L-PI-14-043, Independent Spent Fuel Storage Installation, 2013 Annual Radiological Environmental Monitoring Program (REMP) Report

Independent Spent Fuel Storage Installation, 2013 Annual Radiological Environmental Monitoring Program (REMP) Report

ML14175A978
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Site:	Prairie Island
Issue date:	12/31/2013
From:	ATI Environmental, Midwest Lab
To:	Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
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ATI Environmental, Inc.

Midwest Laboratory 700 Landwehr Road

• Northbrook. IL 60062-2310 phone (847) 564-0700 - fax (847) 564-4517 XCEL ENERGY CORPORATION PRAIRIE ISLAND NUCLEAR GENERATING PLANT ANNUAL REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION Radiological Environmental Monitoring Program January 1 to December 31, 2013 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 Section Paqe P re fa c e .................................................................................................................................................... ii List of Tables .......................................................................................................................................... iv List of Figures .......................................................................................................................................... v

1.0 INTRODUCTION

..................................................................................................................................... 1 2.0 SUM MARY .............................................................................................................................................. 2 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP) ....................................... 3 3.1 Program Design and Data Interpretation .................................................................................. 3 3.2 Program Description ...................................................................................................................... 4 3.3 Program Execution ....................................................................................................................... 5 3.4 Laboratory Procedures .......................................................................................................... 6 3.5 Program Modifications ................................................................................................................... 6 3.6 Land Use Census .......................................................................................................................... 6 4.0 RESULTS AND DISCUSSION ........................................................................................................ 7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents ........................................................ 7 4.2 Sum mary of Preoperational Data ............................................................................................. 7 4.3 Program Findings .......................................................................................................................... 8 5.0 FIGURES AND TABLES ....................................................................................................................... 12

6.0 REFERENCES

CITED .......................................................................................................................... 24 APPENDICES A Interlaboratory Comparison Program Results .................................................................................. A-1 Attachm ent A, Acceptance Criteria for "Spiked" Samples ................................................................ A-2 B Data Reporting Conventions ............................................................................................................... B-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 W ell and Surface W ater Samples ....................................................................................... E-1

LIST OF TABLES No. Title Page 5.1 Sample Collection and Analysis Program .............................................................................................. 15 5.2 Sampling Locations ................................................................................................................................... 16 5.3 Missed Collections and Analyses ............................................................................................................. 19 5.4 Radiological Environmental Monitoring Program Summary ................................................................. 20 In addition, the following tables can be found in the Appendices:

Appendix A A-1 Environmental Resources Associates, Crosscheck Program Results .............................................. Al-1 A-2 Program Results; (TLDs) ..................................................................................................................... A2-1 A-3 In-house "Spiked" Samples .................................................................................................................. A3-1 A-4 In-house "Blank" Samples ..................................................................................................................... A4-1 A-5 In-house "Duplicate" Samples ........................................................................................................ A5-1 A-6 Department of Energy MAPEP comparison results ....................................................................... A6-1 A-7 Environmental Resources Associates, Crosscheck Program Results (EML study replacement)......... A7-1 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas .................................................................................. C-2 Appendix E E-4.1 Sample collection and analysis program ................................................................................................ E-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-1 3 iv

LIST OF FIGURES No. Title Page 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator locatio ns versus control .............................................................................................................................. 13 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6) versus control location (P-i) ................................................................................. 14 MAPS Appendix D Title Page TLD locations within a one m ile radius ..................................................................................................... D-2 TLD locations, Controls .............................................................................................................................. D-3 TLD locations, surrounding the ISFSI Area ............................................................................................... D-3 TLD locations within a five mile radius ..................................................................................................... D-4 REM P sampling points within a one mile radius ...................................................................................... D-5 REM P sampling points within a five m ile radius ....................................................................................... D-6 REM P sampling points, Control locations ............................................................................................... D-7 Appendix E Groundwater Monitoring W ell locations .................................................................................................. E-14 v

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiological Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December, 2013. 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, 2014b 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 2013 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-1 31. Most samples are analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40. The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown. On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope.

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

The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141. These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the final group, manganese-54, iron-59, cobalt-58 and -

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

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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-i). The particulates are collected on membrane filters, airborne iodine is trapped by activated charcoal. Particulate filters are analyzed for gross beta activity and charcoal filters 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 CaSO 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 CaSO 4:Dy dosimeters. Twelve dosimeters are located inside of the earthen berm in direct line of sight from the storage casks and eight dosimeters are located outside of the earthen berm. They are replaced and measured quarterly.

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

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

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

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3.2 Progqram 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 three locations. 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) Airborne Particulates /Airborne Iodine:

No air particulate / air iodine sample was available from location P-06 for the week ending May 7, 2013. There was no indication of flow through the air sampler.

A partial sample was collected from location P-04 for the week ending 7/16/13. Sampler run-time was reduced by approximately 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

Air samples were not collected from the site boundary location with the highest calculated annual average ground level D/Q from January through the first three weeks of October, 2013. In 2011, annual average ground level D/Q values were updated, and identified the West sector as the highest D/Q location. A new air station (P-7) was installed in the sector and became operational during the last week of October, 2013.

(2) Thermoluminescent Dosimeters:

The TLD for location PI-03A was missing in the field for the first quarter, 2013.

The TLD for location PI-07S was missing in the field for the second quarter, 2013.

(3) Vegetation:

No broadleaf vegetation sample was available from location P-38 for the September collection. The farmer was not available for contact.

Deviations from the program are summarized in Table 5.3.

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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-1 31 in charcoal samples were determined by gamma spectroscopy.

Tritium concentrations are determined by liquid scintillation.

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

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

Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of data obtained. Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2012). The QA Program includes participation in Interlaboratory Comparison (crosscheck) Programs. Results obtained in the crosscheck programs are presented in Appendix A.

3.5 Progqram Modifications Air station P-7, (0.5 mi @ 271°/N) was added in the fourth quarter, 2013.

3.6 Land Use Census In accordance with the Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual, H4, (ODCM) a land use census is conducted in order to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft2 producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles. This census is conducted at least once per 12 months between the dates of May 1 and October 31. If new locations yield a calculated dose or dose equivalent (via the same exposure pathway) twenty percent greater than the required locations per the ODCM, then the new locations are added to the radiological environmental monitoring program within 30 days, and sampling locations having lower calculated doses or a lower dose commitment may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted.

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

The Land Use Census was completed in October, 2013. There were no changes to any of the highest D/Q locations for nearest milk animal, garden sites, or nearest residence.

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 2013. The Fukushima Daiichi nuclear accident occurred March 11, 2011.

There were no reported atmospheric nuclear tests in 2013. 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 fallout declined yearly from a level of 12,167 pCi/ m3 to 1,020 pCi/ M 3 , 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-operational studies. Gross beta in air particulates declined from levels of 0.38 to 0.037 pCi/m 3.

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

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

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

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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 15.0 mRi91 days at inner ring locations to 15.2 mR/91 days at outer ring locations.

The mean at special interest locations was 13.8 mR/91 days and 16.0 mR/91 days at the control location. Dose rates measured at the inner and outer ring and the control locations were slightly lower than those observed from 1998 through 2012. The results are tabulated below. No plant effect on ambient gamma radiation measurements was indicated (Figure 5-1).

Average (Inner and Average (Inner and Year Outer Rings) Control Year Outer Rings) Control 1998 16.7 17.3 2006 16.6 16.6 1999 16.6 17.5 2007 17.5 17.7 2000 17.0 17.1 2008 16.9 17.1 2001 16.8 17.2 2009 15.9 16.3 2002 17.4 16.9 2010 16.0 16.0 2003 16.2 16.0 2011 15.7 15.7 2004 17.6 17.6 2012 16.5 16.2 2005 16.8 16.3 2013 15.1 16.0 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates (mR/91 days).

ISFSI Facility Operations Monitorinq 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 122.6 mR/91 days inside the ISFSI earth berm and 24.0 mR/91 days outside the ISFSI earth berm. Six additional casks were placed on the ISFSI pad in 2013, a total of thirty-five loaded casks remain. The higher levels inside the earth berm are expected, due to the loaded spent fuel casks being in direct line-of-sight of the TLDs.

The 2013 fourth quarter TLD results for ISFSI monitoring locations P-011B, P-021B, P-031B and P-081B (located north and east of the ISFSI berm) were elevated. The higher doses were due to the temporary use of the adjacent area for preparing steam generators for shipment. Now that the steam generators have been shipped, doses are expected to return to their previous levels during the first quarter of 2014.

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 14.1 and 13.7 mR/91 days. Although the skyshine neutron dose rates are not directly measured, the neutron levels measured next to the casks are below the levels predicted in the ISFSI SAR Report, Table 7A-4, "TN-40 Dose Rates at Short Distances". Therefore, the skyshine dose rates at farther distances from the casks should be at or below the calculated dose rates. No spent fuel storage effect on offsite ambient gamma radiation was indicated (Fig. 5-1).

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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.

Average annual gross beta concentrations in airborne particulates were 0.027 pCi/m 3 at the indicators and 0.028 pCi/m 3 at the control location and similar to levels observed from 1998 through 2006 and 2008 to 2012. The results are tabulated below.

Average of Year Indicators Control Concentration (pCi/m )

1998 0.022 0.018 1999 0.024 0.022 2000 0.025 0.025 2001 0.023 0.023 2002 0.028 0.023 2003 0.027 0.025 2004 0.025 0.026 2005 0.027 0.025 2006 0.026 0.025 2007 0.037 0.031 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 Average annual gross beta concentrations in airborne particulates.

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced continuously in the upper atmosphere by cosmic radiation (Arnold and AI-Salih, 1955) was detected in all samples, with an average activity of 0.069 pCi/m 3 for all locations. All other isotopes were below the lower limit of detection.

There was no indication of a plant effect.

Airborne Iodine 3

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

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Milk Iodine-1 31 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 general, radiocontaminants from cattlefeed are not found in milk, due to the selective metabolism of the cow. The common exceptions are isotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968).

In summary, the data for 2013 show no radiological effects of the plant operation.

Drinkinq Water In drinking water from the City of Red Wing well, tritium activity measured below a detection limit of 184 pCi/L for all samples.

Gross beta concentrations averaged 12.2 pCi/L throughout the year, ranging from 8.0-15.7 pCi/L.

These concentrations are consistent with levels observed from 1998 through 2012. The most likely contribution is the relatively high levels of naturally-oc'curring 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 2013 data of any effect of plant operation.

Year Gross Beta (pCi/L) 1998 5.4 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 Average annual concentrations; Gross beta in drinking water.

River Water The third quarter, 2013, river water composite from downstream location P-6, tested positive for tritium at a level of 500 pCi/L. Further analyses confirmed that the activity was due to the September 24, 2013 sample collection, and coincided with a scheduled plant release. All other river water samples measured below an LLD level of 182 pCi/L.

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

In summary, the data for 2013 show no radiological effects from the plant operation.

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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 155 pCi/L. Gamma-emitting isotopes were below detection limits in all samples.

In summary, well water data for 2013 show no radiological effects of the plant operation.

Crops Two samples of broadleaf vegetation, cabbage leaves, were collected in September, 2013 and analyzed for gamma-emitting isotopes, including iodine-131. The 1-131 level was below 0.016 pCi/g wet weight in all samples. With exceptions for naturally-occurring beryllium-7 and potassiurn-40, all other gamma-emitting isotopes were below their respective detection limits.

There was no indication of a plant effect.

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

Fish Fish were collected in May and September, 2013 and analyzed for gamma emitting isotopes. Only naturally-occurring potassium-40 was detected, and there was no significant difference between upstream and downstream results. There was no indication of a plant effect.

Aquatic Insects or Periphyton Aquatic insects (invertebrates) or periphyton were collected in May and. September, 2013 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, downstream and downstream recreational area shoreline sediments were sampled in May, September and November, 2013 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.

-Indicator 20 19 18 17 16 15

-D 14 jý 13 E

12 11 10 C)' CD (D C O O (:n ) C) N) N) N)

Q) Co - N3 Ca) .0 al 0)(D0 o ~ N ~

1 -- Control (P-01C) 20 19 18 17 16 W 15

-_ 14 Y' 13 E 12 11 4in 10 r) ro IQ N) PQ to to N IQ N) )

Co CO 0 0 0 0 0? 0 0 0 Co Co 0 01 01 0 0 0 0 0 -0 w.-.

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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)]

0.039 0.037 0.035 0.033 0.031 0.029 0.027 E 0.025 C)

CL 0.023 0.021 0.019 0.017 A 015 0015 Il N3 N N3 N) K) K3 PN M Il N)

C0 0 CD 0 (D 3 0 0) 0) 0) 0D C 0 0 (0 (D 0) 0 0D 0 0 0D 0 0 C0 0 -C-. - ý-

00 (0 0) M~ CO) It, Ci 0) -4 03 CC) 0) w~N

- Control (P-1)

C--

0.039 0.037 0.035 0.033 0.031 0.029 0.027

/\S E 0.025

- 0.023 0.021 0.019 0.017 0 .017 0015 w0 ( 0D 0 0 0 0 C0 0 0D 0D 0) 0 0 0

0) CD00 C)' co . U1 a) --4 00 (0 0) w~N 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)a Frequency' Frequencyc Ambient radiation (TLD's) 54 P-OILA - P-1bA C/Q Ambient gamma P-01B -P-15B P-OIS - P-0SS P-OiIA -P-081A P-OIIB - P-081B P-01IX- P-041X, P-OiC Airborne Particulates 5 P-I(C), P-2, C/W GB, GS (QC of P-3, P4, P-6, P-7 each location)

Airborne Iodine 5 P-I(C), P-2, P-3, P-4, P-6, P-7 C/W 1-131 Milk 4 P48, P-37, P-43 (C) G/Mc 1-131, GS River water 2 P-5(C), P-6 G/W GS(MC), H-3(QC)

Drinking water I P-11 G/W GB(MC), 1-131(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 a Location codes are defined in Table D-2. Control stations are indicated by (C). All other stations are indicators.

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

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

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

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

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

15

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

Distance and Direction Code Typea Collection Site Sample Type0 from Reactor P-1 C Air Station P-i AP, Al 11.8 mi @ 3160/NNW P-2 Air Station P-2 AP, Al 0.5 mi @ 2940/WNW P-3 Air Station P-3 AP, Al 0.8 mi @ 313°/NW P-4 Air Station P-4 AP, Al 0.4 mi @ 3590 /N P-5 C Upstream of Plant RW 1.8 mi @ 110/N P-6 Lock and Dam #3 & Air Station P-6 AP, Al, RW WW, BS, BOc 1.6 mi @ 1290/SE P-7 Air Station P-7 AP, Al 0.5 mi @ 2710/W P-8 Community Center WW 1.0 mi @ 321°/WNW P-9 Plant Well #2 WW 0.3 mi @ 3060/NW P-11 Red Wing Service Center DW 3.3 mi @ 1580/SSE P-12 Downstream of Plant SS 3.0 mi @ 1160/ESE P-13 Downstream of Plant Fc 3.5 mi @ 1130/ESE P-18 Christiansen Farm M 3.8 mi @ 880/E P-19 C Upstream of Plant Fe 1.3 mi @ O/N P-20 C Upstream of Plant BS 0.9 mi @ 450/NE P-24 Suter Residence WW 0.6 mi @ 1580/SSE P-28 Allyn Residence VE 1.0 mi @ 1520/SSE P-37 Welsch Farm M 4.1 mi @ 87 0/E P-38 C Cain Residence VE 14.2 mi @ 3590/N P-40 C Upstream of Plant B0c 0.4 mi @ O/N P-43 C Peterson Farm M, WW 13.9 mi. @ 3550/N P-45 Glazier Residence VE 0.6 mi. @ 3410 /NNW General Area of the Site Boundary P-OIA Property Line TLD 0.4 mi @ 359°/N P-02A Property Line TLD 0.3 mi @ iO°/N P-03A Property Line TLD 0.5 mi @ 1830/S P-04A Property Line TLD 0.4 mi @ 2040 /SWW P-05A Property Line TLD 0.4 mi @ 2250/SW P-06A Property Line TLD 0.4 mi @ 249°/WSW P-07A Property Line TLD 0.4 mi @ 2680/W P-08A Property Line TLD 0.4 mi @ 2910/WNW P-09A Property Line TLD 0.7 mi @ 3170/NW P-IOA Property Line TLD 0.5 mi @ 3330/NNW 16

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

Distance and Direction Code Typea Collection Site Sample Typeb from Reactor Approximately 4 to 5 miles Distant from the Plant P-a l Thomas Killian Residence TLD 4.7 mi @ 3550 /N P-02E3 Roy Kinneman Residence TLD 4.8 mi @ 170/NNE P-03B Wayne Anderson Farm TLD 4.9 mi @ 460/NE P-04B Nelson Drive (Road) TLD 4.2 mi @ 610/ENE P-05E3 County Road E and Coulee TLD 4.2 mi @ 1020/ESE P-06[3 William Hauschiblt Residence TLD 4.4 mi @ 112 0/ESE P-07B Red Wing Public Works TLD 4.7 ml @ 1400/SE P-08B David Wnuk Residence TLD 4.1 mi @ 1650/SSE P-0913 Highway 19 South TLD 4.2 mi @ 1870/S P-1OB Cannondale Farm TLD 4.9 mi @ 2000 /SSW P-1113 Wallace Weberg Farm TLD 4.5 mi @ 2210 /SW P-1213 Ray Gergen Farm TLD 4.6 mi @ 2510/WSW P-13E3 Thomas O'Rourke Farm TLD 4.4 mi @ 2700/W P-1.4E David J. Anderson Farm TLD 4.9 mi @ 3060 /NW P-i.5B Hoist Farms TLD 3.8 mi @ 3450 /NNW Special Interest Locations P-01 s Federal Lock & Dam #3 TLD 1.6 mi @ 129 0/SE P-02S Charles Suter Residence TLD 0.5 ml @ 1550/SSE P-03S Carl Gustafson Farm TLD 2.2 mi @ 1730/S P-04S Richard Burt Residence TLD 2.0 mi @ 2020/SSW P-05S Kinney Store TLD 2.0 mi @ 2700/W P-06S Earl Flynn Farm TLD 2.5 mi @ 2990/WNW P-07S Indian Community TLD 0.7 mi @ 271°/W P-08S Indian Community TLD 0.7 mi @ 2870 /NWW 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 Code Typea Collection Site Sample Type" from ISFSI Center.

ISFSI Area Inside Earth Berm P-OIIA ISFSI Nuisance Fence TLD 190' @ 45 0/NE P-021A ISFSI Nuisance Fence TLD 360'@ 82 0/E P-031A ISFSI Nuisance Fence TLD 370' @ 1000 /E P-041A ISFSI Nuisance Fence TLD 200' @ 134 0/SE P-051A ISFSI Nuisance Fence TLD 180' @ 219 0 /SW P-061A ISFSI Nuisance Fence TLD 320' @ 2580 /WSW P-071A ISFSI Nuisance Fence TLD 320' @ 2810 /WNW P-081A ISFSI Nuisance Fence TLD 190' @ 3180 /NW P-011X ISFSI Nuisance Fence TLD 140' @ 1800/S P-021X ISFSI Nuisance Fence TLD 310' @ 270 0/W P-031X ISFSI Nuisance Fence TLD 140' @ O/N P-041X ISFSI Nuisance Fence TLD 360' @ 90 0/E ISFSI Area Outside Earth Berm P-0IlB ISFSI Berm Area TLD 340'@ 3'/N P-021B ISFSI Berm Area TLD 380' @ 28 0 /NNE P-031B ISFSI Berm Area TLD 560' @ 85°/E P-041B ISFSI Berm Area TLD 590'@ 1650 /SSE P-051B ISFSI Berm Area TLD 690'@ 1860/S P-061B ISFSI Berm Area TLD 720' @ 2010 /SSW P-071B ISFSI Berm Area TLD 610' @ 2710 /W P-081B ISFSI Berm Area TLD 360' @ 3320 /NNW a "C" denotes control location. All other locations are indicators.

b Sample Codes:

AP Airborne particulates F Fish Al Airborne Iodine M Milk BS Bottom (river) sediments SS Shoreline Sediments BO Bottom organisms SW Surface Water (periphyton or macroinvertebrates) VE Vegetation/vegetables DW Drinking water WW Well water O 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 TLD Gamma PI-3A 1st Qtr 2013 TLD missing in field. None required.

AP/AI Beta, 1-131 P-6 5/7/2013 No air flow through sampler. Replaced pump.

TLD Gamma PI-7S 2nd Qtr 2013 TLD missing in field. None required.

AP/AI Beta, 1-131 P-4 7/16/2013 Partial sample due to Add cautionary note tripped breaker, to breaker work order.

VE Gamma (1-131) P-38 09/01/13 Unable to contact farmer. Find new control location.

AP/AI Beta, 1-131 P-7 2013 Station was not operational None required.

until last week in October.

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, 2013

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Range' Range' Results' Direct Radiation TLD (Inner Ring, Gamma 39 3.0 15.0 (39/39) P-06A 16.2 (4/4) (See Control 0 Area at Site (10.1-18.4) 0.4 mi @ 249'/WSW (14.8-18.2) below.)

Boundary) mRJ91 days)

TLD (Outer Ring, Gamma 60 3.0 15.2 (60/60) P-04B, Nelson Dr., 19.7 (4/4) (See Control 0 4-5 mi. distant) (10.0-22.4) 4.2 mi @ 61'/ENE (16.5-22.4) below.)

mR/91 days)

TLD (Special Gamma 31 3.0 13.8 (31/31) P-03S, Gustafson Farm, 16.4 (4/4) (See Control 0 Interest Areas) (10.0-18.1) 2.2 mi @ 173'/S (14.8-18.1) below.)

mR/91 days)

TLD (Control) Gamma 4 3.0 None P-01C, Robert Kinneman 16.0 (4/4) 16.0 (4/4) 0 mR/91 days) 11.1 mi @ 331° /NNW (15.1-17.6) (15.1-17.6)

Airborne Pathway Airbome GB 269 0.005 0.027 (217/217) P-07, Air Station 0.033 (10 /10) 0.028 (52/52) 0 Particulates (0.011-0.063) 0.5 mi W (0.016-0.050) (0.012-0.059)

(pCi/m 3 )

GS 21 Be-7 0.015 0.069 (17/17) P-02, Air Station 0.072 (4/4) 0.069 (4/4) 0 (0.042-0.084) 0.5 mi @ 2940 /WNW (0.042-0.084) (0.049-0.079)

Mn-54 0.0007 < LLD - < LLD 0 Co-58 0.0008 < LLD < LLD 0 Co-60 0.0008 < LLD < LLD 0 Zn-65 0.0012 < LLD - < LLD 0 Zr-Nb-95 0.0010 < LLD - - < LLD 0 Ru-103 0.0011 < LLD - - < LLD 0 Ru-106 0.0069 < LLD - - < LLD 0 Cs-1 34 0.0007 < LLD - - < LLD 0 Cs-1 37 0.0008 < LLD - - < LLD 0 Ba-La-140 0.0034 < LLD - - < LLD 0 Ce-141 0.0016 < LLD - - < LLD 0 Ce-I44 0.0041 < LLD - - < LLD 0 Airborne Iodine 1-131 269 0.030 < LLD - - < LLD 0 (pCi/mi3) 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, 2013

( 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)0 Mean (F)' Routine (Units) Analysesa Range' Locationd Range' Range' Resultse Terrestrial Pathway Milk (pCi/L) 1-131 54 0.5 < LLD < LLD 0 GS 54 K-40 200 1414 (36/36) P-43 (C), Peterson Farm 1456 (18 /18) 1456 (18/18) 0 (1274-1574) 13.9 mi @ 355' /N (1324-1543) (1324-1543)

.Cs-134 5 < LLD - - < LLD 0 Cs-137 5 < LLD - - < LLD 0 Ba-La-140 5 < LLD - - < LLD 0 Crops-Cabbage 1-131 2 0.016 < LLD - - < LLD 0 (pCi/gwet)

Well Water H-3 20 155 < 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 47 < 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, 2013

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse Waterborne Pathway Drinking Water GB 12 1.0 12.2 (12/12) P-11, Red Wing S.C. 12.2 (12/12) None 0 (pCi/L) (8.0-15.7) 3.3 mi @ 1580 /SSE (8.0-15.7) 1-131 12 1.0 < LLD - - None 0 H-3 4 182 < 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 42 < LLD - - None 0 River Water H-3 8 182 500 (1/4) P-6, Lock and Dam #3, 500 (1/4) < LLD 0 (pCi/L) 1.6 mi @ 1290 /SE 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 12 (pCi/g wet) K-40 0.10 2.80 (6/6) P-19, Upstream 2.96 (6/6) 2.96 (6/6) 0 (2.55-3.15) 1.3 mi @ 00 /N (2.62-3.31) (2.62-3.31)

Mn-54 0.029 < LLD - - < LLD 0 Fe-59 0.087 < LLD - - < LLD 0 Co-58 0.041 < LLD - - < LLD 0 Co-60 0.017 < LLD - - < LLD 0 Zn-65 0.050 < LLD - - < LLD 0 Zr-Nb-95 0.072 < LLD - - < LLD 0 Cs-1 34 0.022 <LLD - - < LLD 0 Cs-137 0.020 < LLD - - < LLD 0 Ba-La-140 0.58 < 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, 2013 State )

( County,

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Rangec Rangec Resultse Waterborne Pathway Invertebrates GS 4 (pCi/g wet) Be-7 0.62 < LLD - < LLD 0 K-40 0.98 < LLD - < LLD 0 Mn-54 0.046 < LLD - < LLD 0 Co-58 0.063 < LLD - - < LLD 0 Co-60 0.045 < LLD - -< LLD 0 Zn-65 0.10 < LLD - - < LLD 0 Zr-Nb-95 0.13 < LLD - - < LLD 0 Ru-103 0.10 < LLD - - < LLD 0 Ru-106 0.31 < LLD - - < LLD 0 Cs-134 0.033 < LLD - - < LLD 0 Cs-1 37 0.032 < LLD - - < LLD 0 Ba-La-140 0.96 < LLD - - < LLD 0 Ce-141 0.16 < LLD - - < LLD 0 Ce-144 0.23 < LLD - - < LLD 0 Bottom and GS 6 Shoreline Be-7 0.35 < LLD - - < LLD 0 Sediments (pCi/g dry) K-40 0.10 7.66 (4/4) P-20, Upstream 9.87 (2/2) 9.87 (2/2) 0 (4.59-9.24) 0.9 mi. @ 45°/NE (8.95-10.78) (8.95-10.78)

Mn-54 0.019 < LLD < LLD 0 Co-58 0.019 < LLD - < LLD 0 Co-60 0.015 < LLD - - < LLD 0 Zn-65 0.055 < LLD - - < LLD 0 Zr-Nb-95 0.039 < LLD - - < LLD 0 Ru-1 03 0.036 < LLD - - < LLD 0 Ru-106 0.15 < LLD - - < LLD 0 Cs-1 34 0.014 < LLD - - < LLD 0 Cs-137 0.020 < LLD - - < LLD 0 Ba-La-140 0.21 < LLD - - < LLD 0 Ce-i41 0.10 < LLD - - < LLD 0 Ce-144 0.17 < LLD - - < LLD 0 GB = gross beta, GS = gamma scan.

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

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.

e Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten 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-7 Produced by Cosmic Rays. Science 121: 451-453.

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

Environmental, Inc., Midwest Laboratory.

___ 2001a through 2014a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2013.

___ 2001b through 2014b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000 through 2013.

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.

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

Northern States Power Company.

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

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

Minneapolis, Minnesota.

Prairie Island Nuclear Generating Plant, 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 Ambient 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 2014. Monticello Nuclear Generating Plant, Annual Radiological Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2013.

Minneapolis, Minnesota.

2009 to 2014. Prairie Island Nuclear Generating Plant, Annual Radiological Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2008 through 2013.

Minneapolis, Minnesota.

25

26 mb mTIEnvironmental, Inc.

Midwest Laboratory 700 Landwehr Road Northbrook. IL60062-2310 phone (847) 564-0700

• fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January through December, 2013

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

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

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

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

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

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

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

Complete analytical data for duplicate analyses is available upon request.

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

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

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

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

Al

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

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

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

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

> 20 pCi/liter 25% of known value Gross beta < 100 pCi/liter 5.0 pCi/liter

> 100 pCi/liter 5% of known value Tritium < 4,000 pCi/liter + la =

0 0933 169.85 x (known) .

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

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

b Laboratory limit.

A2

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result b Result C Limits Acceptance ERW-76 01/07/13 Ra-226 10.04 +/- 0.55 9.91 7.42-11.60 Pass ERW-76 01/07/13 Ra-228 6.11 +/- 1.29 5.22 3.14 -6.96 Pass ERW-76 01/07/13 Uranium 5.90 +/- 0.58 5.96 4.47 -7.13 Pass ERW-1593 04/08/13 Sr-89 43.60 +/- 4.32 41.30 31.60 - 48.40 Pass ERW-1593 04/08/13 Sr-90 23.20 +/- 1.70 23.90 17.20 - 28.00 Pass ERW-1596 04/08/13 Ba-1 33 74.80 +/- 4.00 82.10 69.00 - 90.30 Pass ERW-1596 04/08/13 Co-60 65.50 +/- 3.42 65.90 59.30 - 75.00 Pass ERW-1596 04108/13 Cs-1 34 41.10 +/- 3.47 42.80 34.20 - 47.10 Pass ERW-1596 04/08/13 Cs-1 37 42.30 +/- 4.03 41.70 37.00 - 48.80 Pass ERW-1 596 04/08/13 Zn-65 200.3 +/- 10.1 189.0 170.0 -222.0 Pass ERW-1 598 04/08/13 Gr. Alpha 34.30 +/- 1.98 40.80 21.10 - 51.90 Pass ERW-1 598 04/08/13 Gr. Beta 18.70 +/- 0.98 21.60 13.00 - 29.70 Pass ERW-1600 04/08/13 1-131 23.00 +/- 1.10 23.80 19.70 - 28.30 Pass ERW-1600 04/08/13 1-131(G) 23.48 +/- 9.44 23.80 19.70 - 28.30 Pass ERW-1605 04/08/13 Ra-226 16.30 +/- 0.70 15.40 11.50 - 17.70 Pass ERW-1605 04/08/13 Ra-228 5.32 +/- 1.30 4.36 2.54 - 5.98 Pass ERW-1605 04/08/13 Uranium 57.30 +/- 4.20 61.20 49.80 - 67.90 Pass ERW-1606 04/08/13 H-3 4041 +/- 194 4050 3450 - 4460 Pass ERW-6009 10/07/13 Sr-89 22.00 +/- 2.80 21.90 14.40 +/- 28.20 Pass ERW-6009 10/07/13 Sr-90 17.10 +/- 2.55 18.10 12.80 +/- 21.50 Pass ERW-6012 10/07/13 Ba-133 48.20 +/- 4.29 54.20 44.70 +/- 59.90 Pass ERW-6012 10/07/13 Co-60 100.8 +/- 4.7 102.0 91.80 +/- 114.00 Pass ERW-6012 10/07/13 Cs-134 87.30 +/- 4.35 86.70 71.10 +/- 95.40 Pass ERW-6012 10/07/13 Cs-1 37 199.6 +/- 7.4 206.0 185.0 - 228.0 Pass ERW-6012 10/07/13 Zn-65 356.2 +/- 13.2 333.0 300.0 - 389.0 Pass ERW-6015 10/07/13 Gr. Alpha 30.70 +/- 11.90 42.80 22.20 +/- 54.30 Pass ERW-6015 10/07/13 Gr. Beta 25.70 +/- 6.48 32.20 20.80 +/- 39.90 Pass ERW-6019 10/07/13 1-131 22.50 +/- 1.01 23.60 19.60 +/- 28.00 Pass ERW-6022 10/07/13 Ra-226 12.70 +/- 1.62 12.10 9.04 +/- 14.00 Pass ERW-6022 10/07/13 Ra-228 5.70 +/- 0.56 4.02 2.30 +/- 5.59 Fail ERW-6022 10/07/13 Uranium 6.59 +/- 0.38 6.24 4.70 +/- 7.44 Pass ERW-6024 10/07/13 H-3 18397 +/-695 17700 15500 - 19500 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 The reported result was obtained in the first cycle of counting. It can be positively biased due to extra beta counts contributed by Pb-214 and Bi-214 daughters of Rn-222. Result of second cycle of counting 4.47 pCi/L.

Al-I

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

mR Lab Code Date Known Lab Result Control Description Value + 2 sigma Limits Acceptance Environmental, Inc.

2013-1 5/6/2013 40 cm. 34.26 39.92 +/- 2.67 23.98 -44.54 Pass 2013-1 5/6/2013 50 cm. 21.93 25.44 +/- 3.31 15.35 -28.51 Pass 2013-1 5/6/2013 60 cm. 15.23 15.88 +/- 1.12 10.66 - 19.80 Pass 2013-1 5/6/2013 70 cm. 11.19 10.89 +/- 0.66 7.83 -14.55 Pass 2013-1 5/6/2013 80 cm. 8.57 9.21 +/- 0.41 6.00 -11.14 Pass 2013-1 5/6/2013 90 cm. 6.77 6.52 +/- 0.34 4.74 -8.80 Pass 2013-1 5/6/2013 100 cm. 5.48 5.02 +/- 0.53 3.84 -7.12 Pass 2013-1 5/6/2013 110 cm. 4.53 4.51 +/- 0.34 3.17 -5.89 Pass 2013-1 5/6/2013 120 cm. 3.81 4.28 +/- 0.35 2.67 -4.95 Pass 2013-1 5/6/2013 135 cm. 3.01 2.64 +/- 0.18 2.11 -3.91 Pass 2013-1 5/6/2013 150 cm. 2.44 2.10 +/- 0.25 1.71 -3.17 Pass 2013-1 5/6/2013 180 cm. 1.69 1.78 +/- 0.33 1.18 -2.20 Pass Environmental. Inc.

2013-2 11/18/2013 50 cm. 19.93 22.75 +/- 3.67 13.95 - 25.91 Pass 2013-2 11/18/2013 60 cm. 13.84 15.75 +/- 1.94 9.69 -17.99 Pass 2013-2 11/18/2013 70 cm. 10.17 11.24 +/- 0.88 7.12 -13.22 Pass 2013-2 11/18/2013 75 cm. 8.86 9.18 +/- 1.23 6.20 -11.52 Pass 2013-2 11/18/2013 80 cm. 7.79 7.81 +/- 1.10 5.45 -10.13 Pass 2013-2 11/18/2013 90 cm. 6.15 5.98 +/- 0.90 4.31 -8.00 Pass 2013-2 11/18/2013 100 cm. 4.98 5.13 +/- 0.73 3.49 -6.47 Pass 2013-2 11/18/2013 110 cm. 4.12 3.87 +/- 0.32 2.88 -5.36 Pass 2013-2 11/18/2013 120 cm. 3.46 3.11 +/- 0.39 2.42 -4.50 Pass 2013-2 11/18/2013 135 cm. 2.73 2.71 +/- 0.83 1.91 -3.55 Pass 2013-2 11/18/2013 150 cm. 2.21 2.11 +/- 0.63 1.55 -2.87 Pass 2013-2 11/18/2013 180 cm. 1.54 1.81 +/- 0.10 1.08 -2.00 Pass A2-1

TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPW-66 1/9/2013 Tc-99 1009 +/- 5 1078 754.9 - 1402.0 Pass SPW-1 891 1/18/2013 Ra-228 35.60 +/- 2.75 30.85 21.60 - 40.11 Pass SPSO-12313S 1/23/2013 Tc-99 103.5 +/- 2.2 107.8 75.46 - 140.14 Pass SPMI-264 1/25/2013 Cs-134 110.9 +/-6.7 107.5 96.73 - 118.23 Pass SPMI-264 1/25/2013 Cs-137 82.84 +/- 7.47 77.48 67.48 - 87.48 Pass SPMI-264 1/25/2013 Sr-90 38.19 +/- 1.49 40.11 32.09 - 48.13 Pass SPW-266 1/25/2013 Co-60 46.89 +/- 4.68 44.48 34.48 - 54.48 Pass SPW-266 1/25/2013 Cs-134 105.9 +/- 8.0 107.5 96.73 - 118.23 Pass SPW-266 1/25/2013 Cs-137 42.17 +/- 5.65 39.49 29.49 - 49.49 Pass SPW-266 1/25/2013 Sr-90 39.84 +/- 1.65 40.11 32.09 - 48.13 Pass SPAP-376 2/1/2013 Gr. Beta 44.20 +/- 0.11 45.68 27.41 - 63.95 Pass SPAP-378 2/1/2013 Cs-134 3.71 +/- 0.65 3.87 2.32 - 5.42 Pass SPAP-378 2/1/2013 Cs-137 97.47 +/- 2.50 102.9 92.61 - 113.19 Pass SPW-391 2/1/2013 H-3 63719 +/- 703 65626 52501 -78751 Pass SPW-380 2/10/2013 Ni-63 217.0 +/-3.7 205.3 143.7 - 266.9 Pass W-30413 3/4/2013 Gr. Alpha 19.77 +/- 0.40 20.00 10.00 - 30.00 Pass W-30413 3/4/2013 Gr. Beta 30.48 +/- 0.34 30.90 20.90 - 40.90 Pass W-30713 3/7/2013 Ra-226 18.06 +/- 0.51 16.70 11.69 - 21.71 Pass W-42713 4/27/2013 Gr. Alpha 20.67 +/- 0.40 20.00 10.00 -30.00 Pass W-42713 4/27/2013 Gr. Beta 28.44 +/- 0.32 30.90 20.90 - 40.90 Pass WW-2870 5/7/2013 Co-60 166.1 +/- 7.4 161.6 145.4 - 177.8 Pass WW-2870 5/7/2013 Cs-137 161.2 +/- 9.3 149.0 134.1 - 163.9 Pass WW-2870 5/7/2013 H-3 6853 +/- 250 6735 5388 - 8082 Pass W-53113 5/31/2013 Ra-226 16.83 +/- 0.41 16.70 11.69 - 21.71 Pass SPAP-3332 6/19/2013 Am-241 4.60 +/- 0.14 4.00 2.40 - 5.60 Pass SPW-3334 6/19/2013 Th-230 4.36 +/- 0.34 4.00 2.40 - 5.60 Pass SPW-3458 6/24/2013 C-14 3825 +/- 13 4736 2842 - 6630 Pass SPAP-3529 6/27/2013 Cs-134 3.49 +/- 1.26 3.30 1.98 -4.62 Pass SPAP-3529 6/27/2013 Cs-137 102.0 +/- 2.9 101.1 90.99 - 111.21 Pass SPAP-3531 6/27/2013 Gr. Beta 45.64 +/- 0.11 45.42 27.25 - 63.59 Pass SPF-3533 6/27/2013 Cs-134 1.31 +/- 0.14 1.50 0.90 -2.10 Pass SPF-3533 6/27/2013 Cs-137 2.77 +/- 0.27 2.43 1.46 - 3.40 Pass SPW-3535 6/27/2013 Ni-63 204.3 +/- 3.5 204.8 143.4 - 266.2 Pass SPW-3537 6/27/2013 Tc-99 104.5 +/- 1.7 107.8 75.46 - 140.14 Pass SPW-3539 6/27/2013 Fe-55 97015 +/- 860 90677 72542 - 108812 Pass SPW-1 893 6/28/2013 Ra-228 30.16 -2.73 30.85 21.60 - 40.11 Pass A3-1

TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPW-72913S 7/29/2013 Tc-99 126.6 +/-2.2 107.8 75.46 +/- 140.14 Pass SPW-4373 7/31/2013 Cs-134 91.71 +/- 6.02 90.94 80.94 +/- 100.94 Pass SPW-4373 7/31/2013 Cs-137 83.05 +/- 7.20 76.57 66.57 +/- 86.57 Pass SPW-4373 7/31/2013 Sr-90 39.28 +/- 1.77 39.64 31.71 +/- 47.57 Pass SPW-4374 7/31/2013 Sr-90 42.17 +/- 1.71 39.64 31.71 +/- 47.57 Pass SPMI-4376 7/31/2013 Cs-1 34 82.22 - 7.23 90.94 80.94 +/- 100.94 Pass SPMI-4376 7/31/2013 Cs- 137 83.31 -8.29 76.57 66.57 +/- 86.57 Pass SPMI-4376A 7/31/2013 Sr-90 35.00 +/- 1.63 39.64 31.71 +/- 47.57 Pass W-73113 7/31/2013 Ra-226 17.61 +/- 0.41 16.70 11.69 +/- 21.71 Pass SPS-4514 8/5/2013 Sr-90 78.63 +/- 2.95 79.28 63.42 +/- 95.14 Pass W-82013 8/20/2013 Gr. Alpha 21.53 +/- 0.45 20.00 10.00 +/- 30.00 Pass W-82013 8/20/2013 Gr. Beta 28.03 +/- 0.32 30.90 20.90 +/- 40.90 Pass SPW-1 894 8/28/2013 Ra-228 32.49 +/- 3.00 30.85 21.60 +/- 40.11 Pass W-90913 9/9/2013 Gr. Alpha 19.08 +/- 0.51 20.10 10.05 +/- 30.15 Pass W-90913 9/9/2013 Gr. Beta 32.12 +/- 0.35 32.10 22.10 +/-42.10 Pass WW-5623 10/3/2013 Co-60 157.0 +/- 7.0 155.3 139.8 - 170.8 Pass WW-5623 10/3/2013 Cs-137 156.0 +/- 8.8 148.1 133.3 - 162.9 Pass WW-5623 .10/3/2013 H-3 6590 +/- 245 6322 5058 - 7586 Pass WW-5750 10/3/2013 Co-60 87.00 +/- 7.80 77.40 77.00 +/- 97.00 Pass WW-5750 10/3/2013 Cs-1 37 82.30 +/- 7.80 78.80 68.80 +/- 88.80 Pass WW-5750 10/3/2013 H-3 6181 +/- 238 6322 5058 - 7586 Pass W-1 02813 10/28/2013 Ra-226 15.69 +/- 0.37 16.70 11.69 +/- 21.71 Pass SPW-1 898 12/17/2013 Ra-228 28.15 +/- 2.37 30.85 21.60 +/- 40.11 Pass W-122313 12/23/2013 Gr. Alpha 20.96 +/- 0.47 20.10 10.05 +/- 30.15 Pass W-122313 12/23/2013 Gr. Beta 31.00 +/- 0.34 32.10 22.10 +/- 42.10 Pass a Liquid sample results are reported in pCi/Liter, air filters( pCi/m 3), 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 .6 6 a) Acceptance Type LLD Activityc Criteria (4.66 a)

SPW-67 Water 1/9/2013 Tc-99 1.10 0.69 +/- 0.68 10 SPW-190 Water 1/18/2013 Ra-228 0.74 0.66 +/- 0.43 2 SPW-1901 Water 1/18/2013 Ra-228 0.74 0.66 +/- 0.43 2 SPMI-263 Milk 1/25/2013 Sr-90 0.64 0.31 +/- 0.34 1 SPMI-263 Milk 1/25/2013 Sr-90 0.64 0.31 +/- 0.34 1 SPW-265 Water 1/25/2013 Co-60 2.86 2.10 +/- 1.72 10 SPW-265 Water 1/25/2013 Cs-134 2.98 2.25 +/- 1.57 10 SPW-265 Water 1/25/2013 Cs-137 2.71 0.44 +/- 1.61 10 SPW-266 Water 1/25/2013 Sr-90 0.72 -0.12 +/- 0.32 1 SPAP-375 Air Filter 2/1/2013 Gr. Beta 0.003 0.016 +/- 0.003 0.010 SPAP-377 Air Filter 2/1/2013 Co-60 2.31 -0.34 +/- 1.75 100 SPAP-377 Air Filter 2/1/2013 Cs-134 2.72 1.22 +/- 1.62 100 SPAP-377 Air Filter 2/1/2013 Cs-137 1.50 -0.52 +/- 1.80 100 SPW-391 Water 2/1/2013 H-3 92.04 -29.44 +/- 69.24 200 SPW-379 Water 2/10/2013 Ni-63 2.11 0.91 +/- 1.30 20 W-30413 Water 3/4/2013 Gr. Alpha 0.35 0.08 +/- 0.26 1 W-30413 Water 3/4/2013 Gr. Beta 0.73 0.10 +/- 0.51 3.2 W-30713 Water 3/7/2013 Ra-226 0.031 0.032 +/- 0.024 1 W-42713 Water 4/27/2013 Gr. Alpha 0.45 -0.14 +/- 0.30 1 W-42713 Water 4/27/2013 Gr. Beta 0.72 -0.23 +/- 0.50 3.2 W-53113 Water 5/31/2013 Ra-226 0.03 0.01 +/- 0.02 1 SPW-3335 Water 6/19/2013 Th-230 0.01 0.01 +/- 0.01 1 SPW-3459 Water 6/24/2013 C-14 10.89 10.44 +/- 6.82 200 SPAP-3528 Air Filter 6/27/2013 Cs-134 2.10 -0.98 +/- 1.11 100 SPAP-3528 Air Filter 6/27/2013 Cs-137 2.71 -0.24 +/- 1.36 100 SPAP-3530 Air Filter 6/27/2013 Gr. Beta 0.004 0.018 +/- 0.003 0.010 SPF-3532 Fish 6/27/2013 Cs-134 8.38 -1.39 +/- 5.69 100 SPF-3532 Fish 6/27/2013 Cs-137 8.37 -1.88 +/- 6.41 100 SPW-3534 Water 6/27/2013 Ni-63 2.47 -1.04 +/- 1.48 20 SPW-3536 Water 6/27/2013 Tc-99 1.15 -1.11 +/-0.68 10 SPW-3538 water 6/27/2013 Fe-55 170.27 -17.50 +/- 102.70 1000 SPW-1903 Water 6/28/2013 Ra-228 0.85 -0.02 +/- 0.39 2 A4-1

TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)a Lab Code Sample Date AnalysisD Laboratory results (4.66a) Acceptance Type LLD Activityc Criteria (4.66 a)

SPW-72913B Water 7/29/2013 Tc-99 1.44 -0.33 +/- 0.87 10 SPW-4372 Water 7/31/2013 Co-60 1.41 -1.42 +/- 3.00 10 SPW-4372 Water 7/31/2013 Cs-134 3.68 -2.66 +/-3.46 10 SPW-4372 Water 7/31/2013 Cs-137 3.53 0.29 +/- 3.31 10 SPMI-4375 Milk 7/31/2013 Co-60 3.92 2.65 +/- 2.26 10 SPMI-4375 Milk 7/31/2013 Cs-134 4.67 0.68 +/- 2.54 10 SPMI-4375 Milk 7/31/2013 Cs-137 4.79 1.30 +/-2.68 10 SPMI-4375 Milk 7/31/2013 Sr-90 0.57 0.32 +/- 0.30 1 W-73113 Water 7/31/2013 Ra-226 0.02 0.04 +/- 0.02 1 SPS-4515 Powder 8/5/2013 Sr-90 0.09 -0.01 +/- 0.04 1 W-82013 Water 8/20/2013 Gr. Alpha 0.42 -0.15 +/- 0.28 1 W-82013 Water 8/20/2013 Gr. Beta 0.74 -0.24 +/- 0.51 3.2 SPW-1904 Water 8/28/2013 Ra-228 0.96 0.85 +/- 0.56 2 CHW-90913 Water 9/9/2013 Gr. Alpha 0.25 .0.20 +/- 0.29 1 CHW-90913 Water 9/9/2013 Gr. Beta 0.49 -0.18 +/- 0.53 3.2 CHW-102013 Water 10/20/2013 Gr. Alpha 0.29 0.24 +/- 0.33 1 CHW-102013 Water 10/20/2013 Gr. Beta 0.54 -0.32 +/- 0.54 3.2 W-102813 Water 10/28/2013 Ra-226 0.02 0.02 +/- 0.01 1 SPW-1908 Water 12/17/2013 Ra-228 0.69 0.55 +/- 0.39 2 CHW-122313 Water 12/23/2013 Gr. Alpha 0.25 -0.09 +/- 0.26 1 CHW-122313 Water 12/23/2013 Gr. Beta 0.48 0.05 +/- 0.53 3.2 CHW-122713 Water 12/27/2013 Gr. Alpha 0.28 0.04 +/- 0.31 1 CHW-122713 Water 12/27/2013 Gr. Beta 0.49 -0.33 +/- 0.53 3.2 0 Liquid sample results are reported in pCi/Liter, air filters( pCi/rn), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

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

c Activity reported is a net activity result.

A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-41, 42 1/2/2013 Gr. Beta 8.45 +/- 0.37 7.90 +/- 0.35 8.17 +/- 0.26 Pass CF-41, 42 1/2/2013 Sr-90 0.030 +/- 0.015 0.029 +/- 0.014 0.030 +/- 0.010 Pass SWT-8243, 8244 1/2/2013 Gr. Beta 1.07 +/- 0.54 0.98 +/- 0.51 1.03 +/- 0.37 Pass AP-8454, 8455 1/2/2013 Be-7 0.053 +/- 0.010 0.042 +/- 0.010 0.048 +/- 0.007 Pass AP-8517, 8518 1/3/2013 Be-7 0.051 +/- 0.015 0.049 +/- 0.017 0.050 +/- 0.011 Pass MI-62, 63 1/8/2013 K-40 1317.70 +/- 91.70 1351.90 +/- 72.50 1334.80 +/- 58.45 Pass WW-151, 152 1/8/2013 H-3 222.70 +/- 81.00 289.70 +/- 84.10 256.20 +/- 58.38 Pass SG-107, 108 1/11/2013 Ra-226 55.20 +/- 5.53 58.60 +/- 5.94 56.90 +/- 4.06 Pass SG-107, 108 1/11/2013 Ra-228 71.60 +/- 1.10 74.30 +/- 1.70 72.95 +/- 1.01 Pass SG-130, 131 1/14/2013 Ra-226 3.91 +/- 0.20 3.45 +/- 0.27 3.68 +/- 0.17 Pass SG-130, 131 1/14/2013 Ra-228 2.40 +/- 0.33 2.70 +/- 0.39 2.55 +/- 0.26 Pass WW-277, 278 1/17/2013 H-3 159.71 +/- 77.91 196.57 +/- 79.72 178.14 +/- 55.73 Pass WW-256,257 1/22/2013 H-3 502.70 +/- 93.40 483.30 +/- 92.60 493.00 +/- 65.76 Pass DW-40010, 40011 1/24/2013 Ra-226 2.55 +/- 0.18 2.86 +/- 0.20 2.71 +/- 0.13. Pass DW-40010, 40011 1/24/2013 Ra-228 1.78 +/- 0.62 2.22 +/- 0.62 2.00 +/- 0.44 Pass SWT-361, 362 1/29/2013 Gr. Beta 0.90 +/- 0.40 1.01 +/- 0.38 0.96 +/- 0.28 Pass DW-484, 485 1/29/2013 Gr. Beta 14.85 +/- 1.93 14.81 +/- 2.06 14.83 +/- 1.41 Pass S-945, 946 1/29/2013 Cs-1 37 14.50 +/-0.18 14.45 +/- 0.19 14.48 +/- 0.13 Pass S-945, 946 1/29/2013 K-40 7.90 +/- 0.74 8.00 +/- 0.73 7.95 +/- 0.52 Pass S-340, 341 1/31/2013 Cs-1 37 0.16 +/- 0.05 0.15 +/- 0.06 0.15 +/- 0.04 Pass S-340, 341 1/31/2013 K-40 17.35 +/- 1.34 19.75 +/- 1.25 18.55 +/- 0.92 Pass AP-463, 464 1/31/2013 Be-7 0.27 +/- 0.10 0.26 +/- 0.10 0.26 +/- 0.07 Pass MI-631, 632 2/13/2013 K-40 1350.50 +/- 105.20 1413.70 +/- 85.94 1382.10 +/- 67.92 Pass WW-769, 770 2/25/2013 Gr. Beta 1.20 +/- 0.33 1.35 +/- 0.34 1.28 +/- 0.24 Pass DW-736, 737 2/26/2013 Gr. Beta 1.09 +/- 0.54 1.57 +/- 0.58 1.33 +/- 0.40 Pass SWU-790, 791 2/26/2013 Gr. Beta 2.68 +/- 0.96 2.08 +/- 0.95 2.38 +/- 0.67 Pass W-925, 926 2/27/2013 H-3 2265.00 +/- 153.00 2329.00 +/- 154.00 2297.00 +/- 108.54 Pass AP-1034, 1035 3/7/2013 Be-7 0.17 +/- 0.08 0.16 +/- 0.09 0.17 +/- 0.06 Pass MI-1076, 1077 3/13/2013 K-40 1347.70 +/- 99.32 1396.10 +/- 108.00 1371.90 +/- 73.36 Pass CH-1118, 1119 3/14/2013 1-131(G) 109.41 +/- 5.69 103.88 +/- 7.76 106.65 +/- 4.81 Pass WW-1221, 1222 3/14/2013 H-3 452.11 +/-97.43 403.29 +/- 95.46 427.70 +/- 68.20 Pass P-1 368, 1369 3/15/2013 H-3 735.24 +/- 113.99 666.04 +/- 111.41 700.64 +/- 79.70 Pass DW-40017, 40018 3/19/2013 Gr. Alpha 1.43 +/- 0.94 1.61 +/- 1.00 1.52 +/- 0.69 Pass MI-1473, 1474 4/1/2013 K-40 1618.00 +/- 107.00 1767.00 +/- 129.00 1692.50 +/- 83.80 Pass AP-2014, 2015 4/1/2013 Be-7 0.055 +/- 0.008 0.057 +/- 0.006 0.056 +/- 0.005 Pass DW-40023, 40024 4/1/2013 Ra-226 2.29 +/- 0.18 2.54 +/- 0.20 2.42 +/- 0.13 Pass DW-40023, 40024 4/1/2013 Ra-228 2.99 +/- 0.69 2.96 +/- 0.67 2.98 +/- 0.48 Pass SWU-736, 737 4/2/2013 Gr. Beta 4.80 +/- 0.95 4.43 +/- 0.86 4.62 +/- 0.64 Pass AP-2035, 2036 4/2/2013 Be-7 0.070 +/- 0.013 0.065 +/- 0.013 0.068 +/- 0.009 Pass BS-1680, 1681 4/8/2013 K-40 1995.30 +/- 265.70 1992.00 +/- 289.40 1993.65 +/- 196.44 Pass SW-1638, 1639 4/9/2013 H-3 1350.77 +/- 130.08 1320.45 +/- 129.25 1335.61 +/- 91.69 Pass A5-1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance WW-2394, 2395 4/9/2013 H-3 348.08 +/- 88.40 302.43 +/- 86.41 325.25 +/- 61.81 Pass DW-40035, 40036 4/12/2013 Ra-226 1.36 +/- 0.15 1.29 +/- 0.13 1.33 +/- 0.10 Pass DW-40035,40036 4/12/2013 Ra-228 1.22 +/- 0.49 1.38 +/- 0.53 1.30 +/- 0.36 Pass MI-1825, 1826 4/15/2013 K-40 1290.20 +/- 113.80 1378.60 +/- 91.99 1334.40 +/- 73.17 Pass MI-1825, 1826 4/15/2013 Sr-90 0.68 +/- 0.32 0.46 +/- 0.31 0.57 +/- 0.22 Pass DW-40049, 40050 4/15/2013 Gr. Alpha 1.88 +/- 0.69 2.51 +/- 0.71 2.20 +/- 0.50 Pass WW-1909, 1910 4/16/2013 H-3 2145.68 +/- 156.65 2108.32 +/- 155.80 2127.00 +/- 110.47 Pass DW-40064, 40065 4/23/2013 Gr. Alpha 1.95 +/- 0.79 1.80 +/- 0.81 1.88 +/- 0.57 Pass DW-40066,40067 4/23/2013 Ra-226 1.98 +/- 0.17 1.66 +/- 0.16 1.82 +/- 0.12 Pass DW-40066, 40067 4/23/2013 Ra-228 2.30 +/- 0.59 2.32 +/- 0.59 2.31 +/- 0.42 Pass F-2225, 2226 5/1/2013 K-40 2.81 +/- 0.37 2.67 +/- 0.39 2.74 +/- 0.27 Pass BS-2267, 2268 5/1/2013 K-40 13.46 +/- 0.64 13.59 +/- 0.62 13.52 +/- 0.45 Pass SG-2235,2236 5/2/2013 Ac-228 18.30 +/- 0.60 18.50 +/- 0.60 18.40 +/- 0.42 Pass SG-2235, 2236 5/2/2013 Gr. Alpha 54.00 +/- 3.70 51.90 +/- 3.40 52.95 +/- 2.51 Pass SG-2235,2236 5/2/2013 Pb-214 11.30 +/- 0.30 11.20 +/- 0.20 11.25 +/- 0.18 Pass AP-2288, 2289 5/2/2013 Be-7 0.19 +/- 0.10 0.19 +/- 0.08 0.19 +/- 0.07 Pass WW-3091, 3092 5/2/2013 H-3 1107.91 +/- 153.49 1263.37 +/- 157.43 1185.64 +/- 109.94 Pass SW-2373, 2374 5/8/2013 H-3 324.80 +/- 86.81 364.61 +/- 88.53 344.71 +/- 62.00 Pass W-2352,2353 5/9/2013 Ra-226 0.91 +/- 0.20 1.29 +/- 0.22 1.10 +/- 0.15 Pass W-2352,2353 519/2013 Ra-228 1.28 +/- 0.87 1.03 +/- 0.94 1.16 +/- 0.64 Pass CF-2499, 2500 5/13/2013 K-40 11.52 +/- 0.45 12.55 +/- 0.61 12.04 +/- 0.38 Pass F-3987, 3988 5/20/2013 K-40 3.07 +/- 0.48 3.05 +/- 0.43 3.06 +/- 0.32 Pass BS-4113, 4114 5/20/2013 K-40 8.06 +/- 0.44 7.99 +/- 0.44 8.02 +/- 0.31 Pass SO-2902,2903 5/22/2013 Th-228 0.57 +/- 0.07 0.51 +/- 0.06 0.54 +/- 0.05 Pass SO-2902,2903 5/22/2013 Th-230 0.39 +/- 0.06 0.40 +/- 0.05 0.40 +/- 0.04 Pass SO-2902,2903 5/22/2013 Th-232 0.55 +/- 0.07 0.62 +/- 0.06 0.59 +/- 0.05 Pass WW-2776, 2777 5/23/2013 H-3 261.76 +/- 100.85 283.17 +/- 101.68 272.46 +/- 71.61 Pass WW-2818, 2819 5123/2013 H-3 999.35 +/- 126.15 880.63 +/- 122.43 939.99 +/- 87.90 Pass S-7271, 7272 5/27/2013 Cs-1 37 2.82 +/- 0.10 2.91 +/- 0.09 2.86 +/- 0.07 Pass S-7271, 7272 5/27/2013 K-40 21.52 +/- 0.97 21.13 +/- 1.02 21.32 +/- 0.70 Pass P-2923, 2924 5/2912013 H-3 441.31 +/- 92.75 374.30 +/- 89.94 407.80 +/- 64.60 Pass WW-3133, 3134 6/1/2013 H-3 278.42 +/- 86.54 209.45 +/- 83.44 243.93 +/- 60.11 Pass WW-3049, 3050 6/5/2013 H-3 156.08 +/- 79.16 244.66 +/- 83.86 200.37 +/- 57.66 Pass DW-40079,40080 6/5/2013 Ra-226 6.67 +/- 0.30 7.03 +/- 0.35 6.85 +/- 0.23 Pass DW-40079, 40080 6/5/2013 Ra-228 5.55 +/- 0.75 6.11 +/- 0.77 5.83 +/- 0.54 Pass DW-40089, 40090 6/5/2013 Gr. Alpha 6.82 +/- 0.90 5.64 +/- 1.02 6.23 t 0.68 Pass DW-40091, 40092 6/512013 Ra-226 3.44 +/- 0.19 3.66 +/- 0.19 3.55 +/- 0.13 Pass DW-40091, 40092 6/5/2013 Ra-228 3.70 +/- 0.68 4.69 +/- 0.73 4.20 +/- 0.50 Pass DW-40103, 40104 6/5/2013 Ra-226 0.98 +/- 0.22 0.62 +/- 0.15 0.80 +/- 0.13 Pass MI-3154, 3155 6/12/2013 K-40 1513.00 +/- 128.10 1456.70 +/- 110.30 1484.85 +/- 84.52 Pass P-3385, 3386 6/14/2013 H-3 236.88 +/- 87.87 242.87 +/- 88.14 239.88 +/- 62.23 Pass F-3776, 3777 6/16/2013 Cs-137 0.039 +/- 0.015 0.048 +/- 0.019 0.044 +/- 0.012 Pass F-3776, 3777 6/16/2013 Gr. Beta 4.52 +/- 0.09 4.63 +/- 0.09 4.57 +/- 0.06 Pass F-3776, 3777 6/16/2013 K-40 3.40 +/- 0.41 3.52 +/- 0.39 3.46 +/- 0.29 Pass A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance S-3238, 3239 6/17/2013 Be-7 1139.80 +/- 215.00 1102.00 +/- 194.70 1120.90 +/- 145.03 Pass S-3238, 3239 6/17/2013 Cs-1 34 26.23 +/- 13.23 39.91 +/- 11.73 33.07 +/- 8.84 Pass S-3238, 3239 6/17/2013 Cs-1 37 72.75 +/- 25.99 85.91 +/- 22.58 79.33 +/- 17.21 Pass S-3238, 3239 6/17/2013 K-40 21847.00 +/- 656.50 22158.00 +/- 622.80 22002.50 +/- 452.46 Pass SO-3343, 3344 6/17/2013 Cs-137 0.087 +/- 0.022 0.084 +/- 0.017 0.086 +/- 0:014 Pass SO-3343, 3344 6/17/2013 K-40 8.90 +/- 0.53 9.47 +/- 0.49 9.19 +/- 0.36 Pass DW-40118, 40119 6/26/2013 Gr. Alpha 3.56 +/- 1.07 4.51 +/- 0.96 4.04 +/- 0.72 Pass DW-40118, 40119 6/26/2013 Ra-226 2.52 +/- 0.22 2.48 +/- 0.19 2.50 +/- 0.15 Pass DW-40118, 40119 6/26/2013 Ra-228 2.75 +/- 0.71 2.86 +/- 0.75 2.81 +/- 0.52 Pass WW-3583, 3584 6/27/2013 H-3 6732.57 +/- 246.74 6807.94 +/- 247.98 6770.26 +/- 174.91 Pass AP-4092, 4093 6/28/2013 Be-7 0.078 +/- 0.015 0.083 +/- 0.017 0.080 +/- 0.011 Pass E-3608, 3609 7/1/2013 K-40 1.28 +/- 0.13 1.29 +/- 0.11 1.28 +/- 0.09 Pass MI-3629, 3630 7/1/2013 K-40 1840.70 +/- 130.10 1804.90 +/- 143.00 1822.80 +/- 96.66 Pass AP-4050, 4051 7/1/2013 Be-7 0.094 +/- 0.009 0.093 +/- 0.009 0.093 +/- 0.006 Pass DW-40134, 40135 7/1/2013 Ra-226 1.75 +/- 0.15 1.56 +/- 0.15 1.66 +/- 0.11 Pass DW-40134, 40135 7/1/2013 Ra-228 2.07 +/- 0.60 1.61 +/- 0.57 1.84 +/- 0.41 Pass AP-4071, 4072 7/3/2013 Be-7 0.066 +/- 0.009 0.069 +/- 0.011 0.067 +/- 0.007 Pass DW-40144, 40145 7/9/2013 Gr. Alpha 3.66 +/- 0.85 2.85 +/- 0.79 3.26 +/- 0.58 Pass DW-40146, 40147 7/9/2013 Ra-226 0.70 +/- 0.11 0.72 +/- 0.11 0.71 +/- 0.08 Pass DW-40146, 40147 7/9/2013 Ra-228 1.00 +/- 0.58 0.70 +/- 0.52 0.85 +/- 0.39 Pass VE-3818, 3819 7/9/2013 Be-7 0.41 +/- 0.11 0.46 +/- 0.18 0.43 +/- 0.11 Pass VE-3818, 3819 7/9/2013 K-40 4.67 +/- 0.30 4.52 +/- 0.43 4.60 +/- 0.26 Pass XW-4646, 4647 7/15/2013 H-3 465.00 +/- 111.00 525.00 +/- 114.00 495.00 +/- 79.56 Pass WW-4134, 4135 7/16/2013 H-3 315.86 +/- 123.54 264.98 +/- 121.78 290.42 +/- 86.73 Pass AP-4155, 4156 7/18/2013 Be-7 0.20 +/- 0.11 0.16 +/- 0.09 0.18 +/- 0.07 Pass MI-4218, 4219 7/22/2013 K-40 1426.80 +/- 117.50 1335.70 +/- 110.60 1381.25 +/- 80.68 Pass MI-4218, 4219 7/22/2013 Sr-90 0.62 +/- 0.32 0.67 +/- 0.32 0.65 +/- 0.23 Pass WW-4239, 4240 7/23/2013 H-3 223.71 +/- 92.64 221.74 +/- 92.56 222.73 +/- 65.48 Pass WW-4394, 4395 7/30/2013 Gr. Alpha 2.63 +/- 1.49 2.57 +/- 1.11 2.60 +/- 0.93 Pass WW-4394, 4395 7/30/2013 Gr. Beta 3.72 +/- 1.17 2.63 +/- 1.29 3.18 +/- 0.87 Pass WW-4394, 4395 7/30/2013 H-3 271.50 +/- 91.30 297.60 +/- 91.50 284.55 +/- 64.63 Pass SWU-4478, 4479 7/30/2013 Gr. Beta 2.07 +/- 0.54 2.24 +/- 0.55 2.16 +/- 0.39 Pass DW-40159, 40160 7/31/2013 Ra-226 3.39 +/- 0.63 2.39 +/- 0.45 2.89 +/- 0.39 Pass DW-40159, 40160 7/31/2013 Ra-228 3.29 +/- 0.73 2.94 +/- 0.68 3.12 +/- 0.50 Pass VE-4436, 4437 8/1/2013 Be-7 0.98 +/- 0.21 0.89 +/- 0.17 0.94 +/- 0.14 Pass VE-4436, 4437 8/1/2013 K-40 3.95 +/- 0.39 3.75 +/- 0.31 3.85 +/- 0.25 Pass G-4457, 4458 8/1/2013 Be-7 0.78 +/- 0.19 0.67 +/- 0.16 0.72 +/- 0.12 Pass G-4457, 4458 8/1/2013 Gr. Beta 6.15 +/- 0.14 6.10 +/- 0.14 6.13 +/- 0.10 Pass G-4457, 4458 8/1/2013 K-40 4.25 +/- 0.36 4.60 +/- 0.41 4.42 +/- 0.27 Pass VE-4520, 4521 8/1/2013 K-40 2.20 +/- 0.16 2.09 +/- 0.17 2.15 +/- 0.12 Pass WW-4772, 4773 8/6/2013 H-3 143.80 +/- 86.70 157.80 +/- 87.30 150.80 +/- 61.52 Pass A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-4709, 4710 8/8/2013 Gr. Beta 31.40 +/- 1.00 30.70 +/- 1.00 31.05 +/- 0.71 Pass VE-4709, 4710 8/8/2013 H-3 1504.00 +/- 132.00 1468.00 +/- 131.00 1486.00 +/- 92.99 Pass VE-4709, 4710 8/8/2013 U-233/4 0.009 +/- 0.002 0.005 +/- 0.002 0.007 +/- 0.001 Pass VE-4709, 4710 8/8/2013 U-238 0.005 +/- 0.002 0.004 +/- 0.001 0.005 +/- 0.001 Pass WW-4562, 4563 8/8/2013 H-3 208.82 +/- 105.55 213.13 +/- 105.73 210.97 +/- 74.70 Pass SG-4651, 4652 8/13/2013 Gr. Alpha 29.00 +/- 3.10 28.80 +/-+3.20 28.90 +/- 2.23 Pass SG-4651, 4652 8/13/2013 Gr. Beta 34.10 +/- 1.80 34.00 +/- 1.80 34.05 +/- 1.27 Pass SG-4651, 4652 8/13/2013 Ra-226 9.00 +/- 0.20 8.70 +/- 0.20 8.85 +/- 0.14 Pass VE-4835, 4836 8/13/2013 K-40 3.01 +/- 0.24 3.08 +/- 0.28 3.04 +/- 0.19 Pass WW-4877, 4878 8/14/2013 H-3 217.35 +/- 87.57 276.63 +/- 90.20 246.99 +/- 62.86 Pass LW-4856, 4857 8/15/2013 Gr. Beta 0.96 +/- 0.40 0.94 +/- 0.38 0.95 +/- 0.28 Pass W-4982, 4983 8/16/2013 H-3 757.43 +/- 112.40 767.56 +/- 112.76 762.50 +/- 79.60 Pass VE-4919, 4920 8/19/2013 K-40 4891.90 +/- 407.90 4907.40 +/- 350.40 4899.65 +/- 268.87 Pass VE-4919, 4920 8/19/2013 Be-7 470.50 +/- 159.60 325.10 +/- 104.10 397.80 +/- 95.27 Pass DW-40184, 40185 8/19/2013 Ra-228 2.35 +/- 0.72 2.53 +/- 0.70 2.44 +/- 0.50 Pass DW-40184, 40185 8/19/2013 Ra-228 1.44 +/- 0.35 2.30 +/- 0.56 1.87 +/- 0.33 Pass AP-5003, 5004 8/22/2013 Be-7 0.23 +/- 0.10 0.21 +/- 0.10 0.22 +/- 0.07 Pass LW-5229, 5230 8/29/2013 Gr. Beta 1.09 +/- 0.86 2.28 +/- 0.96 1.69 +/- 0.64 Pass SS-5333, 5334 9/3/2013 Cs-137 89.20 +/- 41.60 97.80 +/- 34.60 93.50 +/- 27.05 Pass SS-5333, 5334 9/3/2013 K-40 11893.00 +/- 681.30 12353.00 +/- 778.90 12123.00 +/- 517.41 Pass VE-5313, 5314 9/3/2013 K-40 1.84 +/- 0.20 1.85 +/- 0.20 1.85 +/- 0.14 Pass VE-5313, 5314 9/3/2013 Gr. Beta 2.38 +/- 0.04 2.43 +/- 0.04 2.41 +/- 0.03 Pass WW-5617, 5618 9/5/2013 H-3 1987.00 +/- 147.00 2094.00 +/- 150.00 2040.50 +/- 105.01 Pass AP-5355, 5356 9/5/2013 Be-7 0.22 +/- 0.12 0.27 +/- 0.14 0.25 +/- 0.09 Pass XW-5694, 5695 9/8/2013 C-14 0.94 +/- 0.09 0.78 +/- 0.10 0.86 +/- 0.07 Pass VE-5409, 5410 9/9/2013 K-40 3.60 +/- 0.26 3.33 +/- 0.29 3.46 +/- 0.19 Pass AP-5430, 5431 9/12/2013 Be-7 0.26 +/- 0.10 0.26 +/- 0.10 0.26 +/- 0.07 Pass MI-5401, 5402 9/12/2013 K-40 1404.60 +/-114.10 1356.10 +/- 128.60 1380.35 +/- 85.96 Pass WW-5451, 5452 9/12/2013 H-3 196.66 +/- 84.44 200.78 +/- 84.64 198.72 +/- 59.78 Pass MI-5484, 5485 9/16/2013 K-40 1398.50 +/- 88.93 1364.60 +/- 113.30 1381.55 +/- 72.02 Pass WW-5568, 5569 9/17/2013 H-3 274.69 +/- 87.95 203.72 +/- 84.71 239.20 +/- 61.05 Pass BS-5764, 5765 9/20/2013 Cs-137 0.40 +/- 0.03 0.37 +/- 0.02 0.39 +/- 0.02 Pass BS-5764, 5765 9/20/2013 K-40 17.97 +/- 0.59 17.54 +/- 0.55 17.76 +/- 0.40 Pass VE-5638, 5639 9/23/2013 K-40 4.15 +/- 0.33 4.46 +/- 0.38 4.31 +/- 0.25 Pass WW-5596, 5597 9/23/2013 Gr. Beta 5.97 +/- 1.39 5.95 +/- 1.45 5.96 +/- 1.01 Pass G-5680, 5681 9/25/2013 Be-7 0.36 +/- 0.13 0.35 +/- 0.09 0.35 +/- 0.08 Pass G-5680, 5681 9/25/2013 Gr. Beta 3.81 +/- 0.11 3.77 +/- 0.11 3.79 +/- 0.08 Pass G-5680, 5681 9/25/2013 K-40 3.23 +/- 0.32 2.99 +/- 0.24 3.11 +/- 0.20 Pass S-5659, 5660 9/26/2013 Ac-228 1.19 +/- 0.21 1.06 +/- 0.21 1.13 +/- 0.15 Pass S-5659, 5660 9/26/2013 Cs-137 0.13 +/- 0.04 0.14 +/- 0.05 0.14 +/- 0.03 Pass S-5659, 5660 9/26/2013 K-40 16.08 +/- 1.39 16.65 +/- 1.46 16.37 +/- 1.01 Pass S-5659, 5660 9/26/2013 Pb-214 0.97 +/- 0.15 1.10 +/- 0.16 1.04 +/- 0.11 Pass AP-6345, 6346 9/30/2013 Be-7 0.077 +/- 0.010 0.081 +/- 0.008 0,079 +/- 0.006 Pass AP-6366, 6367 9/30/2013 Be-7 0.078 +/- 0.012 0.083 +/- 0.014 0.081 +/- 0.009 Pass A5-4

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

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance DW-5701, 5702 9/30/2013 Gr. Beta 14.48 +/- 2.04 13.32 +/- 1.84 13.90 +/- 1.37 Pass SG-5722, 5723 9/30/2013 Ra-226 12.41 +/- 0.47 11.98 +/- 0.59 12.20 +/- 0.38 Pass SG-5722, 5723 9/30/2013 Ra-228 7.84 +/- 0.71 8.13 +/- 0.97 7.99 +/- 0.60 Pass G-5806, 5807 10/1/2013 Be-7 3.26 +/- 0.30 3.11 +/- 0.13 3.19 +/- 0.16 Pass G-5806, 5807 10/1/2013 K-40 6.65 +/- 0.21 6.68 +/- 0.5O 6.67 +/- 0.27 Pass SG-5827, 5828 10/1/2013 Ac-228 4.08 +/- 0.33 3.92 +/- 0.40 4.00 +/- 0.26 Pass SG-5827, 5828 10/1/2013 K-40 2.55 +/- 0.65 2.37 +/- 0.63 2.46 +/- 0.45 Pass SG-5827, 5828 10/1/2013 Pb-214 3.82 +/- 0.17 3.93 +/- 0.20 3.88 +/- 0.13 Pass VE-5848, 5849 10/1/2013 K-40 1.62 +/- 0.16 1.57 +/- 0.14 1.60 +/- 0.11 Pass AP-6408, 6409 10/3/2013 Be-7 0.072 +/- 0.015 0.063 +/- 0.012 0.068 +/- 0.010 Pass f-5954, 5955 10/3/2013 K-40 2.74 +/- 0.36 3.02 +/- 0.34 2.88 +/- 0.25 Pass P-6035, 6036 10/7/2013 H-3 198.41 +/- 85.00 288.60 +/- 89.15 243.51 +/- 61.59 Pass SG-6115, 6116 10/8/2013 Ac-228 5.22 +/- 0.50 4.87 +/- 0.48 5.05 +/- 0.35 Pass SG-6115, 6116 10/8/2013 K-40 5.61 +/- 1.08 6.61 +/- 1.04 6.11 +/- 0.75 Pass SG-61.15, 6116 10/8/2013 Pb-214 4.29 +/- 0.24 4.24 +/- 0.20 4.27 +/- 0.16 Pass VE-6136, 6137 10/8/2013 Be-7 0.55 +/- 0.18 0.60 +/- 0.15 0.58 +/- 0.12 Pass VE-6136, 6137 10/8/2013 K-40 2.78 +/- 0.35 2.61 +/- 0.33 2.69 +/- 0.24 Pass WW-6198, 6199 10/8/2013 H-3 12973.70 +/- 332.60 12757.80 +/- 330.00 12865.75 +/- 234.27 Pass VE-6240, 6241 10/9/2013 K-40 14.29 +/- 0.29 14.95 +/- 0.54 14.62 +/- 0.31 Pass W-5996, 5997 10/9/2013 Gr. Alpha 3.87 +/- 1.18 4.07 +/- 1.08 3.97 +/- 0.80 Pass W-5996, 5997 10/9/2013 Gr. Beta 9.82 +/- 0.85 8.53 +/- 0.82 9.18 +/-.0.59 Pass W-5996, 5997 10/9/2013 Ra-228 3.42 +/- 1.02 3.39 +/- 1.01 3.41 +/- 0.72 Pass DW-40224, 40225 10/11/2013 Ra-226 0.62 +/- 0.10 0.76 +/- 0.10 0.69 +/- 0.07 Pass DW-40224, 40225 10/11/2013 Ra-228 0.87 +/- 0.55 1.00 +/- 0.54 0.94 +/- 0.39 Pass WW-6219, 6220 10/11/2013 H-3 455.41 +/- 111.54 354.66 +/- 107.84 405.03 +/- 77.57 Pass CF-6261, 6262 10/14/2013 Be-7 1.97 +/- 0.24 2.06 +/- 0.22 2.01 +/- 0.16 Pass CF-6261, 6262 10/14/2013 K-40 11.55 +/- 0.56 12.06 +/- 0.61 11.80 +/- 0.41 Pass MI-6303, 6304 10/14/2013 K-40 1507.30 +/- 110.80 1482.40 +/- 110.00 1494.85 +/- 78.07 Pass VE-6534, 6535 10/17/2013 K-40 15.96 +/- 0.17 16.16 +/- 0.36 16.06 +/- 0.20 Pass S-6471, 6472 10/1812013 Ac-228 0.94 +/- 0.19 0.78 +/- 0.18 0.86 +/- 0.13 Pass S-6471, 6472 10/18/2013 K-40 12.82 +/- 1.05 12.90 +/- 1.17 12.86 +/- 0.79 Pass S-6471, 6472 10/18/2013 Pb-214 0.88 +/- 0.11 0.72 +/- 0.12 0.80 +/- 0.08 Pass VE-6597, 6598 10/22/2013 K-40 2.46 +/- 0.22 2.58 +/- 0.20 2.52 +/- 0.15 Pass WW-6576, 6577 10/22/2013 H-3 745.60 +/- 110.70 663.30 +/- 107.60 704.45 +/- 77.19 Pass LW-6681, 6682 10/29/2013 Gr. Beta 2.00 +/- 0.92 2.17 +/- 0.98 2.09 +/- 0.67 Pass SWU-6765, 6766 10/29/2013 Gr. Beta 3.07 +/- 0.61 2.90 +/- 0.65 2.99 +/- 0.45 Pass WW-6849, 6850 10/29/2013 H-3 863.00 +/- 113.80 826.60 +/- 112.50 844.80 +/- 80.01 Pass MI-6786, 6787 10/30/2013 K-40 1370.60 +/- 109.60 1449.20 +/- 105.50 1409.90 +/- 76.06 Pass SO-6744, 6745 10/30/2013 Ac-228 0.46 +/- 0.11 0.51 +/- 0.11 0.48 +/- 0.08 Pass SO-6744, 6745 10/30/2013 Bi-214 0.48 +/-0.10 0.30 +/- 0.10 0.39 +/- 0.07 Pass SO-6744, 6745 10/30/2013 Cs-1 37 0.21 +/- 0.04 0.24 +/- 0.04 0.23 +/- 0.03 Pass SO-6744, 6745 10/30/2013 Gr. Beta 27.40 +/- 1.14 27.44 +/- 1.11 27.42 +/- 0.80 Pass SO-6744, 6745 10/30/2013 K-40 14.93 +/- 0.88 15.20 +/- 0.90 15.07 +/- 0.63 Pass SO-6744, 6745 10/30/2013 Pb-212 0.43 +/- 0.04 0.40 +/- 0.05 0.42 +/- 0.03 Pass SO-6744, 6745 10/30/2013 Ra-226 1.47 +/- 0.35 1.31 +/- 0.36 1.39 +/- 0.25 Pass SO-6744, 6745 10/30/2013 TI-208 0.16 +/- 0.04 0.16 +/- 0.04 0.16 +/- 0.03 Pass A5-5

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance DW-40238, 40239 10/31/2013 Ra-228 0.94 +/- 0.41 1.60 +/- 0.55 1.27 +/- 0.34 Pass WW-7018, 7019 11/1/2013 H-3 593.09 +/- 104.72 648.69 +/- 106.89 620.89 +/- 74.82 Pass CF-6870, 6871 11/4/2013 K-40 12.67 +/-0.49 13.30 +/- 0.47 12.98 +/- 0.34 Pass XW-6828, 6829 11/4/2013 K-40 97.99 +/- 55.33 160.21 +/- 74.99 129.10 +/- 46.60 Pass BS-6891, 6892 11/5/2013 Cs-1 37 0.018 +/- 0.010 0.018 +/- 0.009 0.018 +/- 0.007 Pass BS-6891, 6892 11/5/2013 Gr. Beta 12.41 +/- 1.74 9.97 +/- 1.57 11.19 +/- 1.17 Pass BS-6891, 6892 11/5/2013 K-40 6.49 +/- 0.33 6.28 +/- 0.40 6.39 +/- 0.26 Pass WW-6912, 6913 11/5/2013 Gr. Alpha 2.87 +/- 1.30 4.46 +/- 1.47 3.67 +/- 0.98 Pass WW-6912, 6913 11/5/2013 Gr. Beta 3.18 +/- 0.87 3.18 +/- 0.87 3.18 +/- 0.62 Pass WW-6912, 6913 11/5/2013 H-3 349.01 +/- 101.42 430.14 +/- 98.06 389.58 +/- 70.54 Pass SO-6954, 6955 11/6/2013 Cs-1 37 0.14 +/- 0.03 0.12 +/- 0.02 0.13 +/- 0.02 Pass SO-6954, 6955 11/6/2013 K-40 15.16 +/- 0.72 14.11 +/- 0.64 14.64 +/- 0.48 Pass S-6976, 6977 11/13/2013 K-40 22.36 +/- 0.69 22.62 +/- 0.72 22.49 +/- 0.50 Pass DW-40246, 40247 11/15/2013 Gr. Alpha 15.00 +/- 3.41 20.31 +/- 4.00 17.65 +/- 2.63 Pass CF-7102, 7103 11/18/2013 Be-7 17.79 +/- 0.51 18.09 +/- 0.80 17.94 +/- 0.48 Pass DW-40250, 40251 11/18/2013 Ra-226 27.77 +/- 2.84 26.15 +/- 2.67 26.96 +/- 1.95 Pass DW-40250, 40251 11/18/2013 Ra-228 7.91 +/- 0.94 6.32 +/- 0.84 7.12 +/- 0.63 Pass WAN-7164, 7165 11/19/2013 H-3 266.90 +/- 91.10 268.90 +/- 91.20 267.90 +/- 64.45 Pass SS-7334, 7335 11/20/2013 K-40 15.51 +/- 0.72 14.14 +/- 0.80 14.83 +/- 0.54 Pass WW-7558, 7559 11/22/2013 H-3 229.86 +/- 83.89 191.77 +/- 82.05 210.82 +/- 58.67 Pass LW-7292, 7293 11/26/2013 Gr. Beta 1.92 +/- 0.75 2.38 +/- 0.77 2.15 +/- 0.54 Pass W-7229, 7230 12/1/2013 Ra-226 0.87 +/- 0.23 0.88 +/- 0.25 0.88 +/- 0.17 Pass W-7229, 7230 12/1/2013 Ra-228 3.00 +/- 0.98 3.27 +/- 1.16 3.14 +/- 0.76 Pass SG-7313, 7314 12/2/2013 Ac-228 6.33 +/- 0.23 6.69 +/- 0.30 6.51 +/- 0.19 Pass SG-7313, 7314 12/2/2013 K-40 5.47 +/- 0.61 6.24 +/- 0.74 5.86 +/- 0.48 Pass SG-7313, 7314 12/2/2013 Pb-214 5.60 +/- 0.14 5.37 +/- 0.16 5.49 +/- 0.11 Pass W-7432, 7433 12/4/2013 Gr. Beta 5.35 +/- 1.20 3.89 +/- 1.23 4.62 +/- 0.86 Pass WW-7516, 7517 12/10/2013 H-3 369.30 +/- 95.64 269.22 +/- 91.35 319.26 +/- 66.13 Pass SG-7579, 7580 12/20/2013 Ra-226 3.72 +/- 0.11 3.85 +/- 0.30 3.79 +/- 0.16 Pass SG-7579, 7580 12/20/2013 Ra-228 2.38 +/- 0.18 2.77 +/- 0.44 2.58 +/- 0.24 Pass LW-7684, 7685 12/23/2013 Gr. Beta 0.84 +/- 0.51 1.96 +/- 0.61 1.40 +/- 0.40 Pass DW-40261, 40262 12/27/2013 Ra-226 0.54 +/- 0.10 0.67 +/- 0.10 0.61 +/- 0.07 Pass DW-40261, 40262 12/27/2013 Ra-228 1.09 +/- 0.51 1.12 +/- 0.43 1.11 00.33 Pass SWU-7663, 7664 12/30/2013 Gr. Beta 2.85 +/- 0.71 3.88 +/- 0.77 3.37 +/- 0.52 Pass Note: Duplicate analyses are performed on every twentieth sample received in-house. Results are not listed for those analyses with activities that measure below the LLD.

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

A5-6

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-738 02/01/13 Am-241 0.10 +/- 0.02 0.10 0.07 -0.14 Pass MAAP-738 02/01/13 Co-57 2.58 +/- 0.06 2.36 1.65 -3.07 Pass MAAP-738 02/01/13 Co-60 0.01 +/- 0.03 0.00 NA c Pass MAAP-738 02/01/13 Cs-1 34 1.82 +/- 0.13 1.78 1.25 - 2.31 Pass MAAP-738 02/01/13 Cs-1 37 2.93 +/- 0.10 2.60 1.82 -3.38 Pass MAAP-738 02/01/13 Mn-54 4.87 +/- 0.13 4.26 2.98 - 5.54 Pass MAAP-738 02/01/13 Pu-238 0.12 +/- 0.02 0.13 0.09 -0.17 Pass MAAP-738 02/01/13 Pu-239/40 0.11 +/- 0.02 0.12 0.09 -0.16 Pass MAAP-738 02/01/13 Sr-90 1.39 +/- 0.14 1.49 1.04-1.94 Pass MAAP-738 02/01/13 U-233/4 0.03 +/- 0.01 0.03 0.02 - 0.04 Pass MAAP-738 02/01/13 U-238 0.23 +/- 0.03 0.23 0.16 - 0.30 Pass MAAP-738 02/01/13 Zn-65 3.84 +/- 0.20 3.13 2.19 -4.07 Pass MAAP-738 02/01/13 Gr. Alpha 0.14 +/- 0.03 1.20 0.36 - 2.04 Fail MAAP-738 02/01/13 Gr. Beta 0.93 +/- 0.06 0.85 0.43 - 1.28 Pass MAW-806 02/01/13 Am-241 0.71 +/- 0.08 0.69 0.48 - 0.90 Pass MAW-806 02/01/13 Co-57 31.20 +/- 0.40 30.90 21.60 - 40.20 Pass MAW-806 02/01/13 Co-60 19.70 +/- 0.30 16.56 13.69 - 25.43 Pass MAW-806 02/01/13 Cs- 134 23.20 +/- 0.50 24.40 17.10 - 31.70 Pass MAW-806 02/01/13 Cs-1 37 0.03 +/- 0.12 0.00 NA c Pass MAW-806 02/01/13 Fe-55 34.00 +/- 3.30 44.00 30.80 - 57.20 Pass MAW-806 02/01/13 H-3 511.60 +/- 12.50 507.00 355.00 - 659.00 Pass MAW-806 02/01/13 K-40 2.20 +/- 0.90 0.00 NAc Pass MAW-806 02/01/13 Mn-54 27.60 +/- 0.50 27.40 19.20 - 35.60 Pass MAW-806 02/01/13 Ni-63 34.30 +/- 2.80 33.40 23.40 - 43.40 Pass MAW-806 02/01/13 Pu-238 0.83 +/- 0.10 0.88 0.62 -1.15 Pass MAW-806 02/01/13 Pu-239/40 0.02 +/- 0.02 0.01 NA d Pass MAW-806 02/01/13 Sr-90 9.30 +/- 0.80 10.50 7.40 -13.70 Pass MAW-806 02/01/13 Tc-99 10.25 +/- 0.40 13.10 9.20 - 17.00 Pass MAW-806 02/01/13 U-233/4 0.31 +/- 0.05 0.32 0.22 - 0.41 Pass MAW-806 02/01/13 U-238 1.91 +/- 0.13 1.95 1.37 -2.54 Pass MAW-806 02/01/13 Zn-65 31.60 +/- 0.80 30.40 21.30 - 39.50 Pass MAW-811 02/01/13 Gr. Alpha 1.87 +/- 0.09 2.31 0.69 - 3.93 Pass MAW-811 02/01/13 Gr. Beta 13.04 +/- 0.13 13.00 6.50 - 19.50 Pass MAW-811 02/01/13 1-129 4.60 +/- 0.19 6.06 4.24 - 7.88 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 MASO-739 02/01/13 Am-241 106.90 +/- 11.40 113.00 79.00 - 147.00 Pass MASO-739 02/01/13 Co-57 0.60 +/- 0.50 0.00 NA c Pass MASO-739 02/01/13 Co-60 739.20 +/- 28.50 691.00 484.00 -898.00 Pass MASO-739 02/01/13 Cs-1 34 863.30 +/- 34.10 887.00 621.00 -1153.00 Pass MASO-739 02/01/13 Cs-1 37 661.80 +/- 25.70 587.00 411.00 -763.00 Pass MASO-739 02/01/13 K-40 745.80 +/- 33.30 625.30 437.70 -812.90 Pass MASO-739 02/01/13 Mn-54 1.10 +/- 1.00 0.00 NAc Pass MASO-739 02/01/13 Zn-65 1109.60 +/- 44.10 995.00 697.00 - 1294.00 Pass MASO-744 02/01/13 Ni-63 682.60 +/- 16.80 670.00 469.00 -871.00 Pass MASO-744 02/01/13 Pu-238 0.20 +/- 0.90 0.52 NAd Pass MASO-744 02/01/13 Pu-239/40 88.30 +/- 9.00 79.50 55.70 - 103.40 Pass MASO-744 f 02/01/13 Sr-90 408.40 +/- 14.00 628.00 440.00 -816.00 Fail MASO-744 02/01/13 Tc-99 380.50 +/- 16.80 444.00 311.00 - 577.00 Pass MASO-744 02/01/13 U-233/4 53.20 +/- 4.80 62.50 43.80 - 81.30 Pass MASO-744 02/01/13 U-238 242.10 +/- 10.20 281.00 197.00 - 365.00 Pass MAVE-747 02/01/13 Co-57 10.37 +/- 0.17 8.68 6.08-11.28 Pass MAVE-747 02/01/13 Co-60 6.48 +/- 0.17 5.85 4.10 -7.61 Pass MAVE-747 02/01/13 Cs-1 34 0.02 +/- 0.04 0.00 NAc Pass MAVE-747 02/01/13 Cs-1 37 7.79 +/- 0.21 6.87 4.81 -8.93 Pass MAVE-747 02/01/13 Mn-54 0.00 +/- 0.05 0.00 NA c Pass MAVE-747 02/01/13 Zn-65 7.29 +/- 0.33 6.25 4.38 -8.13 Pass MASO-5043 08/01/13 Am-241 1.40 +/- 1.70 0.00 NA c Pass MASO-5043 g 08/01/13 Co-57 699.60 +/- 3.90 0.00 NA c Fail MASO-5043 08/01/13 Cs-1 34 1191.70 +/- 23.00 1172.00 820.00 - 1524.00 Pass MASO-5043 08/01/13 Cs-1 37 1072.00 +/- 5.10 977.00 684.00 - 1270.00 Pass MASO-5043 08/01/13 K-40 760.00 +/- 16.20 633.00 443.00 - 823.00 Pass MASO-5043 08/01/13 Mn-54 753.80 +/- 4.90 674.00 472.00 - 876.00 Pass MASO-5043 08/01/13 Ni-63 560.00 +/- 23.70 571.00 400.00 -742.00 Pass MASO-5043 08/01/13 Pu-238 68.40 +/- 7.50 61.50 43.10 -80.00 Pass NA d Pass MASO-5043 08/01/13 Pu-239/40 0.40 +/- 0.80 0.36 MASO-5043 08/01/13 Sr-90 383.90 +/- 14:50 460.00 322.00 -598.00 Pass MASO-5043 08/01/13 Tc-99 -1.00 +/- 10.50 0.00 NA c Pass MASO-5043 08/01/13 U-233/4 23.80 +/- 3.30 30.00 21.00 - 39.00 Pass MASO-5043 08/01/13 U-238 26.80 +/- 3.50 34.00 23.80 -44.20 Pass MASO-5043 08/01/13 Zn-65 -351.50 +/- 5.50 0.00 NA c 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-5052 08/01/13 1-129 2.75 +/- 0.20 3.79 2.65 -4.93 Pass MAW-5094 08/01/13 Am-241 0.00 +/- 0.01 0.00 NA c Pass MAW-5094 08/01/13 Co-57 0.01 +/- 0.09 0.00 NA c Pass MAW-5094 08/01/13 Co-60 23.20 +/- 0.32 23.58 16.51 -30.65 Pass MAW-5094 08/01/13 Cs-134 27.60 +/- 0.58 30.40 21.00 - 39.00 Pass MAW-5094 08/01/13 Cs-137 32.31 +/- 0.52 31.60 22.10 - 41.10 Pass MAW-5094 08/01/13 Fe-55 39.20 +/- 3.50 53.30 37.30 - 69.30 Pass MAW-5094 08/01/13 Gr. Alpha 0.54 +/- 0.05 0.70 0.21 -1.19 Pass MAW-5094 08/01/13 Gr. Beta. 5.85 +/- 0.09 5.94 2.97 -8.91 Pass MAW-5094 08/01/13 H-3 1.20 +/-3.00 0.00 NAC Pass MAW-5094 08/01/13 K-40 2.22 +/- 0.90 0.00 NA c Pass MAW-5094 08/01/13 Mn-54 0.01 +/- 0.11 0.00 NA c Pass MAW-5094 08/01/13 Ni-63 21.80 +/- 3.30 26.40 18.50 - 34.30 Pass MAW-5094 08/01/13 Pu-238 1.30 +/- 0.11 1.22 0.85 -1.58 Pass MAW-5094 08/01/13 Pu-239/40 0.98 +/- 0.09 1.00 0.70 -1.30 Pass MAW-5094 08/01/13 Sr-90 6.40 +/- 0.60 7.22 5.05 -9.39 Pass MAW-5094 08/01/13 Tc-99 13.10 +/- 0.70 16.20 11.30 - 21.10 Pass MAW-5094 08/01/13 U-233/4 0.08 +/- 0.02 0.07 NA d Pass MAW-5094 08/01/13 U-238 0.03 +/- 0.01 0.03 NA d Pass MAW-5094 08/01/13 Zn-65 35.30 +/- 0.90 34.60 24.20 - 45.00 Pass MAVE-5046 08/01/13 Co-57 0.01 +/- 0.03 0.00 NA c Pass MAVE-5046 08/01/13 Co-60 0.00 +/- 0.04 0.00 NA c Pass MAVE-5046 08/01/13 Cs-1 34 5.71 +/- 0.23 5.20 3.64 -6.76 Pass MAVE-5046 08/01/13 Cs-1 37 7.64 +/- 0.20 6.60 4.62 -8.58 Pass MAVE-5046 08/01/13 Mn-54 9.08 +/- 0.24 7.88 5.52 - 10.24 Pass MAVE-5046 08/01/13 Zn-65 2.92 +/- 0.25 2.63 1.84 -3.42 Pass A6-3

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

a Concentration Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAAP-5046 08/01/13 Am-241 0.01 +/- 0.02 0.00 NA c Pass MAAP-5046 08/01/13 Co-57 3.48 +/- 0.14 3.40 1.90 -3.50 Pass MAAP-5046 08/01/13 Co-60 2.44 +/- 0.08 3.40 1.60 -3.00 Pass MAAP-5046 08/01/13 Cs-134 0.01 +/- 0.03 0.00 NAG Pass MAAP-5046 08/01/13 Cs-137 3.09 +/- 0.13 2.70 1.90 -3.50 Pass MAAP-5046 08/01/13 Gr. Alpha 0.28 +/- 0.04 0.90 0.27 -1.53 Pass MAAP-5046 08/01/13 Gr. Beta 1.90 +/- 0.08 1.63 0.82 -2.45 Pass MAAP-5046 08/01/13 Mn-54 3.95 +/- 0.12 3.50 2.50 -4.60 Pass MAAP-5046 08/01/13 Pu-238 0.14 +/- 0.028 0.12 0.087 -0.16 Pass MAAP-5046 08/01/13 Pu-239/40 0.10 +/- 0.022 0.092 0.064 -0.12 Pass MAAP-5046 08/01/13 Sr-90 1.69 +/- 4.10 1.81 1.27 -2.35 Pass MAAP-5046 h 08/01/13 U-233/4 0.04 +/- 0.01 0.03 0.02 -0.04 Fail MAAP-5046 08/01/13 U-238 0.19 +/- 0.027 0.21 0.14 -0.27 Pass MAAP-5046 08/01/13 Zn-65 3.27 +/- 0.18 2.70 2.50 -4.60 Pass a Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

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

e The filter was recounted overnight, no significant alpha activity could be detected.

fThe sample was reanalyzed using additional fuming nitric separations. Result of reanalysis: 574.4 +/- 35.2 Bq/kg.

g Interference from Eu-152 resulted in misidentification of Co-57.

h Result of repeat analysis: 0.031 +/- 0.013 pCi/filter.

A6-4

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

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERAP-1 174 03/18/13 Am-241 65.2 +/- 4.4 66.8 41.2 -90.4 Pass ERAP-1 174 03/18/13 Co-60 226.5 +/- 4.1 214.0 166.0 - 267.0 Pass ERAP-1 174 03/18/13 Cs-1 34 1101.2 +/- 23.6 1110.0 706.0 - 1380.0 Pass ERAP-1 174 03/18/13 Cs-i 37 1065.6 +/- 21.4 940.0 706.0 - 1230.0 Pass ERAP-1 174 03/18/13 Fe-55 178.8 +/- 88.0 225.0 69.8 -440.0 Pass ERAP-1 174 03/18/13 Mn-54 <3.1 0.0 0.0 -50.0 Pass ERAP-1 174 03/18/13 Pu-238 50.0 +/- 3.0 51.1 34.3 - 65.9 Pass ERAP-1 174 03/18/13 Pu-239/40 65.7 +/- 2.6 65.2 47.2 - 85.2 Pass ERAP-1 174 03/18/13 U-233/4 54.0 +/- 2.5 59.4 36.8 - 89.6 Pass ERAP-1 174 03/18/13 U-238 55.6 +/- 2.6 58.9 38.1 -81.4 Pass ERAP-1 174 03/18/13 Uranium 112.0 +/- 5.6 121.0 67.0 - 184.0 Pass ERAP-1 174 03/18/13 Zn-65 236.6 +/- 13.8 199.0 142.0 - 275.0 Pass ERAP-1 175 03/18/13 Gr. Alpha 52.3 +/- 2.8 42.3 14.2 -65.7 Pass ERAP-1 175 03/18/13 Gr. Beta 36.2 +/- 2.0 25.1 15.9 -36.6 Pass ERSO-1 176 03/18/13 Am-241 293.1 +/- 97.4 229.0 134.0 - 297.0 Pass ERSO-1 176 03/18/13 Pu-238 909.0 +/- 180.0 788.0 474.0 -1090.0 Pass ERSO-1 176 03/18/13 Pu-239/40 432.0 +/- 120.0 366.0 239.0 - 506.0 Pass ERSO-1 176 03/18/13 Sr-90 8050.8 +/- 376.0 8530.0 3250.0 - 13500.0 Pass ERSO-1 176 03/18/13 U-233/4. 1662.6 +/- 150.0 1920.0 1170.0 - 2460.0 Pass ERSO-1 176 03/18/13 U-238 1682.8 +/- 160.0 1900.0 1180.0 - 2410.0 Pass ERSO-1 176 03/18/13 Uranium 3404.0 +/- 330.5 3920.0 2130.0 - 5170.0 Pass ERSO-1 176 03/18/13 Ac-228 1335.0 +/- 132.0 1240.0 795.0 - 1720.0 Pass ERSO-1 176 03/18/13 Bi-212 1420.0 +/- 311.0 1240.0 330.0 - 1820.0 Pass ERSO-1 176 03/18/13 Bi-214 2626.0 +/- 60.0 3660.0 2200.0 - 5270.0 Pass ERSO-1 176 03/18/13 Co-60 7951.0 +/- 45.4 7920.0 5360.0 - 10900.0 Pass ERSO-1 176 03/18/13 Cs-1 34 5785.0 +/- 51.0 6370.0 4160.0 - 7650.0 Pass ERSO-1 176 03/18/13 Cs-137 6106.0 +/- 47.9 6120.0 4690.0 - 7870.0 Pass ERSO-1 176 03/18/13 K-40 11756.0 +/- 284.3 10300.0 7520.0 - 13800.0 Pass ERSO-1 176 03/18/13 Mn-54 < 28.0 0.0 0.0 - 1000.0 Pass ERSO-1 176 03/18/13 Pb-212 1096.0 +/- 29.1 1240.0 812.0 - 1730.0 Pass ERSO-1 176 03/18/13 Pb-214 2875.0 +/- 60.0 3660.0 2140.0 - 5460.0 Pass ERSO-1 176 03/18/13 Th-234 2404.0 +/- 218.3 1900.0 601.0 - 3570.0 Pass ERSO-1 176 03/18/13 Zn-65 1542.0 +/- 56.4 1400.0 1110.0 - 1860.0 Pass A7-1

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

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result C Result d Limits Acceptance ERVE-1180 03/18/13 Am-241 569.8 +/- 81.7 553.0 338.0 -735.0 Pass ERVE-1180 03/18/13 Cm-244 1260.9 +/- 107.3 1340.0 657.0 - 2090.0 Pass ERVE-1180 03/18/13 Co-60 2130.5 +/- 48.0 1920.0 1320.0 -2680.0 Pass ERVE-1180 03/18/13 Cs-134 1296.5 +/- 68.0 1240.0 797.0 - 1610.0 Pass ERVE-1180 03/18/13 Cs-137 600.1 +/- 34.3 544.0 394.0- 757.0 Pass ERVE-1180 03/18/13 K-40 34078.0 +/- 787.0 31900.0 23000.0 -44800.0 Pass ERVE-1 180 03/18/13 Mn-54 < 28.7 0.0 0.0 -300.0 Pass ERVE-1180 03/18/13 Pu-238 2476.5 +/- 259.4 1980.0 1180.0 - 2710.0 Pass ERVE-1180 03/18/13 Pu-239/40 2659.3 +/- 273.2 2260.0 1390.0 - 3110.0 Pass ERVE-1180 03/18/13 Sr-90 3809.7 +/- 420.5 3840.0 2190.0- 5090.0 Pass ERVE-1180 03/18/13 U-233/4 2460.6 +/- 205.0 2460.0 1620.0 - 3160.0 Pass ERVE-1 180 03/18/13 U-238 2319.1 +/- 189.6 2440.0 1630.0 - 3100.0 Pass ERVE-1 180 03/18/13 Uranium 4866.3 +/- 375.6 5010.0 3390.0 - 6230.0 Pass ERVE-1180 03/18/13 Zn-65 1052.5 +/- 82.1 878.0 633.0 - 1230.0 Pass ERW-1184 03/18/13 Am-241 114.5 +/-8.1 118.0 79.5-158.0 Pass ERW-1184 03/18/13 Co-60 2221.8 +/- 17.0 2270.0 1970.0 - 2660.0 Pass ERW-1184 03/18/13 Cs-134 1309.4 +/- 58.4 1400.0 1030.0 - 1610.0 Pass ERW-1184 03/18/13 Cs-137 1865.9 +/- 22.0 1880.0 1600.0 - 2250.0 Pass ERW-1184 03/18/13 Fe-55 503.1 +/- 105.0 712.0 424.0 - 966.0 Pass ERW-1184 03/18/13 Mn-54 < 9.4 0.0 0.0 -100.0 Pass ERW-1184 03/18/13 Pu-238 98.4 +/-_5.6 98.8 73.1 -123.0 Pass ERW-1184 03/18/13 Pu-239/40 184.5 +/- 7.7 185.0 144.0 - 233.0 Pass ERW-1184 03/18/13 Sr-90 125.7 +/-_6.0 137.0 89.2 -181.0 Pass ERW-1184 03/18/13 U-233/4 44.9 +/- 3.4 48.8 36.7 -62.9 Pass ERW-1184 03/18/13 U-238 46.5 +/- 3.5 48.4 36.9 -59.4 Pass ERW-1184 03/18/13 Uranium 93.3 +/- 7.1 99.5 73.1 -129.0 Pass ERW-1184 03/18/13 Zn-65 412.8 +/- 32.0 384.0 320.0 - 484.0 Pass ERW-1186 03/18/13 Gr. Alpha 109.1 +/-_5.7 130.0 46.2-201.0 Pass ERW-1186 03/18/13 Gr. Beta 74.5 +/-_6.4 78.9 45.2 -117.0 Pass ERW-1188 03/18/13 H-3 12279.0 +/- 319.0 12300.0 8240.0 - 17500.0 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).

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.

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 = 2ay counting uncertainty (corresponding to the 95% confidence level).

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

3.0. Duplicate analyses If duplicate analyses are reported, the convention is as follows.

3.1 Individual results: For two analysis results; x, +/- si and x2 +/- s2 Reported result: x +/- s; where x = (1/2) (xi + x 2) ands = (1/2) S2+/-

3.2. Individual results: < L1i, < L2 Reported result: < L, where L = lower of L, and L2 3.3. Individual results: x +/- s, < L Reported result: x +/- s if x _>L; < L otherwise.

4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average 11 and standard deviation "s" of a set of n numbers xi, x2 ... xn are defined as follows:

0= 1 Yix S=

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 Air (pCi/m3) Water (pCi/L)

-J Gross alpha 1 x 10 Strontium-89 8,000 Gross betab 1 -1 Strontium-90 500 Iodine-I 31 2.8 x 10 Cesium-1 37 1,000 Barium-140 8,000 Iodine-131 1,000 Potassium-40 4,000 Gross alpha 2 Gross beta 10 6

Tritium I x10 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

TLO LOCATIONS ONE MILE RADIUS E

POANT A~REA~ ENLARGED PLAN (1.00 MILE RADIUS]

[NO SCALE]

MONITORING LEGEND-0 PRAIRIE ISLAND TL.D POINTS D-2

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

) PRAIRIE ISLAND TLD POINTS D-3

TLO LOCATIONS FIVE MILE RADIUS MONITORING LEGEND.-

0 PRAIRIE ISLAND TLD POINTS D-4

ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS E

PLANT AREA ENL.ARGED PLAN [1.00 MILE RADIUS3 (NO SCALE]

MONITORING LEGEND

• MILK SAMPLING POINT ID NUMBERS FISH SAMPLING P.OINT 10 NUMBERS P-18,P37. P-43 P-MO.-Iq A AIR SAMPLING.. POINT I1 NUMBERS PLI,: P-2, P-3, P-4. P-6, P-7 INVERTEBRATES POINT 1IDNUMBERS

..P-6. P-40 Q WATER SAMPLING POINT 10 NUMBERS P-5. P-6, P-8. P-9. P-1l. P-241 P SEDIMENT SAMPLING: POINT ID) NUMBERS P-9, P-12., P.20 VEGETATION / VEGETABLES ID NUMBERS Vl P-28. P-38. P-4 D-5

ENVIRONMENTAL SAMPLING POINTS

-FIVE MILE RADIUS MONITORING LEGEND MILK SAMPLING. POINT I NUMBERS FISH SAMPLING POINT 10 NUMBERS P-18, P-37. P-42. P-43 P-13, P-19 AIR SAMPLING POINT I NUMBERS INVERTEBRATES POINT 10 NUMBERS P-1. P-2, P-3,.P-4, P-6. P-7 P-6. P-40 WATER SAMPLING POINT ID NUMBERS SEDIMENT SAMPLING POINT 10 NUMBERS kZ* P-5, PýG. PA, P-,*P-11, P-24, PL43 P-G.,.P7.12, P-20 El VEGETATION / VEGETABLES .10. NUMBERS P-28, P-38. P-45 D-6

ENVIRONMENTAL SAMPLING POINTS P-.

P-i 4$l P43, Peterson Farm, W10322 St Rd 29, River Falls, WI ID P-38, Cain Residence, N7395 950th St, River Falls, WI CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND

<* MILK SAMPLING POINT ID NUMBERS P-18, P-37, P-41, P-42, P.43 A AIR SAMPLING POINT IDNUMBERS P-1, P-2, P-3, P-4, P-6, P-7 O WATER SAMPLING POINT IDNUMBERS P-6, P-6, P-8, P-9, P-11, P-43 0* VEGETATION / VEGETABLES ID NUMBERS P-28, P-38, P-45 D-7

APPENDIX E Special Well and Surface Water Samples E-1

1.0 INTRODUCTION

This appendix to the 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, 2013. 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 2013 are summarized and discussed.

Program findings for 2013 detected low levels of tritium in nearby residence wells, ground water, and surface samples at or near the expected natural background levels with the exception of ground water sample well MW-8. The 2013 sample results (except for MW-8) ranged from <19 pCi/L to 100 pCi/L.

Sample well MW-8 ranged from 266 pCi/L to 378 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 Samnlinq Procram 3.1 Proqram 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 forty-two locations. The Peterson (P-43) and Hanson (SW-1) farm wells are used as control locations for these special samples.

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

3.3 Progqram Execution The special water sampling program was executed as described in the preceding section with the following exceptions:

• No samples were available from wells P-8, PIIC-02, PIIC-03, PIIC-19, PIIC-20, PIIC-21, P1IC-22, PIIC-23, PIIC-24, PIIC-26, PIIC-27, and PIIC-28 in 2013.

• An annual (versus a semi-annual) sample was taken from locations 11 CST, 12 CST, and 13 CST. The second collection was missed.

3.4 Progqram Modifications Changes to the program in 2013 include:

• Samples taken from wells P-10 and MW-8 and stormwater runoff from S-6 and S-7 were sent to ATI Environmental, Incorporated for analysis of hard-to-detect nuclides, in accordance with American Nuclear Insurers recommendations (Table E-4.5).

• Samples were not collected from the warehouse septic or the D5 Fuel Oil Storage Tank vault. Sampling is not required.

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-8 ground water sample well. 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 well MW-8, the 2013 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 well MW-8 in 2013 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 11/14/2009. The main warehouse heating system was repaired in 1979. An additional discharge of approximately one gallon of heating steam condensate was released in 2013 from the maintenance warehouse. Corrective actions were taken to repair the steam isolation valve. The heating steam system was not used in the outer plant buildings during the 2013- 2014 heating season.

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, 2013.

Medium No. Location codes Collection type Analysis and type a and frequency b type Well water 17 P-8, REMP P-6, PIIC-02, PIIC-03, G/A H-3 Annual PIIC-19, PIIC-20, PIIC-21, PIIC-22, PIIC-23, PIIC-24, PIIC-26, PIIC-27, PIIC-28, P-7, P-11, PZ-1, PZ-2, PZ-4, PZ-5, PZ-7, MW-6, P-26, P-30, SW-3, SW-4, SW-5, SW-6, SW-7, P-9 Well water P-24D G/Q H-3 quarterly Well water 18 P-2, P-3, P-5, P-6, GIQ' H-3 quarterly' PZ-8, MW-4, MW-5 Well water monthly 60 P-43(C), SW-i (C), G/M H-3 MW-7, MW-8, P-10 Surface water 9 S-1, S-2, S-3, S-4, S-5, G/Ad H-3 S-6, S-7, P-31 Storage Tank 7 11 CST, 21 CST, 22 CST, G/S H-3 U1I/U2 Demin Hdr Storage Tank 12 Septic Tank 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.

bCollection 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.

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

A 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, 2013.

Code Collection site Type of Distance and sample ' direction from reactor P-8 P1 Community well WW 1.0 mi. @ 321°iWNW REMP P-6 Lock &Dam #3 well WW 1.6 mi. @ 129°/SE PIIC-02 2077 Other Day Road WW 1.4 mi. @ 315°/NW PIIC-03 6096 Whipple Way WW 1.4 mi. @ 310°/NW PIIC-19 6372 Sturgeon Lake Rd WW 1.7 mi. @ 293°/WNW PIIC-20 2158 Holmquist Road WW 1.6 mi @ 300°WNW PIIC-21 1802 Messiah Road WW 0.9 mi @ 281"W PIIC-22 1773 Buffalo Slough Rd WW 1 mi. @ 315°/NW PIIC-23 2.7 miles NW WW 2.7 mi @315"/NW PIIC-24 6424 Sturgeon Lake Rd WW 1.7 mi. (a 293A/WNW PIIC-26 1771 Buffalo Slough Rd WW 1 mi. @ 315°/NW PIIC-27 6372 Sturgeon Lake Rd WW 1.7 mi. @ 293°NVNW PIIC-28 1960 Larson Lane WW 1.5 mi @ 288"/WNW P-24D Suter residence WW 0.6 mi. @ 158°/SSE P-43 Peterson Farm (Control) WW 13.9 mi. @ 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-1I Sample well WW See map PZ-1 Sample well WW See map PZ-2 Sample well WW See map PZ-4 Sample well WW See map PZ-5 Sample well WW See map PZ-7 Sample well WW See map PZ-8 Sample well WW See map MW-4 Sample well WW See map MW-5 Sample well WNW See map MW-6 Sample well WW See map MW-7 Sample well WW See map MW-8 Sample well WW See map P-26 PITC well WW 0.4 mi. @ 258°iWSW 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, 2013 (continued).

Code Collection site Type of Distance and sample a direction from reactor SW-3 Cooling Tower pump WW See map SW-4 New Admin Bldg WW 0.05 mi. @ 315°/NW SW-5 Plant Screenhouse well WW 0.05 mi. @ 0°/N SW-6 Restroom Trailer well WW 0.2 mi @ 310"/NW SW-7 Distribution Center WW 0.35 mi @ 271°NW P-9 Plant well # 2 WW 0.3 mi. a 306°/NW S-1 Upstream Miss. River SW See map S-2 Recirc/Intake canal SW See map S-3 Cooling water canal SW See map S-4 Discharge Canal (end) SW See map S-5 Mid Discharge Canal SW See map S-6 Roof Stormwater Runoff (also snow) SW 0.05 mi. @ 0'/N S-7 Parking Lot Stormwater (also snow) SW 0.3 mi @ 306"/NW S-8 P-10 area snow SW See map S-9 MW-7/8 area snow SW See map P-31 Birch Lake Seepage SW 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 Building Septic System Storage Tank ST Outside #1 Warehouse Warehouse Septic Storage Tank ST Outside #1 Warehouse D5 Vault Concrete Vault ST Outside Turbine Bldg 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, 2013 (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 Range' Range c Range C Non-(Units) Analyses a Routine Results e Offsite Well H-3 5 19 23 (1/5) P-24D 23 (1/4) (See Control Water (23) (23) Below)

(pCi/L)

Onsite H-3 73 19 111 (60/73) MW-8 320 (12/12) (See Control Well Water (21-378) (266-378) Below)

(pCi/L)

Onsite H-3 13 19 58 (10/13) S-7 94(2/2) (See Control Surface Water (21-160) (28-160) Below) 0 (pCi/L)

Onsite H-3 19 19 98 (17/19) 121 (12/12). (See Control Storage Tank (24-293) Septic System (29-293) Below) 1 (pCi/L)

Control (offsite H-3 25 19 none SW-i 27 (4/12) 25 (5/25) well water) (24-30) (21-30) a H-3 = tritium b LLD = Nominal lower limit of detection based on 4.66 sigma error for background sample. Value shown is lowest for the period.

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

d Locations are specified by code.

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

E-8

Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2013.

SAMPLE DATES (2013) JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC STATION LOCATION-CODE OFFSITE WELLS H-3 Concentration (pCi/L)

P-8 PI Community Well

<19 REMP P-6 Lock & Dam #3 well PIIC-02 2077 Other Day Road PIIC-03 6096 Whipple Way PIIC-19 6372 Sturgeon Lake Rd PIIC-20 2158 Holmquist Rd PIIC-21 1802 Messiah Road PIIC-22 1773 Buffalo Slough Rd PIIC-23 2.7 miles NW of plant PIIC-24 6424 Sturgeon Lake Rd PIIC-26 1771 Buffalo Slough Rd PIIC-27 6372 Sturgeon Lake Rd PIIC-28 1960 Larson Lane 19 <19 23 <19 P-24D Suter residence

<19/21*

Peterson Farm (Control) <19 <19 <19 <19 <19 <19 <19 <19 <19 <19 snow <19 P-43 Hanson Farm (Control) <19 <19 <19 <19 27 <19 <19 <19 25 30 24 <19 SW-I E-9

Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2013 (continued).

SAMPLE DATES (2013) JAN FEB MAR APR MAY JUN JUL IAUG SEP OCT NOV DEC STATION LOCATION-CODE ONSITE WELLS H-3 Concentration (pCi/L)

P-2 Sample well 34 100 60 P-3 Sample well 57 29 63 P-5 Sample well 84 98 71 P-6 Sample well 33 <19 68 P-7 Sample well 76 P-10 Sample well 82 55 31 55 58 69 74 44 55 94 74 86 P-1I Sample well 80 PZ-1 Sample well 22 PZ-2 Sample well 29 PZ-4 Sample well 67 PZ-5 Sample well 33 PZ-7 Sample well 21 PZ-8 Sample well <19 47 44 MW-4 Sample well <19 50 <19 MW-5 Sample well <19 52 45 MW-6 Sample well 47 MW-7 Sample well 52 85 25 59 47 77 74 55 56 71 74 68 MW-8 Sample well 337 378 314 369 298 308 284 293 316 336 336 266 P-26 PITC well <19 P-30 Env. lab well <19 SW-3 Cooling Tower pump <19 P-9 Plant well # 2 <19 SW-4 New Admin Bldg. <19 SW-5 Plant Screenhouse Well <19 SW-6 Restroom Trailer <19 SW-7 Distribution Center <19 E-1 0

Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2013 (continued).

SAMPLE DATES (2013) JAN FEB MAR APR MAY JUN IJUL IAUG SEP OCT NOV DEC STATION LOCATION-CODE ONSITE SURFACE WATER H-3 Concentration (pCi/L)

S-1 Mississippi River upstream 31 S-2 Recirculation/Intake canal <19 S-3 Cooling water canal <19 S-4 Discharge Canal (end) <19 S-5 Discharge Canal (midway) 21 S-6 Stormwater runoff 89 61*

S-7 Parking Lot runoff 160 28*

S-8 P-10 area snow 24*

S-9 MW-7/8 area snow 76*

P-31 Birch Lake Seepage 33 56

• snow samples E-11

Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2013 (continued).

SAMPLE DATES (2013) JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC STATION LOCATION-CODE ONSITE STORAGE TANKS H-3 Concentration (pCi/L) 11 CST Storage tank <19 21 CST Storage tank 31 22 CST Storage tank <19 U1/U2 Demin Storage tank 24/40 68/61 Header Septic Storage tank 29 63 46 128 49 175 67 60 225 144 169 293 System E-1 2

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

Location P-1 0 Well MW-8 Well S-60 AB Roof S-7 Parking Lot Collection Date 09-16-13 09-16-13 09-16-13 09-16-13 Lab Code PXW-5493 PXW-5494 PXW-5495 PXW-5496 Isotope Concentration (pCi/mL)

Fe-55 < 7.4 E-07 < 7.9 E-07 < 7.5 E-07 < 7.6 E-07 Ni-63 < 1.1 E-08 < 1.2 E-08 < 1.3 E-08 < 1.3 E-08 Sr-90 < 4.2 E-10 < 4.4 E-10 < 5.4 E-10 < 5.4 E-10 Pu-238 < 1.0 E-10 < 2.3 E-10 < 1.7 E-10 < 2.0 E-10 Pu-239/240 < 5.9 E-11 < 2.1 E-10 < 1.2 E-10 < 1.2 E-10 Am-241 < 8.2 E-11 < 1.1 E-10 < 1.3 E-10 < 7.8 E-11 Cm-242 < 8.2 E-11 < 1.9 E-10 < 1.1 E-10 < 1.1 E-10 Cm-243/244 < 1.8 E-10 < 2.3 E-10 < 2.0 E-10 < 2.1 E-10 E-1 3

4

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-8 Groundwater Monitoring Well Locations E-1 4