 +/- 0.07 Pass DW-60195, 60196 8/17/2015 Ra-228 1.43 +/- 0.51 1.97 +/- 0.61 1.70 +/- 0.40 Pass DW-60198, 60199 8/17/2015 Gr. Alpha 2.93 +/- 0.94 2.11 +/- 0.96 2.52 +/- 0.67 Pass VE-4578, 4579 8/18/2015 K-40 4.14 +/- 0.25 4.32 +/- 0.24 4.23 +/- 0.17 Pass SW-4662, 4663 8/25/2015 H-3 351.3 +/- 89.8 415.6 +/- 92.8 383.4 +/- 64.6 Pass DW-60212, 60213 8/25/2015 Ra-226 0.09 +/- 0.07 0.10 +/- 0.08 0.10 +/- 0.05 Pass LW-4788, 4789 8/27/2015 Gr. Beta 0.97 +/- 0.51 1.68 +/- 0.59 1.32 +/- 0.39 Pass AP-083115 8/31/2015 Gr. Beta 0.032 +/- 0.005 0.031 +/- 0.005 0.031 +/- 0.003 Pass AP-4875, 4876 9/3/2015 Be-7 0.294 +/- 0.125 0.202 +/-0.109 0.248 +/- 0.083 Pass VE-5083, 5084 9/14/2015 Be-7 0.47 +/- 0.23 0.56 +/-0.19 0.52 +/-0.15 Pass VE-5083, 5084 9/14/2015 K-40 6.20 +/- 0.51 6.36 +/- 0.50 6.28 +/- 0.36 Pass VE-5167, 5168 9/16/2015 Be-7 0.40+/-0.11 0.41+/-0.10 0.41 +/- 0.07 Pass VE-5167, 5168 9/16/2015 K-40 3.56 +/- 0.27 3.91 +/- 0.24 3.74 +/- 0.18 Pass BS-5188, 5189 9/16/2015 K-40 9.69 +/- 0.51 10.51 +/- 0.52 10.10 +/- 0.36 Pass F-5419, 5420 9/17/2015 K-40 3.48 +/- 0.47 3.49 +/- 0.56 3.49 +/- 0.36 Pass DW-60238, 60239 9/18/2015 Ra-226 1.93 +/- 0.23 2.31 +/- 0.26 2.12 +/- 0.17 Pass DW-60238, 60239 9/18/2015 Ra-228 4.44 +/- 0.78 5.61 +/- 0.84 5.03 +/- 0.57 Pass AP-092215A/B 9/22/2015 Gr. Beta 0.021 +/- 0.004 0.025 +/- 0.004 0.023 +/- 0.00 Pass WW-5398, 5399 9/22/2015 H-3 1,857 +/- 145 1,846 +/- 144 1,852 +/- 102 Pass AP-6007, 6008 9/28/2015 Be-7 0.08 +/- 0.01 0.08 +/- 0.01 0.08 +/- 0.01 Pass A 5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance XW-7490, 7491 9/29/2015 Ni-63 2,332 +/- 233 2,108+/-211 2,220 +/- 157 Pass WW-5377, 5378 9/30/2015 H-3 220.0 +/- 84.6 197.0 +/- 83.5 208.5 +/- 59.4 Pass AP-6028, 6029 9/30/2015 Be-7 0.073 +/- 0.009 0.083 +/- 0.012 0.078 +/- 0.007 Pass G-5461,2 10/1/2015 Be-7 2.02 +/- 0.32 1.98 +/- 0.25 2.00 +/- 0.20 Pass G-5461 ,2 10/1/2015 K-40 8.77 +/- 0.66 9.31 +/- 0.59 9.04 +/- 0.44 Pass S0-5482, 5483 10/1/2015 Ac-228 0.76 +/- 0.12 0.74 +/- 0.30 0.75 +/-0.16 Pass S0-5482, 5483 10/1/2015 Bi-214 0.53 +/- 0.04 0.52 +/- 0.04 0.52 +/- 0.03 Pass S0-5482, 5483 10/1/2015 Cs-137 0.12 +/- 0.03 0.12 +/- 0.03 0.12 +/- 0.02 Pass S0-5482, 5483 10/1/2015 K-40 2.17 +/- 0.73 2.10 +/- 0.72 2.13 +/- 0.51 Pass S0-5482, 5483 10/1/2015 Pb-214 0.57 +/- 0.04 0.55 +/- 0.04 0.56 +/- 0.03 Pass S0-5482, 5483 10/1/2015 Ra-226 1.45 +/- 0.27 1.46 +/- 0.30 1.45 +/- 0.20 Pass S0-5482, 5483 10/1/2015 Tl-208 0.24 +/- 0.03 0.25 +/- 0.03 0.24 +/- 0.02 Pass WW-5524, 5525 10/5/2015 H-3 1,192 +/- 123 1,318 +/- 127 1,255 +/- 89 Pass AP-5881, 5882 10/5/2015 Be-7 0.078 +/- 0.008 0.085 +/- 0.011 0.082 +/- 0.007 Pass AP-5881, 5882 10/5/2015 K-40 0.009 +/- 0.004 0.010 +/- 0.006 0.010 +/- 0.004 Pass SG-6400,1 10/5/2015 Gr. Alpha 19.09 +/- 3.14 19.45 +/- 3.25 19.27 +/- 2.26 Pass SG-6400,1 10/5/2015 Gr. Beta 31.36 +/- 2.08 29.80 +/- 2.13 30.58 +/- 1.49 Pass VE-5923, 5924 10/12/2015 K-40 4.29 +/- 0.29 4.13 +/- 0.33 4.21 +/- 0.22 Pass SS-5818, 5819 10/14/2015 Ac-228 0.20 +/- 0.06 0.24 +/- 0.06 0.22 +/- 0.04 Pass SS-5818, 5819 10/14/2015 Cs-137 0.03 +/- 0.02 0.02 +/- 0.01 0.03 +/- 0.01 Pass SS-5818, 5819 10/14/2015 Gr. Beta 8.10 +/- 0.87 8.08 +/- 0.96 8.09 +/- 0.65 Pass SS-5818, 5819 10/14/2015 Pb-212 0.19 +/- 0.03 0.17 +/- 0.02 0.18 +/- 0.02 Pass SS-5818, 5819 10/14/2015 Ra-226 0.47 +/- 0.24 0.45+/-0.19 0.46 +/- 0.15 Pass SS-5818, 5819 10/14/2015 Tl-208 0.06 +/- 0.02 0.06 +/- 0.02 0.06 +/- 0.01 Pass DW-60251, 60252 10/15/2015 Ra-226 0.56 +/- 0.12 0.50 +/- 0.08 0.53 +/- 0.07 Pass DW-60251, 60252 10/15/2015 Ra-228 0.79 +/- 0.48 1.16 +/- 0.59 0.98 +/- 0.38 Pass S0-5944, 5945 10/21/2015 Ac-228 1.08 +/- 0.15 1.14 +/- 0.15 1.11 +/- 0.10 Pass S0-5944, 5945 10/21/2015 Bi-214 0.89 +/- 0.08 0.82 +/- 0.06 0.85 +/- 0.05 Pass S0-5944, 5945 10/21/2015 Cs-137 0.06 +/- 0.02 0.08 +/- 0.03 0.07 +/- 0.02 Pass S0-5944, 5945 10/21/2015 Pb-212 1.06 +/- 0.06 0.99 +/- 0.05 1.03 +/- 0.04 Pass S0-5944, 5945 10/21/2015 Pb-214 1.00 +/- 0.09 0.89 +/- 0.06 0.95 +/- 0.05 Pass S0-5944, 5945 10/21/2015 Ra-226 2.13 +/-0.43 2.16 +/- 0.37 2.14 +/-0.28 Pass S0-5944, 5945 10/21/2015 Tl-208 0.36 +/- 0.04 0.34 +/- 0.04 0.35 +/- 0.03 Pass S-6175, 6176 10/23/2015 K-40 16.86 +/- 1.92 14.28 +/- 1.66 15.57 +/- 1.27 Pass XWW-6196, 6197 10/26/2015 H-3 2,856 +/- 170 2,815 +/- 169 2,836 +/- 120 Pass S0-6259, 6260 10/28/2015 Ac-228 0.60 +/- 0.10 0.53 +/- 0.08 0.57 +/- 0.07 Pass S0-6259, 6260 10/28/2015 Bi-214 0.40 +/- 0.06 0.50 +/- 0.05 0.45 +/- 0.04 Pass S0-6259, 6260 10/28/2015 Cs-137 0.17+/-0.03 0.19 +/- 0.03 0.18 +/-0.02 Pass S0-6259, 6260 10/28/2015 Gr. Beta 21.6+/-1.1 23.36 +/- 1.21 22.48 +/- 0.82 Pass S0-6259, 6260 10/28/2015 Pb-212 0.53 +/- 0.04 0.49 +/- 0.04 0.51 +/- 0.03 Pass S0-6259, 6260 10/28/2015 Tl-208 0.16 +/- 0.03 0.19 +/- 0.04 0.18 +/- 0.02 Pass A 5-4

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)"

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance LW-6280, 6281 10/29/2015 Gr. Beta 2.03 +/- 0.91 1.97 +/- 0.97 2.00 +/- 0.67 Pass Ml-6484, 6485 11/11/2015 K-40 1,384 +/- 82 1,432 +/- 89 1,408 +/- 60 Pass S0-6841, 6842 11/24/2015 Cs-137 0.18 +/-0.03 0.16 +/- 0.03 0.17 +/- 0.02 Pass S0-6841, 6842 11/24/2015 K-40 13.62 +/- 0.76 13.67 +/- 0.69 13.64 +/- 0.51 Pass WW-6978, 6979 11/30/2015 H-3 569.0 +/- 97.7 480.3 +/- 93.9 524.7 +/- 67.8 Pass SW-6936, 6937 12/10/2015 H-3 151.9 +/- 80.0 176.2 +/- 81.2 164.0 +/- 57.0 Pass SW-7017, 7018 12/10/2015 H-3 584.3 +/- 98.7 451.6 +/- 93.9 518.0 +/- 68.1 Pass LW-7020, 7021 12/10/2015 H-3 236.9 +/- 84.2 285.6 +/- 86.5 261.2 +/- 60.3 Pass AP-7351, 7352 12/29/2015 Be-7 0.099 +/- 0.020 0.084 +/- 0.018 0.091 +/- 0.014 Pass AP-7414, 7415 12/30/2015 Be-7 0.049 +/- 0.013 0.048 +/- 0.011 0.048 +/- 0.008 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.

Results are reported In units of pCUL, except for air filters (pCUFIIter or pCilm3), food products, vegetation, soil, sediment (pCilg).

A5-5

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 MAS0-975 2/1/2015 Ni-63 341 +/- 18 448 314-582 Pass MAS0-975 2/1/2015 Sr-90 523 +/- 12 653 457- 849 Pass MAS0-975 2/1/2015 Tc-99 614 +/- 12 867 607- 1,127 Pass MAS0-975 2/1/2015 Cs-134 533 +/-6 678 475 - 881 Pass MAS0-975 2/1/2015 Cs-137 0.8 +/- 2.5 0.0 NA c Pass MAS0-975 2/1/2015 Co-57 0.5 +/- 1.0 0.0 NA c Pass MAS0-975 2/1/2015 Co-60 741 +/-8 817 572 - 1,062 Pass MAS0-975 2/1/2015 Mn-54 1,153 +/-9 1,198 839- 1,557 Pass MAS0-975 2/1/2015 Zn-65 892 +/- 18 1064 745 - 1,383 Pass MAW-969 2/1/2015 Am-241 0.650 +/- O.D78 0.654 0.458 - 0.850 Pass MAW-969 2/1/2015 Cs-134 21.1 +/- 0.3 23.5 16.5-30.6 Pass MAW-969 2/1/2015 Cs-137 19.6 +/- 0.3 19.1 13.4 - 24.8 Pass MAW-969 d 2/1/2015 Co-57 10.2 +/- 0.4 29.9 20.9-38.9 Fail MAW-969 2/1/2015 Co-60 0.02 +/- 0.05 0.00 NA c Pass MAW-969 2/1/2015 H-3 569 +/- 13 563 394 -732 Pass MAW-969 2/1/2015 Fe-55 6.00 +/- 6.60 6.88 4.82 - 8.94 Pass MAW-969 . 2/1/2015 Mn-54 0.02 +/- 0.07 0.00 NA c Pass MAW-969 2/1/2015 Ni-63 2.9 +/- 3.0 0.00 NA c Pass MAW-969 2/1/2015 Zn-65 16.5 +/- 0.9 18.3 12.8-23.8 Pass MAW-969 2/1/2015 Tc-99 3.40 +/- 0.60 3.18 2.23-4.13 Pass 8

MAW-969 2/1/2015 Pu-238 0.02 +/- 0.03 0.01 NA Pass MAW-969 2/1/2015 Pu-239/240 0.81 +/- 0.10 0.83 0.58 - 1.08 Pass MAW-969 2/1/2015 U-233/234 0.150 +/- 0.040 0.148 0.104-0.192 Pass MAW-969 2/1/2015 U-238 0.84 +/- 0.09 0.97 0.68- 1.26 Pass MAW-969 2/1/2015 Sr-90 9.40 +/- 1.30 9.48 6.64- 12.32 Pass MAW-950 2/1/2015 Gr. Alpha 0.66 +/- 0.05 1.07 0.32 - 1.81 Pass MAW-950 2/1/2015 Gr. Beta 2.72 +/- 0.06 2.79 1.40 -4.19 Pass MAW-947 2/1/2015 1-129 1.26 +/- 0.12 1.49 1.04-1.94 Pass MAAP-978 2/1/2015 Am-241 0.069 +/- 0.200 0.068 0.048 - 0.089 Pass MAAP-978 2/1/2015 Cs-134 1.00 +/- 0.04 1.15 0.81 - 1.50 Pass MAAP-978 2/1/2015 Cs-137 0.004 +/- 0.023 0.00 NA c Pass MAAP-978 r 2/1/2015 Co-57 0.04 +/- 0.04 1.51 1.06 - 1.96 Fail MAAP-978 2/1/2015 Co-60 0.01 +/- 0.02 0.00 NA c Pass MAAP-978 2/1/2015 Mn-54 1.11 +/- 0.08 1.02 0.71 - 1.33 Pass MAAP-978 2/1/2015 Zn-65 0.83 +/- 0.10 0.83 0.58 - 1.08 Pass MAAP-978 2/1/2015 Pu-238 -0.003 +/- 0.010 0.000 NA c Pass MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 0.085 0.059 - 0.110 Pass MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 0.016 0.011 - 0.020 Pass MAAP-978 2/1/2015 U-238 0.073 +/- 0.018 0.099 0.069-0.129 Pass 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 MAAP-981 2/1/2015 Sr-89 38.1 +/- 1.0 47.5 33.3 -61.8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/-0.13 1.06 0.74-1.38 Pass MAAP-984 2/1/2015 Gr. Alpha 0.59 +/- 0.06 1.77 0.53-3.01 Pass MAAP-984 2/1/2015 Gr. Beta 0.95 +/- 0.07 0.75 0.38 -1.13 Pass MAVE-972 2/1/2015 Cs-134 6.98+/-0.13 7.32 5.12-9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/- 0.21 9.18 6.43 -11.93 Pass 2/1/2015 Co-57 0.01 +/- 0.04 0.00 NA c Pass MAVE-972 MAVE-972 2/1/2015 Co-60 3.89 +/- 0.20 5.55 3.89 -7.22 Pass MAVE-972 2/1/2015 Mn-54 0.04 +/- 0.07 0.00 NA c Pass 2/1/2015 Zn-65 0.09 +/-0.12 0.00 NA c Pass MAVE-972 MAAP-978 2/1/2015 Pu-238 -0.003 +/- 0.010 0.000 NA c Pass MAAP-978 2/1/2015 Pu-239/240 0.090 +/- 0.022 0.085 0.059-0.110 Pass MAAP-978 2/1/2015 U-233/234 0.020 +/- 0.010 0.016 0.011 -0.020 Pass MAAP-978 2/1/2015 U-238 0.073 +/- 0.018 0.099 0.069-0.129 Pass MAAP-981 2/1/2015 Sr-89 38.1 +/- 1.0 47.5 33.3-61.8 Pass MAAP-981 2/1/2015 Sr-90 1.22 +/- 0.13 1.06 0.74-1.38 Pass MAAP-984 2/1/2015 Gr. Alpha 0.59 +/- 0.06 1.77 0.53 - 3.01 Pass MAAP-984 2/1/2015 Gr. Beta 0.95 +/- 0.07 0.75 0.38- 1.13 Pass MAVE-972 2/1/2015 Cs-134 6.98 +/-0.13 7.32 5.12-9.52 Pass MAVE-972 2/1/2015 Cs-137 9.73 +/- 0.21 9.18 6.43 -11.93 Pass 2/1/2015 Co-57 0.01 +/- 0.04 0.00 NA c Pass MAVE-972 MAVE-972 2/1/2015 Co-60 3.89 +/- 0.20 5.55 3.89 -7.22 Pass MAVE-972 2/1/2015 Mn-54 0.04 +/- 0.07 0.00 NA c Pass 2/1/2015 Zn-65 0.09 +/- 0.12 0.00 NA c Pass MAVE-972 MAS0-4903 8/1/2015 Ni-63 556 +/- 18 682 477-887 Pass MAS0-4903 9 8/1/2015 Sr-90 231 +/-7 425 298-553 Fail MAS0-4903 9 8/1/2015 Sr-90 352 +/- 10 425 298-553 Pass MAS0-4903 h 8/1/2015 Tc-99 411 +/-11 631 442-820 Fail MAS0-4903 8/1/2015 Cs-134 833 +/- 10 1,010 707-1,313 Pass MAS0-4903 8/1/2015 Cs-137 808 +/- 11 809.00 566 -1,052 Pass MAS0-4903 8/1/2015 Co-57 1,052 +/- 10 1,180 826 -1,534 Pass 8/1/2015 Co-60 2 +/-2 1.3 NAe Pass MAS0-4903 MAS0-4903 8/1/2015 Mn-54 1,331 +/- 13 1,340 938 -1,742 Pass MAS0-4903 8/1/2015 Zn-65 686 +/- 15 662 463-861 Pass 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 MAW-5007 8/1/2015 Cs-134 16.7 +/- 0.4 23.1 16.2 - 30.0 Pass MAW-5007 8/1/2015 Cs-137 -0.4 +/- 0.1 0.0 NA c Pass MAW-5007 8/1/2015 Co-57 21.8 +/- 0.4 20.8 14.6 -27.0 Pass MAW-5007 8/1/2015 Co-60 17.3 +/-0.3 17.1 12.0 -22.2 Pass MAW-5007 8/1/2015 H-3 227.5 +/- 8.9 216.0 151.0-281.0 Pass 1

MAW-5007 8/1/2015 Fe-55 4.2+/-14.1 13.1 9.2-17.0 Fail MAW-5007 8/1/2015 Mn-54 16.6 +/- 0.5 15.6 10.9 -20.3 Pass MAW-5007 8/1/2015 Ni-63 9.1 +/- 2.6 8.6 6.0 -11.1 Pass MAW-5007 8/1/2015 Zn-65 15.5 +/- 0.9 13.9 9.7 -18.1 Pass MAW-5007 8/1/2015 Tc-99 6.80 +/- 0.60 7.19 5.03-9.35 Pass MAW-5007 8/1/2015 Sr-90 4.80 +/- 0.50 4.80 3.36-6.24 Pass MAW-5007 8/1/2015 Gr. Alpha 0.41 +/- 0.04 0.43 0.13-0.73 Pass MAW-5007 8/1/2015 Gr. Beta 3.45 +/- 0.07 3.52 1.76 - 5.28 Pass MAW-5007 8/1/2015 1-129 1.42 +/- 0.13 1.49 1.04 - 1.94 Pass MAAP-4911 8/1/2015 Sr-89 3.55 +/- 0.67 3.98 2.79-5.17 Pass MAAP-4911 8/1/2015 Sr-90 0.94 +/- 0.16 1.05 0.74-1.37 Pass MAAP-4907 8/1/2015 Gr. Alpha 0.30 +/- 0.04 0.90 0.27 - 1.53 Pass MAAP-4907 8/1/2015 Gr. Beta 1.85 +/- 0.09 1.56 0.78-2.34 Pass MAVE-4901 8/1/2015 Cs-134 5.56 +/- 0.16 5.80 4.06 -7.54 Pass MAVE-4901 8/1/2015 Cs-137 -0.02 +/- 0.06 0.00 NA c Pass MAVE-4901 8/1/2015 Co-57 7.74 +/-0.18 6.62 4.63 -8.61 Pass MAVE-4901 8/1/2015 Co-60 4.84 +/- 0.15 4.56 3.19-5.93 Pass MAVE-4901 8/1/2015 Mn-54 8.25 +/- 0.25 7.68 5.38-9.98 Pass MAVE-4901 8/1/2015 Zn-65 5.78 +/- 0.29 5.46 3.82 -7.10 Pass a Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

b Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (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 Lab result was 27.84. Data entry error resulted in a non-acceptable result.

Provided in the series for "sensitivity evaluation". MAPEP does not provide control limits.

1 Lab result was 1.58. Data entry error resulted in a non-acceptable result.

9 The incomplete separation of calcium from strontium caused a failed low result. The result of reanalysis acceptable.

h The complex sample matrix is interfering with yield calculations causing a failed low result. An investigation is in process to determine a more reliable yield determination.

1 The known activity was below the routine laboratory detection limits for the available aliquot fraction.

A6-3

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

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERAP-1091 3/16/2015 Am-241 46.8 +/- 2.2 49.8 30.7 - 67.4 Pass ERAP-1091 3/16/2015 Co-60 85.1 +/- 2.9 79.1 61.2 -98.8 Pass ERAP-1091 3/16/2015 Cs-134 825.6 +/- 34.7 909.0 578.0 - 1 '130.0 Pass ERAP-1091 3/16/2015 Cs-137 1,312 +/- 12 1,170 879 -1,540 Pass ERAP-1091 3/16/2015 Fe-55 760.6 +/- 48.2 836.0 259.0 -1630.0 Pass ERAP-1091 3/16/2015 Mn-54 <2.7 <50 0.0-50.0 Pass ERAP-1091 3/16/2015 Pu-238 51.0 +/- 3.9 52.1 35.7-68.5 Pass ERAP-1091 3/16/2015 Pu-239/240 38.3 +/- 1.3 40.3 29.20-52.70 Pass ERAP-1091 3/16/2015 Sr-90 95.3 +/- 11.4 96.6 47.2 -145.0 Pass ERAP-1091 3/16/2015 U-233/234 29.0 +/- 1.2 34.3 21.3-51.7 Pass ERAP-1091 3/16/2015 U-238 31.0+/-1.1 34.0 22.0-47.0 Pass ERAP-1091 3/16/2015 Zn-65 1099.3 +/- 146.5 986.0 706.0 - 1360.0 Pass ERAP-1094 3/16/2015 Gr. Alpha 73.7 +/- 0.7 62.2 20.8-96.6 Pass ERAP-1094 3/16/2015 Gr. Beta 69.6 +/- 0.8 58.4 36.9 - 85.1 Pass ERS0-1098 3/16/2015 Am-241 1571.8 +/- 209.6 1,500 878 -1,950 Pass ERS0-1098 3/16/2015 Ac-228 1198.8 +/- 140.4 1,250 802 -1,730 Pass ERS0-1098 3/16/2015 Bi-212 1420.1 +/-455.7 1,780 474-2,620 Pass ERS0-1098 3/16/2015 Bi-214 3466.9 +/- 86.9 4,430 2,670 - 6,380 Pass ERS0-1098 3/16/2015 Co-60 1779.8 +/-41.0 1,880 1,270 - 2,590 Pass ERS0-1098 3/16/2015 Cs-134 5204.6 +/- 64.5 6,390 4,180-7,680 Pass ERS0-1098 3/16/2015 Cs-137 1417.1 +/-41.9 1,490 1 '140 - 1,920 Pass ERS0-1098 3/16/2015 K-40 10,597 +/- 380 10,700 7,810 -14,400 Pass ERS0-1098 3/16/2015 Mn-54 <62.2 < 1000 0.0 -1,000 Pass ERS0-1098 3/16/2015 Pb-212 1,032+/-41 1,230 806-1,710 Pass ERS0-1098 3/16/2015 Pb-214 3,629 +/- 93 4,530 2,640 - 6,760 Pass ERS0-1098 3/16/2015 Pu-238 942.9 +/- 128.8 998.0 600.0 - 1 ,380.0 Pass ERS0-1098 3/16/2015 Pu-239/240 1,185 +/- 140 1,210 791 - 1,670 Pass ERS0-1098 3/16/2015 Sr-90 1,724 +/- 125 1,940 740 -3,060 Pass ERS0-1098 3/16/2015 Th-234 3,666 +/- 948 3,890 1,230 - 7,320 Pass ERS0-1098 3/16/2015 U-233/234 3,474 +/-226 3,920 2,400 - 5,020 Pass ERS0-1098 3/16/2015 U-238 3,620 +/- 232 3,890 2,410 -4,930 Pass ERS0-1098 3/16/2015 Zn-65 7,362 +/- 145 7,130 5,680 - 9,470 Pass ERW-1095 3/16/2015 Gr. Alpha 93.4 +/- 11.5 119.0 42.2 - 184.0 Pass ERW-1095 3/16/2015 Gr. Beta 145.2 +/- 4.8 158.0 90.5-234.0 Pass ERW-1110 3/16/2015 H-3 10,573 +/- 78 10,300 6,900 -14,700 Pass ERVE-1100 3/16/2015 Am-241 4,537 +/- 266 4,340 2,650 - 5,770 Pass ERVE-1100 3/16/2015 Cm-244 1,338 +/- 146 1,360 666-2,120 Pass A7-1

TABLE A-7. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERAt Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERVE-1100 e 3/16/2015 Co-60 1,030 +/- 29 1,540 1,060 -2,150 Fail 1 1,060-2,150 Pass ERVE-1100 3/16/2015 Co-60 1,684 +/- 48 1,540 ERVE-1100 e 3/16/2015 Cs-134 1,615 +/-27 2,650 1,700-3,440 Fail 1 Pass ERVE-1100 3/16/2015 Cs-134 2,554 +/- 49 2,650 1'700 - 3,440 6

ERVE-1100 3/16/2015 Cs-137 1,248 +/- 29 1,810 1,310-2,520 Fail 1 1,310-2,520 Pass ERVE-1100 3/16/2015 Cs-137 2,078 +/- 68 1,810 ERVE-1100 e 3/16/2015 K-40 22,037 +/- 463 30,900 22,300 -43,400 Fail ERVE-1100 1 3/16/2015 K-40 34,895 +/- 764 30,900 22,300 - 43,400 Pass 6

ERVE-1100 3/16/2015 Mn-54 <13.8 <300 0.0-300.0 Pass 1 <300 0.0-300.0 Pass ERVE-1100 3/16/2015 Mn-54 <24.4 ERVE-1100 3/16/2015 Pu-238 3,232 +/- 232 3,680 2,190-5,040 Pass ERVE-1100 3/16/2015 Pu-239/240 3,606 +/- 240 4,180 2,570 -5,760 Pass ERVE-1100 3/16/2015 Sr-90 6,023 +/- 326 6,590 3,760 -8,740 Pass ERVE-1100 3/16/2015 U-233/234 2,653 +/- 153 3,150 2,070 -4,050 Pass ERVE-1100 3/16/2015 U-238 2,717 +/- 163 3,130 2,090 -3,980 Pass ERVE-1100 e 3/16/2015 Zn-65 <94.6 1,090 786 -1,530 Fail ERVE-1100 1 3/16/2015 Zn-65 1,306 +/- 75 1,090 786 -1,530 Pass ERW-1103 3/16/2015 Am-241 47.1 +/-4.0 46.0 31.0 - 61.7 Pass ERW-1103 3/16/2015 Co-60 1,217 +/- 17 1,250 1,090 - 1,460 Pass ERW-1103 3/16/2015 Cs-134 1,121 +/-18 1,260 925 -1,450 Pass ERW-1103 3/16/2015 Cs-137 1,332 +/-31 1,360 1,150 -1,630 Pass ERW-1103 3/16/2015 Mn-54 <3.7 <100 0.00 - 100.00 Pass ERW-1103 3/16/2015 Pu-238 54.5 +/- 1.6 72.4 53.6-90.1 Pass ERW-1103 9 3/16/2015 Pu-239/240 140.2 +/- 7.8 184.0 143.0 -232.0 Fail ERW-3742h 9/27/2012 Pu-239/240 89.3 +/- 4.9 97.7 66.6 -108.0 Pass ERW-1103 3/16/2015 U-233/234 56.5 +/- 6.4 61.8 46.4 -79.7 Pass ERW-1103 3/16/2015 U-238 58.4 +/- 5.8 61.3 46.7 -75.2 Pass.

ERW-1103 3/16/2015 Zn-65 1'191 +/- 136 1'180 984 -1,490 Pass ERW-1103 3/16/2015 Fe-55 1,149+/-144 1,070 638 - 1,450 Pass ERW-1103 3/16/2015 Sr-90 860.0 +/- 37.0 912.0 594.0 - 1,210.0 Pass

Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

b Laboratory codes as follows: ERW (water), ERAP (air filter), ERSO (soil), ERVE (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.

Technician error weighing sample caused submitted gamma results to be understated and outside the controllimits.(low) 1 The result of reanalysis with the correct sample volume (Compare to original result, footnoted "e" above).

9 The results of reanalysis were outside the control limits (low).

h Sample ERW-3742 was ordered from ERA to determine why ERW-11 03 results for Pu-239 were outside the acceptable range.

The results for ERW-3742 were acceptable. No reason for the unacceptable results for ERW-1103 was determined.

A7-2

APPENDIX B. DATA REPORTING CONVENTIONS 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 = 2cr counting uncertainty (corresponding to the 95% confidence level).

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

3.0. Duplicate analvses 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) (x1 + x2) and s = (1/2) ~ s: + s; 3.2. Individual results: < L1 , < L2 Reported result: < L, where L = lower of L1 and L2 3.3. Individual results: x +/- s, < L Reported result: x +/- s if x ;::: L; < L otherwise.

4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average and standard deviation "s" of a set of n numbers x 1, x2 . . . X0 are defined as follows:

1

= ii LX s-

- /llil

- '\1---nT 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-1

APPENDIX C Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural a

background in unrestricted areas .

3 Air (pCi/m ) Water (pCi/L)

Gross alpha 1 X 10 Strontium-89 8,000 Gross beta 1 Strontium-90 500 b -1 lodine-131 2.8 X 10 Cesium-137 1,000 Barium-140 8,000 lodine-131 1,000 c

Potassium-40 4,000 Gross alpha 2 Gross beta 10 6

Tritium 1 X 10 a

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

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

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

c A natural radionuclide.

C-1

APPENDIX D Sample Collection and Analysis Program D-1

TLD LOCATIONS ONE MILE RADIUS R

c J

PLANT AREA ENLARGED PLAN [1.00 MILE RADIUS]

CNO SCALEJ MONITORING LEGEND:

0 PRAinlE ISLAND TLD POINTS D-2

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

0 PRAIRIE ISLAND TLO POINTS D-3

TLD LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:

0 PRAIRIE ISLAND TLD POINTS D-4

ENVIRONMENTAL SAfv1PLING POINTS ONE MILE RADIUS A

B l)'tl!RG£0N LAKE c

0 E

F M

L PLANT AREA ENLARGED PLAN [1.00 MILE RAOIUSJ

[NO SCALEJ MON!JORINO. LEGEND FISH SAMPLING POINT 10 NUMBERS 0 MILK SAMPLING POINT lD NUMBERS P-1$, P*37, P*43 P*i3, P*ICJ AJR SAMPLING POtNT .!0 NUMBERS INVERTEBRATES POINI 10 NUMBERS 8 P-1,. P-;?, P*3, P-~. P*G, P*? P*6,P*40 WATER SAMPLING POINT lO NUMBERS Sf.:OIMENr SAMPLING POINT ID NUMBERS 0 P*51P-6, P*B, p.q, P*ll, P-24, P*43 p,s, P*i2, P*20 .

[II VEGETATION I VEGETABLES 10 NUMBERS P-2B.P-38.P*45 D-5

ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS MONITORING LEGEND MILK SAMPLING POINT lO NUMBERS FISH SAMPLING POINT 10 NUMBERS P*18, P-37, P-42, p-43 P-13, P*l'l AIR SAMPLlNG POINT 10 NUM8ERS lNVERIEBRATES POINT 10 NUMBERS P*l, P-2, P*3,P*4, P*S, p-7 P*S, P-40 .

WATER SAMPLING POINT lD NUMBERS SEDIMENT.SAMPLING POINT 10 NUMBERS P-5; P*S, P*!l, P*'l, P-11, P-2.4, P-43 P*G, H2, P-20

vEGETATION ( VEGETABLES !D NUMBERS P*28,P*38,P-45 D-6

ENVIRONMENTAL SAMPLING POINTS

~

0 <2;> P-43, Peterson Farm, W10322 St Rd 29, River Falls, WI EJ P-38, Cain Residence, N7395 950th St, River Falls, WI

\--~---------------------------****-*---*---

CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND MILK SAMPLING POINT 10 NUMBERS P-18, P-37, P-41, P-42, P-43 AIR SAMPLING POINT 10 NUMBERS P-1, P-2, P-3, P-4, P-6, P-7 WATER SAMPl.ING POINT 10 NUMBERS P-6, P-6, P-8, P-9, P-11, P-43 VEGETATION I VEGETABl-ES 10 NUMBERS P-28, P-38, P-45 D-7

APPENDIX E Special Well and Surface Water Samples E-1

1.0 INTRODUCTION

This appendix to the Radiation Environmental Monitoring Program Annual Report to the United States Nuclear Regulatory Commission summarizes and interprets results of the special well and surface water samples taken at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January- December, 2015. This supplemental special sampling program was established in December of 1989 when higher than expected levels of tritium were detected in a nearby residence well sample.

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

2.0

SUMMARY

This special sampling program was established following the detection of tritium in a residence well water sample south of the PINGP during 1989. This program is described and the results for 2015 are summarized and discussed.

Program findings for 2015 detected low levels of tritium in nearby residence wells, ground water, surface samples, and storage tanks at or near the expected natural background levels with the exception of ground water sample wells MW-7 and MW-8, 05/6 tank vaults, and the septic system. The 2015 sample results (except for MW-7, MW-8, 05/6 tank vaults, and the septic system) ranged from <19 pCi!L to 308 pCi!L. Sample well MW-7 ranged from 28 pCi!L to 568 pCi/L. Sample well MW-8 ranged from 182 pCi/L to 480 pCi/L. 05/6 tank vaults were 578 and 888 pCi!L. The septic system sample ranged from <19 pCi/L to 1832 pCi/L. All tritium results are far below the Environmental Protection Agency's drinking water standard of 20,000 pCi!L and present no harm to any members of the public.

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

E-2

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

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

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

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

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

3.4 Program Modifications Changes to the program in 2015 include:

samples were taken from monitoring wells P-10, and MW-8 and snow from S-6, S-7, S-8, S-9, and P-43 and were sent to Environmental Incorporated for analysis for hard-to-detect nuclides in accordance with American Nuclear Insurers recommendation

sample location SW-6 was renamed from Restroom Trailer to Site Admin Building due to the change in use for this well

samples were taken from the D5/6 Fuel Oil Storage Tank vaults because the area was accessible in 2015

samples were taken from location P-28 at the request of the resident E-3

3.5 Results and Discussion Results show tritium in well water and ground water samples at or near expected natural background levels except the MW-7 and MW-8 ground water sample wells. Table E-4.4 provides the complete data table of results for each period and sampling location.

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

Except for sample wells MW-7 and MW-8, D5/6 tank vaults, and the septic system, the 2015 sample results are within the range of expected background tritium levels in shallow ground water and surface water due to tritium concentrations measured in precipitation. Sampling points in North America have shown tritium concentrations in precipitation ranging from 5 pCi/L to 157 pCi/L (Environmental Isotope Data No. 10; World Survey of Isotope Concentration in Precipitation (1988-1991 )).

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

The elevated tritium levels in sample wells MW-7 and MW-8 in 2015 may be due to prior leakage from the PINGP liquid radwaste discharge pipe, discharge of turbine building sump water into the landlocked area, or discharge of heating steam condensate from the main warehouse in 1978/1979.

The liquid radwaste discharge pipe was replaced in 1992 and the discharge to the landlocked area has been terminated, the last discharge took place on 11/14/09. The main warehouse heating system was repaired in 1979. The heating steam system has not been used in the outer plant buildings since the 2011 -2012 heating season.

The elevated tritium levels in the septic system are still under investigation.

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

E-4

Table E-4.1. Sample collection and analysis program for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2015.

Medium No. Location codes Collection type Analysis and type a and frequency b type c P-8 post-treat, P-8 pre-treat, REMP P-6, PIIC-22, PIIC-26, PIIC-28, PIIC-29, P-28, P-7, Well water G/A H-3 24 P-11, PZ-1, PZ-2, PZ-4, PZ-5, PZ-7, Annual MW-6, P-26, P-30, SW-3, SW-4, SW-5, SW-6, SW-7, P-9 Well water P-240 G/Q H-3 1

quarterly Well water P-2, P-3, P-5, P-6, G/Q' H-3 7

quarterly' PZ-8, MW-4, MW-5 P-43(C), SW-1(C), G/M H-3 Well water monthly 5 MW-7, MW-8, P-1 0 S-1, S-2, S-3, S-4, S-5, H-3 Surface water S-6, S-7, P-31 G/Ad 8

11 CST, 21 CST, 22 CST, GIS H-3 Storage Tank 7 U1/2 Oemin Hdr, 05/6 vaults Storage Tank 1 Septic System G/M H-3 Snow 5 S-6, S-7, S-8, S-9, P-43(C) G/A H-3 a Location codes are defined in table D-4.2. Control Stations are indicated by (C). All other stations are indicators.

b Collection type is codes as follows: G/ = grab. Collection frequency is coded as follows: M = monthly; Q = quarterly; Q' = quarterly (spring, summer, and fall), S= semiannually: A= annually.

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

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

E-5

Table E-4.2. Sampling locations for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2015.

Code Collection site Type of Distance and sample a direction from reactor P-8 PI Community well post treat ww 1.0 mi.@ 321°/WNW P-8 PI Community well pre treat ww 1.0 mi.@ 321°/WNW REMP P-6 Lock & Dam #3 well ww 1.6 mi.@ 129°/SE PIIC-22 1773 Buffalo Slough Rd ww 1 mi.@ 315°/NW PIIC-26 1771 Buffalo Slough Rd ww 1 mi. @ 315°/NW PIIC-28 1960 Larson Lane ww 1.5 mi@ 288'/WNW PIIC-29 Buffalo Project ww 4.3 mi @ 302°/WNW P-28 4802 Lock & Dam Rd ww 1.0 mi@ 152°/SSE P-24D Suter residence ww 0.6 mi.@ 158°/SSE P-43 Peterson Farm (Control) ww 13.9 mi.@ 355°/N SW-1 Hanson Farm (Control) ww 2.2 mi.@ 315°/NW P-2 Sample well ww See map P-3 Sample well ww See map P-5 Sample well ww See map P-6 Sample well ww See map P-7 Sample well ww See map P-10 Sample well ww See map P-11 Sample well ww See map PZ-1 Sample well ww See map PZ-2 Sample well ww See map PZ-4 Sample well ww See map PZ-5 Sample well ww See map PZ-7 Sample well ww See map PZ-8 Sample well ww See map MW-4 Sample well ww See m~Q_

MW-5 Sample well ww See map MW-6 Sample well ww See map MW-7 Sample well ww See map MW-8 Sample well ww See map P-26 PITCwell ww 0.4 mi. @ 258°/WSW P-30 Environ lab well ww 0.2 mi. @ 32°/NNE E-6

Table E-4.2. Sampling locations for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2015 (continued).

Code Collection site Type of Distance and sample a direction from reactor SW-3 CoolinQ Tower pump ww See maj:>_

SW-4 New Admin Bldg ww 0.05 mi.@ 315./NW SW-5 Plant Screenhouse well ww 0.05 mi.@ o*tN SW-6 Site Admin Building well ww 0.2 mi@ 310./NW SW-7 Distribution Center ww 0.35 mi@ 271./W P-9 Plant well# 2 ww 0.3 mi. C02 306°/NW S-1 Upstream Miss. River sw See map S-2 Recirc/lntake canal sw See map S-3 Cooling water canal sw See map S-4 Discharge Canal (end) sw See map S-5 Mid Discharge Canal sw See map S-6 Roof Stormwater Runoff (also snow) sw 0.05 mi.@ o*tN S-7 Parking Lot Stormwater (also snow) sw 0.3 mi C02 306./NW S-8 P-10 area snow sw See maQ_

S-9 MW-7/8 area snow sw See map P-31 Birch Lake Seepage sw 0.69 mi.@ 172°/S 11 CST Storage Tank ST Turbine Building 21 CST Storage Tank ST Turbine Building 22 CST Storage Tank ST Turbine Building Unit 1/2 demin hdr Storage Tank ST Turbine BuildinQ Septic System Storage Tank ST Outside #1 Warehouse D5/6 Vault Concrete Vault ST Outside Turbine BldQ a Sample codes: WW =Well water; SW = Surface Water: ST = Storage Tank.

E-7

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

Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January- December, 2015 (County, State)

Indicator Location with Highest Control Locations Annual Mean Locations Sample Type and Mean (F) c Location d Mean (F) c Mean (F) c Number Type Number of LLD b Range c Range c Range c Non-(Units) Analyses a Routine Results" Offsite Well H-3 16 19 187 (4/16) P-28 243 (3/3) (See Control 0

Water (21-272) (211-272) Below)

(pCi/L)

Onsite H-3 74 19 158 (58/74) MW-8 320 (12/12) (See Control 3

Well Water (22-568) (182-480) Below)

(pCi/L)

Onsite H-3 15 19 84 (7/15) S-6 171 (2/3) (See Control Surface Water (21-246) (96-246) Below) 0 (pCIIL)

Onsite D-6 Fuel Oil (See Control H-3 24 19 316 (22/24) 888 (1/1)

Storage Tank Storage Tank Below) 6 (28-1832) (888)

(pCi/L) Vault Control (offsite 19 none P-43 49 (2/12) 42 (5/24)

H-3 24 0 well water) (23-74) (21-74) a H-3 =tritium b LLD =Nominal lower limit of detection based on 4.66 sigma error for background sample. Value shown is lowest for the period.

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

d Locations are specified by code.

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

E-8

Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2015.

SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2015 2015 2015 2015 2015 2015 2015 2015 2015 2015 2015 2015 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L OFFSITE WELLS

<19 P-8 Post-treat PI Comm. Well

<19 P-8 Pre-treat PI Comm. Well

<19 REMP P-6 Lock & Dam #3 well

<19 PIIC-22 1773 Buffalo Slough Rd

<19 PIIC-26 1771 Buffalo Slough Rd

<19 PIIC-28 1960 Larson Lane

<19 PIIC-29 Buffalo Project

<19 21 <19 <19 <19 <19 P-24D Suter residence

<19/32* <19 <19 <19 <19 <19 74 <19 <19

<19 <19 23 P-43 Peterson Farm(Control snow

<19 <19 <19 <19 <19 <19 <19 30 <19 21 <19 60 SW-1 Hanson Farm (Control) 272 211 245 P-28 4802 Lock & Dam Rd E-9

---~ -- - - ~ - ----- -- -- ' - - ------ ---~ - - ~' - -- -------- -- -

SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2015 2015 2015 2015 2015 2015 2015 2015 2015 2015 2015 2015 CODE SAMPLE LOCATIONS pCi!L pCi/L pCi/L pCi/L pCi/L pCi!L pCi/L pCi/L pCi/L pCi/L pCi/L pC1/L ONSITE WELLS P-2 Sample well 50 48 46 P-3 Sample well <19 74 25 P-5 SampJewell 308 101 45 55 P-6 Sample well <19 <19 46 P-7 Sample well 58 P-10 Sample well 137 120 180 77 122 73 92 76 116 93 98 132 P-11 Sample well 54 PZ-1 Sample well 26 PZ-2 Sample well <19 PZ-4 Sample well <19 PZ-5 Sample well 29 PZ-7 Sample well <19 PZ-8 Sample well 26 33 35 MW-4 Sample well 44 22 60 MW-5 Sample well 24 <19 <19 MW-6 Sample well 25 <19 MW-7 Sample well 28 42 149 44 195 382 342 282 89 151 481 568 MW-8 Sample well 270 286 275 182 330 324 276 324 370 404 315 480 P-26 PITCwell <19 P-30 Env.labwell <19 SW-3 CTpump <19 P-9 Plant well #2 <19 SW-4 New Admin <19 SW-5 Pint Scrnhs <19 SW-6 Site Admin Bldg <19 SW-7 Dist Center <19 E-10

Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2015 (continued).

SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC I 2015 2015 2015 2015 2015 2015 2015 2015 2015 2015 2015 2015 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L I ONSITE SURFACE WATER 50 S-1 Mississippi River upstream S-2 Recirculation/Intake canal 34 S-3 Cooling water canal <19 S-4 Discharge Canal (end) <19 S-5 Discharge Canal (midway) <19 S-6 Stormwater runoff 246* <19 96 S-7 Parking Lot runoff <19* 107 <19 S-8 P-10 area snow 35*

S-9 MW-7/8 area snow 21*

P-31 Birch Lake Seepage <19 <19

snow samples E-11

Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2015 (continued).

SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC I 2015 2015 2015 2015 2015 2015 2015 2015 2015 2015 2015 2015 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi!L pCi!L pCi/L pCi!L pCi/L pCi/L pCi!L pCi/L pCi/L pCi!L ONSITE STORAGE TANKS 11 CST Storage tank 41 62 21 CST Storage tank 28 35 22CST Storage tank <19 62 U1/U2 Demin Storage tank 36/82 40/118 Header Septic 130 236 1832 630 261 36 <19 66 87 668 913 116 Storage tank System D5/6 Fuel Oil Storage Tank 578/888 D5/6 Vaults E-12

Table E-4.5. Supplementary Data Tables.

Results of the analyses for iron-55, nickel-63, strontium-90, isotopic plutonium, americium-241 and isotopic curium on five samples.

Location P-10 Snow Peterson Snow MW-7/8 Snow OAB Snow Parking Lot Snow Collection Date 01-13-15 01-13-15 01-08-15 01-08-15 01-06-15 Lab Code PXW-206 PXW-207 PXW-208 PXW-209 PXW-211 Isotope Concentration (!JCilmL)

Fe-55 < 6.9 E-07 < 6.9 E-07 < 7.1 E-07 < 6.8 E-07 < 7.3 E-07 Ni-63 < 9.7 E-08 < 9.5 E-08 < 1.0 E-07 < 1.1 E-07 < 1.1 E-07 Sr-90 < 5.6 E-10 < 5.7 E-10 < 6.5 E-10 < 5.7 E-10 <5.0E-10 Pu-238 < 1.1 E-10 < 5.7 E-11 < 5.4 E-11 < 1.2 E-10 < 1.1 E-10 Pu-239/240 <4.7E-11 < 5.7 E-11 <1.3E-10 < 5.1 E-11 <6.4E-11 Am-241 < 5.5 E-11 < 2.1 E-10 < 8.6 E-11 < 8.5 E-11 < 1.2 E-10 Cm-242 < 5.5 E-11 < 1.7 E-10 <1.5E-10 < 1.2 E-10 < 1.5 E-10 Cm-243/244 < 1.4 E-10 < 2.5 E-10 < 1.7 E-10 < 8.5 E-11 < 1.7 E-10 The error given is the probable counting error at 95% confidence level. Less than (<), value is based on a 4.66 sigma counting error for the background sample.

E-13

Table E-4.5. Supplementary Data Tables.( continued)

Results of the analyses for iron-55, nickel-63, strontium-90, isotopic plutonium, americium-241 and isotopic curium on two samples.

Location OAB Roof Parking Lot Collection Date 06-11-15 06-11-15 Lab Code PXW-2973 PXW-2974 Isotope Concentration (!JCi/mL)

Fe-55 < 7.6 E-07 < 7.4 E-07 Ni-63 < 8.9 E-08 < 9.0 E-08 Sr-90 < 6.1 E-10 < 6.2 E-10 Pu-238 < 9.2 E-11 < 1.2 E-10 Pu-239/240 < 1.6 E-10 < 1.7 E-10 Am-241 < 4.8 E-11 < 6.9 E-11 Cm-242 <2.0E-10 <9.8E-11 Cm-243/244 <4.8E-11 <9.8E-11 Less than (<), value is based on a 4.66 sigma counting error for the background sample.

E-14

Table E-4.5. Supplementary Data Tables.( continued)

Results of the analyses for iron-55, nickel-63, strontium-90, isotopic plutonium, americium-241 and isotopic curium on two samples.

Location P-10 MW-8 Collection Date 06-15-15 06-15-15 Lab Code PXWW-3245 PXWW-3246 Isotope Concentration {1..1Ci/mL)

Fe-55 < 7.1 E-07 < 7.5 E-07 Ni-63 < 9.1 E-08 < 9.0 E-08 Sr-90 < 4.3 E-10 < 6.1 E-10 Pu-238 < 1.1 E-10 < 1.1 E-10 Pu-239/240 < 6.5 E-11 < 6.5 E-11 Am-241 < 4.1 E-11 < 1.2 E-10 Cm-242 < 1.8 E-10 <8.8E-11 Cm-243/244 < 2.0 E-10 < 2.8 E-10 Less than (<), value is based on a 4.66 sigma counting error for the background sample.

E-15

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Xcel Energy L-PI-16-038 MAY 0 5 2016 TS 5.6.2 ISFSI TS 5.2 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Prairie Island Independent Spent Units 1 and 2 Fuel Storage Installation Docket Nos. 50-282 and 50-306 Docket 72-10 Renewed Facility Operating License Materials License No. SNM-2506 Nos. DPR-42 and DPR-60 2015 Annual Radiological Environmental Monitoring Program Report Pursuant to Prairie Island Nuclear Generating Plant Technical Specification (TS) 5.6.2, Appendix A, to Renewed Operating Licenses DPR-42 and DPR-60, and Prairie Island Independent Spent Fuel Storage Installation Technical Specification (ISFSI TS) 5.2, Appendix A, to Materials License SNM-2506, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), submits one copy of the annual Radiological Environmental Monitoring Program report for the period January 1, 2015, through December 31, 2015, as Enclosure 1.

Summary of Commitments

~;;;;_o new commitment and no revision to any existing commitment.

Scott Northard Acting Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc: Regional Administrator, USNRC, Region Ill Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector, Prairie Island Nuclear Generating Plant Billy Dickson, USNRC, Region Ill Director of NMSS, USNRC Department of Health, State of Minnesota PI Dakota Community Environmental Coordinator 1717 Wakonade Drive East

Welch, Minnesota 55089-9642 Telephone: 651.388.1121