NRC 2013-0038, Submittal of 2012 Annual Monitoring Report

Submittal of 2012 Annual Monitoring Report

ML13120A028
Person / Time
Site:	Point Beach
Issue date:	04/26/2013
From:	Millan M Point Beach
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
NRC 2013-0038
Download: ML13120A028 (152)

Text

NExTera ENERGY Q BEACH April 26, 2013 NRC 2013-0038 10 CFR 72.44 TS 5.6.2 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266, 50-301 and 72-005 Renewed License Nos. DPR-24 and DPR-27 2012 Annual Monitoring Report In accordance with Point Beach Nuclear Plant (PBNP) Technical Specification 5.6.2, enclosed is the Annual Monitoring Report for PBNP Units 1 and 2, for the period January 1 through December 31, 2012.

The Annual Monitoring Report contains information relating to the effluent impact upon the public, as well as information relating to plant releases, solid waste shipments, results from the radiological environmental monitoring program, and miscellaneous monitoring activities that occurred in 2012. The report also covers the results of radiological monitoring of the PBNP Independent Spent Fuel Storage Installation (ISFSI), as required by 10 CFR 72.44.

This letter contains no new regulatory commitments and no revisions to existing regulatory commitments.

Very truly yours, NextEra Energy Point Beach, LLC Michael Millan Licensing Manager Enclosures cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW American Nuclear Insurers WI Division of Public Health, Radiation Protection Section Office of Nuclear Material Safety and Safeguards, USNRC NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241

ENCLOSURE1 ANNUAL MONITORING REPORT 2012 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT DOCKETS 50-266 (UNIT 1), 50-301 (UNIT 2),72-005 (ISFSI)

January 1, 2012 through December 31, 2012

TABLE OF CONTENTS Summary 1 Part A: Effluent Monitoring 1.0 Introduction 4 2.0 Radioactive Liquid Releases 5 3.0 Radioactive Airborne Releases 11 4.0 Radioactive Solid Waste Shipments 17 5.0 Nonradioactive Chemical Releases 20 6.0 Circulating Water System Operation 21 Part B: Miscellaneous Reporting Requirements 7.0 Additional Reporting Requirements 22 Part C: Radiological Environmental Monitoring 8.0 Introduction 23 9.0 Program Description 24 10.0 Results 35 11.0 Discussion 40 12.0 REMP Conclusion 50 Part D: Groundwater Monitoring 13.0 Program Description 51 14.0 Results 54 15.0 Groundwater Summary 60 Appendix 1: Environmental, Inc. Midwest Laboratory, "Final Report for Point Beach Nuclear Plant" 11

LIST OF TABLES Table 2-1 Comparison of 2012 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives 5 Table 2-2 Summary of Circulating Water Discharge 7 Table 2-3 Isotopic Composition of Circulating Water Discharges (Curies) 8 Table 2-4 Subsoil System Drains - Tritium Summary 9 Table 3-1 Comparison of 2012 Airborne Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives 14 Table 3-2 Radioactive Airborne Effluent Release Summary 14 Table 3-3 Isotopic Composition of Airborne Releases 15 Table 3-4 Comparison of Airborne Effluent Doses 16 Table 4-1 Quantities and Types of Waste Shipped from PBNP in 2012 17 Table 4-2 2012 Estimated Solid Waste Major Radionuclide Composition 18 Table 4-3 2012 PBNP Radioactive Waste Shipments 19 Table 6-1 Circulating Water System Operation for 2012 21 Table 9-1 PBNP REMP Sample Analysis and Frequency 26 Table 9-2 PBNP REMP Sampling Locations 27 Table 9-3 ISFSI Sampling Sites 31 Table 9-4 Minimum Acceptable Sample Size 31 Table 9-5 Deviations from Scheduled Sampling and Frequency 32 Table 9-6 Sample Collection for State of Wisconsin 32 Table 10-1 Summary of Radiological Environmental Monitoring Results for 2012 37 Table 10-2 ISFSI Fence TLD Results for 2012 39 Table 11-1 Average Indicator TLD Results from 1993-2012 40 Table 11-2 Average ISFSI Fence TLD Results (mR/7days) 41 Table 11-3 Average TLD Results Surrounding the ISFSI (mR/7days) 42 Table 11-4 Average Gross Beta Measurements in Air 44 Table 14-1 Intermittent Streams and Bogs Tritium Concentration (pCi/I) 54 Table 14-2 2012 Beach Drain Average Tritium Concentration (pCi/I) 55 Table 14-3 2012 Unit 2 Facade SSD Sump Monthly Tritium Concentration (pCi/I) 56 Table 14-4 2012 East Yard Area Manhole Tritium Concentration (pCi/I) 56 Table 14-5 2012 Facade Well Water Tritium Concentration (pCi/I) 57 Table 14-6 2012 Potable Wells Tritium Concentration (pCi/I) 58 Table 14-7 2012 Quarterly Monitoring Well Water Tritium Concentration (pCi/I) 58 Table 14-8 2012 AC Condensate and Beach Drain Tritium Concentration (pCi/I) 59 Table 14-9 Tritium in Grass and Tree Transpired Water 59 LIST OF FIGURES Figure 9-1 PBNP REMP Sampling Sites 28 Figure 9-2 Map of REMP Sampling Sites Located Around PBNP 29 Figure 9-3 Enhanced Map Showing REMP Sampling Sites Closest to PBNP 30 Figure 11-1 ISFSI Area TLD Results (1995 - 2012) 42 Figure 11-2 Sr-90 Concentration in Milk 43 Figure 11-3 2012 Airborne Gross Beta 44 Figure 13-1 Groundwater Monitoring Locations 53 iii

SUMMARY

1 The Annual Monitoring Report for the period from January 1, 2012, through December 31, 2012, is submitted in accordance with Point Beach Nuclear Plant (PBNP) Units 1 and 2, Technical Specification 5.6.2 and filed under Dockets 50-266 and 50-301 for Facility Operating Licenses DPR-24 and DPR-27, respectively. It also contains results of monitoring in support of the Independent Spent Fuel Storage Installation (ISFSI), Docket 72-005. The report presents the results of effluent and environmental monitoring programs, solid waste shipments, non-radioactive chemical releases, and circulating water system operation.

During 2012, the following Curies (Ci) of radioactive material were released via the liquid and atmospheric pathways:

Liquid Atmospheric Tritium (Ci) 829 69.8

'Particulate (Ci) 0.0572 0.000087 Noble Gas (Ci) 0-) 0.887 C-14 2 0.0143 11.67

(-)Noble gases in the liquids are added to the atmospheric release totals.

2'Atmospheric particulate includes radioiodine (1-131 133).

Liquid is measured, atmospheric is calculated.

For the purpose of compliance with the effluent design objectives of 10 CFR 50, Appendix I, doses from effluents are calculated for the hypothetical maximally exposed individual (MEI) for each age group and compared to the Appendix I objectives. Doses less than or equal to the Appendix I values are considered to be evidence that PBNP releases are as low as reasonably achievable (ALARA). The maximum annual calculated doses in millirem (mrem) or milliard (mrad) are shown below and compared to the corresponding design objectives of 10 CFR 50, Appendix I.

LIQUID RELEASES Dose Category Calculated Dose Appendix I Dose Whole body dose 0.00684 mrem 6 mrem Organ dose 0.00793 mrem 20 mrem ATMOSPHERIC RELEASES Dose Category Calculated Dose Appendix I Dose Particulate organ dose 0.240 mrem 30 mrem Noble gas beta air dose 0.000100 mrad 40 mrad Noble gas gamma ray air dose 0.000236 mrad 20 mrad Noble gas dose to the skin 0.000335 mrem 30 mrem Noble gas dose to the whole body 0.000223 mrem 10 mrem 1

The results show that during 2012, the doses from PBNP effluents were a small percentage (50.80%) of the Appendix I design objectives. Therefore, operation of PBNP continues to be ALARA.

A survey of land use with respect to the location of dairy cattle was made pursuant to Section 2.5 of the PBNP Environmental Manual. As in previous years, no dairy cattle were found to be grazing at the site boundary. Therefore, the assumption that cattle graze at the site boundary used in the evaluation of doses from PBNP effluents remains conservative. Of the sixteen compass sectors around PBNP, six are over Lake Michigan. A land use census (LUC) of the remaining ten land containing sectors identified the closest garden, occupied dwelling and dairy in each sector. The LUC results confirm the assumption that the maximally exposed person lives at the south boundary. Therefore, the use of this assumption for the purpose of calculating effluent doses remains conservative.

The 2012 Radiological Environmental Monitoring Program (REMP) collected 788 individual samples for radiological analyses. Quarterly composites of weekly air particulate filters generated an additional 24 samples and quarterly composites of monthly lake water samples resulted in a further 16 samples. This yields a total of 828 samples. The ambient radiation measurements in the vicinity of PBNP and the ISFSI were conducted using 128 sets of thermoluminescent dosimeters (TLDs).

Air monitoring from six different sites did not reveal any effect from PBNP effluents.

Terrestrial monitoring consisting of soil, vegetation and milk found no influence from PBNP.

Similarly, samples from the aquatic environment, consisting of lake water, well water, fish, and algae revealed no buildup of PBNP radionuclides released in liquid effluents. Therefore, the data show no effect on the environs from PBNP.

Nine new dry storage units were added to the ISFSI in 2012. This brings the total number to 39 dry storage casks: 16 ventilated, vertical storage casks (VSC-24) and 23 NUHOMS, horizontally stacked storage modules. The subset of the PBNP REMP samples used to evaluate the environmental impact of the PBNP ISFSI showed no environmental impact from its operation.

The environmental monitoring conducted during 2012 confirmed that the effluent control program at PBNP ensured a minimal impact on the environment.

Two hundred twenty-three (223) samples were analyzed for tritium (H-3), a part of the groundwater protection program (GWPP). These samples came from drinking water wells, monitoring wells, yard drain outfalls, yard manholes, and surface water on site. Also included in this number were a sump and manholes associated with the subsurface drainage system (SSD) located under the plant foundation and four groundwater containment integrity monitoring wells located in the facades. The results show no substantial change in H-3 from previous years.

Low levels of H-3 continue to be detected under the plant foundation. No drinking water wells (depth >100 feet) have any detectable H-3. Tritium continues to be confined to the upper soil layer where the flow is toward the lake. Groundwater samples from wells in the vicinity of the remediated, former earthen retention pond continue to show low levels of H-3 whereas none was detectable in the wells monitoring the potential offsite tritium movement.

In addition to the normal groundwater sampling, eight biota related samples associated with the former retention pond were analyzed for H-3. Three of the four grass samples gave positive 2

indications for H-3 but the results could not be quantified because they were less than the associated MDC. Four samples of water transpired from trees at the retention pond area were collected. Although three positive results were obtained, only one was statistically significant, being slightly above its MDC.

The results of GWPP monitoring indicate no significant change from previous years.

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Part A EFFLUENT MONITORING

1.0 INTRODUCTION

The PBNP effluent monitoring program is designed to comply with federal regulations for ensuring the safe operation of PBNP with respect to releases of radioactive material to the environment and its subsequent impact on the public. Pursuant to 10 CFR 50.34a, operations should be conducted to keep the levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA). In 10 CFR 50, Appendix I, the Nuclear Regulatory Commission (NRC) provides the numerical values for what it considers to be the appropriate ALARA design objectives to which the licensee's calculated effluent doses may be compared. These doses are a small fraction of the dose limits specified by 10 CFR 20.1301 and lower than the Environmental Protection Agency (EPA) limits specified in 40 CFR 190.

10 CFR 20.1302 directs NextEra Energy Point Beach, LLC (NextEra) to make the appropriate surveys of radioactive materials in effluents released to unrestricted and controlled areas. Liquid wastes are monitored by inline radiation monitors as well as by isotopic analyses of samples of the waste stream prior to discharge from PBNP.

Airborne releases of radioactive wastes are monitored in a similar manner. Furthermore, for both liquid and atmospheric releases, the appropriate portions of the radwaste treatment systems are used as required to keep releases ALARA. Prior to release, results of isotopic analyses are used to adjust the release rate of discrete volumes of liquid and atmospheric wastes (from liquid waste holdup tanks and from gas decay tanks) such that the concentrations of radioactive material in the air and water beyond PBNP are below the PBNP Technical Specification concentration limits for liquid effluents and release rate limits for gaseous effluents.

Solid wastes are shipped offsite for disposal at NRC licensed facilities. The amount of radioactivity in the solid waste is determined prior to shipment in order to determine the proper shipping configuration as regulated by the Department of Transportation and the NRC.

10 CFR 72.210 grants a general license for an Independent Spent Fuel Storage Installation (ISFSI) to all nuclear power reactor sites operating under 10 CFR 50. The annual reporting requirement pursuant to 10 CFR 72.44(d)(3) is no longer applicable.

However, any release of radioactive materials from the operation of the ISFSI must also comply with the limits of Part 20 and Part 50 Appendix I design objectives. The dose criteria for effluents and direct radiation specified by 10 CFR 72.104 states that during normal operations and anticipated occurrences, the annual dose equivalent to any real individual beyond the controlled area must not exceed 25 mrem to the whole body, 75 mrem to the thyroid, and 25 mrem to any other organ. The dose from naturally occurring radon and its decay products are exempt. Because the loading of the storage casks occurs within the primary auxiliary building of PBNP, the doses from effluents due to the loading process will be assessed and quantified as part of the PBNP Radiological Effluent Control Program (RECM).

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2.0 RADIOACTIVE LIQUID RELEASES The radioactive liquid release path to the environment is via the circulating water discharge. A liquid waste treatment system in conjunction with administrative controls is used to minimize the impact on the environment and maintain doses to the public ALARA from the liquid releases.

2.1 Doses From Liquid Effluent Doses from liquid effluent are calculated using the methodology of the Offsite Dose Calculation Manual (ODCM). These calculated doses use parameters such as the amount of radioactive material released, the total volume of liquid, the total volume of dilution water, and usage factors (e.g., water and fish consumption, shoreline and swimming factors). These calculations produce a conservative estimation of the dose. For compliance with 10 CFR 50, Appendix I design objectives, the annual dose is calculated to the hypothetical maximally exposed individual (MEI). The MEI is assumed to reside at the site boundary in the highest X/Q sector and is maximized with respect to occupancy, food consumption, and other uses of this area. As such, the MEI represents an individual with reasonable deviations from the average for the general population in the vicinity of PBNP. A comparison of the calculated doses to the 10 CFR 50, Appendix I design objectives is presented in Table 2-1. The conservatively calculated dose to the MEI is a very small fraction of the Appendix I design objective.

Table 2-1 Comparison of 2012 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Annual Limit [mrem] Highest Total Calculated Dose  % of Design

[mrem] Objective 6 (whole body) 0.00684 0.114%

20 (any organ) 0.00793 0.040%

2.2 2012 Circulating Water Radionuclide Release Summary Radioactive liquid releases via the circulating water discharge are summarized by individual source and total curies released on a monthly basis and presented in Table 2-2. These releases are composed of processed waste, wastewater effluent, and blowdown from Units 1 and 2. The wastewater effluent consists of liquid from turbine hall sumps, plant well house backwashes, sewage treatment plant effluent, water treatment plant backwashes, the Unit 1 and 2 facade sumps, and the subsurface drainage system sump.

2.3 2012 Isotopic Composition of Circulatinq Water Discharges The isotopic composition of circulating water discharges during the current reporting period is presented in Table 2-3. The noble gases released in liquids are reported with the airborne releases in Section 3.

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The total isotopic curie distribution (gamma emitters plus hard-to-detects other that strontium) decreased by about 30% from 2011. The isotopes of Co, Ag, Sn, and Sb decreased whereas Cr-51, Fe-59, Ni-63, Zn-65, and Nb/Zr-95 increased.

As in 2011, there was no Sr-89/90 in liquids during 2012. H-3 was up about 60%

compared to 2011. The major H-3 increases occurred in July and September and are associated with the reactor trips. Tritium continues to be the major radionuclide released via liquid discharges.

2.4 Beach Drain System Releases Tritium Summary Beach drain is the term used to describe the point at which the site yard drainage system empties onto the beach of Lake Michigan. Six of these outfalls carry yard and roof drain runoff to the beach. A seventh outfall drains a small portion of the grassy area on top of the bluff overlooking the lake. Each of the drains is sampled monthly. The quarterly results of monitoring the beach drains are presented in Table 2-4. The total monthly flow is calculated assuming that the flow rate at the time of sampling persists for the whole month. During 2012, no tritium was observed in any of the beach drains at the effluent LLDs. The source of the previous H-3 in the beach drains has been determined to be recapture as described below. Therefore, if H-3 had been found in the beach drains, it would not be counted as effluent as including beach drain H-3 in the effluent totals would be double counting (NRC RIS 2008-03, Return/Re-use of Previously Discharged Radioactive Effluents).

The principle source of water for the beach drains is the yard drain system. Yard drain water sources are rain and snow melt. During the winter natural melting is enhanced by the use of snow melting machines. The melt water empties into the yard drains. Additionally, various roof drains connect to the yard drain system.

In addition to precipitation, the roof drains also carry condensate from various building AC units. A secondary source appears to be groundwater inleakage.

This is evidenced by flow during periods of no precipitation.

Because there are no external storage tanks or pipes that carry radioactive liquids, the main source of radioactivity for this system is recapture/washout of airborne H-3 discharges via the yard drain system. Groundwater inleakage may bring groundwater flow of H-3 from the up gradient area of the former retention pond as well as precipitation recharging the groundwater close to the plant in areas not drained by the yard drains. Because of these various recapture sources, the beach drains also are sampled as part of the ground water monitoring program. These results and other groundwater monitoring results are presented in Part D of this Annual Monitoring Report.

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Table 2-2 Summary of Circulating Water Discharge January 1, 2012 through December 31, 2012 I I Total Annual Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Total Total Activity Released (Ci)

Gamma Scan(+HIDs))' 3.56E-05 5.09E-03 1.89E-04 7.98E-04 2.63E-03 4.64E-05 8.79E-03 1.79E-03 4.62E-03 7.42E-03 1.44E-03 1.94E-02 1.38E-02 5.72E-02 Gross Alpha 0.00E+00 0.00E+00 0OOE+00 0.00E+00 0.00E+00 0.00E+00 0,00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 Tritium 3.86E+00 9.98E+00 6.87E+00 5.97E+00 8.54E+01 1.36E+01 1.26E+02 2.56E+02 7.36E+01 2.27E+02 8.39E+01 3.07E+01 3.23E+01 8.29E+02 Strontium (89/90/92) 0.00E+00 0.00E+00 0,00E+00 0.OOE+00 0.OOE+00 0,OOE+00 0,00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Total Vol Released (gal)

Processed Waste 2.41E+04 6.49E+04 4.93E+04 2.50E+04 7.18E+04 6.17E+04 2.97E+05 1.22E+05 5.78E+04 8.82E+04 1.14E+05 1.32E+05 1.03E+05 9.14E+05 Waste Water lttluente 3.14E+06 3.10E+06 3.38E+06 3.05E+06 3.07E+06 2.39E+06 1.81E+07 2.97E+06 2.69E+06 9.75E+09 3.51E+06 3.06E+06 3.39E+06 9.78E+09 U1 SG Blowdown 6.14E+06 5.42E+06 4.60E+06 4.16E+06 4.43E+06 3.69E+06 2.84E+07 5.04E+06 5.13E+06 4.92E+06 2.93E+06 4.20E+06 2.64E+06 5.33E+07 U2 SG Blowdown 3.95E+06 3.55E+06 2.89E+06 4.37E+06 3.63E+06 2.90E+06 2.13E+07 5.00E+06 4.69E+06 4.23E+06 2.84E+06 1.81E+05 5.11E+06 4.34E+07 Total Gallons 1.33E+07 1.21E+07 1.09E+07 1.16E+07 1.12E+07 9.05E+06 6.82E+07 1.31E+07 1.26E+07 9.76E+09 9.40E+06 7.57E+06 1.12E+07 9.88E+09 Total cc 5.02E+10 4.59E+10 4.13E+10 4.39E+10 4.24E+10 3.42E+10 2.58E+11 4.97E+10 4.76E+10 3.69E+13 3.56E+10 2.87E+10 4.26E+10 3.74E+13 Dilution vol(cc)' 6.62E+13 5.98E+13 6.62E+13 1.03E+14 1.15E+14 1.11E+14 5.21E+14 1.15E+14 1.15E+14 1.11E+14 1.13E+14 5.91E+13 9.42E+13 1.13E+15 Avg diluted discharge conc (pCi/cc)

Gamma Scan (+HTDs)' 5.38E-13 8.51E-11 2.85E-12 7.75E-12 2.29E-11 4.18E-13 1.56E-11 4.02E-11 6.67E-11 1.28E-11 3.28E-10 Gross Alpha 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 1.76E-14 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Tritium 5.83E-08 1.67E-07 1.04E-07 5.80E-08 7.43E-07 9.53E-07 2.23E-06 6.41E-07 2.04E-06 7.45E-07 5.19E-07 3.43E-07 Strontium (89/90/92) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 Max Batch Discharge Conc (pCi/cc) -

Tritium 5.28E-06 1.04E-05 3.71 E-06 6.13E-06 3.37E-05 4.25E-06 3.73E-05 3.5iE-05 3.98E-05 2.44E-05 9.742-06 1.421-05 Gamma Scan 3.73E-11 6.80E-10 1.19E-11 5.82E-11 8.92E-11 9.65E-12 7.34E-10 4.07E-11 1.77E-11 1.21 E-09 8.17E-09 8.55E-09 1 HTDs include Fe-55, C-14, Ni-63, and Tc-99. Does not include strontium which is totaled separately.

2 The waste water effluent system replaced the Retention Pond which was taken out of service in September 2002.

3 Circulating water discharge from both units.

Note: Dissolved noble gases detected in liquid effluents (e.g., Xe-1 33, Xe-1 35, etc.) are added to the atmospheric release summaries 7

Table 2-3 Isotopic Composition of Circulating Water Discharges (Curies)

January 1, 2012 through December 31, 2012 Total Total Nuclide Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Jan-Dec H-3 3.86E+00 9.98E+00 6.87E+00 5.97E+00 8.54E+01 1.36E+01 1.26E+02 2.56E+02 7.36E+01 2.27E+02 8.39E+01 3.07E+01 3.23E+01 8.29E+02 C-14 0.OOE+00 5.16E-04 0.OOE+00 0.OOE+00 1.17E-03 0.OOE+00 1.69E-03 8.78E-04 3.72E-03 6.58E-03 7.34E-04 4.60E-04 2.04E-04 1.43E-02 F-18 1.76E-06 0.OOE+00 1.78E-04 7.76E-04 1.21 E-03 3.04E-05 2.20E-03 2.57E-06 7.79E-04 6.68E-04 4.47E-04 5.09E-04 7.76E-04 5.38E-03 Cr-51 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.53E-05 0.OOE+00 0.OOE+00 0.OOE+00 9.28E-03 6.14E-03 1.55E-02 Mn-54 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.38E-06 0.OOE+00 0.OOE+00 0.OOE+00 1.95E-04 1.25E-04 3.21 E-04 Fe-55 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fe-59 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.24E-04 6.28E-05 1.86E-04 Co-57 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Co-58 6.83E-06 2.28E-05 1.55E-06 0.OOE+00 3.08E-06 0.OOE+00 3.43E-05 1.83E-04 4.12E-06 0.OOE+00 0.OOE+00 2.12E-03 1.50E-03 3.85E-03 Co-60 1.25E-05 1.01 E-04 8.66E-06 2.27E-05 9.49E-05 1.60E-05 2.56E-04 4.12E-04 5.37E-05 7.89E-05 1.02E-04 2.27E-03 1.71 E-03 4.88E-03 Ni-63 1.46E-05 4.13E-03 0.OOE+00 0.OOE+00 5.70E-05 0.OOE+00 4.20E-03 1.15E-04 3.06E-05 6.34E-05 1.08E-04 8.01E-05 1.06E-04 4.71E-03 Zn-65 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.45E-04 6.53E-05 2.1OE-04 As-76 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.O0E+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 2.71 E-05 1.76E-04 2.03E-04 Sr-90 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Nb-95 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 8.76E-06 0.OOE+00 O.OOE+00 0.OOE+00 9.40E-04 7.08E-04 1.66E-03 Nb-97 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Zr-95 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 5.63E-04 4.OOE-04 9.63E-04 Tc-99 0.OOE+00 2.95E-06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.95E-06 2.86E-05 9.40E-06 9.01E-06 2.76E-05 7.51E-06 6.66E-06 9.18E-05 Ag-110m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.05E-06 0.OOE+00 4.05E-06 3.13E-06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 7.18E-06 Sn-113 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 4.92E-05 4.29E-05 9.21E-05 Sn-1i17m 0.OOE+00 1.45E-04 0.OOE+00 0.OOE+00 5.48E-05 0.OOE+00 2.OOE-04 2.48E-05 2.20E-05 2.36E-05 1.64E-05 2.57E-03 1.87E-03 4.73E-03 Sb-122 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.73E-06 0.OOE+00 0.OOE+00 0.OOE+00 4.67E-06 2.32E-06 8.72E-06 Sb-124 0.OOE+00 2.55E-05 0.OOE+00 0.OOE+00 1.80E-06 0.OOE+00 2.73E-05 6.69E-05 3.31E-06 3.05E-06 1.46E-06 8.12E-05 4.56E-05 2.29E-04 Sb-125 0.OOE+00 1.44E-04 0.OOE+00 0.OOE+00 4.51E-05 0.00E+00 1.89E-04 2.48E-05 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 2.14E-04 1-131 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Te-132 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.28E-06 O.OOE+00 1.28E-06 Cs-137 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.35E-06 0.OOE+00 1.35E-06 Ba-140 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 La-140 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ce-141 O.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Note: The dissolved noble gases detected in liquid effluents (e.g., Xe-133, Xe-135, etc.) are added to the atmospheric release summaries. "- = no analysis 8

Table 2-4 Subsoil System Drains - Tritium Summary January 1, 2012, through December 31, 2012 S-1 S-3 S-7 S-8 S-9 S-10 S-11 1st Qtr H-3 (Ci) O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Flow (gal) 1.84E+06 1.88E+05 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 4.46E+04 2nd Qtr H-3 (Ci) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Flow (gal) 7.93E+05 1.99E+05 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 3.01 E+04 3rd Qtr H-3 (Ci) 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Flow (gal) 5.21 E+05 1.25E+05 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 2.03E+04 4th Qtr H-3 (Ci) 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Flow (gal) 4.71 E+05 2.44E+05 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 3.76E+04 2.6 Land Application of Sewage Sludge On January 13, 1988, pursuant to 10 CFR 20.302(a), NextEra received NRC approval for the disposal of sewage sludge, which may contain trace amounts of radionuclides, by land application on various properties surrounding the plant. Land application of sewage sludge is regulated by the Wisconsin Department of Natural Resources (WDNR). PBNP has not land applied sewage sludge for over a decade.

Therefore, NextEra has not renewed its WDNR permit to dispose of sewage sludge in this manner.

There were no sludge disposals by land application during 2012. All disposals were done at the Manitowoc Sewage Treatment Plant.

9

2.7 Carbon-14 Carbon-14 (C-14) is a naturally occurring radionuclide. Nuclear weapons testing of the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Small amounts of C-14 also are produced by nuclear reactors, but the amounts produced are less than C-14 produced by weapons testing or that occur naturally. NextEra began evaluating C-14 liquid discharges in 2009, prior to the issuance of Regulatory Guide (RG) 1.21, Rev 2 in June of 2009. NextEra continues to analyze batch liquid waste discharges for C-14 and reporting the results in the Annual Monitoring Report.

Beginning with the 2010 monitoring reports, the NRC requested that all nuclear plants report C-14 emissions. Pursuant to NRC guidance in RG 1.21, Rev 2, evaluation of C-14 in liquid wastes is not required because the quantity released via this pathway is much less than that contributed by gaseous emissions.

However, based upon prior information received at the industry sponsored RETS-REMP Workshops, NextEra began C-14 analyses and reporting prior to the issuance of RG 1.21, Rev 2. The results show that C-14 meets the principal radionuclide criterion of RG 1.21. A principal radionuclide may be determined based on its relative contribution to the public dose compared to the 10 CFR 50, Appendix I, dose objectives, or the amount of activity discharged compared to other radionuclides in its effluent type. In this case, it is compared to other radionuclides discharged in liquids. Furthermore, RG 1.21 states that a radionuclide is a principal effluent component if it contributes greater than 1% of the Appendix I design objective dose compared to the other radionuclides in the effluent type, or, if it is greater than 1% of the activity of all radionuclides in the effluent type. The 2012 liquid discharge monthly and total C-14 in liquid discharges are documented in Table 2-3. The liquid C-14 dose contribution is included in the doses calculated for the hypothetically, maximally exposed individual.

10

3.0 RADIOACTIVE AIRBORNE RELEASES The release paths to the environment contributing to radioactive airborne release totals during this reporting period were the auxiliary building vent stack, the drumming area vent stack, the letdown gas stripper, the Unit 1 containment purge stack, and the Unit 2 containment purge stack. A gaseous radioactive effluent treatment system in conjunction with administrative controls is used to minimize the impact on the environment from the airborne releases and maintain doses to the public ALARA.

3.1 Doses from Airborne Effluent Doses from airborne effluent are calculated for the MEI following the methodology contained in the PBNP ODCM. These calculated doses use parameters such as the amount of radioactive material released, the concentration at and beyond the site boundary, the average site weather conditions, and usage factors (e.g., breathing rates, food consumption). In addition to the MEI doses, the energy deposited in the air by noble gas beta particles and gamma rays is calculated and compared to the corresponding Appendix I design objectives. A comparison of the annual Appendix I design objectives for atmospheric effluents to the highest organ dose and the noble gas doses calculated using ODCM methodology is listed in Table 3-1. The calculated doses include the C-14 contribution. The C-14 dose contribution has been required since 2010 (see Sections 3.4 through 3.6 for a more detailed description). The comparison between airborne effluent doses with and without C-14 is shown in Table 3-4. The highest dose is the child-bone category. The doses demonstrate that releases from PBNP to the atmosphere continue to be ALARA.

3.2 Radioactive Airborne Release Summary Radioactivity released in airborne effluents for 2012 is summarized in Table 3-2.

The total noble gas is about one-tenth of the 2011 value. Airborne particulates are about 25% of the 2011 total. Airborne tritium is about 10% lower.

3.3 Isotopic Airborne Releases The monthly isotopic airborne releases for 2012, from which the airborne doses were calculated, are presented in Table 3-3. C-14 is not included in Table 3-3 because it was calculated and not measured. C-14 is discussed in the following sections.

3.4 Carbon-14 C-14 is a naturally occurring radionuclide. Nuclear weapons testing of the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Small amounts of C-14 also are produced by nuclear reactors as neutrons interact with the dissolved oxygen and nitrogen in the primary coolant. However, these amounts produced by nuclear reactors are much less that those produced by weapons testing or that occur naturally. The NRC has requested that nuclear plants report C-14 emissions.

Pursuant to NRC guidance RG 1.21, Rev 2, most of the C-14 emissions from nuclear plant occur in the gaseous phase.

11

C-14 is a hard-to-detect radionuclide. It is not a gamma emitter and must be chemically separated from the effluent stream before it can be measured.

Because nuclear plants currently are not equipped to perform this type of sampling, RG 1.21 allows for calculating C-14 discharges based on fission rates.

The Electric Power Research Institute (EPRI) undertook the task of developing the methodology for calculating C-14 generation and releases for the nuclear industry. The results were published as Technical Report 1021106, December 2010, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents."

The PBNP C-14 generation for 2012 was calculated using the EPRI guidance and the new core parameter resulting from the power uprate. The calculated amounts were 5.85 Ci for Unit 1 and 5.83 Ci for Unit 2 yielding a total of 11.67 Ci.

This total is higher than the calculated amount for 2010 and 2011 due to the power uprate. This calculated total is roughly 800 times higher than the 1.43E-02 Ci of C-14 determined by analyses of composites from liquid waste batch discharges, steam generator blowdown, and other waste streams.

3.5 C-14 Airborne Effluent Dose Calculation The dose from the airborne C-14 is dependent on its chemical form. The C-14 released to the atmosphere consists of both organic and inorganic species. Both the inorganic and organic C-14 contributes to the inhalation dose. Only the inorganic 14CO2 species contributes to the dose from the ingestion of photosynthetically incorporated C-14. The organic forms such as methane, CH4 ,

are not photosynthetically active. For PWRs such as PBNP, most of the gaseous C-14 occurs as methane, 14CH 4, not as carbon dioxide, 14CO2.

The amount of 14CO2 present in the PBNP airborne effluent has not been measured. However, such measurements have been made at a comparable PWR sites similar to the PBNP design. The Ginna Nuclear Generating Station is of similar design to PBNP. It is a Westinghouse 2-loop PWR of the same vintage as PBNP and approximately the same power (prior to the PBNP power uprate).

Measurements at Ginna for 18 months in 1980 - 1981 (Kunz, "Measurement of 14C Production and Discharge From the Ginna Nuclear Power Reactor," 1982) found that ten percent of the C-14 was discharged as 14CO2. Therefore, 10% of the 11.67 Ci of C-14 calculated for PBNP by EPRI will be used in the ingestion dose calculations.

C-14 dose calculations were made using the dose factors and the methodology of RG 1.109. The inhalation dose was calculated using all of the C-14 calculated to be released. All the C-14 is used because whether the C-14 is in the form of 14CO2 or one of the organic forms, such as CH , both would be 4 inhaled and contribute to a lung dose.

For the other existing pathways, milk, meat, and produce, the dose depends upon the amount incorporated into biomass consumed by cattle and people; forage for cattle and produce for humans. Incorporation only occurs via 12

photosynthesis. Photosynthesis only incorporates 14002 and hence the use of only the 10% fraction of the total C-14 release for these pathways.

The airborne effluent C-14 dose calculations were made as described above.

They were made for the MEI as explained in Section 2.1. This approach utilizes all the pathways that are applicable to a hypothetical person residing at the site boundary. Because C-14 is present as a gas, the pathways are milk, meat, and produce (vegetables, fruit, and grain) and the RG 1.109, Table E-5, usage factors applied to the calculation. As such, the resulting dose will be conservative in that the produce usage factor includes grain and fruit and these pathways do not exist in the vicinity of the point for which the C-14 doses are calculated. Furthermore, because leafy vegetables are included in the produce pathway, they are not used as a separate pathway because that would result in double accounting for leafy vegetable dose contribution.

3.6 C-14 Measurements No C-14 measurements were made of PBNP airborne effluents. In 2010, C-14 was measured in crops grown on fields in the owner controlled area located in the highest X/Q sector at the site's south boundary. One field is leased for feed corn by a dairy south of the plant. That dairy is part of the REMP. In an adjacent field soybeans are grown by another farmer. These two crops were sampled in this sector and as well as in a background location about 17 miles SW of the plant. Based on the measurement error, there was no statistical difference between the results obtained on site in the highest X/Q sector as compared to the background site some 17 miles away (2011 AMR, Table 10-3). These results demonstrated that the dose from C-14 in PBNP airborne effluents should not measurably increase the C-14 dose compared to that received from naturally occurring C-14 in plants (1 mrem: NCRP Report 93, Ionizing Radiation Exposure of the Population of the United States, 1987, p.12).

3.7 Errata to Previous Annual Monitoring Reports There are no airborne effluent corrections required for the 2011 Annual Monitoring Report.

13

Table 3-1 Comparison of 2012 Airborne Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Annual Appendix I Design January-December Percent of Appendix I Category Objective Calculated Dose Design Objective Particulate 30 mrem/organ 0.240 mrem 0.800 Noble gas 40 mrad (beta air) 0.000100 mrad 0.00025 Noble gas 20 mrad (gamma air) 0.000236 mrad 0.00118 Noble gas 30 mrem/skin 0.000335 mrem 0.00011 Noble gas 10 mrem (whole body) 0.000223 mrem 0.00223 Table 3-2 Radioactive Airborne Effluent Release Summary January 1, 2012, through December 31, 2012 Total Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Total Total NG from Liq (Ci) O.OOE+00 4.76E-04 O.OOE+00 O.OOE+00 1.81E-04 O.OOE+00 6.57E-04 3.80E-03 5.44E-04 2.18E-03 1.03E-02 1.06E-02 1.51E-02 4.32E-02 Total Noble Gas (Ci)1 6.79E-02 6.11E-02 6.48E-02 5.03E-02 5.15E-02 4.99E-02 3.46E-01 6.63E-02 4.73E-02 4.33E-02 1.35E-01 1.85E-01 6.47E-02 8.87E-01 Total Radioiodines (Ci) O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 1.80E-05 O.OOE+00 O.OOE+00 O.OOE+00 1.04E-05 O.00E+00 2.85E-05 Total Particulate (Ci) 3 1.34E-10 9.78E-11 1.28E-10 7.28E-11 5.81E-11 5.84E-11 5.49E-10 1.01E-06 1.25E-06 9.89E-07 O.OOE+00 5.48E-05 O.OOE+00 5.80E-05 Alpha (Ci) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Strontium(Ci) O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 All other beta + gamma (Ci) 1.34E-10 9.78E-11 1.28E-10 7.28E-11 5.81E-11 5.84E-11 5.49E-10 1.01E-06 1.25E-06 9.89E-07 O.OOE+00 5.48E-05 O.OOE+00 5.80E-05 Total Tritium (Ci) 6.29E+00 4.38E+00 6.41E+00 7.04E+00 7.02E+00 4.57E+00 3.57E+01 6.32E+00 8.69E+00 2.66E+00 3.81E+00 7.66E+00 4.99E+00 6.98E+01 Max NG H'rlyRel.(Ci/sec) 4.60E-08 9.19E-08 5.99E-08 5.38E-08 5.61E-08 6.15E-08 5.61E-08 6.54E-08 5.88E-08 6.01E-08 4.76E-08 5.18E-08 Total noble gas (airborne + liquid releases).

2 Airborne radioiodines only include 1-131 and 1-133. Although for dose calculations iodines are grouped with particulates, for this reporting table they are separated from the particulate group.

Total Particulate is the sum of alpha, strontium, and others. It does not include radioiodines or C-14. C-14 was calculated for the year and no monthly values are available.

14

TABLE 3-3 Isotopic Composition of Airborne Releases January 1,2012 through December 31, 2012 Jan Feb Mar Apr May Jun Semi- Jul Aug Sep Oct Nov Dec Total Nuclide (Ci) (Ci) (Ci) (Ci) (Ci) (Ci) Annual (Ci) (Ci) (Ci) (Ci) (Ci) (Ci) (Ci)

H-3 6.29E+00 4.38E+00 6.41 E+00 7.04E+00 7.02E+00 4.57E+00 3.57E+01 6.32E+00 8.69E+00 2.66E+00 3.81 E+00 7.66E+00 4.99E+00 6.98E+01 Ar-41 4.42E-02 4.15E-02 5.21E-02 4.25E-02 4.54E-02 4.24E-02 2.68E-01 5.45E-02 3.75E-02 3.49E-02 5.62E-02 1.48E-02 4.81E-02 5.14E-01 Kr-85 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Kr-85m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.33E-05 7.62E-04 O.OOE+00 7.75E-04 Kr-87 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.98E-04 O.OOE+00 1.98E-04 Kr-88 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 9.54E-04 O.OOE+00 9.54E-04 Xe-131m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+O0 O.OOE+00 0.00E+00 3.23E-04 O.OOE+00 3.23E-04 Xe-133 2.35E-02 1.97E-02 1.27E-02 7.74E-03 6.14E-03 7.44E-03 7.72E-02 1.15E-02 9.67E-03 8.40E-03 7.58E-02 1.47E-01 1.62E-02 3.46E-01 Xe-133m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.07E-06 O.OOE+00 O.OOE+00 1.08E-03 2.33E-03 1.50E-04 3.57E-03 Xe-135 2.82E-04 1.72E-06 O.OOE+00 7.49E-05 O.OOE+00 O.OOE+00 3.59E-04 2.91 E-04 4.71E-05 4.72E-05 1.79E-03 1.82E-02 2.34E-04 2.09E-02 Xe-1 35m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Xe-1 38 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 F-18 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.47E-08 O.OOE+00 O.OOE+00 O.OOE+00 1.47E-08 Cr-51 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.36E-05 O.OOE+00 2.36E-05 Mn-54 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.75E-06 O.OOE+00 4.75E-06 Co-58 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.90E-06 O.OOE+00 5.90E-06 Co-60 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 7.30E-06 O.OOE+00 7.30E-06 Zn-65 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.39E-07 O.OOE+00 4.39E-07 Nb-95 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.80E-06 O.OOE+00 5.80E-06 Zr-95 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.49E-06 O.OOE+00 3.49E-06 1-131 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.48E-06 O.OOE+00 O.OOE+00 0.00E+00 6.05E-07 O.OOE+00 2.09E-06 1-132 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 9.84E-06 O.OOE+00 9.84E-06 1-133 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.66E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.66E-05 Sb-124 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 6.98E-08 O.OOE+00 6.98E-08 Sb-125 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.55E-08 O.OOE+00 4.55E-08 Cs-137 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 2.44E-07 O.OOE+00 O.OOE+00 1.12E-08 O.OOE+00 2.56E-07 Fe-55 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.39E-06 O.OOE+00 2.39E-06 Ni-63 1.34E-10 9.78E-11 1.28E-10 O.OOE+00 O.OOE+00 O.OOE+00 3.60E-10 1.01E-06 1.01E-06 9.75E-07 O.OOE+00 1.52E-06 O.OOE+00 4.51E-06 Tc-99 O.OOE+00 O.OOE+00 O.OOE+00 7.28E-11 5.81E-11 5.84E-11 1.89E-10 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.89E-10 Sr-89 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Sr-90 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Note: The Noble Gases listed above include the liquid contribution 15

Table 3-4 Comparison of Airborne Effluent Doses 2012 Airborne Particulate + Tritium Dose (mrem)

Bone Liver T-WB Thyroid Kidney Lung GI-LLI Skin Adult 1.71 E-04 1.63E-02 1.66E-02 1.64E-02 1.63E-02 1.63E-02 1.64E-02 2.83E-04 Teen 2.30E-04 1.88E-02 1.90E-02 1.88E-02 1.88E-02 1.87E-02 1.88E-02 2.83E-04 Child 3.66E-04 2.74E-02 2.77E-02 2.75E-02 2.74E-02 2.74E-02 2.74E-02 2.83E-04 Infant 1.05E-04 1.21 E-02 1.23E-02 1.22E-02 1.21 E-02 1.21 E-02 1.21 E-02 2.83E-04 2012 Carbon-14 Dose (mrem)

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 6.61 E-02 1.31 E-02 1.31 E-02 1.31 E-02 1.31 E-02 1.31 E-02 1.31 E-02 0.OOE+00 Teen 1.04E-01 2.06E-02 2.06E-02 2.06E-02 2.06E-02 2.06E-02 2.06E-02 0.00E+00 Child 2.40E-01 4.78E-02 4.78E-02 4.78E-02 4.78E-02 4.78E-02 4.78E-02 0.OOE+00 Infant 1.22E-01 2.59E-02 2.59E-02 2.59E-02 2.59E-02 2.59E-02 2.59E-02 0.OOE+00 2012 Total Airborne Non-Noble Gas Dose (Particulate + H-3 + C-14 (mrem))

Bone Liver T-WB Thyroid Kidney Lung GI-LLI Skin Adult 6.63E-02 2.95E-02 2.97E-02 2.95E-02 2.95E-02 2.95E-02 2.95E-02 2.83E-04 Teen 1.04E-01 3.94E-02 3.96E-02 3.94E-02 3.94E-02 3.94E-02 3.94E-02 2.83E-04 Child 2.40E-01 7.52E-02 7.55E-02 7.53E-02 7.52E-02 7.52E-02 7.52E-02 2.83E-04 Infant 1.22E-01 3.80E-02 3.82E-02 3.81 E-02 3.80E-02 3.80E-02 3.80E-02 2.83E-04 Ann.Limit 3.OOE+01 3.OOE+01 3.OOE+01 3.OOE+01 3.OOE+01 3.OOE+01 3.OOE+01

% Limit 8.OOE-01 2.51 E-01 2.51E-01 2.51E-01 2.51E-01 2.51E-01 9.43E-04 The percent of limit is calculated using the highest total dose, the Child Age Group.

16

4.0 RADIOACTIVE SOLID WASTE SHIPMENTS 4.1 Types, Volumes, and Activity of Shipped Solid Waste The following types, volumes, and activity of solid waste were shipped from PBNP for offsite disposal or burial during 2012. No Type C or D waste was shipped. No irradiated fuel was shipped offsite. The volume, activity and type of waste are listed in Table 4-1.

Table 4-1 Quantities and Types of Waste Shipped from PBNP in 2012 Type of Waste Quantity Activity A. Spent resins, filter sludge, evaporator bottoms, etc. 9.900 m3 71.590 Ci 349.6 ft3 B. Drycompressible waste, contaminated equipment, etc 335.7 0 3 0.925 Ci 11854.6 ft3 C. Irradiated components, control rods, etc. N/A m3 N/A Ci 3

ft D. Other N/A 0 3 N/A Ci 3

11ft 4.2 Maior Nuclide Composition (by Tvr)e of Waste)

The major radionuclide content of the 2012 solid waste was determined by gamma isotopic analysis and the application of scaling factors for certain indicator radionuclides based on the measured isotopic content of representative waste stream samples. The estimated isotopic content is presented in Table 4-2.

Only those radionuclides with detectable activity are listed.

17

Table 4-2 2012 Estimated Solid Waste Major Radionuclide Composition TYPE A TYPE B Percent Percent Nuclide Abundance Nuclide Abundance Ni-63 45.5055% Co-60 34.1720%

Co-60 25.2948% Ni-63 19.2701%

Fe-55 10.5678% Cs-i137 14.3109%

Co-58 8.7378% Fe-55 12.1233%

Mn-54 3.2226% Nb-95 6.2200%

Cs-137 3.1089% Sb-125 2.3689%

Sb-125 1.9609% Co-58 1.6714%

Ni-59 0.4015% Zr-95 1.5739%

Ce-144 0.2735% Tc-99 0.9741%

H-3 0.2017% H-3 0.9688%

C-14 0.1917% Mn-54 0.9469%

Co-57 0.1373% Pu-241 0.8838%

Pu-241 0.1012% Cr-51 0.7354%

Nb-95 0.0854% Sb-124 0.6978%

Sr-90 0.0737% Sr-90 0.6841%

Sb-124 0.0432% Ag-110m 0.4424%

Sr-89 0.0279% Am-241 0.4306%

Ag-110m 0.0248% Ce-144 0.3979%

Zr-95 0.0190%/0 Zn-65 0.3079%

Tc-99 0.0097% Pu-238 0.1282%

Zn-65 0.0033% Pu-239 0.12070/6 Arm-241 0.0025% Pu-240 0.1198%

Nb-94 0.0011% Nb-94 0.1126%

Pu-238 0.0010% Ag-108m 0.0855%

Pu-239 0.0009% Co-57 0.0755%

Ag-108m 0.0009% Sr-89 0.0689%

Cm-243 0.0007% C-14 0.0682%

Pu-240 0.0002% Cm-243 0.0212%

Cm-244 0.0002% Cm-244 0.0165%

Cm-242 0.0001% Cm-242 0.0029%

Pu-242 0.0001% 1 1 1 18

4.3 Solid Waste Disposition There were nine solid waste shipments from PBNP during 2012. The dates and destinations are shown in Table 4-3.

Table 4-3 2012 PBNP Radioactive Waste Shipments Date Destination 01/15/12 Erwin, TN 02/29/12 Oak Ridge, TN 03/09/12 Oak Ridge, TN 06/15/12 Oak Ridge, TN 09/25/12 Erwin, TN 10/11/12 Clive, UT 11/06/12 Oak Ridge, TN 11/28/12 Oak Ridge, TN 11/30/12 Clive, UT 19

5.0 NONRADIOACTIVE CHEMICAL RELEASES 5.1 Scheduled Chemical Waste Releases Scheduled chemical waste releases to the circulating water system from January 1, 2012, to June 30, 2012, included 8.60E+05 gallons of neutralized wastewater. The wastewater contained 0 lbs. of suspended solids and 8.64E+03 lbs. of dissolved solids.

Scheduled chemical waste releases to the circulating water system from July 1,2012, to December 31, 2012, included 5.47E+05 gallons of neutralized wastewater. The wastewater contained 1.36E+00 lbs. of suspended solids and 1.36E+03 lbs. of dissolved solids.

Scheduled chemical waste releases are based on the average analytical results obtained from sampling a representative number of neutralizing tanks.

5.2 Miscellaneous Chemical Waste Releases Miscellaneous chemical waste releases from the wastewater effluent (based on effluent analyses) to the circulating water for January 1, 2012, to June 30, 2012, included 1.82E+07 gallons of clarified wastewater. The wastewater contained 4.05E+03 lbs. of suspended solids.

Miscellaneous chemical waste releases from the wastewater effluent (based on effluent analyses) to the circulating water for July 1, 2012, to December 31, 2012, included 1.81 E+07 gallons of clarified wastewater. The wastewater contained 2.93E+03 lbs. of suspended solids.

Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from January 1, 2012, to June 30, 2012, included 4.36E+05 lbs. of sodium bisulfite solution (1.66E+05 lbs. sodium bisulfite),

4.70E+05 lbs of Sodium Hypochlorite Solution (5.87E+04 lbs. sodium hypochlorite), and 5.48E+03 lbs. Acti-Brom 1338 (2.47E+03 lbs. sodium bromide).

Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from July 1, 2012, to December 31, 2012, included 5.80E+05 lbs. of sodium bisulfite solution (2.20E+05 lbs sodium bisulfite),

54.38E+05 lbs. Sodium Hypochlorite Solution (5.48E+04 lbs. sodium hypochlorite), 6.04E+03 lbs. Acti-Brom 1338 (2.72E+03 lbs. sodium bromide).

20

6.0 CIRCULATING WATER SYSTEM OPERATION The circulating water system operation during this reporting period for periods of plant operation is described in Table 6-1.

Table 6-1 Circulating Water System Operation for 2012 UNIT JAN FEB MAR APR MAY JUN Average Volume Cooling 1 291.9 291.9 291.5 460.9 499.3 495.9 Water Discharge [million gal/day]** 2 291.9 291.9 291.5 460.6 499.3 495.9 Average Cooling Water 1 41.0 41.8 44.8 48.0 49.6 53.0 Intake Temperature [OF] 2 41.8 42.1 44.5 48.6 50.1 52.1 Average Cooling Water 1 79.8 79.9 82.5 72.1 70.9 71.3 Discharge Temperature [OF] 2 78.0 78.6 80.9 68.2 67.3 66.4 Average Ambient Lake Temperature [OF] 35.0 35.7 39.5 44.1 45.2 46.2 OOS - Data not available due to instrument issues.

Table 6-1 (continued)

Circulating Water System Operation for 2012 UNIT JUL AUG SEP OCT NOV* DEC Average Volume Cooling 1 498.6 499.3 499.3 499.8 491.0 438.0 Water Discharge [million gal/day]** 2 498.6 499.3 499.3 479.3 203.9 409.6 Average Cooling Water 1 68.0 66.8 59.7 51.9 43.7 41.3 Intake Temperature [OF] 2 57.8 65.2 59.8 51.4 44.7 40.5 Average Cooling Water 1 89.2 86.0 79.1 71.7 67.9 66.1 Discharge Temperature [OF] 2 84.0 84.4 77.6 71.1 41.3 64.6 Average Ambient Lake Temperature [OF] 62.4 61.1 54.8 47.5 42.6 36.8

• U2 outage circ water shut down 11/2/12 - 11/25/12

• • For days with cooling water discharge flow.

21

Part B Miscellaneous Reporting Requirements 7.0 ADDITIONAL REPORTING REQUIREMENTS 7.1 Revisions to the PBNP Effluent and Environmental Programs The ODCM, the EM, and the RECM were not revised in 2012.

7.2 Interlaboratory Comparison Program ATI Environmental, Inc, Midwest Laboratory, the analytical laboratory contracted to perform the radioanalyses of the PBNP environmental samples, participated in the Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP) as well as in the interlaboratory comparison studies administered by Environmental Resources Associates (ERA) during 2012. The ERA environmental crosscheck program replaces the Environmental Measurements Laboratory (EML) Quality Assessment Program which was discontinued. The results of these comparisons can be found in Appendix A.

7.3 Special Circumstances No special circumstances report regarding operation of the explosive gas monitor for the waste gas holdup system was needed during 2012.

22

Part C RADIOLOGICAL ENVIRONMENTAL MONITORING

8.0 INTRODUCTION

The objective of the PBNP Radiological Environmental Monitoring Program (REMP) is to determine whether the operation of PBNP or the ISFSI has radiologically impacted the environment. To accomplish this, the REMP collects and analyzes air, water, milk, soil, vegetation, and fish samples for radionuclides and uses thermoluminescent dosimeters (TLDs) to determine the ambient radiation background. The analyses of the various environmental media provide data on measurable levels of radiation and radioactive materials in the principal pathways of environmental exposure. These measurements also serve as a check of the efficacy of PBNP effluent controls.

The REMP fulfills the requirements of 10 CFR 20.1302, PBNP General Design Criterion (GDC) 17, GDC 64 of 10 CFR 50, Appendix A, and Sections IV.B.2 and IV.B.3 of 10 CFR 50, Appendix I, for the operation of the plant. A subset of the PBNP REMP samples, consisting of air, soil and vegetation, also fulfills 10 CFR 72.44(d)(2) for operation of the ISFSI. Additionally, TLDs provide the means to measure changes in the ambient environmental radiation levels at sites near the ISFSI and at the PBNP site boundary to ensure that radiation levels from the ISFSI are maintained within the dose limits of 10 CFR 72.104. Because the ISFSI is within the PBNP site boundary, radiation doses from PBNP and the ISFSI, combined, must be used to assess compliance with 10 CFR 72.122 and 40 CFR 190. Therefore, radiological environmental monitoring for the ISFSI is provided by selected sampling sites, which are part of the PBNP REMP.

For the aquatic environment, the samples include water as well as the biological integrators, such as fish and filamentous algae. Because of their migratory behavior, fish are wide area integrators. In contrast, the filamentous algae periphyton is attached to shoreline rocks and concentrate nuclides from the water flowing by their point of attachment. Grab samples of lake water provide a snapshot of radionuclide concentrations at the time the sample is taken; whereas analysis of fish and filamentous algae yield concentrations integrated over time.

The air-grass-cow-milk exposure pathway unites the terrestrial and atmospheric environments. This pathway is important because of the many dairy farms around PBNP. Therefore, the REMP includes samples of air, general grasses and milk from the PBNP environs. An annual land use survey is made to determine whether the assumptions on the location of dairy cattle remain conservative with respect to dose calculations for PBNP effluents. The dose calculations assume that the dairy cattle are located at the south site boundary, the highest depositional sector. In addition, soil samples are collected and analyzed in order to monitor the potential for long-term buildup of radionuclides in the vicinity of PBNP.

For the measurement of ambient environmental radiation levels that may be affected by direct radiation from PBNP or by noble gas effluents, the REMP employs a series of TLDs situated around PBNP and the ISFSI.

23

9.0 PROGRAM DESCRIPTION 9.1 Results Reporting Convention The vendor used by NextEra to analyze the environmental samples is directed to report analysis results as measured by a detector, which can meet the required lower limit of detection (LLD) as specified in Table 2-2 of the Environmental Manual for each sample. The report provided by the vendor (see Appendix 1) contains values, which can be either negative, positive or zero plus/minus the two sigma counting uncertainty, which provide the 95% confidence level for the measured value.

The LLD is an a prioriconcentration value that specifies the performance capability of the counting system used in the analyses of the REMP samples.

The parameters for the a prioriLLD are chosen such that only a 5% chance exists of falsely concluding a specific radionuclide is present when it is not present at the specified LLD. Based on detector efficiency and average background activity, the time needed to count the sample in order to achieve the desired LLD depends upon the sample size. Hence, the desired LLD may be achieved by adjusting various parameters. When a suite of radionuclides are required to be quantified in an environmental sample such as lake water, the count time used is that required to achieve the LLD for the radionuclide with the longest counting time. Therefore, in fulfilling the requirement for the most difficult to achieve radionuclide LLD, the probability of detecting the other radionuclides is increased because the counting time used is longer than that required to achieve the remaining radionuclide LLDs.

The REMP results in this report are reported as averages of the measurements made throughout the calendar year plus/minus the associated standard deviation. If all net sample concentrations are equal to or less than zero, the result is reported as "Not Detectable" (ND), indicating no detectable level of activity present in the sample. If any of the net sample concentrations indicate a positive result statistically greater than zero, all of the data reported are used to generate the reported statistics. Because of the statistical nature of radioactive decay, when the radionuclide of interest is not present in the sample, negative and positive results centered about zero will be seen. Excluding validly measured concentrations, whether negative or as small positive values below the LLD, artificially inflates the calculated average value. Therefore, all generated data are used to calculate the statistical values (i.e., average, standard deviation) presented in this report. The calculated average may be a negative number.

As mentioned above, radioactive decay is a statistical process that has an inherent uncertainty in the analytical result. No two measurements will yield exactly the same result. However, the results are considered equal if the results fall within a certain range based upon the statistical parameters involved in the process. The REMP analytical results are reported at the 95% confidence limit in which the true result may be two standard deviations above or below the reported result. This means that there is only a 5% chance of concluding that the identified radioactive atom is not there when it really is present in the sample. A false positive is an analytical result which statistically shows that the radionuclide is present in the sample when it really is not there. Typically, if the 95%

24

confidence interval for a positive does not include zero, the radionuclide is considered to be present. For example, the result is reported as 100 +/- 90. One hundred minus 90 yields a positive result and therefore may be considered to be present. However, this may be a false positive. If the radionuclide was not in the plant effluent, this result would fall into that category which 5% of the time it is falsely concluded that the radionuclide is present when in actuality it is not. This usually happens at low concentrations at or near the LLD where fluctuations in the background during the counting process skew the results to produce a positive result.

In interpreting the data, effects due to the plant must be distinguished from those due to other sources. A key interpretive aid in assessment of these effects is the design of the PBNP REMP, which is based upon the indicator-control concept.

Most types of samples are collected at both indicator locations and at control locations. 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 fluctuation in radiation levels arising from other sources.

9.2 Sampling Parameters Samples are collected and analyzed at the frequency indicated in Table 9-1 from the locations described in Table 9-2 and shown in Figures 9-1, 9-2 and 9-3. (The latter two figures show sampling locations not shown in preceding figures due to space limitations. The location of the former retention pond, retired and remediated to NRC unrestricted access criteria, is indicated in Figure 9-3). The list of PBNP REMP sampling sites used to determine environmental impact around the ISFSI is found in Table 9-3. The minimum acceptable sample size is found in Table 9-4. In addition, Table 9-1 indicates the collection and analysis frequency of the ISFSI fence TLDs.

9.3 Deviations from Required Collection Frequency Deviations from the collection frequency given in Table 9-1 are allowed because of hazardous conditions, automatic sampler malfunction, seasonal unavailability, and other legitimate reasons (Section 2.2.6 of the Environmental Manual).

Table 9-5 lists the deviations from the scheduled sampling frequency that occurred during the reporting period.

9.4 Assistance to the State of Wisconsin The Radiation Protection Unit of the Wisconsin Department of Health and Family Services maintains a radiological environmental monitoring program to confirm the results from the PBNP REMP. As a courtesy to the State of Wisconsin, NextEra personnel also collect certain environmental samples (Table 9-6) for the State from sites that are near PBNP sampling sites, or are co-located.

9.5 Program Modifications No new permanent monitoring sites were added in 2012.

25

Table 9-1 PBNP REMP Sample Analysis and Frequency Sample Type Sample Codes Analyses Frequency Environmental Radiation E-01, -02, -03, -04, -05 TLD Quarterly Exposure -06, -07, -08, -09, -12

-14, -15, -16, -17, -18,

-20, -22, -23, -24, -25,

-26, -27, -28, -29, -30,

-31, -32, -38, -39,-41,

-42,-43, -TC Vegetation E-01, -02, -03, -04, -06, Gross Beta 3x/yr as available

-08, -09, -20, Gamma Isotopic Analysis Algae E-05, -12 Gross Beta 3x/yr as available Gamma Isotopic Analysis Fish E-13 Gross Beta 3x/yr as available Gamma Isotopic Analysis (Analysis of edible portions only)

Well Water E-10 Gross Beta, H-3 Quarterly Sr-89, 90,1-131 Gamma Isotopic Analysis Lake Water E-01, -05, -06, -33 Gross Beta, Sr-89/90, H-3 Monthly / Quarterly composite of monthly collections 1-131 Monthly Gamma Isotopic Analysis Monthly Milk E-11, -40, -21 Sr-89, 90 Monthly 1-131 Gamma Isotopic Analysis Air Filters E-01, -02, -03, -04, Gross Beta Weekly (particulate)

-08, -20 1-131 Weekly (charcoal)

Gamma Isotopic Analysis Quarterly (on composite particulate filters)

Soil E-01, -02, -03,-04, Gross Beta 2x/yr

-06, -08, -09, -20, Gamma Isotopic Analysis Shoreline Sediment E-01, -05, -06, -12, -33, Gross Beta 2x/yr Gamma Isotopic Analysis ISFSI Ambient North, East, South, Radiation Exposure West Fence Sections TLD Quarterly 26

Table 9-2 PBNP REMP Sampling Locations Location Code Location Description E-01 Primary Meteorological Tower South of the Plant E-02 Site Boundary Control Center - East Side of Building E-03 Tapawingo Road, about 0.4 Miles West of Lakeshore Road E-04 North Boundary E-05 Two Creeks Park Point Beach State Park - Coast Guard Station; TLD located South of the Lighthouse on E-06 Telephone pole E-07 WPSC Substation on County V, about 0.5 Miles West of Hwy 42 E-08 G.J. Francar Property at Southeast Corner of the Intersection of Cty. B and Zander Road E-09 Nature Conservancy E-10 PBNP Site Well E-1 1 Dairy Farm about 3.75 Miles West of Site E-12 Discharge Flume/Pier E-13 Pumphouse E-14 South Boundary, about 0.2 miles East of Site Boundary Control Center E-15 Southwest Corner of Site E-16 WSW, Hwy 42, a residence about 0.25 miles North of Nuclear Road E-17 North of Mishicot, Cty. B and Assman Road, Northeast Corner of Intersection E-18 Northwest of Two Creeks at Zander and Tannery Roads E-20 Reference Location, 17 miles Southwest, at Silver Lake College E-21 Local Dairy Farm just South of Site on Lakeshore and Irish Roads E-22 West Side of Hwy 42, about 0.25 miles North of Johanek Road E-23 Greenfield Lane, about 4.5 Miles South of Site, 0.5 Miles East of Hwy 42 E-24 North Side of County Rt. V, near intersection of Saxonburg Road E-25 South Side of County Rt. BB, about 0.5 miles West of Norman Road E-26 804 Tapawingo Road, about 0.4 miles East of Cty. B, North Side of Road E-27 Intersection of Saxonburg and Nuclear Roads, Southwest Corner, about 4 Miles WSW E-28 TLD site on western most pole between the 2rd and 3d parking lots.

E-29 Area of North Meteorological Tower.

E-30 NE corner at Intersection of Tapawingo and Lakeshore Roads.

E-31 On utility pole North side of Tapawingo Road closest to the gate at the West property line.

E-32 On a tree located at the junction of property lines, as indicated by trees and shrubs, about 500 feet east of the west gate on Tapawingo Road and about 1200 feet south of Tapawingo Road. The location is almost under the power lines between the blue and gray transmission towers.

Lake Michigan shoreline accessed from the SE corner of KNPP parking lot. Sample South of E-33 creek.

E-38 Tree located at the West end of the area previously containing the Retention Pond.

E-39 Tree located at the East end of the area previously containing the Retention Pond.

E-40 Local Dairy Farm, W side of Hwy 42, about 1.8 miles north of the Nuclear Rd intersection E-41 NW corner of Woodside and Nuclear Rds (Kewaunee County)

E-42 NW corner of Church and Division, East of Mishicot E-43 West side of Tannery Rd south of Elmwood (7th pole south of Elmwood)

E-TC Transportation Control; Reserved for TLDs 27

W4U1 M1 C-,

C, 5,.

1-POINT BEACH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SITES I.......... MILE

,'"'r,' KILOMETER Figure 9-1 PBNP REMP Sampling Sites 28

FIGURE2-1b SITE MAP POINT BEACH NUCLEAR PLANT r -, - --

I il AleW, p SITE BOtIJEARY LL.

I ,,4001o, 0 SIX

, 22,* T I I ISFSI TAPAiFNGORD.

LiIQU30 29 P F'LUNES

\FENCE INTAKE

• . .12 I RELEASE i1*0 - TRAINING BLDG.

i IS 0'" !

/.CONTRIN.

SITE 80OUNDARY CENTER RD.

MICJLEAR ENV IRONMENTAL MON ITORING STAT IONS STLD () TLD& AIR ,, OTHER COSFILE IOT48 Figure 9-2 Map of REMP Sampling Sites Located Around PBNP 29

FIC* 2-10 E-29 LAKE MICH[GAN TAPAWI1RO RD.

I 2 TI 1 A I

WOODS WOODS -J, Figure 9-3 Enhanced Map Showing REMP Sampling Sites Closest to PBNP 30

Table 9-3 ISFSI Sampling Sites Ambient Radiation Monitoring (TLD) Soil, Vegetation and Airborne Monitoring E-03 E-02 E-28 E-03 E-29 E-04 E-30 E-31 E-32 Table 9-4 Minimum Acceptable Sample Size Sample Type Size Vegetation 100-1000 grams Lake Water 8 liters Air Filters 250 m3 (volume of air)

Well Water 8 liters Milk 8 liters Algae 100-1000 grams Fish (edible portions) 1000 grams Soil 500-1000 grams Shoreline Sediment 500-1000 grams 31

Table 9-5 Deviations from Scheduled Sampling and Frequency Sample Location Collection Reason for not conducting REMP Plans for Preventing Recurrence Type Date as required AP/AI E-04 5/9/12 Power loss In all three cases the power was lost to the sampler E-01 08/16/12 Power loss to sampler resulting in a low volume. Hence each sample was E-01 08/22/12 Power loss to sampler considered to lost.

Table 9-6 Sample Collections for State of Wisconsin Sample Type Location Frequency Lake Water E-01 Monthly Air Filters E-07 Weekly E-08 Fish E-13 Quarterly, As Available Precipitation E-04 Twice a month, E-08 As Available Milk E-1 1 Monthly E-1 9 Well Water E-10 Twice per year 32

9.6 Analytical Parameters The types of analyses and their frequencies are given in Table 9-1. The LLDs for the various analyses are found in the Section 10 (Table 10-1) with the summary of the REMP results. All environmental LLDs listed in Table 2-2 of the Environmental Manual (also in Table 10-1) were achieved during 2012.

9.7 Description of Analytical Parameters in Table 9-1 9.7.1 Gamma isotopic analysis Gamma isotopic analysis consists of a computerized scan of the gamma ray spectrum from 80 keV to 2048 keV. Specifically included in the scan are Mn-54, Fe-59, Co-58, Co-60, Zr-95, Nb-95, Ru-103, Ru-106, 1-131, Ba-La-140, Cs-134, Cs-137, Ce-141, and Ce-144. However, other detected nuclear power plant produced radionuclides also are noted. The above radionuclides detected by gamma isotopic analysis are decay corrected to the time of collection. Frequently detected, but not normally reported in the Annual Monitoring Report, are the naturally occurring radionuclides Ra-226, Bi-214, Pb-212, TI-208, Ac-228, Be-7, and K-40.

9.7.2 Gross Beta Analysis Gross beta analysis is a non-specific analysis that consists of measuring the total beta activity of the sample. No individual radionuclides are identifiable by this method. Gross beta analysis is a quick method of screening samples for the presence of elevated activity that may require additional, immediate analyses.

9.7.3 Water Samples Water samples include both Lake Michigan and well water. The Lake Michigan samples are collected along the shoreline at two locations north and two locations south of PBNP. The well water is sampled from the on-site PBNP well. Gross beta measurements are made on the solids remaining after evaporation of the unfiltered sample to dryness. Gamma isotopic analyses are performed using 1-liter liquid samples. Strontium is determined by chemical separation and beta counting.

9.7.4 Air Samples Particulate air filters are allowed to decay at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before gross beta measurements are made in order for naturally occurring radionuclides to become a negligible part of the total activity. Gross beta measurements serve as a quick check for any unexpected activity that may require immediate investigation. Quarterly composites of the particulate air filters are analyzed for long-lived radionuclides such as Cs-1 34 and Cs-1 37. Charcoal cartridges for radioiodine are counted as soon as possible so the 1-131 will undergo only minimal decay prior to analyses. The weekly charcoal cartridges are screened for 1-131 by 33

counting them all at the same time to achieve a lower LLD. If a positive result is obtained, each cartridge is counted individually.

In order to ensure that the air sampling pumps are operating satisfactorily, a gross leak check is performed weekly. The pumps are changed out annually for calibration and maintenance beyond what can be accomplished in the field.

9.7.5 Vegetation Vegetation samples consist predominantly of green, growing plant material (grasses and weeds most likely to be eaten by cattle if they were present at the sampling site). Care is taken not to include dirt associated with roots by cutting the vegetation off above the soil line.

No special vegetation samples were obtained for C-14 analyses in 2012.

9.7.6 Environmental Radiation Exposure The 2012 environmental radiation exposure measurements were made using TLD cards. The TLD card is a small passive detector, which integrates radiation exposure. Each TLD consists of a Teflon sheet coated with a crystalline, phosphorus material (calcium sulfate containing dysprosium) which absorbs the gamma ray energy deposited in them.

Each TLD is read in four distinct areas to yield four exposure values which are averaged. Prior to the third quarter of 2001, exposure data was obtained using three lithium fluoride (LiF) TLD chips sealed in black plastic. The difference in material types can impact the amount of exposure measured. A comparison of the first quarters to the last two quarters in 2001, shows that the TLD cards typically produce a higher measured exposure value than the LiF chips (Table 9-7).

The reported field exposure is the arithmetic average of the measured exposure values at each location minus the exposure transportation control TLD (exposure received while the field TLD is in storage and transit). The gamma rays may originate from PBNP produced radionuclides or from naturally occurring radionuclides. The TLDs remain at the monitoring site for roughly three months prior to analyses and the results are reported as mrem per seven days. Because the TLDs are constantly bombarded by naturally occurring gamma radiation, even during shipment to and from PBNP, the amount of exposure during transportation is measured using transportation controls with each shipment of TLDs to and from the laboratory. The doses recorded on the transportation controls are subtracted from the monitoring TLDs in order to obtain the net in situ dose.

As documented in the 2011 AMR, the 2001 change from LiF chips to TLD cards resulted in an average readout increase of 14%.

34

9.7.7 ISFSI Ambient Radiation Exposure Although the ISFSI fence TLDs are not considered part of the REMP because of their location directly on site, their results can be used indirectly to determine whether the operation of the ISFSI is having an impact on the ambient environmental radiation beyond the site boundary.

Impacts are determined by comparison of fence TLD results to the results of the monitoring at PBNP site boundary and other selected locations.

10.0 RESULTS 10.1 Summary of 2011 REMP Results Radiological environmental monitoring conducted at PBNP from January 1, 2012, through December 31, 2012, consisted of analysis of air filters, milk, lake water, well water, soil, fish, shoreline sediments, algae, and vegetation as well as TLDs. The results are summarized, averages and high values, in Table 10-1 which contains the following information:

Sample: Type of the sample medium

Description:

Type of measurement N: Number of samples analyzed LLD: a priorilower limit of detection Average: Average value +/- the standard deviation of N samples High: Highest measured value +/- it's associated 2 sigma counting error Units: Units of measurement For certain analyses, an LLD, which is lower than that required by REMP, is used because the lower value derives from the counting time required to obtain the LLDs for radionuclides that are more difficult to detect. For these analyses, both LLDs are listed with the technical specification required REMP LLD given in parentheses. The results are discussed in the narrative portion of this report (Section 11). Blank values have not been subtracted from the results presented in Table 10-1. A listing of all the individual results obtained from the contracted analytical laboratory and the laboratory's radioanalytical quality assurance results and Interlaboratory Crosscheck Program results are presented in Appendix 1.

In Table 10-1, no results are reported as less than LLD (<LLD). All results are reported to NextEra by the contracted radioanalytical laboratory "as measured" whether positive or negative (see Section 9-1). Based on these results, a radionuclide is considered detected if it meets the criterion that the measured value minus its 2a counting error is greater than zero (x-2o >0). An "ND" entry in Table 10-1 means that for this radionuclide the criterion was not satisfied for any of the measurements. If one analysis fulfilled the criterion, then all of the reported results, both positive and negative, were used in calculating the average shown in Table 10-1.

The method of determining averages based on "as measured" results follows the recommendations made in NUREG-0475 (1978), "Radiological Environmental 35

Monitoring by NRC Licensees for Routine Operations of Nuclear Facilities Task Force Report," and in Health Physics Society Committee Report HPSR-1 (1980),

"Upgrading Environmental Radiation Data" released as document EPA 520/1 012 and in more recent documents such as ANSI N42.23-1996, "Instrument Quality Assurance for Radioassay Laboratories;" ANSI N13.30-1996, "Performance Criteria for Radiobioassay;" DE91-013607, "Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance" and NUREG-1576, "Multi-Agency Radiological Laboratory Analytical Protocols Manual."

Table 10-2 contains the ISFSI fence TLD results.

36

Table 10-1 Summary of Radiological Environmental Monitoring Results for 2012 Aierage + 1 Std.

Sample Description N LLD (a) Deviation (b) High +/-2 sigma Units TLD Envronrmertal Radiation 124 1 mrem 1.17 t 0.17 1.60 t 0.14 mR/7Tda Cortrol (E-20) 4 1 rnem 1.14 +/- 0.07 1.18 +/- 0.09 mR/7days Ar Grcss Beta 2621 0.01 0.026 +/- 0.010 0.060 +/- 0.005 pCi/m3 Control (E-20) Gross beta 53 0.01 0.026 +/- 0.011 0.063 +/- 0.004 pCi/m3 1-131 262 0.030 (0.07) ND

• pCi/m3 Control (E-20) 1-131 53 0.030 (0.07) ND pCi/m3 Cs-134 20 0.01(0.05) ND pCi/m3 Cortrol (-20) a-1 34 4 0.01(0.05) ND pCi/m3 Cs-137 20 0.01(0.06) ND pCi/m3 Cortrol (E-20) Os-1 37 4 0.01(0.06) ND pCi/m3 Other gamma emitters 20 0.1 0.0000 +/- 0.0004 0.0006 +/- 0.0004 pCi/m3 Control (E-20) Other 4 0.1 0.00(0 +/- 0.0004 0.0006 +/- 0.0004 pCi/m3 Milk Sr-89 36 5 ND pa/L Sr-90 36 1 0.7 +/- 0.4 1.7 +/- 0.5 pa/L 1-131 36 0.5 ND pa/L Cs-134 36 5(15) ND pa/L Cs-137 36 5(18) 0.4 +/- 1.0 3.4 +/- 1.9 pa/L_

Ba-La-140 36 5(15) -0.1 +/- 1.8 3.2 +/- 21 p0i/L Other gammaaemitters(Co-60) 36 15 02 +/- 1.5 3.4 +/- 23 pa/L Well Water Gross beta 4 4 25 +/- 0.3 2.8 +/- 1.8 p01/L 1+3 4 200(3000) ND - p/L Sr-89 4 5(10) ND - pa/L Sr-90 4 1 (2) ND - pa/L 1-131 4 0.5(2) ND - pO/L Mh-54 4 10(15) ND - pa/L Fe-59 4 30 ND - p/L Co-58 4 10(15) ND - p/l Co-60 4 10(15) ND - p/L Zn-65 4 30 ND - p/L Zr-Nb-95 4 15 ND - p0/

Cs-134 4 10(15) ND - p/1 Cs-137 4 10(18) ND - p/L Ba-La-140 4 15 0.6 +/- 1.3 1.9 +/- 1.8 p0/L Other gammaemitters(Ru-103) 4 30 0.4 +/- 1.2 1.5 +/- 1.4 p/L.

Algae Gross beta 6 0.25 5.30 +/- 1.43 7.16 +/- 0.26 pa/g Co-58 6 0.25 0.003 +/- 0.006 0.010 +/- 0.006 pCI/g Co-60 6 0.25 0.002 +/- 0.004 0.007 +/- 0.006 PC/g Cs-134 6 0.25 ND apaig Cs-137 16 0.25 1 0.021 +/- 0.011 0.035 +/- 0.012 pO/g (a) When two LLD values are listed, the required LLD per the PBNP REMP is enclosed in the parentheses. Whenever possible, PBNP uses the lower value to obtain greater sensitivity.

(b) "ND" indicates that the sample result is Not Detectable, i.e., sample concentrations were statistically equivalent to zero and less than the MDA.

37

Table 10-1 (continued)

Summary of Radiological Environmental Monitoring Results for 2012 Average +/- 1 Std.

Sample Description N LLD (a) Deviation (b) High +/- 2 sigma Units Lake Water Gross beta 48 4 2.2 -+/- 0.7 4.2 +/- 0.8 pCi/L 1-131 48 0.5 (2) ND pCi/L Mn-54 48 10(15) ND pCi/L Fe-59 48 30 0.1 +/- 1.8 4.6 +/- 3.4 pCi/L Co-58 48 10(15) -0.1 +/- 0.9 1.4 _ 1.3 pCi/L Co-60 48 10(15) 0.2 +/- 1.0 2.9 +/- 1.7 pCi/L Zn-65 48 30 -0.7 +/- 4.6 4.2 + 3.2 pCi/L Zr-Nb-95 48 15 ND pCi/L Cs-134 48 10(15) ND pCiA/

Cs-137 48 10(18) 0.0 +/- 0.9 3.4 _ 2.4 pCi/L Ba-La-1 40 48 15 -0.2 +/- 2.1 5.0 +/- 1.8 pCi/L Ru-103 (Other gamma) 48 30 -0.6 +/- 0.8 1.4 +/- 1.2 pCi/L Sr-89 16 5(10) ND pCi/L Sr-90 16 1(2) 0.28 +/- 0.10 0.48 00.30 pCi/L H-3 16 200 (3000) 179 +/- 346 1192 + 126 pCi/L Fish Gross beta 14 0.5 3.57 +/- 0.56 4.72 +/- 0.13 pCi/g Mn-54 14 0.13 ND pCi/g Fe-59 14 0.26 -0.004 +/- 0.016 0.021 +/- 0.015 pCi/g Co-58 14 0.13 0.001 +/- 0.007 0.012 +/- 0.007 pCi/g Co-60 14 0.13 0.000 +/- 0.010 0.016 +/- 0.009 pCi/g Zn-65 14 0.26 -0.011 +/- 0.024 0.026 +/- 0.016 pCi/g Cs-134 14 0.13 ND pCi/g Cs-137 14 0.15 0.024 +/- 0.020 0.074 +/- 0.023 pCi/g Ru-103 (Other gamma) 14 0.5 0.002 +/- 0.010 0.011 +/- 0.006 pCi/g Shoreline Gross beta 10 2 10.20 +/- 2.24 14.20 _ 0.89 pCi/g Sediment Cs-137 10 0.15 0.019 +/- 0.005 0.030 +/- 0.014 pCi/g Soil Gross beta 16 2 24.56 +/- 6.52 36.27 +/- 1.25 i Cs-137 16 0.15 0.15 +/- 0.09 0.39 +/- 0.04 pCi/g Vegetation Gross beta 24 0.25 6.92 _ 1.12 9.79 +/- 0.14 pCi/g 1-131 24 0.06 0.001 +/- 0.010 0.022 +/- 0.011 pCi/g Cs-134 24 0.06 ND pCi/g Cs-137 24 0.08 0.004 +/- 0.011 0.051 + 0.022 pCi/g Othergamma emitters (Co-60) 24 0.25 0.001 +/- 0.004 0.009 +/- 0.006 pCi/g (a) When two LLD values are listed, the required LLD per the PBNP REMP is enclosed in the parentheses. Whenever possible, PBNP uses the lower value to obtain greater sensitivity.

(b) "ND" indicates that the sample result is Not Detectable, i.e., sample concentrations were statistically equal to zero or <MDA.

Other gamma emitters typically refer to Co-60 if not specifically called out in the analyses. See explanation on page 1 of the Environmental Inc, report which is Appendix A 38

Table 10-2 ISFSI Fence TLD Results for 2012 Fence Location Average + Standard Deviation Units North 2.59 + 0.27 mR/7 days East 3.27 + 0.96 mR/7 days South 1.40 + 0.19 mR/7 days West 4.92 + 0.40 mR/7 days 39

11.0 DISCUSSION 11.1 TLD Cards The ambient radiation was measured in the general area of the site boundary, at an outer ring four - five miles from the plant, at special interest areas, and at one control location, roughly 17 miles southwest of the plant. The average indicator TLD is 1.17 +/- 0.17 mR/7-days compared to 1.14 +/- 0.07 mR/7-days at the background location. These two values are not significantly different from each other. Neither are the indicator TLD values significantly different from those observed from 2001 through 2011 for the same type of TLD (tabulated below in Table 11-1). Prior to third quarter of 2001 TLD LiF chips were used versus the current TLD cards, see Section 9.7.6 for additional information).

Table 11-1 Average Indicator TLD Results from 1993 - 2012 Year Average _ St. Dev* Units 1993 0.82 + 0.15 mR/7 days 1994 0.90 + 0.12 mR/7 days 1995 0.87 + 0.13 mR/7 days 1996 0.85 + 0.12 mR/7 days 1997 0.87 +/- 0.11 mR/7 days 1998 0.79 +/- 0.13 mR/7 days 1999 0.79 +/- 0.21 mR/7days 2000 0.91 + 0.15 mR/7 days 2001 1.06 + 0.19 mR/7 days 2002 1.17 + 0.21 mR/7 days 2003 1.10 + 0.20 m R/7 days 2004 1.10 + 0.22 m R/7 days 2005 1.04 +/- 0.21 mR/7 days 2006 1.14 + 0.21 mR/7 days 2007 1.08 + 0.20 mR/7 days 2008 1.05 + 0.17 mR/7 days 2009 1.08 +/- 0.17 mR/7 days 2010 1.11 +/- 0.15 mR/7 days 2011 1.14 +/- 0.50 mR/7 days 2012 1.17 +/- 0.17 mR/7 days

• St. Dev = Standard Deviation There were nine new dry fuel storage cask additions to the ISFSI in 2012 (2 in June, 5 in July, 2 in August). The west fence TLDs continue to record higher exposures. The north and east fence TLDs are statistically equal at the 95% confidence level (2.59+/- 0.55 vs. 3.27+/- 1.92). The south fence continues to record the lowest exposures (Table 11-2). Due to the placement and orientation of the new storage modules, the doses measured at the fence increased by roughly 20% to 90% from the second quarter to the fourth quarter with the biggest increase observed at the east fence: 2.62 mR/7-days to 4.51 mR/7-days.

40

Table 11-2 Average ISFSI Fence TLD Results (mR/7 days)

I TLD FENCE LOCATION North East South West 1995 1.29 1.28 1.10 1.26 1996 2.12 1.39 1.10 1.68 1997 2.05 1.28 1.00 1.66 1998 2.08 1.37 1.02 1.86 1999 2.57 1.84 1.11 3.26 2000 2.72 2.28 1.25 5.05 2001 2.78 2.54 1.36 6.08 2002 2.79 2.74 1.42 6.46 2003 2.70 2.60 1.50 6.88 2004 2.61 2.12 1.41 6.50 2005 2.54 2.05 1.44 5.63 2006 2.73 2.35 1.38 5.80 2007 2.72 2.73 1.34 5.47 2008 2.64 2.37 1.36 5.36 2009 2.36 2.35 1.20 4.63 2010 2.64 3.02 1.41 5.05 2011 2.44 2.62 1.31 4.75 2012 2.59 3.27 1.40 4.92 There is no significant exposure impact on the TLD monitoring locations around the ISFSI (Table 11-3). The results continue to be higher at E-03 and E-31 which are west of the ISFSI corresponding to the higher exposure at the west fence.

As expected, the values at E-03, being closer to the ISFSI, are higher than those at E-31 located at the site boundary (see Figs. 9-1 and 9-2 for locations). The results for the two locations nearest the site boundary (E-31, 1.21 + 0.34; E-32, 1.39 +/- 0.15) are higher than at the background site E-20 (1.11 +/- 0.14) but comparable at the 95% confidence level, indicating a small, but not significant, increase in ambient gamma radiation at the site boundary due to the operation of the ISFSI.

Further data supporting this conclusion is the comparison of the TLD results at selected locations around the ISFSI before and after the storage of spent fuel at the ISFSI (Figure 11-1). As stated in Section 9.7.6, the TLD values increased by 14% in the second half of 2001 when the TLD monitoring devices were changed from LiF chips in the first half of the 2001 to calcium sulfate impregnated TLD cards. After that initial change, the measured radiation exposure, as measured by the TLD cards, has remained fairly constant with a slight increase with the addition of stored fuel at the ISFSI. The results from E-30 continue to be lower than the results from E-31 even though E-30 is closer to the ISFSI than E-31.

Each year the variations in the TLD results appear to move in concert with each other and with the background site, E-20, which is 17 miles south west of the ISFSI.

41

Therefore, the TLD monitoring results indicate that there is little or no effect on the ambient gamma radiation from the operation of the plant. Data supporting this conclusion is the comparison of TLD results for the first half of 2001 with the last half of 2001. As previously mentioned, for the last two quarters of 2001, the LiF TLD chips were replaced with calcium sulfate impregnated Teflon TLD cards which resulted in a higher reported background exposure (Figure 11-1).

Figure 11-1 ISFSI AREA TLD RESULTS (1995 -2012) 1.8

• E-03 1.6 1.4

• E-28 1.2 E-29 1

x E-30 0.8 E 0.6 + E-31 0.4 *E-32 0.2 + E-20 0

1990 1995 2000 2005 2010 2015 YEAR Table 11-3 Average TLD Results Surrounding the ISFSI (mR/7 days)

Sampling Site E-03 E-28 E-29 E-30 E-31 E-32 E-20 Pre-Operation* 0.93 0.87 0.87 0.81 0.93 0.98 0.88 1996 0.87 0.78 0.81 0.79 0.93 1.00 0.78 1997 0.91 0.89 0.84 0.84 0.89 0.97 0.79 1998 0.82 0.68 0.80 0.82 0.91 0.85 0.77 1999 0.88 0.83 0.76 0.80 0.90 0.99 0.78 2000 0.98 0.88 0.92 0.99 0.98 1.06 0.90 2001 1.31 0.95 1.07 1.02 1.10 1.04 1.03 2002 1.45 0.91 1.22 1.10 1.26 1.25 1.14 2003 1.29 0.82 0.94 1.02 1.20 1.15 0.99 2004 1.35 0.80 0.96 1.05 1.23 1.18 1.06 2005 1.30 0.72 0.96 0.98 1.15 1.04 1.00 2006 1.44 0.80 1.19 1.07 1.21 1.07 1.11 2007 1.37 0.78 1.07 1.05 1.18 0.97 1.05 2008 1.33 0.75 0.81 1.00 1.12 1.03 1.00 2009 1.39 0.82 0.85 1.01 1.17 1.05 1.09 2010 1T 0784 5. 1.07 1T2T 1.24 1.10 2011 1.4 6 070 0.90 1.6 1.25 .2 1 2012 1.54 0.91 58 1.1 1.21 19 114

• Pre-Operational data are the averages of the years 1992 through 3rd quarter of 1995.

• • Sites E-31 and E-32 are located at the Site Boundary to the West and South-West of the ISFSI.

• • • E-20 is located approximately 17 miles WSW of the ISFSI.

42

11.2 Milk Naturally occurring potassium-40 (1431 +/- 70 pCi/I) continues to be the most prevalent radionuclide measured in milk at concentrations roughly 1800 times higher than the only potential plant related radionuclide, Sr-90 (0.7 +/- 0.8 pCi/I),

detected in milk. The annual average Sr-90 concentrations in milk continue to be similar to previous years. None of the other required radionuclides in the milk analyses, 1-131, Cs-1 34/137, Ba-La-140, and Co-60 were detected.

Though similar to previous years, the Strontium-90 results show a logarithmic decrease over time (Figure 11-2). The environmental half-life of Sr-90 calculated using the annual average Sr-90 concentrations in milk between 1997 and 2012 is 19.3 years. Because the radiological half-life is 28 years, the shorter environmental half-life indicates that environmental factors as well as radioactive decay are working to decrease the concentration of Sr-90 in milk. The calculated physical removal half-life is 59.3 years. This indicates that the radiological Figure 11-2 Sr-90 Concentration in Milk Sr-90 in Milk 10 n

C.

0 0

0 0.

Year half-life dominates the decrease of Sr-90 in the milk samples obtained around PBNP. The Sr-90 in milk persists due to cycling in the biosphere after the atmospheric weapons tests of the '50s, '60s, and '70s and the Chernobyl accident in the late 1980s. Therefore, it is concluded that the milk data for 2012 show no radiological effects of the plant operation.

11.3 Air The average annual gross beta concentrations (plus/minus the two-sigma uncertainty) in weekly airborne particulates at the indicator and control locations were 0.026 +/- 0.020 pCi/m 3 and 0.026 +/- 0.022 pCi/m 3, respectively, and are similar to levels observed from 1993 through 2011 (Table 11-4).

43

Table 11-4 Average Gross Beta Measurements in Air 1993 0.022 1994 0.022 1995 0.021 1996 0.021 1997 0.021 1998 0.022 1999 0.024 2000 0.022 2001 0.023 2002 0.023 2003 0.023 2004 0.021 2005 0.024 2006 0.021 2007 0.025 2008 0.023 2009 0.025 2010 0.022 2011 0.026 2012 0.026 The 2012 weekly gross beta concentrations reveal higher winter values and lower summer values (Figure 11-3). This is a repeat of the patterns seen in 2006 - 2011. What appears as new during 2012 is greater week-to-week scatter in August and in November through December. The cause of the scatter is not known. However, the control and indicators are moving in concert. Therefore, a plant effect can be ruled out.

Figure 11-3 2012 Airborne Gross Beta 0.070 -

0.060 -

0.050 ,

0.040-0.

0.030 E-01 0.020-- E-02 0.010 E-03 0.000 --4-- E-04

, ,, , --- E-08 D'.t" ' " "7 E-20 Date 44

In 2005, the new method of evaluating airborne 1-131 was instituted. Instead of counting each charcoal cartridge separately, all six cartridges for the week are counted as one sample in a predetermined geometry to screen the samples for 1-131. If any airborne radioiodine is detected, each sample cartridge is counted individually. With no detectable 1-131, the reported analytical result is the minimum detectable activity (MDA) conservatively calculated using the smallest of the six sample volumes. The reported MDAs ranged from 0.005 to 0.020 pCi/m 3 . Because the analysis LLD is based on counting only one cartridge, the use of six cartridges or roughly six times the sample volume with the same count time as would be needed to achieve the desired LLD for only one sample, the actual LLD is about six times lower than the programmatic value given in Table 10-1. Similarly, the actual MDA is about one-sixth of that reported, or in the range of 0.001 to 0.003 pCi/m 3 .

At each sampling location, the particulate filters are composited quarterly and analyzed for Cs-134, Cs-137 and any other (Co-60) detectable gamma emitters.

As summarized in Table 10-1, only Co-60 had a positive indication. One of the two positive results occurred at E-01 in the first quarter when no airborne Co-60 was emitted. The second Co-60 detection was in the 4th quarter at E-20, the background site some 17 miles from PBNP. Co-60 was emitted in November.

However, it was not detected at E-01, the location closest to PBNP. Based on the time and location of the positive Co-60 results it is concluded that these two events are false positives. No other gamma emitter that may be indicative of PBNP effluent was detected. By contrast, naturally occurring Beryllium-7 was found in all of the quarterly composites. Be-7 (T1/2= 53.3 days) is produced in the atmosphere by the interaction of cosmic rays with oxygen and nitrogen nuclei. Its half-life is long enough to allow for it to be detected in the quarterly composited filters.

In summary, the 2012 air data does not demonstrate an environmental impact from the operation of PBNP.

11.4 Lake Water For the REMP-specified gamma emitting radionuclides listed in Table 10-1, reported concentrations continue to occur as small, negative and positive values scattered around zero, indicating no radiological impact from the operation of PBNP. Lake Michigan water samples are collected north (E-33 and E-05) and south (E-01 and E-06) of PBNP (see Figure 9-1).

There were 21, slightly positive indications of gamma emitters during 2012.

None of the concentrations were equal to or greater than their MDC. Seven positive results occurred at the two locations 1.5 and 4.5 miles north of the plant.

These locations are considered to be upstream based on the north to south current flow on the west shore of Lake Michigan and therefore are very unlikely to be an indication of PBNP effluent. Of the remaining fourteen occurrences, twelve are for radionuclides not discharged the months they had a positive indication in Lake Michigan. Ba-La-140, a short half-life radionuclide not discharged from PBNP during 2012 shows up most frequently (9 of the 21) as a small positive result. In each case, the highest measured concentration is about 45

100 times higher than the corresponding discharge concentration. Because the positive concentrations measured in the lake are higher than the discharge concentrations and because any discharges would be further diluted by mixing in the lake, the observed positive concentrations are considered to be false positives. Based on the results of the gamma scans of Lake Michigan water, there is no measureable impact on the lake from PBNP discharges.

Aliquots of the monthly samples are composited quarterly and analyzed for Sr-89/90 and for tritium. No Sr-89 was detected in any of the samples.

There were nine lake water composites in which the Sr-90 concentration were slightly positive but below the MDC. Four of these occurrences were about five miles north of PBNP and "upstream" with respect to the average current direction in this area of the lake. Because PBNP discharged no Sr-90 during 2012, these results are considered to be either false positives or the indication of persisting low levels of Sr-90 in the lake which resulted from fallout from atmospheric weapons testing in the1950s and 1960s.

Tritium, in addition to being produced by water-cooled reactors such as PBNP, also is a naturally occurring radionuclide. The quarterly composite lake water samples collected and analyzed for H-3 in 2012, ranged from non-detectable to 1,192 pCi/l. This high occurred in the second quarter at a location about 5 miles north of the plant, E-33. Tritium analyses of the individual months in this quarter indicated that H-3 was non-detectable in April and May but that the June lake water sample had a tritium concentration of 3,975 + 197 pCi/I. Similarly, a high of 904 +/- 114 pCi/I occurred in the third quarter composite sample from a site about two miles north of the plant, E-05. Analyses of individual months found the August sample had a tritium concentration of 2184 +/- 159, whereas H-3 was not detectable in July (39 +/- 85) and slightly positive in September (372 +/- 100 pCi/I).

Both locations are considered to be up-current from PBNP based on the currents on the west side of Lake Michigan. As a check for the third quarter, the individual months at E-01 located a few hundred feet downstream (south) of the discharge were analyzed for H-3. All three H-3 results were not detectable (x -2a < 0).

Based on tritium and strontium analyses of Lake Michigan water, there is no measureable impact on the waters of Lake Michigan from PBNP discharges.

11.5 Ala Filamentous algae attached to rocks along the Lake Michigan shoreline are known to concentrate radionuclides from the water. Samples were obtained at Two Creeks Park and at the PBNP discharge (locations 5 and 12 in Figure 9-1) in June, August, and October. Cs-137 was detected in all six samples. Four of the six samples had measureable Cs-1 37 concentrations which were above the MDC. The positive results occurred at the PBNP discharge and at E-05 north of the plant. Because PBNP did not discharge any Cs-137 until November, the positive results are attributable to the recycling of bomb fallout, from weapons testing in the '50s, 60's and other nuclear events such as Chernobyl, in the Lake Michigan environment.

46

PBNP discharged Co-60 and Co-58 every month in 2012. Two, small positive indications were found, Co-58 at 0.010 +/- 0.006 pCi/g (MDA = 0.011) and Co-60 at 0.007 +/- 0.006 pCi/I (MDA = 0.010) at site E-05 about two miles north of the PBNP discharge. No radio-cobalt was detected near the discharge. Because these results occurred at an "upstream" location and were below the minimum detectable concentration, these Co-60 results are considered to be false positives.

The Cs-137 results are well below the naturally occurring radionuclides Be-7 and K-40. The concentrations of these two radionuclides range from 0.48 +/- 0.07 to 1.65 +/- 0.17 pCi/g for Be-7 and from 2.99 +/- 0.29 to 6.08 +/- 0.33 pCi/g for K-40.

The naturally occurring radionuclides K-40 and Be-7 were at concentrations about 100 times higher than Cs-1 37. K-40 is primordial isotope of potassium with a billion year half-life. By contrast Be-7 is produced by cosmic ray interactions with oxygen and nitrogen atoms in the atmosphere.

Based on the low concentrations of Cs-1 37, the algae monitoring results indicate no effect by PBNP upon the environs.

11.6 Fish Seventeen fish were analyzed in 2012. Of the 17 fish, 12 of the fish were positive for Cs-137 with results greater than the MDC. The positive Cs-137 concentrations ranged from a low of 0.015 +/- 0.012 pCi/g to a high of 0.074 _

0.023 pCi/g (Table 10-1). As PBNP did not discharge any Cs-137 in the months prior to the detection of Cs-1 37, the Cs-1 37 is attributable to the recycling of this radionuclide in Lake Michigan. The majority of Cs-137 entered Lake Michigan as fallout from atmospheric weapons testing in the '50s and '60s with lesser amounts from events at Chernobyl and Fukushima.

Small amounts of Fe-59, Co-58, Co-60, Zn-65, and Ru-103 also were detected.

The Fe-59, Zn-65, and Ru-1 03 two are not attributable to plant operations as PBNP did not release any Ru-103 during 2012 and PBNP did not release any Fe-59 and Zn-65 until November whereas Fe-59 and Zn-65 detection occurred in January and July respectively.

By comparison to the aforementioned radionuclides, the concentration of naturally occurring K-40 (2.06- 3.47 pCi/g) is about 10 times higher than the highest Cs-1 37 concentration.

Based on these results, it is concluded that there is only a slight indication of plant effluents in fish.

11.7 Well Water No plant related radionuclides were detected in well water during 2012, as all results were less than the MDC and not significantly different from zero. The gross beta values result from naturally occurring radionuclides. Therefore, it is concluded that there is no evidence of PBNP effluents getting into the aquifer supplying drinking water to PBNP.

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11.8 Soil Cs-1 37 is present in the soils throughout North America and the world resulting from the atmospheric nuclear weapons testing in the 1950s, 1960s, and1970s and from the 1986 Chernobyl accident, and more recently, from the Fukushima event. Soil is an integrating sample media, in that it is a better indicator of long term buildup of Cs-1 37 as opposed to current deposition for local sources. Soil erosion, radioactive decay, and human activities modify the Cs-1 37 concentrations. Evidence for the latter are the typically higher Cs-137 concentrations found at E-06, where trees growing and incorporating Cs-1 37 during the time of atmospheric fallout are now being burned in camp fires thereby releasing the incorporated Cs-1 37 to the surrounding area. All 2012 samples had low levels of Cs-1 37 with the highest level (0.39 +/- 0.04 pCi/g) being found at E-03 and the second highest (0.26 +/- 0.03) occurring at E-06. The average results (0.12 +/- 0.02 pCi/g) from the remaining indicator sites are comparable to the concentration (0.12 +/- 0.05 pCi/g) at the background site some 17 miles away in the low x/Q sector. This is expected for the source of Cs-1 37 being atmospheric fallout as discussed above. Therefore, there is no indication of a plant effect based on the comparison of indicator and background results. By comparison to naturally occurring radionuclides, the Cs-137 concentrations continue to be present in soil samples at well below levels of naturally occurring K-40 (5.74 +/- 0.39 to 23.33 +/- 1.52 pCi/g).

11.9 Shoreline Sediment Shoreline sediment consists of sand and other sediments washed up on the Lake Michigan shore. As in soil samples, the only non-naturally occurring radionuclide found in these samples is Cs-1 37. All ten samples have Cs-1 37 concentrations statistically different from zero. The shoreline sediment Cs-1 37 concentrations continue to be about one-tenth of that found in soils. This is expected because Cs-1 37 in the geological media is bound to fine particles, such as clay, as opposed to the sand found on the beach. Lake Michigan sediments are a known reservoir of fallout Cs-1 37. Wave action suspends lake sediments depositing them on the beach. The fine particles deposited on the beach eventually are winnowed from the beach leaving the heavier sand; hence the lower Cs-1 37 concentrations in beach samples. In contrast to Cs-1 37, K-40, which is actually part of the minerals making up the clay and sand, is at a concentration about 300 times higher than the Cs-1 37 that is attached to particle surfaces. Therefore, it is not surprising that Cs-1 37 is present at concentrations 1% or less of the naturally occurring concentrations of K-40. The absence of any PBNP effluent nuclides, such as Co-58/60, other than Cs-1 37 indicates that the most likely source of the observed Cs-1 37 is the cycling of radionuclide in the Lake Michigan environment and not current PBNP discharges. Therefore, the shoreline sediment data indicate no radiological effects from current plant operation.

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11.10 Vegetation The naturally occurring radionuclides Be-7 and K-40 were found in all of the vegetation samples. The source of Be-7 is atmospheric deposition. It is continuously formed in the atmosphere by cosmic ray spallation of oxygen, carbon, and nitrogen atoms. (Spallation is a process whereby a cosmic ray breaks up the target atom's nucleus producing a radionuclide of lower mass.)

Be-7 concentrations ranged from 0.17 +/- 0.06 to 3.62 +/- 0.32 pCi/g. The concentrations were lower in May than in July and September. This is consistent with the known temporal variability in Be-7 concentrations in air near the earth's surface. In contrast, K-40 is a primordial radionuclide which is incorporated into vegetation from the soil during the growing process. By not being dependent upon seasonal atmospheric variations and plant surface to capture deposition, the K-40 concentrations are more uniform, 3.22 + 0.34 to 7.66 +/- 0.21 pCi/g which is range that varies by about a factor of two whereas the Be-7 varies by a factor of roughly 20.

Cs-137 can be present in vegetation via both pathways. Fresh Cs-137 fallout is associated, like Be-7, with deposition on the plant surface. Old fallout from the

'50s and '60s is now being incorporated into growing plants in the same manner as potassium because it is in the same chemical family as potassium. This fallout Cs-1 37 has been found in firewood ash at many locations in the United States that are far from any nuclear plants (S. Farber, "Cesium-1 37 in Wood Ash, Results of a Nationwide Survey," 5th Ann. Nat. Biofuels Conf., 10/21/1992).

In 2012 only three of the twenty-four vegetation samples had a positive indication for Cs-1 37 and only one of these (E-06, 0.051 +/- 0.022, MDC = 0.021 pCi/g) was detected above the MDA. Typically, only the vegetation collected at monitoring site E-06, in the Point Beach State Park south of PBNP, has detectable levels of Cs-137. In 2012, Point Beach released airborne Cs-1 37 only in November. All of the positive indications occurred prior to that month. Therefore, it is unlikely that the three positive Cs-1 37 values resulted from PBNP releases.

The only other radionuclides having positive indications were 1-131 and Co-60.

PBNP released airborne 1-131 in July and November and Co-60 only in November of 2012. The July radioiodine release included 1-133 which was not detected in any samples. All the vegetation results were below their respective MDAs. Therefore the small, positive results for these two radionuclides which occurred between May and October are considered to be false positives.

Based on the 2012 vegetation sampling results, it is concluded that there little or no effect from PBNP effluents.

11.12 Land Use Census In accordance with the requirements of Section 2.5 of the Environmental Manual, a visual verification of animals grazing in the vicinity of the PBNP site boundary was completed in 2012. No significant change in the use of pasturelands or grazing herds was noted. Therefore, the existing milk-sampling program 49

continues to be acceptable. The nearest dairy lies in the SSE sector and it is one of the PBNP REMP milk sampling sites. This dairy leases land in the S and SSE sectors at the PBNP site boundary for growing feed corn. Also, the highest X/Q (1.09E-06) and D/Q (6.23E-09) values occur in these sectors. Therefore, dose calculations to the maximum exposed hypothetical individual, assumed to reside at the site boundary in the S sector, continues to be conservative for the purpose of calculating doses via the grass-cow-milk and the other ingestion pathways.

12.0 REMP CONCLUSION Based on the analytical results from the 828 environmental samples, and from 128 sets of TLDs that comprised the PBNP REMP for 2012, PBNP effluents had no discernable effect on the surrounding environs. The calculated effluent doses are below the 10 CFR 50, Appendix I dose objectives demonstrate that NextEra continues to have good controls on effluent releases. The control of effluents from PBNP continues to be acceptable pursuant to the ALARA criteria of 10 CFR 50.34a. Additionally, when the TLD results are factored in to the overall exposure, the resulting doses are lower than the ISFSI (10 CFR 72.104) and EPA (40 CFR 190) limits of 25 mrem whole body, 75 mrem thyroid, and 25 mrem any other organ.

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Part D GROUNDWATER MONITORING 13.0 PROGRAM DESCRIPTION PBNP monitors groundwater for tritium as part of the Groundwater Protection Program (GWPP). During 2012, the sampling program consisted of beach drains, intermittent stream and bog locations, drinking water wells, fagade wells, yard electrical manholes, ground water monitoring wells, and the subsurface drainage (SSD) system sump located in the U-2 fagade.

In the late 1970s, the beach drains entering Lake Michigan were found to contain tritium.

The beach drains are the discharge points for yard drainage system, which carries storm water runoff, and are known to be infiltrated by groundwater as observed by discharges even when no rain has occurred. In the 1980s, the source of H-3 for this pathway was postulated to be spent fuel pool leakage into the groundwater under the plant. Based on this observation, modifications were made to the pool, and the tritium concentrations decreased below the effluent LLDs. Beach drain effluents continue to be monitored and are accounted for in the monthly effluent quantification process. Because the beach drains are susceptible to groundwater in-leakage from other sources such as the area around the former retention pond which is known to contain H-3, the beach drains are monitored as part of the groundwater monitoring program.

Three intermittent stream locations and the Energy Information Center (EIC) well were added to the groundwater monitoring program in the late 1990s when it was discovered that tritium diffusion from the then operable, earthen retention pond was observable in the intermittent streams which transverse the site in a NW to SE direction. A fourth stream location closer to the plant was added in 2008. These streams pass on the east and west sides of the former retention pond and empty into Lake Michigan about half a mile south of the plant near the meteorological tower. The intermittent stream samples track H-3 in the surface groundwater.

The groundwater monitoring program also includes two bogs / ponds on site. One is located about 400 feet SSE of the former retention pond; the other, about 1500 feet N.

In addition to the main plant well, four other drinking water wells also are monitored. The Site Boundary Control Center well, located at the plant entrance, the Warehouse 6 well, on the north side of the plant, and the EIC well, located south of the plant. In 2012, a new building (Warehouse 7) was constructed for radwaste. The well for this building was added to the GWPP. These wells do not draw water from the top 20 - 30 feet of soil which is known to contain H-3. These wells monitor the deeper (200 - 600 feet), drinking water aquifer from which the main plant well draws its water. The two soil layers are separated by a gray, very dense till layer of low permeability identified by hydrological studies.

Manholes in the plant yard and for the subsurface drainage (SSD) system under the plant are available for obtaining ground water samples. The plant yard manholes for accessing 51

electrical conduits are susceptible to ground water in-leakage. Therefore, a number of these were sampled. The SSD system was designed to lessen hydrostatic pressure on the foundation by controlling the flow of water under the plant and around the perimeter of the foundation walls. The SSD system flows to a sump in the Unit 2 facade. The sump was sampled monthly during 2012. Access to other parts of the SSD can be obtained vial manholes located in the facades, turbine building, and other locations. The SSD manholes were not sampled in 2012.

In the 1990s, two wells were sunk in each unit's fagade to monitor the groundwater levels and look for evidence of concrete integrity as part of the ISI IWE Containment Inspection Program. These wells are stand pipes which are sampled periodically for chemical analyses. Beginning in 2007, samples for the GWPP also are being taken. These wells are sampled at least three times a year.

The groundwater sampling sites (other than the beach drains, SSDs and manholes) are shown in Figure 13.1.

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53 14.0 RESULTS AND DISCUSSION 14.1 Streams and Bogs The results from the surface groundwater monitoring associated with the former retention pond are presented in Table 14-1. For the most part, the creek results are barely above the detection level and less than the MDC. There are more positive and higher values for the East Creek and STP than for the West Creek and GW-01, the confluence of the two creeks south of the plant near Lake Michigan. GW-08, a bog SE of the former retention pond has a higher H-3 concentration than the bog at GW-07 which is north of the pond area.

Table 14-1 Intermittent Streams and Bogs Tritium Concentration (pCi/I)

Month GW-01(E-01) GW-02 GW-03 GW-17 BOGS MDC Creek Confluence E. Creek W. Creek STP GW-07 GW-08 Jan ND + 243 +/- 88 ND +/- 177 +/- 85 145 Feb ND + 224 +/- 84 ND +/- 171 +/- 81 146 Mar ND +/- 204 +/- 90 89 +/- 85 210 +/- 91 152 Apr ND +/- 179 +/- 85 82 +/- 80 167 +/- 85 153 May 120 +/- 87 ND +/- 94 +/- 85 116 +/- 86 110 +/- 80 297 - 89 148 Jun ND +/- 111 +/- 77 103 +/- 77 109 +/- 77 148 Jul ND +/- 136 +/- 84 ND +/- ND +/- 156 Aug 104 +/- 96 135 +/- 97 99 +/- 96 97 +/- 95 150 Sep 109 +/- 86 179 +/- 89 ND +/- 311 +/- 95 153 Oct ND +/- 193 +/- 89 ND +/- 152 +/- 87 152 Nov ND +/- 122 +/- 82 83 +/- 80 181 +/- 85 144 Dec ND +/- 97 +/- 81 ND +/- ND +/- 145 NF = no flow: Streams are sampled monthly; bogs, annually.

Values are presented as the measured value and the 95% confidence level counting error.

ND = measured value is less than the minimum detectable concentration. The LLD = 200 pCi/l.

The analyses of these surface water samples show low concentrations of H-3.

Although small positive H-3 concentrations occur in samples from the confluence of the two creeks (GW-01) and from the West Creek (GW-03), all of these concentrations are below their associated MDCs. In contrast, results from GW-03 (south end of East Creek) and GW-17 (located at the north end of the East Creek) are more strongly positive and have at least six samples of their result above the MDC. The East Creek concentrations are generally lower than the 300 - 350 pCi/I found before the retention pond was remediated in 2002. It should be noted that the East Creek, in addition to being path of the west to east groundwater flow from the old retention pond, also is fed by yard runoff from the west side of the yard.

The bog (GW-08) SE of the former retention pond is higher than the bog at GW-07 north of the former retention pond. These results are in conformance with the west to east groundwater flow described in the Site Conceptual Model and the FSAR. The E-08 bog result is down from the 3000 pCi/I seen before the pond was remediated.

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14.2 Beach Drains and SSD Sump The 2012 results for the beach drains are presented in Table 14-2. [The drain data from left to right in the table are in the order of the drains from north to south.] S-1 collects yard drainage from the north part of the site yard; S-3, from the south part of the site yard. Note that S-1 no longer receives the output from the SSD sump located in the Unit 2 fagade. Drains S-8 and S-9 carry water from the lake side yard drains whereas drains S-7 and S-10 are from the turbine building roof. S-1 1 is not connected to any yard drain system and mainly carries groundwater flow and runoff from a small lawn area south of the plant.

Table 14-2 2012 Beach Drain Average Tritium Concentration (pCi/I)

Month S-1 S-7 S-8 S-9 S-10 S-3 S-11 MDC Jan 248+/- 85 NF + NF +/- NF t NF +/- 381 +/- 91 NF +/- 145 Feb 132+/- 92 NF +/- NF +/- NF +/- NF +/- 338+/- 101 NF +/- 142 Mar 157 +/- 83 NF +/- NF +/- NF +/- NF +/- 533 +/- 100 269 +/- 88 143 Apr 246+/- 92 NF +/- NF +/- NF +/- NF +/- 239+/- 91 ND +/- 152 May 191 +/- 84 NF +/- NF +/- NF +/- NF +/- 287+/- 88 114+/- 80 148 Jun 278+/- 94 NF +/- NF +/- NF +/- NF +/- 327+/- 96 89+/- 86 135 Jul 118+/- 86 NF +/- NF +/- NF +/- NF +/- 615+/- 108 167+/- 88 152 Aug 171 +/- 81 NF +/- NF +/- NF +/- NF +/- 3367+/- 181 138+/- 80 146 Sep 126+/- 85 NF +/- NF +/- NF +/- NF +/- 395+/- 97 126+/- 85 149 Oct 111 +/- 100 NF +/- NF +/- NF +/- NF +/- 268+/- 92 ND +/- 157 Nov 273+/- 106 NF +/- NF +/- NF +/- NF +/- 273+/- 106 ND +/- 183 Dec 185+/- 83 NF +/- NF +/- NF +/- NF +/- 301 +/- 89 110+/- 80 149 Avg= 186+/- 123 1 610+/- 1751 145+/- 120 ND = not detected and <MDC S-3 avg. without Aug.-> 360 +/- 117 NF = no sample due to no flow Unlike 2011, there were no beach drain H-3 concentration peaks at >1000 pCi/I at S-1 and S-3 during January - March of 2012. There is a slightly higher value during March at S-3 but not as high as in 2011. This may be attributable because at that time it was believed that the S-1 peak to be caused by the discharge of the subsurface drainage system (SSD) into the yard drains emptying into Lake Michigan at S-1. While that may have been a contributing factor, it did not explain the concurrence with the S-3 peak. Based on the completed H-3 washout/recapture study, it is now concluded that recapture of airborne H-3 discharges by snow followed by snow melting is the result of the concurrent, elevated H-3 concentrations found at S-1 and S-3. During February and March snow was melted on site and discharged via the yard drains. The reason for the higher H-3 concentrations at S-3 for the remainder of the year also may be related to washout and recapture. The washout study results will be discussed in more detail later in this section.

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The SSD sump is located in the Unit 2 fagade and its contents are discharged via the wastewater effluent line. The monthly sump results are p-resented in Table 14-3.

Table 14-3 2012 Unit 2 Facade SSD Sump Monthly Tritium Concentration (pCi/I)

Month Avg 2a MDC Jan 479 +/- 100 147 Feb 534 +/- 96 142 Mar 366 +/- 93 142 Apr 470 +/- 107 143 May 327 +/- 96 154 Jun 511 +/- 101 147 Jul 527 +/- 100 142 Aug 470 +/- 104 158 Sep 735 +/- 114 157 Oct 369 +/- 109 183 Nov 620 +/- 101 139 Dec 748 +/- 105 139 Average 513 +/- 269 14.3 Electrical Vaults and Other Manholes Manholes for access to below ground electrical facilities are susceptible to groundwater in-leakage. The manholes east side of the plant, between the Turbine building and Lake Michigan have low H-3 concentrations (Table 14-4).

These manholes, Z-066A and Z-067A through Z-066D AND Z-067D, run in parallel in the NE section of the yard beginning just north of the Unit 2 truck bay and run from the Unit 2 truck bay north to the EDG building. Z-068 is located just west of the EDG building. Based on being side-by-side, it is not unexpected that the each pair of manholes 66A/67A, etc. would have similar H-3 concentrations.

It is interesting to note that the highest concentrations occur near the time that beach drains S-1 and S-2 also have their highest H-3 concentration.

Table 14-4 2012 East Yard Area Manhole Tritium Concentration(pCi/l)

MH 5/16/2012 10/25/2012 Z-066A 208 +/- 87 102 +/- 100 Z-067A 137 +/- 84 141 +/- 101 Z-066B 119 +/- 83 ND +/-

Z-067B 83 +/- 81 ND +/-

Z-066C 127 +/- 83 ND +/-

Z-067C 289 +/- 91 171 +/- 102 Z-066D 321 +/- 92 186 +/- 88 Z-067D 206 +/- 87 230 +/- 90 Z-068 279 +/-90 97 +/- 83 MDC 146 158 ND = not detected 56

14.4 Facade Wells The four fagade wells monitor the H-3 concentration under the plant footprint (Table 14-5). Each unit's fagade has two wells used to monitor the groundwater for conditions which could impact containment integrity. Samples from these wells also are analyzed for H-3 (Table 14-5). In Unit 2 there is one well on each side of containment, approximately 1800 apart. The Unit 1 fagade wells are east of the containment in the SE (1Z-361A) and NE (1Z-361 B) corners of the fagade.

The 2012 results are similar to those obtained in previous years. The Unit 1 wells continue to have higher H-3 concentrations than the U2 wells with 1Z-361A, in the SE corner of the Unit 1 fagade, having the highest H-3 concentrations.

The 2012 high is comparable to the 1169 - 1331 pCi/I tritium concentrations of 2007 and 2008. Reanalysis confirmed the high 1Z-361A result. The origin of this peak is not known. Based on these results, the conclusion that H-3 is not evenly distributed under the plant remains valid.

Table 14-5 2012 Facade Well Water Tritium Concentration (pCi/I)

UNIT I UNIT 2 Date IZ-361A 1Z-361B 2Z-361A 2Z-361B MDC 27-Jan 154 +/- 79 ND +/- ND +/- ND + 142, 7-Mar 282 +/- 89 ND +/- 123 +/- 81 164 +/- 83 142 7-Mar 190 +/- 91 ND +/-

30-Mar 257 +/- 98 100 T 91 ND 112 92 143 T-May 212 +/- 91 ND +/- Tr ND -7154 71-un 158 ++/-85 ND +/- ND7 66 86 147 11-Jul 404 +/- 94 354 +/- 92 ND +/- 171 + 84 142 1-Sep 1342 +/- 135 345 +/- 99 ND +/- ND +/- 157 29-Sep 191 +/- 103166 +/- 103 ND +/- ND +/- 184 1-NTov 263 +/- 88 ND +/- ND +/- ND +/- 152 71F-N =37 150 +/- 86 1+ _N++ 151 29-Dec 255 +/- 85 160 +/- 81 89 + 77 ND 138 ND = not detected 14.5 Potable Water and Monitorinq Wells Outside of the protected area, ten wells, in addition to the main plant well (Section 11.7), are used for monitoring H-3 in groundwater: The wells that are monitored are four potable water wells, GW-04 (Energy Information Center

[EIC]), GW-05 (Warehouse 6), GW-06 (Site Boundary Control Center), and GW-18 (Radwaste Facility) along with six H-3 groundwater monitoring wells, GW-1 1 through GW-1 6 (Figure 13-1). The fourth potable water well (GW-1 8) was installed at the new, radwaste facility in 2012 and added to the monitoring program in late May. The potable water wells monitor the deep, drinking water aquifer whereas the monitoring wells penetrate less than 30 feet to monitor the top soil layer. The potable water aquifer is separated from the shallow, surface water aquifer by a thick, impermeable clay layer. Two of the monitoring wells, 57

GW-15 and GW-16, are in the apparent groundwater flow path from the former retention pond. The other four of the surface layer wells are located at the periphery of the area which may be affected by diffusion from the former retention pond. The potable water wells have no detectable H-3 (Table 14-6).

Table 14-6 2012 Potable Well Water Tritium Concentration (pCi/I)

Warehouse SBCC IfL; (3w-UbU6 EIC WELL 6 Well Well MDC MDC WH7 GW-18 Month GW-04 GW-05 GW-06 GW-18 MDC Jan ND ND ND 145 146 NS Feb ND 146 Mar ND 152 Apr ND ND ND 153 143 NS May ND 155 ND 155 Jun ND 148 Jul ND ND ND 156 147 Aug ND 150 ND 150 Sep ND 153 ND 153 Oct ND ND ND 152 151 ND 151 Nov ND 144 Dec ND 145 NU=Not uetected I=No Sample The two monitoring wells showing consistent, detectable H-3 (GW-1 5, GW-1 6) are in the flow path from the retention pond area to the lake (Table 14-7). The highest H-3 concentrations occur at GW-15, the well closest to the former retention pond.

Table 14-7 2012 Quarterly Monitoring Wells Tritium Concentration (pCi/I)

MW-01 MW-02 MW-06 MW-05 MW-04 MW-03 Q GW-11 GW-12 GW-13 GW-14 GW-15 GW-16 MDC 1 ND +/- ND +/- ND +/- ND +/- 263 +/- 86 126 +/- 79 144 2 149 +/- 81 ND +/- 105 +/- 83 134 +/- 81 251 +/- 87 175 +/- 83 152 3 ND +/- ND +/- ND +/- ND +/- 202 +/- 92 208 +/- 92 157 4 ND +/- ND+/- a ND +/- ND +/- 236 +/- 90 149 +/- 86 158 ND= not statistically different from zero.

14.6 AC Condensate The 2011 AMR discussed the recapture of H-3 via precipitation around the plant.

It was demonstrated that H-3 concentrations are higher close to the plant. It also was shown that the condensate from AC units located on the roofs of buildings and within the plant contained high concentrations of H-3. Table 14-8 presents the H-3 concentrations for 2012 from various AC units with the H-3 concentration 58

measured in the closest beach drain, S-3. External samples were obtained from building roofs with duplicates at the South Gate and S Service Building. Unlike previous years, the AC condensate and beach drain samples were taken within a day of each other.

Table 14-8 2012 AC Condensate and Beach Drain Tritium Concentration (pCi/I)

Location H-3 MDC (pCi/I) 2a (pCi/I)

NSB (4th floor) 557 +/- 102 146 Turbine Bldg 66' (Control Rm AC) 998 +/- 118 146 S Service Bldg Roof (1) 5510 +/- 226 146 S Service Bldg Roof (2) 5822 +/- 231 146 South Gate Roof (1) 473 +/- 99 146 South Gate Roof (2) 395 +/- 95 146 Turbine Bldg 8' 602 +/- 104 146 Training Bldg Roof 185 +/- 86 146 Beach Drain S-3 387 +/- 95 146 These results show that the H-3 concentration is higher in the immediate vicinity of Units 1 and 2 (South Service Building and South Gate) than at the Training Building, which is some 800 feet south. The higher concentrations occur within the area of the yard drains feeding beach drain S-3 and support the conclusion that precipitation scavenging and roof drains can account for the H-3 concentrations found in the beach drains. Recapture of Turbine Building exhaust also would contribute to the H-3 seen in the beach drains.

14.7 Biota Tritium Biota near the former retention pond and in its drainage path was analyzed for H-3 to determine whether this material could be used to define the impacted area around the pond. The results proved to be inconclusive. Although positive results were found, none of the results were statistically significant (Table 14-9).

Table 14-9 H-3 IN GRASS AND TREE TRANSPIRED WATER Grass pCi/I 2a MDC East Creek (GW-02) 83 +/- 81 145 GW-17 124 +/- 82 145 Pond NE 126 +/- 83 145 Pond S 81 +/- 81 145 Tree pCi/I 2a MDC

1. 1 branch 1 109 +/- 85 151

1. 1 branch 2 170 +/- 88 151

1. 2 158 +/- 87 151

1. 3 ND +/- 73 59

The grass tritium was higher on the east side of the former -retention pond conforming to the site groundwater flow pattern. The results for the East Creek are higher at the north end (GW-17) than at the south end (GW-02). This may be expected in that GW-1 7 is closer to the retention pond area and in a flow path directly east of the pond. Three of the four tree transpired water samples had positive indications for H-3. Of these, only the second sample from tree #1 was greater than the MDC.

Based on these results it is not possible to determine whether monitoring biota would provide conclusive evidence of groundwater tritium.

15.0 GROUNDWATER

SUMMARY

Groundwater monitoring indicates that low levels of tritium continue to occur in the upper soil layer but not in the deep, drinking water aquifer. These results also indicate that the low levels of tritium are restricted to a small, well defined area close to the plant. Results from precipitation analyses show that airborne H-3 concentrations are higher close to the plant as compared to results at the site boundaries. The observed tritium concentrations in the yard manholes can be explained by the higher H-3 in precipitation close to the plant. In addition to tritium captured by precipitation, the beach drains also receive the H-3 captured in the AC condensate because the condensate drainage is connected to the yard drain system.

Tritium continues in the soil below the plant foundation as evidenced by results from the subsurface drainage system and from the fagade wells.

Except for the monitoring wells downstream from the former retention pond, the monitoring well tritium concentrations are not different from zero. These results conform to the known west-to-east groundwater flow at the site. Therefore, the impact of the flow of tritiated groundwater from the vicinity of the former retention pond toward the lake on the S-3 tritium results as can not be discounted. The impact of this flow would be greater on beach drain S-3 than on S-1 because the eastward flow in the area of S-3 would be less impacted by plant structures than the drainage system feeding beach drain S-1.

In conclusion, the groundwater H-3 concentrations observed at PBNP are below the EPA drinking water standards prior to emptying into Lake Michigan where they will undergo further dilution. All analyses to date indicate that the drinking water contains no tritium. None of the H-3 in the upper soil layer is migrating off-site toward the surrounding population. This is based on the known west-to-east groundwater flow toward Lake Michigan and the negative results from the four wells (GW-1 1 through GW-1 4, Figure 13-1). Additionally, because no H-3 is detected in either the four on-site drinking water wells close to the power block or from the drinking water well at the site boundary, none of the H-3 observed in the upper soil layer has penetrated into the drinking water aquifer to endanger either on-site or off-site personnel.

60

APPENDIX 1 Environmental, Inc. Midwest Laboratory Final Report for the Point Beach Nuclear Plant and Other Analyses Reporting Period: January - December 2012 87 pages follow

xI ATI -A1 IMidwest nvironmental, Laboratory Inc.

700 Landwehr Road - Northbrook, IL60062-2310 phone (847) 564-0700

• fax (847) 564-4517 FINAL REPORT TO NextEra Energy RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

FOR THE POINT BEACH NUCLEAR PLANT TWO RIVERS, WISCONSIN PREPARED AND SUBMITTED BY ENVIRONMENTAL INCORPORATED MIDWEST LABORATORY Project Number: 8006 Reporting Period: January-December, 2012 Reviewed and Approved by Date 03 00(rS Distribution: K. Johansen, 1 hardcopy, 1 e-mail

POINT BEACH NUCLEAR PLANT TABLE OF CONTENTS Section PaQe List o f Ta b les ............................................................................ iii

1.0 INTRODUCTION

................................................................. iv 2.0 LISTING OF MISSED SAMPLES ........................................ v 3 DATA TABLES ................................................................... vi Appendices A Interlaboratory Comparison Program Results ...................... A-1 B Data Reporting Conventions ............................................... B-1 C Sampling Program and Locations ........................................ C-1 D Graphs of Data Trends ........................................................ D-1 E Supplemental Analyses ............................................................ E-1 ii

POINT BEACH NUCLEAR PLANT LIST OF TABLES Title Page Airborne Particulates and Iodine-131 Location E-01, Meteorological Tower .............................................. 1-1 Location E-02, Site Boundary Control Center .................................. 1-2 Location E-03, W est Boundary ...................................................... 1-3 Location E-04, North Boundary ...................................................... 1-4 Location E-08, G . J. Francar Residence ......................................... 1-5 Location E-20, Silver Lake College ................................................. 1-6 Airborne Particulates, Gam m a Isotopic Analyses ....................................... 2-1 Milk ........................................................................................................ 3 -1 W ell W ater ............................................................................................. 4-1 Lake W ater ............................................................................................. 5-1 Lake W ater, Analyses on Q uarterly Com posites ............................................... 6-1 Fis h .................................................................................................................... 7 -1 Shoreline Sedim ents .......................................................................................... 8-1 S oil ..................................................................................................................... 9 -1 Vegetation .......................................................................................................... 10-1 Aquatic Vegetation ............................................................................................. 11-1 Gam m a Radiation, as Measured by TLDs ........................................................ 12-1 G roundwater Monitoring Program ...................................................................... 13-1 iii

POINT BEACH NUCLEAR PLANT

1.0 INTRODUCTION

The following constitutes the final 2012 Monthly Progress Report for the Environmental Radiological Monitoring Program conducted at the Point Beach Nuclear Plant, Two Rivers, Wisconsin. Results of analyses are presented in the attached tables. Data tables reflect sample analysis results for both Technical Specification requirements and Special Interest locations and samples are randomly selected within the Program monitoring area to provide additional data for cross-comparisons.

For gamma isotopic analyses, the spectrum covers an energy range from 80 to 2048 KeV. Specifically included are Mn-54, Fe-59, Co-58, Co-60, Zn-65, Zr-95, Nb-95, Ru-103, Ru-106, 1-131, Ba-La-140, Cs-134, Cs-137, Ce-141, and Ce-144. Naturally occurring gamma-emitters, such as K-40 and Ra daughters, are frequently detected in soil and sediment samples. Specific isotopes listed are K-40, TI-208, Pb-212, Bi-214, Ra-226 and Ac-228. Unless noted otherwise, the results reported under "Other Gammas" are for Co-60 and may be higher or lower for other radionuclides.

Duplicate analyses are reported in Appendix F unless otherwise noted.

All concentrations, except gross beta, are decay corrected to the time of collection.

All samples were collected within the scheduled period unless noted otherwise in the Listing of Missed Samples.

iv

POINT BEACH NUCLEAR PLANT 2.0 LISTING OF MISSED SAMPLES Expected Collection Sample Type Location Date Reason AP/AI E-04 05-09-12 Loss of power to sampler.

AP/AI E-01 08-16-12 Sampler turned off.

AP/AI E-01 08-22-12 Equipment failure.

V

POINT BEACH NUCLEAR PLANT 3.0 Data Tables vi

POINT BEACH NUCLEAR PLANT Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

Location: E-01, Meteorological Tower Units: pCi/m 3 Collection: Continuous, weekly exchange.

Date Vol. Date Vol.

Collected (m3) Gross Beta 1-131 Collected (M3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-04-12 327 0.030 +/- 0.003 < 0.008 07-05-12 341 0.028 +/- 0:004 < 0.006 01-11-12 306 0.031 +/- 0.003 < 0.011 07-11-12 266 0.020 +/- 0.004 < 0.006 01-18-12 311 0.021 +/- 0.003 < 0.012 07-18-12 298 0.031 +/- 0.004 < 0.009 01-25-12 293 0.031 + 0.004 < 0.005 07-25-12 303 0.026 +/- 0.004 < 0.014 02-01-12 306 0.034 +/- 0.004 < 0.009 08-01-12 308 0.018 +/- 0.003 < 0.015 02-09-12 354 0.022 +/- 0.003 < 0.009 08-09-12 247 0.031 +/- 0.004 < 0.015 02-16-12 312 0.023 +/- 0.003 < 0.007 08-16-12 NDa

.02-22-12 275 0.028 _ 0.004 < 0.011 08-22-12 NDa 03-01-12 352 0.028 +/- 0.003 < 0.009 08-29-12 248 0.050 +/- 0.005 < 0.009 03-07-12 263 0.039 +/- 0.004 < 0.011 09-05-12 252 0.027 _ 0.004 < 0.008 03-14-12 284 0.029 +/- 0.004 < 0.010 09-12-12 288 0.024 +/- 0.004 < 0.010 03-21-12 303 0.029 +/- 0.004 < 0.008 09-19-12 310 0.027 +/- 0.004 < 0.011 03-28-12 309 0.020 +/- 0.003 < 0.008 09-26-12 301 0.016 +/- 0.003 < 0.017 10-03-12 296 0.023 +/- 0.003 < 0.010 1st Quarter 3rd Quarter dean +/- s.d. 0.028 +/- 0.005 < 0.009 Mean +/- s.d. 0.027 +/- 0.009 <0.011 04-04-12 274 0.015 +/-0.003 < 0.006 10-10-12 322 0.019 +/- 0.003 < 0.012 04-11-12 306 0.018 +/- 0.003 < 0.005 10-18-12 344 0.027 +/- 0.003 < 0.007 04-18-12 302 0.019 +/- 0.003 < 0.006 10-24-12 264 0.027 +/- 0.004 < 0.010 04-25-12 298 0.018 +/- 0.003 < 0.009 10-31-12 317 0.021 +/- 0.003 < 0.012 05-02-12 311 0.031 _ 0.004 < 0.006 11-07-12 309 0.019 +/- 0.003 < 0.012 05-09-12 366 0.013 +/- 0.003 < 0.007 11-14-12 319 0.039 +/- 0.004 < 0.006 05-16-12 307 0.017 +/- 0.003 < 0.009 11-22-12 349 0.059 +/- 0.004 < 0.015 05-23-12 301 0.019 +/- 0.003 < 0.010 11-27-12 228 0.033 +/- 0.005 < 0.020 05-30-12 302 0.019 +/- 0.004 < 0.007 12-05-12 341 0.049 +/- 0.004 < 0.013 06-06-12 298 0.012 +/- 0.003 < 0.011 12-12-12 302 0.026 +/- 0.004 < 0.016 06-13-12 300 0.017 +/- 0.003 < 0.011 12-19-12 303 0.040 +/- 0.004 < 0.010 06-19-12 255 0.020 +/- 0.004 < 0.009 12-26-12 302 0.026 +/- 0.004 < 0.012 06-27-12 350 0.014 + 0.003 < 0.015 01-02-13 309 0.044 +/- 0.004 < 0.012 2nd Quarter 4th Quarter Mean +/- s.d. 0.0 18 +/- 0.005 < 0.009 Mean +/- s.d. 0.033 +/- 0.012 < 0.012 Cumulative Averaqe 0.027 +/-0.010 <0.010 a "ND" = No data; see Table 2.0, Listing of Missed Samples.

1-1

POINT BEACH NUCLEAR PLANT Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

Location: E-02, Site Boundary Control Center 3

Units: pCi/mr Collection: Continuous, weekly exchange.

Date Vol. Date Vol.

Collected (m 3) Gross Beta 1-131 Collected (M 3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-04-12 316 0.028 _ 0.003 < 0.008 07-05-12 342 0.029 *0.004 < 0.006 01-11-12 303 0.031 + 0.004 < 0.011 07-11-12 264 0.018 +/- 0.004 < 0.006 01-18-12 315 0.028 - 0.003 < 0.012 07-18-12 302 0.032 +/- 0.004 < 0.009 01-25-12 301 0.030 - 0.004 < 0.005 07-25-12 298 0.027 +/- 0.004 < 0.014 02-01-12 302 0.030 4. 0.004 < 0.009 08-01-12 303 0.020 + 0.003 < 0.016 02-09-12 349 0.024 . 0.003 < 0.009 08-09-12 348 0.024 +/- 0.003 < 0.011 02-16-12 310 0.025 +/- 0.003 < 0.007 08-16-12 280 0.026 +/- 0.004 < 0.012 02-22-12 268 0.025 :10.004 < 0.011 08-22-12 247 0.011 +/- 0.004 < 0.020 03-01-12 322 0.027 +/-l0.003 < 0.010 08-29-12 301 0.051 +/- 0.005 < 0.007 03-07-12 261 0.023 :l 0.004 < 0.012 09-05-12 299 0.033 +/- 0.004 < 0.007 03-14-12 300 0.032 +/-t 0.004 < 0.010 09-12-12 292 0.025 +/- 0.004 < 0.010 03-21-12 294 0.023 +/-t 0.004 < 0.008 09-19-12 308 0.025 +/- 0.003 < 0.011 03-28-12 307 0.027 :1 0.003 < 0.008 09-26-12 304 0.016 +/- 0.003 < 0.017 10-03-12 304 0.024 +/- 0.003 < 0.010 1st Quarter 3rd Quarter Mean +/- s.d. 0.027 +/- 0.003 < 0.009 Mean +/- s.d. 0.026 +/- 0.009 < 0.011 04-04-12 306 0.012 +/- 0.003 < 0.006 10-10-12 310 0.023 +/- 0.004 < 0.013 04-11-12 306 0.020 +/- 0.003 < 0.005 10-18-12 349 0.029 +/- 0.003 < 0.007 04-18-12 299 0.022 +/- 0.003 < 0.006 10-24-12 267 0.027 +/- 0.004 < 0.010 04-25-12 299 0.018 +/- 0.003 < 0.009 10-31-12 315 0.020 +/- 0.003 < 0.012 05-02-12 307 0.021 +/- 0.004 < 0.006 11-07-12 307 0.018 +/- 0.003 < 0.012 05-09-12 307 0.015 +/- 0.003 < 0.009 11-14-12 314 0.038 +/- 0.004 < 0.006 05-16-12 300 0.019 +/- 0.003 < 0.010 11-22-12 322 0.060 +/- 0.005 < 0.016 05-23-12 307 0.024 +/- 0.004 < 0.009 11-27-12 227 0.033 +/- 0.005 < 0.020 05-30-12 306 0.021 +/- 0.004 < 0.006 12-05-12 336 0.052 +/- 0.004 < 0.013 06-06-12 299 0.013 +/- 0.003 < 0.011 12-12-12 305 0.026 +/- 0.004 < 0.016 06-13-12 302 0.018 +/- 0.004 < 0.011 12-19-12 298 0.047 +/- 0.004 < 0.010 06-19-12 259 0.019 +/- 0.004 < 0.009 12-26-12 296 0.025 +/- 0.004 < 0.012 06-27-12 356 0.015 +/- 0.003 < 0.015 01-02-13 310 0.047 +/- 0.004 < 0.012 2nd Quarter 4th Quarter Mean +/- s.d. 0.018 +/- 0.004 < 0.009 Mean +/- s.d. 0.034 +/--0.013 < 0.012 Cumulative Averaqe 0.026 +/- 0.010 < 0.010 1-2

POINT BEACH NUCLEAR PLANT Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131. E Location: E-03, West Boundary 3

Units: pCi/m Collection: Continuous, weekly exchange.

Date Vol. Date Vol.

Collected (m 3) Gross Beta 1-131 Collected (M3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-04-12 318 0.024 - 0.003 < 0.008 07-05-12 342 0.031 +/- 0.004 < 0.006 01-11-12 304 0.030 +/- 0.003 < 0.011 07-11-12 271 0.018 +/- 0.004 < 0.006 01-18-12 320 0.024 +/- 0.003 < 0.012 07-18-12 302 0.029 +/- 0.004 < 0.009 01-25-12 305 0.027 +/- 0.003 < 0.005 07-25-12 297 0.021 + 0.003 < 0.014 02-01-12 300 0.031 +/- 0.004 < 0.009 08-01-12 305 0.015 +/- 0.003 < 0.016 02-09-12 350 0.024 +/-0.003 < 0.009 08-09-12 355 0.024 +/- 0.003 < 0.011 02-16-12 307 0.023 +/- 0,003 < 0.007 08-16-12 298 0.021 +/- 0.003 < 0.011 02-22-12 264 0.028 +/- 0.004 < 0.011 08-22-12 254 0.011 +/- 0.004 < 0.019 03-01-12 347 0.024 +/- 0.003 < 0.009 08-29-12 221 0.048 +/- 0.005 < 0.010 03-07-12 259 0.021 + 0.004 < 0.012 09-05-12 222 0.022 +/- 0.004 < 0.009 03-14-12 292 0.027 +/- 0.004 < 0.010 09-12-12 286 0.027 +/- 0.004 < 0.011 03-21-12 301 0.019 +/- 0,003 < 0.008 09-19-12 308 0.027 +/- 0.004 < 0.011 03-28-12 307 0.022 +/- 0.003 < 0.008 09-26-12 304 0.017 +/- 0.003 < 0.017 10-03-12 309 0.025 +/- 0.003 < 0.010 1st Quarter 3rd Quarter Mean +/- s.d. 0.025 +/- 0.003 < 0.009 Mean +/- s.d. 0.024 +/- 0.009 < 0.011 04-04-12 310 0.012 +/- 0.003 < 0.006 10-10-12 287 0.024 +/- 0.004 < 0.014 04-11-12. 307 0.021 +/- 0.003 < 0.005 10-18-12 335 0.028 +/- 0.003 < 0.008 04-18-12 299 0.021 +/- 0.003 < 0.006 10-24-12 265 0.027 +/- 0.004 < 0.010 04-25-12 304 0.016 +/- 0.003 < 0.008 10-31-12 315 0.024 +/- 0.004 < 0.012 05-02-12 310 0.021 +/- 0.004 < 0.006 11-07-12 307 0.020 _ 0.003 < 0.012 05-09-12 311 0.013 +/- 0.003 < 0.009 11-14-12 310 0.040 +/- 0.004 < 0.006 05-16-12 299 0.018 +/- 0.003 < 0.010 11-22-12 345 0.059 +/- 0.004 < 0.015 05-23-12 306 0.027 +/- 0.004 < 0.009 11-27-12 228 0.031 +/- 0.005 < 0.020 05-30-12 304 0.018 +/- 0.004 < 0.007 12-05-12 342 0.056 +/- 0.004 < 0.013 06-06-12 300 0.013 +/- 0.003 < 0.011 12-12-12 302 0.027 +/- 0.004 < 0.016 06-13-12 294 0.021 +/- 0.004 < 0.012 12-19-12 305 0.045 +/- O.004 < 0.010 06-19-12 256 0.020 +/- 0.004 < 0.009 12-26-12 63 0.027 + 0.012 < 0.057 a 06-27-12 348 0.010 +/- 0.003 < 0.015 01-02-13 305 0.047 +/- 0.004 < 0.012 2nd Quarter 4th Quarter Mean +/- s.d. 0.018 +/- 0.005 < 0.009 Mean +/- s.d. 0.035 +/- 0.013 < 0.016 Cumulative Average 0.025 +/-0.010 <0.011 a Low volume due to power loss caused by storm.

1-3

POINT BEACH NUCLEAR PLANT Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

Location: E-04, 3

North Boundary Units: pCi/m Collection: Continuous, weekly exchange.

Date Vol. Date Vol.

Collected (m3) Gross Beta. 1-131 Collected (m3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-04-12 326 0.028 +/- 0.003 < 0.008 07-05-12 346 0.032 +/-0.004 < 0.006 01-11-12 306 0.033 +/- 0.004 < 0.011 07-11-12 271 0.021 +/-0.004 < 0.006 01-18-12 319 0.023 +/- 0.003 < 0.012 07-18-12 291 0.031 +/- 0.004 < 0.009 01-25-12 306 0.027 +/- 0.003 < 0.005 07-25-12 284 0.022 +/- 0.004 < 0.015 02-01-12 328 0.027 +/- 0.003 < 0.008 08-01-12 242 0.015 +/- 0.004 < 0.020 02-09-12 347 0.025 +/- 0.003 < 0.009 08-09-12 342 0.023 +/- 0.003 < 0.011 02-16-12 307 0.026 +/- 0.003 < 0.007 08-16-12 299 0.019 +/- 0.003 < 0.011 02-22-12 262 0.026 +/- 0.004 < 0.011 08-22-12 252 0.010 +/- 0.004 < 0.020 03-01-12 344 0.029 +/- 0.003 < 0.009 08-29-12 325 0.045 +/- 0.004 < 0.007 03-07-12 253 0.022 +/- 0.004 < 0.012 09-05-12 310 0.027 +/- 0.004 < 0.007 03-14-12 286 0.027 +/- 0.004 < 0.010 09-12-12 310 0.021 +/- 0.003 < 0.010 03-21-12 300 0.023 + 0.003 < 0.008 09-19-12 318 0.029 +/- 0.004 < 0.011 03-28-12 306 0.027 + 0.003 < 0.008 09-26-12 321 0.016 +/- 0.003 < 0.016 10-03-12 313 0.024 +/- 0,003 < 0.010 1st Quarter 3rd Quarter Mean +/- s.d. 0.026 +/- 0.003 < 0.009 Mean +/- s.d. 0.024 +/- 0.009 < 0.011 04-04-12 311 0.011 +/- 0.003 < 0.006 10-10-12 317 0.022 +/- 0.003 < 0.012 04-11-12 309 0.018 +/- 0.003 < 0.005 10-18-12 350 0.025 +/- 0.003 < 0.007 04-18-12 301 0.023 +/- 0.003 < 0.006 10-24-12 269 0.027 +/- 0.004 < 0.010 04-25-12 301 0.017 + 0.003 < 0.008 10-31-12 317 0.022 +/- 0.003 < 0.012 05-02-12 313 0.020 +/- 0.004 < 0.006 11-07-12 312 0.021 +/- 0.003 < 0.012 05-09-12 NDa 11-14-12 312 0.036 +/- 0.004 < 0.006 05-16-12 291 0.016 +/- 0.003 < 0.010 11-22-12 350 0.058 +/- 0.004 < 0.015 05-23-12 308 0.022 +/- 0.004 < 0.009 11-27-12 231 0.034 +/- 0.005 < 0.020 05-30-12 209 0.012 +/- 0.004 < 0.009 12-05-12 345 0.057 +/- 0.004 < 0.013 06-06-12 300 0.014 +/- 0.003 < 0.011 12-12-12 304 0.027 +/- 0.004 < 0.016 06-13-12 303 0.020 +/- 0.004 < 0.011 12-19-12 308 0.045 +/- 0.004 < 0.010 06-19-12 254 0.018 +/-0.004 < 0.009 12-26-12 308 0.025 +/- 0.003 < 0.012 06-27-12 358 0.014 +/- 0.003 < 0.015 01-02-13 311 0.049 +/- 0.004 < 0.012 2nd Quarter 4th Quarter Mean +/- s.d. 0.017 +/- 0.004 < 0.009 Mean +/- s.d. 0.035 +/- 0.013 < 0.012

, Cumulative Averaae 0.026 +/-0.010 <0.010 a "ND" = No data; see Table 2.0, Listing of Missed Samples.

1-4

POINT BEACH NUCLEAR PLANT Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-131.

Location: E-08, G.J. Francar Residence Units: pCi/rn 3 Collection: Continuous, weekly exchange.

Date Vol. Date Vol.

Collected (m 3) Gross Beta 1-131 Collected (m3 ) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-04-12 319 0.026 +/- 0.003 < 0.008 07-05-12 344 0.037 +/- 0.004 < 0.006 01-11-12 298 0.031 4 0.004 < 0.011 07-11-12 270 0.020 +/- 0.004 < 0.006 01-18-12 307 0.021 _ 0.003 < 0.012 07-18-12 289 0.034 +/- 0.004 < 0.009 01-25-12 293 0.028 - 0.004 < 0.005 07-25-12 299 0.024 +/- 0.004 < 0.014 02-01-12 303 0.025 _ 0.003 < 0.009 08-01-12 308 0.016 +/- 0.003 < 0.015 02-09-12 348 0.022 +/- 0.003 < 0.009 08-09-12 347 0.021 +/- 0.003 < 0.011 02-16-12 305 0.026 +/- 0.003 < 0.007 08-16-12 303 0.021 4-0.003 < 0.011 02-22-12 263 0.027 +/- 0.004 < 0.011 08-22-12 257 0.010 +/- 0.003 < 0.019 03-01-12 344 0.028 +/- 0.003 < 0.009 08-29-12 304 0.038 +/- 0.004 < 0.007 03-07-12 256 0.021 +/- 0.004 < 0.012 09-05-12 284 0.027 +/- 0.004 < 0.007 03-14-12 288 0.028 +/- 0.004 < 0.010 09-12-12 299 0.026 +/- 0.004 < 0.010 03-21-12 299 0.022 +/- 0.003 < 0.008 09-19-12 313 0.027 - 0.004 < 0.011 03-28-12 304 0.025 +/- 0.003 < 0.008 09-26-12 307 0.015 +/- 0.003 < 0.017 10-03-12 303 0.024 +/- 0.003 < 0.010 1st Quarter 3rd Quarter Mean +/- s.d. 0.025 +/- 0.003 < 0.009 Mean +/- s.d. 0.024 +/- 0.008 < 0.011 04-04-12 303 0.012 +/- 0.003 < 0.006 10-10-12 313 0.023 - 0.004 < 0.012 04-11-12 302 0.018 +/- 0.003 < 0.005 10-18-12 344 0.028 - 0.003 < 0.007 04-18-12 295 0.020 + 0.003 < 0.006 10-24-12 261 0.025 +/- 0.004 < 0.010 04-25-12 304 0.014 +/- 0.003 < 0.008 10-31-12 321 0.024 +/- 0.003 < 0.012 05-02-12 310 0.023 +/- 0.004 < 0.006 11-07-12 309 0.024 +/- 0.004 < 0.012 05-09-12 302 0.011 +/- 0.003 < 0.009 11-14-12 315 0.036 +/- 0.004 < 0.006 05-16-12 298 0.020 +/- 0.003 < 0.010 11-22-12 353 0.054 +/- 0.004 < 0.015 05-23-12 309 0.022 +/- 0.004 < 0.009 11-27-12 232 0.030 +/- 0.005 < 0.020 05-30-12 301 0.019 +/- 0.004 < 0.007 12-05-12 338 0.054 +/- 0.004 < 0.013 06-06-12 299 0.013 +/- 0.003 < 0.011 12-12-12 307 0.029 +/- 0.004 < 0.016 06-13-12 293 0.021 +/- 0.004 < 0.012 12-19-12 307 0.041 +/- 0.004 < 0.010 06-19-12 243 0.022 - 0.005 < 0.010 12-26-12 303 0.025 +/- 0.003 < 0.012 06-27-12 352 0.016 + 0.003 < 0.015 01-02-13 317 0.048 - 0.004 < 0.011 2nd Quarter 4th Quarter Mean +/- s.d. 0.018 +/- 0.004 < 0.009 Mean +/- s.d. 0.034 +/- 0.012 < 0.012 Cumulative Average 0.025 +/- 0.009 < 0.010 Indicator Locations Annual Mean +/- s.d. 0.026 - 0.010 < 0.010 1-5

POINT BEACH NUCLEAR PLANT Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-1 31.

Location: E-20, Silver Lake Units: pCi/m3 Collection: Continuous, weekly exchange.

Date Vol. Date Vol.

Collected (m 3) Gross Beta 1-131 Collected (M 3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-04-12 320 0.027 +/- 0.003 < 0.008 07-05-12 310 0.027 +/- 0.004 < 0.007 01-11-12 303 0.036 +/- 0.004 < 0.015 07-11-12 265 0.021 +/- 0.004 < 0.006 01-18-12 316 0.026 +/- 0.003 < 0.012 07-18-12 282 0.031 +/- 0.004 < 0.010 01-25-12 301 0.032 +/- 0.004 < 0.005 07-25-12 303 0.026 +/- 0.004 < 0.014 02-01-12 304 0.030 +/- 0.004 < 0.009 08-01-12 301 0.020 +/- 0.003 < 0.016 02-09-12 351 0.022 +/- 0.003 < 0.009 08-09-12 350 0.022 +/- 0.003 < 0.011 02-16-12 287 0.027 +/- 0.003 < 0.008 08-16-12 301 0.021 +/- 0.003 < 0.011 02-22-12 258 0.021 +/- 0.003 < 0.012 08-22-12 265 0.009 +/- 0.003 < 0.019 03-01-12 344 0.028 +/- 0.003 < 0.009 08-29-12 309 0.043 +/- 0.004 < 0.007 03-07-12 260 0.020 +/- 0.003 < 0.012 09-05-12 296 0.028 +/- 0.004 < 0.007 03-14-12 296 0.027 +/- 0.004 < 0.010 09-12-12 301 0.026 +/- 0.004 < 0.010 03-21-12 303 0.024 +/- 0.003 < 0.008 09-19-12 323 0.027 +/- 0.003 < 0.011 03-28-12 311 0.022 +/- 0.003 < 0.008 09-26-12 313 0.017 +/- 0.003 < 0.016 10-03-12 309 0.026 +/- 0.003 < 0.010 1st Quarter 3rd Quarter Mean +/- s.d. 0.026 +/- 0.005 < 0.010 Mean +/- s.d. 0.025 +/- 0.008 < 0.011 04-04-12 304 0.013 +/- 0.003 < 0.006 10-10-12 323 0.022 +/- 0.003 < 0.012 04-11-12 308 0.019 +/- 0.003 < 0.005 10-18-12 349 0.027 +/- 0.003 < 0.007 04-18-12 303 0.021 +/- 0.003 < 0.006 10-24-12 270 0.027 +/- 0.004 < 0.010 04-25-12 305 0.016 +/- 0.003 < 0.008 10-31-12 327 0.022 +/- 0.003 < 0.011 05-02-12 307 0.026 +/- 0.004 < 0.006 11-07-12 314 0.024 +/- 0.004 < 0.012 05-09-12 302 0.012 +/- 0.003 < 0.009 11-14-12 316 0.041 +/- 0.004 < 0.006 05-16-12 302 0.017 +/- 0.003 < 0.010 11-22-12 374 0.063 +/- 0.004 < 0.014 05-23-12 303 0.021 +/- 0.004 < 0.010 11-27-12 239 0.028 +/- 0.004 < 0.019 05-30-12 302 0.022 +/- 0.004 < 0.007 12-05-12 349 0.061 +/- 0.004 < 0.012 06-06-12 298 0.014 +/- 0.003 < 0.011 12-12-12 311 0.029 +/- 0.004 < 0.016 06-13-12 295 0.020 +/- 0.004 < 0.012 12-19-12 309 0.044 +/- 0.004 < 0.010 06-19-12 246 0.018 +/- 0.004 < 0.009 12-26-12 298 0.025 +/- 0.003 < 0.012 06-27-12 356 0.013 +/- 0.003 < 0.015 01-02-13 320 0.056 +/- 0.004 < 0.011 2nd Quarter 4th Quarter Mean +/- s.d. 0.018 +/- 0.004 < 0.009 Mean +/- s.d. 0.036 +/- 0.015 < 0.012 Cumulative Average 0.026 +/- 0.011 < 0.010 Control Annual Mean +/- s.d. 0.026 +/- 0.011 < 0.010 1-6

POINT BEACH NUCLEAR PLANT Table 2. Gamma emitters in quarterly composites of air particulate filters Units: pCi/m3 (Other) (Other)

Location Lab Code Be-7 Be-7 Cs-134 Cs-134 Cs-137 Cs-137 Co-60 (Co-60) Volume Req. LLD MDC 0.01 MDC 0.01 MDC (0.10) MDC m3 1st Quarter E-01 EAP- 2103 0.080 +/- 0.016 - -0.0001 +/- 0.0004 < 0.0004 0.0005 +/- 0.0005 < 0.0006 0.0000 +/- 0.0004 < 0.0004 3993 E-02 - 2105 0.072 +/- 0.014 - -0.0006 .k 0.0005 < 0.0007 0.0003 +/- 0.0004 < 0.0006 0.0000 +/- 0.0005 < 0.0006 3947 E-03 - 2106 0.064 +/- 0.012 - 0.0001 +/- 0.0003 < 0.0004 -0.0003 +/- 0.0004 < 0.0005 0.0000 +/- 0.0003 < 0.0003 3973 E-04 - 2107 0.072 +/- 0.021 - -0.0009 +/- 0.0007 < 0.0011 0.0002 + 0.0007 < 0.0014 -0.0003 +/- 0.0008 < 0.0007 3991 E-08 - 2108 0.061 +/- 0.014 - 0.0001 +/- 0.0005 < 0.0005 0.0002 t 0.0005 < 0.0005 -0.0005 +/- 0.0005 < 0.0004 3924 E-20 - 2109 0.074 +/- 0.017 - -0.0004 +/- 0.0004 < 0.0003 0.0003 +/- 0.0005 < 0.0005 0.0003 +/- 0.0005 < 0.0004 3953 2nd Quarter E-01 EAP- 4369 0.092 +/- 0.017 . -0,0004 +/- 0.0005 < 0.0005 -0.0002 +/- 0.0005 < 0.0005 0.0006 +/- 0.0004 < 0.0006 3970 E-02 - 4371 0.090 +/- 0.015 - 0.0004 +/- 0.0005 < 0.0009 -0.0002 +/- 0.0005 < 0.0008 -0,0006 +/- 0.0006 < 0.0004 3952 E-03 - 4372 0.087 t 0.015 - 0.0001 +/- 0.0004 < 0.0006 -0.0001 +/- 0.0004 < 0.0005 0.0003 +/- 0.0006 < 0.0005 3948 E-04 - 4373 0,104 +/- 0,017 - 0.0002 +/- 0.0004 < 0.0008 -0.0004 +/- 0.0005 < 0.0007 -0.0001 +/- 0.0005 < 0.0003 3557 E-08 - 4374 0.109 +/- 0.020 - 0.0000 +/- 0.0005 < 0.0007 0.0002 +/- 0.0006 < 0.0009 0.0007 +/- 0.0007 < 0.0007 3910 E-20 - 4375 0.095 +/- 0.016 - 0.0004 +/- 0.0005 < 0.0010 -0.0003 +/- 0.0005 < 0.0008 0.0000 +/- 0.0004 < 0.0004 3931 3rd Quarter E-01 EAP- 6446 0.079 1 0.013 - 0.0003 +/- 0.0005 < 0.0008 0.0000  : 0,0005 < 0.0005 -0,0001 +/- 0.0005 < 0.0007 3457 E-02 - 6447 0.083 +/- 0.011 - -0.0001 +/- 0.0002 < 0.0004 0.0002 +/- 0.0004 < 0.0005 -0.0003 +/- 0.0004 < 0.0003 4191 E-03 - 6448 0.071 +/- 0.016 - -0.0001 +/- 0.0005 < 0.0006 -0.0005 + 0.0005 < 0.0006 -0.0002 +/- 0.0007 < 0.0008 4076 E-04 - 6449 0.071 + 0.014 - -0.0003 +/- 0.0004 < 0.0006 0.0001  : 0.0005 < 0.0009 0.0004 . 0.0005 < 0.0007 4221 E-08 - 6450 0.070 +/- 0.012 - -0.0009 + 0.0005 < 0.0002 -0.0001 +/- 0.0005 < 0.0004 0.0002 +/- 0.0004 < 0.0010 4227 E-20 - 6451 0.075 +/- 0.015 - 0.0001 +/- 0.0004 < 0.0006 -0.0001 +/- 0.0006 < 0.0004 0.0006 + 0.0004 < 0.0010 4229 4th Quarter E-01 EAP- 8484 0.051 +/- 0.012 - -0.0001 1 0.0004 < 0.0005 -0.0002 + 0.0006 < 0.0004 0.0002 + 0.0004 < 0.0007 4010 E-02 - 8485 0.063 +/- 0.018 - 0.0003 +/- 0.0005 < 0.0010 0.0000 +/- 0.0005 < 0.0006 -0.0001 +/- 0.0008 < 0.0011 3956 E-03 - 8486 0.050 +/- 0.013 - 0.0000 +/- 0.0003 < 0.0005 0.0000 +/- 0.0004 < 0.0005 -0.0002 +/- 0.0005 < 0,0003 3709 E-04 - 8487 0.051 +/- 0.012 - -0.0005 +/- 0.0005 < 0.0007 -0.0002 +/- 0.0005 < 0.0005 -0.0005 +/- 0.0005 < 0.0003 4034 E-08 -.8488 0.050 +/- 0.011 - 0.0003 +/- 0.0003 < 0.0005 -0.0001 +/- 0.0005 < 0.0005 0.0003 +/- 0.0004 < 0.0004 4018 E-20 - 8489 0.050 +/- 0.016 - -0.0001 +/- 0.0005 < 0.0007 0.0000 +/- 0.0005 < 0.0007 -0.0002 +/- 0.0006 < 0.0008 4098 Annual Meants.d. 0.074 :k 0.017 -0.0001 +/- 0.0004 < 0.0006 0.0000 +/- 0.0002 < 0.0006 0.0000 +/- 0.0004 < 0.0006 2-1

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L)

E-1 1 Lambert Dairy Farm MDC MDC MDC Required Collection Date 01-11-12 02-08-12 03-14-12 LLD Lab Code EMI- 140 EMI- 705 EMI- 1233 Sr-89 -0.3 +/- 1.3 < 1.1 -0.4 +/- 0.9 < 0.7 0.8 +/- 1.1 < 1.0 5.0 Sr-90 1.7 +/- 0.5 < 0.7 1.3 +/- 0.4 < 0.5 0.8 +/- 0.4 < 0.7 1.0 1-131 -0.07 +/- 0.11 < 0.16 -0.09 +/- 0.15 < 0.27 0.12 +/- 0.15 < 0.26 0.5 K-40 1328 +/- 115 1396 +/- 114 1371 +/- 87 Cs-1 34 1.1 +/- 2.0 < 3.4 0.3 +/- 2.0 < 3.5 -0.1 _ 1.3 < 2.3 5.0 Cs-137 0.3 +/- 2.3 <3.1 0.3 +/- 2.4 < 3.8 0.6 + 1.8 < 2.9 5.0 Ba-La-140 3.2 +/- 2.1 < 3.4 2.1 +/- 2.2 < 4.1 1.6 + 1.4 < 2.5 5.0 Other (Co-60) -1.7 +/- 2.3 < 1.9 0.7 +/- 2.5 < 4.1 -0.5 +/- 1.7 < 1.7 15.0 Collection Date 04-11-12 05-09-12 06-13-12 Lab Code EMI- 1839 EMI- 2692 EMI- 3627 Sr-89 -0.1 +/- 1.0 < 0.9 0.9 +/- 1.0 < 0.8 0.1 +/- 0.8 < 0.7 5.0 Sr-90 1.4 +/- 0.4 < 0.5 1.2 +/- 0.4 < 0.6 1.3 +/- 0.4 < 0.5 1.0 1-131 0.07 +/- 0.18 < 0.32 -0.20 +/- 0.18 < 0.34 -0.42 +/- 0.13 < 0.21 0.5 K-40 1562 +/- 116 1409 +/- 109 1445 +/- 120 Cs- 134 -0.6 +/- 2.1 < 2.9 -1.2 +/- 2.1 <3.1 -2.2 +/- 2.2 < 2.8 5.0 Cs-i 37 0.1 +/- 2.5 < 4.6 1.2 +/- 2.1 < 3.8 0.6 +/- 2.5 < 3.7 5.0 Ba-La-140 -1.2 +/- 2.1 < 1.8 -3.5 +/- 2.0 <2.1 -3.2 +/- 2.3 < 3.6 5.0 Other (Co-60) -0.9 +/- 2.4 < 3.4 -2.0 +/- 2.2 < 2.2 -1.2 +/- 2.2 < 2.5 15.0 3-1

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L)

E-1 I Lambert Dairy Farm MDC MDC MDC Required Collection Date 07-11-12 08-08-12 09-12-12 LLD Lab Code EMI- 4088 EMI- 4943 EMI- 5717 Sr-89 -0.5

• 0.7 < 0.7 -0.9 +/- 0.8 < 0.7 -0.8 +/- 0.7 < 0.7 5.0 Sr-90 0.9 k 0.3 < 0.5 1.3 +/- 0.3 < 0.5 1.1 +/- 0.3 < 0.5 1.0 1-131 0.10 +/- 0.11 < 0.16 0.02 +/- 0.14 < 0.20 0.06 +/- 0.15 < 0.27 0.5 K-40 1452 + 108 1435 +/- 114 1414 +/- 99 Cs-134 -0.9 +/- 1.4

• 3.2 -0.9 +/- 2.2 < 3.5 0.1 +/- 1.6

• 3.0 5.0 Cs-137 -1.0 +/- 1.9 < 2.8 0.5 +/- 2.3 < 3.6 -0.3 +/- 2.1 < 3.9 5.0 Ba-La-140 -0.5 +/- 1.4 < 4.9 2.9 +/- 1.5

• 3.0 -0.5 +/- 1.5 < 4.0 5.0 Other (Co-60) 0.6 + 1.6 < 2.3 1.5 +/- 2.1 <3.1 -2.0 +/- 2.0 < 2.3 15.0 Required Collection Date 10-10-12 11-14-12 12-12-12 LLD Lab Code EMI- 6320 EMI- 7371 EMI- 8018 Sr-89 -0.6 +/- 0,8 < 0.7 0.3 +/- 0.7 < 0.6 0.2 +/- 0.8 < 0.7 5.0 Sr-90 1.1 +/- 0.3 < 0.4 0.8 +/- 0.3 < 0.5 1.0 1 0.3 < 0.5 1.0 1-131 0.07 +/- 0.13 < 0.22 0.10 +/- 0.11 < 0.19 -0.05 +/- 0.15 < 0.28 0.5 K-40 1333 +/- 86 1601 +/- 82 1500 +/- 119 Cs-1 34 0.5 +/- 1.6 < 2.6 -1.1 +/- 1.4 < 2.0 0.2 +/- 1.9 < 2.5 5.0 Cs-137 -0.2 +/- 1.9 < 3.5 -0.2 +/- 1.5 <2.1 0.7 +/- 2.2 < 4.0 5.0 Ba-La-140 -0.5 +/- 1.5 < 2.8 1.2 +/- 1.3 < 4.8 1.1 +/- 1.5 < 1.6 5.0 Other (Co-60) 0.8 +/- 1.9 < 2.4 -0.8 +/- 1.5 < 1.7 -0.5 + 2.4 < 3.6 15.0 3-2

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L)

E-21 Strutz Dairy Farm MDC MDC MDC Required Collection Date 01-11-12 02-08-12 03-14-12 LLD Lab Code EMI- 141 EMI- 706 EMI- 1234 Sr-89 -0.5 +/- 0.8 < 0.8 -0.3 +/- 0.7 < 0.8 0.5 +/- 0.7 <0.7 5.0 Sr-90 0.6 +/- 0.3 < 0.5 0.5 +/- 0.3 < 0.5 0.2 +/- 0.2 <0.5 1.0 1-131 -0.03 +/- 0.10 < 0.14 0.09 +/- 0.15 < 0.26 -0.04 +/- 0,15 < 0.28 0.5 K-40 1485 +/- 119 1370 +/- 112 1438 +/- 106 Cs-1 34 -1.2 +/- 2.0 < 2.7 1.2 +/- 1.6 < 3.1 0.2 +/- 1,9 < 2.4 5.0 Cs-137 -0.3 +/- 2.5 < 3.9 0.8 +/- 2.2 < 3.9 1.2 +/- 2.1 < 3.5 5.0 Ba-La-140 1.0 +/- 2.1 < 3.5 2.5 +/- 2.2 < 2.8 -0.5 +/- 1.9 < 1.8 5.0 Other (Co-60) 3.4 +/- 2.4 < 3.3 0.4 +/- 2.1 < 3.3 -0.1 +/- 2.2 < 3.7 15.0 Collection Date 04-11-12 05-09-12 06-13-12 Lab Code EMI- 1840 EMI- 2693 EMI- 3628 Sr-89 0.5+/-0.8 <1.0 0.5+/-0.8 <1.0 -0.3 10.6 <0.7 5.0 Sr-90 0.2 +/- 0.3 <0.6 0.1 +/- 0.3 <0.6 0.3 +/- 0.3 <0.5 1.0 1-131 0.05 +/- 0.18 < 0.33 -0.02 +/- 0.21 < 0.37 0.04 +/- 0.16 < 0.29 0.5 K-40 1335 +/- 101 1423 +/- 124 1457 +/- 121 Cs-1 34 -0.4 +/- 1.5 <3.1 -0.1 +/- 2.5 < 4.0 0.1 +/- 1.7 < 2.5 5.0 Cs-137 1.0 +/- 1.9 < 3.3 0.9 +/- 2.9 < 4.7 -0.4 +/- 2.7 <4.1 5.0 Ba-La-140 -0.1 +/- 1.5 < 1.0 -2.7 +/- 2.8 < 2.2 2.2 +/- 1.3 < 2.9 5.0 Other (Co-60) 0.2 +/- 1.6 < 2.9 -1.1 +/- 3.0 < 5.5 -0.4 +/- 2.5 < 2.7 15.0 3-3

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCiJL)

E-21 Strutz Dairy Farm MDC MDC MDC Required Collection Date 07-11-12 08-08-12 09-12-12 LLD Lab Code EMI- 4089 EMI- 4944 EMI- 5718 Sr-89 -0.2 1 0.6 < 0.8 -1.1 +/- 0.7 < 0.8 -0.1 +/- 0.6 < 0.8 5.0 Sr-90 0.4 +/- 0.3 < 0.5 0.8 +/- 0.3 < 0.5 0.3 +/- 0.3 < 0.5 1.0 1-131 -0.01 +/- 0.10 < 0.14 -0.03 +/- 0.13 <0.19 0.00 +/- 0.16 < 0.29 0.5 K-40 1461 +/- 121 1482 +/- 110 1466 +/- 98 Cs-I 34 -0.7 +/- 1.9 < 3.1 -0.7 +/- 2.2 < 4.0 -0.1 +/- 2.0

• 3.6 5.0 Cs-1 37 -2.0 +/- 2.0 < 2.5 -0.5 +/- 2.4 < 3.8 0.7 +/- 1.9 < 2.6 5.0 Ba-La-140 0.7 +/- 1.4 < 4.7 -0.5 + 1.4 < 4.2 -1.1 +/- 1.3 < 4.2 5.0 Other (Co-60) -1.7 +/- 2.3 < 3.2 -0.5 +/- 2.4 < 3.4 1.3 +/- 2.3 < 3.8 15.0 Required Collection Date 10-10-12 11-14-12 12-12-12 LLD Lab Code EMI- 6321 EMI- 7372 EMI- 8019 Sr-89 -0.4 +/- 0.6 < 0.8 0.7 t 0.9 < 0.8 -0.1 +/- 0.6 < 0.8 5.0 Sr-90 0.3 +/- 0.3 < 0.5 0.5 + 0.5 < 0.9 0.4 +/- 0.3 < 0.5 1.0 1-131 0.00 +/- 0.16 < 0.31 0.01 + 0.10 < 0.19 0.09 +/- 0.16 < 0.28 0.5 K-40 1430 +/- 80 1448 +/- 102 1421 +/- 110 Cs-1 34 -0.5 +/- 1.1 < 2.0 -1.9* 1.9 < 2.5 0.6 +/- 2.1 < 3.4 5.0 Cs-137 0.7 +/- 1.5 < 2.2 2.3 + 2.2 < 4.2 1.0 +/- 2.1 < 3.7 5.0 Ba-La-140 2.0 +/- 1.1 < 3.5 -1.8 + 1.9 < 1.9 0.3 +/- 1.5 <2.1 5.0 Other (Co-60) -2.4 +/- 1.7 < 2.4 1.3 +/- 1.6 < 2.3 2.2 +/- 2.6 < 4.3 15.0 3-4

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L)

E-40 Barta MDC MDC MDC Required Collection Date 01-11-12 02-08-12 03-14-12 LLD Lab Code EMI- 142 EMI- 707 EMI- 1235 Sr-89 -0.1 +/- 0.7 < 0.7 -0.3 +/- 0.7 < 0.7 0.0 +/- 0.7 < 0.7 5.0 Sr-90 0.7 +/- 0.3 < 0.4 0.8 +/- 0.3 < 0.4 0.7 +/- 0.3 < 0.5 1.0 1-131 -0.07 +/- 0.13 < 0.23 -0.07 +/- 0.13 < 0.24 0.08 +/- 0.17 < 0.30 0.5 K-40 1409 +/- 102 1402 +/- 110 1371 +/- 108 Cs- 134 -0.7 +/- 1.6 < 3.3 -0.3 +/- 1.4 3.1 1.4 +/- 1.5 < 2.9 5.0 Cs-1 37 -0.7 +/- 2.3 < 3.4 3.4 +/- 1.9 3.4 0.5 +/- 2.1 < 2.9 5.0 Ba-La-140 -0.8 +/- 1.4 < 2.8 -0.5 +/- 1.5 2.4 -0.5 +/- 1.6 < 2.0 5.0 Other (Co-60) -0.8 +/- 2.0 < 2.5 1.7 +/- 2.0 3.2 1.6 +/- 1.7 < 2.9 15.0 Collection Date 04-11-12 05-09-12 06-13-12 Lab Code EMI- 1841 EMI- 2694 EMI- 3629 Sr-89 -0.2 +/- 1.0 < 1.0 -0.8 +/- 0.8 < 0.8 0.1 +/- 0.6 < 0.6 5.0 Sr-90 0.5 +/- 0.4 < 0.6 0.8 +/- 0.3 < 0.5 0.4 +/- 0.2 < 0.4 1.0 1-131 0.09 +/- 0.23 < 0.40 -0.12 +/- 0.24 < 0.44 -0.02 +/- 0.19 < 0.34 0.5 K-40 1429 +/- 106 1282 +/- 104 1377 + 110 Cs-134 -0.2 +/- 1.3 < 3.0 -0.2 +/- 1.5 < 3.0 0.1 +/- 1.5 < 3.4 5.0 Cs-137 1.1 +/- 1.9 < 2.9 0.0 +/- 2.2 < 4.6 . 1.0 +/- 2.2 < 3.9 5.0 Ba-La-140 -2.1 +/- 1.7 < 1.7 -0.2 +/- 1.6 < 1.8 -3.7 +/- 1.9 < 2.4 5.0 Other (Co-60) 1.2 +/- 1.7 < 2.3 -0.7 +/- 2.1 < 1.6 1.2 +/- 2.1 < 3.0 15.0 3-5

POINT BEACH NUCLEAR PLANT Table 3. Radioactivity in milk samples Collection: Monthly Sample Description and Concentration (pCi/L)

E-40 Barta MDC MDC MDC Required Collection Date 07-11-12 08-08-12 09-12-12 LLD Lab Code EMI- 4090 EMI- 4945 EMI- 5719 Sr-89 -0.4 +/- 0.7 < 0.7 -0.1 +/- 0.9 < 0.7 -0.3 +/- 0.6 < 0.6 5.0 Sr-90 0.7 +/- 0.3 < 0.4 1.0 +/- 0.3 < 0.5 0.8 +/- 0.3 < 0.4 1.0 1-131 -0.04 +/- 0.15 < 0.28 0.09 +/- 0.11 < 0.16 0.05 +/- 0.24 < 0.47 0.5 K-40 1470 +/- 113 1523 +/- 114 1580 +/- 96 Cs-1 34 -0.9 +/- 1.7 < 2.9 0.4 +/- 1.4 < 3.1 0.3 +/- 1.7 < 3.1 5.0 Cs-1 37 -0.4 +/- 2.3 < 2.8 2.5 +/- 1.8 < 3.4 -0.1 +/- 1.8 < 2.9 5.0 Ba-La-140 1.7 +/- 1.6 < 4.6 -2.5 +/- 1.5 < 3.7 1.1 +/- 1.3 < 4.5 5.0 Other (Co-60) 2.2 +/- 2.0 <4.1 -0.5 +/- 2.2 < 2.9 0.8 +/- 1.7 < 3.3 15.0 Required Collection Date 10-10-12 11-14-12 12-12-12 LLD Lab Code EMI- 6322 EMI- 7373 EMI- 8020 Sr-89 -0.3 +/- 0.7 < 0.7 0.0 +/- 0.6 < 0.6 0.0 +/- 0.7 < 0.7 5.0 Sr-90 0.7 +/- 0.3 < 0.4 0.6 +/- 0.3 < 0.5 0.8 +/- 0.3 < 0.5 1.0 1-131 0.09 +/- 0.12 < 0.21 0.10 +/- 0.12 < 0.20 0.03 +/- 0.23 < 0.42 0.5 K-40 1479 +/- 113 1386 +/- 104 1358 + 108 Cs-134 -0.4 +/- 2.1 < 3.5 -0.5 +/- 1.6 < 2.4 -1.2 +/- 1.5 < 2.7 5.0 Cs-137 -0.5 +/- 2.2 < 2.8 -1.0 +/- 2.1 < 3.8 1.2 +/- 2.2 < 3.9 5.0 Ba-La-140 -0.9 +/- 1.7 < 2.1 -0.2 +/- 1.7 < 1.3 1.0 +/- 1.4 < 2.5 5.0 Other (Co-60) 3.4 +/- 2.3 < 3.3 -0.9 +/- 2.2 < 2.4 0.6 _ 1.8 < 3.7 15.0 Sr-89 Annual Mean + s.d. -0.1 +/- 0.5 Sr-90 Annual Mean + s.d. 0.7 + 0.4 1-131 Annual Mean + s.d. 0.00 +/- 0.10 K-40 Annual Mean + s.d. 1431 +/- 70 Cs-I 34 Annual Mean + s.d. -0.3 +/- 0.8 Cs-137 Annual Mean + s.d. 0.4 +/- 1.0 Ba-La Annual Mean + s.d. -0.1 +/- 1.8 Co-60 Annual Mean + s.d. 0.2 +/- 1.5 3-6

POINT BEACH NUCLEAR PLANT Table 4. Radioactivity in Well Water Samples, E-10 Collection: Quarterly Units: pCi/L 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr. Req. Annual LLD Mean +/-s.d Collection Date 01-12-12 04-12-12 07-12-12 10-16-12 Req.

Lab Code EWW- 175 EWW- 1851 EWW- 4125 EWW- 6705 LLD Gross Beta 2.8 +/- 1.8 2.6 +/- 1.1 2.0 +/- 0.9 2.4 +/- 0.8 4.0 2.5 +/- 0.3 H-3 81.9 +/- 92.3 40.4 +/- 77.3 19.2 +/- 78.5 -69.1 +/- 67.2 500 18.1 +/- 63.7 Sr-89 -0.2 +/- 0.8 0.0 +/- 0.4 0.3 +/- 0.4 0.4 +/- 0.4 5.0 0.1 +/- 0.3 Sr-90 0.1 +/- 0.4 -0.1 +/- 0.2 0.0 +/- 0.2 0.1 +/- 0.2 1.0 0.0 +/- 0.1 1-131 -0.01 +/- 0.17 -0.13 +/- 0.14 0.05 +/- 0.16 0.10 +/- 0.19 0.5 0.00 -k0.10 Mn-54 -0.4 +/- 1.3 -0.7 +/- 2.0 1.5 +/- 1.5 0.3 +/- 1.4 10 0.2 +/- 1.0 Fe-59 0.7 +/- 2.1 0.8 +/- 4.4 2.2 +/- 2.6 -0.9 +/- 3.1 30 0.7 +/- 1.3 Co-58 -0.8 +/- 1.2 1.0 +/- 1.8 0.3 +/- 1.3 0.2 +/- 1.2 10 0.2 +/--0.8 Co-60 0.0 +/- 1.4 2.0 +/- 2.1 0.3 +/- 1.7 0.2 +/- 1.5 10 0.6 +/- 0.9 Zn-65 -2.2 +/- 2.6 0.3 +/- 4.5 -0.5 +/- 2.4 2.4 +/- 3.6 30 0.0 +/- 1.9 Zr-Nb-95 -0.6 +/- 1.3 -2.3 +/- 2.5 -4.2 +/- 1.7 0.9 +/- 1.5 15 -1.5 +/-_2.2 Cs-134 0.9 +/- 1.2 -1.8 +/- 2.1 0.1 +/- 1.5 -1.9 +/- 1.2 10 -0.7 +/-1.4 Cs-137 0.8 +/- 1.4 -3.5 +/- 2.4 0.6 +/- 2.0 0.1 +/- 1.9 10 -0.5 +/--2.0 Ba-La-140 0.6 +/- 1.6 -1.1 +/- 1.9 0.9 +/- 1.8 1.9 +/- 1.8 15 0.6 +/-1.3 Other (Ru-103) 1.3 +/- 1.1 -1.2 +/- 2.3 1.5 +/- 1.4 0.1 +/- 1.6 30 0.4 +/-1.2 MDC Data Collection Date 01-12-12 04-12-12 07-12-12 10-16-12 Req.

Lab Code EWW- 175 EWW- 1851 EWW- 4125 EWW- 6705 LLD Gross Beta <3.1 < 1.8 < 1.4 < 1.2 4.0 H-3 < 145.9 < 142.9 < 147.4 < 148.7 500 Sr-89 < 0.8 < 0.6 < 0.6 < 0.5 5.0 Sr-90 < 0.8 < 0.5 < 0.5 < 0.4 1.0 1-131 < 0.30 < 0.26 < 0.28 < 0.33 0.5 Mn-54 < 1.4 < 2.6 < 3.0 < 2.2 10 Fe-59 < 4.7 < 6.7 < 6.2 < 6.1 30 Co-58 < 1.8 < 3.5 < 1.9 < 1.9 10 Co-60 < 1.8 < 2.7 < 2.0 < 2.7 10 Zn-65 < 2.9 < 7.2 < 2.2 < 5.0 30 Zr-Nb-95 < 2.6 < 2.5 < 1.9 < 2.7 15 Cs-134 < 2.3 < 3.2 < 2.4 < 2.0 10 Cs-137 < 1.9 < 2.4 < 3.7 < 3.2 10 Ba-La-140 < 3.7 < 1.5 < 4.9 < 5.0 15 Other (Ru-1 03) < 2.4 < 2.3 < 3.9 < 2.7 30 4-1

POINT BEACH Table 5. Lake water, analyses for gross beta, iodine-131 and gamma emitting Isotopes.

Location: E-01 (Meteorological Tower)

Collection: Monthly composites Units: pCifL MDC MDC MDC MDC Lab Code ELW- 169 ELW- 770 ELW- 1309 ELW- 1855 Date Collected 01-12-12 02-15-12 03-14-12 04-12-12 Req. LLD Gross beta 1.1 + 0,5 < 0.8 1.7 +/- 0.8 < 1.3 2.2 +/- 0.5 < 0.7 2.3 +/- 0.7 < 1.2 4.0 1-131 -0.05 +/- 0.13 < 0.24 -0.04 +/- 0.14 < 0.29 0.12 +/- 0.14 < 0.21 -0.02 +/- 0.16 < 0.30 0.5 Be-7 -1.2 +/- 10.4 < 19.5 11.0 +/- 11.9 < 26.8 6.3 +/- 10.5 < 23.5 13.0 +/- 17.3 < 39.8 Mn-54 0.4 + 1.3 < 3.0 1.5 +/- 1.6 < 2.8 -0.6 +/- 1.2 < 2.1 -0.5 +/- 2.1 < 2.7 10 Fe-59 1.8 t 2.6 < 6.0 -1.0 +/- 2.6 < 3.9 0.4 +/- 2.7 < 4.0 -3.2 + 3.8 < 4.5 30 Co-58 -1.3 +/- 1.4 < 2.4 -2.2 +/- 1.4 < 1.8 0.4 +/- 1.2 < 2.1 0.7 :l:2.1 < 3.5 10 Co-60 2.1 +/- 1.6 < 2.1 -0.2 +/- 1.2 < 1.6 -0,9 +/- 1.3 < 1.6 0.6 + 2.2 < 3.8 10 Zn-65 -0.2 +/- 2.9 < 3.3 -0.1 +/- 2.9 < 2.2 -1.7 +/- 2.8 < 3.9 1.0 t 5.4 < 7.8 30 Zr-Nb-95 -0.6 +/- 1.5 < 2.2 -0.7 + 1.6 < 2.3 -0.3 +/- 1.4 < 2.6 -1.1 +/- 2.4 < 4.3 15 Cs-134 -0.8 +/- 1.4 < 2.1 -0.4 +/- 1.5 < 2.1 0.0 t 1.2 < 2.5 -1.7 t 2.4 < 3.7 10 Cs-137 0.3 +/- 1.7 < 2.9 -0.1 +/- 1.7 < 3.0 0.1 +/- 1.6 < 2.5 0.3 + 2.5 < 4.9 10 Ba-La-140 0.9 +/- 1.7 < 7.9 -0.4 +/- 1.6 < 6.1 0.1 +/- 1.3 < 2.0 1.0 +/- 2.7 < 5.4 15 Other(Ru-103) -0.9 +/- 1.3 < 3.2 -0.3 +/- 1.3 < 2.8 -1.5 +/- 1.3 < 2,3 -1.3 +/- 2.2 < 3.1 30 Lab Code ELW- 2873 ELW- 3671 a ELW- 4121 ELW- 5233 Date Collected 05-16-12 06-13-12 07-12-12 08-16-12 Req. LLD Gross beta 2.0 +/- 0.9 < 1.6 1.8 +/- 0.6 < 0.8 1.6 +/- 0.8 < 1.3 3.6 +/- 0.7 < 0.9 4.0 1-131 -0.01 t 0.15 < 0.27 0.17 : 0.19 <0.33 0.04 +/- 0.16 <0.28 0.03 :k0.15 <0.23 0.5 Be-7 11.1 L 21.7 < 35.5 -7.8 +/- 12.0 < 24.6 4.8 +/- 14.0 < 33.2 4.2 *: 13.3 < 31.5 Mn-54 2.3 t 2.8 < 5.3 -0.3 +/- 1.3 < 2.3 -1.0 +/- 1.4 < 1.6 0.1 :f: 1.9 < 2.9 10 Fe-59 1.8 +/- 5.3 < 3.8 -2.1  : 2.4 < 4.8 0.3 +/- 2.6 < 4.8 3.2 :t 3.2 < 7.0 30 Co-58 0.8 +/- 2.7 < 5.0 0.2 +/- 1.4 < 2.3 -0.7 +/- 1.6 < 2.6 0.9 :L1.6 < 1.7 10 Co-60 0.1 +/- 2.8 < 2.8 1.7 +/- 1.4 < 2.2 0.3 +/- 1.5 < 2.1 -0.5 t 2.0 < 3.1 10 Zn-65 -29.9 +/- 8.9 < 10.7 1.4 +/- 2.7 < 4.2 -0.1 +/- 2.6 < 4.1 -0.8 :l: 2.6 < 3.6 30 Zr-Nb-95 -7.7 +/- 3.7 < 6.7 -1,2 +/- 1.4 < 2.7 -2.2 +/- 1.5 < 2.5 -1.2  : 1.9 < 3.1 15 Cs-134 -1.8 +/- 3.1 < 5.9 -1.0 +/- 1.1 < 1.8 -0.3 +/- 1.2 < 2.2 -0.7 +/- 1.5 < 2.6 10 Cs-137 -1.1 + 3.0 < 5.2 0.1 +/- 1.6 < 2.6 -0.4 +/- 1.6 < 2.4 -0.4 +/- 1.9 < 2.5 10 Ba-La-140 3.3 - 3.2 < 3.9 -2.9 +/- 1.4 < 2.7 0.3 +/- 1.8 < 5.1 -2.0 +/- 2.3 < 3.7 15 Other (Ru-103) -1.1 t 2.8 < 4.9 -0.8 +/- 1.4 < 2.8 -0.6 +/- 1.4 < 2.3 1.7 +/- 1.7 < 3.5 30 Lab Code ELW- 5766 ELW- 6701 ELW- 7419 ELW- 7862 Date Collected 09-11-12 10-16-12 11-14-12 12-04-12 Req. LLD Gross beta 1.8 t 0.8 < 1.3 1.7 +/- 0.6 < 0.9 1.5 +/- 0.4 < 0.7 2.1 +/- 0.7 < 0.9 4.0 1-131 0.13 t 0.19 < 0.34 0.00 +/- 0.23 < 0.47 0.02 +/- 0,16 < 0.28 0.23 +/- 0.26 < 0.48 0.5 Be-7 18.5 t 11.4 < 39.1 20.1 +/- 12.3 < 30.1 -1.8 +/- 15.0 < 42.1 -3.1 t 10.2 < 24.3 Mn-54 -0.4 +/- 1.4 < 1.8 -0.4 +/- 1.6 < 1.9 0.8 +/- 1.6 < 3.3 0.1 k 1.3 < 1.5 10 Fe-59 4.3 +/- 2.2 < 4.6 -1.7 +/- 2,5 < 5.4 1,2 + 3.0 < 5.6 -0.3 +/- 2.3 < 5.3 30 Co-58 -0.9 +/- 1.3 < 21 0.5 +/- 1.3 < 1.4 -0.7 +/- 1.8 < 2.4 0.4 +/- 1.2 < 2.2 10 Co-60 1.4 +/- 1.4 < 26 0.5 +/- 1.5 < 2.5 -1.0 +/- 1.7 < 1.9 0.3 t 1.4 < 2.0 10 Zn-65 -1.1 +/- 2.4 < 1.8 2.2 +/- 3.1 < 3.4 2.4 +/- 3.4 < 5.6 -0.9 +/- 2.6 < 3.2 30 Zr-Nb-95 -2.7 +/- 1.3 <3.1 -1.0 +/- 1.6 < 3.6 -2.2 t 1.7 < 3.5 -0.3 -t1.3 < 2.9 15 Cs-134 -0.7 +/- 0.9 < 1.8 0.6 t 1.3 < 2.7 0.5 +/- 1.8 < 2.6 -0.6 t 1.2 < 2.1 10 Cs-137 -0.4 +/- 1.8 < 2.5 -1.5 +/- 1.6 < 2.0 -1.1 +/- 2.0 <3.4 1.2 - 1.3 < 2.6 10 Ba-La-140 3.2 +/- 1.3 -< 7.6 5.0 .k 1.8 < 6.7 1.8 +/- 1.7 < 4.1 -2.9

• 1.7 < 2.8 15 Other (Ru-103) -2.3 +/- 1.4 < 2.8 1.1 t 1.4 < 4.0 -0.6 +/- 1.6 < 3.7 -1.6 t 1.2 < 2.7 30

'Tritium analysis requested on monthly sample; result = <153 pCi/L.

5-1

POINT BEACH Table 5. Lake water, analyses for gross beta, iodine-131 and gamma emitting isotopes.

Location: E-05 (Two Creeks Park)

Collection: Monthly composites Units: pCi/L MDC MDC MDC MDC Lab Code ELW- 170 ELW- 771 ELW- 1310 ELW- 1866 Date Collected 01-12-12 02-15-12 03-16-12 04-12-12 Req. LLD Gross beta 4.2 +/- 0.8 < 0.9 2.5 -t 0.8 < 1.2 2.2 +/- 0.5 < 0.6 1.8 +/- 0.8 < 1.3 4.0 1-131 0.01 +/- 0.14 < 0.14 0.12 +/- 0.14 < 0.20 -0.13 +/- 0.14 < 0.26 0.17 1 0.18 < 0.32 0.5 Be-7 7.4 1 11.9 < 28.6 9.4 +/- 10.9 < 26.7 -2.6 +/- 17.1 < 35,6 1.1 +/- 16.4 < 36.7 Mn-54 -0.9 +/- 1.3 < 1.6 0.2 +/- 1.3 < 2.2 -0.1 +/- 1.6 < 2.6 0.1 +/- 1.9 < 2.7 10 Fe-59 1.3 +/- 2.3 < 6.0 0.4 +/- 2.6 < 5.4 -0,7 +/- 3.5 < 5.1 0.7 +/- 3.5 < 5.4 30 Co-58 1.0 +/- 1.4 < 2.5 0.4 +/- 1.3 < 1.6 * -0.3 +/- 1.7 < 2.8 -0.8 +/- 2.1 < 3.7 10 Co-60 -0.4 +/- 1.9 < 3.4 -0.1 +/- 1.5 < 1.8 1.3 +/- 1.7 < 3.0 1.5 +/- 2.2 < 3.1 10 Zn-65 -1.3 +/- 2.4 < 1.7 -1.3 +/- 2.4 < 1.9 1.1 +/- 3.7 < 6.1 -4.3 +/- 4.2 < 3.0 30 Zr-Nb-95 -1.0 l 1.3 < 2.1 0.1 +/- 1.4 < 2.9 -0.2 +/- 1.4 < 1.5 -0.4 +/- 2.2 < 3.6 15 Cs-134 -0.6 *: 1.2 < 2.3 -0.8 +/- 1.1 < 1.3 0.3 +/- 1.7 < 2.9 -0.2 +/- 2.0 < 2.6 10 Cs-137 -1.0  :: 1.7 < 2.8 -0.3 + 1.8 < 2.7 -2.0 +/- 2.0 < 1.9 -1.9 +/- 2.4 < 2.7 10 Ba-La-140 -0.3 l 1.5 < 3.6 1.8 +/- 1.3 < 3.6 -3.3 +/- 1.8 < 1.3 1.2 +/- 2.2 < 4.2 15 Other (Ru-103) -0.9 L 1.2 < 2.7 0.0 +/- 1.1 < 2.7 0.6 +/- 1.9 < 3.5 -1.0 +/- 2,3 < 4.0 30 Lab Code ELW- 2874 ELW- 3672 a ELW- 4122 ELW- 5234 Date Collected 05-16-12 06-13-12 07-12-12 08-16-12 Req. LLD Gross beta 2.0 +/- 1.0 < 1.8 2.9 +/- 0.6 < 0.8 2.0 +/- 0.7 < 1.2 2.3 +/- 0.9 < 1.6 4.0 1-131 0.02 +/- 0.17 <0.30 0.01 +/- 0.18 <0.32 0.07 +/- 011 <0.16 -0.05 +/- 0.17 <0.26 0.5 Be-7 6.3 +/- 15.8 < 29.0 -7.1 +/- 12.8 < 24.4 -2.1 +/- 11.6 < 22.0 -11.5 +/- 11.1 < 22.2 Mn-54 0.4 +/- 1.9 < 3.0 0.6 +/- 1.3 < 2.3 0.3 +/- 1.5 < 2.9 0.4 +/- 1.2 < 1.9 10 Fe-59 -0.8 +/- 4.0 < 3.8 -2.4 +/- 2.9 < 4.8 0.7 +/- 2.9 < 7.1 -0.4 +/- 3.0 < 5.2 30 Co-58 -0.6 :k 2.0 < 2.6 -1.2 +/- 1.6 < 2.5 1.5 +/- 1.6 < 2.9 0.1 +/- 1.6 < 3.2 10 Co-60 -0.1 +/- 2.1 < 3.7 -0.3 +/- 1.6 < 2.4 1.1 +/- 1.4 < 1.5 0.9 +/- 1.4 < 3.0 10 Zn-65 0.3 +/- 4.6 < 6.5 1.4 +/- 2.9 < 4.6 2.2 +/- 3.6 < 6.4 -1.4 +/- 3.2 < 2.9 30 Zr-Nb-95 -2.7 1 2.1 < 2.1 -1.3 +/- 1,7 < 3.1 0.5 +/- 1.6 < 3.7 1.8 +/- 1.8 < 3.7 15 Cs-134 -1.2 l 2.4 < 3.6 0.6 +/- 1.4 < 2.8 -0.8 +/- 1.6 < 2.8 -0.3 +/- 1.3 < 2.2 10 Cs-137 -0.2 +/- 2.2 < 3.6 0.2 +/- 1.8 < 2.5 -0.8 +/- 1.5 < 2.6 -0.2 +/- 1.8 < 3.6 10 Ba-La-140 -1.1 +/- 2.4 < 1.8 -2.1 +/- 1.9 < 4.6 -2.0 +/- 1.5 < 3.2 -3.2 +/- 1.9 < 2.2 15 Other (Ru-103) -0.9 + 2.2 < 2.8 -0.3 +/- 1.3 < 2.4 -0.3 +/- 1.4 < 3,8 -0.8 +/- 1.5 < 2.9 30 Lab Code ELW- 5767 ELW- 6702 ELW- 7420 ELW- 7863 Date Collected 09-11-12 10-16-12 11-14-12 12-04-12 Req. LLD Gross beta 2.3 +/- 0.7 < 1.1 3.2 +/- 0.7 < 0.9 1.1 +/- 0.4 < 0.6 2.2 +/- 0.6 < 0.8 4.0 1-131 0.02 +/- 0.19 < 0.35 0.05 +/- 0.18 < 0.32 0.06 +/- 0.15 < 0.26 -0.04 + 0.18 < 0.33 0.5 Be-7 -8.5 + 10.9 < 22.9 0.3 +/- 11.8 < 29.0 -0.3 +/- 15.0 < 30.7 12.1 +/- 9.9 < 19.4 Mn-54 1.2 +/- 1.4 < 3.0 -1.2 +/- 1.2 < 1.5 -0.8 +/- 1.7 < 2.8 0.6 +/- 1.2 < 1.7 10 Fe-59 0.6 : 2.1 <5.5 -0.9 +/- 2.3 <2.7 4.6 +/- 3.4 <7.2 2.9 +/- 2.0 <4.0 30 Co-58 0.2 1 1.3 < 2.6 -0.8 +/- 1.1 < 1.5 0.1 +/- 1.8 < 3.6 0.6 +/- 1.0 < 2.3 10 Co-60 -0.3 + 1.5 < 1.4 -0.5 +/- 1.4 < 1.8 0.1 +/- 2.0 < 3.2 0.9 -t 1.3 < 2.5 10 Zn-65 -1.9 t 2.5 < 3.4 -0.9 +/- 2.7 < 2.2 0.1 + 3.6 < 6.3 -2.2 +/- 1.9 < 1.4 30 Zr-Nb-95 -1.3

• 1.5 < 2.9 -0.8 +/- 1.5 < 2.5 0.9 +/- 1.8 < 4.2 -0.2 +/- 1.2 < 2.4 15 Cs-134 -0.3 +/- 1.5 < 2.3 0.7 +/- 1.4 < 2.6 1.3 +/- 1.9 < 1.9 0.1 +/-: 1.0 < 1.8 10 Cs-137 0.2 1 1.6 < 3.0 0.8 +/- 1.5 < 2.8 -0.2 +/- 2.1 < 3.7 1.0 +/- 1.3 < 2.3 10 Ba-La-140 0.7 :t 1.7 < 9.5 1.2 +/- 1.6 < 6.4 0.1 +/- 2.0 < 5.5 2.5 +/- 1.1 < 3.6 15 Other (Ru-103) -1.4 1 1.2 < 3.1 -0.5 +/- 1.3 < 2.5 -1.0 +/- 1.7 < 4.9 -0.9 +/- 1.1 < 2.4 30 aTritium analysis requested on monthly sample; result = <153 pCV/L.

5-2

POINT BEACH Table 5. Lake water, analyses for gross beta, iodine-131 and gamma emitting isotopes.

Location: E-06 (Coast Guard Station)

Collection: Monthly composites Units: pCi/L MDC MDC MDC MDC Lab Code ELW- 171 ELW- 772 ELW- 1311 ELW- 1857 Date Collected 01-12-12 02-15-12 03-14-12 04-12-12 Req. LLD Gross beta 3.3 + 0.7 < 0.9 3.6 +/- 0.8 < 1.3 2.0 0.5 < 0.6 2.0 +/- 0.7 < 1.2 4.0 1-131 0.15 4 0.19 < 0.33 0.14 +/- 0.20 < 0.38 0.13 +/- 0.16 < 0.22 0.11 +/- 0.13 < 0.19 0.5 Be-7 -3.1

• 12.8 < 30.3 2.0 +/- 9.9 < 29.5 -0.7 +/- 12.8 < 25.6 2.9 +/- 15.5 < 36.8 Mn-54 1.5

• 1.7 < 3,5 -1.1 +/- 1.5 < 1.9 -1,0 +/- 1.3 < 1.6 1.1 +/- 1.9 < 3.1 10 Fe-59 -2.2 :k3.1 < 5.2 -2.1 +/- 2.4 < 3.0 -0.8 +/- 2.6 < 3.4 0.2 +/- 4.2 < 7.5 30 Co-58 -1.0 +/- 1.9 < 2.2 -0.5 +/- 1.3 < 2.3 1.1 4 1.6 < 2.2 -0.6 + 2.0 < 2.9 10 Co-60 -0.6 4 1.3 < 1.4 -1.1 +/- 1.6 < 1.6 -0.8 +/- 1.4 < 1.5 2.9 + 1.7 < 3.1 10 Zn-65 4.2

• 3.2 < 4.9 3.3 +/- 2.9 < 5.3 -1.3 +/- 3.1 < 4.0 1.0 +/- 4.7 < 6.4 30 Zr-Nb-95 0.0 :k1.8 < 3.0 0.4 +/- 1.4 < 3.1 -1.3 +/- 1.5 < 2.6 -0.2 +/- 2.0 < 3.2 15 Cs-134 0.4  : 1,5 < 2.6 -0.1 +/- 1.3 < 2.3 -1.0 11.1 < 1.7 0.2 +/- 1.9 < 3.7 10 Cs-137 -0.1

• 1.7 < 3.1 -1.0 +/- 1.5 < 2.2 0.7 +/- 1.6 < 2.7 -0.3 +/- 2.2 < 3.0 10 Ba-La-140 1.1 4`2.3 < 5.3 -3.8 t 1.4 < 5.0 1.5 +/- 1.6 < 1.5 2.5 +/- 1.8 < 4.1 15 Other (Ru-103) 0.7 +/- 1.4 -z 2.8 -0.7 +/- 1.2 < 2.4 0.0 +/- 1.4 < 2.5 -0.6 +/- 2.0 < 2.6 30 Lab Code ELW- 2875 ELW- 3673 ELW- 4123 ELW- 5235 Date Collected 05-16-12 06-13-12 07-12-12 08-16-12 Req. LLD Gross beta 2.2 :h0.9 <1.6 2.2 +/- 0.5 < 0.7 1.8 +/- 0.8 < 1.3 3.5 +/- 1.1 < 1.8 4.0 1-131 0.00 4`0.14 <0.24 0.10 +/- 0.14 < 020 0.10 +/- 0.13 < 0.22 0.17 +/- 0.28 < 0.49 0.5 Be-7 3.0 +/- 13.2 < 27.2 6.9 +/- 11.7 < 23.8 -2.3 +/- 11.8 < 28.4 -1.2 +/- 16.4 < 31.3 Mn-54 1.1 + 1.6 < 3.2 0.3 +/- 1.3 < 2.2 -1.1 +/- 1.5 < 1.6 -0.5 +/- 1.6 < 2.0 10 Fe-59 0.8 1 2.8 < 4.8 0.5 +/- 2.4 < 5.9 -0.4 +/- 2.0 < 3.7 -1.5 +/- 3.2 < 4.2 30 Co-58 1.4 +/- 1.3 < 2.5 -0.1 +/-1.5 < 3.5 -2.1 + 1.7 < 2.3 -1.9 + 1.8 < 2.2 10 Co-60 0.2 +/- 1.8 < 2.2 -0.5 +/- 1.2 < 1.8 -0.2 +/- 1.5 < 2.1 -1.2 +/- 1.6 < 2.0 10 Zn-65 -1.3 +/- 3.0 < 2.5 -0.8 +/- 2.5 < 2.7 -0.4 +/- 2.6 < 3.1 -1.5 +/-- 3.6 < 5.0 30 Zr-Nb-95 -0.3 +/- 1.6 < 2.9 -1.0 +/- 1.7 < 4.5 -2.3 +/- 1.5 < 2.4 -0.4 +/- 1.9 < 3.4 15 Cs-134 1.0 :t 1.7 < 2.8 -0.4 1.3 < 2.1 -0.3 +/- 1.3 < 2.8 -1.9 +/- 1.9 < 3.6 10 Cs-137 0.4 +/- 1.7 < 3.1 -0.1 - 1.8 < 1.8 1.3 +/- 1.8 < 2.9 0.0 +/- 2.0 < 3.3 10 Ba-La-140 -1.3 +/- 2.2 < 3.5 -2.5 +/- 1.7 < 7.4 -0.5 +/- 2.1 < 6.3 1.0 +/- 2.1 < 2.7 15 Other (Ru-103) -1.1 +/- 1.4 < 1.7 -0.1 - 1.4 < 4.2 0.5 +/- 1.3 < 3.4 -0.4 +/- 1.9 < 3.4 30 Lab Code ELW- 5768 ELW- 6703 ELW- 7421 ELW- 7864 Date Collected 09-11-12 10-16-12 11-14-12 12-04-12 Req. LLD Gross beta 2.2 -+/-0.8 < 1.3 3.5 +/- 0.7 < 0.9 1.4 +/- 0.4 < 0.6 2.6 +/- 0.6 < 0.9 4.0 1-131 0.03 2t 0.21 < 0.37 0.13 +/- 0.20 < 0.34 0.13 +/- 0.20 < 0.39 0.00 +/- 0.18 < 0.32 0.5 Be-7 -4.4 +/-k12.7 < 35.6 0.3 +/- 12.2 < 29.0 12.2 +/- 14.5 < 30.1 1.2 +/- 12.3 < 20.1 Mn-54 0.3 +/- 1.5 < 2.7 -0.2 +/- 1.6 < 3.4 -0.6 +/- 1.5 < 2.2 0.6 +/- 1.3 < 2.4 10 Fe-59 0.8 +/-t 2.8 < 7.1 1.4 +/- 2.1 < 3.4 -0.9 +/- 3.1 < 3.5 -2.1 +/- 2.8 < 4.4 30 Co-58 0.3 +/- 1.5 < 3.1 -1.9 +/- 1.4 < 2.2 0.2 +/- 1.7 < 2.8 0.6 +/- 1.2 < 1.9 10 Co-60 0.8 :t 1.4 < 2.9 0.1 +/- 1.6 < 2.7 1.0 +/- 1.6 < 3.0 0.3 +/- 1.7 < 2.1 10 Zn-65 1.4 +/- 2.7 < 3.8 -0.8 +/- 3.1 < 2.5 0.9 +/- 3.2 < 6.3 -0.4 +/- 2.8 < 3.9 30 Zr-Nb-95 0.1 :t 1.6 < 3.0 0.5 +/- 1.5 < 3.1 -3.2 +/- 1.9 < 3.0 -0.5 +/- 1.7 < 3.5 15 Cs-134 -0.1 :k 1.2 < 2.1 -0.2 +/- 1.3 < 2.9 0.6 +/- 1.5 < 2.9 0.3 +/- 1.5 < 2.7 10 Cs-137 0.3 1z1.7 < 2.8 0.7 +/- 1.7 < 3.0 0.8 +/- 2.0 < 3.4 -0.6 +/- 1.7 < 2.0 10 Ba-La-140 2.3 4`1.7 < 11.0 -2.6 +/- 1.7 < 3.8 2.9 +/- 1.7 < 4.0 1.8 +/- 1.6 < 3.6 15 Other (Ru-103) -0.8 1 1.3 < 2.8 1.4 +/- 1.2 < 3.2 -1.4 +/- 1.5 < 2.3 -0.1 +/- 1.3 < 3.3 30 5-3

POINT BEACH Table 5. Lake water, analyses for gross beta, iodine-131 and gamma emitting isotopes.

Location: E-33 (Kewaunee)

Collection: Monthly composites Units: pCi/L MDC MDC MDC MDC MDC MDC Lab Code ELW- 172 ELW- 773 ELW- 1312 ELW- 1858 Date Collected 01-12-12 02-15-12 03-16-12 04-12-12 Req. LLD Gross beta 2.4 +/- 1.0 < 1.8 2.4 +/- 0.8 . < 1.3 1.1 +/- 0.4 < 0.6 2.9 +/- 0.8 < 1.3 4.0 1-131 -0.04 +/- 0.14 < 0.26 0.13 +/- 0.19 < 0.37 0.15 +/- 0.16 < 0.27 0.08 +/- 0.19 < 0.38 0.5 Be-7 13.7 +/- 12.5 < 35.6 5.0 +/- 10.9 < 24.6 9.4 +/- 10.7 < 22.9 -13.5 +/- 17.2 < 31.3 Mn-54 0.7 +/- 1.4 < 2,8 1.0 +/- 1.3 < 2.6 0.6 +/- 1.4 < 2.8 0.3 +/- 1.6 < 2.7 10 Fe-59 -1.7 +/- 3.1 < 6.4 0.4 +/- 2.5 < 4,9 1.6 +/- 2.4 < 4.4 -0.9 +/- 4.2 < 7.0 30 Co-58 -0.1 +/- 1,7 < 27 0.3 +/- 1.3 < 2.1 -0.5 +/- 1.3 < 2,2 0.7 +/- 1.8 < 3.3 10 Co-60 1.2 +/- 2,0 < 3.2 -0.5 +/- 1.6 < 1.8 -0.1 +/- 1.2 < 1.6 1.3 +/- 2.1 < 2.1 10 Zn-65 -1.1 +/- 3.5 < 4.2 -1.6 +/- 2.5 < 3.3 -2.2 +/- 2.6 < 2.4 2.8 +/- 3.9 < 2.4 30 Zr-Nb-95 -5.9 +/- 1.8 < 2.5 -1.7 +/- 1.3 < 2.1 -1.4 +/- 1.5 < 1.4 0.0 +/- 1.9 < 3.2 15 Cs-134 -0.8 +/- 1.3 < 20 -0.7 +/- 1.0 < 1.9 -1.0 +/- 1.1 < 2.2 0.8 +/- 1.7 < 3.2 10 0.3 +/- 1.9 < 2.8 0.3 +/- 1.6 < 2.9 1.2 +/- 1.6 < 3.1 -0.2 +/- 2.1 < 3.1 10 Cs-137 Ba-La-140 -3.9 +/- 1.5 < 4.0 -3.0 +/- 1.5 < 3.3 -0.7 +/- 1.6 < 1.7 -1.3 +/- 2.5 < 2.4 15 Other (Ru-103) -0.4 +/- 1.6 < 3.4 -2.1 +/- 1.3 < 2.6 -0.5 +/- 1.1 < 2.1 -1.3 +/- 2.0 < 2.4 30 Lab Code ELW- 2876 ELW- 3674 ELW- 4124 ELW- 5236 Date Collected 05-16-12 06-13-12 07-12-12 08-16-12 Req. LLD Gross beta 1.7 +/- 1.0 < 1.8 2.1 +/- 0.6 < 0.8 1.5 +/- 0.7 < 1.2 2.2 +/- 1.0 < 1.8 4.0 1-131 -0.10 +/- 0.21 < 0.39 0.12 +/- 0.15 < 0,21 0.07 +/- 0.13 < 0.23 0.14 +/- 0.16 < 0.23 0.5 Be-7 5.9 +/- 14.4 < 26.7 0.4 +/-8.7 < 20.9 -0.4 +/- 10,9 < 28.8 11.7 +/- 12.9 < 30.1 Mn-54 -0.1 +/- 2.1 < 3.5 0.9 +/- 1.1 < 1,3 0,7 +/- 1.3 < 2.1 0.3 +/- 1.3 < 2.1 10 Fe-5 3.8 +/- 3.1 < 4.9 0.3 +/- 2.1 < 5.3 0.3 +/- 2.3 < 3.7 -0.5 +/- 2.3 < 4.9 30 Co-56 0.5 +/- 2.0 < 2.7 -0.2 +/- 1.1 < 1,9 0.7 +/- 1.1 < 1.6 -0.2 +/- 1.4 < 2.2 10 Co-60 1.3 +/- 2.0 < 3.1 -0.7 +/- 1.2 < 1,2 -1.1 +/- 1.5 < 1.8 -0.1 +/- 1.5 < 2,0 10 Zn-65 -0.5 +/- 4.5 < 3.9 0.5 +/- 1.9 < 3,8 0.0 +/- 2.5 < 2.1 -1.6 +/- 3.0 < 3.3 30 Zr-Nb-95 -0.6 +/- 2.1 < 4.1 -1.7 +/- 1.1 < 2,2 -0.2 +/- 1.5 < 3.5 1.1 +/- 1.5 < 3.1 15 Cs-134 0.1 +/- 2.3 <2.8 0.1 +/- 0.9 < 1.7 -0.2 +/- 1.1 <2.2 -0.6 +/- 1.3 < 3,0 10 Cs-137 -1.4 +/- 2.2 < 2.5 0.6 +/- 1.2 < 2.2 1.1 +/- 1.4 < 2.7 0.1 +/- 1.7 < 2.0 10 Ba-La-140 -3.2 +/- 2.7 < 2.1 -1.5 +/- 1.3 < 31 -1.2 +/- 1.0 < 3.5 0.4 +/- 1.9 < 5.2 15 Other (Ru-103) -1.3 +/- 2.1 < 3.9 0.6 +/-:0.9 < 3.1 -0.6 +/- 1.3 < 2.9 -0.7 t 1.3 < 2.5 30 All locations Lab Code ELW- 5769 ELW- 6704 ELW- 7422 ELW- 7865 Annual Date Collected 09-11-12 10-16-12 11-14-12 12-05-12 Req. LLD Mean +/- s.d.

Gross beta 2.1 +/- 0.8 < 1.2 1.5 +/- 0.5 < 0.8 1.2 +/- 0.4 < 0.6 2.2 +/- 0.6 < 0.8 4.0 2.2 +/- 0.7 1-131 0.13 +/- 0.19 < 0.32 -0.14 +/- 0.17 < 0.32 0.08 +/- 0.14 < 0.25 0.05 +/- 0.22 < 0.40 0.5 0.06 +/- 0.08 Be-7 17.5 +/- 12.8 < 37.6 -2.4 +/- 10.0 < 17.4 6.3 +/- 15.6 < 31.3 6.8 +/- 14.3 < 32.4 3.3 +/- 7.6 Mn-54 0.0 +/- 1.4 < 1.7 0.0 +/- 1.2 < 2.0 -0.1 +/- 2.0 < 3.3 1,2 +/- 1.6 < 2.9 10 0.2 +/- 0.8 Fe-59 -2.3 +/- 2.5 < 5.3 1.0 +/- 2.0 < 4.1 -0.4 +/- 3.9 < 7.8 -2.8 +/- 3.2 < 4.1 30 0.1 +/- 1.8 Co-58 1.5 +/- 1.5 < 35 -1.0 +/- 1.1 < 1.6 -0.3 +/- 2.1 < 4.4 -0.7 +/- 1.5 < 3.1 10 -0.1 +/- 0.9 Co-60 -1.6 +/- 1.5 < 1.4 0.2 +/- 1.3 < 2.4 0.6 +/- 2.1 < 2.5 2.0 +/- 1.4 < 2.4 10 0.2 +/- 1.0 Zn-65 0.2 +/- 2.2 < 3.3 2.0 +/- 2.4 < 3.6 0.1 +/- 3.9 < 7.2 -1.4 +/- 3.4 < 3.4 30 -0.7 +/- 4.6 Zr-Nb-95 1.2 +/- 1.4 < 4.6 -0.3 +/- 1.4 < 3.4 0.8 +/- 2.1 < 5.1 0.3 +/- 1.4 < 2.9 15 .0.9 +/- 1.6 Cs-134 0.8 +/- 1.3 < 2.7 -0.7 +/- 1.0 < 1.6 -1.7 +/- 2.0 < 3.0 -1.9 +/- 1.6 < 3.0 10 -0.3 +/- 0.8 Cs-137 0.8 +/- 1.7 < 3.5 1.3 +/- 1.5 < 2.2 3.4 +/- 2.4 < 4.3 0.1 +/- 1.8 < 3.3 10 0.0 +/- 0.9 Ba-La-140 -1.1 +/-l 1.3 < 9.5 -0.2 +/- 1.6 < 6.6 1.6 +/- 2.1 < 3.7 -1.5 +/- 1.7 < 3.1 15 -0.2 +/- 2.1 Other (Ru-103) -0.7 +/- 1.2 < 3.7 -2.0 +/- 1.2 < 2.5 -1.7 +/- 2.0 < 5.3 -1.0 +/- 1.7 < 3.2 30 -0.6 +/- 0.8

'Tritium requested on monthly sample; result = 406+/-99 pCiIL.

POINT REACH NUCLEAR PLANT Table 6. Lake water, analyses for tritium, strontium-89 and strontium-90.

Collection: Quarterly composites of weekly grab samples Units: pCi/L Location E-01 (Meteorological Tower)

Period 1st Qtr. MDC 2nd Qtr. MDC 3rd Qtr. b MDC 4th Qtr. MDC Lab Code ELW- 1362 ELW- 3746 ELW- 5817 ELW- 7898 Req. LLDs H-3 73 +/-79 < 143 29 +/- 79 < 148 30 +/- 75 < 148 -29 +/- 72 < 149 500 Sr-89 -0.24 +/-0.67 < 0.79 -0.18 +/- 0.74 < 0.90 -0.30 +/- 0.62 < 0.78 -0.03 +/-:0.52 < 0.64 5.0 Sr-90 0.33 +/- 0.28 < 0.52 0.26 +/- 0.26 < 0.49 0.25 +/- 0.28 < 0.55 0.28 +/- 0.22 < 0.40 1.0 Location E-05 (Two Creeks Park)

Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Lab Code ELW- 1363 ELW- 3747 ELW- 5819 ELW- 7899 Req. LLDs H-3 55 +/-78 < 143 117 +/- 84 < 148 904 +/- 114 c< 148 39 +/-76 < 149 500 Sr-89 0.53 +/- 0.71 < Q.91 0.19 +/- 0.92 < 1.13 0.89 +/- 0.92 < 1.05 0.01 +/- 0.60 < 0.72 5.0 Sr-90 0.08 +0.27 < 0.57 0.28 +/- 0.30 < 0.59 0.16 +/- 0.36 < 0.74 0.31 +/- 0.24 < 0.44 1.0 Location E-06 (Coast Guard Station)

Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Lab Code ELW- 1364 ELW- 3748 ELW- 5820 ELW- 7900 Req. LLDs H-3 73 +/-79 < 143 31 +/-80 < 148 55 +/- 77 < 148 8 +/-74 < 149 500 Sr-89 0.07 +/- 0.62 < 0.75 -0.18 +/- 0.87 < 1.00 0.56 +/- 0.73 < 0.63 0.26 +/- 0.57 < 0.72 5.0 Sr-90 0.20 +/- 0.24 < 0.47 0.40 +/- 0.29 < 0.53 0.40 +/- 0.35 < 0.62 0.15 +/- 0.23 < 0.46 1.0 Location E-33 (Kewaunee)

Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Lab Code ELW- 1365 ELW- 3749 ELW- 5821 ELW- 7901 Req. LLDs H-3 32 +/-77 < 143 1192 +/- 126 a< 148 128 +/- 87 < 153 124 +/-80 < 149 500 Sr-89 0.10 +/- 0.58 < 0.71 0.68 +/- 0.78 < 0.87 -0.05 +/- 0.68 < 0.73 0.01 +/- 0.70 < 0.89 5.0 Sr-90 0.25 :t0.23 < 0.43 0.33 +/- 0.24 < 0.43 0.48 +/- 0.30 < 0.51 0.32 +/- 0.29 < 0.55 1.0 aTritium repeated with a result of 1261+/-127 pCi/L. Monthly results: April = 35+/-81 (<151), May = 49+/-82 (<151), June = 3975+/-197 pCi/L.

b Monthly tritium requested; results: July = 24+/-85 (<158), Aug = -7+/-82 (<158), Sept = 49+/-85 (<157) pCi/L.

cTritium repeated with a result of 956+/-120 pCi/L. Monthly results: July = 39+/-85 (<158), Aug = 2184+/-1 59, Sept = 372+/-100 pCi/L.

Tritium Annual Mean +/- s.d. 179 +/-346 Sr-89 Annual Mean +/- s.d. 0.15 +/- 0.35 Sr-90 Annual Mean +/- s.d. 0.28 +/- 0.10 6-1

POINT BEACH NUCLEAR PLANT Table 7. Fish, analyses for gross beta and gamma emitting isotopes.

Location: E-13 Collection: 2x / year Units: pCi/g wet Sample Description and Concentration Req.

MDC MDC MDC LLD Collection Date 01-10-12 01-02-12 02-08-12 Lab Code EF- 266 EF- 709 EF- 708 Type Lake Trout Drum Whitefish Ratio (wetldry wt.) 4.73 3.11 4.77 Gross Beta 3.24 +/- 0.07 < 0.024 4.12 +/- 0.09 < 0.031 3.60 +/- 0.07 < 0.022 0.5 K-40 2.35 +/- 0.33 3.40 +/- 0.42 3.47 +/- 0.41 Mn-54 -0.002 +/- 0.008 < 0.008 -0.001 +/- 0.008 < 0.014 -0.004 +/- 0.009 < 0.013 0.13 Fe-59 -0.029 +/- 0.017 < 0.037 0.021 +/- 0.015 < 0.051 -0.015 +/- 0.015 < 0.027 0.26 Co-58 0.012 +/- 0.007 < 0.017 0.001 +/- 0.008 < 0.019 0.006 +/- 0.008 < 0.017 0.13 Co-60 -0.013 +/- 0.010 < 0.011 0.004 +/- 0.011 < 0.012 0.008 +/- 0.009 < 0.014 0.13 Zn-65 -0.037 +/- 0.022 < 0.014 0.010 +/- 0.018 < 0.031 -0.005 +/- 0.016 < 0.037 0.26 Cs-134 0.000 +/- 0.009 < 0.014 -0.009 +/- 0.008 < 0.013 0.006 +/- 0.009 < 0.015 0.13 Cs-137 0.029 +/- 0.013 < 0.009 0.011 +/- 0.012 < 0.021 0.074 +/- 0.023 < 0.019 0.15 Other (Ru-1 03) 0.011 +/- 0.006 < 0.015 0.002 +/- 0.007 < 0.041 -0.005 +/- 0.007 < 0.012 0.5 Collection Date 03-02-12 03-14-12 05-31-12 Lab Code EF- 1495 EF- 1496 EF- 3255 Type Trout Herring Lake Trout Ratio (wet/dry wt.) 6.10 8.70 3.11 Gross Beta 3.05 +/- 0.06 < 0.021 3,50 +/- 0.08 < 0.026 3.76 +/- 0.08 < 0.030 0.5 K-40 2.31 +/- 0.37 2.82 +/- 0.38 3.39 +/- 0.39 Mn-54 -0.002 +/- 0.009 < 0.017 0.006 +/- 0.009 < 0.016 -0.004 +/- 0.008 < 0.009 0.13 Fe-59 -0.020 +/- 0.021 < 0.036 -0.005 +/- 0.022 < 0.047 -0,016 +/- 0.020 < 0.029 0.26 Co-58 -0.005 +/- 0.010 < 0.019 -0.015 +/- 0.011 < 0.016 0.001 +/- 0.007 < 0.009 0.13 Co-60 -0.005 +/- 0.013 < 0.020 -0.002 +/- 0.011 < 0.015 0.008 +/- 0.009 < 0.006 0.13 Zn-65 -0.001 +/- 0.026 < 0.023 0.003 +/- 0.023 < 0.028 -0.009 +/- 0.020 < 0.010 0.26 Cs-134 0.000 +/- 0.009 < 0.017 0.005 +/- 0.009 < 0.013 0.001 +/- 0.008 < 0.006 0.13 Cs-137 0.015 +/- 0.012 < 0.021 -0.007 +/- 0.013 < 0.019 0.042 +/- 0.019 < 0.014 0.15 Other (Ru-103) -0.001 +/- 0.010 < 0.034 0.010 +/- 0.008 < 0.020 -0.001 +/- 0.007 < 0.015 0.5 7-1

POINT BEACH NUCLEAR PLANT Table 7. Fish, analyses for gross beta and gamma emitting isotopes.

Location: E-13 Collection: 2x/year Units: pCi/g wet Sample Description and Concentration (pCi/g wet) Req.

MDC MDC MDC LLD Collection Date 05-31-12 05-31-12 07-25-12 Lab Code EF- 3256 EF- 3257 EF- 4519 Type Lake Trout Brown Trout Brown Trout Ratio (wet/dry wt.) 4.44 6.00 3.24 Gross Beta 3.06 +/- 0.06 < 0.019 3.16 +/- 0.07 < 0.022 4.72 +/- 0.13 < 0.044 0.5 K-40 2.59 +/- 0.42 2.73 +/- 0.43 3.02 +/- 0.47 -

Mn-54 0.001 +/- 0M009 < 0.014 0.006 - 0.010 < 0.021 0.007 +/- 0.010 < 0.016 0.13 Fe-59 -0.012 +/- 0.021 < 0.039 0.017 +/- 0.020 < 0.057 0.006 +/- 0.024 < 0.047 0.26 Co-58 -0.008 +/- 0.009 < 0.011 0.003 +/- 0.009 < 0.018 0.003 +/- 0.010 < 0.011 0.13 Co-60 0.002 +/- 0.011 < 0.015 0.009 +/- 0.011 < 0.017 -0.009 +/- 0.010 < 0.008 0.13 Zn-65 0.006 +/- 0.022 < 0.036 -0.003 - 0.020 < 0.041 -0.002 +/- 0.027 < 0.038 0.26 Cs-1 34 -0.001 +/- 0.010 < 0.015 0.004 +/- 0.009 < 0.016 0.004 +/- 0.010 < 0.018 0.13 Cs-137 0.021 +/- 0.014 < 0.025 0.021 +/- 0.012 < 0.018 0.021 +/- 0.013 < 0.019 0.15 Other (Ru-1 03) 0.006 +/- 0.010 < 0.024 -0.001 +/- 0.007 < 0.025 0.011 +/- 0,010 < 0.022 0.5 Collection Date 07-25-12 07-25-12 08-09-12 Lab Code EF- 4520 EF- 4521 EF- 5313 Type Sucker Lake Trout Brown Trout Ratio (wet/dry wt.) 5.00 5.44 3.81 Gross Beta 3.28 +/- 0.09 < 0.029 3.55 +/- 0.11 < 0.038 4.12 +/- 0.08 < 0.026 0.5 K-40 3.20 +/- 0.42 2.90 +/- 0.39 3.07 +/- 0.42

,Mn-54 0.001 +/- 0.007 < 0.010 0.005 +/- 0.009 < 0.017 0.000 +/- 0.010 < 0.023 0.13 Fe-59 -0.009 +/- 0.022 < 0.023 -0.004 + 0.020 < 0.023 -0,007 +/- 0.020 < 0,065 0.26 Co-58 -0.003 +/- 0.009 < 0.009 -0.001 + 0.011 < 0.020 0.004 +/- 0.010 < 0.031 0.13 Co-60 0.006 +/- 0.007 < 0.008 -0.005 +/- 0.009 < 0.009 0.009 +/- 0.010 < 0.008 0.13 Zn-65 0.026 +/- 0.016 < 0.017 -0.017 +/- 0.021 < 0.026 -0.049 +/- 0.025 < 0.025 0.26 Cs-134 -0.013 +/- 0.010 < 0.012 -0.006 +/- 0.009 < 0.013 -0.005 +/- 0.008 < 0.014 0.13 Cs-137 0.004 +/- 0.011 < 0.018 0.017 +/- 0.013 < 0.024 0.047 +/- 0.024 < 0.023 0.15 Other (Ru-103) 0.007 +/- 0.008 < 0.011 -0.002 +/- 0.008 < 0.019 -0.020 +/- 0.010 < 0.037 0.5 7-2

POINT BEACH NUCLEAR PLANT Table 7. Fish, analyses for gross beta and gamma emitting isotopes.

Location: E-13 Collection: 2x / year Units: pCi/g wet Sample Description and Concentration (pCi/g wet) Req.

MDC MDC MDC LLD Collection Date 08-28-12 08-29-12 10-18-12 Lab Code EF- 5512 EF- 5513 EF- 6870 Type Brown Trout Lake Trout Smallmouth Bass Ratio (wet/dry wt.) 5.80 4.65 3.36 Gross Beta 3.60 +/- 0.07 < 0.020 2.49 +/- 0.05 < 0.015 3.43 +/- 0.07 < 0.036 0.5 K-40 2.85 +/- 0.39 2.63 +/- 0.41 2.06 +/- 0.72 Mn-54 0.001 +/- 0.009 < 0.016 -0.003 +/- 0.010 < 0.017 0.000 +/- 0.021 < 0.039 0.13 Fe-59 -0.019 +/- 0.018 < 0.030 0.017 +/- 0.021 < 0.039 0.024 +/- 0.040 < 0.057 0.26 Co-58 0.001 +/- 0.008 < 0.015 0.007 +/- 0.009 < 0.016 0.011 +/- 0.019 < 0.050 0.13 Co-60 -0.011 +/- 0.011 < 0.009 0.016 +/- 0.009 < 0.013 -0.022 +/- 0.024 < 0.037 0.13 Zn-65 -0.016 +/- 0.018 < 0.015 -0.003 +/- 0.023 < 0.017 -0.078 +/- 0.048 < 0.030 0.26 Cs-134 -0.008 +/- 0.007 < 0.014 -0.008 +/- 0.010 < 0.010 -0.028 +/- 0.023 < 0.035 0.13 Cs-1 37 0.042 +/- 0.020 < 0.021 0,027 +/- 0.015 < 0.026 0.005 +/- 0,021 < 0.029 0.15 Other (Ru-103) 0.003 +/- 0.008 < 0.025 0.007 +/- 0.010 < 0.023 0.019 +/- 0.022 < 0.087 0.5 Collection Date 10-16-12 10-19-12 Lab Code EF- 6871 EF- 6872 Annual Type Lake Trout Whitefish Ratio (wet/dry wt.) 4.32 3.75 Mean +/- s.d.

Gross Beta 3.47 +/- 0.05 < 0.017 4.51 +/- 0.06 < 0.022 3.57 + 0.56 0.5 K-40 2.58 +/- 0.31 - 3.19 +/- 0.39 2.91 +/- 0.41 Mn-54 -0.005 +/- 0.008 < 0.011 -0.001 +/- 0.007 < 0.012 0.000 +/- 0.004 0.13 Fe-59 -0.010 +/- 0.012 < 0.028 -0.010 +/- 0.017 < 0.022 -0.004 +/- 0.016 0.26 Co-58 - 0.004 +/- 0.006 < 0.020 0.006 +/- 0.008 < 0.020 0.001 +/- 0.007 0.13 Co-60 0.001 +/- 0.007 < 0,012 -0.003 +/- 0.011 < 0.015 0.000 + 0.010 0.13 Zn-65 -0.006 +/- 0.016 < 0.037 -0.008 +/- 0.021 < 0.024 -0.011 +/- 0.024 0.26 Cs-1 34 -0.002 +/- 0.005 < 0.009 0.005 +/- 0.008 < 0.016 -0.003 +/- 0.009 0.13 Cs-137 0.037 +/- 0.014 < 0.015 -0.001 +/- 0.010 < 0.017 0.024 +/- 0.020 0.15 Other (Ru-1 03) -0.017 +/- 0.006 < 0.015 0.011 +/- 0.008 < 0.031 0.002 +/- 0.010 0.5 7-3

POINT BEACH NUCLEAR PLANT Table 8. Radioactivity in shoreline sediment samples Collection: Semiannual Sample Description and Concentration (pCilg dry)

MDC MDC MDC Collection Date 4/1212012 4/1212012 4/12/2012 Lab Code ESS- 1859 ESS- 1860 ESS- 1861 LLD Location E-01 E-05 E-06 Gross Beta 8.61 +/- 0.98 < 1.24 8.47 +/- 0.87 < 1.06 12.44 +/- 1.01 < 1.18 2.0 Be-7 0.007 +/- 0.046 < 0.09 0.055 +/- 0.045 < 0.08 -0.013 +/- 0.046 < 0.09 K-40 7.24 + 0.37 5.13 +/- 0.34 - 7.96 +/- 0.41 Cs-137 0.021 +/- 0.011 < 0.010 0.013 +/- 0.006 < 0.00,9 0.012 +/- 0.007 < 0.009 0.15 TI-208 0.040 +/- 0.016 0.040 +/- 0.015 0.044 +/- 0.015 Pb-212 0.13 +/- 0.043 0.13 0.046 - 0.11 +/- 0.027 Bi-214 0.10 +/- 0.021 0.10 +/- 0.022 - 0.09 +/- 0.022 Ra-226 0.24 +/- 0.14 0.29 +/- 0.12 < 0.23 0.24 +/- 0.14 Ac-228 0.15 +/- 0.044 0.14 0.050 - 0.17 +/- 0.063 4/12/2012 Collection Date 4/12/2012 Lab Code ESS- 1862 ESS- 1863 Location E-12 E-33 Gross Beta 7.63 +/- 0.68 < 1.06 9.48 +/- 0.97 < 1.21 2.0 Be-7 0.095 +/- 0,045 < 0.09 0.028 +/- 0.046 < 0.07 K-40 4.88 +/- 0.54 7.36 +/- 0.38 -

Cs-137 0.021 +/- 0.011 < 0.010 0.016 +/- 0.009 < 0.o08 0.15 TI-208 0.047 +/- 0.015 0.045 +/- 0.015 Pb-212 0.13 +/- 0.050 0.14 +/- 0.053 Bi-214 0.09 +/- 0,023 0.11 +/- 0.022 Ra-226 0.19 +/- 0.12 < 0.20 0.25 +/- 0.13 Ac-228 0.12 +/- 0.037 0.11 +/- 0.043 8-1

POINT BEACH NUCLEAR PLANT RADIOACTIVITY IN SHORELINE SEDIMENT SAMPLES (Semiannual Collections)

Sample Description and Concentration (pCi/g dry)

MDC MDC MDC Collection Date 10116/2012 10/1612012 10/16/2012 Req.

Lab Code ESS- 6711 ESS- 6713 ESS- 6714 LLD Location E-01 E-05 E-06 Gross Beta 14.20 +/- 0,89 < 0.93 10.15 +/- 0.90 < 1.05 12.07

• 0.94 < 1.06 2.0 Be-7 0.028 _ 0.055 < 0.14 -0.02 +/- 0,051 < 0.09 0.058 +/- 0.052 < 0.15 K-40 10.02 +/- 0.51 6.98 +/- 0.42 8.00 t 0.46 Cs-137 0.018 +/- 0.009 < 0.014 0.016 +/- 0.008 < 0.012 0.024 +/- 0.014 < 0.013 0.15 TI-208 0.057 +/- 0.019 0.034 +/- 0.014 0.026 +/- 0.009 < 0.018 -

Pb-212 0.15 +/- 0.055 0.10 +/- 0.040 < 0.081 0.16 +/- 0.056 Bi-214 0.13 + 0.025 0.12 +/- 0.027 0.10 +/- 0.025 Ra-226 0.43 +/- 0.15 < 0.27 0.35 + 0.13 < 0.25 0.15 +/- 0.14 < 0.25 Ac-228 0.16 +/- 0.046 0.14 +/- 0.055 0.18 +/- 0.075 Collection Date 10116/2012 10/16/2012 Lab Code ESS- 6715 ESS- 6716 Annual Location E-12 E-33 Mean -s.d.

Gross Beta 7.60 +/- 0.79 < 0.92 11.36 +/- 0.92 < 1.06 2.0 10.20 +/- 2.24 Be-7 0.035 +/- 0.053 < 0.16 0.45 +/- 0.21 0.073 +/- 0.138 K-40 4.91 +/- 0.38 7.11 +/-7.11 - 6.96 +/- 1.62 Cs-137 0.030 +/- 0.014 < 0.011 0.019 +/- 0.009 < 0.013 0.15 0.019 +/- 0.005 TI-208 0,047 +/- 0.016 0.036 +/- 0.037 - 0.04 +/- 0.01 Pb-212 0.12 +/- 0.019 0.14 +/- 0.144 - 0.13 +/- 0.02 Bi-214 0.12 +/- 0.024 0.11 +/- 0.106 - 0.11 +/- 0.01 Ra-226 0.38 +/- 0.14 < 0.26 0.32 +/- 0.14 < 0.25 0.28 +/- 0.09 Ac-228 0.16 +/- 0.043 0.17 +/- 0.052 0.15 +/- 0.02 8-2

POINT BEACH NUCLEAR PLANT Table 9. Radioactivity in soil samples Collection: Semiannual Sample Description and Concentration (pCi/g dry)

MDC MDC MDC Collection Date 5/30/2012 5/30/2012 5/30/2012 Req.

Lab Code ESO- 3301 ESO- 3302 ESO- 3303 LLD Location E-01 E-02 E-03 Gross Beta 25.19 +/- 1.15 < 1.12 32.30 +/- 1.15 < 0.96 36.27 +/- 1.25 < 1.07 2,0 Be-7 0.064 + 0.090 < 0.22 -0.037 +/- 0.11 < 0.24 0.12 +/- 0.10 < 0.22 K-40 10.67 +/- 1.04 20.51 +/- 0.94 18.73 +/- 0.85 Cs-137 0.17 +/- 0.031 < 0.020 0.16 +/- 0.034 < 0.032 0.39 +/- 0.044 < 0.027 0.15 TI-208 0.16 +/- 0.029 0.19 t 0.034 0.19 +/- 0.029 Pb-212 0.49 +/- 0.093 0.53 +/- 0.043 0.65 +/- 0.11 Bi-214 0.27 +/- 0.047 0.36 +/- 0.052 0.39 +/- 0.047 Ra-226 1.12 +/- 0.28 1.35 +/- 0.36 1.22 +/- 0.32 Ac-228 0.44 +/- 0.10 0.70 +/- 0.10 0.81 +/- 0.14 Collection Date 5/30/2012 5/30/2012 5/30/2012 Lab Code ESO- 3304 ESO- 3305 ESO- 3307 Location E-04 E-06 E-08 Gross Beta 27.21 +/- 1.07 < 0.92 10.95 +/- 0.89 < 1.02 18.83 +/- 1.05 < 1.09 2.0 Be-7 0.040 +/- 0.081 < 0.21 -0.014 +/- 0.054 < 0.092 0.11 +/- 0.082 < 0.21 K-40 16.88 +/- 0.79 7.21

• 0.45 12.05 +/- 0.67 Cs-137 0.14 +/- 0.028 < 0.024 0.024 +/- 0.013 < 0,012 0.035 +/- 0.021 <0.021 0.15 TI-208 0.13 +/- 0.026 0.068 +/- 0.018 0.082 +/- 0.029 Pb-212 0.31 +/- 0.031 0.15 +/- 0.022 0.22 +/- 0.029 Bi-214 0.25 +/- 0.044 0.094 +/- 0.029 0.12 +/- 0.036 Ra-226 1.01 +/- 0.33 0.42 +/- 0.14 < 0.27 0.52 +/- 0.21 < 0.45 Ac-228 0.45 +/- 0.10 0.23 +/- 0.057 0.30 +/- 0.076 Collection Date 5/30/2012 5/30/2012 Lab Code ESO- 3308 ESO- 3309 Location E-09 E-20 Gross Beta 30.01 +/- 1.12 < 0.96 25.13 +/- 1.11 < 1.06 2.0 Be-7 -0.016 +/- 0.099 < 0.21 0.089 +/- 0.101 < 0.22 K-40 19.18 +/- 0.91 - 7.98 +/- 0.93 -

Cs-137 0.14 +/- 0.028 < 0.028 0.14 +/- 0.040 < 0.039;) 0.15 TI-208 0.17 +/- 0.032 - 0.14 +/- 0.038 -

Pb-212 0.48 t 0.041 - 0.43 +/- 0.057 Bi-214 0.51 +/- 0.056 - 0.25 +/- 0.053 -

Ra-226 1.66 +/- 0.41 - 0.77 +/- 0.31 -

Ac-228 0.57 +/- 0.10 - 0.49 +/- 0.11 -

9-1

POINT BEACH NUCLEAR PLANT Table 9. Radioactivity in soil samples Collection: Semiannual Sample Description and Concentration (pCilg dry)

MDC MDC MDC Collection Date 10131/2012 10/31/2012 10/31/2012 Req.

Lab Code ESO- 7135 ESO- 7136 ESO-, 7137 LLD Location E-01 E-02 E-03 Gross Beta 23.22 +/- 1.10 < 1.09 27.15 +/- 1.05 < 0.91 26.40 +/- 1.12 < 1.05 2.0 Be-7 -0.057 +/- 0.090 < 0.17 0.092 +/- 0.078 < 0.20 0.043 +/- 0.11 < 0.22 K-40 12.40 +/- 0.61 15.40 +/- 0.67 16.10 +/- 0.88 Cs-137 0.12 +/- 0.031 < 0.026 0.054 +/- 0.021 < 0.026 0.13 +/- 0.032 < 0.024 0.15 TI-208 0.13 +/- 0.027 0.15 +/- 0.028 0.17 +/- 0.036 Pb-212 0.37 +/- 0.030 0.42 +/- 0.032 0.44 +/- 0.060 Bi-214 0.33 +/- 0.040 0.33 +/- 0.039 0.36 +/- 0.052 Ra-226 0.85 +/- 0.27 0.96 +/- 0.26 0.84 +/- 0.32 Ac-228 0.44 +/- 0.10 0.45 +/- 0.073 0.68 +/- 0.13 Collection Date 10/31/2012 10/31/2012 10/3112012 Lab Code ESO- 7138 ESO- 7139 ESO- 7140 Location E-04 E-06 E-08 Gross Beta 17.56 +/- 0.93 < 0.91 15.51 +/- 0.90 < 0.92 23.33 +/- 1.06 < 1.02 2.0 Be-7 0.074 +/- 0.076 < 0.18 0.061 +/- 0.060 < 0.15 0.06 +/- 0.076 < 0.16 K-40 9.94 +/- 0.61 8.02 +/- 0,50 13.28 +/- 0.69 Cs-137 0.19 +/- 0.030 < 0.019 0.26 +/- 0.027 < 0.017 0.15 +/- 0.022 < 0.014 0.15 TI-208 0.081 +/- 0.084 0.086 +/- 0.020 0.11 +/- 0.028 Pb-212 0.35 +/- 0.355 0.24 +/- 0.033 0.29 +/- 0.031 Bi-214 0.21 +/- 0.207 0.14 +/- 0.033 0.29 +/- 0.044 Ra-226 0.47 +/- 0.47 0.40 +/- 0.17 < 0.32 0.50 +/- 0.25 Ac-228 0.28 +/- 0.29 0.24 +/- 0.062 0.36 +/- 0.083 Collection Date 10/31/2012 10/31/2012 Lab Code ESO- 7141 ESO- 7142 Annual Location E-09 E-20 Mean + s.d.

Gross Beta 30.83 +/- 1.13 < 1.00 23.01 +/- 0.98 < 0.89 24.56 +/- 6.52 2.0 Be-7 0.032 +/- 0.11 < 0.26 0.057 +/- 0.089 < 0.20 0.044 -t 0.05 K-40 18.23 +/- 0.79 12.93 +/- 0.67 13.72 +/- 4.29 Cs-137 0.13 +/- 0.026 < 0.026 0.11 +/- 0.032 < 0.022 0.15 +/- 0.09 0.15 TI-208 0.17 +/- 0.033 0.13 +/- 0.031 0.13 +/- 0.04 Pb-212 0.50 +/- 0.036 0.40 +/- 0.040 0.39 +/- 0.13 Bi-214 0.89 +/- 0.065 0.44 +/- 0.048 0.33 +/--0.19 Ra-226 0.81 +/- 0.32 0.64 +/- 0.26 0.85 +/- 0.36 Ac-228 0.58 +/- 0.095 0.53 +/- 0.12 0.47 +/- 0.17 9-2

POINT BEACH NUCLEAR PLANT Table 10. Radioactivity in vegetation samples Collection: Tri-annual Sample Description and Concentration (pCi/g wet)

MDC MDC MDC Location E-01 E-02 E-03 Collection Date 5/23/2012 5/23/2012 5/23/2012 Lab Code EG- 3091 EG- 3092 EG- 3093 Req. LLD Ratio (wet/dry) 4.00 4.44 3.81 Gross Beta 6.87 +/- 0.13 < 0.041 8.56 +/- 0.15 < 0.047 8.04 +/- 0.15 < 0.052 0.25 Be-7 1.01 :t 0.17 0.22 +/- 0.12 0.17 +/- 0.06 < 0.13 K-40 4.82 +/- 0.36 7.11 +/- 0.46 7.10 +/- 0,43 1-131 0.009 +/- 0.007 < 0.028 -0.009 +/- 0.007 < 0.017 -0.006 +/- 0.006 < 0.013 0.060 Cs-134 0.004 +/- 0.006 < 0.010 -0.003 +/- 0.006 < 0.009 0.001 +/- 0.006 < 0.009 0.060 Cs-137 0.000 +/- 0.007 < 0.010 0,000 +/- 0.008 < 0.012 -0.004 +/- 0.007 < 0.011 0.080 Other (Co-60) 0.004 +/- 0.006 < 0.010 0.009 +/- 0.006 < 0.010 0.002 +/- 0.007 < 0.010 0.060 Location E-04 E-06 E-08 Collection Date 5/23/2012 5/23/2012 5/23/2012 Lab Code EG- 3094 EG- 3096 EG- 3097 Req. LLD Ratio (wet/dry) 4.07 3.55 4.14 Gross Beta 7.89 +/- 0.16 < 0.048 7.85 +/- 0.15 < 0.044 7.19 +/- 0.14 < 0.044 0.25 Be-7 0.42 +/- 0.14 1.14 + 0.15 0.88 +/- 0.13 K-40 6.49 +/- 0.46 4.98 +/- 0.33 6.03

• 0.32 1-131 0.001 +/- 0.008 < 0.030 0.001 +/- 0.005 < 0.016 -0.003 +0.006 < 0.019 0.060 Cs-134 -0.002 +/- 0,007 < 0.011 0.003 +/- 0.006 < 0,009 0.001 ` 0.006 < 0.011 0.060 Cs-137 -0.001 +/- 0.009 < 0.014 -0.001 +/- 0.007 < 0.013 0.004 +/- 0.007 < 0.010 0.080 Other (Co-60) -0.003 _ 0.009 < 0.011 0.004 +/- 0.006 < 0.009 0.001 . 0.006 < 0.010 0.060 Location E-09 E-20 Collection Date 5/23/2012 5/23/2012 Lab Code EG- 3098 EG- 3099 Req. LLD Ratio (wet/dry) 4.40 6.33 Gross Beta 7.03 +/- 0.14 < 0.046 7.62 +/- 0.14 < 0.042 0.25 Be-7 0.29 + 0.12 0.35 +/- 0.15 K-40 6.08 +/- 0.42 6.51 +/- 0.41 1-131 0.011 +/- 0.007 < 0.025 -0.002 +/- 0.007 < 0.023 0.060 Cs-1 34 0.002 +/- 0.007 < 0.011 -0.001 +/- 0.006 < 0.006 0.060 Cs-1137 0.002 +/- 0.009 < 0.013 0.001 +/- 0.008 < 0.015 0.080 Other (Co-60) 0.005 +/- 0.007 < 0.008 0.002 +/- 0.008 < 0.015 0.060 10-1

POINT BEACH NUCLEAR PLANT Table 10, Radioactivity in vegetation samples Collection: Tri-annual Sample Description and Concentration (pCi/g wet)

MDC MDC MDC Location E-01 E-02 E-03 Collection Date 7/24/2012 7/24/2012 7/24/2012 Lab Code EG- 4467 EG- 4468 EG- 4469 Req. LLD Ratio (wet/dry) 4.34 3.08 3.02 Gross Beta 6.80 + 0.21 < 0078 7.75 +/- 0.23 < 0.075 6.10 +/- 0.22 < 0.087 0.25 Be-7 2.22 +/- 0.26 1.46 +/- 0.20 1.52 +/- 0.15 K-40 3.89 +/- 0.41 4.68 +/- 0.38 6.81 +/- 0.39 1-131 0.000 +/- 0.011 < 0.034 -0.006 +/- 0.006 < 0.018 -0.002 +/- 0.005 < 0.017 0.060 Cs-1 34 -0.006 +/- 0.010 < 0.013 0.004 +/- 0.007 < 0.013 -0.002 +/- 0.005 < 0.012 0.060 Cs-137 0.001 +/- 0.009 < 0,013 -0.001 +/- 0.008 < 0.016 -0.004 +/- 0.007 < 0.008 0.080 Other (Co-60) 0.002 +/- 0.009 < 0.014 0.003 +/- 0.008 S0.012 0.004 +/- 0.006 < 0.010 0.060 Location E-04 E-06 E-08 Collection Date 7/24/2012 7/24/2012 7/24/2012 Lab Code EG- 4470 EG- 4471 EG- 4472 Req. LLD Ratio (wet/dry) 4.58 2.64 2.71 Gross Beta 5.03 +/- 0.16 < 0.063 3.71 +/- 0.12 < 0.045 7.65 +/- 0.24 < 0.085 0.25 Be-7 2.01 +/- 0.24 1.36 +/- 0.18 2.96 +/- 0.30 K-40 4.89 +/- 0.38 3.22 +/- 0.34 5.48 +/- 0.49 1-131 -0.011 - 0.008 < 0.027 0.005 +/- 0.009

• 0.022 0.019 +/- 0.010 < 0.040 0.060 Cs-134 -0.006 - 0.006 < 0.009 -0.008 + 0.008 < 0.012 -0.008 +/- 0.008 < 0.011 0.060 Cs-1 37 0.006 - 0.008 < 0.012 0.006 +/- 0.009 < 0.013 0.013 +/- 0.011 < 0.018 0.080 Other (Co-60) 0.002 - 0.007 < 0.008 -0.003 +/- 0.007 < 0.010 0.007 +/- 0.010 < 0.019 0.060 Location E-09 E-20 Collection Date 7/24/2012 7/24/2012 Lab Code EG- 4473 EG- 4474 Req. LLD Ratio (wet/dry) 3.08 3.75 Gross Beta 7.64 +/- 0.23 < 0.082 7.37 +/- 0.23 < 0.084 0.25 Be-7 1.84 +/- 0.26 1.38 +/- 0.28 K-40 6.67 +/- 0.56 7.56 +/- 0.69 1-131 0.001 +/- 0.009 < 0.037 0.022 +/- 0.011 < 0.041 0.060 Cs-1 34 -0.001 +/- 0.007 < 0.015 -0.004 +/- 0.010 < 0.017 0.060 Cs-137 0.002 +/- 0.010 < 0.016 0.009 +/- 0.013

• 0.023 0.080 Other (Co-60) -0.008 +/- 0.011 < 0.022 0.003 +/- 0.011 < 0.011 0.060 10-2

POINT BEACH NUCLEAR PLANT Table 10. Radioactivity in vegetation samples Collection: Tri-annual Sample Description and Concentration (pCifg wet)

MDC MDC MDC Location E-01 E-02 E-03 Collection Date 9/17/2012 9/17/2012 9/17/2012 Lab Code EG- 5916 EG- 5917 EG- 5918 Req. LLD Ratio (wet/dry) 3.29 3.76 3.52 Gross Beta 5.75 +/- 0..11 <0.047 6.37 +/- 0.15 < 0.061 9.79 +/- 0.14 < 0.043 0.25 Be-7 3.00

• 0.16 1.55 +/- 0.24 1.32 +/- 0.10 K-40 4.25 - 0.23 5.09 +/- 0.48 7.66 +/- 0.21 1-131 0.005 + 0.005

• 0.033 -0.013 +/- 0.008 < 0.044 -0.013 +/- 0.004 < 0.021 0.060 Cs-134 0.002 +/- 0.004 < 0.008 -0.004 +/- 0.007 < 0.012 -0.001 +/- 0.004 < 0.007 0.060 Cs-137 0.000 +/- 0.005 < 0.008 0.001 +/- 0.010 < 0.020 -0.003 +/- 0.004 < 0.006 0.080 Other (Co-60) -0.003 +/- 0.005 < 0.010 0.004 +/- 0.010 < 0.017 0.000 +/- 0.004 < 0.006 0.060 Location E-04 E-06 E-08 Collection Date 9/17/2012 9/17/2012 9/17/2012 Lab Code EG- 5919 EG- 5920 EG- 5921 Req. LLD Ratio (wet/dry) 4.33 3.10 3.43 Gross Beta 6.57 _ 0.12 < 0.048 5.95 +/- 0.19 < 0.096 6.12 +/- 0.15 < 0.059 0.25 Be-7 1.51 +/- 0.13 3.62 +/- 0.32 3.02 +/- 0:27 K-40 6.48 +/- 0.30 4.78 +/- 0.43 4.56 +/- 0.38 1-131 -0.009 +/- 0.005 < 0.022 0.018 " 0.008 < 0.052 0.015 +/- 0.008 < 0.044 0.060 Cs-134 0.002 +/- 0.004 < 0.006 0.002 +/- 0.007 < 0.014 0.000 +/- 0.006 < 0.012 0.060 Cs-137 0.008 +/- 0.005 < 0.010 0.051 +/- 0.022 < 0.021 0.001 +/- 0.008 < 0.013 0.080 Other (Co-60) 0.002 +/- 0.006 < 0.009 0.003 + 0.009 < 0.017 0.001 +/- 0.008 < 0.008 0.060 Location E-09 E-20 Collection Date 9/17/2012 9/17/2012 Lab Code EG- 5922 EG- 5924 Req. LLD Ratio (wet/dry) 2.80 5.04 Gross Beta 7.41 +/- 0.16 < 0.067 7.31 +/-0.18 < 0.067 0.25 Be-7 2.58 +/- 0.12 2.59 +/- 0.25 K-40 5.07 +/- 0.18 6.68 +/- 0.47 1-131 -0.004 +/- 0.003 < 0.025 -0.003  : 0.008 < 0.050 0.060 Cs-134 -0.002 +/- 0.003 < 0.005 0.005 +/- 0.007 < 0.013 0.060 Cs-137 0.003 +/- 0.004 < 0.008 0.001 +/- 0.008 < 0.013 0.080 Other (Co-60) 0.003 +/- 0.004 < 0.005 0.001 +/- 0.009 < 0.013 0.060 Beta Annual Mean +/- s.d. 6.92 +/- 1.12 Be-7 Annual Mean +/- s.d. 1.60 +/- 0.99 K-40 Annual Mean t s.d. 5.70 t 1.22 1-131 Annual Mean +/- s.d. 0.001 +/- 0.010 Cs-134 Annual Mean +/- s.d. -0.001 +0.004 Cs-137 Annual Mean +/- s.d. 0.004 +/- 0.011 Co-60 Annual Mean +/- s.d. 0.001 + 0.004 10-3

POINT BEACH NUCLEAR PLANT Table 11. Aquatic Vegetation, analyses for gross beta and gamma emitting isotopes.

Collection: Triannual Units: pCi/g wet Sample Description and Concentration Collection Date 06-06-12 MDC 06-06-12 MDC Req.

Lab Code ESL- 3460 ESL- 3461 LLD Location E-05 E-12 Ratio (wet wt./dry wt.) 4.56 2.67 Gross Beta 4.49 + 0.18 < 0.16 5.70 +/- 0.23 < 0.20 0.25 Be-7 1.65 + 0.17 0.77 +/- 0.15 K-40 2.99 + 0.29 3.91 +/- 0.36 Co-58 0.010 + 0.006 < 0.011 0.004 +/- 0.006 < 0.013 0.25 Co-60 0.006 + 0.007 < 0.011 0.001 +/- 0.008 < 0.013 0.25 Cs-134 -0.002 + 0.005 < 0.011 -0.001 +/- 0.005 < 0.010 0.25 Cs-137 0.035 _ 0.012 < 0.013 0.017 +/- 0.009 < 0.014 0.25 Collection Date 08-07-12 08-07-12 Req.

Lab Code ESL- 4949 ESL- 4950 LLD Location E-05 E-12 Ratio (wet wt./dry wt.) 6.21 3.28 Gross Beta 3.34 +/- 0.15 < 0.14 4.56 +/- 0.24 < 0.24 0.25 Be-7 1.03 +/- 0.21 0.87 +/- 0.15 K-40 2.58 +/- 0.27 6.08 +/- 0.33 Co-58 -0.005 +/- 0.006 < 0.009 0.001 +/- 0.005 < 0.013 0.25 Co-60 0.007 _ 0.006 < 0.010 0.000 +/- 0.006 < 0.009 0.25 Cs-134 0.003 +/- 0.005 < 0.008 -0.004 +/- 0.005 < 0.007 0.25 Cs-137 0.009 + 0.008 < 0.014 0.011 +/- 0.007 < 0.013 0.25 Collection Date 10-09-12 10-09-12 Req.

Lab Code ESL- 6316 ESL- 6317 LLD Annual Location E-05 E-12 Mean +/- s.d.

Ratio (wet wt./dry wt.) 2.49 2.82 Gross Beta 7.16 +/- 0.28 < 0.24 6.53 +/- 0.22 < 0.18 0.25 5.30 + 1.43 Be-7 0.48 +/- 0.07 0.72 +/- 0.12 0.92 +/- 0.40 K-40 5.39 +/- 0.14 3.91 +/- 0.56 4.14 +/- 1.36 Co-58 0.001 +/- 0.002 < 0.006 0.009 +/- 0.013 < 0.035 0.25 0.003 +/- 0.006 Co-60 0.000 +/- 0.003 < 0.004 -0.004 +/- 0.015 < 0.022 0.25 0.002 +/- 0.004 Cs-134 -0.002 +/- 0.002 < 0.004 -0.004 +/- 0.012 < 0.028 0.25 -0.002 +/- 0.002 Cs-137 0.021 +/- 0.005 < 0.006 0.034 + 0.017 < 0.035 0.25 0.021 + 0.011 11-1

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation LLD/7days: < lmRITLD 1st. Quarter, 2012 Date Annealed: 12-19-11 Days in the field 89 Date Placed: 01-06-12 Days from Annealing Date Removed: 04-04-12 to Readout: 109 Date Read: 04-06-12 Days in mRlStnd Qtr Location Field Total mR Net mR (91 days) Net mR per 7 days Indicator E-1 89 13.5 +/- 0.5 10.8 +/- 0.6 13.8 +/- 0.5 0.85 +/- 0.05 E-2 89 18.7 +/- 0.4 16.0 +/- 0.5 19.1 +/- 0.4 1.25 +/- 0.04 E-3 89 23.1 +/- 1.8 20.4 +/- 1.8 23.6 +/- 1.8 1.60 +/- 0.14 E-4 89 17.3 +/- 1.5 14.6 +/- 1.5 17.7 +/- 1.5 1.14 +/- 0.12 E-5 89 18.0 +/- 1.3 15.3 +/- 1.3 18.4 +/- 1.3 1.20 +/- 0.11 E-6 89 17.0 +/- 0,8 14.3 +/- 0.9 17.4 +/- 0.8 1.12 +/- 0,07 E-7 89 18.4 +/- 0.5 15.7 +/- 0.6 18.8 +/- 0.5 1.23 +/- 0.05 E-8 89 17.7 +/- 1.0 15.0 +/- 1.1 18.1 +/- 1.1 1.18 +/- 0.08 E-9 89 20.1 +/- 0.3 17.4 +/-. 5 20.5 +/- 0.3 1.36 +/- 0.04 E-12 89 14.3 +/- 0.4 11.6 +/-+0.5 14.4 +/- 0.5 0.91 +/- 0.04 E-14 89 19.2 +/- 0.6 16.5 +/- 0.7 19.6 +/- 0.6 1.29 +/- 0.06 E-1 5 89 15.6 +/- 0.3 12.9 +/- 0.5 16.0 +/- 0,3 1.01 +/- 0.04 E-16 89 17.3 +/- 0.3 14.6 +/- 0.5 17.7 +/- 0.3 1.14 +/- 0.04 E-1 7 89 18.5 +/- 0.6 15.8 +/- 0.7 18.8 +/- 0.6 1.24 +/- 0.06 E-18 89 19.5 +/- 1.1 16.8 +/- 1.2 20.0 +/- 1.2 1.32 +/- 0.09 E-22 89 19.1 +/-1.2 16.4 +/- 1.3 19.5 +/- 1.2 1.29 +/- 0.10 E-23 89 18.7 +/-0.4 16.0 +/- 0.5 19.1 +/- 0.5 1.25 +/- 0.04 E-24 89 18.8 +/- 0.7 16.1 +/- 0.8 19.2 +/- 0.7 1.26 +/- 0.06 E-25 89 17.7 +/- 0.5 15.0 +/- 0.6 18.1 +/- 0.5 1.18 +/- 0.05 E-26 89 16.0 +/- 0.4 13.3 +/- 0.5 16.3 +/- 0.4 1.04 +/- 0.04 E-27 89 19.9 ` 0.3 17,2 +/-0.5 20.4 +/- 0.3 1.35 +/- 0.04 E-28 89 13.9 +/- 0.4 11.2 +/-.0.5 14.3 +/- 0.4 0.88 +/- 0.04 E-29 89 14.5 +/- 0.7 11.8 +/-.0.8 14,6 +/- 0.7 0.92 +/- 0.06 E-30 89 16.7 +/- 0.9 14.0 +/- 1.0 16.9 +/- 0.9 1.10 +/- 0.08 E-31 89 15.9 +/- 0.2 13.2 +/- 0.4 16.3 +/- 0.2 1.03 +/- 0.03 E-32 89 21.1 +/- 0.7 18.4 +/- 0.8 21.6 +/- 0.7 1.44 +/- 0.06 E-38 89 18.4 +/- 1.5 15.7 +/- 1.5 18.8 +/- 1.5 1.23 +/- 0.12 E-39 89 16.6 +/- 0.8 13.9 +/- 0.9 16.8 +/- 0.8 1.09 +/- 0.07 E-41 89 16.1 +/- 0.7 13.4 +/- 0.8 16.3 +/- 0.7 1.05 +/- 0.06 E-42 89 17.0 +/- 0.9 14.3 +/- 1.0 17.2 +/- 0.9 1.12 +/- 0.08 E-43 89 16.5 +/- 0.7 13.8 +/- 0.8 16.7 +/- 0.7 1.08 +/- 0.06 Control E-20 89 17.8 +/- 1.0 15.1 +/-1.1 18.2 +/- 1.0 1.18 +/- 0.08 Mean+/-s.d. 17.6 +/- 2.1 14.8 +/-2.1 17.9 +/-2.2 1.17 +/- 0.16 In-Transit Exposure Date Annealed Date Read ITC-1 ITC-2 12-19-11 01-12-12 3.0 +/--0.2 2.9 +/- 0.2 03-21-12 04-09-12 2.6 +/-+0.1 2.5 +/- 0.2 a The CaSO4 :Dy dosimeter cards provide four separate readout areas. Values listed represent the mean and standard deviation of the average of the four readings.

12-1

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation a LLD/7days: < 1mR/TLD 2nd Quarter, 2012 Date Annealed: 03-21-12 Days in the field 90 Date Placed: 04-04-12 Days from Annealing Date Removed: 07-03-12 to Readout: 112 Date Read: 07-11-12 Days in mR/Stnd Qtr Location Field Total mR Net mR (91 days) Net mR per 7 days Indicator E-1 90 13.8 +/- 0.5 10.6 +/- 0.7 14.0 +/- 0.5 0.82 +/- 0.05 E-2 90 19.6 +/- 0.8 16.4 +/- 0.9 19.8 +/- 0.8 1.27 +/- 0.07 E-3 90 21.6 +/- 1.2 18.4 +/- 1.3 21.9 +/- 1.2 1.43 + 0.10 E-4 90 17.0 +/- 0.5 13.8 +/- 0.7 17.2 +/--0.5 1.07 +/- 0.05 E-5 90 19.2 +/- 0.5 16.0 +/- 0.7 19.4 +/- 0.5 1.24 +/- 0.05 E-6 90 16.5 +/- 0.2 13.3 +/- 0.5 16.7 +/- 0.3 1.03 +/- 0.04 E-7 90 16.3 +/- 0.4 13.1 +/-0.6 16.5 +/-0.4 1.02 - 0.05 E-8 90 17.3 +/- 0.8 14.1 +/- 0.9 17.5 +/- 0.8 1.09 +/- 0.07 E-9 90 19.2 +/- 0.7 16.0 +/- 0.8 19.4 +/- 0.7 1.24 +/- 0.06 E-12 90 13.6 +/- 1.0 10.4 +/- 1.1 13.9 +/- 1.0 0.81 - 0.08 E-14 90 17.9 +/- 1.3 14.7 +/- 1.4 18.1 +/- 1.3 1.14 +/- 0.11 E-15 90 20.2 +/- 1.1 17.0 +/- 1.2 20.4 +/- 1.1 1.32 +/- 0.09 E-16 90 16.8 +/- 0.3 13.6 +/-0.5 17.0 +/- 0.3 1.06 + 0.04 E-17 90 17.6 +/- 1.1 14.4 +/- 1.2 17.8 +/- 1.1 1.12 +/- 0.09 E-18 90 18.8 +/- 0.2 15.6 +/- 0.5 19.0 +/- 0.3 1.21 +/- 0.04 E-22 90 18.3 +/- 0.5 15.1 +/-0.7 18.5 +/- 0.5 1.17 +/- 0.05 E-23 90 19.9 +/- 0.6 16.7 +/- 0.7 20.2 +/- 0.6 1.30 + 0.06 E-24 90 17.9 +/- 0.1 14.7 +/- 0.4 18.1 +/- 0.1 1.14 +/- 0.03 E-25 90 19.5 +/- 0.6 16.3 +/- 0.7 19.8 +/- 0.6 1.27 +/- 0.06 E-26 90 15.7 +/- 0.9 12.5 +/- 1.0 15.9 +/- 0.9 0.97 +/- 0.08 E-27 90 20.9 +/- 0.8 17.7 +/- 0.9 21.1 +/- 0.8 1.37 +/- 0.07 E-28 90 13.8 +/- 0.4 10.6 +/- 0.6 14.2 +/- 0.4 0.82 +/- 0.05 E-29 90 14.3 +/- 0.7 11.1 +/-0.8 14.6 +/- 0.7 0.86 +/- 0.06 E-30 90 16.8 +/- 0.5 13.6 +/- 0.7 17.1 +/- 0.5 1.06 +/- 0.05 E-31 90 20.1 +/- 1.5 16.9 +/- 1.6 20.3 +/- 1.5 1.31 +/- 0.12 E-32 90 20.1 +/- 0.4 16.9 +/- 0.6 20.3 +/- 0.4 1.31 +/- 0.05 E-38 90 16.9 +/- 0.4 13.7 +/- 0.6 17.2 +/- 0.4 1.06 +/- 0.05 E-39 90 16.8 +/--0.7 13.6 +/- 0.8 17.2 +/- 0.7 1.06 +/- 0.06 E-41 90 17.2 +/- 0.6 14.0 +/- 0.7 17.5 +/- 0.6 1.09 +/- 0.06 E-42 90 18.3 +/- 0.5 15.1 +/- 0.7 18.7 +/- 0.5 1.17 +/- 0.05 E-43 90 16.3 +/- 0.5 13.1 +/- 0.7 16.6 +/- 0.5 1.02 +/- 0.05 Control E-20 92 16.8 +/-0 .7 13.6 +/- 0.8 17.0 +/- 0.7 1.03 +/- 0.06 Mean+/-s.d. 17.7 +/- 2.1 14.4 t 2.1 17.9 +/- 2.1 1.12 +/- 0.16 In-Transit Exposure Date Annealed Date Read ITC-1 ITC-2 03-21-12 04-09-12 2.6 +/- 0.1 2.5 +/-0.2 06-12-12 07-11-12 4.0 +/- 0.3 3.8 +/- 0.2 a The CaSO 4:Dy dosimeter cards provide four separate readout areas. Values listed represent the mean and standard deviation of the average of the four readings.

12-2

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation a LLD/7days: < 1mR/TLD 3rd Quarter, 2012 Date Annealed: 06-12-12 Days in the field 91 Date Placed: 07-03-12 Days from Annealing Date Removed: 10-02-12 to Readout: 118 Date Read: 10-08-12 Days in mR/Stnd Qtr Location Field Total mR Net mR (91 days) Net mR per 7 days Indicator E-1 91 14.4 +/- 0.4 10.8 +/- 0.6 14.4 +/- 0.4 0.83 +/- 0.04 E-2 91 19.9 +/- 0.4 16.3 +/- 0.6 19.9 +/- 0.4 1.25 +/- 0.04 E-3 91 23.5 +/- 2.2 19.9 +/- 2.2 23.5 +/- 2.2 1.53 +/- 0.17 E-4 91 18.7 +/- 0.9 15.1 +/- 1.0 18.7 +/- 0.9 1.16 +/- 0.08 E-5 91 19.9 +/- 1.1 16.3 +/- 1.2 19.9 +/- 1.1 1.25 +/- 0.09 E-6 91 18.4 +/- 0.8 14.8 +/- 0.9 18.4 +/-0.8 1.13 +/- 0.07 E-7 91 19.3 +/- 0.9 15.7 +/- 1.0 19.3 +/-0.9 1.20 +/- 0.08 E-8 91 19.3 +/- 1.4 15.7 +/- 1.5 19.3 +/- 1.4 1.20 +/- 0.11 E-9 91 21.7 +/- 0.2 18.1 +/- 0.5 21.7 +/- 0.2 1.39 +/- 0.04 E-1 2 91 15.6 +/- 0.5 12.0 +/- 0.6 15.6 +/- 0.5 0.92 +/- 0.05 E-14 91 20.4 +/- 0.5 16.8 +/- 0.7 20.4 +/- 0.5 1.29 +/- 0.05 E-15 91 17.3 _+0.3 13.7 +/- 0.5 17.3 +/- 0.3 1.05 +/- 0.04 E-16 91 18.7 +/- 0.3 15.1 +/- 0.5 18.7 +/- 0.3 1.16 +/- 0.04 E-17 91 19.9 +/- 0.6 16.3 +/- 0.7 19.9 +/- 0.6 1.25 +/- 0.06 E-18 91 21.4 +/- 0.9 17.8 +/- 1.0 21.4 +/- 0.9 1.37 +/- 0.08 E-22 91 20.4 +/- 1.2 16.8 +/- 1.3 20.4 +/- 1.2 1.29 +/- 0.10 E-23 91 20.4 +/- 0.4 16.8 +/- 0.6 20.4 +/- 0.4 1.29 +/- 0.04 E-24 91 20.0 +/- 0.7 16.4 +/- 0.8 20.0 +/- 0.7 1.26 +/- 0.06 E-25 91 19.6 +/- 0.4 16.0 +/- 0.6 19.6 +/- 0.4 1.23 +/- 0.04 E-26 91 17.7 +/- 0.4 14.1 +/- 0.6 17.7 +/- 0.4 1.08 +/- 0.04 E-27 91 21.8 +/- 0.5 18.2 +/- 0.6 21.8 +/- 0.5 1.40 +/- 0.05 E-28 91 14.9 +/- 0.5 11.3 +/- 0.7 14.9 +/- 0.5 0.87 +/- 0.05 E-29 91 15.6 +/-_0.9 12.0 +/- 1.0 15.6 +/- 0.9 0.92 +/- 0.08 E-30 91 18.3 +/- 0.8 14.7 +/- 0.9 18.3 +/- 0.8 1.13 +/- 0.07 E-31 91 17.8 +/- 0.4 14.2 +/- 0.6 17.8 +/- 0.4 1.09 +/- 0.04 E-32 91 22.8 +/- 0.9 19.2 +/- 1.0 22.8 +/- 0.9 1.47 +/- 0.08 E-38 91 19.7 +/- 1.4 16.1 +/- 1.5 19.7 +/- 1.4 1.23 +/- 0.11 E-39 91 17.9 +/- 0.7 14.3 +/-+0.8 17.9 +/- 0.7 1.10 +/- 0.06 E-41 91 18.1 +/- 0.6 14.5 +/- 0.7 18.1 +/- 0.6 1,11 +/- 0.06 E-42 91 18.9 +/- 0.3 15.3 +/--0.5 18.9 +/- 0.3 1.17 +/- 0.04 E-43 91 18.6 +/- 0.8 15.0 +/- 0.9 18.6 +/- 0.8 1.15 +/- 0.07 Control E-20 91 19.0 +/- 1.1 15.4 +/- 1.2 19.0 +/- 1.1 1.18 +/- 0.09 Mean+/-s.d. 19.1 +/-_2.1 15.4 +/-+2,1 19.1 +/- 2.1 1.19 +/- 0.15 In-Transit Exposure Date Annealed Date Read ITC-1 ITC-2 06-12-12 07-11-12 4.0 +/-0.3 3.8 +/-0.2 09-10-12 09-10-12 3.4 +/-0.2 3.4 +/- 0.1 The CaSO 4 :Dy dosimeter cards provide four separate readout areas. Values listed represent the mean and standard deviation of the average of the four readings.

12-3

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation a LLD/7days: < 1mR/TLD 4th Quarter, 2012 Date Annealed: 09-10-12 Days in the field 92 Date Placed: 10-02-12 Days from Annealing Date Removed: 01-02-13 to Readout: 120 Date Read: 01-08-13 Days in mR/Stnd Qtr Location Field Total mR Net mR (91 days) Net mR per 7 days Indicator E-1 92 16.0 +/- 0.9 12.0 +/- 1.0 15.8 +/-0.9 0.91 +/- 0.08 E-2 92 22.5 +/- 1.1 18.5 +/- 1.2 22.2 +/- 1.1 1.40 +/- 0.09 E-3 92 24.8 +/- 1.5 20.8 +/- 1.6 24.6 +/- 1.5 1.58 + 0.12 E-4 92 20.3 +/- 1.5 16.3 +/- 1.6 20.1 +/- 1.4 1.24 + 0.12 E-5 92 21.7 +/- 0.5 17.7 +/- 0.7 21.5 +/- 0.5 1.34 + 0.05 E-6 92 20.2 +/- 1.5 16.2 +/- 1.6 20.0 +/- 1.4 1.23 + 0.12 E-7 92 18.8 +/- 0.3 14.8 +/- 0.5 18.6 +/-0.3 1.12 +/- 0.04 E-8 92 19.8 +/- 0.9 15.8 +/- 1.0 19.6 +/- 0.9 1.20 +/- 0.08 E-9 92 22.2 +/- 0.9 18.2 +/- 1.0 21.9 +/- 0.9 1.38 +/- 0.08 E-12 92 16.4 +/- 1.0 12.4 +/- 1.1 16.1 +/-0.9 0.94 +/- 0.08 E-14 92 19.9 +/- 0.6 15.9 +/-0.7 19.7 +/- 0.6 1.21 +/- 0.06 E-15 92 22.8 +/- 0.7 18.8 + 0.8 22.6 +/- 0.7 1.43 + 0.06 E-16 92 19.1 +/- 0.5 15.1 +/- 0.7 18.9 +/- 0.5 1.15 +/-0.05 E-1 7 92 19.8 +/- 1.3 15.8 +/- 1.4 19.6 +/- 1.2 1.20 +/- 0.10 E-1 8 92 20.9 +/- 0.4 16.9 +/- 0.6 20.7 +/- 0,4 1.28 + 0.04 E-22 92 20.6 +/- 0.7 16.6 +/- 0.8 20.3 4 0.7 1.26 +/- 0.06 E-23 92 22.7 +/- 0.4 18.7 +/- 0.6 22.5 +/- 0.3 1.42 + 0.04 E-24 92 20.5 +/- 0.2 16.5 +/- 0.5 20.3 +/- 0.2 1.25 +/- 0.04 E-25 92 22.5 +/- 0.2 18.5 +/- 0.5 22.2 +/- 0.2 1.40 0.04 0

E-26 92 18.7 +/- 1.2 14.7 +/- 1.3 18.5 +/- 1.2 1.11 +/-0.10 E-27 92 22.2 +/- 0.8 18.2 +/- 0.9 22.0 +/- 0.8 1.38 0.07 0

E-28 92 16.2 +/- 1.0 12.2 +/- 1.1 15.8 +/-+1.0 0.92 +/- 0.08 E-29 92 16.4 +/-0.6 12.4 +/- 0.7 16.0 +/-0.6 0.94 +/- 0.06 E-30 92 18.7 +/- 0.7 14.7 +/- 0.8 18.3 +/- 0.7 1.11 +/-0.06 E-31 92 22.3 +/- 1.5 18.3 +/- 1.6 22.0 +/- 1.5 1.39 - 0.12 E-32 92 21.7 +/- 0.3 17.7 +/- 0.5 21.5 +/- 0.3 1.34 00.04 E-38 92 18.7 +/- 0.2 14.7 +/- 0.5 18.3 +/-0.2 1.11 +0.04 E-39 92 18.6 +/- 0.7 14.6 +/- 0.8 18.2 +/- 0.7 1.11 +/--0.06 E-41 92 18.7 +/- 0.7 14.7 +/- 0.8 18.5 +/-0.7 1.11 +/--0.06 E-42 92 20.7 +/- 0.7 16.7 +/- 0.8 20.5 +/- 0.7 1.27 - 0.06 E-43 92 17.8 +/-0.7 13.8 +/- 0.8 17.6 +/-0.7 1.05 +/- 0.06 Control E-20 92 19.1 +/- 1.3 15.1 +/- 1.4 18.8 +/- 1.3 1.15 +/- 0.10 Mean+/-s.d. 20.0 +/- 2.2 16.0 +/- 2.2 19.8 +/- 2.2 1.22 - 0.16 In-Transit Exposure Date Annealed Date Read ITC-1 ITC-2 09-10-12 10-08-12 3.4 +/- 0.2 3.4 +/-0.1 10-08-12 01-08-13 4.7 +/- 0.3 4.7 +/-0.2 a The CaSO4 :Dy dosimeter cards provide four separate readout areas. Values listed represent the mean and standard deviation of the average of the four readings.

Annual Indicator Mean+/-s.d. 18.6 +/- 2.4 15.2 +/- 2.2 18.7 +/- 2.3 1.2 +/- 0.2 Annual Control Mean+/-s.d. 18.2 +/- 1.1 14.8 +/- 0.8 18.3 +/- 0.9 1.1 +/- 0.1 Annual Indicator/Control Mean+/-s.d. 18.6 +/- 2.4 15.2 +/- 2.2 18.7 +/- 2.3 1.2 +/- 0.2 12-4

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Monthly Collections)

Units = pCi/L Intermittent Streams Sample ID GW-01 GW-02 Collection MDC Collection MDC Date Lab Code Tritium (pCi/L) (pca_ Date Lab Code Tritium (pCi/L) (pCi/L) 01-26-12 EWW- 409 22 +/- 77 < 145 01-26-12 EWW- 410 243 +/- 88 < 145 03-01-12 EWW- 1081 37 +/- 74 < 146 03-01-12 EWW- 1083 224 +/- 84 < 146 03-28-12 EWW- 1537 29 +/- 82 < 152 03-28-12 EWW- 1538 204 +/- 90 < 152 04-25-12 EWW- 2322 18 +/- 77 < 153 04-25-12 EWW- 2323 179 +/- 85 < 153 05-31-12 EWW-3378 120 +/- 87 < 155 05-31-12 EWW-3379 46 +/--83 < 155 06-27-12 EWW- 3889 44 +/- 74 < 148 06-27-12 EWW- 3890 111 +/- 77 < 148 07-24-12 EWW-4490 64 +/- 81 < 156 07-24-12 EWW- 4491 136 +/- 84 < 156 08-29-12 EWW- 5439 104 +/- 96 < 150 08-29-12 EWW- 5440 135 +/- 97 < 150 09-19-12 EWW-5958 109 +/- 86 < 153 09-19-12 EWW-5959 179 +/- 89 < 153 10-31-12 EWW- 7129 26 +/- 81 < 152 10-31-12 EWW- 7130 193 +/- 89 < 152 11-27-12 EWW-7625 63 +/- 79 < 144 11-27-12 EWW-7626 122 +/-82 < 144 12-19-12 EWW-8189 16 +/- 77 < 145 12-19-12 EWW-8190 97 +/- 81 < 145 Mean + s.d. 57 +/- 39 Mean +/- s.d. 165 +/- 59 Sample ID GW-03 GW-17 Collection MDC Collection MDC Date Lab Code Tritium (pCi/L) (pcOI) Date Lab Code Tritium (pCi/L) (pCvL) 01-26-12 EWW-411 24 +/- 77 < 145 01-26-12 EWW-413 177 +/- 85 < 145 03-01-12 EWW- 1084 61 +/- 76 < 146 03-01-12 EWW- 1086 171 +/- 81 < 146 03-28-12 EWW- 1539 89 +/- 85 < 152 03-28-12 EWW- 1541 210 +/- 91 < 152 04-25-12 EWW- 2324 82 +/- 80 < 153 04-25-12 EWW- 2326 167 +/-L85 < 153 05-31-12 EWN- 3380 94 +/- 85 < 155 05-31-12 EWW-3382 116 +/- 86 < 152 06-27-12 EWW- 3891 103 +/- 77 < 148 06-27-12 EWW- 3893 109 +/- 77 < 148 07-24-12 EWW- 4492 30 +/- 79 < 156 07-24-12 EWW- 4494 68 +/- 81 < 156 08-29-12 EW1N- 5441 99 +/- 96 < 150 08-29-12 EWW- 5443 97 +/- 95 < 150 09-19-12 EWW-.5960 74 +/- 84 < 153 09-19-12 EWW-5962 311 +/- 95 < 153 10-31-12 EWW- 7131 -14 +/- 79 < 152 10-31-12 EWW-7134 152 +/-87 < 152 11-27-12 EWW- 7627 83 +/- 80 < 144 11-27-12 EWW- 7629 181 +/- 85 < 144 12-19-12 EWW-8191 42 +/- 78 < 145 12-19-12 EWW-8193 63 +/- 79 < 145 Mean +/- s.d. 66 +/- 37 Mean +/- s.d. 160 +/- 66 Wells Sample ID GW-04 (EIC Well) GW-11 (MW-1) [Quarterly]

Collection MOC Collection MOC Date Lab Code Tritium (pCilL) (pCi/L) Date Lab Code Tritium (pCi/L) (pca-)

01-26-12 EWW- 412 -20 +/- 75 < 145 01-26-12 EWW- 533 24 +/- 74 < 146 03-01-12 EWW- 1085 13 +/- 73 < 146 05-21-12 EWW-3688 37 +/- 79 < 147 03-28-12 EWW-1540 -7 +/- 80 < 152 06-20-12 EWW-4786 149 +/- 81 < 152 04-25-12 EWW- 2325 -28 +/- 74 < 153 09-18-12 EWW- 5951 1 +/- 82 < 157 05-31-12 EWW- 3381 70 +/- 84 < 155 10-23-12 EWW- 6916 -1 +/- 78 < 158 06-27-12 EWW- 3892 5 +/- 71 < 148 07-24-12 EWW- 4493 -26 +/- 76 < 156 08-29-12 EWW- 5442 -47 +/- 89 < 150 09-19-12 EWW-5961 8 +/- 81 < 153 10-31-12 EWW- 7132 9 +/- 80 < 152 11-27-12 EWW- 7628 69 +/- 79 < 144 12-19-12 EWW- 8192 -105 +/- 71 < 145 Mean +/- s.d. 4 +/- 37 Mean +/- s.d. 42 +/- 62 13-1

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Quarterly Collections)

Units = pCi/L Wells (cont.)

Sample ID GW-12 (MW-2) GW-13 (MW-6)

Collection MDC Collection MDC Date Lab Code Tritium (pCi/L) (pC'L) Date Lab Code Tritium (pCiIL) (pC/L) 01-26-12 EWW- 534 -42 +/- 70 < 146 01-26-12 EWW-536 36 +/- 75 < 146 05-21-12 EWW- 3689 -35 +/- 75 < 147 05-21-12 EWW- 3690 105 +/- 83 < 147 06-20-12 EWW- 4787 -12 +/- 72 < 152 06-20-12 EWW- 4788 43 +/- 76 < 152 09-18-12 EWW- 5952 -64 +/- 79 < 157 09-18-12 EWW- 5953 32 + 64 < 157 10-23-12 EWW-6917 -6 +/- 78 < 158 10-23-12 EWW-6918 -33 +/- 77 < 158 Mean +/- s.d. -32 +/- 23 Mean t s.d. 37 +/- 49 Sample ID GW-14 (MW-5) GW-15A (MW-4)

Collection MOC Collection MOC Date Lab Code Tritium (pCilL) (pCs.) Date Lab Code Tritium (pCi/L) (pcva) 01-26-12 EWW- 537 71 +/- 76 < 146 01-26-12 EWW-538 263 +/- 86 < 146 05-21-12 EWW. 3691 80 +/- 81 < 147 05-21-12 EWW- 3692 203 +/-87 < 147 06-20-12 EWW-4789 134 +/- 81 < 152 06-20-12 EWW-4790 251 +/- 87 < 152 09-18-12 EWW- 5954 51 +/- 85 < 157 09-18-12 EWW- 5955 202 +/- 92 < 157 10-23-12 EWW- 6919 26 +/- 80 < 158 10-23-12 EWW- 6920 236 +/- 90 < 158 Mean +/- s.d. 72 +/- 40 Mean i s.d. 231 +/- 28 Sample ID GW-15B (MW-4) GW-16A (MW-3)

Collection Moc Collection MOO Date Lab Code Tritium (pCi/L) (pCi/L) Date Lab Code Tritium (pCi/L) (pc L) 09-18-12 EWW-5956 244 +/- 94 < 157 01-26-12 EWW- 539 126 +/- 79 < 146 05-21-12 EWW- 3693 152 +/- 85 < 147 06-20-12 EWW-4792 175 +/- 83 < 152 09-18-12 EWW- 5957 208 +/- 92 < 157 10-23-12 EWW- 6921 149 +/- 86 < 158 Mean +/- s.d. 162 +/- 31 Sample ID GW-16B (MW-3)

Collection Moc Date Lab Code Tritium (pCiIL) (pCi_)

06-20-12 EWW- 4793 207 t 84 < 152 10-23-12 EWW-6923 253 +/- 91 < 158 Mean +/- s.d. 230 +/- 33 13-2

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Monthly Collections)

Units = pCi/L Beach Drains Sample ID S-1 S-3 Collection MOC Collection MoC Date Lab Code Tritium (pCiIL) (pCL) Date Lab Code Tritium (pCi/L) (pcvL) 01-05-12 EW- 97 248 +/- 85 < 145 01-05-12 EW- 98 381 +/- 91

• 145 02-09-12 EW- 744 132 +/- 92

• 142 02-09-12 EW- 746 338 +/- 101 < 142 03-07-12 EW- 1176 157 +/- 83

• 143 03-07-12 EW- 1177 533 1 100

• 143 04-05-12 EW- 1702 246 +/- 92

• 152 04-05-12 EW- 1703 239 t 91

• 152 05-10-12 EW- 2735 191 +/- 84

• 148 05-10-12 EW- 2736 287 +/- 88

• 148 06-05-12 EW- 3462 278 +/- 94

• 135 06-05-12 EW- 3463 327 +/- 96

• 135 07-05-12 EW- 4032 118 +/- 86 < 152 07-05-12 EW- 4033 615 +/- 108

• 152 08-07-12 EW- 4946 171 +/- 81

• 146 08-07-12 a EW- 4947 3367 +/- 181

• 146 09-04-12 EW- 5520 126 +/- 85

• 149 09-04-12 EW- 5521 395 +/- 97

• 149 10-09-12 EW- 6318 111 +/- 100

• 157 10-15-12 EW- 6709 268 +/- 92 < 151 11-07-12 EW- 7287 273 +/- 106

• 183 11-07-12 EW- 7288 273 +/- 106

• 183 12-04-12 EW- 7867 185 +/- 83

• 149 12-04-12 EW- 7868 301 +/- 89 < 149 Mean +/- s.d. 186 +/- 61 Mean +/- s.d. 610 +/- 875

'Tritium reanalyzed with a result of 3345+/-179 pCi/L.

13-3

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Monthly Collections)

Units = pCi/L Beach Drains Sample ID S-7 S-8 Collection MoC Collection MOC Date Lab Code Trtium (pCi/L) (pCV_) Date Lab Code Tritium (pCi/L) (pcvL) 01-05-12 NSa 01-05-12 NSa 02-09-12 NSa 02-09-12 NSa 03-07-12 NSa 03-07-12 NSa 04-05-12 NSa 04-05-12 NSa NS' 05-10-12 NSa 05-10-12 NSa 06-05-12 NSa 06-05-12 07-05-12 NSa 07-05-12 NSa 08-07-12 NS' 08-07-12 NS' 09-04-12 NS' 09-04-12 NSa 10-15-12 NSa 10-15-12 NSa 11-07-12 NSa 11-07-12 NSa 12-04-12 NSa 12-04-12 NSa Mean t s.d. Mean + s.d.

Sample ID S-9 S-10 Collection MDC Collection MDC Date Lab Code Tritium (pCi/L) (pci.) Date Lab Code Tritium (pCI/L) (pcv/)

01-05-12 NSa 01-05-12 NSa 02-09-12 NS' 02-09-12 NSO 03-07-12 NSa 03-07-12 NSa 04-05-12 NSa. 04-05-12 NSa 05-10-12 NSa 05-10-12 NS4 06-05-12 NSa 06-05-12 NSa 07-05-12 NSa 07-05-12 NSa 08-07-12 NSa 08-07-12 NS4 09-04-12 NSa 09-04-12 NSa 10-15-12 NSa 10-15-12 NSa 11-07-12 NS4 11-07-12 NS' 12-04-12 NSa 12-04-12 NSa Mean +/- s.d. Mean +/- s.d.

Sample ID S-11 Collection MDC Date Lab Code Tritium (pCi/L) (pcVL) 01-05-12 NSa 02-09-12 NSa 03-07-12 EW- 1178 269 +/- 88 < 143 04-05-12 EW- 1704 78 +/- 84 < 152 05-10-12 EW- 2737 114 +/- 80 < 148 06-05-12 EW- 3464 89 +/- 86 < 135 07-05-12 EW- 4035 167 +/- 88 < 152 08-07-12 EW- 4948 138 +/- 80 < 146 09-04-12 EW- 5522 126 1 85 < 149 10-15-12 EW- 6710 56 t 82 < 151 11-07-12 EW- 7289 1 : 96 < 183 12-04-12 EW- 7869 110 +/-:80 < 149 Mean + s.d, 115 t 76 a "NS" = no sample; not sent.

13-4

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program Units = DCi/L Samole ID U2 Facade Subsurface Drain Sump Collection Collection Date Lab Code Tritium (pCi/L) Moc Date Lab Code Tritium (pCi/L) MDC (pCIIL) (pC!IL) 01-03-12 EW- 103 479 :E100

• 147 02-06-12 EW- 781 534 t 96

• 142 03-13-12 EW- 1452 366 +/- 93

• 142 04-02-12 EW- 2251 470 +/- 107

• 143 05-07-12 EW- 2893 327 +/- 96

• 154 06-04-12 EW- 3683 511 +/- 101

• 147 07-12-12 EW- 4961 527 +/- 100

• 142 08-20-12 EW- 5942 470 +/- 104 < 158 09-03-12 EW- 5943 735 +/- 114 < 157 11-04-12 EW- 7286 369 +/- 109 < 183 11-24-12 EW- 8384 620 +/- 101

• 139 12-13-12 EW- 8385 748 +/- 105 < 139 Mean +/- s.d. 474 +/- 192 13-5

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program Units = pCi/L Manholes Sample ID MH Z-065A MH Z-065B Collection. Collection Date Lab Code Tritium (pCI/L) MDC Date Lab Code Tritium (pCi/L) MOC (pC!/L) (pCI/L)

NSa 05-16-12. NSa 05-16-12 Mean +/- s.d. Mean +/- s.d.

Sample ID MH Z-065C MH Z-065D Collection Lab Code Tritium (pCi/L) MDC Collection Lab Code Tritium (pCi/L) MDC Date (pCiL) Date (pCi/L) 05-16-12 NSa 05-16-12 NSa Mean +/- s.d. Mean +/- s.d.

Sample ID MH Z-066A MH Z-066B Collection Lab Code Tritium (pCi/L) MDC Collection Lab Code Tritium (pCi/L) MDC Date (pCl/tL) Date (pCi/),

05-17-12 EW- 3105 208 +/- 87 < 145 05-16-12 EW- 3106 119 +/- 83 < 146 10-25-12 EW- 7207 102 +/- 100 < 183 10-25-12 EW- 7208 24 +/- 97 < 183 Mean +/- s.d. 155 +/- 75 Mean +/- s.d. 71 +/- 67 Sample ID MH Z-066C MH Z-066D Collection Lab Code Tritium (pCi/L) MDC Collection Lab Code Tritium (pCi/L) MDC Date (pCi/L) Date (pciIL) 05-16-12 EW- 3107 127 +/- 83 < 146 05-16-12 EW- 3108 321 +/- 92 < 146 10-25-12 EW- 7209 84 +/- 99 < 183 10-23-12 EW- 6926 186 +/- 88 < 158 Mean +/- s.d. 106 +/- 30 Mean +/- s.d. 253 +/- 95 Sample ID MH Z-067A MH Z-067B Collection Lab Code Tritium (pCi/L) MDC Collection Lab Code Tritium (pCl/L) MDC Date (pCI/L) Date (pCi/L) 05-17-12 EW- 3109 137 +/- 84 < 145 05-16-12 EW- 3110 83 +/- 81 < 146 10-25-12 EW- 7210 141 i: 101 < 183 10-25-12 EW- .7211 40 t 98 < 183 Mean s.d. 139 +/- 3 Mean +/- s.d. 62 +/- 31 8 "NS" = No sample; not sent.

13-6

POINT BEACH NUCLEAR PLANT Manholes (cont.)

Sample ID MH Z-067C MH Z-067D Collection Lab Code Tritium (pCi/L) MDC Collection Lab Code Tritium (pCi/L) MDC Date (pCiIL) Date (pci/L) 05-16-12 EW- 3111 289 +/- 91 < 146 05-16-12 EW- 3112 206 +/- 87 < 146 10-25-12 EW- 7212 171 +/- 102 < 183 10-23-12 EW- 6927 230 +/- 90 < 158 Mean +/- s.d. 230 +/- 84 Mean +/- s.d. 218 +/- 17 Sample ID MH Z-068 MHI-Collection Date Lab Code Tritium (pCi/L) MDC Collection Lab Code Tritium (pCi/L) MDC Date (pCIIL) Date (pCjI/L) 05-16-12 EW- 3113 279 +/- 90 < 146 05-16-12 NSa 10-23-12 EW- 6928 97 +/- 83 < 158 10-23-12 EW- 6924 72 +/- 82 <158 Mean _ts.d. 188 +/- 129 Mean +/- s.d.

Sample ID MH-4 MH-6 Collection Lab Code Tritium (pCi/L) MDC Collection Lab Code Tritium (pCi/L) MDC Date (pCIIL) Date (pCI/L) 05-16-12 NSa 05-16-12 NSa Mean +/- s.d. Mean +/- s.d.

Sample ID MH-7 MH-8 Collection Lab Code MDC Collection Lab Code Tritium (pCi/L) MDC Tritium (pCi/L) (pCi/L)

Date (pCI/L) Date 05-16-12 NSa 05-16-12 NSa Mean +/- s.d. Mean +/- s.d.

Sample ID MH-16 MH-2 Collection Lab Code Tritium (pCVL) MDC Collection Lab Code Tritium (pCi/L) MDC Date (pCi/L) Date (pCi/L) 05-16-12 NSa 05-16-12 NSa 10-22-12 EW- 6925 122 +/- 85 < 158 Mean +/- s.d. Mean +/- s.d.

Sample ID MH-5A MH-9 Collection Lab Code Tritium (pCVL) MDC Collection Lab Code Tritium (pCi/L) MDC Date (pCi/L) Date (pCi/I) 05-16-12 NSa 05-16-12 NS 3 Mean +/- s.d. Mean +/- s.d.

No sample;

="NS" not sent.

13-7

POINT BEACH NUCLEAR PLANT Table 13. Groundwater Tritium Monitoring Program (Quarterly Collections)

Units = pCi/L Quarterlv Wells Sample ID GW-05 (WH 6 Well) GW-06 (SBCC Well)

Collection MDC Collection MDC Date Lab Code Tritium (pCi/L) (pCi/L) Date Lab Code Tritium (pCi/L) (pCi/L) 01-12-12 EWW- 176 37 +/- 90 < 146 01-12-12 EWW- 177 27 +/- 90 < 146 04-12-12 EWW- 1852 24 +/- 76 < 143 04-12-12 EWW- 1853 22 +/- 76 < 143 07-12-12 EWW- 4126 11 +/- 78 < 147 07-12-12 EWW- 4127 32 +/- 79 < 147 10-16-12 EWW- 6706 1 +/- 80 < 151 10-16-12 EWW- 6707 -32 +/- 78 < 151 Mean +/- s.d. 18 +/- 16 Mean +/- s.d. 12 +/- 29 Sample ID GW-18 (WH 7 Well)

Collection MDC Collection MDC Date Lab Code Tritium (pCiJL) (pCYL) Date Lab Code Tritium (pCi/L) (PCIIL) 05-31-12 EWW- 3383 63 +/- 83 < 152 10-16-12 EWW- 6708 5 +/- 80 < 151 08-29-12 EWW- 5444 -44 +/- 89 < 150 12-19-12 EWW- 8194 70 +/- 80 < 145 09-19-12 EWW- 5963 -84 +/- 76 < 153 Mean +/- s.d. 2 +/- 67 Fagade Wells Sample ID GW-09 1Z-361A GW-09 1Z-361B Collection MDC Collection MDC Date Lab Code Tritium (pCi/L) (pCij/L) Date Lab Code Tritium (pCi/L) (pCYL) 01-27-12 EWW- 782 154 t 79 < 142 01-27-12 EWW- 783 54 +/- 74 < 142 03-07-12 EWW- 1448 282 +/- 89 < 142 03-07-12 EWW- 1449 63 +/- 78 < 142 03-07-12 EWW- 2884 190 t 91 < 155 03-07-12 EWW- 2885 . 19 +/- 83 < 155 03-30-12 EWW- 2258 257 +/- 98 < 143 03-30-12 EWW- 2259 100 +/- 91 < 143 05-04-12 EWW- 2888 212 +/- 91 < 154 05-04-12 EWW- 2890 48 +/- 83 < 154 06-01-12 EWW- 3684 158 +/- 85 < 147 06-01-12 EWW- 3685 41 +/- 79 < 147 07-11-12 EWW- 4957 404 +/- 94 < 142 07-11-12 EWW- 4958 354 +/- 92 < 142 09-01-12 EWW- 5947 1342 +/- 135 < 157 09-01-12 EWW- 5948 345 +/- 99 < 157 09-29-12 EWW- 7203 191 +/- 103 < 184 09-29-12 EWW- 7204 166 +/- 103 < 184 11-11-12 EVWW- 7395 263 +/- 88 < 152 11-11-12 EWW- 7396 57 +/- 78 < 152 11-18-12 EWW- 7983 150 +/- 86 < 151 11-18-12 EWW- 7984 158 - 87 < 151 12-29-12 EWW- 8386 255 +/- 85 < 138 12-29-12 EWW- 8387 160 +/- 81 < 138 Mean +/- s.d. 354 +/- 378 Mean +/- s.d. 132 +/- 130 Sample ID GW-10 2Z-361A GW-10 2Z-361B Collection MOC Collection MDC Date Lab Code Tritium (pCi/L) (pCi/L) Date Lab Code Tritium (pCi/L) (pCiL) 01-27-12 EWW- 784 18 1 72 < 142 01-27-12 EWW- 785 64 +/- 74 < 142 01-27-12 (b) EWW- 1068 -22 +/- 72 < 147 03-07-12 a EWW- 1451 164 +/- 83 < 142 03-07-12 - EWW- 1450 123 +/- 81 < 142 03-07-12 EWW- 2887 17 +/- 82 < 155 03-07-12 " EWW- 2886 -15 +/- 81 < 155 03-30-12 EWW- 2261 112 +/- 92 < 143 03-30-12 EWW- 2260 54 +/- 89 < 143 05-04-12 EWW- 2892 -36 +/- 79 < 154 05-04-12 EWW- 2891 69 +/- 84 < 154 06-01-12 EWW- 3687 166 +/- 86 < 147 06-01-12 EWW- 3686 21 t 78 < 147 07-11-12 EWW- 4960 171 t 84 < 142 07-11-12 EWW- 4959 -2 +/- 75 < 142 09-01-12 EWW- 5950 12 +/- 83 < 157 09-01-12 EWW- 5949 16 +/- 83 < 157 09-29-12 EWW- 7206 -54 +/- 95 < 184 09-29-12 EWW- 7205 -4 +/- 96 < 184 11-11-12 EWW- 7398 42 +/- 78 < 152 11-11-12 EWW- 7397 -40 t 73 < 152 11-18-12 EWW- 7986 57 +/- 82 < 151 11-18-12 EWW- 7985 51 +/- 82 < 151 12-29-12 EWW- 8389 33 +/- 74 < 138 12-29-12 EWW- 8388 89 +/- 77 < 138 Mean +/- s.d. 29 +/- 49 Mean s.d. 84 +/- 81 03-30-12 EWW- 2895 160 +/- 89 < 155 (1Z361AL)

(Annual Collections)

Units = pCi/L Bogs Sample ID GW-07 (North Bog) GW-08 EIC Bog Collection MoC Collection MDC Date Lab Code Tritium (pCi/L) (pCi/LI Date Lab Code Tritium (pCi/L) (pCi/L) 05-10-12 EWW- 2733 110 +/- 80 < 148 05-10-12 EWW- 2734 297 +/- 89 < 148 a Received 03-22-12. c Tritium repeated with a result of 1444 +/- 136 pCi/L.

b Received 05-18-12. 13-8

• T Environmental, Midwest Laboratory Inc.

700 Lardwehr Road -Norhbrook, IL80062-23 10 phone (847) 564-0700 - lax (847) 564-4517 APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January, 2012 through December, 2012

APPENDIX B DATA REPORTING CONVENTIONS B-1

Data Reporting Conventions 1.0. All activities, except gross alpha and gross beta, are decay corrected to collection time or the end of the collection period.

2.0. Single Measurements Each single measurement is reported as follows: x+/-s where: x = value of the measurement; s = 2a counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is less than the lower limit of detection L, it is reported as: < L, where L = the lower limit of detection based on 4.66ar 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; x1 +/- si and x2 +/- s2 Reported result: x + s; where x = (1/2) (x 1 + x2 ) and s = (1/2) *+s .

3.2. Individual results: < L1 , < L2 Reported result: < L, where L = lower of L1 and L2 3.3. Individual results: x +/- s, < L Reported result: x +/- s if x >- L; < L otherwise.

4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average x and standard deviation "s" of a set of n numbers xV, x 2 . . . x, are defined as follows:

X= n'x n-1 4.2 Values below the highest lower limit of detection are not included in the average.

4.3 If all values in the averaging group are less than the highest LLD, the highest LLD is reported.

4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.

4.5 In rounding off, the following rules are followed:

4.5.1. If the number following those to be retained is less than 5, the number is dropped, and the retained numbers are kept unchanged. As an example, 11.443 is rounded off to 11.44.

4.5.2. If the number following those to be retained is equal to or greater than 5, the number is dropped and the last retained number is raised by 1. As an example, 11.445 is rounded off to 11.45.

B-2

POINT BEACH NUCLEAR PLANT APPENDIX C Sampling Program and Locations C-1

POINT BEACH NUCLEAR PLANT Locations Collection Type Analysis Sample Type No. Codes (and Type)a (and Frequency)b (and Frequency)b Airborne Filters 6 E-1-4, 8, 20 Weekly GB, GS, on QC for each location Airborne Iodine 6 E-1-4, 8, 20 Weekly 1-131 Ambient Radiation 22 E-1-9, 12, 14-18, 20, Quarterly Ambient Gamma (TLD's) 22-32, 34-36, 38,39 Lake Water 5 E-1, 5, 6, 33 Monthly GB, GS, 1-131 on MC H-3, Sr-89-90 on QC Well Water I E-10 Quarterly GB, GS, H-3, Sr-89-90, 1-131 Vegetation 8 E-1-4, 6, 9, 20 3x / year GB, GS as available Shoreline Silt 5 E-1, 5, 6,12, 33 2x / year GB, GS Soil 8 E-1-4, 6, 8, 9, 20 2x / year GB, GS Milk 3 E-11, 40, 21 Monthly GS, 1-131, Sr-89-90 Algae 2 E-5, 12 3x / year GB, GS as available Fish 1 E-13 2x / year GB, GS (in edible portions) as available a Locations codes are defined in Table 2. Control Stations are indicated by (C). All other stations are indicators.

b Analysis type is coded as follows: GB = gross beta, GA = gross alpha, GS = gamma spectroscopy, H-3 = tritium, Sr-89 = strontium-89, Sr-90 = strontium-90, 1-131 = iodine-1 31. Analysis frequency is coded as follows:

MC = monthly composite, QC = quarterly composite.

C-2

POINT BEACH NUCLEAR PLANT APPENDIX D Graphs of Data Trends D-1

POINT BEACH Air Particulates - Gross Beta D-2

POINT BEACH Air Particulates - Gross Beta D-3

POINT BEACH Air Particulates - Gross Beta Location E-8, monthly averages 2008-2012 0.050 0.040 CY) 0.030 E

C0 0.020 0.010 0.000 ol 1!iiiI i 1111 1 f11111 1111s!!1121!6HI 24008 2009 2010 2011 2012 2013 Year Location E-20, monthly averages 2008-2012 0.050 0.040 ot 0.030 E

. 0.020 0.010 0.000 111IN 1to 1  !!!!!I ! I till H1 I I I If I I I ! Hiii 2(008 2009 2010 2011 2012 2013 Year D-4

POINT BEACH NUCLEAR PLANT APPENDIX E Supplemental Analyses E-1

POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: = pCi\L Gamma isotopic analysis Location GW-04 GW-15 GW-16 Collection Date 05-31-12 05-23-12 05-23-12 Lab Code EWW- 3381 MDC EWW- 3692 MDC EWW- 3693 MDC Be-7 8.4 +/- 12.3 24.1 -1.4 +/- 13.4 < 32.0 2.3 _ 13.0 < 36.7 Mn-54 1.0 +/- 1.5 1.6 -0.9 +/- 1.6 < 2.3 1.2 +/- 1.6 < 3.4 Fe-59 2.2 +/- 2.3 4.7 -9.5 +/- 3.2 < 10.2 1.3 +/-3.1 < 6.4 Co-58 1.3 +/- 1.6 2.6 -1.6 +/- 1.5 < 3.6 -1.1 +/- 1.5 < 1.7 Co-60 0.9 +/- 1.7 1.2 3.6 +/- 1.8 < 2.6 0.7 +/- 1.7 < 1.4 Zn-65 1.6 +/-3.1 5.8 1.8 +/- 3.2 < 4.5 2.9 +/- 3.3 < 2.5 Zr-Nb-95 1.1 - 1.6 3.1 1.4 + 1.6 < 4.6 1.5 +/- 1.6 < 5.6 Cs-134 -0.8 _ 1.3 2.3 0.0 +/- 1.5 < 2.6 0.9 +/- 1.5 < 2.4 Cs- 137 0.6 +/- 1.7 2.9 -2.3 +/- 1.8 < 2.3 0.1 +/- 1.8 < 3.4 Ba-La-140 2.6 _ 1.9 4.6 -8.0 - 1.9 < 7.5 2.3 +/- 1.9 < 11.9 Location GW- 15 S-3 Collection Date 05-23-12 08-07-12 Lab Code EWW- 3710 EWW- 4947 H-3 Be-7 13.2 +/- 12.1 42.2 -4.7 +/- 10.0 < 17.1 Mn-54 0.6 +/- 1.5 2.7 1.4 +/- 1.3 < 2.1 Fe-59 -0.6 + 3.1 6.4 -0.9 +/- 2.5 < 5.7 Co-58 -1.7 - 1.4 3.4 -0.1 +/- 1.2 < 1.7 Co-60 1.2 + 1.7 2.8 0.9 +/- 1.3 < 2.3 Zn-65 4.7 + 2.7 5.1 -1.1 +/- 2.6 < 3.0 Zr-Nb-95 -2.0 - 1.5 7.4 -2.3 +/- 1.5 < 3.6 Cs-134 -0.4 - 1.4 2.4 0.4 +/- 1.1 < 2.2 Cs- 137 -1.2 +/- 1.6 2.5 0.8 +/- 1.4 < 2.6 Ba-La-140 -15.4 +/- 1.6 21.4 -3.1 +/- 1.4 < 4.8 E-2

POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: = pCiXL Tritium analysis Location So. Mausoleum Sump No. Mausoleum Sump So. Mausoleum Sump Collection Date 05-08-12 05-08-12 06-20-12 Lab Code EW- 2894 MDC EW- 5320 MDC EW- 5322 MDC H-3 199 +/- 91 < 154 6310 +/- 250 156 256 +/- 105 < 155 Location No. Mausoleum Sump So. Mausoleum Sump No. Mausoleum Sump Collection Date 06-20-12 07-20-12 07-20-12 Lab Code EW- 5321 MDC EW- 5307 MDC EW- 5306 MDC H-3 7824 +/- 273 < 155 224 +/- 90 151 6286 +/- 242 < 151 Location So. Mausoleum Sump No. Mausoleum Sump So. Mausoleum Sump Airborne Collection Date 08-09-12 08-09-12 06-20-12 Lab Code EW- 5309 MDC EW- 5308 MDC EW- 5311 MDC H-3 225 +/- 90 < 150 6784 +/- 250 :150 48 +/- 82 < 151 Location No. Mausoleum Sump Tree #1/Branch #1 Tree #1/Branch #2 Airborne Collection Date 06-20-12 09-05-12 09-05-12 Lab Code EW- 5310 MDC EW- 5709 MDC EW- 5710 MDC H-3 314 +/- 95 < 151 109 +/- 85 <:151 170 +/- 88 < 151 Location Tree #2 Tree #3 Collection Date 09-05-12 09-05-12 Lab Code EW- 5711 MDC EW- 5712 MDC H-3 158 +/- 87 < 151 -12 +/- 44 73 E-3

POINT BEACH NUCLEAR PLANT APPENDIX F Special Analyses F-1

%m¢tAT! Environmental, Inc.

• ýý l Midwest Laboratory 700 Landwehr Road *Northbrook.IL 60062-2310 phone (847) 564-0700- fax (847) 564-45t7 Dr. Kjell Johansen NextEra Energy LABORATORY REPORT NO.: 8006-100-1023 Point Beach Nuclear Plant DATE: 06-13-2012 6610 Nuclear Road SAMPLES RECEIVED: 05-25-2012 Two Rivers, Wisconsin 54241 PURCHASE ORDER NO.:

Below are the results of the analyses for tritium on four grass samples.

Sample Collection Lab Concentration / MDC (pCi/L)

Location Date Code H-3 GW-02-East Creek 05-23-12 EG-3100 83 1 81 / < 145 GW-17-SE Corner STP 05-23-12 EG-3101 124 +/- 82 / < 145 Retention Pond-North & East 05-23-12 EG-3102 126 +/- 83 / < 145 Retention Pond Trees-South 05-23-12 EG-3103 81 +/- 81 / < 145 The error given is the probable counting error at the 95% confidence level. The less than (<) value, is based on 4.66 sigma counting error for the background sample.

E-mail: kiell.iohansenaNextERAEnergy.com

'rob, Manager APPROVED BY:-[ f CWJN Tony Coorlim, Quality Assurance

1,Environmental, Inc.

-049411k Midwest Laboratory 700Landwehr Road - Northbrook. IL 60062-2310 phone (847) 564-0700 -t~ax(847)564-45t7 Dr. Kiell Johansen NextEra Energy LABORATORY REPORT NO.: 8006-100-1023A Point Beach Nuclear Plant DATE: 06-13-2012 6610 Nuclear Road SAMPLES RECEIVED: 05-25-2012 Two Rivers, Wisconsin 54241 PURCHASE ORDER NO.:

Below are the results of the analyses for tritium on four grass samples.

Sample Collection Lab Concentration / MDC (pCi/p wet)

Location Date Code H-3 GW-02-East Creek 05-23-12 EG-3100 0.068 +/- 0.066/ < 0.120 GW-17-SE Corner STP 05-23-12 EG-3101 0.097 +/- 0.064/ < 0.113 Retention Pond-North & East 05-23-12 EG-3102 0.101 +/- 0.067 < 0.117 Retention Pond Trees-South 05-23-12 EG-3103 0.053 +/- 0.053/ < 0.096 The error given is the probable counting error at the 95% confidence level. The less than (<) value, is based on 4.66 sigma counting error for the background sample.

E-mail: kiell.iohansen(,NextERAEnergy.com APPROVED Coorlim, Assurance

TI Environmental, Midwest Laboratory Inc.

700 Landwehr Road

• Northbrook, IL 60052-2310 phone (847) 564-0700 . fax (847) 564-4517 Dr. Kjell Johansen NextEraEnergy Point Beach Nuclear Plant DATE: 08-23-2012 6610 Nuclear Road SAMPLES RECEIVED: 08-21-2012 Two Rivers, Wisconsin 54241 PURCHASE ORDER NO.:

Below are the results of the analyses for tritium in eight water samples collected August 15, 2012.

Sample Lab Concentration / MDC (pCi/L)

Description Code H-3 NSB-AC EW-5217 557 +/- 102 1 < 146 Control Room AC EW-5218 998 +/- 118 / < 146 SSB-AC-1 EW-5519 5,510 +/- 226 / < 146 SSB-AC-2 EW-5520 5,822 +/- 231 / < 146 SG AC-1 EW-5221 473 +/- 99 / < 146 SG AC-2 EW-5222 395 +/- 95 / < 146 TB AC EW-5223 185 +/- 86 / < 146 TurbBIdg AC 8' EW-5224 602 _ 104 /146 S-3 South of Ul Discharge ESW-5225a 387 + 95 / < 146 a Collected August 16, 2012.

The results will be included in the monthly progress report.

The error given is the probable counting error at the 95% confidence level. The less than (<) value, is based on 4.66 sigma counting error for the background sample.

E-mail: KjellJohansen@nexteraenergy.corn I

APPROVED BY Tony Coorlim, Quality Assurance

btA I Environmental, Inc.

F419II Midwest Laboratory 700 Landwehr Road Noa1hbreok. IL 60062-2310 phone (847) 564-0700 . fox (847) W4-4517 Mr. Richard Welty LABORATORY REPORT NO.: 8006-100-1016 Radiation Protection Mgr. DATE: 04-13-12 Point Beach Nuclear Plant SAMPLES RECEIVED: 04-06-12 NextEraEnergy PURCHASE ORDER NO.:

6610 Nuclear Road Two Rivers, WI 54241 Below are the results of the readout of supplemental TLDs deployed during the first quarter, 2012.

Period: 1st Quarter, 2012 Date Annealed: 12/19/11 Date Placed: 01/05/12 Date Removed: 04/05/12 Date Read: 04/09/12 Days in the Field: 91 Days from Annealing to Readout: 112 In-transit exposure: 3.47 +/- 0.30 Net mR Net mR Location Total mR Net mR Std Qtr per 7 days SGSF-North 14.8 +/- 0.8 11.3 +/- 0.8 11.3 +/- 0.8 0.87 +/- 0.06 SGSF-East 15.2 +/- 0.4 11.7 +/- 0.5 11.7 +/- 0.5 0.90 +/- 0.04 SGSF-South 17.4 +/- 0.2 13.9 +/- 0.4 13.9 +/- 0.4 1.07 +/- 0.03 SGSF-West 16.5 +/- 0.6 13.0 +/- 0.7 13.0 +/- 0.7 1.00 +/- 0.05 ISFSI-North 35.3 +/- 1.1 31.8 +/- 1.1 31.8 +/- 1.1 2.45 +/- 0.09 ISFSI-East 34.8 +/- 0.9 31.3 +/- 1.0 31.3 +/- 1.0 2.41 +/- 0.08 ISFSI-South 19.8 +/- 0.7 16.4 +/- 0.7 16.4 +/- 0.7 1.26 +/- 0.06 ISFSI-West 65.8 +/- 2.7 62.3 +/- 2.7 62.3 +/- 2.7 4.79 +/- 0.21 Control 16.3 +/- 0.8 12.9 +/- 0.8 12.9 +/- 0.8 0.99 +/- 0.06 (IQI SA Coorlim, Quality Assurance APPROVED cc: K. Johansen

Envlronmentai, Inc.

A I Midwest Laboratory 700 LanoWehr Rod - Nor~dkroA. ILX60062-2310 phone (847) 5W4-0700 - fax (847) 564-4517 Mr. Richard Welty LABORATORY REPORT NO.: 8006-100-1028 Radiation Protection Mgr. DATE: 07-23-12 Point Beach Nuclear Plant SAMPLES RECEIVED: 07-06-12 NextEraEnergy PURCHASE ORDER NO.:

6610 Nuclear Road Two Rivers, WI 54241 Below are the results of the readout of supplemental TLDs deployed during the second quarter, 2012.

Period: 2nd Quarter, 2012 Date Annealed: 03/21/12 Date Placed: 04/05/12 Date Removed: 07/02/12 Date Read: 07/09/12 Days in the Field: 88 Days from Annealing to Readout: 110 In-transit exposure: 3.29 + 0.17 Net mR Net mR Location Total mR Net mR Std Qtr per 7 days SGSF-North 16.1 +/- 1.3 12.8 +/- 1.3 13.2 +/- 1.4 1.02 +/- 0.10 SGSF-East 16.2 +/- 0.6 12.9 +/- 0.6 13.3 +/- 0.7 1.03 +/- 0.05 SGSF-South 16.8 +/- 0.6 13.6 +/- 0.7 14.0 +/- 0.7 1.08 +/- 0.05 SGSF-West 18.3 +/- 0.7 15.0 +/- 0.8 15.5 +/- 0.8 1.19 +/- 0.06 ISFSI-North 34.3 +/- 1.9 31.0 +/- 1.9 32.0 +/- 2.0 2.46 +/- 0.15 ISFSI-East 36.2 +/- 1.0 32.9 +/- 1.0 34.1 +/- 1.0 2.62 +/- 0.08 ISFSI-South 20.5 +/- 1.0 17.3 +/- 1.0 17.8 +/- 1.1 1.37 +/- 0.08 ISFSI-West 62.7 +/- 2.3 59.4 +/- 2.3 61.5 +/- 2.4 4.73 +/- 0.19 Control 17.9 +/- 0.7 14.6 +/- 0.7 15.1 +/- 0.7 1.17 +/- 0.06 SA Coorlim, Quality Assurance APPROVED cc: K.Johansen

-309-A II Environmental, Midwest Laboratory Inc.

700 Lendwehr Rood Northbrook. IL 60062-2310 phone (847) 564-0700 - fox (847) 564-4517 Mr. Richard Welty LABORATORY REPORT NO.: 8006-100-1036 Radiation Protection Mgr. DATE: 10-26-12 Point Beach Nuclear Plant SAMPLES RECEIVED: 10-05-12 NextEraEnergy PURCHASE ORDER NO.:

6610 Nuclear Road Two Rivers, WI 54241 Below are the results of the readout of supplemental TLDs deployed during the third quarter, 2012.

Period: 3rd Quarter, 2012 Date Annealed: 06/12/12 Date Placed: 07/02/12 Date Removed: 10/02/12 Date Read: 10/09/12 Days in the Field: 92 Days from Annealing to Readout: 119 In-transit exposure: 3.78 +/- 0.28 Net mR Net mR Location Total mR Net mR Std Qtr per 7 days SGSF-North 15.5 +/- 0.7 11.7 +/- 0.7 11.6 +/- 0.7 0.89 +/- 0.06 SGSF-East 15.4 +/- 1.1 11.7 +/- 1.1 11.5 +/- 1.1 0.89 +/- 0.08 SGSF-South 17.8 +/- 0.4 14.0 +/- 0.5 13.9 +/- 0.5 1.07 +/- 0.04 SGSF-West 16.9 +/- 0.5 13.1 +/- 0.6 13.0 +/- 0.6 1.00 +/- 0.05 ISFSI-North 35.9 +/- 1.5 32.2 +/- 1.5 31.8 +/- 1.5 2.45 +/- 0.12 ISFSI-East 50.4 +/- 2.0 46.6 +/- 2.1 46.1 +/- 2.0 3.55 +/- 0.16 ISFSI-South 20.6 +/- 1.0 16.9 +/- 1.0 16.7 +/- 1.0 1.28 +/- 0.08 ISFSI-West 65.0 +/- 3.8 61.2 +/- 3.8 60.6 +/- 3.8 4.66 +/- 0.29 Control 17.3 +/- 0.8 13.5 +/- 0.9 13.4 +/- 0.9 1.03 +/- 0.07 SA Coorlim, Quality Assurance APPROVED, fr2.?

cc: K. Johansen

A

• ATI Environmentall, Midwest Laboratory 700"Lndwr Road

• Nrthbook, IL 60062-2310 Inc.

phono (847) 564-0700. fax (847) 564-4517 Mr. Richard Welty LABORATORY REPORT NO.: 8006-100-1048 Radiation Protection Mgr. DATE: 01-24-13 Point Beach Nuclear Plant SAMPLES RECEIVED: 01-04-13 NextEraEnergy PURCHASE ORDER NO.:

6610 Nuclear Road Two Rivers, WI 54241 Below are the results of the readout of supplemental TLDs deployed during the fourth quarter, 2012.

Period: 4th Quarter, 2012 Date Annealed: 09/10/12 Date Placed: 10/02/12 Date Removed: 01/03/13 Date Read: 01/08/13 Days in the Field: 93 Days from Annealing to Readout: 120 In-transit exposure: 4.24 +/- 0.34 Net mR Net mR Location Total mR Net mR Std Qtr per 7 days SGSF-North 19.4 +/- 1.0 15.2 +/- 1.0 14.9 +/- 1.0 1.14 +/- 0.08 SGSF-East 20.6 +/- 0.4 16.3 +/- 0.6 16.0 +/- 0.5 1.23 +/- 0.04 SGSF-South 21.5 +/- 0.9 17.2 +/- 1.0 16.8 +/- 1.0 1.30 +/- 0.07 SGSF-West 22.7 +/- 1.1 18.5 +/- 1.2 18.1 +/- 1.2 1.39 +/- 0.09 ISFSI-North 44.0 +/- 2.7 39.8 +/- 2.7 38.9 +/- 2.6 3.00 +/- 0.20 ISFSI-East 64.2 +/- 1.6 60.0 +/- 1.7 58.7 +/- 1.6 4.51 +/- 0.13 ISFSI-South 26.5 +/- 1.3 22.3 +/- 1.3 21.8 +/- 1.3 1.68 +/- 0.10 ISFSI-West 77.4 +/- 3.3 73.2 +/- 3.3 71.6 +/- 3.3 5.51 +/- 0.25 Control 21.5 +/- 1.9 17.3 +/- 1.9 16.9 +/- 1.9 1.30 +/-0.14 1I.L SA Coorlim, Quality Assurance APPROVED 1/2q II3 cc: K. Johansen

• ATI Midwest Environmental, Laboratory Inc.

700 Lendweh, Road -Northbrook, IL 0062-2310 phone (847) 664.0700 - 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, 2012 through December, 2012

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

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

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

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

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

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

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

Complete analytical data for duplicate analyses is available upon request.

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

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

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

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

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

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

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

> 30 pCi/liter or kg 10% of known value Potassium-40

• 0.1 g/liter or kg 5% of known value Gross alpha < 20 pCi/liter 5.0 pCi/liter

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

> 100 pCi/liter 5% of known value Tritium -54,000 pCi/liter Icy =

0 0 933 169.85 x (known)

> 4,000 pCi/liter 10% of known value Radium-226,-228 > 0.1 pCi/liter 15% of known value Plutonium > 0.1 pCi/liter, gram, or sample 10% of known value Iodine-1 31, < 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 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-1783 04/09/12 Sr-89 62.2 +/- 6.0 58.5 46.9 - 66.3 Pass ERW-1783 04/09/12 Sr-90 33.7 +/- 2.1 37.4 27.4 -43.1 Pass ERW-1786 04/09/12 Ba-133 75.7 +/- 4.1 82.3 69.1 -90.5 Pass ERW-1 786 04/09/12 Co-60 71.9 +/- 4.0 72.9 65.6 - 82.6 Pass ERW-1786 04/09/12 Cs-134 70.0 +/- 4.3 74.2 60.6 - 81.6 Pass ERW-1786 04/09/12 Cs-1 37 151.5 +/- 6.1 155.0 140.0 - 172.0 Pass ERW- 1786 04/09/12 Zn-65 108.3 +/- 89.0 105.0 94.5 - 125.0 Pass ERW-1789 04/09/12 Gr. Alpha 55.0 +/- 2.4 62.9 33.0 - 78.0 Pass ERW-1789 d 04/09/12 Gr. Beta 38.3 +/- 1.3 44.2 29.6 -51.5 Pass ERW-1795 04109/12 Ra-226 6.4 +/- 0.4 5.7 4.3 - 6.9 Pass ERW-1795 04/09/12 Ra-228 5.4 +/- 1.2 4.6 2.7 - 6.3 Pass ERW-1795 04/09/12 Uranium 56.2 +/- 2.6 61.5 50.0 - 68.2 Pass ERW-1798 04/09/12 H-3 16023 +/- 355 15800 13800-17400 Pass ERW-6283 10/05/12 Sr-89 41.5 +/- 4.1 39.1 29.7 - 46.1 Pass ERW-6283 10/05/12 Sr-90 19.7 +/- 1.6 20.1 14.4 - 23.8 Pass ERW-6286 10/05/12 Ba-1 33 82.7 +/- 4.4 84.8 71.3 - 93.3 Pass ERW-6286 10/05/12 Co-60 77.2 +/- 3.7 78.3 70.5 - 88.5 Pass ERW-6286 10/05/12 Cs-134 74.4 +/- 1.5 76.6 62.6 - 84.3 Pass ERW-6286 10/05/12 Cs-1 37 183.0 +/- 6.2 183.0 165.0 - 203.0 Pass ERW-6286 10/05/12 Zn-65 211.0 +/-9.9 204.0 184.0 - 240.0 Pass ERW-6288 10/05/12 Gr. Alpha 47.0 +/- 2.3 58.6 30.6 - 72.9 Pass ERW-6288 10/05/12 Gr. Beta 33.4 +/- 1.2 39.2 26.0 - 46.7 Pass ERW-6290 10/05112 1-131 23.3 +/- 1.0 24.8 20.6 - 29.4 Pass ERW-6295e 10/05/12 Ra-226 16.5 +/- 0.7 15.0 11.2 -17.2 Pass ERW-6295e 10/05/12 Ra-228 4.9 +/- 1.1 4.6 2.7 - 6.2 Pass ERW-6295 10/05/12 Uranium 61.2 +/- 1.8 62.5 50.8 - 69.3 Pass 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, I determination) and control limits as provided by ERA.

d Result of reanalysis, Sample dilution problem suspected. A new dilution was prepared and the sample reanalyzed.

Original analysis results, 76.2 +/- 1.8 pCi/L.

e Results of reanalyses, original submission (pCi/L): Ra-226, 17.52 +/- 0.69 Ra-228, 7.44 +/- 1.1.49.

A new test was ordered from Environmental Resources Associates, results will be updated for first quarter, 2013.

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

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

2012-1 2/7/2012 30 cm. 74.87 87.22 +/- 2.86 52.41 -97.33 Pass 2012-1 2/7/2012 40 cm. 42.12 53.70 +/- 4.53 29.48 - 54.76 Pass 2012-1 2/7/2012 50 cm. 26.95 33.04 +/- 1.96 18.87 - 35.04 Pass 2012-1 2/7/2012 70 cm. 13.75 13.26 +/- 1.15 9.63 - 17.88 Pass 2012-1 2/7/2012 75 cm. 11.98 13.38 +/- 1.68 8.39 - 15.57 Pass 2012-1 2/7/2012 80 cm. 10.53 11.27 +/- 0.95 7.37 - 13.69 Pass 2012-1 2/7/2012 90 cm. 8.32 7.79 +/- 0.83 5.82 - 10.82 Pass 2012-1 2/7/2012 100 cm. 6.74 5.91 +/- 0.25 4.72 - 8.76 Pass 2012-1 2/7/2012 110 cm. 5.57 4.63 +/- 0.83 3.90 - 7.24 Pass 2012-1 2/7/2012 120 cm. 4.68 3.96 +/- 1.68 3.28 - 6.08 Pass 2012-1 2/712012 150 cm. 2.99 2.41 +/- 0.08 2.09 - 3.89 Pass 2012-1 2/7/2012 180 cm. 2.08 2.02 +/- 0.25 1.46 -2.70 Pass Environmental, Inc.

2012-2 9/1112012 40 cm. 33.75 43.74 - 1.31 23.63 - 43.88 Pass 2012-2 9/11/2012 50 cm. 21.6 25.37 +/- 0.82 15.12 -28.08 Pass 2012-2 9/11/2012 60 cm. 15 16.63 +/- 0.45 10.50 - 19.50 Pass 2012-2 9/11/2012 70 cm. 11.02 10.58 +/- 0.20 7.71 -14.33 Pass 2012-2 9/11/2012 80 cm. 8.44 8.55 +/- 1.18 5.91 - 10.97 Pass 2012-2 9/11/2012 90 cm. 6.67 5.75 +/- 0.33 4.67 - 8.67 Pass 2012-2 9/11/2012 100 cm. 5.4 4.44 +/- 0.22 3.78 - 7.02 Pass 2012-2 9/11/2012 110 cm. 4.46 3.85 +/- 0.05 3.12 -5.80 Pass 2012-2 9/11/2012 120 cm. 3.75 3.03 +/- 0.71 2.63 - 4.88 Pass 2012-2 9/11/2012 150 cm. 2.4 1.82 _ 0.10 1.68 -3.12 Pass 2012-2 9/11/2012 180 cm. 1.67 1.19 + 0.34 1.17 -2.17 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=l ' Activity Limits d Acceptance SPW-41824 2/15/2012 Ra-228 24.85 +/- 2.14 28.75 20.13 - 37.38 Pass W-22712 2/27/2012 Gr. Alpha 14.59 +/- 0.34 20.00 10.00 - 30.00 Pass W-22712 2/27/2012 Gr. Alpha 43.57 +/- 0.40 41.70 20.85 - 62.55 Pass SPAP-1032 3/5/2012 Cs-134 7.06 +/- 1.71 5.26 0.00 - 15.26 Pass SPAP-1032 3/5/2012 Cs-137 102.63 +/- 3.13 104,24 93.82 - 114.66 Pass SPAP-1034 315/2012 Gr. Beta 44.30 +/- 0.11 46.88 28.13 -65.63 Pass SPW-1036 3/5/2012 Cs-134 43.23 +/- 3.84 39.42 29.42 - 49.42 Pass SPW-1036 3/5/2012 Cs-137 57.44 +/- 4.60 52.12 42.12 -62.12 Pass SPW-1036 3/5/2012 Sr-90 60.51 +/- 1.93 61.52 49.22 - 73.82 Pass SPMI-1038 3/5/2012 Cs-134 37.79 +/- 4.06 39.42 29.42 - 49.42 Pass SPMI-1038 3/5/2012 Cs-137 54.75 +/- 5.09 52.12 42.12 - 62.12. Pass SPW-1045 3/5/2012 H-3 68022 +/- 746 69048 55238 - 82858 Pass SPW-1047 3/5/2012 Ni-63 217.10 +/- 3.64 206.64 144.65 - 268.63 Pass SPW-1049 3/5/2012 C-14 3858.90 +/- 12,79 4738.80 2843.28 - 6634.32 Pass W-31412 3/14/2012 Ra-226 13.13 +/- 0.36 16.70 11.69 - 21,71 Pass SPW-1520 3/23/2012 U-238 45.67 +/- 2.02 41.70 29.19 - 54.21 Pass SPW-41825 4/1012012 Ra-228 28.48 +/- 2.51 28.35 19.85 - 36.86 Pass WW-1547 4/16/2012 Ba-133 18.99 +/- 4.67 26.70 16.70 - 36.70 Pass WW-1547 4/16/2012 Cs-134 9.28 +/- 2.82 8.68 0.00 - 18.68 Pass WW-1547 4/16/2012 Cs-137 27.77 +/- 4,49 29.70 19.70 - 39.70 Pass W-51712 5/17/2012 Ra-226 17.29 +/- 0.43 16.70 11.69 - 21.71 Pass W-61112 6/11/2012 Gr. Alpha 22.16 +/- 0.45 20.00 10.00 - 30.00 Pass W-61112 -6/11/2012 Gr. Beta 43.57 +/- 0.40 45.20 35.20 - 55.20 Pass SPAP-4418 7/25/2012 Gr. Beta 43.74 +/- 0.11 46.50 27.90 - 65.10 Pass SPAP-4420 7/25/2012 Cs-134 4.54 +/- 0.73 4.60 2.76 - 6.44 Pass SPAP-4420 7/25/2012 Cs-1 37 104.70 +/- 2.77 103.30 92.97 - 113.63 Pass SPMI-4422 7/25/2012 Co-60 31.43 +/- 2.12 31.62 21.62 - 41.62 Pass SPMI-4422 7/25/2012 Cs-134 16.50 +/- 1.17 16.15 6.15 -26.15 Pass SPMI-4422 7/25/2012 Cs-137 29.60 +/- 2.61 26.64 16.64 - 36.64 Pass SPMI-4422 7/25/2012 Sr-90 31.60 +/- 1.35 30.47 24.38 - 36.56 Pass SPW-4424 7/25/2012 Co-60 38.52 +/- 1.76 37.95 27.95 - 47.95 Pass SPW-4424 7/25/2012 Cs-137 33.23 +/- 2.27 32.01 22.01 - 42.01 Pass SPW-4424 7/25/2012 Sr-90 36.56 +/- 1.58 40.60 32.48 - 48.72 Pass SPF-4426 7125/2012 Cs-1 34 947.50 +/- 42.50 1025.00 922.50 - 1127.50 Pass SPF-4426 7/2512012 Cs-1137 2692.00 1 62.40 2480.00 2232.00 - 2728.00 Pass SPW-4428 7/25/2012 C-14 4325.70 +/- 15.80 4738.80 2843.28 - 6634.32 Pass SPW-4430 7/25/2012 H-3 70119.40 +/- 773.40 67570.00 54056.00 - 81084.00 Pass SPW-4432 7/25/2012 Ni-63 187.20 +/- 3.85 206.80 144.76 -268.84 Pass W-81712 8/17/2012 Ra-226 14.94 +/- 0.40 16.70 11.69 - 21.71 Pass SPW-5407 8/29/2012 U-238 42.95 +/- 0.11 41.70 29.19 - 54.21 Pass SPW-18022 9/10/2012 Ra-228 29.03 +/- 2.80 28.21 19.75 - 36.67 Pass A3-1

TABLE A-3. In-House "Spiked" Samples Concentration (pCi/L)a Lab Code b Date Analysis Laboratory results Known Control 2s, n=1 c Activity Limitsd Acceptance W-91012 9/10/2012 Gr. Alpha 19.95 +/- 0.42 20.00 10.00 - 30.00 Pass W-91012 9/10/2012 Gr. Beta 43.47 +/- 0.40 45.20 35.20 - 55.20 Pass W-1100312 10/3/2012 Gr. Alpha 19.95 +/- 0,41 20.00 10.00 -30.00 Pass W-100312 10/3/2012 Gr. Beta 44.21 +/- 0.40 45.20 35.20 - 55.20 Pass W-101812 10/18/2012 Ra-226 18.80 +/- 0.43 16.70 11.69 -21.71 Pass ESO-7235 12/6/2012 Sr-90 138.79 +/- 2.67 161.05 128.84 - 193.26 Pass SPW-7753 12/6/2012 U-238 45.55 +/- 5.05 41.70 29.19 -54.21 Pass SPW-18023 12/18/2012 Ra-228 31.59 +/- 2.99 25.98 18.19 -33.77 Pass 8 Liquid sample results are reported In pCi/Liter, air filters( pCi/filter), charcoal (pCi/m 3), and solid'samples (pCi/g).

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

Results are based on single determinations.

d Control limits are established from the precision values listed In Attachment A of this report, adjusted to +/- 2ar.

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)8 Lab Code Sample Date Analysisb Laboratory results (4.66a) Acceptance Type LLD Activityc Criteria (4.66 0)

SPW-41814 Water 2/15/2012 Ra-228 0.65 0.49 +/- 0.36 2 W-22712 Water 2/27/2012 Gr. Alpha 0.42 -0.04 +/- 0.29 1 W-22712 Water 2/27/2012 Gr. Beta 0.74 -0.54 +/- 0.50 3.2 SPAP-1031 Air Filter 3/5/2012 Cs-134 1.89 100 SPAP-1031 Air Filter 3/5/2012 Cs-137 1.16 100 SPAP-1033 Air Filter 3/5/2012 Gr. Beta 0.003 0.013 + 0.003 0.01 SPW-1035 Water 3/5/2012 Cs-134 2.40 10 SPW-1035 Water 315/2012 Cs-137 2.88 10 SPW-1 035 Water 3/5/2012 1-131(G) 2.35 20 SPW-1035 Water 3/5/2012 Sr-90 0.60 -0.11 +/- 0.26 1 SPMI-1037 Milk 3/5/2012 Cs-134 2.85 10 SPMI-1037 Milk 315/2012 Cs-1 37 3.73 10 SPMI-1037 Milk 3/5/2012 1-131(G) 3.24 20 SPW-1 044 Water 3/5/2012 H-3 146.10 37.10 +/- 74.40 200 SPW-1046 Water 3/5/2012 Ni-63 19.07 8.30 +/- 11.79 20 SPW-1 048 Water 3/5/2012 C-14 5.70 2.99 +/- 3.04 200 SPW-1166 water 3/9/2012 C-14 6.79 1.11 200 W-31412 Water 3/14/2012 Ra-226 0,034 0.043 +/- 0.027 1 SPW-1521 Water 3/23/2012 U-238 0.10 0.09 +/- 0.11 1 W-51712 Water 4/24/2012 Ra-226 0.04 0.04 +/- 0.03 1 W-61112 Water 6/11/2012 Gr. Alpha 0.47 -0.14 +/- 0.32 1 W-61"112 Water 6/11/2012 Gr. Beta 0.71 0.29 +/- 0.51 3.2 SPW-41815 Water 7/7/2011 Ra-228 0.77 0.52 +/- 0.42 2 SPAP-4417 Air Filter 7125/2012 Gr. Beta 0.001 0.021 +/- 0.003 0.01 SPMI-4421 Milk 7125/2012 Co-60 4.29 10 SPMI-4421 Milk 7/25/2012 Cs-134 3.58 10 SPMI-4421 Milk 7/25/2012 Cs-137 4.60 10 SPMI-4421 Milk 7/25/2012 Sr-90 0.45 0.53 +/- 0.27 I SPW-4423 Water 7/25/2012 Co-60 1.88 10 SPW-4423 Water 7/25/2012 Cs-134 2.38 10 SPW-4423 Water 7/25/2012 Cs-137 2.80 10 SPW-4423 water 7/25/2012 Sr-90 0.45 0.08 +/- 0.22 1 SPF-4425 Fish 712512012 Co-60 6.74 100 SPF-4425 Fish 7/25/2012 Cs-134 7.47 100 SPF-4425 Fish 7/25/2012 Cs-137 9.62 100 SPW-4427 Water 7/25/2012 C-14 10.93 3.54 +/- 5.84 200 SPW-4431 Water 7/25/2012 Ni-63 19.00 5.50 +/- 11.70 20 W-81712 Water 8/17/2012 Ra-226 0.038 0.035 +/- 0.030 1 SPW-5408 Water 8/29/2012 U-238 0.039 0.015 +/- 0.057 1 A4-1

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

SPW-18032 Water 9/10/2012 Ra-228 0.78 0.85 +/- 0.46 2 W-91012 Water 9110/2012 Gr. Alpha 0.42 0.027 +/- 0.29 1 W-91012 Water 9/10/2012 Gr. Beta 0.75 -0.13 +/- 0.52 3.2 W-100312 Water 10/3/2012 Gr. Beta 0.77 -0.32 +/- 0.53 3.2 W-100312 Water 10/312012 Gr. Beta 0.43 0.06 +/- 0.30 3.2 W-101812 Water 10/18/2012 Ra-226 0.04 0.04 +/- 0.03 1 SPW-7754 Water 12/6/2012 U-238 0.10 0.02 +/- 0.08 1 SPW-18033 Water 12/18/2012 Ra-228 0.98 0.43 +/- 0.50 2 Liquid sample results are reported in pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

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

' Activity reported Is a net activity result. For gamma spectroscopic analysis, activity detected below the LLD value Is not reported.

A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance CF-20, 21 1/3/2012 Gr. Beta 14.50 +/- 0.29 15.02 +/- 0.30 14.76 +/- 0.21 Pass CF-20, 21 1/312012 K-40 12.88 +/- 0.55 12.40 +/- 0.53 12.64 +/- 0.38 Pass CF-20, 21 1/3/2012 Sr-90 0.01 +/- 0.01 0.01 +/- 0.01 0.01 +/- 0.00 Pass P-9133, 9134 1/3/2012 H-3 108.86 +/- 83.03 206.60 +/- 86.38 157.73 +/- 59.91 Pass U-302, 303 1M1712012 Beta (-K40) 6.84 +/- 2.91 5.24 +/- 2.56 6.04 +/- 1.94 Pass S-386, 387 1/23/2012 Ac-228 0.77 +/- 0.11 0.79 +/- 0.14 0.78 +/- 0.09 Pass S-386, 387 1/23/2012 Bi-214 0.80 +/- 0.07 0.73 +/- 0.11 0.77 +/- 0.07 Pass S-386, 387 1/23/2012 Pb-214 0.74 +/- 0.06 0.75 +/- 0.11 0.75 +/- 0.06 Pass S-386, 387 1/23/2012 TI-208 0.21 +/- 0.02 0.21 +/- 0.04 0.21 +/- 0.02 Pass S-386, 387 1/23/2012 U-235 0.05 +/- 0.02 0.12 +/- 0.05 0.09 +/- 0.03 Pass WW-619, 620 1/31/2012 H-3 257.20 +/- 86.00 305.80 +/- 88.30 281.50 +/- 61.63 Pass MI-702, 703 2/6/2012 K-40 1337.00 +/- 123.00 1460.40 +/- 102.00 1398.70 +/- 79.90 Pass WW-892,893 2/17/2012 Gr. Beta 3.46 +/- 0.56 3.77 +/- 0.59 3.61 +/- 0.41 Pass S-850,851 2122/2012 Cs- 134 0.14 +/- 0.02 0.13 +/- 0.02 0.14 +/- 0.01 Pass S-850, 851 2122/2012 Cs-137 0.21 +/- 0.03 0.22 +/- 0.03 0.22 +/- 0.02 Pass W-1251, 1252 3/6/2012 Gr. Alpha 1.20 +/- 0.62 1.27 +/- 0.92 1.24 +/- 0.55 Pass W-1251, 1252 3/6/2012 Gr. Beta 16.86 +/- 1.43 15.14 +/- 1.34 16.00 +/- 0.98 Pass W-1251, 1252 3/6/2012 H-3 5235.52 +/- 230.91 4893.24 +/- 224.55 5064.38 + 161.05 Pass W-1251, 1252 3/6/2012 Tc-99 19.67 +/- 3.60 14.46 +/- 3.51 17.07 +2.51 Pass AP-1209, 1210 31812012 Be-7 0.24 +/- 0.12 0.20 +/- 0. 11 0.22 +/- 0.08 Pass XWW-1564, 1565 3/14/2012 H-3 308.00 +/- 88.00 293.00 +/- 87.00 300.50 +61.87 Pass SG-1438, 1439 3/19/2012 Ac-228 6.01 +/- 0.30 6.23 +/- 0.31 6.12 +/-0.22 Pass SG-1438, 1439 3/19/2012 Pb-214 4.69 +/- 0.49 5.20 +/- 0.54 4.95 00.36 Pass WW-1585, 1586 3/19/2012 H-3 3124.50 +/- 176.96 2982.38 +/- 173.62 3053.44 +/- 123.96 Pass AP-2103, 2104 3/28/2012 Be-7 0.080 +/- 0.016 0.076 +/- 0.013 0.078 +/- 0.010 Pass AP-2166, 2167 3/28/2012 Be-7 0.061 +/- 0.020 0.071 +/- 0.016 0.066 +/- 0.013 Pass AP-1632, 1633 3/29/2012 Be-7 0.26 +/- 0.12 0.24 +/- 0.12 0.25 +/- 0.08 Pass E-1653,1654 4/2/2012 Gr. Beta 1.53 +/- 0.05 1.55 +/- 0.04 1.54 +/- 0.03 Pass E-1653, 1654 4/212012 K-40 1.34 +/- 0.13 1.36 +/- 0.14 1.35 +/- 0.10 Pass SG-1677, 1678 4/2/2012 Ac-228 6.63 +/- 0.37 6.49 +/- 0.33 6.56 +/- 0.25 Pass SG-1677, 1678 4/2/2012 Pb-214 4.77 +/- 0.16 5.07 +/- 0.14 4.92 +/- 0.11 Pass SWU-1719, 1720 4/3/2012 Gr. Beta 1.16 +/- 0.41 1.53 +/- 0.44 1.35 +/- 0.30 Pass W-1698,1699 4/5/2012 Gr. Beta 10.86 +/- 1.49 9.42 +/- 1.32 10.14 +/- 1.00 Pass W-1698,`1699 4/5/2012 Ra-226 0.41 +/- 0.15 0.67 +/- 0.18 0.54 +/- 0.12 Pass W-1698,1699 4/5/2012 Ra-228 1.46 +/- 0.76 1.48 +/- 0.74 1.47 +/- 0.53 Pass SG-1761, 1762 4/10/2012 Ac-228 16.26 +/- 0.53 16.55 +/- 0.44 16.41 +/- 0.34 Pass SG-1761,1762 4/10/2012 Pb-214 14.16 +/- 1.44 15.40 +/- 1.56 14.78 +/- 1.06 Pass AP-2019, 2020 4/12/2012 Be-7 0.17 +/- 0.10 0.17 +/- 0.08 0.17 +/- 0.07 Pass DW-2272, 2273 4/20/2012 1-131 0.52 +/- 0.24 0.49 +/- 0.27 0.51 +/- 0.18 Pass DW-2356,2357 4/2412012 Gr. Beta 12.82 +/- 2.01 9.47 +/- 1.74 11.14 +/- 1.33 Pass A5-1

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

Averaged Lab Code Date Analysis First Result Second Result Result Acceptance G-2403,2404 5/1/2012 Be-7 1.77 +/- 0.21 1.55 +/- 0.33 1.66 +/- 0.20 Pass G-2403,2404 5/1/2012 K-40 6.38 +/- 0.50 6.93 +/- 0.72 6.66 +/- 0.44 Pass BS-2445, 2446 5/1/2012 Gr. Beta 8.92 +/- 1.52 9.29 +/- 1.63 9.11 +/- 1.11 Pass BS-2445, 2446 5/1/2012 K-40 5.86 +/- 0.38 6.22 +/- 0.48 6.04 +/- 0.31 Pass SWU-2550, 2551 5/1/2012 Gr. Beta 2.07 +/- 0.65 1.59 +/- 0.62 1.83 +/- 0.45 Pass WW-2614,2615 5/1/2012 Gr. Beta 2.03 +/- 1.04 2.36 +/- 1.14 2.20 +/- 0.77 Pass WW-2614, 2615 5/1/2012 H-3 750.60 +/- 106.20 653.20 +/- 102.30 701.90 + 73.73 Pass BS-2656, 2657 5/2/2012 Cs-1 37 0.13 +/- 0.07 0.07 +/- 0.04 0.10 +/- 0.04 Pass 8S-2656, 2657 5/2/2012 K-40 10.15 +/- 0.97 11.13 +/- 0.90 10.64 +/- 0.66 Pass SO-2635, 2636 5/3/2012 Cs-137 0.046 +/- 0.024 0.050 +/- 0.027 0.048 +/- 0.018 Pass SO-2635, 2636 5/3/2012 K-40 13.20 +/- 0.74 14.01 +/- 0.67 13.61 +/- 0.50 Pass MI-2677, 2678 5/7/20112 K-40 1415.30 +/- 131.40 1348.10 +/- 109.00 1381.70 +/- 85.36 Pass VE-2719, 2720 517/2012 K-40 4.15 +/- 0.36 4.19 +/- 0.38 4.17 +/- 0.26 Pass SWU-3221, 3222 5/8/2012 Gr, Beta 1.67 +/- 0.47 1.39 +/- 0.45 1.53 +/- 0.33 Pass SWU-3221, 3222 5/8/2012 H-3 236.90 +/- 101.90 281.90 +/- 103.70 259.40 +/- 72.69 Pass WW-3073,3074 5/14/2012 H-3 339.12 +/- 145.45 337.23 +/- 98.19 338.18 +/- 87.74 Pass AP-2968, 2969 5/17/2012 Be-7 0.25 +/- 0.12 0.21 + 0.09 0.23 +/- 0.07 Pass F-3031, 3032 5/2212012 H-3 11291.00 +/- 372.80 11167.00 +/- 315.00 11229.00 +/- 244.03 Pass F-3031, 3032 5/22/2012 K-40 3528.90 +/- 372.80 3677.20 + 392.40 3603.05 +/- 270.63 Pass G-3094,3095 5/23/2012 Gr. Beta 7.89 +/- 0.16 8.01 +/- 0.16 7.95 +/- 0.11 Pass F-3412, 3413 5/23/2012 Gr. Beta 3.46 +/- 0.10 3.33 +/- 0.10 3.40 +/- 0.07 Pass F-3412,3413 5/23/2012 K-40 2.40 +/- 0.38 2.55 +/- 0.43 2.48 +/- 0.29 Pass MI-3067, 3068 5/24/2012 K-40 1267.20 +/- 105.00 1305.70 +/- 109.80 1286.45 +/- 75.96 Pass SO-3305,3306 5/30/2012 Cs-137 0.024 +/- 0.013 0.030 +/- 0.015 0.027 +/- 0.010 Pass SO-3305, 3306 5/30/2012 Gr. Beta 10.95 +/- 0.89 10.86 +/- 0.89 10.91 +/- 0.63 Pass SO-3305, 3306 5/30/2012 TI-208 0.068 +/- 0.018 0.062 +/- 0.017 0.065 +/- 0.012 Pass LW-3454, 3455 5/31/2012 Gr. Beta 2.12 +/- 0.86 2.27 +/- 0.77 2.20 +/- 0.58 Pass BS-3697, 3698 6/14/2012 Be-7 2.05 +/- 0.19 2.27 +/- 0.38 2.16 +/- 0.21 Pass BS-3697, 3698 6/14/2012 Cs-137 2.32 +/- 0.39 2.26 +/- 0.66 2.29 +/- 0.38 Pass 8S-3697, 3698 6/14/2012 K-40 6.67 +/- 0.28 6.64 +/- 0.42 6.66 +/- 0.25 Pass VE-3798, 3799 6/20/2012 K-40 5.93 +/- 0.38 6.03 +/- 0.37 5.98 +/- 0.26 Pass WW-4790,4791 6/20/2012 H-3 251.33 +/- 86.51 372.48 +/- 92.27 311.90 +/- 63.24 Pass DW-30103, 30104 6/27/2012 Ra-226 0.30 +/- 0.08 0.42 +/- 0.09 0.36 +/- 0.06 Pass DW-30103,30104 6/27/2012 Ra-228 0.76 +/- 0.54 0.78 +/- 0.54 0.77 +/- 0.38 Pass LW-3970, 3971 6/28/2012 Gr. Beta 1.49 +/- 1.06 0.72 +/- 0.53 1.11 +/- 0.59 Pass DW-3949, 3950 6/29/2012 1-131 0.54 +/- 0.26 0.25 +/- 0.26 0.40 +/- 0.18 Pass SG-4075,4076 7/2/2012 Ac-228 0.33 +/- 0.09 0.34 +/- 0.06 0.34 +/- 0.05 Pass SG-4075, 4076 7/2/2012 K-40 6.71 +/- 0.58 7.20 +/- 0.32 6.96 +/- 0.33 Pass SG-4075,4076 7/2/2012 Pb-214 0.46 +/- 0.05 0.49 +/- 0.03 0.48 +/- 0.03 Pass AP-4390, 4391 7/3/2012 Be-7 0.09 +/- 0.02 0.09 +/- 0.01 0.09 +/- 0.01 Pass AP-4390, 4391 7/3/2012 Be-7 0.11 +/- 0.02 0.10 +/- 0.01 0.11 +/- 0.01 Pass AP-4012, 4013 7/5/2012 Be-7 0.27 +/- 0.09 0.29 +/- 0.16 0.28 +/- 0.09 Pass SW-4033, 4034 7/5/2012 H-3 614.99 +/- 107.99 512.31 +/- 103.83 563.65 +/- 74.91 Pass A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance VE-4054, 4055 7/9/2012 K-40 7.28 +/- 0.56 7.42 +/- 0.63 7.35 +/- 0.42 Pass VE-4222, 4223 7/13/2012 Be-7 0.16 +/- 0.08 0.22 +/- 0.09 0.19 +/- 0.06 Pass VE-4222, 4223 7/13/2012 K-40 7.20 +/- 0.30 6.60 +/- 0.30 6.90 +/- 0.21 Pass DW-30113, 30114 7/13/2012 Ra-228 1.93 +/- 0.66 1.03 +/- 0.53 1.48 +/- 0.42 Pass DW-30115, 30116 7/13/2012 Gr. Alpha 7.46 +/- 1.21 7.02 +/- 1.14 7.24 +/- 0.83 Pass DW-30124, 30125 7/13/2012 Ra-226 1.16 +/- 0.15 0.90 +/- 0.12 1.03 +/- 0.10 Pass DW-30124, 30125 7/13/2012 Ra-228 1.38 +/- 0.56 1.72 +/- 0.60 1.55 +/- 0.41 Pass DW-30126, 30127 7/13/2012 Gr. Alpha 6.23 +/- 1.16 6.75 +/- 1.29 6.49 +/- 0.87 Pass AP-4433, 4434 7/19/2012 Be-7 0.17 +/- 0.09 0.21 +/- 0.10 0.19 +/- 0.07 Pass SG-4475, 4476 7/19/2012 Gr. Alpha 17.03 +/- 4.17 15.56 +/- 3.96 16.30 +/- 2.88 Pass SG-4475, 4476 7/19/2012 Gr. Beta 13.23 +/- 2.61 14.36 +/- 2.47 13.80 +/- 1.80 Pass WW-4685, 4686 7/24/2012 H-3 289.00 +/- 99.00 375.00 +/- 103.00 332.00 +/- 71.43 Pass AP-4706, 4707 7/26/2012 Be-7 0.28 +/- 0.14 0.24 +/- 0.14 0.26 +/- 0.10 Pass SO-4748, 4749 7/26/2012 Gr. Beta 20.45 +/- 1.04 19.22 +/- 0.94 19.84 +/- 0.70 Pass SO-4748, 4749 7/26/2012 Gr. Beta 20.45 +/- 1.04 19.22 +/- 0.94 19.84 +/- 0.70 Pass SO-4748, 4749 7/26/2012 U-233/4 0.11 +/-0.02 0.10 +/- 0.01 0.11 +/- 0.01 Pass SO-4748, 4749 7/26/2012 U-238 0.12 +/- 0.02 0.11 +/- 0.01 0.12 +/- 0.01 Pass VE-4832, 4833 8/1/2012 K-40 4.06 +/- 0.22 4.08 +/- 0.24 4.07 +/- 0.16 Pass DW-30149, 30150 8/1/2012 Ra-226 2.69 +/- 0.22 2.79 +/- 0.22 2.74 +/- 0.16 Pass DW-30149, 30150 8/1/2012 Ra-228 2.77 +/- 0.75 1.61 +/- 0.57 2.19 +/- 0.47 Pass SG-4916, 4917 8/3/2012 Ac-228 11.03 +/- 0.33 11.08 +/- 0.44 11.06 +/- 0.28 Pass SG-4916, 4917 8/3/2012 K-40 6.39 +/- 0.80 6.98 +/- 0.88 6.69 +/- 0.59 Pass F-5313, 5314 8/9/2012 Cs-137 0.05 +/- 0.02 0.05 +/- 0.02 0.05 +/- 0.01 Pass F-5313, 5314 8/9/2012 Gr. Beta 4.12 +/- 0.08 4.10 +/- 0.08 4.11 +/- 0.06 Pass F-5313, 5314 8/9/2012 K-40 3.07 +/- 0.42 3.14 +/- 0.40 3.11 +/- 0.29 Pass VE-5166, 5167 8/15/2012 K-40 4.26 +/- 0.28 3.66 +/- 0.47 3.96 +/- 0.27 Pass VE-5376, 5377 8/22/2012 Gr. Beta 7.72 +/- 0.17 7.61 +/- 0.16 7.67 +/- 0.12 Pass VE-5334, 5335 8/27/2012 K-40 1.65 +/- 0.17 1.72 +/- 0.15 1.68 +/- 0.12 Pass VE-5481, 5482 8/28/2012 Be-7 2.52 +/- 0.19 2.65 +/- 0.21 2.59 +/- 0.14 Pass VE-5481, 5482 8/28/2012 K-40 5.05 +/- 0.37 4.79 +/- 0.39 4.92 +/- 0.27 Pass VE-5481, 5482 8/28/2012 Sr-90 0.01 +/- 0.00 0.01 +/- 0.01 0.01 +/- 0.00 Pass DW-30164, 30165 8/30/2012 Ra-226 1.33 +/- 0.15 1.59 +/- 0.17 1.46 +/- 0.11 Pass DW-30164, 30165 8/30/2012 Ra-228 2.76 +/- 0.66 1.54 +/- 0.56 2.15 +/- 0.43 Pass VE-5166, 5167 9/4/2012 K-40 2.05 +/- 0.32 2.53 +/- 0.36 2.29 +/- 0.24 Pass ME-5607, 5608 9/4/2012 Gr. Beta 2.92 +/- 0.08 2.89 +/- 0.08 2.90 +/- 0.06 Pass ME-5607, 5608 9/4/2012 K-40 2.06 +/- 0.32 2.53 +/- 0.36 2.29 +/- 0.24 Pass SW-5901, 5902 9/17/2012 H-3 10909.00 +/- 311.00 10817.00 +/- 310.00 10863.00 +/- 219.56 Pass BS-6048, 6049 9/24/2012 K-40 1.24 +/- 0.20 1.18 +/- 0.21 1.21 +/- 0.14 Pass AP-6482, 6483 9/27/2012 Be-7 0.09 +/- 0.02 0.09 +/- 0.03 0.09 +/- 0.02 Pass A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)8 Averaged Lab Code Date Analysis First Result Second Result Result Acceptance G-6090,6091 10/1/2012 Be-7 3.74 +/- 0.33 3.54 +/- 0.30 3.64 +/- 0.22 Pass G-6090,6091 10/1/2012 Gr. Beta 10.81 +/- 0.34 10.72 +/- 0.33 10.77 +/- 0.24 Pass G-6090,6091 10/11/2012 K-40 5.99 +/- 0.47 5.45 +/- 0.44 5.72 + 0.32 Pass SO-6111, 6112 10/1/2012 Cs-137 0.06 +/- 0.03 0.04 +/- 0.02 0.05 +/- 0.02 Pass SO-6111, 6112 10/1/2012 K-40 19.66 +/- 0.84 20.09 +/- 0.80 19.88 +/- 0.58 Pass W-6795,6796 10/1/2012 H-3 215.20 +/- 88.00 292.80 +/- 91.60 254.00 +/- 63.51 Pass AP-6461, 6462 10/2/2012 Be-7 0.07 +/- 0.01 0.07 +/- 0.02 0.07 +/- 0.01 Pass WW-6279,6280 10/3/2012 Gr. Beta 1.54 +/- 0.68 1.67 +/- 0.75 1.61 +/- 0.51 Pass W-6346,6347 10/3/2012 Ra-226 0.30 +/- 0.10 0.36 +/- 0.10 0.33 +/- 0.07 Pass VE-6503,6504 10/9/2012 K-40 5.23 +/- 0.83 6.00 +/- 0.45 5.04 +/- 0.27 Pass WW-6606,6607 10/10/2012 Gr. Beta 3.18 +/- 1.31 2.42 +/- 1.27 2.80 +/- 0.91 Pass WW-6606,6607 10/10/2012 H-3 273.10 +/- 85.70 219.80 +/- 83.10 246.45 +/- 59.69 Pass WW-7237,7238 10/12/2012 H-3 175.44 +/- 99.84 180.75 +/- 100.03 178.10 +/- 70.66 Pass F-6627, 6628 10/15/2012 K-40 3.05 +/- 0.39 3.23 +/- 0.37 3.14 +/- 0.27 Pass VE-6669, 6670 10/16/2012 Be-7 0.48 +/- 0.26 0.50 +/- 0.13 0.49 +/- 0.15 Pass VE-6669, 6670 10/16/2012 K-40 4.06 +/- 0.28 3.68 +/- 0.26 3.87 +/- 0.19 Pass SS-6711, 6712 10/16/2012 Ac-228 0.16 +/- 0.05 0.17 +/- 0.06 0.17 +/- 0.04 Pass SS-6711, 6712 10/16/2012 Bi-214 0.13 +/- 0.03 0.16 +/- 0.03 0.14 +/- 0.02 Pass SS-6711, 6712 10/16/2012 Gr. Beta 14.20 +/- 0.89 12.67 +/- 0.88 13.44 +/- 0.63 Pass SS-6711, 6712 10/16/2012 Pb-212 0.15 +/- 0.06 0.13 +/- 0.02 0.14 +/- 0.03 Pass SS-6711, 6712 10/16/2012 TI-208 0.06 +/- 0.02 0.04 +/- 0.02 0.05 +/- 0.01 Pass WW-7258,7259 10/22/2012 H-3 214.69 +/- 85.42 314.60 +/- 90.25 264.65 +/- 62.13 Pass WW-7655,7656 10/25/2012 H-3 159.00 +/- 86.10 159.00 +/- 86.10 159.00 +/- 60.88 Pass WW-7747,7748 10/25/2012 H-3 156.50 +/- 84.70 170.20 +/- 85.30 163.35 +/- 60.10 Pass MI-6963, 6964 10/28/2012 K-40 1384.60 +/- 111.70 1421.60 +/- 107.60 1403.10 +/- 77.55 Pass MI-7174, 7175 11/5/2012 K-40 1283.60 +/- 97.45 1293.20 +/- 91.37 1288.40 +/- 66.79 Pass SG-7221,7222 11/9/2012 Pb-214 31.49 +/- 0.70 30.11 +/- 0.80 30.80 +/- 0.53 Pass DW-30216, 30217 11/9/2012 Gr. Alpha 2.23 +/- 0.86 2.31 +/- 0.92 2.27 +/- 0.63 Pass DW-30216, 30217 11/9/2012 Ra-226 0.72 +/- 0.12 0.82 +/- 0.14 0.77 +/- 0.09 Pass DW-30216, 30217 11/9/2012 Ra-228 0.92 +/- 0.52 1.26 +/- 0.53 1.09 +/- 0.37 Pass MI-7363, 7364 11/13/2012 K-40 1304.40 +/- 103.30 1496.10 +/- 121.30 1400.25 +/- 79.66 Pass CF-7384, 7385 11/13/2012 K-40 11.75 +/- 0.52 10.94 +/- 0.59 11.35 +/- 0.39 Pass VE-7489, 7490 11/16/2012 K-40 2.22 +/- 0.23 1.91 +/- 0.22 2.06 +/- 0.16 Pass AP-7531, 7532 11/21/2012 Be-7 0.19 +/- 0.10 0.29 +/- 0.17 0.24 +/- 0.10 Pass BS-7573,7574 11/24/2012 K-40 7.21 +/- 0.41 7.57 +/- 0.39 7.39 +/- 0.28 Pass LW-7865, 7866 12/5/2012 Gr. Beta 2.16 +/- 0.56 1.64 +/- 0.62 1.90 +/- 0.42 Pass SG-8095,8096 12/19/2012 Ac-228 25.15 +/- 0.73 25.47 +/- 0.54 25.31 +/- 0.45 Pass SG-8095, 8096 12/19/2012 Gamma 26.98 +/- 2.72 28.68 +/- 2.89 27.83 +/- 1.98 Pass Note: Duplicate analyses are performed on every twentieth sample received In-house. Results are not listed for those analyses with activities that measure below the LLD.

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

A5-4

TABLE A-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-1783 04/09/12 Sr-89 62.2 +/- 6.0 58.5 46.9 - 66.3 Pass ERW-1783 04/09/12 Sr-90 33.7 +/- 2.1 37.4 27.4 - 43.1 Pass ERW-1786 04/09/12 Ba-133 75.7 +/- 4.1 82.3 69.1 - 90.5 Pass ERW-1786 04/09/12 Co-60 71.9 +/- 4.0 72.9 65.6 - 82.6 Pass ERW-1786 04/09/12 Cs-134 70.0 +/- 4.3 74.2 60.6 -81.6 Pass ERW-1786 04/09/12 Cs-137 151.5 +/-6.1 155.0 140.0 - 172.0 Pass ERW-1786 04/09/12 Zn-65 108.3 +/- 89.0 105.0 94.5 - 125.0 Pass ERW-1789 04/09/12 Gr. Alpha 55.0 +/- 2.4 62.9 33.0 - 78.0 Pass ERW-1789 ' 04/09/12 Gr. Beta 76.2 +/- 1.8 44.2 29.6 -51.5 Fail ERW-1795 04/09/12 Ra-226 6.4 +/- 0.4 5.7 4.3 - 6.9 Pass ERW-1795 04/09/12 Ra-228 5.4 +/- 1.2 4.6 2.7 - 6.3 Pass ERW-1 795 04/09/12 Uranium 56.2 +/- 2.6 61.5 50.0 - 68.2 Pass ERW-1798 04/09/12 H-3 16023 +/- 355 15800 13800-17400 Pass ERW-6283 10/05/12 Sr-89 41.5 +/- 4.1 39.1 29.7 - 46.1 Pass ERW-6283 10/05/12 Sr-90 19.7 +/- 1.6 20.1 14.4 -23.8 Pass ERW-6286 10/05/12 Ba-133 82.7 +/- 4.4 84.8 71.3 - 93.3 Pass ERW-6286 10/05/12 Co-60 77.2 +/- 3.7 78.3 70.5 - 88.5 Pass ERW-6286 10/05/12 Cs-134 74.4 +/- 1.5 76.6 62.6 - 84.3 Pass ERW-6286 10/05/12 Cs-137 183.0 +/- 6.2 183.0 165.0 - 203.0 Pass ERW-6286 10/05/12 Zn-65 211.0 +/-9.9 204.0 184.0 - 240.0 Pass ERW-6288 10105112 Gr. Alpha 47.0 +/- 2.3 58.6 30.6 - 72.9 Pass ERW-6288 10/05/12 Gr. Beta 33.4 +/- 1.2 39.2 26.0 - 46.7 Pass ERW-6290 10/05/12 1-131 23.3 +/- 1.0 24.8 20.6 - 29.4 Pass ERW-6295e 10/05/12 Ra-226 17.5 +/- 0.7 15.0 11.2 -17.2 Fail ERW-6295e 10/05/12 Ra-228 7.4 +/- 1.5 4.6 2.7 -6.2 Fall ERW-6295 10/05/12 Uranium 61.2 +/- 1.8 62.5 50.8 - 69.3 Pass 8 Results obtained by Environmental, Inc., Midwest Laboratory as a participant In the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

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

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

d Result of reanalysis: 38.3 +/- 1.3 pCi/L. Sample dilution problem suspected. A new dilution was prepared.

e Results of reanalyses, original submission (pCi/L): Ra-226, 16.5 +/- 0.7 Ra-228, 4.9 +/- 1.1 A new test was ordered from Environmental Resources Associates, results will be updated for first quarter, 2013.

Al-1

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

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance STW-1670 02/01/12 1-129 9.31 +/- 0.31 12.29 8.60 - 15.98 Pass STSO-1 766 d 02/01/12 Am-241 88.50 +/- 8.30 159.00 111.00 - 207.00 Fail STSO-1 766 02/01/12 Co-57 1352.10 +/- 4.00 1179.00 825.00 - 1533.00 Pass STSO-1 766 02/01/12 Co-60 1.70 +/- 0.70 1.56 1.00 -2.00 Pass STSO-1 766 02/01/12 Cs-134 842.20 +/- 4.30 828.00 580.00 - 1076.00 Pass STSO-1766 02/01/12 Cs-137 0.40 +/- 0.90 0.00 0.00 - 1.00 Pass STSO-1766 02101/12 K-40 1729.60 +/- 22.20 1491.00 1044.00 - 1938.00 Pass STSO-1 766 02/01/12 Mn-54 647.60 +/- 4.20 558.00 391.00 - 725.00 Pass STSO-1766 02/01/12 Ni-63 781.50 +/- 9.70 862.00 603.00 - 1121.00 Pass STSO-1 766 02/01/12 Pu-238 142,40 +/- 9.70 136.00 97.00 - 177.00 Pass STSO-1 766 02/01/12 Pu-239/40 66.10 +/- 6.40 65.80 46.10 -85.50 Pass STSO-1766 02/01/12 Sr-90 383.20 +/- 15.30 392.00 274.00 - 510.00 Pass STSO-1766 02/01/12 Tc-99 289.60 +/- 10.90 374.00 262.00 - 486.00 Pass STSO-1766 02/01/12 U-233/4 63.20 +/- 5.40 68.10 47.70 - 88.50 Pass STSO-1766 02/01/12 U-238 310.80 +/- 12.10 329.00 230.00 - 428.00 Pass STSO-1766 02/01/12 Zn-65 766.70 +/- 6.70 642.00 449.00 - 835.00 Pass STAP-1772 02/01/12 Am-241 0.062 +/- 0.02 0.073 0.051 -0.10 Pass STAP-1772 02/01/12 Co-57 0.010 +/- 0.01 0.00 0.000 -1.00 Pass STAP-1772 02/01/12 Co-60 2.40 +/- 0.08 2.18 1.53 - 2.84 Pass STAP-1 772 02/01/12 Cs-134 2.33 +/- 0.13 2.38

• 1.67 -3.09 Pass STAP-1 772 02/01/12 Cs-137 2.07 +/- 0.10 1.79 1.25 - 2.33 Pass STAP-1772 02/01/12 Mn-54 3.77 +/--0.14 3.24 2.27 - 4.21 Pass STAP-1772 02/01/12 Pu-238 0.003 +/- 0.004 0.002 0.000 -0.10 Pass STAP-1 772 02/01/12 Pu-239/40 0.098 +/- 0.017 0.097 0.07 -0.13 Pass STAP-1772 02/01/12 Sr-90 -0.010 +/- 0.060 0.000 -0.10 -0.13 Pass STAP-1772 6 02/01/12 U-233/4 0.016 +/- 0.006 0.019 0.013 - 0.024 Pass STAP-1772 02/01/12 U-238 0.11 +/-0.02 0.12 0.09 -0.16 Pass STAP-1772 02/01/12 Zn-65 3.67 +/- 0.20 2.99 2.09 - 3.89 Pass STAP-1773 02/01/12 Gr. Alpha 0.51 +/- 0.05 1.20 0.40 - 2.00 Pass STAP-1773 02/01/12 Gr. Beta 2.75 +/- 0.10 2.40 1.20 - 3.60 Pass STVE-1776 02/01/12 Co-57 14.57 +/- 0.28 12.00 8.40 - 15.60 Pass STVE-1776 02/01/12 Co-60 6.45 +/- 0.23 6.05 4.24 - 7.87 Pass STVE-1776 02/01/12 Cs-1 34 8.39 +/- 0.29 8.43 5.90 - 10.96 Pass STVE-1776 02/01/12 Cs-1 37 0.01 +/- 0.09 0.00 0.00 -0.10 Pass STVE-1776 02/01/12 Mn-54 0.03 +/- 0.08 0.00 0.00 - 0.10 Pass STVE-1776 02/01/12 Zn-65 10.31 +/- 0.67 8.90 6.23-11.57 Pass STW-1960 02/01112 Gr. Alpha 1.68 +/- 0.09 2.14 0.64 - 3.64 Pass STW-1960 02/01/12 Gr. Beta 6.33 +/- 0.10 6.36 3.18 -9.54 Pass A6-1

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

Concentration 8 Known Control Lab Code b Date Analysis Laboratory result Activity Limits ' Acceptance STW-1964 02/01/12 Am-241 1.28 +/- 0.12 1.63 1.14 -2.12 Pass STW-1964 02101112 Co-57 33.30 +/- 0.40 32.90 23.00 - 42.80 Pass STW-1964 02101/12 Co-60 23.20 +/- 0.40 23.72 16.60 - 30.84 Pass STW-1964 02/01/12 Cs-134 0.30 +/- 3.00 0.00 0.00 - 1.00 Pass STW-1964 02/01/12 Cs-137 40.10 +/- 0.60 39.90 27.90 - 51.90 Pass STW-1964' 02/01/12 Fe-55 65.10 +/- 9.50 81.90 57.30 - 106.50 Pass STW-1964 02/01/12 H-3 460.00 +/- 12.10 437.00 306.00 - 568.00 Pass STW-1964 02/01/12 K-40 153.00 +/- 4.20 142.00 99.00 - 185.00 Pass STW-1964 02/01/12 Mn-54 32.70 +/- 0.60 31.80 22.30 - 41.30 Pass STW-1964 02/01/12 Ni-63 49.80 +/- 2.90 60.00 42.00 - 78.00 Pass STW-1964 02/01/12 Pu-238 0.58 +/- 0.06 0.63 0.44 -0.82 Pass STW-1964 02/01/12 Pu-239/40 1.30 +/- 0.15 1.34 0.94 -1.74 Pass STW-1964 02101/12 Sr-90 0.10 +/- 0.20 0.00 0.00-1.00 Pass STW-1964 02/01/12 Tc-99 23.70 +/- 0.80 27.90 19.50 - 36.30 Pass STW-1964 02/01/12 U-233/4 0.40 +/- 0.05 0.39 0.27 - 0.51 Pass STW-1964 02/01/12 U-238 2.67 +/- 0.13 2.76 1.93 -3.59 Pass STW-1964 02/01/12 Zn-65 0.01 +/- 0.20 0.00 0.00 - 1.00 Pass STW-5391 08/01/12 1-129 5.73 +/- 0.28 6.82 4.77 -8.87 Pass STSO-5392 08/01/12 Am-241 129.30 +/- 12.70 111.00 78.00 - 144.00 Pass STSO-5392 08/01/12 Ni-63 376.20 +/- 20.60 406.00 284.00 -528.00 Pass STSO-5392 08/01/12 Pu-238 118.70 +/- 9.30 105.80 74.10 - 137.50 Pass STSO-5392 08/01/12 Pu-239/40 140.70 +/- 9.90 134.00 94.00 - 174.00 Pass STSO-5392 08/01/12 Sr-90 483.52 +/- 16.47 508.00 356.00 - 660.00 Pass STSO-5392 08/01/12 Tc-99 432.50 +/- 23.10 469.00 328.00 - 610.00 Pass STSO-5394 08/01112 Co-57 1528.00 +/- 4.10 1316.00 921.00 - 1711.00 Pass STSO-5394 08/01/12 Co-60 592.00 +/- 3.20 531.00 372.00 - 690.00 Pass STSO-5394 08/01/12 Cs-134 933.60 +/- 5.82 939.00 657.00 - 1221.00 Pass STSO-5394 08/01/12 Cs-137 1319.80 +/- 5.50 1150.00 805.00 - 1495.00 Pass STSO-5394 08/01/12 K-40 737.30 +/- 17.70 632.00 442.00 - 822.00 Pass STSO-5394 08/01/12 Mn-54 1083.20 +/- 5.20 920.00 644.00 - 1196.00 Pass STSO-5394 08/01/12 U-233/4 55.80 +/- 4.20 60.30 42.20 - 78.40 Pass STSO-5394 08/01/12 U-238 231.20 +/- 8.60 263.00 184.00 -342.00 Pass STSO-5394 08/01/12 Zn-65 696.10 +/- 7.00 606.00 424.00 - 788.00 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 STVE-5395 0 08/01/12 Co-57 7.44 +/- 0.17 5.66 3.96 - 7.36 Fail STVE-5395 08/01/12 Co-60 5.90 +/- 0.15 5.12 3.58 - 6.66 Pass STVE-5395 08/01/12 Cs-134 7.40 +/- 0.31 6.51 4.56 - 8.46 Pass STVE-5395 08/01/12 Cs-137 5.45 +/- 0.18 4.38 3.07 - 5.69 Pass STVE-5395 08/01/12 Mn-54 4.06 +/- 0.21 3.27 2.29 - 4,25 Pass STAP-5398 08/01/12 Gr. Alpha 0.41 +/- 0.05 0.97 0.29 - 1.65 Pass STAP-5398 08101/12 Gr. Beta 2.11 +/- 0.09 1.92 0.96 -2.88 Pass STAP-5401 h 08/01/12 Am-241 0.12 +/- 0.02 0.08 0.05 -0.10 Fail STAP-5403 08/01/12 Co-57 1.96 +/- 0.05 1.91 1.34 - 2,48 Pass STAP-5403 08/01/12 Co-60 1.76 +/- 0.07 1.73 1.21 -2.25 Pass STAP-5403 08/01/12 Cs-134 2.74 +/- 0.18 2.74 1.92 - 3.56 Pass STAP-5403 08/01/12 Cs-137 0.00 +/- 0.03 0.00 -0.01 -0.01 Pass STAP-5403 08/01/12 Mn-54 2.52 +/- 0.10 2.36 1.65 -3.07 Pass STAP-5403 08/01/12 Pu-238 0.050 +/- 0.015 0,063 0.044 - 0.081 Pass STAP-5403 08/01/12 Pu-239/40 0.001 +/- 0.004 0.00081 0.000 - 0.010 Pass STAP-5403' 08/01/12 U-233/4 0.009 +/- 0.011 0.014 0.0.10 - 0.018 Fail STAP-5403 08/01/12 U-238 0.08 +/- 0.02 0.10 0,070 - 0.130 Pass STAP-5403 08/01/12 Zn-65 0.01 +/- 0.06 0.00 -0.010 - 0.010 Pass STW-5445 08/01/12 Fe-55 79.80 +/-4.10 89.30 62.50 - 116.10 Pass STW-5445 08/01/12 NI-63 74.30 +/- 3.40 66.30 46.40 - 86.20 Pass STW-5445 08/01/12 U-233/4 0.46 +/- 0.05 0.45 0.32 - 0,59 Pass STW-5445 08/01/12 U-238 3.14 +/- 0.14 3.33 2.33 - 4.33 Pass STW-5445 J 08/01/12 Am-241 0.64 +/- 0.04 1.06 0.74 - 1,38 Fail 8 Results are reported In units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

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

MAPEP results are presented as the known values and expected laboratory precision (1 sigma, 1 determination) and control limits as defined by the MAPEP. A known value of "zero" indicates an analysis was Included in the testing series as a "false positive". MAPEP does not provide control limits.

d Investigation was Inconclusive, there was not enough sample for reanalysis. ERA results (A-7) for the same matrix were acceptable.

e No errors found in calculation or procedure, original analysis result; 0.010 1 0.010 Bq/filter.

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

The efficiency factor was recalculated for the second round of MAPEP testing. Original analysis results 55.8 +/- 12.6 Bq/L.

g Result of reanalysis; 6.74 +/- 0.15 Bq/sample. Gamma emitters for the vegetation matrix exhibited a high bias, only Co-57 exceeded acceptance limits. Recounted using a geometry more closely matched to the MAPEP sample size.

h Result of reanalysis; 0.070 + 0.013 Bq/filter.

Result of reanalysis; 0.013 + 0.005 pCi/filter. A larger sample size was used to reduce the counting error.

Result of reanalysis 1.07 +/- 0.06 pCi/L. The analyses of the MAPEP sample matrix resulted In recovery factors greater than 100%.

A correction was made using recovery based on analysis of blank samples. A new tracer solution is on order, future samples for MAPEP testing will Include batch spike and blank samples.

A6-3

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

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result c Result d Limits Acceptance ERAP-1393 03/19/12 Co-60 917.5 +/- 7.0 880.0 681.0 -1100.0 Pass ERAP-1 393 03/19/12 Cs-134 586.6 +/- 7.4 656.0 417.0 - 814.0 Pass ERAP-1393 03/19/12 Cs-137 1255.9 +/- 9.4 1130.0 849.0 - 1480.0 Pass ERAP-1393 03/19/12 Mn-54 < 3.4 0.0 Pass ERAP-1393 03/19/12 Zn-65 1085.2 +/- 18.0 897.0 642.0 -1240.0 Pass ERAP-1394 03/19/12 Am-241 86.9 +/- 2.9 68.8 42.4 - 93.1 Pass ERAP-11394 03/19/12 Pu-238 70.2 +/- 3.6 63.2 43.3 -83.1 Pass ERAP-1394 03/19/12 Pu-239/40 66.0 +/- 1.0 63.0 45.6 - 82.4 Pass ERAP-1394 03/19/12 Sr-90 112.5 +/- 15.4 89.6 43.8 -134.0 Pass ERAP-1394 03/19/12 U-233/4 43.4 +/- 0.8 47.5 29.4 -71.6 Pass ERAP-1394 03/19/12 U-238 44.0 +/- 1.2 47.1 30.4 - 65.1 Pass ERAP-1394 03/19/12 Uranium 89.1 +/- 2.2 96.7 53.5 -147.0 Pass ERAP-1396 03/19/12 Gr. Alpha 81.1 +/- 1.5 77.8 26.1 -121.0 Pass ERAP-1396 03/19/12 Gr. Beta 68.4 +/- 0.7 52.5 33.2 -76.5 Pass ERSO-1397 03/19/12 Ac-228 1303.4 +/- 89.3 1570.0 1010.0 -2180.0 Pass ERSO-1397 03/19/12 Am-241 856.0 +/- 123.7 938.0 549.0 - 1220.0 Pass ERSO-1397 03/19/12 Bi-212 1379.2 +/- 247.2 1550.0 413.0 -2280.0 Pass ERSO-1397 03/19/12 Bi-214 965.2 +/- 38.4 1100.0 665.0 - 1590.0 Pass ERSO-1397 03/19/12 Co-60 3693.6 +/- 32.1 3500.0 2370.0 - 4820.0 Pass ERSO-1397 03/19/12 Cs-134 2257.3 +/- 45.4 2180.0 1420.0 - 2620.0 Pass ERSO-1397 03/19/12 Cs-137 9444.5 +/- 58.4 8770.0 6720.0 - 11300.0 Pass ERSO-1 397 03/19/12 K-40 11277.0 +/- 275.1 11600.0 8470.0 -15600.0 Pass ERSO-1397 03/19/12 Mn-54 < 21.0 0.0 Pass ERSO-1397 03/19/12 Pb-212 1208.4 +/- 26.3 1510.0 992.0 -2110.0 Pass ERSO-1 397 03/19/12 Pb-214 1041.6 +/- 46.9 1110.0 647.0 - 1650.0 Pass ERSO-1397 03/19/12 Pu-238 921.0 +/- 112.6 984.0 592.0 - 1360.0 Pass ERSO-1397 03/19/12 Pu-239/40 1028.0 +/- 112.6 879.0 575.0 - 1210.0 Pass ERSO-1397 03/19/12 Sr-90 8128.0 +/- 329.0 8800.0 3360.0 - 13900.0 Pass ERSO-1397 03/19/12 Th-234 2711.3 +/- 253.6 2000.0 632.0 - 3760.0 Pass ERSO-1397 03/19/12 U-233/4 1859.3 +/- 126.6 1960.0 1200.0 -2510.0 Pass ERSO-1397 03/19/12 U-238 2003.3 +/- 130.3 2000.0 1240.0 -2540.0 Pass ERSO-1397 03/19/12 Uranium 3939.5 +/- 283.8 4030.0 2190.0 -5320.0 Pass ERSO-1397 03/19/12 Zn-65 4200.4 +/- 65.9 3650.0 2910.0 - 4850.0 Pass A7-1

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

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result C Result a Limits Acceptance ERVE-1400 03/19/12 Am-241 4194.8 +/- 199,5 4540.0 2780.0 - 6040.0 Pass ERVE-1400 03119/12 Cm-244 1471.2 +/- 113.1 1590.0 779.0 - 2480.0 Pass ERVE-1400 03/19/12 Co-60 2347.8 +/- 47.9 2210.0 1520.0 - 3090.0 Pass ERVE-1400 03/19/12 Cs-134 2847.5 +/- 64.0 2920.0 1880.0 - 3790.0 Pass ERVE-1400 03/19/12 Cs-137 1503.5 +/- 52.5 1340.0 972.0 - 1860.0 Pass ERVE-1400 03/19/12 K-40 34105.7 +/- 745.3 28600.0 20700.0 - 40100.0 Pass ERVE-1400 03/19/12 Mn-54 < 26.8 0.0 - Pass ERVE-1400 03/19/12 Pu-238 2509.0 +/- 213.6 2350.0 1400.0 - 3220.0 Pass ERVE-1400 03/19/12 Pu-239/40 2690.4 +/- 208.9 2570.0 1580.0 - 3540.0 Pass ERVE-1400 03/19/12 Sr-90 7881.5 +/- 470.8 8520.0 4860.0 - 11300.0 Pass ERVE-1400 03/19/12 U-233/4 3149.6 +/- 165.2 3610.0 2370.0 - 4640.0 Pass ERVE-1400 03/19/12 U-238 3203.6 +/- 166.5 3580.0 2390.0 - 4550.0 Pass ERVE-1400 03119112 Uranium 6463.7 +/- 363.2 7350.0 4980.0 - 9150.0 Pass ERVE-1400 03/19/12 Zn-65 2701.9 +/- 105.5 2310.0 1670.0 -3240.0 Pass ERW-1403 03/19/12 Am-241 119.9 +/- 3.2 135.0 91.0 - 181.0 Pass ERW-1403 03/19/12 Fe-55 713.7 +/- 127.4 863.0 514.0 - 1170.0 Pass ERW-1403 03/19/12 Pu-238 131.9 +/- 6.4 135.0 99.9 - 168.0 Pass ERW-1403 03/19/12 Pu-239/40 108.9 +/- 10.2 112.0 86.9 - 141.0 Pass ERW-1403 03/19/12 U-233/4 93.1 +/- 7.9 105.0 78.9 - 135.0 Pass ERW-1403 03/19/12 U-238 96.9 +/- 5.5 104.0 79.3 - 128.0 Pass ERW-1403 03/19/12 Uranium 190.0 +/- 13.8 214.0 157.0 - 277.0 Pass ERW-1405 03/19/12 Co-60 858.7 +/- 5.6 875.0 760.0 - 1020.0 Pass ERW-1405 03/19/12 Cs-1 34 560.4 +/- 4.4 609.0 447.0 - 700.0 Pass ERW-1405 03/19/12 Cs-137 1239.9 +/- 7.4 1250.0 1060.0 - 1500.0 Pass ERW-1405 03/19/12 Mn-54 < 7.4 0.0 - Pass ERW-1405 03/19/12 Sr-90 944.3 +/- 26.2 989.0 644.0 - 1310.0 Pass ERW-1405 03/19/12 Zn-65 786.9 +/- 20.6 749.0 624.0 - 945.0 Pass ERW-1406 03/19/12 Gr. Alpha 85.9 +/- 3.0 103.0 36.6 - 160.0 Pass ERW-1406 03/19/12 Gr. Beta 45.7 +/- 1.6 43.7 25.0 -64.7 Pass ERW-1409 03/19/12 H-3 9045.0 +/- 284.0 9150.0 6130.0 - 13000.0 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: STW (water), STAP (air filter), STSO (soil), STVE (vegetation). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCi/kg).

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

d Results are presented as the known values, expected laboratory precision (1 sigma, 1 determination) and control limits as provided by ERA. A known value of "zero" indicates an analysis was included in the testing series as a "false positive". Control limits are not provided.

A7-2