Text

ISFSI - 2014 Annual Radioloqical Environmental Monitoring Program (REMP) Report
	ML15132A656
Person / Time
Site:	Prairie Island
Issue date:	05/11/2015
From:	Davison K; Northern States Power Co, Xcel Energy
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
	L-PI-15-039
	Download: ML15132A656 (75)
	v • d • e

ý&XcelEnergy MAY 11 2014 L-PI-1 5-039 TS 5.6.2 ISFSI TS 5.2 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant Units 1 and 2 Dockets 50-282 and 50-306 Renewed License Nos. DPR-42 and DPR-60 Prairie Island Independent Spent Fuel Storage Installation Docket 72-10 Materials License No. SNM-2506 2014 Annual Radioloqical Environmental Monitorinq Proqram (REMP) Report Pursuant to Prairie Island Nuclear Generating Plant (PINGP) Technical Specification (TS) 5.6.2, Appendix A, to Renewed Operating Licenses DPR-42 and DPR-60, and Prairie Island Independent Spent Fuel Storage Installation Technical Specification (ISFSI TS) 5.2, Appendix A, to Materials License SNM-2506, Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"),

submits one copy of the Annual Radiological Environmental Monitoring._kogram report for the period January 1, 2014, through December 31, 2014, as Enclosure 1.

Summary of Commitments This letter contains no new commitment and no revision to any existing commitment.

Kevin Davison Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota Enclosure cc:

Regional Administrator, USNRC, Region III Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector, Prairie Island Nuclear Generating Plant Billy Dickson, USNRC, Region III Director of NMSS, USNRC Department of Health, State of Minnesota PI Dakota Community Environmental Coordinator vk-1 2!-kS 1717 Wakonade Drive East

Welch, Minnesota 55089-9642 Telephone: 651.388.1121

ENCLOSURE I Annual Report to the United States Nuclear Regulatory Commission Radiological Environmental Monitoring Program January 1 to December 31, 2014 73 pages follow

-,ATI Environmental, Inc.

%Midwest Laboratory 700 Londwehr 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, 2014 Docket No. 50-282 50-306 ISFSI Docket No.72-10 License No. DPR-42 DPR-60 SNM-2506 Prepared under Contract by ENVIRONMENTAL, Inc.

MIDWEST LABORATORY Project No. 8010 Approved:

Laoa M.S.

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

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

ii

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

ii L is t o f T a b le s...........................................................................................................................................

iv L is t o f F ig u re s..........................................................................................................................................

v

1.0 INTRODUCTION

1 2.0 S U M M A R Y..............................................................................................................................................

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

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

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

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

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

6 3.5 Program M odifications...................................................................................................................

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

6 4.0 RESULTS AND DISCUSSIO N.........................................................................................................

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 FIG URES AND TABLES.......................................................................................................................

12

6.0 REFERENCES

CITED..........................................................................................................................

24 APPENDICES A

Interlaboratory Com parison Program Results..................................................................................

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

A-2 B

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

B-1 C

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

C-1 D

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

D-1 E

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

E-1 iii

LIST OF TABLES No.

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

15 5.2 S a m p lin g L o c a tio n s...................................................................................................................................

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

19 5.4 Radiological Environmental Monitoring Program Summary................................................................

20 In addition, the following tables can be found in the Appendices:

Appendix A A-1 Environmental Resources Associates, Crosscheck Program Results..............................................

A1-1 A-2 Program Results; (TLDs)......................................................................................................................

A2-1 A-3 In-house "Spiked" Samples..................................................................................................................

A3-1 A-4 In-house "Blank" Samples.....................................................................................................................

A4-1 A-5 In-house "Duplicate" Samples........................................................................................................

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

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

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

E-5 E -4.2 S a m p lin g lo catio n s.................................................................................................................................

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 Pa*e 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator lo catio n s ve rs us co ntro l..............................................................................................................................

13 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6,7) versus control location (P-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 m ile radius.....................................................................................................

D-4 REMP sampling points within a one m ile radius......................................................................................

D-5 REMP sampling points within a five m ile radius..................................................................................

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

D-7 Appendix E Groundwater Monitoring W ell locations..................................................................................................

E-15 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, 2014. 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.

1

2.0

SUMMARY

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

Results for 2014 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.

2

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

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

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

Sources of environmental radiation include the following:

(1)

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

Fallout from atmospheric nuclear detonations; (3)

Releases from nuclear power plants; (4)

Industrial and medical radioactive waste; and (5)

Fallout from nuclear accidents.

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

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

An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the plant site. The plant's monitoring program includes analyses for tritium and iodine-1 31. Most samples are analyzed for gamma-emitting isotopes with results for the following groups quantified:

zirconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40. The first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor:

each constitutes about 10% of the total activity of fission products 10 days after reactor shutdown. On the other hand, 10 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, 1963).

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

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

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

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

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

3

3.1 Pro-gram 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, 2014). 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 CaSO4:Dy dosimeters with four sensitive areas at each location:

ten in an inner ring in the general area of the site boundary, fifteen in the outer ring within a 4-5 mile radius, eight at special interest locations, and one control location, 11.1 miles distant from the plant.

They are replaced and measured quarterly.

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

Facility by twenty CaSO4:Dy dosimeters. Twelve dosimeters are located inside of the earthen berm in direct line of sight from the storage casks and eight dosimeters are located outside of the earthen berm. They are replaced and measured quarterly.

Milk samples are collected monthly from 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.

4

3.2 Proqram Description (continued)

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

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

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

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

(1) Airborne Particulates / Airborne Iodine:

A partial sample was collected from location P-02 for the week ending January 29, 2014.

Sampler runtime was approximately 45 hours5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months . No air particulate / air iodine sample was available from location P-04 for the week ending February 20, 2014. The location was inaccessible due to snow. The February 27, 2014 samples from P-04 were for a two-week period. A partial sample was collected from location P-01 for the week ending April 30, 2014. Sampler runtime was approximately 108 hours0.00125 days 0.03 hours 1.785714e-4 weeks 4.1094e-5 months .

(2) Milk:

There were no samples collected 05/13/14 from location P-18. The farm is no longer a dairy farm.

There was no milk collected 12/16/14 at location P-37. The farm has temporarily suspended milking operations.

(3) TLD:

TLD's from location P-01A and P-10A were collected three days early due to potential flooding.

Deviations from the program are summarized in Table 5.3.

5

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

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

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

Tritium concentrations are determined by liquid scintillation.

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

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

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

Details of the QA Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 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 None.

3.6 Land Use Census In accordance with the Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual, H4, (ODCM) a land use census is conducted in order to identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 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, 2014. There were no changes to any of the highest D/Q locations for garden sites, or nearest residence. The nearest milk animal changed from P-18 to P-37 following the suspension of milking operations at P-18.

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

Therefore, no corn samples were collected for analysis.

6

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

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

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported accidents involving significant release to the environment at nuclear reactor facilities in 2014. The Fukushima Daiichi nuclear accident occurred March 11, 2011.

There were no reported atmospheric nuclear tests in 2014. 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/ M3, 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.

7

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 14.9 mR/91 days at inner ring locations to 15.7 mR/91 days at outer ring locations.

The mean at special interest locations was 14.1 mR/91 days and 16.2 mR/91 days at the control location. Dose rates measured at the inner and outer ring and the control locations were comparable to 2013 dose rates and 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 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 2006 16.6 16.6 2014 15.3 16.2 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates (mR/91 days).

ISFSI Facility Operations Monitoring Ambient radiation was measured inside the ISFSI earth berm, outside the ISFSI earth berm and at two special locations between the plant ISFSI and the Prairie Island Indian Community. The mean dose rates averaged 135.0 mR/91 days inside the ISFSI earth berm and 20.8 mR/91 days outside the ISFSI earth berm. Three additional casks were placed on the ISFS1 pad in 2014, a total of thirty-eight loaded casks remain. The higher levels inside the earth berm are expected, due to the loaded spent fuel casks being in direct line-of-sight of the TLDs.

Ambient radiation levels measured outside the earth berm show a slight increase as compared to other offsite dose rates around the plant. The cumulative average of the two special Prairie Island Indian Community TLDs measured 13.2 and 13.5 mR/91 days. Although the skyshine neutron dose rates are not directly measured, the neutron levels measured next to the casks are below the levels predicted in the ISFSI SAR Report, Table 7A-4, "TN-40 Dose Rates at Short Distances". Therefore, the skyshine dose rates at farther distances from the casks should be at or below the calculated dose rates. No spent fuel storage effect on offsite ambient gamma radiation was indicated (Fig. 5-1).

8

Airborne Particulates Typically, the highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 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 0.026 pCi/m3 for both the indicators and the control location and similar to levels observed from 1999 through 2006 and 2008 to 2013. The results are tabulated below.

Average of Year Indicators Control Concentration (pCi/m 3) 1999 0.024 0.022 2000 0.025 0.025 2001 0.023 0.023 2002 0.028 0.023 2003 0.027 0.025 2004 0.025 0.026 2005 0.027 0.025 2006 0.026 0.025 2007 0.037 0.031 2008 0.028 0.027 2009 0.029 0.029 2010 0.025 0.025 2011 0.026 0.027 2012 0.031 0.032 2013 0.027 0.028 2014 0.026 0.026 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 mArnold and AI-Salih, 1955) was detected in all samples, with an average activity of 0.064 pCi/mi for indicator locations and 0.069 pCi/i 3 at the control locations. All other isotopes were below the lower limit of detection.

There was no indication of a plant effect.

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

9

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

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

In 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 2014 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 177 pCi/L for all samples.

Gross beta concentrations averaged 11.5 pCi/L throughout the year, ranging from 6.1-18.1 pCi/L.

These concentrations are consistent with levels observed from 1998 through 2013. The most likely contribution is the relatively high levels of naturally-occurring radium. Gamma spectroscopy indicates the presence of lead and bismuth isotopes, which are daughters of the radium decay chain. There is no indication from the 2014 data of any effect of plant operation.

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

River Water All river water samples measured below an LLD level of 179 pCi/L.

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

In summary, the data for 2014 show no radiological effects from the plant operation.

10

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

In summary, well water data for 2014 show no radiological effects of the plant operation.

Crops Two samples of broadleaf vegetation, cabbage leaves, were collected in August, 2014 and analyzed for gamma-emitting isotopes, including iodine-131. The 1-131 level was below 0.017 pCi/g wet weight in all samples. With exceptions for naturally-occurring beryllium-7 and potassium-40, all other gamma-emitting isotopes were below their respective detection limits.

There was no indication of a plant effect.

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

Fish Fish were collected in May and September, 2014 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 July and September, 2014 and analyzed for gamma-emitting isotopes. All gamma-emitting isotopes measured below detection limits. There was no indication of any plant effect.

Bottom and Shoreline Sediments Upstream and downstream bottom sediments and downstream recreational area shoreline sediments were sampled in July, September and October, 2014 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.

11

5.0 FIGURES AND TABLES 12

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

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~. ___.1 CD 0

D 0

C0 01 0

0 0

0 (0

00 0

0D 0

0 0

0

~

(0 0

Q

w.

41'

.0.

MT

-4 co (D

NJ

w.

0 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)

Airborne Particulates 54 P-OIA - P-IOA P-OIB - P-15B P-01S - P-08S P-OlIA - P-O81A P-OIlB - P-081B P-OIlX-P-041X, P-01C C/Q Ambient gamma GB, GS (QC of each location) 5 P-I(C), P-2, P-3, P-4, P-6, P-7 Airborne Iodine 5

P-1(C), P-2, P-3, P-4, P-6, P-7 Milk 4

P-18, P-37, P-43 (C)

River water Drinking water 2

P-5(C), P-6 i

P-1i Well water Edible cultivated crops -

leafy green vegetables Fish (one species, edible portion)

Periphyton or invertebrates Bottom sediment Shoreline sediment 5

P-6, P-8, P-9, P-24, P-43 (C) 3 P-28, P-38(C), P-45 2

P-19(C), P-13 2

P-40(C), P-6 2

P-20(C), P-6 1

P-12 C/W C/W G/Ma G/W G/W G/Q G/A G/SA G/SA G/SA G/SA 1-131 1-131, GS GS(MC), H-3(QC)

GB(MC), 1-131(MC)

GS (MC), H-3 (QC)

H-3, GS GS (1-131)

GS GS GS GS 8 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.

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

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

d 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 Type" from Reactor P-I P-2 P-3 P-4 P-5 P-6 P-7 P-8 P-9 P-11 P-12 P-13 P-18 P-19 P-20 P-24 P-28 P-37 P-38 P-40 P-43 P-45 C

Air Station P-1 Air Station P-2 Air Station P-3 Air Station P-4 C

Upstream of Plant Lock and Dam #3 & Air Station P-6 Air Station P-7 Community Center Plant Well #2 Red Wing Service Center Downstream of Plant Downstream of Plant AP, Al AP, Al AP, Al AP, Al RW AP, Al, RW WW, BS, BOc AP, Al WW WW DW SS Fc M

F0 BS WW VE M

VE B0c M, WW VE C

C C

Christiansen Farm Upstream of Plant Upstream of Plant Suter Residence Allyn Residence Welsch Farm Cain Residence Upstream of Plant Peterson Farm Glazier Residence 11.8 mi @ 316°/NNW 0.5 mi @ 2940/WNW 0.8 mi @ 3130/NW 0.4 mi @ 3590/N 1.8 mi @ 11°/N 1.6 mi @ 1290/SE 0.5 mi @ 271 0/W 1.0 mi @ 3210/WNW 0.3 mi @ 3060/NW 3.3 mi @ 1580/SSE 3.0 mi @ 1160/ESE 3.5 mi @ 113°/ESE 3.8 mi @ 880/E 1.3 mi @ O°/N 0.9 mi @ 450/NE 0.6 mi @ 1580/SSE 1.0 mi @ 1520/SSE 4.1 mi @ 870/E 14.2 mi @ 3590/N 0.4 mi @ O°/N 13.9 mi. @ 3550/N 0.6 mi. @ 3410/NNW 0.4 mi @ 3590/N 0.3 mi @ 100/N 0.5 mi @ 1830/S 0.4 mi @ 2040/SWW 0.4 mi @ 2250/SW 0.4 mi @ 2490/WSW 0.4 mi @ 2680/W 0.4 mi @ 2910/WNW 0.7 mi @ 3170/NW 0.5 mi @ 3330/NNW General Area of the Site Boundary P-OIA P-02A P-03A P-04A P-05A P-06A P-07A P-08A P-09A P-OA Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line Property Line TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 16

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

Distance and Direction Code Typea Collection Site Sample TypeD from Reactor Approximately 4 to 5 miles Distant from the Plant P-OIB P-02B P-03B P-04B P-05B P-06B P-07B P-08B P-09B P-lOB P-11B P-12B P-13B P-14B P-15B Thomas Killian Residence Roy Kinneman Residence Wayne Anderson Farm Nelson Drive (Road)

County Road E and Coulee William Hauschiblt Residence Red Wing Public Works David Wnuk Residence Highway 19 South Cannondale Farm Wallace Weberg Farm Ray Gergen Farm Thomas O'Rourke Farm David J. Anderson Farm Hoist Farms TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD TLD 4.7 mi @ 3550/N 4.8 mi @ 170/NNE 4.9 mi @ 460/NE 4.2 mi @ 610/ENE 4.2 mi @ 1020/ESE 4.4 mi @ 1120/ESE 4.7 mi @ 1400/SE 4.1 mi @ 1650/SSE 4.2 mi @ 1870/S 4.9 mi @ 2000/SSW 4.5 mi @ 221°/SW 4.6 mi @ 251°/WSW 4.4 mi @ 2700/W 4.9 mi @ 3060/NW 3.8 mi @ 3450/NNW 1.6 mi @ 1290/SE 0.5 mi @ 1550/SSE 2.2 mi @ 1730/S 2.0 mi @ 2020/SSW 2.0 mi @ 2700/W 2.5 mi @ 2990/WNW 0.7 mi @ 2710/W 0.7 mi @ 2870/NWW 11.1 mi @ 331°/NNW Special Interest Locations P-015 P-02S P-03S P-04S P-05S P-06S P-07S P-08S P-OIC Federal Lock & Dam #3 Charles Suter Residence Carl Gustafson Farm Richard Burt Residence Kinney Store Earl Flynn Farm Indian Community Indian Community C

Robert Kinneman Farm TLD TLD TLD TLD TLD TLD TLD TLD TLD 17

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-011A ISFSI Nuisance Fence TLD 190' @ 450/NE P-021A ISFSI Nuisance Fence TLD 360' @ 82 0/E P-031A ISFSI Nuisance Fence TLD 370' @ I00°/E P-041A ISFSI Nuisance Fence TLD 200' @ 134°/SE P-051A ISFSI Nuisance Fence TLD 180' @ 2190/SW P-061A ISFSI Nuisance Fence TLD 320' @ 2580/WSW P-071A ISFSI Nuisance Fence TLD 320' @ 281°/WNW P-081A ISFSI Nuisance Fence TLD 190' @ 318°/NW P-OIIX ISFSI Nuisance Fence TLD 140' @ 1800/S P-021X ISFSI Nuisance Fence TLD 310' @ 270°/W P-031X ISFSI Nuisance Fence TLD 140' @ O°/N P-041X ISFSI Nuisance Fence TLD 360' @ 900/E ISFSI Area Outside Earth Berm P-011B ISFSI Berm Area TLD 340' @ 3 0/N P-021B ISFSI Berm Area TLD 380' @ 280/NNE P-031B ISFSI Berm Area TLD 560' @ 85 0/E P-041B ISFSI Berm Area TLD 590' @ 165°/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 Distance and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location.

18

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

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

Collection Reason for not Sample Analysis Location Date or conducting REMP Plans for Preventing Type Period as required Recurrence AP/AI Beta, 1-131 P-2 1/29/2014 Blown fuse on pump.

Pump replaced.

AP/AI Beta, 1-131 P-4 2/20/2014 Location inaccessible due to None required.

snow.

AP/AI Beta, 1-131 P-1 4/30/2014 Blown fuse on pump.

Pump replaced.

Ml Gamma, 1-131 P-18 5/13/2014 Farm is no longer a dairy farm.

None required.

TLD Gamma P-01A, 06/23/14 Samples collected three None required.

P-1 0A days early due to potential flooding.

Ml Gamma, 1-131 P-37 12/16/2014 Welsch Farm has temporarily None required.

suspended milking operations.

19

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

50-282, 50-306 Reporting Period January-December, 2014

( 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)'

Mean (F)c Routine (Units)

Analysesa Rangec Locationd Range' Range0 Resultse Direct Radiation TLD (Inner Ring, Gamma 40 3.0 14.9 (40/40)

P-05A 16.6 (4/4)

(See Control 0

Area at Site (11.8-19.6) 0.4 mi @ 2250 /SW (14.8-19.6) below.)

Boundary) mR/91 days)

TLD (Outer Ring, Gamma 60 3.0 15.7 (60/60)

P-04B, Nelson Dr.,

18.8 (4/4)

(See Control 0

4-5 mi. distant)

(11.8-20.2) 4.2 mi @ 61' /ENE (16.7-20.2) below.)

mR/91 days)

TLD (Special Gamma 32 3.0 14.1 (32/32)

P-04S, Burt Residence, 16.3 (4/4)

(See Control 0

Interest Areas)

(11.5-18.3) 2.0 mi @ 2020/SSW (15.1-18.3) below.)

mR/91 days)

TLD (Control)

Gamma 4

3.0 None P-01C, Robert Kinneman 16.2 (4/4) 16.2 (4/4) 0 mR/91 days) 11.1 mi @ 331'/NNW (14.7-19.7)

(14.7-19.7)

Airborne Pathway Airborne GB 311 0.005 0.026 (259/259)

P-03, Air Station 0.026 (52 /52) 0.026 (52/52) 0 Particulates (0.008-0.053) 0.8 mi @ 3130/NW (0.010-0.051)

(0.010-0.052)

(pCi/n 3)

GS 24 Be-7 0.015 0.064 (20/20)

P-01, Air Station 0.069 (4/4) 0.069 (4/4) 0 (0.041-0.095) 11.8 mi @ 3160 /NNW (0.043-0.086)

(0.043-0.086)

Mn-54 0.0008

< LLD

< LLD 0

Co-58 0.0008

< LLD

< LLD 0

Co-60 0.0008

< LLD

< LLD 0

Zn-65 0.0015

< LLD

< LLD 0

Zr-Nb-95 0.0011

< LLD

< LLD 0

Ru-103 0.0011

< LLD

< LLD 0

Ru-1 06 0.0065

< LLD

< LLD 0

Cs-1 34 0.0007

< LLD

< LLD 0

Cs-1 37 0.0008

< LLD

< LLD 0

Ba-La-140 0.0035

< LLD

< LLD 0

Ce-141 0.0015

< LLD

< LLD 0

Ce-144 0.0042

< LLD

< LLD 0

Airborne Iodine 1-131 311 0.030

< LLD

< LLD 0

(pCi/m3) 20

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

50-282, 50-306 Reporting Period January-December, 2014 Location of Facility Goodhue, Minnesota

( County, State)

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

Analysesa Range' Locationd Rangec Rangec Resultse Terrestrial Pathway Milk (pCi/L) 1-131 39 0.5

< LLD

< LLD 0

GS 39 K-40 200 1378 (21/21)

P-43 (C), Peterson Farm 1424 (18 /18) 1424 (18/18) 0 (1294-1521) 13.9 mi @ 355°/N (1318-1511)

(1318-1511)

Cs-134 5

< LLD

< LLD 0

Cs-137 5

< LLD

< LLD 0

Ba-La-140 5

< LLD

< LLD 0

Crops - Cabbage 1-131 2

0.017

< LLD

< LLD 0

(pCi/gwet)

Well Water H-3 20 172

< 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 38

< 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 Reporting Period January-December, 2014 Location of Facility Goodhue, Minnesota

( 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)c Mean (F)c Routine (Units)

Analysesa Range' Locationd Range' Range' Resultse Waterborne Pathway Drinking Water GB 12 1.0 11.5 (12/12)

P-11, Red Wing S.C.

11.5 (12/12)

None 0

(pCi/L)

(6.1-18.1) 3.3 mi @ 158'/SSE (6.1-18.1) 1-131 12 1.0

< LLD None 0

H-3 4

177

< 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 43

< LLD None 0

River Water H-3 8

179

< LLD

< LLD 0

(pCi/L)

GS 24 Mn-54 10

< LLD

< LLD 0

Fe-59 30

< LLD

< LLD 0

Co-58 10

< LLD

< LLD 0

Co-60 10

< LLD

< LLD 0

Zn-65 30

< LLD

< LLD 0

Zr-Nb-95 15

< LLD

< LLD 0

Cs-134 10

< LLD

< LLD 0

Cs-137 10

< LLD

< LLD 0

Ba-La-140 15

< LLD

< LLD 0

Ce-144 27

< LLD

< LLD 0

Fish GS 6

(pCi/g wet)

K-40 0.10 2.92 (6/6)

P-19, Upstream 3.04 (6/6) 3.04 (6/6) 0 (2.54-3.36) 1.3 mi @ 00 /N (2.82-3.37)

(2.82-3.37)

Mn-54 0.03

< LLD

< LLD 0

Fe-59 0.15

< LLD

< LLD 0

Co-58 0.03

< LLD

< LLD 0

Co-60 0.022

< LLD

< LLD 0

Zn-65 0.049

< LLD

< LLD 0

Zr-Nb-95 0.099

< LLD

< LLD 0

Cs-134 0.022

< LLD

< LLD 0

Cs-1 37 0.022

< LLD

< LLD 0

Ba-La-140 1.97

< LLD

< LLD 0

22

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

50-282, 50-306 Reporting Period January-December, 2014

( County, State )

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

Analysesa Rangec Locationd Range' Rangec Resultse Waterborne Pathway Invertebrates GS 4

(pCi/g wet)

Be-7 1.04

< LLD

< LLD 0

K-40 0.98

< LLD

< LLD 0

Mn-54 0.058

< LLD

< LLD 0

Co-58 0.089

< LLD

< LLD 0

Co-60 0.048

< LLD

< LLD 0

Zn-65 0.13

< LLD

< LLD 0

Zr-Nb-95 0.24

< LLD

< LLD 0

Ru-103 0.17

< LLD

< LLD 0

Ru-106 0.42

< LLD

< LLD 0

Cs-134 0.048

< LLD

< LLD 0

Cs-137 0.057

< LLD

< LLD 0

Ba-La-140 2.98

< LLD

< LLD 0

Ce-141 0.35

< LLD

< LLD 0

Ce-144 0.29

< LLD

< LLD 0

Bottom and GS 6

Shoreline Be-7 0.35

< LLD

< LLD 0

Sediments (pCi/g dry)

K-40 0.10 8.10 (4/4)

P-26, Lock & Dam No. 3 9.24 (2/2) 9.18 (2/2) 0 (6.87-9.35) 1.6 mi @ 1290/SE (9.13-9.35)

(9.00-9.36)

Mn-54 0.017

< LLD

< LLD 0

Co-58 0.021

< LLD

< LLD 0

Co-60 0.016

< LLD

< LLD 0

Zn-65 0.047

< LLD

< LLD 0

Zr-Nb-95 0.036

< LLD

< LLD 0

Ru-103 0.032

< LLD

< LLD 0

Ru-106 0.11

< LLD

< LLD 0

Cs-134 0.012

< LLD

< LLD 0

Cs-137 0.017

< LLD

< LLD 0

Ba-La-140 0.24

< LLD

< LLD 0

Ce-141 0.08

< LLD

< LLD 0

Ce-144 0.11

< LLD

< LLD 0

GB = gross beta, GS = gamma scan.

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

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

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

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

23

6.0 REFERENCES

CITED Arnold, J. R. and H. A. AI-Salih. 1955. Beryllium-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 2014.

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

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

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

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

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

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

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

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

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

December, 1978 through 1982.

2012.

Quality Assurance Program Manual, Rev. 3, 14 November 2012.

2009.

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

2009.

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

Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, University of Chicago Press, Chicago, Illinois, 369-382.

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

Jh 0ATIe Environmental, Inc.

Midwest Laboratory 700 Landwehr Road - Northbrook. IL 60062-2310 phone (847) 564-0700

fax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE:

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

January, 2014 through December, 2014

Appendix A Interlaboratory Comparison Progqram 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 I 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

+/- lo =

169.85 x (known)°°933

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

>0.1 pCi/liter 15% of known value Plutonium

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

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

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

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

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

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

b Laboratory limit.

A2

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result b Result c Limits Acceptance ERW-1384 4/7/2014 Sr-89 40.29 +/- 5.76 36.70 27.50 +/- 43.60 Pass ERW-1 384 4/7/2014 Sr-90 24.08 +/- 2.35 26.50 19.20 +/- 30.90 Pass ERW-1385 4/7/2014 Ba-1 33 78.23 +/- 3.93 87.90 74.00 +/- 96.70 Pass ERW-1385 4/7/2014 Co-60 62.75 +/- 3.53 64.20 57.80 +/- 73.10 Pass ERW-1385 4/7/2014 Cs-134 44.97 +/- 3.99 44.30 35.50 +/- 48.70 Pass ERW-1385 4/7/2014 Cs-137 88.54 +/- 4.93 89.10 80.20 +/- 101.00 Pass ERW-1385 4/7/2014 Zn-65 249.1 +/- 10.4 235.0 212.0 - 275.0 Pass ERW-1388 4/7/2014 Gr. Alpha 56.70 +/- 2.47 61.00 31.90 +/- 75.80 Pass ERW-1388 4/7/2014 Gr. Beta 32.10 +/- 1.20 33.00 21.40 +/- 40.70 Pass ERW-1391 4/7/2014 1-131 25.52 +/- 1.12 25.70 21.30 +/- 30.30 Pass ERW-1394 4/7/2014 Ra-226 12.30 +/- 0.61 12.40 9.26 +/- 14.30 Pass ERW-1 394 4/7/2014 Ra-228 5.08 +/- 1.16 4.26 2.46 +/- 5.86 Pass ERW-1394 4/7/2014 Uranium 10.76 +/- 0.74 10.20 7.95 +/- 11.80 Pass ERW-1397 4/7/2014 H-3 8982 +/- 279 8770 7610 - 9650 Pass ERW-5382 10/6/2014 Sr-89 29.40 +/- 5.32 31.40 22.80 +/- 38.10 Pass ERW-5382 10/6/2014 Sr-90 19.19 +/- 1.85 21.80 15.60 +/- 25.70 Pass ERW-5385 10/6/2014 Ba-133 43.54 +/- 4.54 49.10 40.30 +/- 54.50 Pass ERW-5385 10/6/2014 Cs-134 81.95 +/- 7.49 89.80 73.70 +/- 98.80 Pass ERW-5385 10/6/2014 Cs-137 95.76 +/- 5.50 98.80 88.90 +/- 111.00 Pass ERW-5385 10/6/2014 Co-60 90.25 +/- 2.77 92.10 82.90 +/- 104.00 Pass ERW-5385 10/6/2014 Zn-65 327.4 +/- 23.3 310.0 279.0 - 362.0 Pass ERW-5388 10/6/2014 Gr. Alpha 30.88 +/- 8.05 37.60 19.40 +/- 46.10 Pass ERW-5388 10/6/2014 G. Beta 20.47 +/- 4.75 27.40 17.30 +/- 35.30 Pass ERW-5392 10/6/2014 1-131 19.58 +/- 2.35 20.30 16.80 +/- 24.40 Pass ERW-5394 10/6/2014 Ra-226 15.10 +/- 1.81 14.70 11.00 +/- 16.90 Pass ERW-5394 10/6/2014 Ra-228 4.42 +/- 0.86 4.31 2.50 +/- 5.92 Pass ERW-5394 10/6/2014 Uranium 5.51 +/- 0.37 5.80 4.34 +/- 6.96 Pass ERW-5397 10/6/2014 H-3 6876 +/- 383 6880 5940 - 7570 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.

A1-1

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

mR Lab Code Date Known Lab Result Control Description Value

+/- 2 sigma Limits Acceptance Environmental, Inc.

2014-1 2014-1 2014-1 2014-1 2014-1 2014-1 2014-1 2014-1 2014-1 2014-1 2014-1 2014-1 2014-1 5/15/2014 5/15/2014 5/15/2014 5/15/2014 5/15/2014 5/15/2014 5/15/2014 5/15/2014 5/15/2014 5/15/2014 5/15/2014 5/15/2014 5/15/2014 50 cm.

60 cm.

70 cm.

75 cm.

80 cm.

90 cm.

100 cm.

110 cm.

120 cm.

135 cm.

150 cm.

165 cm.

180 cm.

26.83 18.63 13.69 11.93 10.48 8.28 6.71 5.54 4.66 3.68 2.98 2.46 2.07 34.43 +/- 3.76 22.20 +/- 1.16 14.74 +/- 0.80 12.68 +/- 1.05 11.81 +/- 0.91 7.72 +/- 0.71 6.46 +/- 0.71 5.25 +/- 1.03 4.76 +/- 0.48 2.87 +/- 0.46 2.30 +/- 0.15 2.09 +/- 0.28 1.75 +/- 0.21 18.78 - 34.88 13.04 - 24.22 9.58 -17.80 8.35 -15.51 7.34 -13.62 5.80 - 10.76 4.70 - 8.72 3.88 - 7.20 3.26 - 6.06 2.58 -4.78 2.09 - 3.87 1.72 -3.20 1.45 -2.69 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Environmental, Inc.

2014-2 2014-2 2014-2 2014-2 2014-2 2014-2 2014-2 2014-2 2014-2 2014-2 2014-2 2014-2 2014-2 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 12/9/2014 30 cm.

30 cm.

60 cm.

120 cm.

150 cm.

180 cm.

77.04 77.04 19.26 19.26 4.82 4.82 3.08 3.08 3.08 2.14 2.14 2.14 2.14 84.03 +/- 8.47 83.74 +/- 12.02 20.39 +/- 2.37 20.33 +/- 1.19 5.15 +/- 0.20 5.20 +/- 0.45 3.84 +/- 0.61 3.17 +/- 0.38 3.31 +/- 0.32 2.27 +/- 0.51 2.23 +/- 0.12 2.74 +/- 0.48 1.97 +/- 0.41 53.90 - 100.20 53.90 - 100.20 13.50 -25.00 13.50 -25.00 3.40 - 6.30 3.40 -6.30 2.20 - 4.00 2.20 -4.00 2.00 - 4.00 1.50 -2.80 1.50 -2.80 1.50 -2.80 1.50 -2.80 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A2-1

TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limits d Acceptance SPW-1011 SPAP-1 03 SPAP-1 05 SPAP-1 05 SPW-1 07 SPW-129 SPW-129 SPW-129 SPW-1 30 SPW-1 33 SPMI-135 SPMI-135 W-12014 W-12014 SPW-297 SPW-657 SPW-1127 SPW-1917 SPW-1786 SPW-2168 SPW-2168 SPW-2168 SPW-2168 SPMI-2170 SPMI-2170 SPMI-2170 SPMI-2170 SPW-2792 SPW-2796 WW-2836 WW-2836 WW-2836 1/13/2014 1/13/2014 1/13/2014 1/13/2014 1/13/2014 1/15/2014 1/15/2014 1/15/2014 1/15/2014 1/15/2014 1/15/2014 1/15/2014 1/20/2014 1/20/2014 1/29/2014 2/25/2014 3/26/2014 3/28/2014 4/25/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 6/18/2014 6/18/2014 6/30/2014 6/30/2014 6/30/2014 Ra-228 Gr. Beta Cs-1 34 Cs-1 37 H-3 Cs-1 34 Cs-1 37 Sr-90 Ni-63 C-14 Cs-1 34 Cs-1 37 Gr. Alpha Gr. Beta Tc-99 Ra-226 U-238 Pu-238 Tc-99 Cs-134 Cs-1 37 Sr-89 Sr-90 Cs-1 34 Cs-1 37 Sr-89 Sr-90 U-238 C-14 Co-60 Cs-1 37 H-3 35.47 +/- 2.55 43.91 +/- 0.34 2.46 +/- 0.67 102.4 +/-2.7 62,380 +/- 707 69.90 +/- 3.71 84.36 +/- 7.06 39.48 +/- 1.52 255.8 +/- 3.8 3153 +/- 15 76.80 +/- 4.04 80.44 +/- 6.63 19.69 +/- 0.41 30.35 +/- 0.33 104.2 +/- 1.7 15.84 +/- 0.45 43.28 +/- 2.56 27.37 +/- 2.13 531.1 +/- 8.7 70.90 +/- 5.81 79.72 +/- 6.49 83.35 +/- 5.05 33.37 +/- 1.52 64.15 +/- 4.93 76.21 +/- 6.91 65.82 +/- 4.89 40.90 +/- 1.59 44.80 +/- 1.54 3495 +/- 9 131.8 +/-6.9 143.8 +/- 9.1 6220 +/- 238 30.85 44.82 2.82 99.9 62,246 78.00 75.77 39.20 204.0 4737 78.00 75.80 20.00 30.90 107.8 16.70 41.72 23.80 539.15 69.50 75.17 72.85 38.87 69.50 75.17 72.85 38.87 41.70 4,737 140.90 145.60 6,361 21.60 - 40.11 26.89 - 62.75 1.69 - 3.95 89.9 -109.9 49,797 - 74,695 68.00 - 88.00 65.77 - 85.77 31.36 -47.04 142.8 -265.2 2842 -6632 68.00 - 88.00 65.80 - 85.80 10.00 - 30.00 20.90 - 40.90 75.5 - 140.2 11.69 -21.71 29.20 - 54.24 14.28 - 33.32 377.41 - 700.90 59.50 - 79.50 65.17 -85.17 58.28 - 87.42 31.10 -46.64 59.50 - 79.50 65.17 -85.17 58.28 - 87.42 31.10 -46.64 29.19 -54.21 2,842 - 6632 126.81 - 154.99 131.04 -160.16 5,089 - 7633 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A3-1

TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=l c Activity Limits d Acceptance SPW-3486 SPW-080714 SPW-080714 SPW-081214 SPW-4093 SPW-4093 SPW-4093 SPMI-4095 SPMI-4095 SPW-4104 SPW-4106 SPW-4108 SPW-4108 SPAP-41 10 SPF-4112 SPF-4112 SPF-4112 SPW-081414 W081614 W082614 SPW-090414 SPW-090414 SPW-5124 W100714 W100714 W111014 W111014 W112514 W120814 W120814 SPW-7149 7/17/2014 8/7/2014 8/7/2014 8/12/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/14/2014 8/16/2014 8/26/2014 9/4/2014 9/4/2014 9/29/2014 10/7/2014 10/7/2014 11/10/2014 11/10/2014 11/25/2014 12/8/2014 12/8/2014 12/26/2014 Fe-55 Gr. Alpha Gr. Beta Pu-238 1-131(G)

Sr-90 Sr-89 1-131(G) 1-131 Ni-63 H-3 Cs-1 34 Cs-137 Gr. Beta 1-131 Cs-134 Cs-1 37 H-3 Ra-226 Ra-228 Gr. Alpha Gr. Beta Ra-228 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Ra-226 Gr. Alpha Gr. Beta Ni-63 2211 +/-72 18.42 +/- 0.40 31.70 +/- 0.40 22.59 +/- 2.15 59.95 +/-6.17 39.46 +/- 1.55 105.5 +/-4.9 59.92 +/- 6.17 60.05 +/- 0.72 200.1 +/- 3.4 59,597 +/- 695 2.45 +/- 0.81 90.20 +/- 3.74 43.65 +/- 0.11 2.64 +/- 0.38 0.91 +/- 0.03 2.61 +/- 0.06 14,663 +/- 788 14.30 +/- 0.37 27.18 +/- 2.13 17.85 +/- 0.39 30.03 +/- 0.33 32.93 +/- 2.38 18.56 +/- 0.40 27.71 +/- 0.32 17.84 +/- 0.38 30.12 +/- 0.33 16.63 +/- 0.41 19.29 +/- 0.41 27.93 +/- 0.32 217.53 +/- 3.25 2319 20.10 32.40 22.70 59.62 38.65 115.0 59.62 59.62 203.2 60,261 2.32 98.56 44.19 2.86 1.03 2.39 17,700 16.70 30.49 20.10 30.90 31.94 20.10 30.90 20.10 30.90 16.70 20.10 30.90 203.10 1855 -2783 10.05 -30.15 22.40 - 42.40 18.16 - 27.24 49.62 - 69.62 28.65 - 48.65 92.0 - 149.5 49.62 - 69.62 47.70 -71.54 142.2 - 264.1 48209 -72313 0.00 -12.32 88.56 -108.56 34.19 - 54.19 0.00 -12.86 0.00 -11.03 0.00 - 12.39 14160 -21240 11.69 - 21.71 20.49 - 40.49 10.05 -30.15 20.90 - 40.90 21.94 - 41.94 10.05 -30.15 20.90 - 40.90 10.05 -30.15 20.90 - 40.90 11.69 -21.71 10.05 -30.15 20.90 -40.90 142.17 -264.03 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass a Liquid sample results are reported in pCi/Liter, air filters( pCi/m3), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

b Laboratory codes : W (Water), MI (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).

c Results are based on single determinations.

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 (4.66a)

Acceptance Type LLD Activityc Criteria (4.66 a)

SPW-1001 SPAP-102 SPAP-104 SPAP-104 SPW-1 06 SPW-128 SPW-128 SPW-128 SPW-1 30 SPW-1 33 SPMI-134 SPMI-134 W-12014 W-12014 SPW-297 SPW-656 SPW-1126 SPW-1 127 SPW-1127 SPW-1917 SPW-1785 SPW-1831 SPW-2167 SPW-2167 SPW-2167 SPW-2167 SPW-2167 SPMI-2169 SPMI-2169 SPMI-2169 SPMI-2169 SPMI-2169 SPW-2793 Water Air Particulate Air Particulate Air Particulate Water Water Water Water Water Water Milk Milk Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Milk Milk Milk Milk Milk Water 1/13/2014 1/13/2014 1/13/2014 1/13/2014 1/13/2014 1/15/2014 1/15/2014 1/15/2014 1/15/2014 1/15/2014 1/15/2014 1/15/2014 1/20/2014 1/20/2014 1/29/2014 2/25/2014 3/26/2014 3/26/2014 3/26/2014 3/28/2014 4/25/2014 4/30/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 6/18/2014 Ra-228 Gr. Beta Cs-1 34 Cs-1 37 H-3 Cs-134 Cs-137 Sr-90 Ni-63 C-14 Cs-134 Cs-137 Gr. Alpha Gr. Beta Tc-99 Ra-226 U-238 U-233/234 U-238 Pu-238 Tc-99 1-131 Cs-1 34 Cs-1 37 1-131(G)

Sr-89 Sr-90 Cs-1 34 Cs-1 37 1-131(G)

Sr-89 Sr-90 U-238 0.74 0.003 0.006 0.004 151.0 2.85 2.52 0.61 10.85 13.51 4.43 1.92 0.48 0.78 5.63 0.03 0.13 0.13 0.00 0.02 5.61 0.21 2.29 2.46 2.77 0.81 0.52 4.45 3.91 4.31 0.98 0.61 0.08 0.39 +/- 0.39 0.015 +/- 0.003 0.005 +/- 0.005

-0.002 +/- 0.005 115.0 +/- 97.0 0.59 +/- 1.46 0.68 +/- 1.64 0.74 +/- 0.36 1.57 +/- 6.60 3.10 +/- 8.27 0.14 +/- 2.46

-2.07 +/- 2.48

-0.31 +/- 0.31

-0.24 +/- 0.54

-4.42 +/- 3.34 0.01 +/- 0.02 0.08 +/- 0.12 0.11 +/- 0.13 0.08 +/- 0.12 0.01 +/- 0.01

-4.33 +/- 3.33 0.07 +/- 0.12

-0.79 +/- 1.35 0.36 +/- 1.48 0.25 +/- 1.53 0.01 +/- 0.62 0.03 +/- 0.24

-0.55 +/- 2.39

-0.52 +/- 2.60 2.57 +/- 2.21

-0.02 +/- 0.83 0.35 +/- 0.32 0.02 +/- 0.06 2

0.01 0.05 0.05 200 10 10 1

20 210 10 10 2

4 10 1

1 1

10 0.5 10 10 20 5

1 10 10 20 5

1 1

A4-1

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

Acceptance Type LLD Activityc Criteria (4.66 c)

SPW-3485 SPW-4092 SPW-4092 SPW-4092 SPW-4092 SPW-4092 SPMI-4094 SPMI-4094 SPMI-4094 SPMI-4094 SPMI-4094 SPMI-4094 SPW-4103 SPW-4105 SPW-4107 SPW-4107 SPW-4107 SPAP-4109 SPF-4111 SPF-4111 SPF-4111 W-081614 W-082614 W-092314 W-5123 W-100714 W-100714 W-1 11014 W-111014 W-112514 W-120814 W-120814 SPW-7148 Water Water Water Water Water Water Milk Milk Milk Milk Milk Milk Water Water Water Water Water Air Particulate Fish Fish Fish Water Water Water Water Water Water Water Water Water Water Water Water 7/17/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/13/2014 8/16/2014 8/16/2014 9/23/2014 9/29/2014 10/7/2014 10/7/2014 11/10/2014 11/10/2014 11/25/2014 12/8/2014 12/8/2014 12/26/2014 Fe-55 1-131(G)

Cs-1 34 Cs-1 37 Sr-89 Sr-90 1-131 1-131(G)

Cs-1 34 Cs-137 Sr-89 Sr-90 Ni-63 H-3 1-131(G)

Cs-134 Cs-137 Gr. Beta Cs-134 Cs-1 37 Co-60 Ra-226 Ra-228 Ra-226 Ra-228 Gr. Alpha Gr. Beta Gr. Alpha Gr. Beta Ra-226 Gr. Alpha Gr. Beta Ni-63 597.6 3.59 3.71 2.71 0.89 0.52 0.35 4.50 4.30 3.45 0.80 0.47 0.12 138.1 3.21 2.72 2.56 0.004 0.01 0.01 0.01 0.04 0.62 0.02 0.70 0.39 0.76 0.39 0.75 0.05 0.42 0.74 10.80 10.3 +/- 363.3 0.91 +/- 1.95

-0.31 +/- 1.77

-2.20 +/- 1.98 0.11 +/- 0.63

-0.05 +/- 0.23 0.03 +/- 0.20

-0.41 +/- 2.44

-0.84 +/- 2.02 0.96 +/- 2.51

-0.19 +/- 0.79 0.71 +/- 0.30 0.02 +/- 0.07 104.1 +/- 78.1

-3.68 +/- 1.33

-0.62 +/- 1.49 0.75 +/- 1.62

-0.003 +/- 0.00 0.00 +/- 0.01

-0.01 +/- 0.01 0.00 +/- 0.01 0.05 +/- 0.03 0.29 +/- 0.40 0.04 +/- 0.02 0.43 +/- 0.38 0.04 +/- 0.28

-0.06 +/- 0.53 0.01 +/- 0.28

-0.25 +/- 0.52 0.02 +/- 0.03 0.04 +/- 0.30

-0.42 +/- 0.51

-1.80 +/- 6.50 1000 20 10 10 5

1 0.5 20 10 10 5

1 20 200 20 10 10 0.01 100 100 100 1

2 1

2 2

4 2

2 4

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

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

0 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 AP-7829, 7830 AP-7913, 7914 AP-7871, 7872 S-43, 44 SG-64, 65 SG-64, 65 SG-64, 65 S-136, 137 S-136, 137 WW-220, 221 WW-262, 263 WW-346, 347 SWU-367, 368 F-409, 410 F-409, 410 AP-7829, 7830 AP-7913, 7914 AP-7871, 7872 S-43, 44 SG-64, 65 SG-64, 65 SG-64, 65 S-136, 137 S-136, 137 WW-220, 221 WW-262,263 WW-346, 347 SWU-367, 368 F-409, 410 F-409, 410 WW-491, 492 WW-575, 576 W-617, 618 SWU-743, 744 S-700,701 S-806, 807 SG-928, 929 SG-928, 929 SG-928, 929 SG-928, 929 SG-928, 929 SG-928, 929 SG-928, 929 1/2/2014 1/2/2014 1/3/2014 119/2014 1/9/2014 1/9/2014 1/9/2014 1/13/2014 1/13/2014 1/13/2014 1/21/2014 1/24/2014 1/29/2014 2/2/2014 2/2/2014 1/2/2014 1/2/2014 1/3/2014 1/9/2014 1/9/2014 1/9/2014 1/9/2014 1/13/2014 1/13/2014 1/13/2014 1/21/2014 1/24/2014 1/29/2014 2/2/2014 2/2/2014 2/6/2014 2/13/2014 2/14/2014 2/25/2014 2/26/2014 3/4/2014 3/11/2014 3/11/2014 3/11/2014 3/11/2014 3/11/2014 3/11/2014 3/11/2014 Be-7 Be-7 Be-7 K-40 Gr. Alpha Ra-226 Ra-228 Be-7 K-40 H-3 H-3 H-3 Gr. Beta Cs-137 Gr. Beta Be-7 Be-7 Be-7 K-40 Gr. Alpha Ra-226 Ra-228 Be-7 K-40 H-3 H-3 H-3 Gr. Beta Cs-137 Gr. Beta H-3 H-3 H-3 Gr. Beta K-40 K-40 Ac-228 Bi-214 K-40 Pb-212 Pb-214 Th-228 TI-208 0.08 +/- 0.02 0.07 +/- 0.01 0.05 +/- 0.02 19.28 +/- 0.57 686.08 +/- 69.97 97.30 +/- 9.78 91.90 +/- 9.30 14.90 +/- 0.39 3.29 +/- 0.36 231.85 +/- 80.45 294.80 +/- 89.80 934.97 +/- 118.47 0.74 +/- 0.38 0.05 +/- 0.02 3.60 +/- 0.07 0.08 +/- 0.02 0.07 +/- 0.01 0.05 +/- 0.02 19.28 +/- 0.57 686.08 +/- 69.97 97.30 +/- 9.78 91.90 +/- 9.30.

14.90 +/- 0.39 3.29 +/- 0.36 231.85 +/- 80.45 294.80 +/- 89.80 934.97 +/- 118.47 0.74 +/- 0.38 0.05 +/- 0.02 3.60 +/- 0.07 474.00 +/- 101.10 196.69 +/- 82.94 526.29 +/- 97.65 1.61 +/- 0.65 21.32 +/- 0.64 24.79 +/- 0.57 6.78 +/- 0.34 5.32 +/- 0.20 4.79 +/- 0.80 2.70 +/- 0.09 5.39 +/- 0.17 6.10 +/- 2.07 0.92 +/- 0.06 0.06 +/- 0.01 0.06 +/- 0.01 0.06 +/- 0.01 19.24 +/- 0.57 642.46 +/- 65.59 92.20 +/- 9.27 97.10 +/- 9.87 14.88 +/- 0.38 3.93 +/- 0.36 273.46 +/- 82.47 265.00 +/- 88.47 965.59 +/- 119.52 1.31 +/- 0.42 0.05 +/- 0.02 3.72 +/- 0.07 0.06 +/- 0.01 0.06 +/- 0.01 0.06 +/- 0.01 19.24 +/- 0.57 642.46 +/- 65.59 92.20 +/- 9.27 97.10 +/- 9.87 14.88 +/- 0.38 3.93 +/- 0.36 273.46 +/- 82.47 265.00 +/- 88.47 965.59 +/- 119.52 1.31 +/- 0.42 0.05 +/- 0.02 3.72 +/- 0.07 583.10 +/- 105.30 154.68 +/- 80.89 579.51 +/- 99.77 1.73 +/- 0.71 21.15 +/- 0.59 24.17 +/- 0.59 6.94 +/- 0.35 5.34 +/- 0.22 6.24 +/- 1.01 2.75 +/- 0.09 5.53 +/- 0.17 4.76 +/- 1.93 0.91 +/- 0.06 0.07 +/- 0.01 0.06 +/- 0.01 0.06 +/- 0.01 19.26 +/- 0.40 664.27 +/- 47.95 94.75 +/- 6.74 94.50 +/- 6.78 14.89 +/- 0.27 3.61 +/- 0.25 252.66 +/- 57.60 279.90 +/- 63.03 950.28 +/- 84.14 1.02 +/- 0.28 0.05 +/- 0.01 3.66 +/- 0.05 0.07 +/- 0.01 0.06 +/- 0.01 0.06 +/- 0.01 19.26 +/- 0.40 664.27 +/- 47.95 94.75 +/- 6.74 94.50 +/- 6.78 14.89 +/- 0.27 3.61 +/- 0.25 252.66 +/- 57.60 279.90 +/- 63.03 950.28 +/- 84.14 1.02 +/- 0.28 0.05 +/- 0.01 3.66 +/- 0.05 528.55 +/- 72.99 175.69 +/- 57.93 552.90 +/- 69.80 1.67 +/- 0.48 21.24 +/- 0.44 24.48 +/- 0.41 6.86 +/- 0.24 5.33 +/- 0.15 5.52 +/- 0.64 2.73 +/- 0.06 5.46 +/- 0.12 5.43 +/- 1.42 0.92 +/- 0.04 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance S-2119, 2120 S-2119, 2120 S-2119, 2120 S-2119, 2120 F-1594, 1595 SO-1115, 1116 SO-1115, 1116 SO-1115, 1116 SO-1115, 1116 SO-1115, 1116 S-1033, 1034 S-1033, 1034 S-1033, 1034 S-1033, 1034 S-1033, 1034 S-1033, 1034 W-1094,1095 W-1094,1095 AP-1197, 1198 AP-1698,1699 E-1218, 1219 E-1218, 1219 SWU-1260,1261 AP-1615, 1616 AP-1657,1658 AP-1804,1805 P-1489, 1490 BS-1531, 1532 S-1909, 1910 SWU-1867,1868 AP-1930,1931 SL-1888, 1889 SL-1888, 1889 SL-1888, 1889 SL-1888, 1889 SO-1972, 1973 SO-1972, 1973 SO-1972, 1973 SO-1972, 1973 W-617,618 AP-2077, 2078 3/12/2014 3/12/2014 3/12/2014 3/12/2014 3/16/2014 3/18/2014 3/18/2014 3/18/2014 3/18/2014 3/18/2014 3/19/2014 3/19/2014 3/19/2014 3/19/2014 3/19/2014 3/19/2014 3/23/2014 3/23/2014 3/27/2014 3/31/2014 4/1/2014 4/1/2014 4/1/2014 4/1/2014 4/2/2014 4/3/2014 4/7/2014 4/16/2014 4/22/2014 4/29/2014 5/1/2014 5/1/2014 5/1/2014 5/1/2014 5/1/2014 5/1/2014 5/1/2014 5/1/2014 5/1/2014 5/8/2014 5/8/2014 Ac-228 Cs-1 37 K-40 Pb-214 Cs-1 37 Cs-1 37 Gr. Beta K-40 U-233/4 U-238 Ac-228 Bi-214 Cs-1 37 K-40 Pb-214 TI-208 Ra-226 Ra-228 Be-7 Be-7 Gr. Beta K-40 Gr. Beta Be-7 Be-7 Be-7 H-3 K-40 K-40 Gr. Beta Be-7 Be-7 Cs-137 Gr. Beta K-40 Cs-137 Gr. Alpha Gr. Beta K-40 H-3 Be-7 0.76 +/- 0.20 0.13 +/- 0.05 17.48 +/- 1.48 0.73 +/- 0.18 0.02 +/- 0.01 0.06 +/- 0.01 23.30 +/- 2.10 12.63 +/- 0.18 0.11 +/- 0.02 0.13 +/- 0.02 0.99 +/- 0.20 1.02 +/- 0.18 0.15 +/- 0.04 15.39 +/- 1.19 1.09 +/- 0.13 0.36 +/- 0.05 0.30 +/- 0.20 1.10 +/- 0.79 0.17 +/- 0.08 0.06 +/- 0.02 1.57 +/- 0.04 1.26 +/- 0.14 2.81 +/- 0.51 0.07 +/- 0.01 0.07 +/- 0.01 0.05 +/- 0.02 582.31 +/- 101.85 0.51 +/- 0.19 14.71 +/- 0.54 2.28 +/- 0.40 0.16 +/- 0.09 0.80 +/- 0.04 0.01 +/- 0.00 11.57 +/- 0.72 1.04 +/- 0.05 0.12 +/- 0.03 7.51 +/- 3.24 29.89 +/- 3.25 20.45 +/- 0.85 175.13 +/- 83.82 0.23 +/- 0.11 0.73 +/- 0.21 0.11 +/- 0.05 18.39 +/- 1.53 0.63 +/- 0.12 0.03 +/- 0.02 0.06 +/- 0.00 24.40 +/- 2.20 12.84 +/- 0.15 0.12 +/- 0.02 0.14 +/- 0.02 1.13 +/- 0.26 0.98 +/- 0.16 0.14 +/- 0.04 15.13 +/- 1.19 0.88 +/- 0.17 0.31 +/- 0.05 0.70 +/- 0.20 1.13 +/- 0.86 0.14 +/- 0.08 0.07 +/- 0.02 1.57 +/- 0.04 1.31 +/- 0.18 2.94 +/- 0.50 0.07 +/- 0.02 0.08 +/- 0.01 0.06 +/- 0.01 505.07 +/- 98.72 0.58 +/- 0.23 14.78 +/- 0.53 1.67 +/- 0.35 0.19 +/- 0.11 0.76 +/- 0.08 0.01 +/- 0.00 12.67 +/- 0.78 1.00 +/- 0.09 0.10 +/- 0.02 9.09 +/- 3.63 31.42 +/- 3.04 20.88 +/- 0.76 177.17 +/- 83.92 0.18 +/- 0.11 0.75 +/- 0.15 0.12 +/- 0.04 17.94 +/- 1.06 0.68 +/- 0.11 0.03 +/- 0.01 0.06 +/- 0.00 23.85 +/- 1.52 12.74 +/- 0.12 0.12 +/- 0.01 0.14 +/- 0.01 1.06 +/- 0.16 1.00 +/- 0.12 0.15 +/- 0.03 15.26 +/- 0.84 0.99 +/- 0.11 0.34 +/- 0.04 0.50 +/- 0.14 1.12 +/- 0.58 0.15 +/- 0.05 0.07 +/- 0.01 1.57 +/- 0.03 1.29 +/- 0.11 2.88 +/- 0.36 0.07 +/- 0.01 0.07 +/- 0.01 0.06 +/- 0.01 543.69 +/- 70.92 0.54 +/- 0.15 14.75 +/- 0.38 1.98 +/- 0.27 0.17 +/- 0.07 0.78 +/- 0.05 0.01 +/- 0.00 12.12 +/- 0.53 1.02 +/- 0.05 0.11 +/- 0.02 8.30 +/- 2.43 30.66 +/- 2.23 20.66 +/- 0.57 176.15 +/- 59.31 0.20 +/- 0.08 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance S-2205, 2206 S-2205, 2206 VE-2184, 2185 VE-2184, 2185 DW-50102, 50103 DW-50102, 50103 SW-2226, 2227 DW-50087, 50088 DW-50090, 50091 DW-50090, 50091 DW-50098, 50099 AP-2289, 2290 PM-3174, 3175 G-2415,2416 G-2415,2416 G-2415,2416 WW-2541, 2542 SW-2817, 2818 SS-2943, 2944 S-3048, 3049 SWT-3216, 3217 AP-3699,3700 S-3300, 3301 S-3300,3301 S-3300, 3301 VE-3237,3238 CF-3384,3385 S-3447,3448 WW-3573,3574 VE-3594,3595 WM-3762,3763 SWT-3867, 3868 S-3804,3805 S-3804, 3805 LW-3931, 3932 5/15/2014 5/15/2014 5/19/2014 5/19/2014 5/20/2014 5/20/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/21/2014 5/22/2014 5/28/2014 6/2/2014 6/2/2014 6/2/2014 6/4/2014 6/16/2014 6/24/2014 6/27/2014 7/1/2014 7/3/2014 7/8/2014 7/8/2014 7/8/2014 7/8/2014 7/14/2014 7/16/2014 7/18/2014 7/22/2014 7/25/2014 7/29/2014 7/30/2014 7/30/2014 7/31/2014 Be-7 K-40 Be-7 K-40 Ra-226 Ra-228 H-3 Gr. Alpha Ra-226 Ra-228 Gr. Alpha Be-7 K-40 Be-7 Gr. Beta K-40 H-3 H-3 K-40 K-40 Gr. Beta Be-7 K-40 Ac-228 Ra-226 K-40 K-40 K-40 H-3 K-40 H-3 Gr. Beta Ac-228 Pb-214 Gr. Beta 0.50 +/- 0.19 33.60 +/- 0.79 0.62 +/- 0.18 5.30 +/- 0.44 7.07 +/- 0.76 5.44 +/- 0.85 14318.00 +/- 347.00 1.76 +/- 1.09 0.61 +/- 0.09 0.97 +/- 0.41 13.04 +/- 1.36 0.14 +/- 0.08 30.68 +/- 1.30 0.73 +/- 0.16 5.89 +/- 0.09 5.30 +/- 0.49 5107.00 +/- 223.00 13303.00 +/- 336.00 11.49 +/- 0.79 42.51 +/- 1.31 2.27 +/- 0.94 0.06 +/- 0.01 4.85 +/- 0.97 10.23 +/- 0.43 70.14 +/- 2.37 2.54 +/- 0.27 11.10 +/- 0.58 19.63 +/- 0.64 381.58 +/- 85.76 3.04 +/- 0.19 315.47 +/- 87.02 1.10 +/- 0.53 0.67 +/- 0.11 0.56 +/- 0.05 1.04 +/- 0.40 0.70 +/- 0.18 33.52 +/- 0.70 0.53 +/- 0.17 5.14 +/- 0.44 8.31 +/- 0.90 6.02 +/- 0.67 14350.00 +/- 347.00 2.67 +/- 1.01 0.47 +/- 0.09 1.26 +/- 0.52 10.76 +/- 1.26 0.24 +/- 0.10 32.64 +/- 1.24 0.62 +/- 0.28 5.90 +/- 0.09 5.19 +/- 0.65 5029.00 +/- 222.00 13130.00 +/- 334.00 11.81 +/- 0.70 40.04 +/- 1.39 2.53 +/- 1.05 0.07 +/- 0.02 5.91 +/- 1.17 10.18 +/- 0.32 72.01 +/- 2.38 2.63 +/- 0.24 10.69 +/- 0.60 21.03 +/- 0.96 401.30 +/- 86.67 3.21 +/- 0.15 327.30 +/- 87.56 1.51 +/- 0.58 0.61 +/- 0.10 0.51 +/- 0.04 0.95 +/- 0.41 0.60 +/- 0.13 33.56 +/- 0.53 0.58 +/- 0.12 5.22 +/- 0.31 7.69 +/- 0.59 5.73 +/- 0.54 14334.00 +/- 245.37 2.22 +/- 0.74 0.54 +/- 0.06 1.12 +/- 0.33 11.90 +/- 0.93 0.19 +/- 0.06 31.66 +/- 0.90 0.68 +/- 0.16 5.89 +/- 0.06 5.25 +/- 0.41 5068.00 +/- 157.33 13216.50 +/- 236.88 11.65 +/- 0.53 41.28 +/- 0.95 2.40 +/- 0.70 0.07 +/- 0.01 5.38 +/- 0.76 10.21 +/- 0.27 71.08 +/- 1.68 2.59 +/- 0.18 10.90 +/- 0.42 20.33 +/- 0.58 391.44 +/- 60.96 3.13 +/- 0.12 321.39 +/- 61.72 1.31 +/- 0.39 0.64 +/- 0.07 0.54 +/- 0.03 1.00 +/- 0.29 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance G-3952,3953 G-3952,3953 G-3952,3953 G-3952,3953 WW-4036, 4037 VE-4204,4205 WW-4394,4395 VE-4183,4184 AV-4455, 4456 AV-4455, 4456 WW-4500, 4501 AP-090214A/B SG-5089, 5090 SG-5089, 5090 SG-5194,5 SG-5194,5 SG-5194,5 S-5632,3 S-5632,3 S-5632,3 S-5632,3 S-5632,3 S-5632,3 S-5632,3 DW-50243,4 AP-101414A/B SG-5590,1 SG-5590,1 DW-50251,2 U-5842,3 CF-6074,5 CF-6074,5 8/4/2014 8/4/2014 8/4/2014 8/4/2014 8/5/2014 8/11/2014 8/13/2014 8/14/2014 8/22/2014 8/22/2014 8/26/2014 9/2/2014 9/19/2014 9/19/2014 10/1/2014 10/1/2014 10/1/2014 10/8/2014 10/8/2014 10/8/2014 10/8/2014 10/8/2014 10/8/2014 10/8/2014 10/13/2014 10/14/2014 10/15/2014 10/15/2014 10/16/2014 10/20/2014 10/21/2014 10/21/2014 K-40 Be-7 Gr. Beta H-3 H-3 K-40 H-3 K-40 Be-7 K-40 H-3 Gr. Beta Ac-228 Bi-214 Gr. Alpha Pb-214 Ac-228 K-40 Cs-137 TI-208 Pb-212 Pb-214 Bi-212 Ac-228 Gr. Alpha Gr. Beta Pb-214 Ac-228 Ra-226 H-3 H-3 K-40 5.42 +/- 0.42 1.29 +/- 0.19 8.53 +/- 0.20 140.16 +/- 93.50 190.60 +/- 82.60 6.28 +/- 0.38 1540.26 +/- 136.52 5.70 +/- 0.41 286.67 +/- 102.30 2547.90 +/- 255.70 347.00 +/- 100.00 0.03 +/- 0.04 8.26 +/- 0.63 4.71 +/- 0.29 276.20 +/- 9.51 43.56 +/- 0.73 59.90 +/- 1.37 19.28 +/- 0.88 0.15 +/- 0.03 0.32 +/- 0.03 0.92 +/- 0.05 1.25 +/- 0.08 1.25 +/- 0.29 1.08 +/- 0.14 2.99 +/- 0.94 0.02 +/- 0.00 80.30 +/- 8.08 64.50 +/- 1.87 0.55 +/- 0.13 7376 +/- 949 7509 +/- 283 3.09 +/- 0.31 5.35 +/- 0.34 1.24 +/- 0.16 8.63 +/- 0.20 127.25 +/- 92.99 164.70 +/- 81.30 6.60 +/- 0.37 1499.15 +/- 135.43 5.73 +/- 0.34 251.99 +/- 98.94 2201.40 +/- 203.90 321.00 +/- 98.00 0.03 +/- 0.04 9.48 +/- 0.68 4.41 +/- 0.31 258.60 +/- 9.26 43.94 +/- 0.78 62.80 +/- 1.73 17.94 +/- 0.89 0.13 +/- 0.03 0.34 +/- 0.03 0.92 +/- 0.05 1.09 +/- 0.09 1.34 +/- 0.47 1.10 +/- 0.14 4.98 +/- 1.17 0.02 +/- 0.00 73.40 +/- 7.51 62.80 +/- 1.15 0.32 +/- 0.10 7342 +/- 947 7969 +/- 291 3.30 +/- 0.38 5.38 +/- 0.27 1.27 +/- 0.13 8.58 +/- 0.14 133.70 +/- 65.94 177.65 +/- 57.95 6.44 +/- 0.27 1519.71 +/- 96.15 5.72 +/- 0.27 269.33 +/- 71.16 2374.65 +/- 163.52 334.00 +/- 70.01 0.03 +/- 0.00 8.87 +/- 0.46 4.56 +/- 0.21 267.40 +/- 6.64 43.75 +/- 0.53 61.35 +/- 1.10 18.61 +/- 0.63 0.14 +/- 0.02 0.33 +/- 0.02 0.92 +/- 0.03 1.17 +/- 0.06 1.29 +/- 0.27 1.09 +/- 0.10 3.99 +/- 0.75 0.02 +/- 0.00 76.85 +/- 5.52 63.65 +/- 1.10 0.44 +/- 0.08 7359 +/- 670 7739 +/-203 3.20 +/- 0.25 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-4

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-6269,70 VE-6269,70 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 SO-6500,1 DW-50262,3 DW-50264,5 DW-50264,5 AP-120214A/B AP-120814A/B SG-7068,9 SG-7068,9 S-7152,3 11/3/2014 11/3/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/5/2014 11/10/2014 11/10/2014 11/10/2014 12/2/2014 12/8/2014 12/19/2014 12/19/2014 12/25/2014 K-40 Be-7 Sr-90 Gr. Alpha Gr. Beta U-233/4 U-238 Th-228 Th-230 Th-232 Bi-214 Pb-214 Ac-228 Cs-137 Gr. Alpha Ra-226 Ra-228 Gr. Beta Gr. Beta Pb-214 Ac-228 K-40 6.25 +/- 0.54 0.81 +/- 0.28 0.07 +/- 0.03 11.77 +/- 1.73 26.69 +/- 1.62 0.14 +/- 0.04 0.18 +/- 0.05 0.47 +/- 0.11 0.38 +/- 0.07 0.41 +/- 0.08 0.75 +/- 0.02 0.78 +/- 0.08 1.02 +/- 0.11 0.40 +/- 0.01 8.95 +/- 1.26 3.89 +/- 0.24 2.96 +/- 0.63 0.03 +/- 0.00 0.03 +/- 0.01 4.27 +/- 0.23 2.72 +/- 0.36 20.83 +/- 0.88 6.56 +/- 0.49 0.74 +/- 0.18 0.07 +/- 0.02 12.18 +/- 1.62 24.19 +/- 1.13 0.14 +/- 0.05 0.13 +/- 0.04 0.34 +/- 0.06 0.29 +/- 0.05 0.41 +/- 0.06 0.78 +/- 0.02 0.86 +/- 0.09 1.13 +/- 0.13 0.39 +/- 0.01 7.84 +/- 1.24 3.71 +/- 0.20 2.33 +/- 0.59 0.03 +/- 0.00 0.03 +/- 0.01 4.38 +/- 0.33 3.27 +/- 0.49 20.16 +/- 0.62 6.41 +/- 0.36 0.77 +/- 0.17 0.07 +/- 0.02 11.98 +/- 1.19 25.44 +/- 0.99 0.14 +/- 0.03 0.15 +/- 0.03 0.41 +/- 0.06 0.34 +/- 0.04 0.41 +/- 0.05 0.77 +/- 0.01 0.82 +/- 0.06 1.08 +/- 0.09 0.39 +/- 0.01 8.40 +/- 0.88 3.80 +/- 0.16 2.65 +/- 0.43 0.03 +/- 0.00 0.03 +/- 0.00 4.33 +/- 0.20 3.00 +/- 0.30 20.49 +/- 0.54 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass A5-5

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

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAW-1 140 2/1/2014 Gr. Alpha MAW-1 140 2/1/2014 Gr. Beta MAW-1142 2/1/2014 1-129 MAW-1 184 MAW-1184 MAW-1 184 MAW-1184 f MAW-1 184 f MAW-i 184 MAW-1 184 MAW-1 184 MAW-1 184 MAW-1184 MAW-1 184 MAW-1184 MAW-1 184 MAW-1 184 MAW-i 184 MAW-1 184 MAVE-1 148 MAVE-1 148 MAVE-1 148 MAVE-1 148 MAVE-1 148 MAVE-1 148 MAAP-1 151 MAAP-1151 d MAAP-1151 MAAP-1 151 MAAP-1 151 MAAP-1151 MAAP-1151 f MAAP-1 151 MAAP-1 151 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 Fe-55 H-3 Ni-63 Pu-238 Pu-239/240 Sr-90 Tc-99 U-233/234 U-238 Co-57 Co-60 Cs-1 34 Cs-137 K-40 Mn-54 Zn-65 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Zn-65 Am-241 Co-57 Co-60 Cs-134 Cs-137 Mn-54 Pu-238 Pu-239/240 Zn-65 0.77 +/- 0.06 4.31 +/- 0.08

-0.01 +/- 8.00 0.40 +/- 3.20 345.10 +/- 10.60 32.40 +/- 3.20 1.28 +/- 0.12 0.91 +/- 0.10 7.00 +/- 0.70 8.10 +/- 0.60 0.20 +/- 0.07 1.25 +/- 0.18 27.86 +/- 0.38 15.99 +/- 0.27 21.85 +/- 0.54 28.74 +/- 0.49 1.80 +/- 2.00 14.06 +/- 0.40 0.00 +/- 0.19 11.63 +/-0.19 7.28 +/- 0.18 6.29 +/- 0.29 5.18 +/- 0.20 9.22 +/- 0.26 8.59 +/- 0.40 0.09 +/- 0.02 1.60 +/- 0.05 1.38 +/- 0.08 1.75 +/- 0.11 1.81 +/- 0.10 0.01 +/- 0.03 0.08 +/- 0.02 0.10 +/- 0.02

-0.24 +/- 0.09 0.85 4.19 0.00 NA 0.26 -1.44 2.10 -6.29 0.00 321.00 34.00 0.83 0.68 8.51 10.30 0.23 1.45 27.50 16.00 23.10 28.90 0.00 13.90 0.00 10.10 6.93 6.04 4.74 8.62 7.86 0.09 0.00 1.39 1.91 1.76 0.00 0.00 0.08 0.00

-0.01 -2.00 225.00 - 417.00 23.80 - 44.20 0.58 - 1.08 0.47 - 0.88 5.96 -11.06 7.20 - 13.40 0.16 -0.29 1.02 -1.89 19.30 - 35.80 11.20 - 20.80 16.20 - 30.00 20.20 - 37.60 0.00 - 10.00 9.70 -18.10

-0.01 - 0.00 7.10 - 13.10 4.85 - 9.01 4.23 - 7.85 3.32 -6.16 6.03 -11.21 5.50 - 10.22 0.06 -0.12 NA 0.97 -1.81 1.34 -2.48 1.23 - 2.29 NA NA 0.05 -0.10

-0.50 - 1.00 Pass Pass Pass Pass Pass Pass Fail Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Fail Pass Pass A6-1

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

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAAP-1 151 MAAP-1 151 MAAP-1 151 MAAP-1154 MAAP-1 154 MASO-1 146 MASO-1 146 MASO-1 146 g MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1 146 MASO-1146' MASO-1146 f MASO-1146 MASO-1 146 MASO-1146h MASO-1146 h MASO-4439 MASO-4439 MASO-4439 MASO-4439 MASO-4439 MASO-4439 MASO-4439 MASO-4439 MASO-4439 MASO-4439 MAW-4431 MAW-4431 MAW-4431 MAW-4431 MAW-4431 MAW-4431 MAW-4431 MAW-4431 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 2/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 8/1/2014 U-233/234 U-238 Sr-90 Gr. Alpha Gr. Beta Co-57 Co-60 Cs-134 Cs-137 K-40 Mn-54 Zn-65 Am-241 Ni-63 Pu-238 Pu-239/240 Sr-90 Tc-99 U-233/234 U-238 Am-241 Ni-63 Pu-239/240 Sr-90 Tc-99 Cs-134 Co-57 Co-60 Mn-54 Zn-65 Am-241 Cs-137 Co-57 Co-60 H-3 Fe-55 Mn-54 Zn-65 0.03 +/- 0.01 0.13 +/- 0.02 1.11 +/- 0.14 0.56 +/- 0.06 0.98 +/- 0.06 0.02 0.13 1.18 1.77 0.77 0.01 - 0.03 0.09 -0.17 0.83 -1.53 0.53 - 3.01 0.39 -1.16 1064.50 +/- 3.60 1.70 +/- 0.50 6.10 +/- 1.80 1364.30 +/- 5.30 728.90 +/- 15.90 1588.00 +/- 6.00 763.50 +/- 6.80 68.20 +/- 9.00 4.80 +/- 15.30 140.60 +/- 15.50 102.00 +/- 13.10 1.23 +/- 1.37

-0.30 +/- 12.00 22.90 +/- 3.00 32.00 +/- 3.60 65.90 +/- 6.70 771.62 +/- 23.29 55.63 +/- 5.81 778.34 +/- 17.82 458.20 +/- 9.20 520.60 +/- 7.09 1135.00 +/- 7.40 768.20 +/- 7.70 1050.70 +/- 12.60 407.89 +/- 15.03 0.79 +/- 0.08 18.62 +/- 0.54 24.85 +/- 0.42 12.27 +/- 0.38 207.20 +/- 10.60 55.10 +/- 14.80 14.36 +/- 0.53 11.46 +/- 0.78 966.00 1.22 0.00 1238.00 622.00 1430.00 695.00 68.00 0.00 96.00 76.80 0.00 0.00 81.00 83.00 85.50 980.00 58.60 858.00 589.00 622.00 1116.00 779.00 1009.00 541.00 0.88 18.40 24.70 12.40 208.00 31.50 14.00 10.90 676.00 - 1256.00 NA NA 867.00 - 1609.00 435.00 - 809.00 1001.00 - 1859.00 487.00 - 904.00 47.60 - 88.40 NA 67.00 - 125.00 53.80 - 99.80 NA NA 57.00 -105.00 58.00 - 108.00 59.90 - 111.20 686.00 - 1274.00 41.00 - 76.20 601.00 - 1115.00 412.00 - 766.00 435.00 - 809.00 781.00 - 1451.00 545.00 - 1013.00 706.00 - 1312.00 379.00 - 703.00 0.62 -1.14 12.90 -23.90 17.30 -32.10 8.70 -16.10 146.00 - 270.00 22.10 -41.00 9.80 -18.20 7.60 - 14.20 Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass Pass Pass Fail Fail Pass Pass Fail Fail Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass 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-4431 8/1/2014 Tc-99 6.10 +/- 0.50 6.99 4.89 -9.09 Pass MAW-4431 8/1/2014 Pu-238 0.59 +/- 0.07 0.62 0.43 - 0.80 Pass MAW-4431 8/1/2014 U-233/234 0.22 +/- 0.04 0.21 0.14 - 0.27 Pass MAW-4431 8/1/2014 U-238 1.25 +/- 0.10 1.42 0.99 -1.85 Pass MAW-4493 8/1/2014 Gr. Alpha 0.93 +/- 0.07 1.40 0.42 -2.38 Pass MAW-4493 8/1/2014 Gr. Beta 6.31 +/- 1.35 6.50 3.25 -9.75 Pass MAAP-4433 8/1/2014 Am-241 0.06 +/- 0.02 0.07 0.05 - 0.09 Pass MAAP-4433 8/1/2014 Pu-238 0.10 +/- 0.03 0.11 0.08 -0.14 Pass MAAP-4433 8/1/2014 Pu-239/240 0.04 +/- 0.02 0.05 0.03 - 0.06 Pass MAAP-4433 8/1/2014 Sr-90 0.74 +/- 0.10 0.70 0.49 - 0.91 Pass MAAP-4433 8/1/2014 U-233/234 0.03 +/- 0.01 0.04 0.03 - 0.05 Pass MAAP-4433 8/1/2014 U-238 0.21 +/- 0.03 0.25 0.18 -0.33 Pass MAAP-4444 8/1/2014 Sr-89 7.82 +/- 0.52 9.40 6.60 -12.20 Pass MAAP-4444 8/1/2014 Sr-90 0.76 +/- 0.10 0.76 0.53 - 0.99 Pass MAVE-4436 8/1/2014 Cs-134 7.49 +/- 0.18 7.38 5.17 -9.59 Pass MAVE-4436 8/1/2014 Co-57 11.20 +/- 0.19 9.20 6.40 -12.00 Pass MAVE-4436 8/1/2014 Co-60 6.84 +/- 0.17 6.11 4.28 -7.94 Pass MAVE-4436 8/1/2014 Mn-54 8.11 +/- 0.26 7.11 4.97 - 9.23 Pass MAVE-4436 8/1/2014 Zn-65 7.76 +/- 0.43 6.42 4.49 - 8.35 Pass a Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

t Laboratory codes as follows: MAW (water), MAAP (air filter), MASO (soil), MAVE (vegetation).

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

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

f The high bias on the plutonium crosscheck samples was traced to contamination from a newly purchased standard.

The results of reanalysis with replacement tracer purchased from NIST:

MAW-1184 Pu-238 0.68 +/- 0.10 Bq / L MAW-1184 Pu-239/240 0.66 +/- 0.10 Bq / L MASO-1146 Pu-238 95.15 +/- 8.98 Bq / kg MASO-1146 Pu-239/240 67.21 +/- 7.54 Bq / kg Insufficient sample remained to reanalyze the Air filter sample(MAAP-1 151). High bias results due to same contaminated tracer g False positive test. Long sample counting time lead to interference from naturaling occuring Bi-214 in sample matrix with a close spectral energy.

h 80% of participating laboratories were outside the acceptable range.

Parallel reanalysis was run on ERA spiked sample with acceptable results.

'Result of reanalysis Fe-55 32.63 +/- 16.30 Bq / L A6-3

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

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERAP-1044 ERSO-1050 ERSO-1050 ERSO-1050 ERSO-1 050 ERSO-1 050 ERSO-1 050 ERSO-1 050 ERSO-1050 ERSO-1050 ERSO-1050 ERSO-1050 ERSO-1 050 e ERSO-1 050 e ERSO-1 050 ERSO-1050 ERSO-1050 ERSO-1050 ERSO-1 050 ERSO-1 050 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 Am-241 Co-60 Cs-134 Cs-137 Fe-55 Gr. Alpha Gr. Beta Mn-54 Pu-238 Pu-239/240 Sr-90 U-233/234 U-238 Uranium Zn-65 Am-241 Ac-228 Bi-212 Bi-214 Co-60 Cs-1 34 Cs-1 37 K-40 Mn-54 Pb-212 Pb-214 Pu-238 Pu-239/240 Sr-90 Th-234 U-233/234 U-238 Uranium Zn-65 54.2 +/- 3.0 1177.9 +/- 14.3 1010.5 +/- 15.8 938.3 +/- 45.7 142.3 +/- 87.3 52.3 +/- 0.5 64.4 +/- 2.6

<4.9 63.0 +/- 2.6 52.8 +/- 1.9 81.4 +/- 1.6 30.4 +/- 1.7 30.4 +/- 1.4 62.0 +/- 3.5 852.2 +/- 26.1 426.6 +/- 155.5 1260.0 +/- 107.0 1331.9 +/- 309.7 1804.5 +/- 50.4 6738.8 +/- 167.6 3262.9 +/- 108.8 8538.6 +/- 55.0 11241.3 +/- 296.6

< 21.6 1119.6 +/- 26.1 1861.7 +/- 54.9 1085.5 +/- 167.7 681.6 +/- 128.6 2338.0 +/- 144.0 3474.9 +/- 226.0 3319.5 +/- 250.2 3375.6 +/- 252.6 6810.6 +/- 551.1 5968.0 +/- 226.1 59.7 1120.0 1010.0 828.0 240.0 46.0 53.8 0.0 56.3 48.6 78.9 36.4 36.1 74.3 667.0 399.0 1240.0 1240.0 1960.0 6830.0 3390.0 8490.0 10500.0 0.0 1240.0 2070.0 578.0 471.0 2780.0 3360.0 2780.0 3360.0 6910.0 5400.0 36.8 - 80.8 867.0 - 1400.0 643.0 -1250.0 622.0 -1090.0 74.4 - 469.0 15.4 -71.4 34.0 - 78.4 NA 38.6 - 74.0 35.2 - 63.5 38.6 -118.0 22.6 - 54.9 23.3 -49.9 41.1 -113.0 478.0 -921.0 233.0 - 518.0 795.0 - 1720.0 330.0 - 1820.0 1180.0 -2820.0 4620.0 - 9400.0 2220.0 - 4070.0 6510.0 - 10900.0 7660.0 - 14100.0 NA 812.0 - 1730.0 1210.0 -3090.0 348.0 - 797.0 308.0 -651.0 1060.0 -4390.0 1060.0 -6320.0 1060.0 -4390.0 2080.0 - 4260.0 3750.0 -9120.0 4300.0 -7180.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Fail Pass Pass Pass Pass Pass Pass A7-1

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

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERVE-1051 ERW-1054 ERW-1054 ERW-1054 E RW-1054 E RW-1054 ERW-1054 ERW-1054 ERW-1054 E RW-1054 ERW-1054 ERW-1054 ERW-1055 f ERW-1055 ERW-1055 ERW-1055 ERW-1 060 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 3/17/2014 Am-241 Cm-244 Co-60 Cs-1 34 Cs-1 37 K-40 Mn-54 Pu-238 Pu-239/240 Sr-90 U-233/234 U-238 Uranium Zn-65 Am-241 Co-60 Cs-1 34 Cs-137 Mn-54 Pu-238 Pu-239/240 U-233/234 U-238 Uranium Zn-65 Fe-55 Gr. Alpha Gr. Beta Sr-90 H-3 1532.0 +/- 149.5 519.8 +/- 94.6 981.2 +/- 41.8 701.4 +/- 58.6 961.9 +/- 46.3 32789.7 +/- 758.2

< 25.9 2724.1 +/- 259.4 4361.4 +/- 323.4 2405.7 +/- 263.2 1612.2 +/- 162.0 1574.3 +/- 159.6 3255.4 +/- 356.7 1124.1 +/- 101.2 104.6 +/- 3.4 1195.2 +/- 18.9 1474.9 +/- 47.5 2591.0 +/- 23.4

<4.3 54.1 +/-3.6 185.9 +/- 17.6 74.8 +/- 6.3 76.4 +/- 7.8 154.3 +/- 14.6 1818.5 +/- 56.4 636.3 +/- 176.0 120.9 +/- 3.5 141.6 +/- 2.3 873.9 +/- 56.9 5818.0 +/- 230.0 1490.0 516.0 926.0 646.0 880.0 31900.0 0.0 2110.0 3740.0 2580.0 1760.0 1750.0 3580.0 919.0 114.0 1270.0 1660.0 2690.0 0.0 44.1 160.0 82.4 81.8 168.0 1800.0 1200.0 133.0 174.0 890.0 5580.0 911.0 - 1980.0 253.0 - 804.0 639.0 - 1290.0 415.0 - 839.0 638.0 - 1220.0 23000.0 - 44800.0 NA 1260.0 -2890.0 2300.0 -5150.0 1470.0 -3420.0 1160.0 -2260.0 1170.0 -2220.0 2430.0 -4460.0 663.0 - 1290.0 76.8 - 153.0 1100.0 -1490.0 1220.0 - 1910.0 2280.0 - 3220.0 NA 32.6 - 54.9 124.0 - 202.0 61.9 -106.0 62.4 - 100.0 123.0 -217.0 1500.0 -2270.0 716.0 - 1630.0 47.2 -206.0 99.6 -258.0 580.0 - 1180.0 3740.0 - 7960.0 Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Fail Pass Pass Pass Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

b Laboratory codes as follows: 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.

The high bias on the plutonium crosscheck samples was traced to contamination from a newly purchased standard.

The results of reanalysis with replacement tracer purchased from NIST:

ERSO-1050 Pu-238 634.7 +/- 98.50 Bq / kg ERSO-1050 Pu-239/240 451.8 +/- 82.80 Bq / kg f An error in the efficiency calculation was found. The result of recalculation was 932 pCi/L.

The sample was repeated, result of reanalysis, 1066 pCi/L.

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

In cases where the activity is less than the lower limit of detection L, it is reported as: < L, where L = the lower limit of detection based on 4.66G 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 +/-s1 and x 2 -+/-S2 Reported result:

x +/- s; where x = (1/2) (x1 + x2) and s = (1/2)

+S2 3.2.

Individual results:

< Li,

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

Individual results:

x +/- s, < L Reported result:

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

4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average and standard deviation "s" of a set of n numbers x1, x2...

xn are defined as follows:

= Ix n-nn-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-i.

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 beta 1

Strontium-90 500 b

-1 lodine-131 2.8 x 10 Cesium-137 1,000 Barium-140 8,000 Iodine-131 1,000 C

Potassium-40 4,000 Gross alpha 2

Gross beta 10 6

Tritium 1 x 10 a

b C

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

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

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

A natural radionuclide.

C-1

APPENDIX D Sample Collection and Analysis Program D-1

TLD LOCATIONS ONE MILE RADIUS PLANT AREA ENLARGEO PLAN

[1.00 MILE RADIUS]

(NO SCALE]

MONITORING LEGEND:

(0) PRAIRIE ISLAND TLD POINTS D-2

TLD LOCA~TIONS 2.7 Mi.

o!-I 01C CONTROL POINTS PRESCOTT, WISCONSIN ISFSI AREA TLO LOCATIONS MONITORING LEGEND:

(D PRAIRIE ISLAND TLO POINTS D-3

TLO LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:

0 PRAIRIE ISLAND TLD POINTS D-4

ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS PLANT AREA ENLARGED PLAN

[i.00 MILE RADIUS]

[NO SCALE3 MONITORING LEGEND SMILK SAMPLING POINT IO NUMBERS P-18.P-37,P-43 A

AIR SAMPLING POINT 10 NUMBERS

.P-I.:P-2. P-3i P-4. P-6, P-7

~

WATER SAMPLING. POINT 10 NUMBERS P-5,P-6. P-B. P-9, P-l1. P-24. P-43 VEGETATION / VEGETABLES ID NUMBERS P-28. P-36. P-45 FISH SAMPLING POINT ID NUMBERS P-13, P-I1 INVERTEBRATES POINT ]D NUMBERS P-6. P-40 SEDIMENT SAMPLING POINT 10 NUMBERS P-6, P-i2, P-2B D-5

ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS MONITORING LEGEND

(*

MILK SAMPLING POINT 10 NUMBERS P-18, P-37, P-42. P-43 A

AIR SAMPLING POINT ID NUMBERS P-I. P-2, P-3, P-4. P-G..P-7 O

WATER SAMPLING POINT ID NUMBERS P-5, P-G. P-B, P-q, P-I, P-24, P-43 VEGETATION /

VEGETABLES 10 NUMBERS P-28. P-38. P-45 FISH SAMPLING POINT ID NUMBERS

P-13. P-19 INVERTEBRATES POINT I

NUMBERS P-6. P-40 SEDIMENT SAMPLING POINT I1 NUMBERS P-6, P-12, P-20 D-6

ENVIRONMENTAL SAMPLING POINTS

(

) P.43, Peterson Farm, W10322 St Rd 29, River Falls, WI O 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 ID NUMBERS P-1, P-2, P-3, P-4, P-6,P-7 O

WATER SAMPLING POINT ID NUMBERS P-6, P-6, P-8, P-9, P-11, P-43 9

VEGETATION / VEGETABLES ID NUMBERS P-28, P-38, P-46 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, 2014. 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 2014 are summarized and discussed.

Program findings for 2014 detected low levels of tritium in nearby residence wells, ground water, surface samples, and storage tanks at or near the expected natural background levels with the exception of ground water sample well MW-8, January area snow samples S-6 and S-9, and the December septic sample. The 2014 sample results (except for MW-8, S-6, S-9, and the septic system) ranged from <19 pCi/L to 324 pCi/L. Sample well MW-8 ranged from 60 pCi/L to 388 pCi/L. Snow sample S-6 was 465 pCi/L, snow sample S-9 was 595 pCi/L. The December septic system sample was 764 pCi/L. All tritium results are far below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L and present no harm to any members of the public.

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

E-2

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

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

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

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

3.3 Pro-gram Execution The special water sampling was executed as described in the preceding section.

3.4 Program Modifications Changes to the program in 2014 include:

samples were taken from monitoring wells P-10, MW-7, and MW-8 and snow from S-6, S-7, S-8, S-9, and P-43 and were sent to Environmental Incorporated for analysis for hard-to-detect nuclides in accordance with American Nuclear Insurers recommendation sample location P-8 was renamed P-8 Post-treat to differentiate it from a new sample location named P-8 Pre-treat (the pre-treat sample is taken prior to any water treatment, the post-treat sample is taken after treatment using chlorine, fluoride and hydrous manganese oxide in a greensand pressure filter) sample location PIIC-29 was added to provide a control location for the PI Indian Community samples sample locations PIIC-02, PIIC-03, PIIC-19, PIIC-20, PIIC-21, PIIC-23, PIIC-24, and PIIC-27 were eliminated because they were determined to be duplicate samples of the PI Indian Community community water system that is sampled at location P8 Pre-treat and P8 Post-treat 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 2014 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 2014 may be due to prior leakage from the PINGP liquid radwaste discharge pipe, discharge of turbine building sump water into the landlocked area, or discharge of heating steam condensate from the main warehouse in 1978/1979. The liquid radwaste discharge pipe was replaced in 1992 and the discharge to the landlocked area has been terminated, the last discharge took place on 11/14/09. The main warehouse heating system was repaired in 1979. The heating steam system was not used in the outer plant buildings during the 2014-2015 heating season.

The elevated tritium levels in January snow samples S-6 and S-9 are likely due to recapture of tritium vented from the plant that is entrained in precipitation. This phenomenon has been noted at other nuclear plants (see J.T. Harris, et al, "Tritium Recapture Behavior at a Nuclear Power Reactor Due to Airborne Releases, Health Physics Journal, August 2008, Volume 95, number 2.).

The elevated tritium level in the December septic system sample is still under investigation. Septic system samples in March and April of 2015 have also shown elevated tritium levels.

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, 2014.

Medium No.

Location codes Collection type Analysis and type a and frequency b type c P-8 post-treat, P-8 pre-treat, REMP P-6, PIIC-22, PIIC-26, Well water PIIC-28, PIIC-29, P-7, Annual 23 P-1 1, PZ-1, PZ-2, PZ-4, PZ-5, PZ-7, G/A H-3 MW-6, P-26, P-30, SW-3, SW-4, SW-5, SW-6, SW-7, P-9 Well water 1

P-24D G/Q H-3 quarterly Well water P-2, P-3, P-5, P-6, G/Q' H-3 quarterly' PZ-8, MW-4, MW-5 Well water monthly 5

P-43(C), SW-1(C),

G/M H-3 MW-7, MW-8, P-10 Surface water S-1, S-2, S-3, S-4, S-5, 8

S-6, S-7, P-31 G/Ad H-3 Storage Tank 5

11 CST, 21 CST, 22 CST, G/S H-3 TU1/2 Demin Hdr Storage Tank 1

Septic System G/M H-3 Snow 5

S-6, S-7, S-8, S-9, P-43(C)

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

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

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

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

E-5

Table E-4.2. Sampling locations for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2014.

Code Collection site Type of Distance and sample a direction from reactor P-8 PI Community well post treat WW 1.0 mi. @ 321°iWNW P-8 P1 Community well pre treat WW 1.0 mi. @ 321°/WNW REMP P-6 Lock & Dam #3 well WW 1.6 mi. @ 129°/SE PIIC-22 1773 Buffalo Slough Rd WW 1 mi. @ 315°/NW PIIC-26 1771 Buffalo Slough Rd WW 1 mi. @ 315°/NW PIIC-28 1960 Larson Lane WW 1.5 mi @ 288iWNW PIIC-29 Buffalo Project WW 4.3 mi @ 302°/WNW P-24D Suter residence WW 0.6 mi. @ 158°/SSE P-43 Peterson Farm (Control)

WW 13.9 mi. @ 3551/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-1 0 Sample well WW See map P-11 Sample well WW See map PZ-1 Sample well WW See map PZ-2 Sample well WW See map PZ-4 Sample well WW See map PZ-5 Sample well WW See map PZ-7 Sample well WW See map PZ-8 Sample well WW See map MW-4 Sample well WW See map MW-5 Sample well WW See map MW-6 Sample well WW See map MW-7 Sample well WW See map MW-8 Sample well WW See map P-26 PITC well WW 0.4 mi. @ 258°/WSW P-30 Environ lab well WW 0.2 mi. @ 32°/NNE E-6

Table E-4.2. Sampling locations for special well, storage tank, and surface water samples, Prairie Island Nuclear Generating Plant, 2014 (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. @ 0IN SW-6 Restroom Trailer well WW 0.2 mi @ 310"/NW SW-7 Distribution Center WW 0.35 mi @ 2717/W P-9 Plant well # 2 WW 0.3 mi. @ 306'/NW S-1 Upstream Miss. River SW See map S-2 Recirc/Intake canal SW See map S-3 Cooling water canal SW See map S-4 Discharge Canal (end)

SW See map S-5 Mid Discharge Canal SW See map S-6 Roof Stormwater Runoff (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 0.69 mi. @ 172°/S 11 CST Storage Tank ST Turbine Building 21 CST Storage Tank ST Turbine Building 22 CST Storage Tank ST Turbine Building Unit 1/2 demin hdr Storage Tank ST Turbine 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 Location of Facility Goodhue, Minnesota Docket No.

Reporting Period 50-282, 50-306 January - December, 2014 (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 C Range c Range C Non-(Units)

Analyses a Routine Results e Offsite Well H-3 13 19 33 (5/13)

PIIC-22 43 (1/1)

(See Control 0

Water (28-43)

(43)

Below)

(pCi/L)

Onsite H-3 74 19 114 (59/74)

MW-8 267 (12/12)

(See Control Well Water (23-388)

(60-388)

Below)

(pCi/L)

Onsite H-3 17 19 133 (12/17)

S-9 595 (1/1)

(See Control Surface Water (23-595)

(595)

Below) 2 (pCi/L)

HSt e

H-3 19 19 137 (17/19) 189 (11/12)

(See Control Storage Tank (27-764)

(27-764)

Below) 1 (pCi/L)

Control (offsite H-3 25 19 none P-43 35(4/13) 34(5/25) well water)

(23-50)

(23-50) 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).

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, 2014.

SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L OFFSITE WELLS P-8 Post-treat PI Comm. Well

<19

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

<19 REMP P-6 Lock & Dam #3 well 28 PIIC-22 1773 Buffalo Slough Rd 43 PIIC-26 1771 Buffalo Slough Rd 38 PIIC-28 1960 Larson Lane

<19 PIIC-29 Buffalo Project

<19 P-24D Suter residence 28

<19 28

<19

<19 31/23Y

<19

<19 50 37

<19

<19 P-43 Peterson Farm(Control 'snow SW-i Hanson Farm (Control)

<19

<19 28

<19

<19 E-9

Table E-4.4 Radiological Environmental Monitoring Program Complete Data Table, 2014 (continued).

SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L ONSITE WELLS P-2 Sample well 73 92 40 P-3 Sample well

<19 23 34 P-5 Sample well 89 110 117 P-6 Sample well

<19

<19 P-7 Sample well 40 P-10 Sample well 138 79 60 60 54 110 160 97 102 118 172 207 P-11 Sample well 56 PZ-1 Sample well

<19 PZ-2 Sample well 39 PZ-4 Sample well 46 PZ-5 Sample well 60 PZ-7 Sample well 61 PZ-8 Sample well

<19 49

<19 MW-4 Sample well 32 24 31 MW-5 Sample well

<19 81 158 MW-6 Sample well 226

<19 MW-7 Sample well 26 69 62 43 40 27 43 118 53 60 25

<19 MW-8 Sample well 388 60 346 257 299 347 274 90 285 277 269 316 P-26 PITC well

<19 P-30 Env. lab well

<19 SW-3 CT pump 43 P-9 Plant well # 2

<19 SW-4 New Admin 26 SW-5 Pint Scrnhs 34 SW-6 Restroom Trailer

<19 SW-7 Dist Center

<19 E-1 0

Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2014 (continued).

SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L ONSITE SURFACE WATER 29 S-1 Mississippi River upstream S-2 Recirculation/Intake canal 41 S-3 Cooling water canal

<19 S-4 Discharge Canal (end) 33 S-5 Discharge Canal (midway) 23 S-6 Stormwater runoff 465*

57

<19 26 S-7 Parking Lot runoff 227*

<19

<19 32 S-8 P-10 area snow 46*

S-9 MW-7/8 area snow 595*

P-31 Birch Lake Seepage 23

<19

snow samples E-11

Table E-4.4 Radiological Environmental Monitoring Program, Complete Data Table, 2014 (continued).

SAMPLE DATES JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 2014 CODE SAMPLE LOCATIONS pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L ONSITE STORAGE TANKS 11 CST Storage tank 36 21 CST Storage tank 29 22 CST Storage tank 31 U1/U2 Demin Storage tank 33/77

<19/39 Header Septic Storage tank 91 63

<19 84 324 120 137 98 27 277 98 764 System E-12

Table E-4.5. Supplementary Data Tables.

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

Location Collection Date Lab Code P-10 Snow 01-13-14 PXW-275 Peterson Snow 01-15-14 PXW-276 MW-7/8 Snow 01-13-14 PXW-277 OAB Snow 01-13-14 PXW-278 Parking Lot Snow 01-15-14 PXW-279 Isotope Concentration (pCi/mL)

Fe-55 Ni-63 Sr-90 Pu-238 Pu-239/240 Am-241 Cm-242 Cm-243/244

< 7.4 E-07

< 1.1 E-08

< 4.5 E-10

< 1.8 E-10

< 7.2 E-1 1

< 9.2 E-1 1

< 5.3 E-11

< 7.6 E-07

< 1.2 E-08

< 4.5 E-10

< 1.4 E-10

< 7.8 E-11

< 8.8 E-11

< 1.5 E-10

< 7.3 E-07

< 1.1 E-08

< 5.2 E-10

< 7.3 E-11

< 8.6 E-1 1

< 5.0 E-11

< 7.4 E-07

< 1.2 E-08

< 5.5 E-10

< 1.2 E-10

< 1.7 E-10

< 9.6 E-11

< 7.4 E-07

< 1.2 E-08

< 5.5 E-10

< 1.7 E-10

< 6.7 E-11

< 1.5 E-10

< 5.0 E-11

< 8.7 E-11 The error given is the probable counting error at 95% confidence level. Less than (<), value background sample.

is based on a 4.66 sigma counting error for the E-1 3

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

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

Location P-10 MW-7 MW-8 Collection Date 05-15-14 05-15-14 06-09-14 Lab Code PXW-2194 PXW-2195 PXW-3551 Isotope Concentration (pCi/mL)

Fe-55

< 7.9 E-07

< 8.5 E-07

< 6.9 E-07 Ni-63

< 1.5 E-07

< 1.4 E-07 Sr-90

< 4.4 E-10

< 5.0 E-10

< 5.0 E-10 Pu-238

< 3.6 E-10

< 2.8 E-10

< 9.0 E-11 Pu-239/240

< 1.6 E-10

< 5.2 E-11 Am-241

< 1.1 E-10

< 1.4 E-10

< 1.1 E-10 Cm-242

< 1.1 E-10

< 1.4 E-10

< 1.6 E-10 Cm-243/244

< 1.1 E-10

< 1.0 E-10

< 2.2 E-10 The error given is the probable counting error at 95% confidence level. Less than (<), value is based on a 4.66 sigma counting error for the background sample.

E-14

+

Groundwater Monitoring Well Locations E-15

L-PI-15-039, ISFSI - 2014 Annual Radioloqical Environmental Monitoring Program (REMP) Report

Contents

Text

1.0 INTRODUCTION

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L-PI-15-039, ISFSI - 2014 Annual Radioloqical Environmental Monitoring Program (REMP) Report

Text

1.0 INTRODUCTION

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

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