NRC 2015-0024, 2014 Annual Monitoring Report for the Period January 1 Through December 31, 2014

2014 Annual Monitoring Report for the Period January 1 Through December 31, 2014

ML15124A756
Person / Time
Site:	Point Beach
Issue date:	04/29/2015
From:	Millen M Point Beach
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC 2015-0024
Download: ML15124A756 (196)

Text

NExTerao ENERGYM/4 BEACH April 29, 2015 NRC 2015-0024 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 2014 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, 2014.

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, the groundwater protection program, and miscellaneous monitoring activities which occurred in 2014. 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. The contracted laboratory's final Radiological Environmental Monitoring Program results (Appendix 1) and the 2014 revised Environmental Manual (Appendix 2) are included.

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

Very truly yours, NextEra Energy Point Beach, LLC Michael Millen Licensing Manager Enclosures cc: Administrator, Region III, 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 I, NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241

ENCLOSURE1 ANNUAL MONITORING REPORT 2014 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT DOCKETS 50-266 (UNIT 1), 50-301 (UNIT 2),72-005 (ISFSI)

Ir:M:Wr:: I IC(' Qc nI: DD.-9A anAl 'DD-_"7 January 1, 2014 through December 31, 2014

ENCLOSURE1 January 1, 2014 through December 31, 2014 TABLE OF CONTENTS Summary 1 Part A: Effluent Monitoring 1.0 Introduction 3 2.0 Radioactive Liquid Releases 4 3.0 Radioactive Airborne Releases 10 4.0 Radioactive Solid Waste Shipments 17 5.0 Nonradioactive Chemical Releases 19 6.0 Circulating Water System Operation 20 Part B: Miscellaneous Reporting Requirements 7.0 Additional Reporting Requirements 21 Part C: Radiological Environmental Monitoring 8.0 Introduction 22 9.0 Program Description 23 10.0 Results 34 11.0 Discussion 39 12.0 REMP Conclusion 50 Part D: Groundwater Monitoring 13.0 Program Description 51 14.0 Results and Discussion 54 15.0 Groundwater Summary 60 Appendix 1: Environmental, Inc. Midwest Laboratory, "Final Report for Point Beach Nuclear Plant" 61 Appendix 2: Environmental Manual, Revision 25 62

LIST OF TABLES Table 2-1 Comparison of 2014 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives 4 Table 2-2 Summary of Circulating Water Discharge 6 Table 2-3 Isotopic Composition of Circulating Water Discharges 7 Table 2-4 Subsoil System Drains - Tritium Summary 8 Table 3-1 Comparison of 2014 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 2014 17 Table 4-2 2014 PBNP Radioactive Waste Shipments 17 Table 4-3 2014 Estimated Solid Waste Major Radionuclide Composition 18 Table 6-1 Circulating Water System Operation for 2014 20 Table 9-1 PBNP REMP Sample Analysis and Frequency 25 Table 9-2 PBNP REMP Sampling Locations 26 Table 9-3 ISFSI Sampling Sites 30 Table 9-4 Minimum Acceptable Sample Size 30 Table 9-5 Deviations from Scheduled Sampling and Frequency During 2014 31 Table 9-6 Sample Collection for the State of Wisconsin 31 Table 10-1 Summary of Radiological Environmental Monitoring Results for 2014 36 Table 10-2 ISFSI Fence TLD Results for 2014 38 Table 11-1 Average Indicator TLD Results from 1993-2014 39 Table 11-2 Average ISFSI Fence TLD Results (mR/7days) 40 Table 11-3 Average TLD Results Surrounding the ISFSI (mR/7days) 41 Table 11-4 Average Gross Beta Measurements in Air 44 Table 14-1 Intermittent Streams and Bogs 54 Table 14-2 2014 Beach Drain Tritium 55 Table 14-3 2014 East Yard Area Manhole Tritium (pCi/L) 56 Table 14-4 2014 Fagade Well Water Tritium (pCi/L) 57 Table 14-5 2014 Unit 2 Fagade SSD Sump H-3 (pCi/L) 57 Table 14-6 2014 Quarterly Monitoring Well Tritium (pCi/L) 58 Table 14-7 2014 Potable Well Water Tritium Concentration (pCi/L) 59 Table 14-8 Comparison of 2012 - 2014 AC Condensate 59 LIST OF FIGURES Figure 9-1 PBNP REMP Sampling Sites 27 Figure 9-2 Map of REMP Sampling Sites Located Around PBNP 28 Figure 9-3 Enhanced Map Showing REMP Sampling Sites Closest to PBNP 29 Figure 11-1 ISFSI Area TLD Results (1995- 2014) 41 Figure 11-2 Comparison of ISFSI Fence TLDs to Selected REMP TLDs 42 Figure 11-3 Sr-90 Concentration in Milk (1997- 2014) 43 Figure 11-4 2014 Airborne Gross Beta (pCi/m 3) vs. Time 44 Figure 13-1 Groundwater Monitoring Locations 53 ii

SUMMARY

The Annual Monitoring Report for the period from January 1, 2014, through December 31, 2014, 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 2014, the following Curies (Ci) of radioactive material were released via the liquid and atmospheric pathways:

Liquid Atmospheric Tritium (Ci) 796 75.5 1 Particulate (Ci) 0.0642 0.000066 Noble Gas (Ci) 0- 1.44 C-142 0.0115 11.86

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

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

2Liquid is measured, atmospheric is calculated.

For the purpose of compliance with the effluent design objectives of Appendix I to 10 CFR 50, 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 millirad (mrad) are shown below and compared to the corresponding design objectives of 10 CFR 50, Appendix I.

LIQUID RELEASES Dose Cateqory Calculated Dose Appendix I Dose Whole body dose 0.00738 mrem 6 mrem Organ dose 0.00809 mrem 20 mrem ATMOSPHERIC RELEASES Dose Category Calculated Dose Appendix I Dose Particulate organ dose 0.0297 mrem 30 mrem Noble gas beta air dose 0.000130' mrad 40 mrad Noble gas gamma ray air dose 0.000250 mrad 20 mrad Noble gas dose to the skin 0.000361 mrem 30 mrem Noble gas dose to the whole body 0.000236 mrem 10 mrem 1

The results show that during 2014, the doses from PBNP effluents were a small percentage

(<0.10%) of the Appendix I design objectives. Therefore, operation of the PBNP radwaste treatment system 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 remaining ten land containing sectors identified the closest garden, occupied dwelling, and dairy in each sector. The LUC results confirm the assumption that, for the purpose of calculating effluent doses, the maximally exposed person lives at the south boundary remains conservative.

The 2014 Radiological Environmental Monitoring Program (REMP) collected 778 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 818 samples. The ambient radiation measures in the vicinity of PBNP and the ISFSI was conducted using 152 sets of thermoluminescent dosimeters (TLDs).

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

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

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

No new dry storage units added to the ISFSI in 2014. The total number remains at 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 2014 confirmed that the effluent control program at PBNP ensured a minimal impact on the environment.

One-hundred-fifty-nine (159) samples were analyzed for 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 associated with the subsurface drainage system (SSD) located under the plant foundation, four groundwater containment integrity monitoring wells located in the facades, and AC condensate samples. The results show no substantial change in H-3 from previous years.

Low levels of tritium continue 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. Gamma scans of samples originating within the power block found no plant related gamma emitters.

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

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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 PBNP 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.

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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 MEl 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 2014 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives inual Limit [mrem] Highest Total Calculated Dose  % of Design

[mrem] Objective 6 (whole body) 0.00738 0.123 %

20 (any organ) 0.00809 0.0404%

2.2 2014 Circulatinq 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 semi-annual and annual totals (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 2014 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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In 2014, the discharged volume of processed waste (Table 2-2) increased about 40% (6.08E+05 to 8.76E+05 gallons) from 2013. In addition to the increase in volume, the total isotopic curie distribution (gamma emitters plus hard-to-detects other that strontium) of 6.42E-02 Ci approximately doubled from the 2.99E-02 Ci in 2013. Similar increases were seen in Sn-1 13/117m (from 1.51 E-03 to 3.11 E-03 Ci) and in Sb-122/124/125 (from 2.23E-05 to 3.48E-03 Ci). The largest increases occurred in Co-58/60 (from 2.32E-03 Ci in 2013 to 2.82E-02 Ci in 2014) and in C-14 (from 1.22E-03 to 1.15E-02 Ci in 2014). The 2014 C-14 value is similar to the 1.43E-02 Ci observed in 2012. The monthly totals were higher in months impacted by outages. As in 2013, no Sr-89 or Sr-90 was detected in liquids during 2014. H-3 increased from 737 Ci in 2013 to 796 Ci which is slightly below the 2012 amount of 829 Ci. 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 drains a small portion of the grassy area on top of the bluff overlooking the lake. The quarterly results from the monthly beach drain samples 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. In 2014, no tritium was observed at the effluent LLDs. No H-3 found in the beach drains is included in the effluent totals unless it can be shown to be the result of a spill or similar event. Because the source of beach drain H-3 has been determined to be recapture, 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 is emptied into the yard drains. [See Sections 14.2 and 14.6 for further discussion.]

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 may be groundwater in leakage. This is evidenced by flow during periods of no precipitation.

Because there are no external storage tanks or piping that carries radioactive liquids, the main source of radioactivity for this system is recapture/washout of airborne H-3 discharges via the yard drain system. Because of these various recapture sources, the beach drains also are sampled as part of the groundwater 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, 2014 through December 31, 2014 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(+HTIUs) ' 3.43E-04 2.42E-03 4.38E-03 1.84E-02 8.62E-03 2.48E-03 3.66E-02 2.12E-04 1. 19E-03 1.72E-03 1.35E-02 8.72E-03 2.24E-03 6.42E-02 Gross Alpha 0.OOE+00 0.OOE+00 0.OOE+00 0,OOE+00 0.OOE+00 0,OOE+00 O0OOE+00 0,OOE+00 0,OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Tritium 9.54E+01 4.54E+01 1.43E+02 2.96E+01 1.29E+02 6.41 E+01 5.06E+02 8.51 E+00 5.92E+01 1.58E+02 3.13E+01 1.66E+01 1.56E+01 7.96E+02 Strontium (89190/92) 0.OOE+00 0.00E+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 0.OOE+00 0.OOE+00 0.OOE+00 Total Vol Released (gal)

Processed Waste 4.85E+04 3.85E+04 1.58E+05 1.06E+05 7.05E+04 2.84E+04 4.50E+05 2.55E+04 4.76E+04 9.42E+04 1.53E+05 8.26E+04 2.33E+04 8.76E+05 Waste Water Effluent' 1.29E+07 2.53E+06 2.78E+06 3.45E+06 2.87E+06 2.69E+06 2.72E+07 2.57E+06 2.47E+06 2.62E+06 3.28E+06 3.17E+06 3.16E+06 4.45E+07 U1 SG Blowdown 2.62E+06 2.36E+06 3.OOE+06 2.43E+06 3.07E+06 2.58E+06 1.61E+07 2.52E+06 2.58E+06 1.73E+06 3.95E+05 3.59E+06 3.35E+06 3.02E+07 U2 SG Blowdown 1.76E+06 1.59E+06 9.69E+05 2.47E+06 3.19E+06 2.27E+06 1.22E+07 1.77E+06 2.03E+06 1.72E+06 1.78E+06 1.73E+06 1.78E+06 2.31 E+07 Total Gallons 1.73E+07 6.52E+06 6.91E+06 8.46E+06 9.19E+06 7.57E+06 5.60E+07 6.88E+06 7.12E+06 6.17E+06 5.61E+06 8.58E+06 8.31E+06 9.86E+07 Totalcc 6.56E+10 2.47E+10 2.61E+10 3.20E+10 3.48E+10 2.86E+10 2.12E+11 2.60E+10 2.70E+10 2.33E+10 2.12E+10 3.25E+10 3.15E+10 3.73E+11 Dilution vol(cc)" 8.18E+13 7.39E+13 6.47E+13 8.88E+13 1.26E+14 1.22E+14 5.57E+14 1.26E+14 1.25E+14 1.22E+14 7.92E+13 1.22E+14 1.01E+14 1.23E+15 Avg diluted discharge conc (pCi/cc)

Gamma Scan (+HTDs)' 4.19E-12 3.27E-11 6.76E-11 2.07E-10 6.84E-11 2.04E-11 1.69E-12 9.54E-12 1.42E-11 1.70E-10 7.17E-11 2.21E-11 Gross Alpha 0.OOE+00 0.OOE+00 0.OOE+00 0,OOE+00 0OOE+00 0.OOE+00 0,OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Tritium 1.17E-06 6.15E-07 2.21E-06 2.15E-07 1.02E-06 5.27E-07 6.77E-08 4.75E-07 1.30E-06 3.95E-07 1.37E-07 1.54E-07 Strontium (89/90/92) 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 Max Batch Discharge Conc (pCi/cc)

Tritium 3.60E-05 2.89E-05 2.85E-05 7.82E-06 4.07E-05 4.55E-05 5.66E-06 3.31E-05 4.20E-05 1. 12E-05 4.O0E-06 9.85E-06 Gamma Scan 6.95E-1 1.24E-10 1.24E-08 1.28E-08 2.78E-09 1.03E-09 2.71E-11 3.62E-10 9.25E-10 5.43E-09 4.75E-09 1.44E-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 6

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

January, 2014 through December 31, 2014 Total Total Nuclide Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Jan-Dec H-3 9.54E+01 4.54E+01 1.43E+02 2.96E+01 1.29E+02 6.41E+01 5.06E+02 8.51E+00 5.92E+01. 1.58E+02 3.13E+01 1.66E+01 1.56E+01 7.96E+02 C-14 O.OOE+00 2.04E-03 2.80E-03 O.OOE+00 1.52E-04 8.72E-04 5.86E-03 O.OOE+00 4.32E-04 1.93E-04 4.86E-03 9.69E-05 1.58E-05 1.15E-02 F-18 2.18E-04 1.88E-04 2.88E-04 2.56E-04 O.OOE+00 2.20E-04 1.17E-03 1.86E-04 2.88E-04 9.39E-05 2.83E-04 4.87E-04 5.84E-04 3.09E-03 Cr-51 O.OOE+00 O.OOE+00 1.46E-05 5.19E-03 1.68E-03 1.54E-04 7.04E-03 O.OOE+00 7.61E-06 O.OOE+00 3.73E-04 4.01E-04 O.OOE+00 7.82E-03 Mn-54 O.OOE+00 O.OOE+00 O.OOE+00 2.44E-04 1.53E-04 2.58E-05 4.23E-04 O.OOE+00 1.52E-05 4.09E-05 1.46E-04 8.87E-05 O.OOE+00 7.14E-04 Fe-55 O.OOE+00 O.OOE+00 O.OOE+00 4.80E-04 3.20E-04 O.OOE+00 8.OOE-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 8.OOE-04 Fe-59 O.OOE+00 O.OOE+00 O.OOE+00 8.80E-05 2.22E-05 O.OOE+00 1.1OE-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.1OE-04 Co-57 O.OOE+00 O.OOE+00 O.OOE+00 1.44E-05 4.85E-06 O.OOE+00 1.92E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.92E-05 Co-58 4.60E-06 4.38E-06 2.45E-05 2.26E-03 1.22E-03 2.12E-04 3.73E-03 3.28E-06 6.37E-05 9.42E-05 3.17E-03 4.78E-03 1.25E-03 1.31E-02 Co-60 3.36E-05 2.21E-05 1.30E-04 4.55E-03 2.90E-03 5.19E-04 8.16E-03 2.21E-05 2.02E-04 9.39E-04 3.55E-03 2.OOE-03 1.84E-04 1.51E-02 Ni-63 O.OOE+00 5.80E-05 1.19E-04 8.OOE-05 9.33E-05 5.17E-05 4.02E-04 O.OOE+00 3.42E-05 O.OOE+00 O.OOE+00 1.47E-04 6.51E-05 6.48E-04 Zn-65 O.OOE+00 O.OOE+00 O.OOE+00 1.24E-04 8.49E-05 O.OOE+00 2.09E-04 O.OOE+00 O.OOE+00 6.54E-06 O.OOE+00 O.OOE+00 O.OOE+00 2.15E-04 As-76 O.OOE+00 O.OOE+00 2.15E-04 O.OOE+00 O.OOE+00 O.OOE+00 2.15E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.60E-05 O.OOE+00 2.31E-04 Sr-90 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 O.OOE+00 O.OOE+00 Nb-95 O.OOE+00 O.OOE+00 O.OOE+00 1.27E-03 6.56E-04 1.04E-04 2.03E-03 O.OOE+00 3.47E-05 7.22E-05 2.57E-04 1.93E-04 9.26E-06 2.60E-03 Nb-97 O.OOE+00 O.OOE+00 9.47E-06 O.OOE+00 O.OOE+00 O.OOE+00 9.47E-06 O.OOE+00 4.45E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.39E-05 Zr-95 O.OOE+00 O.OOE+00 O.OOE+00 7.23E-04 3.63E-04 5.57E-05 1.14E-03 O.OOE+00 1.37E-05 1.47E-05 1.23E-04 1.02E-04 O.OOE+00 1.40E-03 Tc-99 1.19E-05 1.30E-05 2.21E-05 O.OOE+00 1.20E-05 1.51E-05 7.41E-05 O.OOE+00 7.20E-06 1.46E-05 9.26E-06 O.OOE+00 1.85E-06 1.07E-04 Ag-110m O.OOE+00 O.OOE+00 O.OOE+00 1.93E-04 4.26E-05 5.55E-06 2.41E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.41E-04 Sn-113 O.OOE+00 O.OOE+00 O.OOE+00 8.20E-05 1.44E-05 O.OOE+00 9.64E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 9.64E-05 Sn-117m 2.71E-05 5.82E-06 4.36E-06 5.82E-04 6.82E-04 2.32E-04 1.53E-03 O.OOE+00 7.31E-05 2.49E-04 6.74E-04 4.05E-04 7.1OE-05 3.01E-03 Sb-122 O.OOE+00 O.OOE+00 7.21E-06 O.OOE+00 O.OOE+00 O.OOE+00 7.21E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 7.21E-06 Sb-124 O.OOE+00 1.87E-08 7.51E-06 1.07E-04 3.33E-05 O.OOE+00 1.48E-04 O.OOE+00 O.OOE+00 O.OOE+00 1.01E-05 O.OOE+00 4.33E-05 2.01E-04 Sb-125 3.80E-05 1.39E-04 7.26E-04 2.14E-03 1.84E-04 1.42E-05 3.24E-03 O.OOE+00 1.23E-05 5.09E-06 O.OOE+00 O.OOE+00 6.53E-06 3.27E-03 1-131 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 Te-132 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 Cs-137 9.51E-06 2.95E-06 1.91E-06 O.OOE+00 4.17E-06 1.51E-06 2.01E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.01E-05 Ba-140 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 La-140 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 Ce-141 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 dissolved noble gases detected in liquid effluents (e.g., Xe-1 33, Xe-1 35, etc.) are added to the atmospheric release summaries. "-" = no analysis 7

Table 2-4 Subsoil System Drains - Tritium Summary January 1, 2014, through December 31, 2014 S-1 S-3 S-7 S-8 S-9 S-10 S-11 1 st Qtr H-3 (Ci) O.OOE+O0 O.OOE+O0 O.OOE+0O O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 Flow (gal) O.OOE+O0 O.OOE+O0 O.OOE+00 O.OOE+O0 O.OOE+O0 O.OOE+O0 O.OOE+O0 2nd Qtr H-3 (Ci) O.OOE+00 O.OOE+00 0.OOE+0 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 Flow (gal) 1.75E+06 3.05E+05 0.OOE+0O 0.OOE+00 O.OOE+00 O.OOE+00 8.86E+04 3rd Qtr H-3 (Ci) O.OOE+00 O.OOE+00 0.OOE+0 0.OOE+00 O.OOE+0O 0.OOE+00 O.OOE+00 Flow (gal) 9.71 E+05 2.20E+05 0.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4th Qtr H-3 (Ci) O.OOE+00 O.OOE+00 0.OOE+0O 0.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Flow (gal) 5.17E+05 1.55E+05 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 4.46E+04 2.6 Land Application of Sewage Sludge and Wastewater In 1988, pursuant to 10 CFR 20.302(a), Point Beach received approval for the disposal of sewage sludge, which may contain trace amounts of radionuclides, by land application on acreage within the site.. Land application of sewage sludge is regulated by the Wisconsin Department of Natural Resources. Point Beach has not land applied sewage sludge for over a decade. Therefore, Point Beach has not renewed its WI DNR permit to dispose of sewage sludge in this manner.

There were no sludge disposals by land application during 2014. All disposals were done at the Manitowoc Sewage Treatment Plant. In February an effluent pump failed resulting in flooding of a holding pit and an adjacent underground vault associated with the PBNP sewage treatment plant. (Some ground water inleakage also may reach the vault.) The flows to the pit and the vault were secured. From February 13 - 16, roughly 75,000 gallons were sent to the Manitowoc POTW for disposal. This is the same facility where the PBNP sewage sludge is sent.

All of the shipments were analyzed using the LLDs applied to REMP lake water samples. Traces of Fe-59, Co-60, Zn-65, and Cs-1 37 showed up on gamma scans.

All were below the calculated MDC and therefore concluded to be false positives. By contrast, K-40 (129.5 +/- 20.7 to 270.9 +/- 27.1 pCi/I) and Ra-226 (64.15 +/- 51.3 to 205.2 +/-

32.8 pCi/I) were higher than the typical concentrations (<100) seen in PBNP digester sludge.

The calculated amount of H-3 in the wastewater sent to the Manitowoc POTW was 2.14E-04 Ci. Assuming all of the liquid were at the maximum detected concentration of 1019 pCi/I and discharged in one day, the resulting discharge concentration would have been about 5 pCi/I prior to dilution in Lake Michigan. This is well below the drinking water standard of 20,000 pCi/I.

8

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 Point Beach began evaluating C-14 liquid discharges in 2009, prior to the issuance of Regulatory Guide 1.21 [RG 1.21], Rev 2 in June of 2009. Point Beach 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 information received at the industry sponsored RETS-REMP Workshops, Point Beach 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. For 2014, the monthly and total C-14 (1.15E-02 Ci) 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.

9

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 maximum exposed individual (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 Appendix I calculations do not include the C-14 contribution because it is not an Appendix I radionuclide. The C-14 dose calculation has been required since 2010 (see Sections 3.4 through 3.6, below, for a more detailed description) and is treated separately. The comparison between airborne effluent doses with and without C-14 is shown in Table 3-4. The highest Appendix I dose is the child age group for the liver, thyroid, kidney, lung, and GI-LLI at 2.97E-02 mrem. Had C-14 been included, the child-bone dose would have been the highest at 2.44E-01 mrem. 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 2014 is summarized in Table 3-2.

The increases in the total amount of particulates increased from 7.91 E-06 Ci in 2013 to 6.60E-05 Ci in 2014. This is attributable to the two outages in 2014.

Similarly, H-3 increased from 64.1 to 75.5 Ci. The impact of the 2014 fall outage is demonstrated by no particulates being discharged in October 2013, non-outage, compared to 4.63E-05 Ci in October 2014, outage month. Similarly, the October H-3 increased from 4.44 Ci in 2013 to 7.94 Ci in 2014.

3.3 Isotopic Airborne Releases The monthly isotopic airborne releases for 2014, from which the airborne doses were calculated, are presented in Table 3-3. Carbon-14 is not included in Table 3-3 because it was calculated and not measured. C-14 is discussed in the following sections.

The outage impact of the isotopic mixture is demonstrated again in the comparison of the October 2013 and 2014 particulate releases. The difference is in that the particulates are released via the open hatch on the 66-foot elevation of containment. The convective flow through the open hatch during purge is unfiltered. Although the flow is into the fagade, there are two circumferential 10

gaps around the facgade. It is assumed that the release into the fagade is transferred to the outside and therefore is treated as a release to the environment. Of the total 4.63E-05 Ci of particulates released in October 2014, 4.59E-05 Ci were via the hatch at the 66-foot elevation.

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 (Regulatory Guide 1.21, Rev 2, p. 16, June 2009),

most of the C-14 emissions from nuclear plant occur in the gaseous phase.

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." In addition to neutron flux, the percent oxygen and nitrogen in the CVTs is used in the C-14 calculation as both gases contribute to the generation of C-14.

The Point Beach C-14 generation for 2014 was calculated using the EPRI guidance and the new core parameters resulting from the power uprate. The calculated amounts were 5.98 Ci for Unit 1 and 5.89 Ci for Unit 2 yielding a total of 11.86 Ci which is 0.12 Ci higher than 2013. It is noted that the nitrogen in the CVTs also was higher in 2014 than in 2013. The calculated total 11.86 Ci is roughly 1000 times higher than the 1.1 5E-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, CH 4 ,

are not photosynthetically active. For PWRs such as PBNP most of the gaseous C-14 occurs as methane, 14CH 4 , not as carbon dioxide, 14CO20 11

The amount of 14C02 present in the PBNP airborne effluent is 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 11.86 Ci of the calculated C-14 for PBNP will be used in the ingestion dose calculations.

C-14 dose calculations were made using the dose factors and the methodology of Regulatory Guide 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 4 , both would be 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 photosynthesis. Photosynthesis only incorporates 14C02 and hence the use only of 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 Regulatory Guide 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.

Carbon-14 is not an Appendix I radionuclide. Therefore, airborne C-14 is not summed with the other airborne radioactive effluents for comparison of airborne effluent dose to the Appendix I dose objectives. However, the C-14 doses are presented and compared to the other radionuclide doses in Table 3-4.

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 (2013 AMR, Table 10-3). These results 12

demonstrated that the dose from C-14 in Point Beach 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).

13

Table 3-1 Comparison of 2014 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 0.0297 mrem 0.099 Noble gas 40 mrad (beta air) 0.000131 mrad 0.000326 Noble gas 20 mrad (gamma air) 0.000250 mrad 0.00125 Noble gas 30 mrem (skin) 0.000361 mrem 0.00120 Noble gas 10 mrem (whole body) 0.000236 mrem 0.00236 Table 3-2 Radioactive Airborne Effluent Release Summary January 1, 2014, through December 31, 2014 Total Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec Total Total NG from Liq (Ci) 1.63E-02 6.33E-03 2.53E-02 7.37E-04 3.04E-03 3.38E-03 5.50E-02 O.OOE+00 3.16E-03 9.68E-03 1.63E-03 1.19E-03 1.47E-03 7.22E-02 Total Noble Gas (Ci)l 4.99E-01 1.24E-01 2.86E-01 7.50E-02 5.20E-02 5.73E-02 1.09E+00 6.03E-02 6.97E-02 6.63E-02 4.94E-02 5.77E-02 4.65E-02 1.44E+00 Total Radioiodines (Ci)2 O.OOE+00 O.OOE+00 7.67E-06 0.00E+00 O.OOE+00 O.OOE+00 7.67E-06 O.OOE+00 O.OOE+00 O.OOE+00 1.06E-07 O.OOE+00 O.OOE+00 7.77E-06 Total Particulate (Ci) 3 2.07E-06 2.64E-09 6.62E-06 7.10E-06 5.08E-09 4.71E-09 1.58E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.63E-05 3.86E-06 1.39E-10 6.60E-05 Alpha (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 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) 2.07E-06 2.64E-09 6.62E-06 7.10E-06 5.08E-09 4.71E-09 1.58E-05 O.OOE+00 O.OOE+00 O.OOE+00 4.63E-05 3.86E-06 1.39E-10 6.60E-05 Total Tritium (Ci) 6.21E+00 5.69E+00 1.15E+01 8.03E+00 7.05E+00 4.50E+00 4.29E+01 3.99E+00 4.23E+00 5.27E+00 7.44E+00 5.46E+00 6.15E+00 7.55E+01 Max NG H'rly Rel.(Ci/sec) 1.80E-06 4.85E-08 3.25E-06 6.99E-07 5.52E-08 6.10E-08 I 6.57E-08 5.88E-08 6.73E-08 6.56E-08 6.87E-08 6.22E-08 1 Total noble gas (airborne + liquid releases) does not include F-18 which is not a noble gas. F-18 monthly and annual totals are presented in Table 3-3..

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.

3 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, 2014 through December 31, 2014 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 6.21E+00 5.69E+00 1.15E+01 8.03E+00 7.05E+00 4.50E+00 4.29E+01 3.99E+00 4.23E+00 5.27E+00 7.44E+00 5.46E+00 6.15E+00 7.55E+01 Ar-41 6.09E-02 5.71E-02 3.45E-02 2.78E-02 4.31E-02 4.58E-02 2.69E-01 5.01 E-02 4.93E-02 4.93E-02 2.67E-02 4.46E-02 3.51E-02 5.24E-01 Kr-85 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 Kr-85m 1.13E-04 0.OOE+00 3.56E-04 7.40E-05 0.OOE+00 0.OOE+00 5.43E-04 0.OOE+00 0.OOE+00 0.OOE+0O 0.OOE+00 0.OOE+00 0.OOE+00 5.43E-04 Kr-87 1.90E-07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.90E-07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.90E-07 Kr-88 4.40E-05 0.OOE+00 1.42E-04 4.50E-05 0.OOE+00 0.OOE+00 2.31E-04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.31E-04 Xe-131m 0.OOE+00 4.13E-04 5.29E-04 0.OOE+00 0.OOE+00 0.OOE+00 9.42E-04 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 9.42E-04 Xe-133 4.27E-01 6.47E-02 2.24E-01 4.40E-02 8.93E-03 1.14E-02 7.80E-01 1.02E-02 2.03E-02 1.67E-02 2.27E-02 1.28E-02 1.13E-02 8.74E-01 Xe-133m 2.21E-03 1.02E-03 4.06E-03 4.81E-04 0.OOE+00 2.83E-05 7.80E-03 0.OOE+00 0.OOE+00 7.25E-05 4.60E-06 0.OOE+00 0.OOE+00 7.88E-03 Xe-135 8.41E-03 1.22E-03 2.26E-02 2.62E-03 5.61E-06 6.25E-05 3.49E-02 0.OOE+00 2.54E-05 2.05E-04 1.24E-05 3.06E-04 2.38E-05 3.55E-02 Xe-1 35m 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 Xe-1 38 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 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 F-18 3.36E-06 0.OOE+00 0.OOE+00 0.OOE+00 6.15E-06 0.OOE+00 9.51E-06 2.OOE-06 0.OOE+00 0.OOE+00 0.OOE+00 3.86E-06 3.24E-06 1.86E-05 Cr-51 0.OOE+00 0.OOE+00 1.43E-06 5.55E-07 0.OOE+00 0.OOE+00 1.99E-06 0.OOE+00 0.OOE+00 0.OOE+00 1.37E-06 0.OOE+00 0.OOE+00 3.35E-06 Mn-54 0.OOE+00 0.OOE+00 1.09E-07 1.95E-07 0.OOE+00 0.OOE+00 3.04E-07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 3.04E-07 Co-58 0.OOE+00 0.OOE+00 4.76E-07 1.16E-06 0.OOE+00 0.OOE+00 1.63E-06 0.OOE+00 0.OOE+00 0.OOE+00 3.48E-05 0.OOE+00 0.OOE+00 3.65E-05 Co-60 0.OOE+00 0.OOE+00 2.20E-06 2.34E-06 0.OOE+00 0.OOE+00 4.54E-06 0.OOE+00 0.OOE+00 0.OOE+00 3.92E-07 0.OOE+00 0.OOE+00 4.94E-06 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 0.OOE+00 0.OOE+00 0.OOE+00 Nb-95 0.OOE+00 0.OOE+00 5.36E-07 6.44E-07 0.OOE+00 0.OOE+00 1.18E-06 0.OOE+00 0.OOE+00 0.OOE+00 1.57E-06 0.OOE+00 0.OOE+00 2.75E-06 Zr-95 0.OOE+00 0.OOE+0O 2.03E-07 3.69E-07 0.OOE+00 O.OOE+00 5.72E-07 0.OOE+00 0.OOE+00 0.OOE+00 7.98E-07 0.OOE+00 0.OOE+00 1.37E-06 1-131 0.OOE+00 0.OOE+00 5.85E-08 0.OOE+00 0.OOE+00 0.OOE+00 5.85E-08 0.OOE+00 0.OOE+00 0.OOE+00 1.06E-07 0.OOE+00 0.OOE+00 1.64E-07 1-132 0.OOE+00 0.OOE+00 7.61E-06 0.OOE+00 0.OOE+00 0.OOE+00 7.61E-06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 7.61E-06 1-133 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 Sb-124 0.OOE+00 0.OOE+00 0.OOE+00 2.25E-07 0.OOE+00 0.OOE+00 2.25E-07 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 2.25E-07 Sb-125 0.OOE+00 0.OOE+00 1.49E-07 9.40E-08 0.OOE+00 0.OOE+00 2.43E-07 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 2.43E-07 Cs-137 0.OOE+00 0.OOE+00 1.12E-08 2.75E-09 0.OOE+00 0.OOE+00 1.39E-08 0.OOE+00 0.OOE+00 0.OOE+00 1.85E-08 0.OOE+00 0.OOE+00 3.24E-08 Fe-55 2.03E-09 1.98E-09 8.76E-07 6.83E-07 3.63E-09 3.36E-09 1.57E-06 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.57E-06 Ni-63 6.76E-10 6.61E-10 5.84E-07 2.73E-07 1.45E-09 1.35E-09 8.61E-07 0.OOE+00 0.OOE+00 0.OOE+00 7.33E-06 2.36E-10 1.39E-10 8.20E-06 Tc-99 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 O.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 Sr-89 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 Sr-90 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 0.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 Sn-113 0.OOE+00 0.OOE+00 3.50E-08 0.OOE+00 0.OOE+00 O.OOE+00 3.50E-08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 3.50E-08 Sn-117m 0.OOE+00 0.OOE+00 1.58E-08 0.OOE+00 0.OOE+00 0.OOE+00 1.58E-08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 1.58E-08 Note: The Noble Gases listed above include the liquid contribution 15

Table 3-4 Comparison of Airborne Effluent Doses (Appendix I and C-14) 2014 Appendix I (Airborne Particulate + Tritium) Dose (mrem)

Bone Liver T-WB Thyroid Kidney Lung GI-LLI Skin Adult 3.04E-04 1.77E-02 1.79E-02 1.77E-02 1.77E-02 1.77E-02 1.77E-02 2.04E-04 Teen 4.07E-04 2.03E-02 2.05E-02 2.03E-02 2.03E-02 2.03E-02 2.04E-02 2.04E-04 Child 6.41E-04 2.97E-02 2.99E-02 2.97E-02 2.97E-02 2.97E-02 2.97E-02 2.04E-04 Infant 1.74E-04 1.31E-02 1.32E-02 1.31E-02 1.31E-02 1.31E-02 1.31E-02 2.04E-04 2014 Carbon-14 Dose (mrem)

Bone Liver T. Body Thyroid Kidney Lungs GI-LLI Skin Adult 6.72E-02 1.34E-02 1.34E-02 1.34E-02 1.34E-02 1.34E-02 1.34E-02 O.OOE+00 Teen 1.05E-01 2.1OE-02 2.1OE-02 2.1OE-02 2.1OE-02 2.1OE-02 2.1OE-02 O.OOE+00 Child 2.44E-01 4.86E-02 4.86E-02 4.86E-02 4.86E-02 4.86E-02 4.86E-02 O.OOE+00 Infant 1.24E-01 2.63E-02 2.63E-02 2.63E-02 2.63E-02 2.63E-02 2.63E-02 O.OOE+00 2014 Total Airborne Non-Noble Gas Dose (Particulate + H-3 + C-14 (mrem)

Bone Liver T-WB Thyroid Kidney Lung GI-LLI Skin Adult 6.75E-02 3.1OE-02 3.12E-02 3.1OE-02 3.1OE-02 3.1OE-02 3.11E-02 2.04E-04 Teen 1.06E-01 4.13E-02 4.15E-02 4.13E-02 4.13E-02 4.13E-02 4.13E-02 2.04E-04 Child 2.44E-01 7.83E-02 7.85E-02 7.82E-02 7.82E-02 7.82E-02 7.83E-02 2.04E-04 Infant 1.24E-01 3.94E-02 3.96E-02 3.94E-02 3.94E-02 3.94E-02 3.94E-02 2.04E-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 8.14E-01 2.61E-01 2.61E-01 2.61E-01 2.61E-01 2.61E-01 6.80E-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 2014. No Type C 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 2014 Type of Waste Quantity Activity A. Spent resins, filter sludge, evaporator bottoms, etc. 7.8 m33 84.880 Ci 274.7 ft B. Dry compressible waste, contaminated equipment, etc 365.6 m33 0.386 Ci 12911.7 ft C. Irradiated components, control rods, etc. 0.00 m33 N/A Ci Wf D. Other 394.2 m3 424.000 Ci 3

Steam generators: Unit 1 removed 1984; Unit 2 removed 1996 13920 ft I 4.2 Solid Waste Disposition There were nine solid waste shipments from PBNP during 2014. The dates and destinations are shown in Table 4-2.

Table 4-2 2014 PBNP Radioactive Waste Shipments Date Destination 03/26/14 Oak Ridge, TN 04/03/14 Oak Ridge, TN 04/15/14 Clive, Utah 04/16/14 Oak Ridge, TN 06/02/14 Andrews, TX 09/16/14 Andrews, TX 09/22/14 Clive, Utah 10/02/14 Oak Ridge, TN 10/17/14 Oak Ridge, TN 4.3 Maoor Nuclide Composition (by Type of Waste)

The major radionuclide content of the 2014 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 4-3. Only those radionuclides with detectable activity are listed.

17

Table 4-3 2014 Estimated Solid Waste Major Radionuclide Composition TYPE A TYPE B TYPE D Percent Activity Percent Activity Percent Activity Nuclide Abundance (mCi) Nuclide Abundance (mCi) Nuclide Abundance (mCi)

Ni-63 3.064E-01 1.74E+03 Co-60 3.846E-01 1.49E+02 Ni-63 6.884E-01 2.92E+05 Co-60 2.853E-01 1.62E+03 Fe-55 3.208E-01 1.24E+02 Cs-1 37 1.389E-01 5.89E+04 H-3 9.439E-02 5.36E+02 Co-58 6.487E-02 2.51 E+01 Co-60 7.992E-02 3.39E+04 Cs-137 6.128E-02 3.48E+02 Cr-51 5.030E-02 1.94E+01 C-14 3.018E-02 1.28E+04 Sb-125 6.093E-02 3.46E+02 Ni-63 3.562E-02 1.38E+01 Pu-241 1.950E-02 8.27E+03 Co-58 4.402E-02 2.50E+02 Sb-125 2.575E-02 9.95E+00 H-3 1.389E-02 5.89E+03 Fe-55 3.628E-02 2.06E+02 Nb-95 2.146E-02 8.29E+00 Ni-59 1.301E-02 5.52E+03 Nb-95 2.641E-02 1.50E+02 Ru-106 1.273E-02 4.92E+00 Fe-55 1.051E-02 4.46E+03 Mn-54 2.465E-02 1.40E+02 Tc-99 1.163E-02 4.49E+00 Sr-90 2.273E-03 9.64E+02 Zr-95 1.271E-02 7.22E+01 Zr-95 1.121E-02 4.33E+00 Arn-241 1.844E-03 7.82E+02 Sb-124 1.115E-02 6.33E+01 Sn-113 1.028E-02 3.97E+00 Pu-239 6.766E-04 2.87E+02 Sn-1 17m 8.594E-03 4.88E+01 Mn-54 9.853E-03 3.81 E+00 Cm-243 4.574E-04 1.94E+02 Cr-51 8.506E-03 4.83E+01 Sb-124 7.917E-03 3.06E+00 Pu-238 4.031E-04 1.71 E+02 Ag-1 10r 5.072E-03 2.88E+01 Ni-59 7.486E-03 2.89E+00 1-129 1.004E-04 4.26E+01 C-14 3.945E-03 2.24E+01 Zn-65 3.933E-03 1.52E+00 Cs-134 1.021E-07 4.33E-02 Zn-65 2.641E-03 1.50E+01 Sn-117m 3.744E-03 1.45E+00 U-234 2.523E-08 1.07E-02 Co-57 2.342E-03 1.33E+01 Fe-59 3.207E-03 1.24E+00 Mn-54 2.332E-08 9.89E-03 Ni-59 2.307E-03 1.31E+01 H-3 2.839E-03 1.1OE+00 Np-237 9.760E-09 4.14E-03 Sn-113 1.747E-03 9.92E+00 Pu-241 2.651E-03 1.02E+00 Ce-144 1.539E-09 6.53E-04 Ce-144 8.664E-04 4.92E+00 Ag-110m 2.047E-03 7.91E-01 U-235 1.469E-11 6.23E-06 Sr-90 3.258E-04 1.85E+00 Co-57 1.562E-03 6.03E-01 Cm-242 2.381E-16 1.01E-10 Pu-241 5.301E-05 3.01E-01 Ce-144 1.356E-03 5.24E-01 Pu-238 3.187E-05 1.81E-01 Cs-137 1.079E-03 4.17E-01 Arn-241 3.029E-05 1.72E-01 Pu-238 8.737E-04 3.37E-01 Pu-239 1.164E-05 6.61E-02 Nb-94 8.127E-04 3.14E-01 Cm-243 9.456E-06 5.37E-02 Pu-239 6.521 E-04 2.52E-01 Cm-242 6.745E-07 3.83E-03 Sr-90 4.080E-04 1.58E-01 Sr-89 1.320E-04 5.1OE-02 Am-241 1.034E-04 3.99E-02 C-14 3.830E-05 1.48E-02 Cm-243 3.331E-05 1.29E-02 Pu-242 1.041 E-05 4.02E-03 Cm-242 3.986E-06 1.54E-03 18

5.0 NONRADIOACTIVE CHEMICAL RELEASES 5.1 Scheduled Chemical Waste Releases Scheduled chemical waste releases to the circulating water system from January 1, 2014, to June 30, 2014, included 6.48E+03 gallons of neutralized wastewater. The wastewater contained 3.41 E-01 lbs. of suspended solids and 3.41 E-01 lbs. of dissolved solids.

Scheduled chemical waste releases to the circulating water system from July 1, 2014, to December 31, 2014, included 6.81 E+03 gallons of neutralized wastewater. The wastewater contained 1.65E+01 lbs. of suspended solids and 1.49E+00 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, 2014, to June 30, 2014, included 1.74E+07 gallons of clarified effluent. The wastewater contained 1.88E+03 lbs. of suspended solids.

Miscellaneous chemical waste releases from the wastewater effluent (based on effluent analyses) to the circulating water for July 1, 2014, to December 31, 2014, included 1.80E+07 gallons of clarified effluent. The wastewater contained 2.09E+03 lbs. of suspended solids.

Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from January 1, 2014, to June 30, 2014, included 3.24E+05 lbs. of sodium bisulfite solution (1.23E+05 lbs. sodium bisulfite),

4.11E+05 lbs. of Sodium Hypochlorite Solution (5.14E+04 lbs. sodium hypochlorite), and 3.04E+03 lbs. Acti-Brom 1338 (1.37E+03 lbs. sodium bromide).

Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from July 1, 2014, to December 31, 2014, included 5.74E+05 lbs. of sodium bisulfite solution (2.18E+05 lbs. sodium bisulfite),

6.08E+05 lbs. Sodium Hypochlorite Solution (7.60E+04 lbs. sodium hypochlorite), 6.04E+03 lbs. Acti-Brom 1338 (2.72E+03 lbs. sodium bromide).

19

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 2014 UNIT JAN FEB MAR APR MAY JUN Average Volume Cooling* 1 358.2 358.2 362.7 473.6 542.5 542.5 Water Discharge [million gal/day]** 2 358.2 358.2 196.0 330.9 548.3 548.3 Average Cooling Water 1 38.5 38.3 38.5 40.3 47.1 51.1 Intake Temperature [OF] 2 39.8 39.6 39.6 41.4 47.5 51.6 Average Cooling Water 1 70.3 69.9 67.9 61.4 65.5 70.2 Discharge Temperature [OF] 2 70.0 69.8 68.5 50.1 64.3 68.5 Average Ambient Lake Temperature [OF] 32.7 34.2 33.7 37.3 42.8 46.8 Table 6-1 (continued)

Circulating Water System Operation for 2014 UNIT JUL AUG SEP OCT NOV DEC Average Volume Cooling*** 1 542.5 543.2 542.5 125.5 543.5 411.2 Water Discharge [million gal/day]** 2 548.3 539.4 548.3 566.9 549.0 469.4 Average Cooling Water 1 48.2 63.2 51.4 54.0 43.8 38.3 Intake Temperature [OF] 2 48.9 63.6 52.2 51.8 44.1 38.5 Average Cooling Water 1 67.0 82.2 70.2 59.5 61.5 63.8 Discharge Temperature [OF] 2 65.5 79.8 69.3 68.7 61.3 61.3 Average Ambient Lake Temperature [OF] 43.8 58.2 47.4 51.0 40.5 35.9

• U2 outage circ water shut down 3/19/14 - 4/12/14

• • For days with cooling water discharge flow.

• • • U1 outage circ water shut down 10/5/14 - 10/28/14 20

Part B Miscellaneous Reporting Requirements 7.0 ADDITIONAL REPORTING REQUIREMENTS 7.1 Revisions to the PBNP Effluent and Environmental Programs Neither the ODCM nor the RECM were revised in 2014. The Environmental Manual (EM) was revised in February 2014. A copy of the EM, Revision 25, February 11, 2014, is provided with this Annual Monitoring Report 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 2014. 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 2014.

21

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 Appendix A to 10 CFR 50, and Sections IV.B.2 and IV.B.3 of Appendix I to 10 CFR 50 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, thermoluminescent dosimeters (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.

22

9.0 PROGRAM DESCRIPTION 9.1 Results Reporting Convention The vendor used by PBNP 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 provides 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 priori LLD are chosen such that only a five percent 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 which 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, ifthe 95%

23

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, PBNP personnel also collects certain environmental samples (Table 9-6) for the State from sites that are near PBNP sampling sites, or are co-located.

9.5 Pro-gram Modifications Two temporary TLD sites were added to provide transition information prior to deleting nearby sites in 2015. Old and new sites running concurrently until 2015.

24

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, -16B, -17,

-18, 20, -22, -23, -24,

-25, -26, -26B, -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-1 3 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 25

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-1 5 Southwest Corner of Site E-16, 16B 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, -26B 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 2nd and 3rd 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 26

M!

Mi I~

C

-9 POINT BEACH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1 SITES 0

. .. . . . . . . . . MILE 0 1 KILOMETER Figure 9-1 PBNP REMP Sampling Sites 27

FIGURE2-1b S.ITE MAP POINT BEACH NUCLEAR PLANT 22 r ---- --- --- --

SITE BOUNDARY I0 I I~ I , ECT 0

16 15

• TLD q1 TLD & A[R A&L OTHER Figure 9-2 Map of REMP Sampling Sites Located Around PBNP 28

FICUFR 2-1C

(-29 LAKE MICH [GAN TAPAWIIM ,D.

a E-1 FORMER HETEM/]* BAS[N

'1/4 EKVIA1JMH1dTAL WS)4ITQIJ[NC; STAT[O45

• TLO ADU~g .

• Figure 9-3 Enhanced Map Showing REMP Sampling Sites Closest to PBNP 29

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 30

Table 9-5 Deviations from Scheduled Sampling and Frequency During 2014 LW E-01, E-05, E-06, E-33 E 1/17/13 Icy conditions at the shore prevented Nautral occurrence 06 2/13/14, getting close enough to the lake to 3/19/14 get a water sample on all three dates.

AP/I E-02 3/5/14 No power to sampler Unknown cause 5/28/14 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 31

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 2013.

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 i-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-137. Charcoal cartridges for radioiodine are counted as soon as possible so the I-131 will undergo only minimal decay prior to analyses. The weekly charcoal cartridges are screened for 1-131 by 32

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 2013.

9.7.6 Environmental Radiation Exposure The 2014 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. An evaluation of the response difference between the two types of TLD in 2001 demonstrated that the TLD cards produced a 14% higher response than the LiF chips (2011 AMR, Table 9-7, p. 36).

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.

33

9.7.7 ISFSI Ambient Radiation Exposure The ISFSI fence TLDs are part of the 10CFR72.44 monitoring and are not considered part of the REMP. However, 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.

These results are used as part of the 40CFR190 compliance demonstration.

10.0 RESULTS 10.1 Summary of 2014 REMP Results Radiological environmental monitoring conducted at PBNP from January 1, 2014, through December 31, 2014, 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 contain the following information:

Sample: Type of the sample medium

Description:

Type of measurement LLD: a priorilower limit of detection N: Number of samples analyzed 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 tech spec 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 the Appendix.

In Table 10-1 no results are reported as less than LLD (<LLD). All results are reported to Point Beach 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-20 >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.

34

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

In addition to the required radionuclides for each medium analyzed, Table 10-1 also has an additional radionuclide listed known to originate with nuclear power plants. This radionuclide is either Co-60, Ru-1 03, or any other radionuclide which has the lowest LLD based on the analytical parameters needed to meet the LLDs required for radionuclides specified for the medium being analyzed.

The radionuclide is identified by parentheses.

During the analyses for those radionuclides specifically required to be identified, naturally occurring radionuclides such as Ra-226, Be-7 and K-40 are detected in many samples. Their concentrations are presented in Table 10-1 for a comparison to those radionuclides for which specific analyses are required by the regulations. There are no regulatory required LLDs for naturally occurring radionuclides.

Finally, Point Beach reports the results for soil analyses. There is no regulatory requirement for soil analyses in standard RETS (NUREG-0472 and NUREG-1301). Point Beach includes soil analyses in the REMP to be able to compare current results to the historical record.

Table 10-2 contains the ISFSI fence TLD results.

35

Table 10-1 Summary of Radiological Environmental Monitoring Results for 2014 Average +/- 1 Std.

Sample Description N LLD (a) Deviation (b) High +/- 2 sigma Units TLD Environmental Radiation 132 1 mrem 1.07 +/- 0.19 1.51 + 0.08 mR/7days Control (E-20) 4 1 mrem 1.15 +/- 0.10 1.30 +/- 0.14 mR/7days Air Gross Beta 258 0.01 0.022 +/- 0.007 0.040 +/- 0.004 pCi/m3 Control (E-20) Gross beta 52 0.01 0.023 +/- 0.006 0.038 +/- 0.004 pCi/m3 1-131 258 0.030 (0.07) ND - pCi/m3 Control (E-20) 1-131 52 0.030 (0.07) ND - pCi/m3 Cs-134 20 0.01(0.05) ND - pCi/m3 Control (E-20) Cs-134 4 0.01(0.05) ND - pCi/m3 Cs-137 20 0.01(0.06) 0.0001 +/- 0.0004 0.0014 + 0.0007 pCi/m3 Control (E-20) Cs-137 4 0.01 (0.06) ND pCi/m3 Other V emitters (Co-60) 20 0.1 0.0000 +/- 0.0004 0.0006 + 0.0004 pCi/m3 Control (E-20) Other (Co-60) 4 0.1 0.0002 +/- 0.0003 0.0007 +/- 0.0005 pCi/m3 Natural Be-7 20 - 0.064 +/- 0.013 0.079 _ 0.014 pCi/m3 Control (E-20) Natural Be-7 4 - 0.055 +/- 0.013 0.073 + 0.018 pCi/m3 Milk Sr-89 36 5 ND pCi/L Sr-90 36 1 0.5 +/- 0.3 1.3 +/- 0.4 pCi/L 1-131 36 0.5 ND pCi/L Cs-134 36 5 (15) ND pCi/L Cs-137 36 5(18) 0.3 +/- 1.1 2.4 + 1.9 pCi/L Ba-La-140 36 5(15) -0.1 +/- 1.5 5.3 + 1.6 pCi/L Other gamma emitters(Co-60) 36 15 ND pCi/L Natural K-40 36 - 1370 +/- 55 1526 + 99 pCi/L Well Water Gross beta 4 4 1.2 +/- 0.5 1.9 +/- 0.7 pCi/L H-3 4 200 (3000) ND pCi/L Sr-89 4 5(10) ND - pCi/L Sr-90 4 1 (2) ND - pCi/L 1-131 4 0.5 (2) ND - pCi/L Mn-54 4 10(15) 1.31 +/-11.5 3.4 +/- 3.1 pCi/L Fe-59 4 30 ND - pCi/L Co-58 4 10(15) ND - pCi/L Co-60 4 10(15) ND - pCi/L Zn-65 4 30 -1.91 +/-16.2 3.5 +/-12.5 pCi/L Zr-Nb-95 4 15 ND - pCi/L Cs-134 4 10(15) ND - pCi/L Cs-137 4 10(18) ND - pCi/L Ba-La-140 4 15 ND - pCi/L Other gamma emitters(Ru-103) 4 30 ND - pCi/L Algae Gross beta 6 0.25 3.42 +/- 1.67 6.43 +/- 0.25 pCi/g Co-58 6 0.25 ND pCi/g Co-60 6 0.25 0.001 +/- 0.002 0.005 +/- 0.003 pCi/g Cs-1 34 6 0.25 ND pCi/g Cs-137 6 0.25 0.015 +/- 0.006 0.023 +/- 0.009 pCi/g Natural Be-7 6 - 0.49 +/- 0.22 0.85 +/- 0.07 pCi/g Natural K-40 6 3.12 +/- 1.11 4.50 +/- 0.10 pCi/g 36

Table 10-1 (continued)

Summary of Radiological Environmental Monitoring Results for 2014 Average +/- 1 Std.

Sample Description N LLD (a) Deviation (b) High +/- 2 sigma Units Lake Water Gross beta 45 4 1.8 +/- 0.8 4.0 + 0.6 pCi/L 1-131 45 0.5 (2) ND pCi/L Mn-54 45 10(15) -0.2 +/- 0.9 1.2 +/- 1.0 pCi/L Fe-59 45 30 -0.2 +/- 1.6 3.4 +/- 2.5 pCi/L Co-58 45 10(15) -0.1 +/- 0.9 1.6 + 1.0 pCi/L Co-60 45 10(15) 0.0 +/- 0.9 1.5 +/- 1.3 pCi/L Zn-65 45 30 ND pCi/L Zr-Nb-95 45 15 -0.6 +/- 1.1 1.5 +/- 1.3 pCi/L Cs-134 45 10(15) -0.2 +/- 0.9 1.7 +/- 1.5 pCi/L Cs-137 45 10(18) 0.1 +/- 0.9 2.0 + 1.6 pCi/L Ba-La-140 45 15 -0.3 +/- 1.8 3.4 + 1.7 pCi/L Other gamma (Ru-103) 45 30 -0.5 +/- 1.8 2.4 +/- 2.1 pCi/L Sr-89 16 5(10) 0.23 +/- 0.30 0.68 +/- 0.62 pCi/L Sr-90 16 1 (2) 0.19 +/- 0.19 0.66 +/- 0.39 pCi/L H-3 16 200(3000) 89 +/- 118 413 +/- 94 pCi/L Fish Gross beta 17 0.5 3.47 +/- 0.60 4.10 +/- 0.08 pCi/g Mn-54 17 0.13 ND pCi/g Fe-59 17 0.26 -0.003 +/- 0.021 0.022 +/- 0.018 pCi/g Co-58 17 0.13 ND pCi/g Co-60 17 0.13 ND pCi/g Zn-65 17 0.26 -0.004 +/- 0.013 0.019 + 0.016 pCi/g Cs-134 17 0.13 -0.001 +/- 0.005 0.010 + 0.008 pCi/g Cs-137 17 0.15 0.031 +/- 0.021 0.096 + 0.027 pCi/g Other gamma (Ru-103) 17 0.5 0.001 +/- 0.011 0.034 +/- 0.008 pCi/g Natural K-40 17 - 2.79 +/- 0.47 3.67 +/- 0.41 pCi/g Gross beta 10 2 8.65 +/- 1.54 10.86 +/- 0.91 pCi/g Cs-134 10 0.18 ND pCi/g Cs-1 37 10 0.15 0.019 +/- 0.009 0.033 +/- 0.016 pCi/g Natural Be-7 10 - 0.041 +/- 0.053 0.108 +/- 0.054 pCi/g Shoreline Natural K-40 10 5.98 +/- 1.88 8.15 +/- 0.49 pCi/g Sediment Natural Ra-226 10 - 0.38 +/- 0.09 0.53 +/- 0.15 pCi/g Soil Gross beta 16 2 22.80 +/- 6.41 34.27 +/- 1.77 pCi/g Cs-134 16 0.15 ND _pCi/g Cs-137 16 0.15 0.130 +/- 0.074 0.350 +/- 0.040 pCi/g Natural Be-7 16 - 0.031 +/- 0.080 0.150 +/- 0.110 pCi/g Natural K-40 16 14.94 +/- 4.07 21.07 +/- 0.89 pCi/g Natural Ra-226 16 - 0.89 +/- 0.3 1.36 +/- 0.33 pCi/g Vegetation Gross beta 24 0.25 5.98 +/- 1.53 9.55 +/- 0.21 pCi/g 1-131 24 0.06 0.001 +/- 0.007 0.02 +/- 0.10 pCi/g Cs-134 24 0.06 0.000 +/- 0.004 0.014 +/- 0.009 pCi/g Cs-137 24 0.08 0.006 +/- 0.008 0.037 +/- 0.020 pCi/g Other gamma emitters (Co-60) 24 0.25 ND pCi/g Natural Be-7 24 - 1.70 +/- 1.89 6.01 +/- 0.37 pCi/g Natural K-40 24 - 4.74 +/- 1.06 6.19 +/- 0.34 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.

37

Table 10-,

ISFSI Fence TLD Results for 2014 Fence Location Average _ Standard Deviation Units North 2.45 + 0.17 mR/7 days East 3.35 + 0.32 mR/7 days South 1.14 + 0.17 mR/7 days West 4.24 + 0.32 mR/7 days 38

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 1.07 +/- 0.19 mR/7-days compared to 1.15 +/- 0.10 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 2013 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 - 2014 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/7 days 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 mR/7 days 2004 1.10 + 0.22 mR/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 2013 1.14 +/- 0.20 mR/7 days 2014 1.07 0.19 mR/7 days

• St. Dev = Standard Deviation There were no new dry fuel storage cask additions to the ISFSI in 2014. The west fence TLDs continue to record higher exposures. Although the east fence average TLDs (3.35+/- 0.63) are higher than the north fence TLDs (2.45+/- 0.35), they are statistically equal at the 95% confidence level. The south fence average continues to record the lowest exposures (Table 11-2).

39

There is no significant change in the exposure on the TLD monitoring locations around the ISFSI (Table 11-3). The results at E-03, E-31, and E-32, which are W and SW of the ISFSI, are nearly identical (1.23, 1.25, and 1.25, respectively) and continue to be higher than the closest TLD site, E-30 (0.97). (See Figs. 9-1 and 9-2 for locations).

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

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 2013 2.62 3.66 1.15 4.28 2014 2.45 3.35 1.14 4.24 Although the mR/7-day results for the three TLD locations nearest the site boundary (E-03 1.23 + 0.26; E-31, 1.25 +/- 0.24; E-32, 1.25 + 0.26) are higher than at the background site E-20 (1.15 +/- 0.21), they are 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. 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.

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Comparing the ISFSI TLD results to results from surrounding REMP indicator and background TLDs reveals minimal impact of the ISFSI on the surrounding Figure 11-1 ISFSI AREA TLD RESULTS 1995 - 2014 ISFSI AREA TLD RESULTS 1.8 1.8 1.4

,1.2 1

• E-28 E-29

~0.8 E-30 E 0.6 0.4 0.2o2 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 1.41 0.84 0.89 1.07 1.21 1.24 1.10 2011 1.46 0.85 0.90 1.06 1.25 1.32 1.12 2012 1.54 0.87 0.91 1.10 1.21 1.39 1.14 2013 1.23 0.87 0.77 1.00 1.40 1.38 1.22 2014 1.23 0.77 0.79 0.97 1.25 1.25 1.15

• 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.

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radiation levels (Figure 11-2). As previously discussed, the small increase is more related to the switch from the LiF chips to the calcium sulfate impregnated Teflon TLD cards as evidenced by the synchronicity with E-20, the background site.

LiF TLD chips were replaced with calcium sulfate impregnated Teflon TLD cards which resulted in a higher reported background exposure.

Figure 11-2 Comparison of ISFSI Fence TLDs to Selected REMP TLDs Comparison of Fence and REMP TLDS -----orh

-o-East 8.00

-- *--South__

7.00 r 6.00

. 5.00 - E-03 E 4.00 -.- E-20

, 3.00 .  ! . -..* E-28 2.002 1.00 . .

0.00 4- - -* E-30 1990 1995 2000 2005 2010 2015 -E-31 YEAR E-32 11.2 Milk Naturally occurring potassium-40 (1370 +/- 55 pCi/I) continues to be the most prevalent radionuclide measured in milk at concentrations roughly 2000 times higher than the only potential plant related radionuclide, Sr-90 (0.5 +/- 0.3 pCi/I),

detected in milk. The annual average Sr-90 concentrations in milk continue to be similar to previous years. There were several positive Ba-La-140 results. However, no Ba-La-140 was detected in PBNP discharges during 2013 or 2014. Given the short half-life of Ba-La-140 (12.8 days), it is unlikely that these results represent a carry- over from previous years. Because the highest Ba-La-140 concentration is very near the detection limit, the positive values are considered to be false positives attributable to the statistical nature of radioactive decay. Some Cs-137 also was detected. Even though PBNP discharged airborne Cs-137 in March, April, and October, the Cs-1 37 values are near the detection limit and therefore may be false positive. Another possibility is residual Cs-137 recycling through the environment from the 1960's atmospheric weapons tests. No 1-131, Co-60, or Cs-i 34 was detected. Given that Co-60 was discharged in much higher concentrations than Cs-137 (Table 3-3) but not detected in milk, supports the conclusion that the Cs-1 37 is not from PBNP effluent but either a false positive or the recycling of radioactive fallout from weapons testing and events such as Chernobyl and Fukushima.

Although the average Sr-90 concentrations have not changed much over the last sixteen (17) years, 1.2 +/- 0.5 pCi/L in 1997 to 0.5 +/- 0.3 pCi/L in 2014, a graph of the annual averages displays a logarithmic decrease over time (Figure 11-3). The 42

annual averages are from the monthly Sr-90 measurements from three different dairies (Fig. 9-1). Only dairy site E-21 has been in the program over the entire 1997

- 2013 timespan under consideration. It is located south of the plant. The other two, E-40 and E-1 1, are replacements for dairies which had dropped out of the program at various times during this time interval. The replacements were chosen to maintain, to the extent possible, the former sampling sites west and north of Point Beach.

The previously calculated Sr-90 decrease half-live over the years 1997 to 2013 is 20.6 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 73.3 years. Given the 2a error associated with each annual average used in the calculation and the fact that only one of the sampling sites is the same as it was in 1997, there probably is not a significant difference between this value and the 59.3 years calculated for the 2012 AMR. The slightly lower 2014 value compared to the 2013 Sr-90 value for milk does not negate this conclusion.

Figure 11-3 Sr-90 Concentration in Milk (1997 - 2014)

=10 0

.W C

U 0

1995 2000 2005 2010 2015 Year The Sr-90 in milk persists due to its 28 year half-life and to cycling in the biosphere after the atmospheric weapons tests of the '50s, '60s, and '70s and later contributions from the Chernobyl accident in the late 1980s and from Fukushima.

Over the time period of this graph (1997 - 2014), PBNP discharged airborne Sr-90 only in 3 years: 1998, 2.4E-08 Ci; 2004, 3.2E-08 Ci; and 2011, 1.6 E-08 Ci. These low discharges do not appear to impact the decreasing concentrations as they continue to decrease over time. It is concluded that the milk data for 2014 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 0.022 +/- 0.014 pCi/m 3 and 0.023 +/- 0.012 pCi/m 3, respectively, and are similar to levels observed from 1993 through 2013 (Table 11-4).

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The 2014 weekly gross beta concentrations reveal higher winter values and lower summer values (Figure 11-4). This is a repeat of the patterns seen in 2006 - 2013.

.As in 2013, there is a slight peak in late summer followed by some lower values in October and early November. The cause for this variation is not known. However, the control and indicators are moving in concert. Therefore, a plant effect can be ruled out. Similarly, there is a decreasing trend in January before returning to the January highs in March. Again, the indicator and background sites move in concert ruling out a plant effect.

Table 11-4 Annual 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 2013 0.024 2014 0.022 Figure 11-4 2014 Airborne Gross Beta (pCi/mA3) vs. Time 0.045 0.040 a E-02 I)0.035

< 0.030 E E,_0.025 02 E-01 0 0L 0.0020 0.015E-03 E0 0.010 0.005 __E-04 0.0000 11/22/13 3/2/14 6/10/14 9/18/14 12/27/14 4/6115 xE-08 0 E-20 DATE 44

No 1-131 was detected during 2014. 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 0.004 to 0.0.24 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, 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-1 37 and any other (Co-60) detectable gamma emitters. As summarized in Table 10-1, no gamma emitters attributable to Point Beach were 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 2014 air data do 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 thirteen, slightly positive indications of gamma emitters during 2014.

Five of these results occurred at one location 4.5 miles north of the plant. This location is considered to be upstream based on the north to south current flow on the west shore of Lake Michigan. Therefore these results are unlikely to be an indication of Point Beach effluent. Positive results for Cs-1 34 and Ba/La-140 are considered false positives for Point Beach effluents because, in addition to occurring at an upstream location, none of the radionuclides were discharged by Point Beach during 2014. Likewise, the positive Zr/Nb-95 also is considered to be a false positive because no Zr/Nb-95 was discharged until the month after detection.

A false positive is concluding an isotope is present when it isn't. False positives occur most often at the detection limit when the random fluctuations of the background result in lower than normal background activity. The result is a higher net count and hence falsely concluding an isotope is present when it isn't because the value is statistically above zero.

The one positive Cs-137 result at this upstream location could be a false positive or be the result of the recycling of radioactive fallout recycling in the Lake Michigan 45

ecosystem. Positive results for Cs-1 37 may be expected because of its environmental persistence from atmospheric weapons testing fallout in the '50s and

'60s as well as events like Chernobyl. This source is made up of direct fallout onto the lake surface as well as watershed runoff. Other, but minor, contributions are the discharges from past and current nuclear plants on Lake Michigan. The 30-year Cs-1 37 half-life and the 62-year hydraulic residence time for Lake Michigan water indicates that Cs-1 37 remains in the lake environment for many years. Because of the strong affinity of Cs-137 for Lake Michigan sediments, it is not usually in liquids.

Its occurrence in this lake water sample may be the result of fine particles in the water. Fine particulate matter containing Cs-137 has been shown to have a residence time of approximately 42 years in near shore environments. PBNP discharged small amounts of Cs-1 37 in January - March and May - June. Although the Cs-1 37 is attributable largely to fallout, it is not possible to distinguish the fallout component from that which has been contributed since the early 1970s by current and past nuclear plants on Lake Michigan.

The remaining positive results are for Mn-54, Fe-59, Co-58, Ba/La-140, and Ru-1 03 and occur south of the plant. Again, no Ba/La-1 40 or Ru-1 03 was discharged in 2014. Positive results occurred in October (2500 feet) and in November (6 miles) south of the PBNP discharge. The last Fe-59 discharge was five months earlier.

Given that Co-58 and Co-60 were discharged but only Co-58 was detected in November but'not in October sheds doubt on the positive Mn-54, Fe-59, and Co-58 results being a true identification. Therefore, the small positive Mn-54, Fe-59 and Co-58 results are concluded to be a false positives resulting from the statistical variation in the radioactive decay detection process.

In conclusion, 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. Small amounts of Sr-89/90 were detected. As in 2012 and 2013, Point Beach did not discharge any Sr-89 or Sr-90 in 2014. There were three lake water composites in which the Sr-90 concentrations were slightly positive. They occurred north and south of the plant. Sr-90 has a 28-year half-life and, like Cs-137, is a remnant of atmospheric weapons testing in the '50s and '60s. Therefore, positive Sr-90 concentrations are indicative of fallout being recycled in Lake Michigan.

Tritium, in addition to being produced by water-cooled reactors such as PBNP, also is a naturally occurring radionuclide. It also was produced by atmospheric weapons testing. However, due to its mobility, any H-3 now found in Lake Michigan at the concentrations typically found in monitoring programs cannot be from that time period. It is the result of power plant discharges. Point Beach discharges on the order of 700 - 800 Ci per year.

Five of the seven positive H-3 indications occurred north, or upstream, from Point Beach. The highest, 431 +/- 94 pCi/I, was from a second quarter composite sample about 1.6 miles north (E-05) of Point Beach. The next highest, 244 +/- 85 pCi/I, occurred in the first quarter at E-33, some 4.5 miles north of the site. During the same quarter, the E-05 concentration was 149 +/- 80 pCi/I.

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

11.5 Algae 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 order to allow the algae time to grow, typically no samples are collected until June and then again August and October. This is done to ensure that there is enough new growth to provide a sample. In 2014 the first sample was collected in July because there was not enough growth in June to obtain a sample. Cs-1 37 was detected in all six samples. The highest positive result (0.023 +/- 0.009 pCi/g) occurred at E-12 near the PBNP discharge. The next highest (0.018 +/- 0.004 pCi/g) occurred about 1.5 miles north of the site.

As previously discussed, fallout Cs-137 recycles in Lake Michigan and is attached to particles. 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 and Fukushima. There also may be a small contribution, but unknown, amount from past nuclear plant discharges.

Point Beach discharged both Co-60 and Co-58 every month in 2014. No Co-58 was found. However, there were two small positive indications of Co-60 with the highest, 0.005 +/- 0.003 pCi/g, at E-05 about 1.5 miles north of the site. Because no Co-58 was detected even though comparable amounts of each were discharged, it is considered unlikely that the Co-60 results are related to PBNP discharges.

Therefore, these results are considered to be false positives.

The Co-60 and Cs-1 37 results are well below the naturally occurring radionuclides Be-7 and K-40. The concentrations of these two radionuclides range from 0.21 +/-

0.09 to 0.85 +/- 0.7 pCi/g for Be-7. This is about half the concentration of 1.54 +/- 0.51 pCi/g found in 2013. The K-40 ranged from 1.78 +/- 0.11 to 4.50 +/- 0.10, comparable to the 2013 results of 2.51 +/- 0.10 to 3.78 +/- 0.11 pCi/g. The better comparison for the K-40 is expected because the K-40 is incorporated into the alga during growth whereas Be-7 is not a natural component of the alga. The naturally occurring K-40 and Be-7 were at concentrations about 200 times higher than Cs-1 37. K-40 is primordial isotope of potassium with a billion year half-life. By contrast Be-7 with a 53 day half-life is produced by cosmic ray interactions with oxygen and nitrogen atoms in the atmosphere.

Assuming that the low concentrations of Co-60 and Cs-1 37 were from Point Beach, the algae monitoring results would indicate a minimal effect by PBNP upon the environs.

11.6 Fish Seventeen fish were analyzed in 2014. Sixteen of the 17 fish had detectable amounts of Cs-1 37 with results ranging from 0.011 +/- 0.010 to 0.096 +/- 0.027 pCi/g.

The Cs-1 37 is attributable to the recycling of this radionuclide in Lake Michigan.

47

The majority of Cs-1 37 entered Lake Michigan as fallout from atmospheric weapons testing in the '50s and '60s with lesser amounts from events at Chernobyl and Fukushima.

Fish analyses also yielded small amounts of Fe-59 (0.022+/- 0.018), Co-58 (0.011+/-

0.088), and Zn-65 (0.019 +/- 0.016). These results could be false positives. For example, Fe-59 was found is a fish from 4/16/14. However, no Fe-59 was released until 4/27/14. Although all of these radionuclides were released by PBNP during the year, it is not possible to attribute these results to PBNP discharges because of the migratory behavior of fish. Given that the measured concentrations are an order of magnitude below their required LLDs, and assuming that the positive results originated from Point Beach effluents, the imputed impact is minimal..

By comparison to the aforementioned radionuclides, the lowest concentration of naturally occurring K-40 (1.88- 3.81 pCi/g) is roughly twenty times higher than the highest Cs-137 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 2014, 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.

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, and 1970s 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-137 as opposed to current deposition for local sources. In addition to erosion and radioactive decay, human activities can modify the soil Cs-1 37 concentrations.

Evidence for the latter are the typically higher Cs-1 37 concentrations found at E-06, 0.34 +/- 0.04 pCi/g, as compared to other locations. At E-06, 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 2014 samples had low levels of Cs-1 37 with the highest level (0.34 +/- 0.04 pCi/g) being found at E-06. The soil from E-20, the background location, had a Cs-137 concentration of 0.13 +/- 0.04 pCi/g. E-20 is located some 17 miles away in the low x/Q sector. 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 (7.08 +/- 0.52 to 21.07 +/- 0.89 pCi/g). In addition to K-40, other naturally occurring radionuclides such as Be-7 and Ra-226 were found in the soil. There is no evidence of Point Beach effluent in the soil samples.

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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. Eight of the 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-137, K-40, which is actually part of the minerals making up the clay and sand, is at a concentration about several hundred 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-137 is the cycling of radionuclide in the Lake Michigan environment and not current PBNP discharges. As with soil, the naturally occurring radionuclides such as Be-7, K-40, and Ra-226 are found in the shoreline sediment samples. In six of the ten samples, the concentrations of naturally occurring Be-7 are higher than those of Cs-1 37. Therefore, the shoreline sediment data indicate no radiological effects from current plant operation.

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 0.058 +/- 0.045 to 6.01 +/- 0.37 pCi/g. The concentrations were lower in May (0.24 +/- 18 pCi/g) than in July (0.74 +/- 0.21) and October (4.14 +/- 1.15). This is consistent with the known temporal variability in Be-7 concentrations in air near the earth's surface and the gradual build-up of fallout on the vegetation over time. 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 with averages of 4.81, 5.08, and 4.01 in May, Jul;u, and October, respectively.

Cs-1 37 can be present in vegetation via both pathways. Fresh Cs-1 37 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-137 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).

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In 2014 only six of the twenty-four vegetation samples had a positive indication for Cs-137 and only E-06 (0.037 +/- 0.020) was significantly above background.

Although this is slightly lower than the 2013 result at E-06 (0.056 +/- 0.025), the difference is not statistically significant. Typically, only the vegetation collected at monitoring site E-06, in the Point Beach State Park south of PBNP, has detectable levels of Cs-1 37. This occurrence is attributed to the above described mechanism.

No airborne Cs-137 was discharged by PBNP in 2013 and small amount were discharge in March and April of 2014. It is unlikely that the six positive Cs-1 37 values resulted from PBNP releases.

The only other radionuclides having positive indications are 1-131 and Cs-134. Due its short half-life, it is unlikely that the airborne 1-131 release in March would be detectable in July. Likewise, the detection of 1-131 in a 10/1/14 sample occurred prior to the release on 10/15/14 and therefore not a PBNP effluent. No Cs-1 34 was released in 2013 of 2014. A review of the 2003 - 2012 time span for Cs-1 34 found no airborne Cs-1 34 over this ten year period. Therefore the small, positive results for these two radionuclides are considered to be false positives.

Based on the 2014 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 201. No significant change in the use of pasturelands or grazing herds was noted. Therefore, the existing milk-sampling program continues to be acceptable. The nearest dairy lies in the SSE sector and it is one of the Point Beach 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 818 environmental samples, and from 144 sets of TLDs that comprised the PBNP REMP for 2014, 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 PBNP 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 2014 the sampling program consisted of beach drains, intermittent stream and bog locations, drinking water wells, facade wells, yard electrical manholes, ground water monitoring wells, and the subsurface drainage (SSD) system sump located in the U-2 facade.

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. In addition to H-3, groundwater beach drain samples also are gamma scanned for the same suite of radionuclides as lake water using the lake water LLDs.

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 twelve times during 2014..

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.

Fagade well sampling has been part of the GWPP since 2007. 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.

52

e 13-1 Gr ns 53

14.0 RESULTS AND DISCUSSION 14.1 Streams and Boqs 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 H-3 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 NS + NS +/- NS +/- NS +/- 145 Feb NS + NS +/- NS +/- NS +/- 144 Mar ND + 230 +/- 86 NS +/- NS +/- 148 Apr 117 +/- 76 254 +/- 83 154 +/- 78 254 +/- 83 183 May 101 +/- 77 246 +/- 84 ND +/- NS +/- ND 393 89 146 Jun 86 +/- 79 266 +/- 88 105 +/- 80 231 +/- 87 156 Jul 98 +/- 79 110 +/- 78 ND +/- 110 +/- 78 161 Aug 230 +/- 94 168 +/- 91 98 +/- 87 NS +/- 149 Sep 119 +/- 84 133 +/- 85 ND +/- 167 +/- 87 143 Oct ND + 165 +/- 93 ND +/- 190 +/- 94 150 Nov NS +/- 148 +/- 106 ND +/- 80 178 +/- 108 150 Dec 95 +/- 93 NS +/- 102 +/- 93, 233 +/- 98 NS = no sample due to dry or frozen. 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/I.

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 but one of these concentrations are below their associated MDCs. In contrast, there are more positive results from GW-02 (south end of the East Creek) and GW-1 7 (located at the north end of the East Creek). GW-1 7 is east of the former retention pond area in the groundwater flow path to Lake Michigan. 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 which may account for the higher values.

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 GW-08 bog result is down from the 3000 pCi/I seen before the pond was remediated.

54

14.2 Beach Drains The 2013 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.

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 2014 Beach Drain Tritium Averae H-3 Concentration (pCi/I)

Month S-1 S-7 S-8 S-9 S-10 S-3 S-11 MDC Jan NF + NF +/- NF +/- NF +/- NF +/- NF + NF +/- 137 Feb NF + NF +/- NF +/- NF +/- NF +/- NF + NF +/-

Mar NF + NF +/- NF +/- NF +/- NF +/- NF + NF +/-

Apr 339 +/-92 NF +/- NF +/- NF +/- NF +/- 333+/- 91 310+/- 90 143 May 245 +/-82 NF +/- NF +/- NF +/- NF +/- 261 +/- 83 157+/- 78 144 Jun 207 +/-81 NF +/- NF N NF +/- NF +/- 228+/- 82 98+/- 75 140 Jul 203+/- 81 NF +/- NF +/- NF +/- NF +/- 287+/- 85 NF +/- 142 Aug 256+/- 110 NF +/- NF +/- NF +/- NF +/- 332+/- 114 NF +/- 193 Sep 110+/- 86 NF +/- NF +/- NF +/- NF +/- 235+/- 92 NF +/- 152 Oct ND + NF +/- NF +/- NF +/- NF +/- 252+/- 92 NF +/- 158 Nov 155+/- 117 NF +/- NF +/- NF +/- NF +/- 255+/- 122 NF +/- 179 Dec 195+/- 100 NF +/- NF +/- NF +/- NF +/- 237+/- 102 NF +/- 177 Avg = 214 +/- 68.8 1 269 +/- 40 188 +/- 109 ND = not detected and <MDC NF = no sample due to no flow The high H-3 concentrations (600 - 1000 pCi/I) seen in January - March of 2013 at S-1 and S-3 were not seen in 2014 because there was no flow due to freezing. As in previous years, measureable H-3 results occur mostly in drains S-1 and S-3. As shown in previous reports, these high values are attributable to precipitation scavenging by rain and snow followed by melting.

Gamma scans were performed on the beach drain samples at the LLD used for lake water. Five indications of small, positive concentration values below the calculated MDC were found for Fe-59, Co-58, and Ba-La-140. There were no airborne releases of Fe-59 or Ba-La-140 in 2014. Therefore, these are considered to be false positives. The absence of Co-60 whose airborne releases were comparable to those of Co-58 suggest that the identification of Co-58 also is a false positive.

Therefore, it is concluded that H-3 is the only PBNP radionuclide found in the beach drains.

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 14-3). These 55

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 and north of Z-66/67D. The two As, Bs, Cs, and Ds are beside each other.

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.

Table 14-3 2014 East Yard Area Manhole Tritium (pCi/I)

MH 5/1/2014 11/19/2014 Z-066A 331 +/- 86 133 +/- 101 Z-067A 253 83 272 +/- 109 Z-066B ND NS +/-

Z-067B ND NS J+

Z-066C ND +/- NS Z-067C 205 +/- 80 NS Z-066D 215 +/- 81 NS Z-067D ND +/- NS Z-068 243 82 219 106 MDC 145 186 ND = not detected 14.4 Facade Wells and Subsurface Drainage System There are two methods of sampling the groundwater under the plant foundation.

The first is a set of four shallow wells, two in each fagade. The other is a subsurface drainage system (SSD). The fagade wells were installed to monitor for groundwater conditions which may be detrimental to the integrity of the concrete and rebar of each unit's foundation. The SSD was designed to relieve hydrostatic pressure on each unit's foundation as well as the Auxiliary and Turbine buildings.

The fagade wells are not located symmetrically in the two units. The Unit 1 fagade wells are east of the containment in the SE (1Z-361A) and NE (1Z-361 B) corners of the fagade. However, in Unit 2, there is one well in the NW corner (2Z-361A) and the other rotated approximately 1800 in the SW corner (2Z-361 B). In each the well cap is level with the floor.

The 2014 fagade well results are shown in Table 14-4. 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. In contrast to the 2012 high of 1342 + 135, the highest 2014 H-3 concentration of 375 +/- 106 pCi/L is in close agreement with the 2013 result of 324 +/- 93 pCi/L. The 2007 and 2008 high concentrations were 1169 - 1331 pCi/l. Based on these fagade well results, the conclusion is that H-3 concentrations are decreasing and that the H-3 is not evenly distributed under the plant.

56

Table 14-4 2014 Facade Well Water Tritium (pCi/I)

UNIT I UNIT 2 Month IZ-361A IZ-361B 2Z-361A 2Z-361B MDC 15-Mar 325 +/- 91 143 +/- 83 NS +/- 119 +/- 81 143 6-Apr ND +/- 131 +/- 77 ND +/- 270 +/- 84 146 25-Jun 258 +/- 84 328 +/- 88 431 +/- 92 202 +/- 82 144 16-Jul 301 +/- 83 224 +/- 80 ND +/- 87 +/- 72 136 19-Aug 322 +/- 96 ND +/- ND +/- 145 +/- 87 151 17-Nov 375 +/- 1061219 +/- 96 ND +/- ND +/- 170 The internal SSD consist of perforated piping which drains groundwater by gravity to a sump located in the Unit 2 fagade. The part of the SSD under the Turbine Building is at a higher elevation than the part under the facades The SSD sump results are presented in Table 14-5. The 2014 average concentration of 725 +/- 235 pCi/I is not much different from the 643 +/- 201 and 513 +

269 pCi/I seen in 2013 and 2012, respectively.

The external SSD system runs along the external foundation walls for the Unit 1 and Unit 2 facades, the Auxiliary Building, the North Service Building, and the Turbine Hall. It is not connected to the internal SSD system. Both the north and south halves of the external SSD system drain toward the beach. During 2014, work to mitigate the possibility of external flooding events uncovered the N and S external SSD outfalls. Only one sample was available. A H-3 concentration of 131+/- 86 pCi/I (MDA = 158 pCi/I). This is lower than the concentrations found in beach drains S-1 and S-3 (Table 14-2) and the east yard manholes (Table 14-3).

Table 14-5 2014 Unit 2 Facade SSD Sump H-3 (pCi/I)

Date Avg 2a MDC 3-Feb 657 +/- 101 144 28-Feb 697 +/- 107 146 5-Apr 1029 +/- 112 136 6-May 688 +/- 103 145 15-May 466 +/- 94 142 23-Jun 1091 +/- 117 144 14-Jul 482 +/- 90 137 28-Aug 626 +/- 111 177 26-Sep 524 +/- 101 149 24-Oct 1120 +/- 124 176 20-Nov 518 +/- 114 172 26-Dec 789 +/- 133 173 Average 724 +/- 236 In addition to H-3, the fagade wells and SSD samples were gamma scanned. As in lake water samples, small positive values below their calculated, minimum detectable concentrations were found.

57

The isotopes in the fagade wells were Be-7, Mn-54, Co-60, Zr-Nb-95, Cs-137, and Ba-La-140. There is no known path for activation products to reach the SSD system as SSD manhole covers are sealed on the control side. The occurrence of Be-7, a short-lived isotope produced in the atmosphere coupled with that no Cs-1 34 and Ba-La-140 was detected in effluents suggests, as for lake water, that these results are false positives.

The SSD sump had small concentrations of Co-58, Zn-65, Zr-Nb-95, and Cs-1 37.

Again, it is concluded that these results are false positives.

It should be noted that the gamma scans of the 6/25/14 fagade well samples turned up anomalous results. The liquid portion had high concentrations of Be-7 (160 +/- 46 to 507 +/- 57 pCi/I), Mn-54 (3.2 +/- 1.8 to 45.2 +/- 5.5 pCi/I), Co-58 (2.0 +/- 1.7 to 242 +/- 9 pCi/I), and 1-131 (18.4 +/- 1.7 to 44.9 +/- 21.2 pCi/I) with trace amounts of Bs-La-140.

The samples were filter and the solids counted. With the exception of 1-131, all of the activity was located on the solids. The 1-131 was in the liquid phase.

Confirmatory samples taken on 7/16/14 and 8/19/14 showed no unusual activity.

Because the major source of Be-7 is the atmosphere and it had not previously been seen in these well, the presence of Be-7 suggests a contamination event. Also, the presence of Co-58 and the absence of Co-60 also suggests some contamination event. The cause of the contamination could not be determined at PBNP or at the contracted radioanalytical laboratory.

14.5 Potable Water and Monitorinq Wells Outside of the protected area, nine wells, in addition to the main plant well (Section 11.7), are used for monitoring H-3 in groundwater: the four potable water wells, GW-04 (Energy Information Center or EIC), GW-05 (Warehouse 6), GW-18 (Warehouse 7), and GW-06 (Site Boundary Control Center), and six H-3 groundwater monitoring wells, GW-1 1 through GW-16 (Figure 13-1). 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.

The monitoring well results are similar to that obtained in 2013. The highest H-3 concentrations occur at GW-15, the well closest to the former unlined retention pond. The two monitoring wells showing consistent, detectable H-3 (GW-15, GW-

16) are in the flow path from the retention pond area to the lake (Table 14-7).

Table 14-6 2014 Quarterly Monitoring Well Tritium (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 + 96 +/- 72 253 +/- 80 206 +/- 76 137 2 133 +/- 72 ND +/- ND + 83 +/- 70 171 +/- 75 234 +/- 85 136 3 ND +/- ND +/- 81 +/- 77 112 +/- 79 191 +/- 82 195 +/- 95 138 4 ND+/- INS+/- ND +/- 148 +/- 93 229 +/- 96 NS + 176 ND= not statistically different from zero. NS = no sample available 58

Two of the monitoring wells, GW-1 5 and GW-1 6, are in the 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 had no detectable H-3 (Table 14-7).

Table 14-7 2014 Potable Well Water Tritium Concentration (pCi/I)

EIG Warehouse SBCC (5W-U5, EIC WELL MDC 6 Well Well WH 7 06, 18 Month GW-04 GW-05 GW-06 GW-18 MDC Jan ND 151 ND ND ND 153 Feb ND 139 Mar ND 143 Apr ND 145 ND ND ND 144 May ND 143 Jun ND 142 Jul ND 138 ND ND ND 143 Aug ND 155 Sep ND 156 Oct ND 175 ND ND ND 158 Nov ND 186 Dec ND 169 ND= not detected NS = no sample 14.6 AC Condensate and Condensation on Equipment The results from the airborne H-3 recapture study presented in the 2011 AMR demonstrated that the H-3 via precipitation was higher close to the plant than away from the plant. Additionally, it was shown that the condensate from AC units located on building roofs and within the plant contained high concentrations of H-3.

Similar results for AC condensate were demonstrated in 2012 and 2013. A comparison of 2012 through 2014 of AC condensate H-3 concentrations is presented in Table 14-8.

Table 14-8 Comparison of 2012 - 2014 AC Condensate Location 2012 H-3 2013 H-3 2014 H-3 (pCi/I) 2o (pCi/I) 2a (pCi/I) 2u NSB (4th floor) 557 +/- 102 478 +/- 102 328 +/- 101 Turbine Bldg 66' 998 +/- 118 757 +/- 112 527 +/- 108 S Service Bldg Roof 5822 +/- 231 2606 +/- 166 2690 +/- 166 South Gate Roof 473 +/- 99 217 +/- 91 173 +/- 95 Turbine Bldg 8' 602 +/- 104 1055 +/- 123 874 +/- 119 Training Bldg Roof 185 +/- 86 203 +/- 90 ND +

ND = not detected 59

These results show that the H-3 concentrations are higher in the immediate vicinity of Units 1 and 2 (S. 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 found in the beach drains.

The persistence of measureable H-3 concentrations in AC condensations units located inside (Turbine Bldg. and NSB) indicates that the condensation of indoor airborne H-3 has the possibility of impacting groundwater. Water condensing on piping and equipment could reach groundwater via piping floor penetrations.

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 Point Beach 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-14, Figure 13-1). Additionally, because no H-3 is detected in either of 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

U APPENDIX 1 Environmental, Inc. Midwest Laboratory Final Report for the Point Beach Nuclear Plant and Other Analyses Reporting Period: January - December 2014 61

SEnvironmental, Inc.

kA T Midwest Laboratory 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, 2014 Approved by Date O2-0o-20(6" Reviewed and ahardco y, I er Distribution: K. Johansen, I hardcpy, 1 e-mail

POINT BEACH NUCLEAR PLANT TABLE OF CONTENTS Section Paqe List o f T a b le s ............................................................................ iii

1.0 INTRODUCTION

................................................................ iv 2.0 LISTING OF M ISSED SAM PLES ....................................... v 3 DATA TABLES .................................................................... vi Appendices A Interlaboratory Comparison Program Results ..................... A-1 B Data Reporting Conventions ................................................ B-1 C Sam pling 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, Gamma Isotopic Analyses ................... 2-1 M ilk ........................................................................................................ 3 -1 W ell W ater ............................................................................................. 4-1 Lake W ater ............................................................................................ 5-1 Lake W ater, Analyses on Quarterly Com posites ............................................... 6-1 F is h .................................................................................................................... 7 -1 Shoreline Sediments .......................................................................................... 8-1 So il ..................................................................................................................... 9 -1 Vegetation .......................................................................................................... 10-1 Aquatic Vegetation ............................................................................................. 11-1 Gam ma Radiation, as Measured by TLDs ........................................................ 12-1 Groundwater Monitoring Program ...................................................................... 13-1 iii

POINT BEACH NUCLEAR PLANT

1.0 INTRODUCTION

The following constitutes the final 2014 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.

All concentrations, except gross beta, are decay corrected.

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 LW E-001 01-13-14 No sample due to icy conditions.

LW E-005 01-13-14 No sample due to icy conditions.

LW E-006 01-13-14 No sample due to icy conditions.

LW E-033 01-13-14 No sample due to icy conditions.

LW E-006 02-13-14 No sample due to icy conditions.

AP/AI E-02 03-05-14 No power to sampler.

LW E-006 03-19-14 No sample due to icy conditions.

AP/AI E-02 05-28-14 No power to sampler.

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-1 31.

Location: E-01, 3

Meteorological Tower 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 01-08-14 259 0.037 +/- 0.004 < 0.011 07-09-14 295 0.015 +/- 0.003 < 0.014 01-16-14 332 0.027 +/- 0.003 < 0.006 07-16-14 302 0.014 +/- 0.003 < 0.010 01-22-14 269 0.023 +/- 0.004 < 0.006 07-23-14 306 0.030 +/- 0.004 < 0.009 01-30-14 357 0.022 +/- 0.003 < 0.007 07-30-14 301 0.019 +/- 0.003 < 0.009 02-05-14 268 0.028 +/- 0.004 < 0.008 08-06-14 297 0.023 +/- 0.003 < 0.012 02-12-14 315 0.026 +/- 0.003 < 0.010 08-13-14 302 0.020 +/- 0.003 < 0.009 02-19-14 293 0.037 +/- 0.004 < 0.006 08-20-14 332 0.018 +/- 0.003 <0.011 02-26-14 308 0.039 +/- 0.004 < 0.007 08-27-14 314 0.022 +/- 0.003 < 0.010 09-03-14 294 0.021 +/- 0.003 < 0.008 03-05-14 302 0.037 +/- 0.004 < 0.005 03-12-14 297 0.027 +/- 0.004 < 0.008 09-09-14 277 0.027 +/- 0.004 < 0.011 03-19-14 289 0.020 +/- 0.003 < 0.017 09-17-14 337 0.019 +/- 0.003 < 0.009 03-27-14 356 0.030 +/- 0.003 < 0.007 09-24-14 303 0.026 +/- 0.004 < 0.009 04-02-14 193 0.027 +/- 0.005 < 0.009 10-01-14 291 0.023 +/- 0.003 < 0.009 1st Quarter 3rd Quarter Mean +/- s.d. 0.029 +/- 0.006 < 0.008 Mean +/- s.d. 0.021 +/- 0.005 < 0.010 04-09-14 286 0.027 +/- 0.004 < 0.010 10-08-14 300 0.019 +/- 0.003 < 0.011 04-16-14 302 0.019 +/- 0.003 < 0.009 10-15-14 298 0.017 +/- 0.003 < 0.007 04-23-14 302 0.022 +/- 0.003 < 0.004 10-23-14 346 0.010 +/- 0.003 < 0.011 04-30-14 300 0.019 +/- 0.003 < 0.006 10-29-14 251 0.025 +/- 0.004 < 0.008 05-07-14 300 0.014 +/- 0.003 < 0.007 11-05-14 307 0.020 +/- 0.003 < 0.013 05-15-14 300 0.019 +/- 0.003 < 0.008 11-13-14 349 0.016 +/- 0.003 < 0.009 05-21-14 300 0.023 +/- 0.003 < 0.007 11-20-14 306 0.023 +/- 0.003 < 0.007 05-28-14 312 0.016 +/- 0.003 < 0.008 11-26-14 253 0.028 +/- 0.004 <0.016 12-03-14 303 0.031 +/- 0.004 < 0.008 06-04-14 317 0.013 +/- 0.003 < 0.006 7 06-11-14 329 0.011 +/- 0.003 < 0.007 12-10-14 306 0.037 +/- 0.004 <0.010 06-18-14 299 0.016 +/- 0.003 < 0.004 12-17-14 294 0.030 +/- 0.004 < 0.009 06-25-14 299 0.014 +/- 0.003 < 0.011 12-23-14 258 0.026 +/- 0.004 < 0.009/

07-02-14 291 0.018 +/- 0.003 < 0.006 12-30-14 307 0.025 +/- 0.003 < 0.011 2nd Quarter 4th Quarter Mean +/- s.d. 0.018 +/- 0.004 <0.007 Mean +/- s.d. 0.024 +/- 0.007 <0.010 Cumulative Averaae 0.023 +/- 0.007 < 0.009 1-1

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

Location: E-02, 3

Site Boundary Control Center 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 01-08-14 278 0.033 +/- 0.004 <0.010 07-09-14 298 0.015 +/- 0.003 < 0.014 01-16-14 331 0.025 +/- 0.003 < 0.006 07-16-14 306 0.018 +/- 0.003 < 0.010 01-22-14 267 0.023 +/- 0.004 < 0.006 07-23-14 311 0.034 +/- 0.004 < 0.009 01-30-14 355 0.021 +/- 0.003 < 0.007 07-30-14 302 0.021 +/- 0.003 < 0.009 02-05-14 267 0.028 +/- 0.004 < 0.008 08-06-14 296 0.027 +/- 0.004 < 0.012 02-12-14 308 0.028 +/- 0.003 <0.010 08-13-14 302 0.023 +/- 0.003 < 0.009 02-19-14 299 0.035 +/- 0.004 < 0.006 08-20-14 301 0.017 +/- 0.003 < 0.012 02-26-14 308 0.035 +/- 0.004 < 0.007 08-27-14 310 0.023 +/- 0.003 < 0.010 09-03-14 312 0.021 +/- 0.003 < 0.008 03-05-14 NDa 03-12-14 284 0.029 +/- 0.004 < 0.008 09-09-14 286 0.027 +/- 0.004 < 0.010 03-19-14. 296 0.019 +/- 0.003 < 0.016 09-17-14 362 0.019 +/- 0.003 < 0.009 03-27-14 358 0.023 +/- 0.003 < 0.007 09-24-14 300 0.024 +/- 0.004 < 0.009 04-02-14 261 0.023 +/- 0.004 < 0.007 10-01-14 293 0.026 +/- 0.004 < 0.009 1st Quarter 3rd Quarter Mean

• s.d. 0.027 +/- 0.005 < 0.008 Mean +/- s.d. 0.023 +/- 0.005 < 0.010 04-09-14 302 0.026 +/- 0.004 <0.010 10-08-14 293 0.017 +/- 0.003 < 0.011 04-16-14 300 0.020 +/- 0.003 < 0.009 10-15-14 300 0.015 +/- 0.003 < 0.007 04-23-14 303 0.025 +/- 0.004 < 0.004 10-23-14 353 0.011 +/- 0.002 < 0.010 04-30-14 301 0.019 +/- 0.003 < 0.006 10-29-14 252 0.023 +/- 0.004 < 0.008 05-07-14 301 0.010 +/- 0.003 < 0.007 11-05-14 311 0.018 +/- 0.003 < 0.012 05-15-14 301 0.018 +/- 0.003 < 0.008 11-13-14 357 0.015 +/- 0.003 < 0.009 05-21-14 301 0.019 +/- 0.003 < 0.007 11-20-14 321 0.014 +/- 0.003 < 0.007 05-28-14 NDa 11-26-14 259 0.026 +/- 0.004 < 0.016 12-03-14 311 0.033 +/- 0.004 < 0.008 06-04-14 315 0.013 +/- 0.003 < 0.006 06-11-14 282 0.016 +/- 0.003 < 0.008 12-10-14 313 0.039 +/- 0.004 <0.010 06-18-14 300 0.018 +/- 0.003 < 0.004 12-17-14 299 0.027 +/- 0.004 < 0.009 06-25-14 303 0.015 +/- 0.003 < 0.011 12-23-14 262 0.026 +/- 0.004 < 0.009 /

07-02-14 293 0.017 +/- 0.003 < 0.006 12-30-14 322 0.023 +/- 0.003 < 0.011 2nd Quarter 4th Quarter Mean +/- s.d. 0.018 +/- 0.004 <0.007 Mean +/- s.d. 0.022 +/- 0.008 <0.010 Cumulative Averaqe 0.022 +/- 0.007 < 0.009 a,,ND, = No data; see Table 2.0, Listing of Missed Samples.

1-2

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

Location: E-03, West Boundary 3

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 01-08-14 257 0.032 +/- 0.004 <0.010 07-09-14 297 0.016 +/- 0.003 < 0.014 01-16-14 335 0.028 +/- 0.003 < 0.006 07-16-14 302 0.014 +/- 0.003 < 0.010 01-22-14 270 0.022 +/- 0.004 < 0.006 07-23-14 301 0.030 +/- 0.004 < 0.009 01-30-14 354 0.019 +/- 0.003 < 0.007 07-30-14 297 0.019 +/- 0.003 < 0.009 02-05-14 270 0.026 +/- 0.004 < 0.008 08-06-14 287 0.025 +/- 0.004 <0.013 02-12-14 299 0.024 +/- 0.003 < 0.010 08-13-14 302 0.020 +/- 0.003 < 0.009 02-19-14 300 0.030 +/- 0.004 < 0.006 08-20-14 298 0.017 +/- 0.003 < 0.012 02-26-14 309 0,036 +/- 0.004 < 0.007 08-27-14 321 0.020 +/- 0.003 < 0.009 09-03-14 312 0.021 +/- 0.003 < 0.008 03-05-14 311 0.035 +/- 0.004 < 0.005 03-12-14 292 0.028 +/- 0.004 < 0.008 09-09-14 280 0.023 +/- 0.004 < 0.011 03-19-14 300 0.019 +/- 0.003 < 0.016 09-17-14 344 0.018 +/- 0.003 < 0.009 03-27-14 354 0.025 +/- 0.003 < 0.007 09-24-14 294 0.022 +/- 0.004 < 0.010 04-02-14 257 0.024 +/- 0.004 < 0.007 10-01-14 294 0.027 +/- 0.004 < 0.009 1st Quarter 3rd Quarter Mean +/- s.d. 0.027 +/- 0.005 < 0.008 Mean +/- s.d. 0.021 +/-0.005 < 0.010 04-09-14 294 0.025 +/- 0.004 < 0.010 10-08-14 297 0.019 +/- 0.003 <0.011 04-16-14 308 0.020 +/- 0.003 < 0.009 10-15-14 300 0.018 +/- 0.003 < 0.007 04-23-14 297 0.020 +/- 0.003 < 0.004 10-23-14 348 0.012 +/- 0.003 < 0.011 04-30-14 298 0.016 +/- 0.003 < 0.006 10-29-14 252 0.023 +/- 0.004 < 0.008 05-07-14 298 0.010 +/- 0.003 < 0.007 11-05-14 310 0.010 +/- 0.003 < 0.013 05-15-14 298 0.018 +/- 0.003 < 0.008 11-13-14 349 0.014 +/- 0.003 < 0.009 05-21-14 298 0.020 +/- 0.003 < 0.007 11-20-14 308 0.024 +/- 0.003 < 0.007 05-28-14 286 0.020 +/- 0.003 < 0.009 11-26-14 256 0.027 +/- 0.004 < 0.016 12-03-14 296 0.034 +/- 0.004 < 0.008 06-04-14 289 0.013 +/- 0.003 < 0.006 06-11-14 290 0.014 +/- 0.003 < 0.008 12-10-14 302 0.039 +/- 0.004 < 0.010 06-18-14. 298 0.015 +/- 0.003 < 0.004 12-17-14 296 0.029 +/- 0.004 < 0.009 06-25-14 301 0.012 +/- 0.003 < 0.011 12-23-14 256 0.027 +/- 0.004 < 0.009 07-02-14. 291 0.018 +/- 0.003 < 0.006 12-30-14 307 0.026 +/- 0.003 < 0.011 /

2nd Quarter 4th Quarter Mean +/- s.d. 0.017 +/- 0.004 < 0.007 Mean +/- s.d. 0.023 +/- 0.009 < 0.010 Cumulative Averaae 0.022 +/- 0.007 < 0.009 0.022 +/- 0.007 < 0,009 1-3

POINT BEACH NUCLEAR PLANT Table 1. Airborne particulates and charcoal canisters, analyses for gross beta and iodine-1 31 Location: E-04, 3

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

Date Vol. Date Vol.

Collected 3 (M ) Gross Beta 1-131 Collected (M3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-08-14 268 0.034 +/- 0.004 < 0.010 07-09-14 302 0.017 +/- 0.003 < 0.013 01-16-14 326 0.025 +/- 0.003 < 0.006 07-16-14 303 0.011 +/- 0.003 < 0.010 01-22-14 273 0.021 +/- 0.004 < 0.006 07-23-14 304 0.027 +/- 0.004 < 0.009 01-30-14 358 0.018 +/- 0.003 < 0.007 07-30-14 297 0.017 +/- 0.003 < 0.009 02-05-14 277 0.028 +/- 0.004 < 0.008 08-06-14 294 0.029 +/- 0.004 < 0.012 02-12-14 316 0.023 +/- 0.003 < 0.010 08-13-14 300 0.022 +/- 0.003 < 0.009 02-19-14 291 0.033 +/- 0.004 < 0.006 08-20-14 300 0.017 +/- 0.003 < 0.012 02-26-14 306 0.036 +/- 0.004 < 0.007 08-27-14 299 0.019 +/- 0.003 < 0.010 09-03-14 298 0.019 +/- 0.003 < 0.008 03-05-14 315 0.034 +/- 0.004 < 0.005 03-12-14 296 0.030 +/- 0.004 < 0.008 09-09-14 274 0.028 +/- 0.004 < 0.011 03-19-14 302 0.020 +/- 0.003 < 0.016 09-17-14 351 0.016 +/- 0.003 < 0.009 03-27-14 349 0.028 +/- 0.003 < 0.007 09-24-14 299 0.024 +/- 0.004 < 0.010 04-02-14 251 0.026 +/- 0.004 < 0.007 10-01-14 305 0.027 +/- 0.004 < 0.009 1st Quarter 3rd Quarter Mean +/- s.d. 0.027 +/- 0.006 < 0.008 Mean +/- s.d. 0.021 +/-0.006 < 0.010 04-09-14 294 0.027 +/- 0.004 < 0.010 10-08-14 296 0.016 +/- 0.003 < 0.011 04-16-14 302 0.020 +/- 0.003 < 0.009 10-15-14 304 0.018 +/- 0.003 < 0.007 04-23-14 302 0.021 +/- 0.003 < 0.004 10-23-14 350 0.010 +/- 0.002 < 0.010 04-30-14 301 0.016 +/- 0.003 < 0.006 10-29-14 253 0.027 +/- 0.004 < 0.008 05-07-14 301 0.012 +/- 0.003 < 0.007 11-05-14 306 0.019 +/- 0.003 < 0.013 05-15-14 301 0.019 +/- 0.003 < 0.008 11-13-14 345 0.015 +/- 0.003 < 0.009 05-21-14 301 0.020 +/- 0.003 < 0.007 11-20-14 317 0.027 +/- 0.003 < 0.007 05-28-14 299 0.020 +/- 0.003 < 0.008 11-26-14 256 0.025 +/- 0.004 < 0.016 12-03-14 305 0.035 +/- 0.004 < 0.008 06-04-14 298 0.013 +/- 0.003 < 0.006 06-11-14 290 0.016 +/- 0.003 < 0.008 12-10-14 307 0.040 +/- 0.004 < 0.010 /

06-18-14 306 0.016 +/- 0.003 < 0.004 12-17-14 296 0.029 +/- 0.004 < 0.009 06-25-14 305 0.013 +/- 0.003 < 0.011 12-23-14 258 0.029 +/- 0.004 < 0.009 07-02-14 291 0.019 +/- 0.003 < 0.006 12-30-14 314 0.024 +/- 0.003 < 0.011 2nd Quarter 4th Quarter Mean +/- s.d. 0.018 +/- 0.004 < 0.007 Mean +/- s.d. 0.024 +/- 0.008 < 0.010 Cumulative Averaae 0.023 +/- 0.007 < 0.009 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 3

Units: pCi/rm 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 01-08-14 265 0.036 +/- 0.004 < 0.010 07-09-14 293 0.013 +/- 0.003 < 0.014 01-16-14 310 0.022 +/- 0.003 < 0.007 07-16-14 300 0.013 +/- 0.003 < 0.010 01-22-14 278 0.022 +/- 0.004 < 0.006 07-23-14 308 0.032 +/- 0.004 < 0.009 01-30-14 353 0.020 +/- 0.003 < 0.007 07-30-14 295 0.016 +/- 0.003 < 0.009 02-05-14 278 0.028 +/- 0.004 < 0.008 08-06-14 286 0.024 +/- 0.004 < 0.013 02-12-14 327 0.025 +/- 0.003 < 0.010 08-13-14 300 0.020 +/- 0.003 < 0.009 02-19-14 278 0.031 +/- 0.004 < 0.006 08-20-14 300 0.018 +/- 0.003 < 0.012 02-26-14 273 0.038 +/- 0.004 < 0.008 08-27-14 306 0.021 +/- 0.003 < 0.010 09-03-14 301 0.022 +/- 0.003 < 0.008 03-05-14 312 0.033 +/- 0.004 < 0.005 03-12-14 284 0.031 +/- 0.004 < 0.008 09-09-14 277 0.027 +/- 0.004 < 0.011 03-19-14 291 0.019 +/- 0.003 < 0.017 09-17-14 310 0.019 +/- 0.003 < 0.010 03-27-14 350 0.026 +/- 0.003 < 0.007 09-24-14 301 0.023 +/- 0.004 < 0.009 04-02-14 257 0.023 +/- 0.004 < 0.007 10-01-14 303 0.031 +/- 0.004 < 0.009 1st Quarter 3rd Quarter Mean +/- s.d. 0.027 +/- 0.006 < 0.008 Mean +/- s.d. 0.021 +/- 0.006 < 0.010 04-09-14 296 0.028 +/- 0.004 < 0.010 10-08-14 305 0.017 +/- 0.003 < 0.011 04-16-14 308 0.016 +/- 0.003 < 0.009 10-15-14 197 0.022 +/- 0.004 < 0.011 04-23-14 303 0.024 +/- 0.004 < 0.004 10-23-14 351 0.012 +/- 0.003 < 0.010 04-30-14 307 0.018 +/- 0.003 < 0.006 10-29-14 255 0.024 +/- 0.004 < 0.008 05-07-14 307 0.011 +/- 0.003 < 0.006 11-05-14 307 0.017 +/- 0.003 < 0.013 05-15-14 307 0.018 +/- 0.003 < 0.007 11-13-14 344 0.015 +/- 0.003 < 0.009 05-21-14 307 0.018 +/- 0.003 < 0.006 11-20-14 327 0.025 +/- 0.003 < 0.007 05-28-14 306 0.018 +/- 0.003 < 0.008 11-26-14 251 0.028 +/- 0.004 < 0.016 12-03-14 287 0.036 +/- 0.004 < 0.009 06-04-14 312 0.016 +/- 0.003 < 0.006 06-11-14 307 0.015 +/- 0.003 < 0.007 12-10-14 303 0.036 +/- 0.004 < 0.010 06-18-14 305 0.018 +/- 0.003 < 0.004 12-17-14 298 0.029 +/- 0.004 < 0.009 06-25-14 308 0.010 +/- 0.003 < 0.011 12-23-14 253 0.025 +/- 0.004 < 0.009 07-02-14 299 0.019 +/- 0.003 < 0.006 12-30-14 316 0.025 +/- 0.003 < 0.011 /

2nd Quarter 4th Quarter Mean +/- s.d. 0.018 +/- 0.005 < 0.007 Mean +/- s.d. 0.024 +/- 0.007 < 0.010 Cumulative Average 0.022 +/- 0.007 < 0.009 Indicator Locations Annual Mean +/- s.d. 0.022 +/- 0.007 < 0.009 1-5

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

Location: E-20, 3

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

Date Vol. Date Vol.

Collected (m3) Gross Beta 1-131 Collected (Mi) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-08-14 267 0.033 +/- 0.004 < 0.010 07-09-14 305 0.016 +/- 0.003 < 0.013 01-16-14 333 0.024 +/- 0.003 < 0.006 07-16-14 300 0.015 +/- 0.003 < 0.010 01-22-14 274 0.025 +/- 0.004 < 0.006 07-23-14 307 0.029 +/- 0.004 < 0.009 01-30-14 348 0.020 +/- 0.003 < 0.007 07-30-14 296 0.022 +/- 0.003 < 0.009 02-05-14 281 0.028 +/- 0.004 < 0.008 08-06-14 296 0.023 +/- 0.004 < 0.012 02-12-14 316 0.029 +/- 0.003 < 0.010 08-13-14 296 0.020 +/- 0.003 < 0.009 02-19-14 280 0.032 +/- 0.004 < 0.006 08-20-14 303 0.018 +/- 0.003 < 0.012 02-26-14 292 0.036 +/- 0.004 < 0.008 08-27-14 314 0.025 +/- 0.003 < 0.010 09-03-14 307 0.022 +/- 0.003 < 0.008 03-05-14 321 0.033 +/- 0.004 < 0.005 03-12-14 299 0.029 +/- 0.004 < 0.008 09-09-14 273 0.026 +/- 0.004 < 0.011 03-19-14 298 0.017 +/- 0.003 < 0.016 09-17-14 360 0.021 +/- 0.003 < 0.009 03-27-14 356 0.023 +/- 0.003 < 0.007 09-24-14 304 0.024 +/- 0.004 < 0.009 04-02-14 260 0.022 +/- 0.004 < 0.007 10-01-14 316 0.028 +/- 0.003 < 0.008 1st Quarter 3rd Quarter Mean +/- s.d. 0.027 +/- 0.006 < 0.008 Mean +/- s.d. 0.022 +/- 0.004 < 0.010 04-09-14 288 0.026 +/- 0.004 < 0.010 10-08-14 303 0.018 +/- 0.003 <0.011 04-16-14 305 0.018 +/- 0.003 < 0.009 10-15-14 302 0.019 +/- 0.003 < 0.007 04-23-14 304 0.020 +/- 0.003 < 0.004 10-23-14 350 0.012 +/- 0.003 < 0.010 04-30-14 297 0.018 +/- 0.003 < 0.006 10-29-14 258 0.022 +/- 0.004 < 0.008 05-07-14 297 0.010 +/- 0.003 < 0.007 11-05-14 306 0.020 +/- 0.003 < 0.013 05-15-14 297 0.017 +/- 0.003 < 0.008 11-13-14 348 0.013 +/- 0.003 < 0.009 05-21-14 297 0.021 +/- 0.003 < 0.007 11-20-14 312 0.023 +/- 0.003 < 0.007 05-28-14 299 0.019 +/- 0.003 < 0.008 11-26-14 255 0.026 +/- 0.004 < 0.016 12-03-14 308 0.033 +/- 0.004 < 0.008 06-04-14 302 0.015 +/- 0.003 < 0.006 06-11-14 298 0.018 +/- 0.003 < 0.007 12-10-14 311 /0.038 +/- 0.004 < 0.010 06-18-14 307 0.018 +/- 0.003 < 0.004 12-17-14 294 0.026 +/- 0.004 < 0.009 06-25-14 306 0.015 +/- 0.003 <0.011 12-23-14 261 0.029 +/- 0.004 < 0.009 07-02-14 299 0.021 +/- 0.003 < 0.006 12-30-14 316 K0.025 +/- 0.003 < 0.011 2nd Quarter 4th Quarter Mean +/- s.d. 0.018 +/- 0.004 <0.007 Mean +/- s.d. 0.023 +/- 0.008 < 0.010 Cumulative Average 0.023 +/- 0.006 < 0.009 Control Annual Mean +/- s.d. 0.023 +/- 0.006 < 0.009 1-6

POINT BEACH NUCLEAR PLANT Table 2. Gamma emitters in quarterly composites of air particulate filters 3

Units: pCi/m (Other) (Other)

Location Lab Code Be-7 Be-7 Cs-134 Cs-134 Cs-137 Cs-137 Co-60 (Co-60) Volume 3

Req. LLD MDC 0.01 MDC 0.01 MDC (0.10) MDC m 1st Quarter E-01 EAP- 1768 0.069 +/- 0.015 0.0002 +/- 0.0006 < 0.0008 0.0000 +/- 0.0006 < 0.0006 0.0004 +/- 0.0005 < 0.0005 3836 E-02 - 1769 0.074 +/- 0.014 -0.0005 +/- 0.0006 < 0.0007 -0.0002 +/- 0.0007 < 0.0006 -0.0001 +/- 0.0006 < 0.0004 3612 E-03 - 1770 0.055 +/- 0.013 0.0003 +/- 0.0005 < 0.0008 -0.0002 +/- 0.0007 < 0.0007 0.0005 +/- 0.0006 < 0.0004 3907 E-04 - 1771 0.069 +/- 0.017 -0.0003 +/- 0.0005 < 0.0007 -0.0004 +/- 0.0006 < 0.0005 -0.0003 +/- 0.0006 < 0.0004 3928 E-08 - 1772 0.061 +/- 0.015 -0.0008 +/- 0.0006 < 0.0006 -0.0008 t 0.0006 < 0.0005 0.0006 +/- 0.0006 < 0.0004 3854 E-20 - 1773 0.054 +/- 0.011 0.0000 +/- 0.0003 < 0.0007 -0.0001 +/- 0.0004 < 0.0004 0.0002 +/- 0.0003 < 0.0003 3922 2nd Quarter E-01 EAP- 3708 0.076 +/- 0.017 0.0002 +/- 0.0005 < 0.0009 0.0005 +/- 0.0007 < 0.0011 -0.0002 +/- 0.0006 < 0.0009 3937 E-02 - 3709 0.073 +/- 0.015 -0.0001 +/- 0.0005 < 0.0010 0.0004 +/- 0.0007 < 0.0007 -0.0006 +/- 0.0007 < 0.0007 3603 E-03 - 3710 0.075 +/- 0.015 0.0001 +/- 0.0005 < 0.0008 0.0014 +/- 0.0007 < 0.0010 0:0006 +/- 0.0004 < 0.0007 3847 E-04 - 3711 0.077 +/- 0.016 -0.0002 +/- 0.0004 < 0.0009 0.0001 +/- 0,0005 < 0.0010 -0.0002 +/- 0.0006 < 0.0007 3892 E-08 - 3712 0.067 +/- 0.014 0.0001 +/- 0.0005 < 0.0010 0.0003 +/- 0.0005 < 0.0008 -0.0004 +/- 0.0006 < 0.0008 3971 E-20 - 3713 0.073 +/- 0.018 0.0000 +/- 0.0005 < 0.0009 0.0004 +/- 0,0007 < 0.0010 0.0001 +/- 0.0004 < 0.0007 3894 3rd Quarter E-01 EAP- 6006 0.079 +/- 0.014 -0.0001 +/- 0.0005 < 0.0009 0.0002 +/- 0,0005 < 0.0008 -0.0002 +/- 0.0006 < 0.0008 3953 E-02 -6007 0.067 +/- 0.015 0.0000 +/- 0.0004 < 0.0008 -0.0003 +/- 0.0004 < 0.0006 0.0002 +/- 0.0003 < 0.0003 3978 E-03 - 6008 0.065 +/- 0.012 0.0002 +/- 0.0004 < 0.0007 -0.0001 +/- 0,0005 < 0.0007 -0.0003 +/- 0.0004 < 0.0005 3928 E-04 - 6009 0.068 +/- 0.014 -0.0002 +/- 0.0006 < 0.0010 I 0.0002 +/- 0.0006 < 0.0006 -0.0001 +/- 0.0007 < 0.0005 3926 E-08 - 6010 0.070 +/- 0.014 -0.0006 +/- 0.0005 < 0.0011 I 0.0004 t 0,0005 < 0.0009 0.0003 +/- 0.0006 <0.0006 3881 E-20 - 6012 0.052 +/- 0.013 -0.0002 +/- 0.0004 < 0.0006 0.0000 +/- 0.0005 < 0.0006 -0.0001 +/- 0.0005 < 0.0008 3976 4th Quarter E-01 EAP- 7460 0.039 +/- 0.012 / 0.0003 0.0005 < 0.0008 0.0006 +/- 0.0005 < 0.0008 0.0005 +/- 0.0006 < 0.0008 3878 E-02 - 7461 0.049 +/- 0.012 -0.0001 +/- 0.0005 < 0.0010 0.0003 +/- 0.0006 < 0.0010 0.0001 +/- 0.0005 < 0.0008 3952 E-03 - 7462 0.047 +/- 0.012 0.0003 +/- 0.0005 < 0.0007 0.0002 +/- 0.0005 < 0.0005 -0.0006 +/- 0.0006 < 0.0007 3875 E-04 - 7463 0.053 +/- 0.014 -0.0001 +/- 0.0005 < 0.0008 -0.0005 +/- 0.0004 < 0.0003 -0,0007 +/- 0.0006 < 0.0006 3907 E-08 - 7464 0.043 +/- 0.014 -0.0001 +/- 0.0005 < 0.0008 -0.0002 +/- 0.0006 < 0.0008 -0,0002 +/- 0.0007 < 0.0006 3793 E-20 - 7465 0.042 +/- 0.013 (" -0.0002 +/- 0.0004 < 0.0007 0.0001 +/- 0.0005 < 0.0003 /0.0007 +/- 0.0005 < 0.0006 3922 Annual Meants.d. 0.062 +/- 0.012 -0.0001 +/- 0.0003 < 0.0008 0.0001 +/- 0.0004 < 0.0007 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 01-08-14 02-12-14 03-12-14 LLD Lab Code EMI- 46 EMI- 506 EMI- 912 Sr-89 0.0 +/- 0.9 < 0.8 1.0 +/- 1.1 < 1.0 -0.1 +/- 0.6 < 0.7 5.0 Sr-90 1.3 +/- 0.4 < 0.5 0.7 +/- 0.4 < 0.6 0.8 +/- 0.3 < 0.5 1.0 1-131 -0.01 +/- 0.12 < 0.22 0.02 +/- 0.15 < 0.26 -0.14 +/- 0.14 < 0.27 0.5 K-40 1489 +/- 101 1360 +/- 97 - 1383 +/- 94 Cs- 134 -0.8 +/- 1.7 < 3.5 -0.1 +/- 1.8 < 3.5 -2.3 +/- 1.5

• 2.3 5.0 Cs-137 1.3 +/- 1.9 < 3.6 -1.0 +/- 2.0 < 2.2 -1.0 +/- 1.6

• 2.8 5.0 Ba-La-140 -0.6 +/- 1.2 < 2.5 -0.5 +/- 1.7 < 2.2 -1.4 +/- 1.7 <2.1 5.0 Other (Co-60) -0.9 +/- 2.2 < 1.9 0.7 +/- 2.1 < 3.4 1.0 +/- 1.7

• 2.7 15.0 Required Collection Date 04-09-14 05-14-14 06-11-14 LLD Lab Code EMI- 1423 EMI- 2092 EM!- 2653 Sr-89 0.5 +/- 0.7 < 0.7 0.4 +/- 0.9 < 0.9 -0.1 +/- 0.8 < 0.7 5.0 Sr-90 0.7 +/- 0.3 <0.5 0.4 +/- 0.4 < 0.8 0.7 +/- 0.3 < 0.5 1.0 1-131 -0.03 +/- 0.16 < 0.29 -0.02 +/- 0.18 < 0.39 0.07 +/- 0.12 < 0.20 0.5 K-40 1363 +/- 89 1325 +/- 100 1400 +/- 95 Cs-1 34 0.4 +/- 1.5

• 2.9 -0.3 + 1.6 < 2.9 -0.5 +/- 1.9 < 4.0 5.0 Cs-137 1.1 +/- 1.5

• 2.8 1.2 +/- 2.0 < 4.0 -1.5 +/- 1.8

• 2.5 5.0 Ba-La-140 0.2 +/- 1.4

• 2.0 -1.2 +/- 1.6 < 3.1 -1.4 +/- 1.7 < 4.3 5.0 Other (Co-60) 0.8 +/- 1.9

• 2.2 -0.2 +/- 2.1 < 3.0 1.0 +/- 1.9 < 1.8 15.0 3-1

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 07-09-14 08-13-14 09-10-14 LLD Lab Code EMI- 3251 EMI- 4159 EMI- 4750 Sr-89 0.0 +/- 0.7 < 0.8 -0.8 +/- 0.9 < 0.8 0.5 +/- 0.8 < 0.7 5.0 Sr-90 0.6 +/- 0.3 < 0.5 1.1 +/- 0.4 < 0.6 0.7 +/- 0.3 < 0.5 1.0 1-131 0.11 +/- 0.17 < 0.25 0.20 +/- 0.20 < 0.35 -0.02 t 0.19 < 0.41 0.5 K-40 1259 +/- 96 1236 +/- 115 - 1399 +/- 108 Cs- 134 -1.4 +/- 1.5 < 2.8 -1.8 +/- 2.1 < 3.5 -1.2 +/- 1.8 < 3.9 5.0 Cs-137 0.2 +/- 1.8 < 2.6 -0.4 +/- 2.1 < 2.1 -1.6 t 2.2 < 3.2 5.0 Ba-La-140 -0.3 +/- 1.4 < 1.4 0.6 +/- 1.8 < 2.7 -1.4 +/- 1.9 < 3.7 5.0 Other (Co-60) -2.1 +/- 2.2 < 2.3 -0.1 +/- 2.4 < 3.0 -1.7 +/- 2.5 < 2.1 15.0 Required Collection Date 10-08-14 11-12-14 12-10-14 LLD Lab Code EMI- 5400 EMI- 6420 EMI- 6977 Sr-89 -0.1 + 0.7 < 0.8 -0.3 +/- 0.7 < 0.7 0.7 +/- 0.8 < 0.7 5.0 Sr-90 0.5 +/- 0.3 < 0.5 0.9 +/- 0.3 < 0.5 0.8 +/- 0.3 / < 0.5 1.0 1-131 -0.02 + 0.16 < 0.30 -0.01 +/- 0.13 < 0.23 0.03 +/- 0.14 < 0.24 0.5 K-40 1344 + 77 1353 +/- 87 1310 +/- 86 Cs-1 34 0.3 +/- 1.4 < 2.2 -2.3 +/- 1.5 < 2.6 0.7 +/- 1.5 < 2.6 5.0 Cs-I 37 0.1 + 1.5 < 2.4 0.4 +/- 1.7 < 3.2 0.3 +/- 1.7 < 2.8 5.0 Ba-La-140 1.9 +/- 1.4 < 4.3 -0.1 +/- 1.3 < 3.0 -1.6 +/- 1.5 < 2.8 5.0 Other (Co-60) -0.3 +/- 1.6 < 2.7 0.6 + 1.4 < 2.3 -0.7 +/- 1.6

• 1.7 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 01-08-14 02-12-14 03-12-14 LLD Lab Code EMI- 47 EMI- 507 EMI- 913 Sr-89 0.3 +/- 0.6 <0.8 0.2 +/- 0.7 < 0.7 -0.5 +/- 0.6 < 0.6 5.0 Sr-90 0.2 +/- 0.2 < 0.5 0.8 +/- 0.3 < 0.5 0.7 +/- 0.3 < 0.5 1.0 1-131 -0.04 +/- 0.13 < 0.23 0.16 +/- 0.16 < 0.28 0.05 +/- 0.15 < 0.26 0.5 K-40 1384 +/- 93 1318 +/- 91 - 1315 +/- 95 Cs-1 34 0.0 +/- 1.7

• 2.8 0.4 +/- 1.6 < 2.9 0.3 +/- 1.4

• 2.7 5.0 Cs-1 37 -2.0 +/- 1.7 *2.1 0.7 +/- 1.7 < 3.4 -0.4 +/- 1.9

• 2.6 5.0 Ba-La-140 1.1 +/- 1.4

• 1.7 -0.8 +/- 1.6 < 1.8 -1.3 +/- 1.5

• 1.3 5.0 Other (Co-60) -0.1 +/- 1.9 < 2.8 0.7 +/- 1.6 < 2.6 0.6 +/- 1.9

• 2.5 15.0 Required Collection Date 04-09-14 05-14-14 06-11-14 LLD Lab Code EMI- 1424 EMI- 2093 EMI- 2654 Sr-89 0.0 +/- 0.7 < 0.8 0.3 +/- 0.6 < 0.7 -0.1 +/- 0.7 < 0.8 5.0 Sr-90 0.2 +/- 0.3 < 0.6 0.2 +/- 0.3 < 0.5 0.4 +/- 0.3 < 0.5 1.0 1-131 0.02 +/- 0.19 < 0.34 0.11 +/- 0.22 < 0.44 0.02 +/- 0.12 < 0.22 0.5 K-40 1369 +/- 99 1414 +/- 112 1389 +/- 107 Cs-1 34 -1.0 +/- 1.7 < 3.5 0.1 +/- 1.7 < 3.3 1.7 +/- 1.6 < 3.2 5.0 Cs-1 37 1.8 +/- 2.1 < 4.2 1.4 +/- 2.1 < 3.9 -0.4 +/- 1.9

• 2.9 5.0 Ba-La-140 -1.4 +/- 1.5

• 1.8 0.4 +/- 1.4 <4.1 2.2 +/- 1.8

• 5.6 5.0 Other (Co-60) -0.8 +/- 2.1 < 2.7 0.3 +/- 2.2

• 3.8 -1.0 +/- 2.3

• 3.6 15.0 3-3

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 07-09-14 08-13-14 09-10-14 LLD Lab Code EMI- 3252 EMI- 4160 EMI- 4751 Sr-89 -0.1 +/- 0.6 < 0.8 0.1 +/- 0.7 < 0.8 -0.3 +/- 0.8 < 0.9 5.0 Sr-90 0.1 +/- 0.3 < 0.5 0.2 +/- 0.3 < 0.6 0.4 +/- 0.3 < 0.7 1.0 1-131 -0.03 +/- 0.16 < 0.23 -0.02 +/- 0.17 < 0.32 0.09 +/- 0.12 < 0.20 0.5 K-40 1347 +/- 100 1401 +/- 108 1406 +/- 109 Cs-1 34 0.7 +/- 1.7 < 3.3 -1.0 +/- 1.9 < 3.4 0.6 +/- 1.9 < 3.5 5.0 Cs- 137 -0.8 +/- 1.9

• 2.2 0.2 +/- 2.0

• 2.9 -0.6 +/- 2.1 < 4.1 5.0 Ba-La-140 -0.6 +/- 1.7

• 2.1 5.3 +/- 1.6 < 4.5 -0.7 +/- 1.6

• 3.8 5.0 Other (Co-60) 0.1 +/- 2.0 < 3.5 1.7 +/- 2.1

• 2.8 0.1 +/- 1.8 < 3.3 15.0 Required Collection Date 10-08-14 11-12-14 12-10-14 LLD Lab Code EMI- 5401 EMI- 6421 EMI- 6978 Sr-89 -0.8 +/- 0.8 < 0.9 0.4 +/- 0.6 < 0.6 -0.1 +/- 0.7 / <0.8 5.0 Sr-90 0.8 +/- 0.3 < 0.5 0.2 +/- 0.2 < 0.4 0.5 +/- 0.3 <0.5 1.0 1-131 -0.04 +/- 0.22 < 0.40 0.15 +/- 0.20 < 0.37 -0.02 +/- 0.11 < 0.20 0.5 K-40 1408 +/- 79 1327 +/- 90 1394 +/- 90 Cs- 134 0.2 +/- 1.4 < 2.3 -2.2 +/- 1.6

• 2.7 -0.5 +/- 1.5 / < 2.4 5.0 Cs-137 1.0 +/- 1.6 < 3.3 2.4 +/- 1.9 < 3.3 0.4 +/- 1.6 < 2.2 5.0 Ba-La-140 -0.2 +/- 1.4 < 3.2 -0.3 +/- 1.5

• 2.6 -0.2 +/- 1.3 < 2.2 5.0 Other (Co-60) -1.3 +/- 1.6

• 1.6 1.7 +/- 1.6 < 2.6 -0.7 +/- 1.4

• 1.3 15.0 3-4

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

E-40 Barta MDC MDC MDC Required Collection Date 01-08-14 02-12-14 03-12-14 LLD Lab Code EMI- 48 EMI- 508 EMI- 914 Sr-89 0.4 +/- 0.7 < 0.8 -0.1 +/- 0.6 < 0.6 0.5 +/- 0.5 < 0.6 5.0 Sr-90 0.4 +/- 0.3 < 0.5 0.7 +/- 0.3 < 0.4 0.2 +/- 0.2 < 0.4 1.0 1-131 0.02 +/- 0.13 < 0.23 0.10 +/- 0.15 < 0.26 -0.06 +/- 0.14 < 0.26 0.5 K-40 1433 +/- 92 1380 +/- 89 1526 +/- 99 Cs- 134 -1.0 +/- 1.7 < 2.7 0.2 +/- 1.5 < 2.7 -1.5 +/- 1.6 < 2.9 5.0 Cs-1 37 0.3 +/- 1.9 < 3.3 1.5 +/- 1.7 < 2.5 -0.6 +/- 1.8 < 1.8 5.0 Ba-La-140 0.2 +/- 1.5 < 2.3 0.5 +/- 1.5 < 2.3 0.5 +/- 2.0 < 3.8 5.0 Other (Co-60) 0.1 +/-1.9 < 3.2 0.3 +/- 1.7 < 2.2 1.1 +/- 1.8 < 2.8 15.0 Required Collection Date 04-09-14 05-14-14 06-11-14 LLD Lab Code EMI- 1425 EMI- 2094 EMI- 2655 Sr-89 0.1 +/- 0.7 <0.8 0.4 +/- 0.6 < 0.6 0.1 +/- 0.6 < 0.7 5.0 Sr-90 0.3 +/- 0.3 < 0.5 0.2 +/- 0.3 < 0.5 0.2 +/- 0.3 <0.5 1.0 1-131 -0.09 +/- 0.22 < 0.40 -0.09 +/- 0.18 < 0.42 -0.01 +/- 0.11 < 0.20 0.5 K-40 1399 +/- 94 1341 +/- 107 1363 +/- 88 Cs- 134 0.7 +/- 1.5 < 2.9 -0.1 +/- 1.9 < 3.5 1.5 +/- 1.4 < 2.8 5.0 Cs-1 37 1.6 +/- 1.8 < 3.0 1.7 +/- 2.0 < 3.4 0.8 +/- 1.6 < 2.8 5.0 Ba-La-140 1.9 +/- 1.4 < 1.4 1.1 +/- 1.2 < 3.3 2.7 +/- 1.2 < 3.3 5.0 Other (Co-60) 0.1 +/- 2.1 < 3.3 1.2 +/- 2.2 < 3.2 0.6 +/- 1.7 < 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 07-09-14 08-13-14 09-10-14 LLD Lab Code EMI- 3253 EMI- 4161 EMI- 4752 Sr-89 -0.4 +/- 0.5 < 0.6 -0.4 +/- 0.6 < 0.6 -0.6 +/- 0.6 < 0.7 5.0 Sr-90 0.4 +/- 0.2 < 0.4 0.4 +/- 0.3 < 0.5 0.4 +/- 0.3 < 0.5 1.0 1-131 0.13 +/- 0.18 < 0.26 0.07 +/- 0.21 < 0.42 0.11 +/- 0.11 < 0.20 0.5 K-40 1344 +/- 109 1338 +/- 111 1307 +/- 110 Cs- 134 1.2 +/- 1.8 < 3.3 0.1 +/- 1.8 < 3.3 -0.6 +/- 1.7 < 3.4 5.0 Cs- 137 -1.4 +/- 2.2

• 2.5 2.0 +/- 2.2 < 4.5 0.9 +/- 2.2 < 2.8 5.0 Ba-La-140 0.8 + 1.3 < 2.0 -1.3 +/- 1.6 < 4.2 -1.5 +/- 2.0 < 2.8 5.0 Other (Co-60) -1.0 +/- 2.4 < 3.4 0.9 +/- 2.1 < 3.3 1.3 +/- 2.2 < 3.9 15.0 Required Collection Date 10-08-14 11-12-14 12-10-14 LLD Lab Code EMI- 5403 EMI- 6422 EMI- 6979 Sr-89 0.4 +/- 0.8 < 0.7 -0.5 +/- 0.6 < 0.6 -0.3 +/- 0.6 <0.7 5.0 Sr-90 0.8 +/- 0.3 < 0.4 0.7 +/- 0.3 < 0.4 0.4 +/- 0.3/ < 0.4 1.0 1-131 -0.07 +/- 0.16 < 0.30 0.06 +/- 0.11 < 0.20 0.03 +/- 0.11 < 0.20 0.5 K-40 1397 +/- 91 1415 +/- 95 1394 +/- 94 Cs-134 -0.1 +/- 1.6 < 3.4 0.0 +/- 1.6

• 3.1 -0.7 +/- 1.5 < 2.2 5.0 Cs-1 37 -1.1 +/- 1.8 < 3.4 1.1 +/- 2.0 < 3.5 0.8 +/- 1.6 < 2.8 5.0 Ba-La-140 -2.4 +/- 1.7 < 2.8 -0.4 +/- 1.6 < 3.3 -1.9 +/- 1.4 < 1.8 5.0 Other (Co-60) -0.4 +/- 1.8 < 1.8 -0.5 +/- 1.9

• 1.7 -1.3 +/- 1.7 < 1.6 15.0 Sr-89 Annual Mean + s.d. 0.0 +/- 0.4 Sr-90 Annual Mean + s.d. 0.5 +/- 0.3 1-131 Annual Mean + s.d. 0.02 +/- 0.08 K-40 Annual Mean + s.d. 1370 +/- 55 Cs-134 Annual Mean + s.d. -0.3 +/-1.0 Cs-137 Annual Mean + s.d. 0.3 +/-1.1 Ba-La Annual Mean + s.d. -0.1 +/- 1.5 Co-60 Annual Mean + s.d. 0.0 +/- 1.0 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 01-09-14 04-16-14 07-10-14 10-15-14 Lab Code EWW- 79 EWW- 1524 EWW- 3293 EWW- 5688 Gross Beta 1.9 +/- 0.7 0.7 +/- 1.0 1.2 +/- 0.7 1.1 +/- 0.6 4.0 1.2 H-3 -88.5 +/- 89.2 -48.4 +/- 73.2 -18.5 +/- 69.9 -85.9 +/- 78.1 500 -60.3 Sr-89 -0.2 +/- 0.4 0.1 +/- 0.5 0.1 +/- 0.4 0.2 +/- 0.4 5.0 0.1 Sr-90 0.2 +/- 0.2 -0.1 +/- 0.3 -0.1 +/- 0.2 0.0 +/- 0.2 1.0 0.0 1-131 0.00 +/- 0.13 -0.01 +/- 0.17 0.04 +/- 0.14 0.03 +/- 0.16 0.5 0.02 Mn-54 3.4 +/- 3.1 0.0 +/- 1.9 0.6 +/- 1.2 1.4 +/- 1.3 10 1.3 Fe-59 -2.0 +/- 5.6 2.4 +/- 3.0 -2.8 +/- 2.5 -0.3 +/- 2.3 30 -0.7 Co-58 -3.1 +/- 3.0 1.8 +/- 1.8 1.1 +/- 1.5 0.3 +/- 1.2 10 0.0 Co-60 -0.4 +/- 3.4 -0.7 +/- 2.1 0.2 +/- 1.3 1.0 +/- 1.2 10 0.0 Zn-65 -10.9 +/- 9.4 -0.1 +/- 2.7 -0.4 +/- 3.0 3.5 +/- 2.5 30 -1.9 Zr-Nb-95 0.2 +/- 3.3 -4.0 +/- 2.0 -0.5 +/- 1.4 -0.1 +/- 1.3 15 -1.1 Cs-134 -2.7 +/- 3.0 -2.1 +/- 2.0 -0.7 +/- 1.5 -0.6 +/- 1.5 10 -1.5 Cs-137 0.5 +/- 3.6 0.1 +/- 2.0 -0.4 +/- 1.5 -1.0 +/- 1.6 10 -0.2 Ba-La-140 0.4 +/- 4.0 -2.8 +/- 2.7 0.2 +/- 1.7 -2.5 +/- 1.7 15 -1.2 Other (Ru-103) 1.1 +/- 3.0 0.1 +/- 1.6 -1.4 +/- 1.3 -2.0 +/- 1.3 30 -0.5 MDC Data Collection Date 01-09-14 04-16-14 07-10-14 10-15-14 Lab Code EWW- 79 EWW- 1524 EWW- 3293 EWW- 5688 Gross Beta < 1.0 < 1.9 < 0.9 < 0.8 4.0 < 1.2 H-3 < 153.0 < 144.2 < 143.2 < 157.6 500 < 149.5 Sr-89 < 0.4 < 0.6 < 0.5 < 0.5 5.0 < 0.5 Sr-90 < 0.4 < 0.6 < 0.4 < 0.4 1.0 < 0.5 1-131 < 0.24 < 0.31 < 0.20 < 0.29 0.5 < 0.26 Mn-54 < 5.8 < 2.0 < 2.1 < 2.6 10 < 3.1 Fe-59 < 7.4 < 5.9 < 1.3 < 4.4 30 < 4.8 Co-58 < 2.5 < 3.2 < 3.3 < 1.7 10 < 2.7 Co-60 < 5.6 < 1.9 < 1.8 < 1.1 10 < 2.6 Zn-65 < 12.8 < 5.0 < 4.4 < 4.0 30 < 6.5 Zr-Nb-95 < 5.5 < 2.4 < 3.7 < 2.4 15 < 3.5 Cs-134 < 6.2 < 3.2 < 2.3 < 2.8 10 < 3.6 Cs-137 < 5.7 < 3.5 < 2.2 < 2.3 10 < 3.4 Ba-La-140 < 6.4 < 4.4 < 2.7 < 3.7 15 < 4.3 Other (Ru-103) < 5.1 < 3.0 < 1.9 < 2.5 30 < 3.1 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: pCi/L MDC MDC MDC MDC Lab Code NSa ELW- 517 ELW- 1064 ELW- 1542 Date Collected 01-13-14 02-13-14 03-19-14 04-16-14 Req. LLD Gross beta 1.2 +/- 0.3 < 0.4 4.0 +/- 0.6 < 0.7 1.2 +/- 0.6 < 0.7 4.0 1-131 -0.03 +/- 0.15 < 0.28 0.07 +/- 0.15 < 0.27 -0.08 +/- 0.16 < 0.30 0.5 Be-7 5.7 +/- 15.8 < 29.3 2.3 +/- 12.6 < 25.2 9.9 +/- 11.8 < 20.9 Mn-54 0.5 +/- 1.4 < 1.8 0.6 +/- 1.6 < 2.3 -0.7 +/- 1.3 < 2.2 10 Fe-59 -0.8 +/- 3.0 < 4.5 1.6 +/- 2.5 < 3.9 -2.1 +/- 2.5 < 2.2 30 Co-58 -1.1 +/- 1.6

• 1.5 0.7 +/- 1.5 < 2.4 0.1 +/- 1.1 < 1.0 10 Co-60 -0.3 +/- 1.6 <2.1 0.7 +/- 1.3 < 1.6 0.3 +/- 1.3 <2.1 10 Zn-65 -1.0 +/- 3.2 <3.1 2.6 +/- 2.7 < 4.0 -0.2 +/- 2.2 < 2.6 30 Zr-Nb-95 -0.1 +/- 1.7 < 3.1 0.5 +/- 1.9 < 3.7 0.9 +/- 1.4 < 2.4 15 Cs-134 0.3 +/- 1.7 < 3.4 -1.9 +/- 1.7 < 2.8 -0.3 +/- 1.3 < 2.3 10 Cs-137 -1.0 +/- 1.9 < 1.8 1.2 +/- 1.9 < 2.6 0.1 +/- 1.5 < 2.0 10 Ba-La-140 -0.3 +/- 1.5 < 3.0 -0.4 +/- 2.0 < 4.2 -1.5 +/- 1.6 < 3.0 15 Other (Ru-1 03) 0.4 +/- 1.9 < 3.3 0.6 +/- 1.6 < 2.9 0.0 +/- 1.3 < 2.9 30 Lab Code ELW- 2111 ELW- 2684 ELW- 3289 ELW- 4251 Date Collected 05-14-14 06-12-14 07-10-14 08-14-14 Req. LLD Gross beta 3.0 +/- 0.8 < 1.2 0.9 +/- 0.5 < 0.9 1.4 +/- 0.6 < 0.9 1.2 +/- 0.5 < 0.9 4.0 1-131 0.01 +/- 0.16 < 0.29 -0.01 +/- 0.23 < 0.50 0.09 +/- 0.16 < 0.24 -0.03 +/- 0.20 < 0.40 0.5 Be-7 -2.8 +/- 17.3 < 31.9 2.3 +/- 10.8 < 22.8 3.5 +/- 11.7 < 23.8 0.8 +/- 19.9 < 41.2 Mn-54 -1.6 +/- 1.7 < 2.8 -0.6 +/- 1.3 <2.1 -1.2 +/- 1.3 < 1.1 -0.6 +/- 2.2 < 3.0 10 Fe-59 1.4 +/- 3.4

• 6.5 -2.8 +/- 2.4 < 3.3 0.7 +/- 2.3 < 4.0 -2.6 +/- 4.2 < 4.6 30 Co-58 0.2 +/- 1.6 < 2.7 0.8 +/- 1.3 < 2.3 0.1 +/- 1.3

• 1.5 1.4 +/- 2.3 < 3.8 10 Co-60 0.3 +/- 1.5 < 2.3 1.0 +/- 1.1 < 2.3 -0.6 +/- 1.8 < 2.6 -0.8 +/- 2.0

• 1.3 10 Zn-65 -0.2 +/- 2.5 < 1.7 -0.1 +/- 2.5 < 3.6 -1.4 +/- 2.5 < 2.9 -4.0 +/- 6.0 < 5.1 30 Zr-Nb-95 -0.6 +/- 1.6 < 2.4 -1.1 +/- 1.3 < 2.3 -0.4 +/- 1.5 < 2.5 -2.7 +/- 2.3 < 2.5 15 Cs-1 34 0.8 +/- 1.6 < 3.2 0.2 +/- 1.2 < 2.5 -0.8 +/- 1.4 < 2.7 -1.6 +/- 2.2 < 4.6 10 Cs- 137 0.3 +/- 1.9 < 2.7 0.6 +/- 1.5 < 2.7 -2.2 +/- 1.8 < 1.7 0.5 +/- 2.2 < 3.4 10 Ba-La-140 -0.8 1 1.4 < 2.2 -0.3 +/- 1.4 < 2.4 -2.1 +/- 2.0 < 3.4 -2.3 +/- 2.8

• 1.8 15 Other (Ru-103) 1.1 +/- 2.1 < 4.5 -0.4 +/- 1.1 < 2.5 -1.2 +/- 1.2 <2.1 0.0 +/- 2.3 < 3.6 30 Lab Code ELW- 4902 ELW- 6128 ELW- 6427 ELW- 7073 Date Collected 09-17-14 10-26-14 11-12-14 12-17-14 Req. LLD Gross beta 2.6 +/- 0.6 < 0.7 1.7 +/- 0.8 < 1.3 1.0 +/- 0.5 < 0.9 2.6 +/- 1.1 < 1.9 4.0 1-131 0.00 +/- 0.19 < 0.38 0.04 +/- 0.18 < 0.32 -0.07 +/- 0.16 < 0.29 0.05 +/- 0.12 < 0.17 0.5 Be-7 9.7 +/- 15.3 < 31.0 25.8 +/- 16.6 < 33.7 -9.9 +/- 13.8 < 19.6 3.2 +/- 14.7 < 27.8 Mn-54 0.5 +/- 1.6 < 2.3 -0.7 +/- 1.6 < 2.1 0.4 +/- 1.4 <2.1 -0.2 +/- 1.4 < 2.2 10 Fe-59 0.7 +/- 2.7 < 3.5 3.4 +/- 2.5

• 5.0 1.0 +/- 2.6 < 5.3 0.6 +/- 3.1 < 5.3 30 Co-58 -1.5 +/- 1.5 < 1.3 0.2 +/- 1.4 < 2.4 0.0 +/- 1.6 < 2.6 0.1 +/- 1.5 < 2.1 10 Co-60 -0.9 +/- 1.6 < 1.5 1.1 +/- 1.5 < 2.7 0.5 +/- 1.5 < 2.3 -0.8 +/- 1.5 < 2.3 10 Zn-65 -2.8 +/- 3.6 < 3.3 -5.0 +/- 4.1 < 2.9 -1.9 +/- 3.0 < 3.5 -2.0 +/- 3.2 < 3.6 30 Zr-Nb-95 -0.4 1 1.6 < 2.3 -1.0 +/- 1.5 < 2.9 -2.3 +/- 1.8 < 3.3 -0.2 +/- 1.7 < 3.5 15 Cs-134 0.3 +/- 1.8 < 3.9 1.1 +/- 1.6 < 3.4 -0.5 +/- 1.7 < 2.9 -1.0 +/- 1.5 < 2.9 10 Cs- 137 -0.8 +/- 1.9 < 2.7 0.8 +/- 1.6 < 2.6 0.0 +/- 1.8 < 3.2 -0.4 +/- 1.6 < 2.6 10 Ba-La-140 -0.4 +/- 1.6

• 1.6 3.4 +/- 1.7 < 3.1 -6.3 +/- 2.1 < 2.6 -0.2 +/- 1.6

• 1.6 15 Other (Ru-103) -0.3 +/- 2.0 < 3.5 0.8 +/- 1.9 < 3.4 -0.8 +/- 1.3 < 2.8 -1.6 +/- 1.9 < 4.0 30 "NS" = No sample; see Table 2.0, Listing of Missed Samples.

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 NSa ELW- 518 ELW- 1065 ELW- 1543 Date Collected 01-13-14 02-13-14 03-19-14 04-17-14 Req. LLD Gross beta 1.9 +/- 0.3 < 0.4 1.7 +/- 0.4 < 0.6 1.7 +/- 0.5 < 0.7 4.0 1-131 -0.04 +/- 0.22 < 0.46 0.03 +/- 0.14

• 0.25 0.14 +/- 0.22 < 0.41 0.5 Be-7 -3.9 +/- 18.6 < 21.5 9.5 +/- 10.0 < 21.5 16.0 +/- 12.7 < 27.5 Mn-54 -2.8 +/- 1.7 < 2.0 0.4 +/- 1.3 < 2.2 -0.5 +/- 1.3 < 1.3 10 Fe-59 -1.1 + 3.5 < 5.9 -1.8 +/- 2.1 < 2.6 0.7 + 2.7 < 4.8 30 Co-58 -2.0 +/- 1.5 < 1.3 1.1 +/- 1.2 < 2.2 0.1 +/- 1.3 < 1.7 10 Co-60 1.1 +/- 2.1 < 3.3 0.1 +/- 1.3 < 1.9 -0.4 +/- 1.5 < 1.5 10 Zn-65 -4.3 +/- 4.8 < 5.1 -0.9 +/- 2.6 < 3.2 0.2 +/- 2.8 < 2.4 30 Zr-Nb-95 0.8 +/- 1.8 < 4.3 -1.2 +/- 1.3 < 1.9 -0.8 +/- 1.6 < 2.1 15 Cs-1 34 0.9 +/- 1.7 < 3.7 -0.1 +/- 1.3 < 2.2 -0.7 +/- 1.5 < 2.5 10 Cs-137 -0.6 +/- 2.0 < 3.4 -1.4 +/- 1.4 < 1.7 -0.8 +/- 1.6 < 2.3 10 Ba-La-140 0.3 +/- 1.8 < 3.8 -0.6 +/- 1.5 < 3.0 -0.9 +/- 1.6 < 2.3 15 Other (Ru-103) 0.6 +/- 2.1 < 3.5 -0.8 +/- 1.2 < 2.2 -0.3 +/- 1.4 < 2.7 30 Lab Code ELW- 2112 ELW- 2685 ELW- 3290 ELW- 4252 Date Collected 05-14-14 06-12-14 07-10-14 08-14-14 Req. LLD Gross beta 2.7 +/-:0.8 < 1.3 1.4 +/- 0.6 < 0.9 1.0 +/- 0.5 < 0.9 1.1 +/- 0.5 < 0.9 4.0 1-131 -0.03 +/- 0.17 < 0.30 0.12 +/- 0.16 < 0.28 0.17 +/- 0.22 < 0.43 0.06 +/- 0.17 < 0.30 0.5 Be-7 4.8 +/- 13.0 < 17.4 -1.8 +/- 9.7 < 20.9 -1.5 +/- 10.8 < 20.6 4.4 +/- 12.6 < 24.5 Mn-54 -0.8 +/- 1.5 < 2.5 0.1 +/- 1.4 < 1.4 -0.2 +/- 1.3 < 1.7 -0.8 +/- 1.8 < 2.7 10 Fe-59 -3.4 +/- 3.0 < 2.4 -1.2 +/- 2.6 < 2.6 -0.3 +/- 2.5 < 3.0 0.6 +/- 2.9 <3.1 30 Co-58 0.6 +/- 1.7 <3.1 -0.4 +/- 1.2 < 1.8 -0.1 +/- 1.2 < 1.6 0.5 +/- 1.6 < 2.4 10 Co-60 0.9 +/- 1.5 < 2.0 0.7 +/- 1.3 < 2.5 -1.6 +/- 1.6 < 1.5 -1.5 + 1.9 < 2.3 10 Zn-65 1.6 +/- 2.4 < 2.8 0.7 +/- 2.7 < 3.8 -2.0 +/- 2.5 < 2.9 1.9 +/- 3.1 < 4.9 30 Zr-Nb-95 -2.1 +/- 1.7 < 2.1 -0.8 +/- 1.2 < 1.3 0.2 +/- 1.5 < 2.4 0.1 +/- 1.8 <4.1 15 Cs-1 34 0.2 +/- 1.4 < 2.5 -0.4 +/- 1.3 < 2.4 0.2 +/- 1.4 < 2.5 0.9 +/- 1.6 < 2.6 10 Cs-137 0.4 +2.1 < 2.7 -0.7 +/- 1.4 < 2.6 0.6 +/- 1.7 < 2.5 -0.4 +/- 1.7 < 1.9 10 Ba-La-140 -1.1 +/- 1.7 < 2.0 -0.5 +/- 1.3 < 2.4 -0.4 +/- 1.5 < 2.9 0.5 +/- 1.7 < 5.0 15 Other (Ru-1 03) 0.7 +/- 1.6 < 3.6 0.1 +/- 1.3 < 2.5 -1.1 +/- 1.4 < 1.9 -1.0 +/- 1.5 < 2.4 30 Lab Code ELW- 4903 ELW- 6129 ELW- 6428 ELW- 7074 Date Collected 09-17-14 10-26-14 11-12-14 12-17-14 Req. LLD Gross beta 1.7 +/- 0.6 < 0.8 3.0 +/- 0.7 < 1.1 1.5 +/- 0.5 < 0.8 2.6 +/- 1.0 < 1.6 4.0 1-131 0.08 + 0.14 < 0.24 -0.08 +/- 0.18 < 0.33 -0.01 +/- 0.16 < 0.28 0.04 +/- 0.12 < 0.18 0.5 Be-7 -3.9 +/- 17.9 < 28.8 -10.9 +/- 11.4 < 19.6 -2.4 +/- 9.5 < 18.6 7.9 11.4 <23.7 Mn-54 -1.8 +/- 1.7 < 1.2 0.0 +/- 1.5 < 2.6 1.0 +/- 1.1 < 2.2 0.7 +/- 1.4 < 2.4 10 Fe-59 0.9 +/- 3.1 < 3.7 1.2 +/- 2.6 < 5.3 1.8 +/- 2.4 < 5.6 -0.3 +/- 2.6 < 2.8 30 Co-58 -0.5 +/- 1.6 < 1.6 -0.3 +/- 1.5 < 3.0 0.2 +/- 1.1 < 1.9 0.1 +/- 1.2 < 1.6 10 Co-60 0.6 +/- 1.8 < 1.8 1.1 +/- 1.1 < 1.4 1.0 +/- 1.4 < 2.0 -0.3 +/- 1.3 < 0.8 10 Zn-65 2.7 +/- 3.4 < 4.7 -2.8 +/- 3.4 < 3.4 -0.9 +/- 2.5 < 2.9 -3.5 +/- 3.2 < 1.4 30 Zr-Nb-95 0.8 +/- 1.8 < 3.7 0.5 +/- 1.5 < 3.5 -0.6 +/- 1.2 < 2.2 0.2 +/- 1.3 < 2.3 15 Cs-134 -0.7 +/- 1.7 < 3.5 0.5 +/- 1.3 < 2.5 0.6 +/- 1.2 <2.4 -1.5 +/- 1.5 < 2.7 10 Cs-137 -0.8 +/- 1.8 < 2.1 -0.6 +/- 1.6 < 2.6 0.7 +/- 1.6 < 3.0 -0.8 +/- 1.7 / < 1.8 10 Ba-La-140 -0.3 +/- 2.5 < 3.1 -0.5 +/- 1.4 < 3.3 -0.1 +/- 1.4 < 3.1 0.6 +/- 1.3 < 2.4 15 Other (Ru-1 03) 0.9 +/- 2.1 < 3.5 0.4 +/- 1.4 < 3.1 0.0 +/- 1.2 < 2.9 0.0 +/- 1.3 < 2.8 30 2 "NS" = No sample; see Table 2.0, Listing of Missed Samples.

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 NSa NSa NS" ELW- 1544 Date Collected 01-13-14 02-13-14 03-19-14 04-17-14 Req. LLD Gross beta 1.5+/-0.6 <0.8 4.0 1-131 -0.01 +/- 0.14 < 0.26 0.5 Be-7 -1.2 +/- 15.3 < 18.2 Mn-54 -1.3 +/- 1.7 < 2.5 10 Fe-59 -3.3 +/- 3.0 < 3.0 30 Co-58 -2.4 +/- 1.8 < 1.6 10 Co-60 -0.8 +/- 1.7 < 1.9 10 Zn-65 -3.1 +/- 3.4 < 2.7 30 Zr-Nb-95 -1.7 +/- 2.0 < 2.4 15 Cs- 134 1.0 +/- 1.7 < 3.4 10 Cs-1 37 0.5 +/- 2.2 < 3.4 10 Ba-La-140 -2.5 +/- 1.9 < 3.0 15 Other (Ru-103) -0.1 +/- 2.1 < 4.4 30 Lab Code ELW- 2113 ELW- 2686 ELW- 3291 ELW- 4253 Date Collected 05-14-14 06-12-14 07-10-14 08-14-14 Req. LLD Gross beta 2.3 +/- 0.7 < 1.1 1.4 +/- 0.6 < 0.8 0.5 +/- 0.5 < 0.9 1.0 +/- 0.5 <0.9 4.0 1-131 0.14 +/- 0.18 < 0.31 0.00 +/- 0.18 < 0.33 0.08 +/- 0.13 < 0.19 0.12 +/- 0.18 <0.32 0.5 Be-7 0.9 +/- 11.7 < 24.3 -4.2 +/- 17.0 < 36.1 -3.9 +/- 11.6 < 16.1 -4.8 +/- 12.1 - 25.7 Mn-54 0.5 +/- 1.7 < 2.7 1.3 +/- 1.6 < 2.8 0.1 +/- 1.2 < 2.0 0.4 +/- 1.3 < 2.2 10 Fe-59 -0.7 +/- 2.8 < 4.3 -1.0 +/- 4.0 < 3.6 1.1 +/- 3.0 < 6.8 -0.2 +/- 2.7 < 2.7 30 Co-58 0.9 +/- 1.5 < 2.6 -0.5 +/- 1.9 < 2.4 -03 +/- 1.2 < 1.7 -0.6 +/- 1.6 < 2.5 10 Co-60 0.7 +/- 1.8 < 2.5 0.1 +/- 1.8 < 2.0 -0.6 +/- 1.8 < 2.9 0.4 +/- 1.4 < 1.7 10 Zn-65 0.4 +/- 2.8 < 4.5 -1.4 +/- 4.4 < 5.2 -0.2 +/- 2.6 < 1.9 -0.3 +/- 3.5 < 5.9 30 Zr-Nb-95 -0.9 +/- 1.5 < 3.0 1.4 +/- 1.8

• 3.5 -1.8 +/- 1.4 < 2.5 -1.0 +/- 1.7 < 2.8 15 Cs-134 -0.4 +/- 1.4

• 2.7 -0.5 +/- 2.1 < 4.7 -1.3 +/- 1.5 < 2.8 0.4 +/- 1.6 < 2.6 10 Cs-137 -0.7 +/- 1.8 <2.1 0.9 +/- 1.9 < 3.2 -0.1 +/- 1.5 < 2.0 0.6 +/- 1.9 < 3.5 10 Ba-La-140 -1.1 +/- 1.8 < 4.0 2.4 +/- 2.3 < 3.8 -2.8 +/- 1.5 < 3.2 -1.2 +/- 2.2 < 2.7 15 Other (Ru-103) -0.6 +/- 1.4 < 2.0 2.4 +/- 2.1 < 4.5 0.0 +/- 1.4 < 3.6 1.9 +/- 1.5 < 3.4 30 Lab Code ELW- 4904 ELW- 6130 ELW- 6429 ELW- 7075 Date Collected 09-17-14 10-26-14 11-12-14 12-17-14 Req. LLD Gross beta 2.1 +/- 0.5 < 0.7 2.6 + 0.7 < 1.2 1.2 +/- 0.5 < 0.9 3.0 +/- 1.1 ' < 1.8 4.0 1-131 -0.11 +/- 0.16 < 0.31 0.08 + 0.18 < 0.31 0.00 +/- 0.17 < 0.31 0.11 +/- 0.14 < 0.20 0.5 Be-7 -7.3 +/- 20.8

• 35.8 -0.4 +/- 11.0

• 31.9 6.6 +/- 9.1 < 24.8 -6.8 +/- 21.8 < 23.1 Mn-54 1.1 +/- 2.1 < 3.6 0.9 +/- 1.3

• 2.7 1.2 +/- 1.0 < 2.0 0.9 +/- 2.4 < 4.3 10 Fe-59 -0.9 +/- 3.5 < 3.2 1.4 +/- 2.6 < 4.8 2.2 +/- 2.0 < 5.4 -2.5 +/- 5.7 < 4.9 30 Co-58 1.0 +/- 2.1 < 2.9 -0.5 +/- 1.3 < 1.4 1.6 +/- 1.0 <2.1 -0.4

• 2.7 < 3.6 10 Co-60 -1.4 +/- 2.3 < 1.5 1.4 +/- 1.6 < 2.0 -0.7 +/- 1.1 < 1.4 -2.2 3.1 +/-2.9

+/-5.2/ <5.1 10 Zn-65 -5.1 +/- 4.5 < 3.5 1.5 +/- 2.2 < 3.1 -1.6 +/- 2.0 < 3.5 < 4.5 30 Zr-Nb-95 -0.6 +/- 2.1 < 3.1 -1.9 +/- 1.5

• 2.5 -0.7 +/- 1.2 < 3.3 -1.6 +/- 2.8 <5.1 15 Cs-134 -1.0 +/- 2.2 < 4.4 -1.4 +/- 1.5 < 2.3 -0.7 +/- 1.1 < 1.8 -0.9 +/- 2.5 < 4.8 10 Cs-137 1.2 +/- 2.6 < 4.6 0.0 +/- 1.6 < 2.7 0.8 +/- 1.3 < 2.3 -0.3 +/- 3.2 < 3.4 10 Ba-La-140 -0.4 +/- 2.3 *2.1 -0.6 +/- 1.9

• 5.2 -0.3 +/- 1.0 < 5.0 3.6 +/- 2.5 < 6.8 15 Other (Ru-103) -1.7 +/- 2.3 < 2.6 0.7 +/- 1.2 < 3.1 1.2 +/- 1.0 < 2.9 -1.6 +/- 2.4 < 4.7 30 a"NS" = No sample; see Table 2.0, Listing of Missed Samples.

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 Lab Code NSa ELW- 519 ELW- 1066 ELW- 1545 Date Collected 01-13-14 02-13-14 03-19-14 04-17-14 Req. LLD Gross beta 0.8 +/- 0.3 < 0.4 1.3 +/- 0.4 < 0.6 1.0 +/- 0.6 < 0.8 4.0 1-131 0.17 +/- 0.19 < 0.33 0.07 +/- 0.14 < 0.24 0.10 +/- 0.14 < 0.24 0.5 Be-7 -6.8 +/- 13.6 < 27.8 -5.8 +/- 10.7 < 19.2 -6.1 +/- 12.3 < 29.8 Mn-54 0.5 +/- 1.5 < 2.1 -0.9 +/- 1.3 < 1.6 0.1 +/- 1.4 < 1.8 10 Fe-59 0.5 i 2.7 < 3.2 0.6 +/- 2.2 <4.1 -0.7 +/- 2.8 < 3.7 30 Co-58 -0.1 +/- 1.6 < 2.2 -1.0 1 1.3

• 1.7 -1.4 +/- 1.4 < 1.4 10 Co-60 -1.1 +/- 2.0 < 1.4 1.0 +/- 1.1 < 1.7 0.2 +/- 1.6 < 2.6 10 Zn-65 0.6 +/- 3.6 < 6.2 -2.6 +/- 2.7 < 4.3 -1.3 +/- 3.1 < 2.5 30 Zr-Nb-95 -1.3 +/- 1.9 < 3.8 1.5 1 1.3 < 2.9 -0.1 +/- 1.5 < 2.8 15 Cs-1 34 -0.1 _ 1.7 < 3.4 -1.5 +/- 1.4 < 2.4 0.5 +/- 1.6 < 2.8 10 Cs-i37 0.9 +/- 1.8 < 2.9 0.3 +/- 1.7 < 3.2 1.4 +/- 1.7 < 2.5 10 Ba-La-140 2.1 + 2.1 < 4.3 -0.8 +/- 1.4 < 2.8 2.4 +/- 1.7 < 4.4 15 Other (Ru-103) -1.2 +/- 1.5 < 2.7 0.8 +/- 1.2 < 2.5 -0.5 +/- 1.4 < 2.6 30 Lab Code ELW- 2114 ELW- 2687 ELW- 3292 ELW- 4254 Date Collected 05-24-14 06-12-14 07-10-14 08-14-14 Req. LLD Gross beta 2.8 +/- 0.8 < 1.3 1.4 +/- 0.6 < 0.9 0.9 +/- 0.5 < 0.8 1.3 +/- 0.5 < 0.8 4.0 1-131 -0.02 +/- 0.17 < 0.31 -0.01 +/- 0.22 < 0.40 0.19 +/- 0.21 < 0.40 -0.02 +/- 0.23 < 0.44 0.5 Be-7 -3.1 +/- 10.8 < 16.1 -2.7 +/- 11.6 < 22.7 -0.3 +/- 11.9 < 22.9 2.5 +/- 8.2 < 18.8 Mn-54 -0.1 +/- 1.6 < 2.8 -1.4 +/- 1.5 < 2.3 0.7 +/- 1.3 < 2.5 0.4 +/- 1.0 < 1.6 10 Fe-59 1.7 +/- 2.3 < 5.4 -1.5 +/- 2.7 < 4.0 1.8 +/- 2.2 < 2.8 0.6 +/- 1.7 < 3.8 30 Co-58 0.5 +/- 1.3 < 2.2 1.2 +/- 1.5 < 2.6 -1.0 +/- 1.4 < 1.4 -0.6 1 0.9 < 1.6 10 Co-60 0.6 +/- 1.5 < 2.4 0.2 +/- 1.5 < 2.5 0.3 +/- 1.7 < 2.2 0.5 +/- 1.0 < 1.9 10 Zn-65 1.2 +/- 2.8 < 4.9 0.3 +/- 3.2 < 4.4 1.5 +/- 3.0 < 4.3 -1.1 +/- 1.8 < 2.3 30 Zr-Nb-95 -0.9 +/- 1.7 < 3.2 -0.1 +/- 1.2 < 1.4 0.4 +/- 1.9 < 4.9 0.0 +/- 1.1 < 2.6 15 Cs-134 -1.5 + 1.8 < 3.4 -0.9 +/- 1.3 < 2.6 -0.3 +/- 1.6 < 2.6 0.8 + 0.9 < 1.9 10 Cs-137 1.4 +/- 1.7 < 3.0 2.0 +/- 1.6 < 2.8 -2.0 +/- 1.8 <2.1 0.8 +/- 1.2 < 2.1 10 Ba-La-140 0.2 +/- 1.7 < 3.6 -0.7 +/- 1.5 < 3.0 -0.5 +/- 2.0 < 5.0 0.8 +/- 1.0 <4.1 15 Other (Ru-1 03) -0.5 +/- 1.5 < 3.3 0.4 +/- 1.4 < 2.1 -1.0 +/- 1.5 < 2.9 -1.1 +/- 0.9 < 1.7 30 Lab Code ELW- 4905 ELW- 6131 ELW- 6430 ELW- 7076 Date Collected 09-17-14 10-26-14 11-12-14 12-17-14 Req. LLD Gross beta 1.9 +/- 0.6 < 0.8 1.0 0.4 < 0.6 1.6 +/- 0.6 < 0.8 3.0 k 1.87 < 3.2 4.0 1-131 0.07 +/- 0.19 < 0.38 0.02 +/- 0.17 < 0.31 -0.09 +/- 0.16 < 0.30 0.10 +/- 0.13 < 0.19 0.5 Be-7 4.0 +/- 17.7 < 29.3 -5.1 +/- 10.9 < 17.0 -7.3 +/- 7.7 < 16.5 -5.7 +/- 11.6 < 26.7 Mn-54 -0.7 +/- 1.6 <2.1 -0.8 +/- 1.6 <2.1 -0.6 +/- 1.0 < 2.0 -0.6 +/- 1.2 < 1.9 10 Fe-59 -0.9 +/- 3.6 < 4.3 -2.3 +/- 2.4 < 4.5 0.2 +/- 2.1 < 5.2 -0.7 +/- 2.0 < 3.3 30 Co-58 0.5 +/- 1.4

• 1.6 -0.6 +/- 1.3 < 2.6 0.8 +/- 1.0 < 2.5 -0.4 +/- 1.3 < 1.3 10 Co-60 -1.3 +/- 1.8

• 1.2 -1.8 +/- 1.6

• 1.0 0.1 +/- 1.1 < 1.6 1.5 +/- 1.3 < 2.2 10 Zn-65 -2.8 +/- 4.0 <4.1 1.3 +/- 2.4 < 3.3 -0.3 +/- 2.2 < 3.7 2.3 +/- 2.6 / < 4.7 30 Zr-Nb-95 -2.8 +/- 1.7 < 2.4 -0.5 +/- 1.4 < 3.5 1.0 +/- 1.0 < 2.7 -1.5 +/- 1.4 < 2.5 15 Cs-1 34 -0.3 +/- 1.8 < 3.8 1.7 +/- 1.5

• 3.0 -0.3 +/- 1.1 < 2.0 -0.3 +/- 1.3 < 2.2 10 Cs-137 -0.5 +/- 1.9 < 2.6 1.5 +/- 1.7 < 3.2 0.3 +/- 1.3 < 2.8 1.2 +/- 1.6 < 2.5 10 Ba-La-140 -1.5 +/- 1.8 < 1.6 3.1 +/- 1.8 < 4.8 0.3 +/- 1.2 < 6.2 -0.4 +/- 1.5 < 3.8 15 Other (Ru-1 03) -1.0 +/- 2.0 < 2.2 1.4 +/- 1.3 < 3.3 -0.3 +/- 1.0 < 3.4 -0.1 +/- 1.3 <2.1 30 a "NS" = No sample; see Table 2.0, Listing of Missed Samples.

Annual All locations Mean +/- s.d. Mean +/- s.d. Mean +/- s.d.

Gross Beta 1.8 + 0.8 1-131 0.04 +/- 0.07 Co-58 -0.1 + 0.9 Cs-I 34 -0.2 +/- 0.9 Be-7 0.3 :1 7.2 Co-60 0.0 +/- 0.9 Cs-137 0.1 +/- 0.9 Mn-54 -0.2 +/- 0.9 Zn-65 -0.7 +/- 2.1 Ba-La-140 -0.3 +/- 1.8 Fe-59 -0.2 +/- 1.6 Zr-Nb-95 -0.6 +/- 1.1 Ru-103 -0.1 +/- 1.0 5-4

POINT BEACH 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. MDC 4th Qtr. MDC Lab Code ELW- 1110 ELW- 2708 ELW- 5029 ELW- 7163 Req. LLDs K

H-3 46 +/-75 < 146 105 +/-80 < 142 79 +/- 83 < 150 -19 +/-99 < 191 500 Sr-89 -0.37 +/- 0.78 < 0.90 0.68 +/- 0.62 < 0.73 0.17 +/- 0.63 < 0.71 0.26 +/- 0.63 < 0.73 5.0 Sr-90 0.66 +/-0.39 < 0.68 -0.10 +/- 0.26 < 0.60 0.11 +/- 0.29 < 0.60 0.22 +/-0.27 < 0.52 1.0 Location E-05 (Two Creeks Park)

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

Lab Code ELW- 1111 ELW- 2079 ELW- 5030 ELW- 7164 Req. LLDs H-3 149+/-80 <146 413+/-94 <142 31 +/-80 <150 -62+/-97 ' <191 500 Sr-89 -0.03 +/-0.55 < 0.70 0.27 +/- 0.66 < 0.63 0.55 +/- 0.67 < 0.80 0.61 +/- 0.68 < 0.84 5.0 Sr-90 0.36 +/-0.27 < 0.49 0.18 +/-0.30 < 0.60 -0.03 +/- 0.30 < 0.65 0.13 +/-0.27 < 0.56 1.0 Location E-06 (Coast Guard Station)

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

Lab Code NDa ELW- 2710 ELW- 5031 ELW- 7165 Req. LLDs H-3 89 +/- 79 < 142 79 +/- 83 < 150 -8 +/- 100 / < 191 500 Sr-89 0.21 +/- 0.69 < 0.76 0.17 +/- 0.65 < 0.72 0.06 +/- 0.59 < 0.68 5.0 Sr-90 -0.04 +/- 0.32 < 0.69 0.16 +/- 0.29 < 0.59 0.24 +/- 0.25 < 0.48 1.0 Location E-33 (Kewaunee)

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

Lab Code ELW- 1112 ELW- 2711 ELW- 5032 ELW- 7166 Req. LLDs H-3 244 +/-85 < 147 89 +/-79 < 142 113 +/- 85 < 150 -17 +/-99 / < 191 500 Sr-89 0.53 +/- 0.58 < 0.67 -0.30 +/- 0.80 < 0.84 0.33 +/- 0.46 < 0.67 0.26 +/- 0.61 < 0.70 5.0 Sr-90 0.29 +/- 0.27 < 0.50 0.31 +/- 0.37 <0.71 0.10 +/- 0.21 < 0.42 0.28 +/- 0.25 < 0.47 1.0 Tritium Annual Mean i s.d. 89 118 Sr-89 Annual Mean +/- s.d. 0.23 + 0.30 Sr-90 Annual Mean i s.d. 0.19 +/- 0.19 a 'ND" = No data; samples not collected due to icy conditions.

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 02-02-14 01-30-14 02-02-14 Lab Code EF- 409 EF- 411 EF- 412 Type Salmon Lake Trout Burbot Ratio (wet/dry wt.) 4.11 5.01 5.47 Gross Beta 3.60 +/- 0.07 < 0.023 3.57 +/- 0.07 < 0.022 2.23 +/- 0.05 < 0.017 0.5 K-40 1.88 +/- 0.28 2.50 +/- 0.28 2.94 +/- 0.31 Mn-54 0.005 +/- 0.006 < 0.010 0.002 +/- 0.007 < 0.007 -0.002 +/- 0.008 < 0.009 0.13 Fe-59 0.012 +/- 0.013 < 0.034 -0.007 +/- 0.013 < 0.034 -0.011 +/- 0.015 < 0.029 0.26 Co-58 0.005 +/- 0.006 < 0.012 -0.001 +/- 0.006 < 0.011 0.011 +/- 0.008 < 0.018 0.13 Co-60 0.004 +/- 0.007 < 0.011 -0.005 +/- 0.009 < 0.012 0.005 +/- 0.010 < 0.018 0.13 Zn-65 -0.010 +/- 0.014 < 0.022 -0,005 +/- 0.014 < 0.024 -0.014 +/- 0.017 < 0.034 0.26 Cs-134 0.005 +/- 0.007 < 0.013 0,004 +/- 0.007 < 0.013 -0.005 +/- 0.008 < 0.014 0.13 Cs- 137 0.050 +/- 0.017 < 0.017 0.023 +/- 0.013 < 0.015 0.096 +/- 0.027 < 0.023 0.15 Other (Ru-103) 0.000 t 0.005 < 0.011 -0.005 +/- 0.005 < 0.010 -0.003 +/- 0.007 < 0.020 0.5 Collection Date 03-16-14 03-16-14 04-14-14 Lab Code EF- 1593 EF- 1594 EF- 1596 Type Largemouth Bass Lake Trout Brown Trout Ratio (wet/dry wt.) 4.94 4.36 3.50 Gross Beta 3.78 +/- 0.07 < 0.240 3.72 +/- 0.08 < 0.025 3.95 +/- 0.09 < 0.032 0.5 K-40 3.67 +/- 0.41 - 2.77 +/- 0.37 3.33 +/- 0.38 Mn-54 0.000 +/- 0.011 < 0.015 -0.008 _ 0.006 < 0.008 0.002 +/- 0.008 < 0.014 0.13 Fe-59 -0.025 +/- 0.019 < 0.042 0.013 + 0.016 < 0.056 -0.016 +/- 0.017 < 0.016 0.26 Co-58 -0.006 +/- 0.010 < 0.019 0.005 + 0.008 < 0.019 -0.003 +/- 0.009 < 0.010 0.13 Co-60 0.005 +/- 0.010 < 0.015 0.001 + 0.009 < 0.010 -0.008 +/- 0.009 < 0.007 0.13 Zn-65 -0.009 +/- 0.020 < 0.029 0.007 + 0.017 < 0.018 -0.028 +/- 0.023 < 0.014 0.26 Cs-1 34 0.000 +/- 0.009 < 0.017 -0.004 + 0.007 < 0.015 -0.001 +/- 0.008 < 0.012 0.13 Cs-1 37 0.016 +/- 0.012 < 0.018 0.025 +/- 0.014 < 0.016 0.026 +/- 0.015 *0.013 0.15 Other (Ru-1 03) 0.007 +/- 0.008 < 0.039 -0.003 +/- 0.006 < 0.017 0.005 +/- 0.006 < 0.013 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 04-14-14 04-16-14 04-17-14 Lab Code EF- 1597 EF- 1598 EF- 1599 Type Catfish Burbot Smallmouth Bass Ratio (wet/dry wt.) 5.60 5.97 5.29 Gross Beta 3.31 +/- 0.06 < 0.019 2.13 +/- 0.05 < 0.016 3.82 +/- 0.08 < 0.025 0.5 K-40 2.40 +/- 0.32 2.09 +/- 0.36 - 2.52 +/- 2.52 Mn-54 0.001 +/- 0.007 < 0.008 -0.003 +/- 0.009 < 0.020 0.003 +/- 0.008 < 0.017 0.13 Fe-59 -0.019 +/- 0.016 < 0.030 0.022 +/- 0.018 < 0.042 -0.012 +/- 0.017 < 0.022 0.26 Co-58 -0.007 +/- 0.008 < 0.011 -0.004 +/- 0.009 < 0.019 0.005 +/- 0.008 < 0.012 0.13 Co-60 -0.006 +/- 0.009 < 0.009 0.009 +/- 0.011 < 0.015 -0.001 +/- 0.011 < 0.005 0.13 Zn-65 0.010 +/- 0.019 < 0.017 -0.025 +/- 0.022 < 0.031 -0.006 +/- 0.022 < 0.031 0.26 Cs-1 34 0.004 +/- 0.007 < 0.015 0.002 +/- 0.009 < 0.018 -0.003 +/- 0.009 < 0.017 0.13 Cs-137 0.011 +/- 0.010 < 0.018 0.039 +/- 0.018 < 0.018 0.039 +/- 0.016 < 0.012 0.15 Other (Ru-103) 0.008 +/- 0.008 < 0.023 0.005 +/- 0.009 < 0.029 0.004 +/- 0.007 < 0.018 0.5 Collection Date 05-29-14 06-07-14 07-26-14 Lab Code EF- 3089 EF- 3090 EF- 4185 Type Rainbow Trout Lake Trout Salmon Ratio (wet/dry wt.) 6.07 4.47 3.87 Gross Beta 3.33 +/- 0.05 < 0.015 3.51 +/- 0.05 < 0.014 4.08 +/- 0.08 < 0.026 0.5 K-40 2.90 +/- 0.37 2.55 +/- 0.44 3.58 +/- 0.42 Mn-54 -0.005 +/- 0.009 < 0.015 -0.006 +/- 0.010 < 0.020 -0.006 +/- 0.010 < 0.013 0.13 Fe-59 -0.016 +/- 0.013 < 0.048 0.033 +/- 0.021 < 0.086 -0.051 +/- 0.020 < 0.030 0.26 Co-58 0.000 +/- 0.007 < 0.017 -0.005 +/- 0.008 < 0.018 0.000 +/- 0.009 < 0.010 0.13 Co-60 -0.005 +/- 0.007 < 0.012 0.001 +/- 0.011 < 0.016 0.002 +/- 0.010 < 0.012 0.13 Zn-65 -0.005 +/- 0.017 < 0.035 0.003 +/- 0.019 < 0.040 0.019 +/- 0.016 < 0.009 0.26 Cs-1 34 0.010 +/- 0.008 < 0.013 -0.012 +/- 0.010 < 0.018 -0.004 +/- 0.009 < 0.014 0.13 Cs-1 37 0.021 +/- 0.012 < 0.016 0.015 +/- 0.012 < 0.019 0.007 +/- 0.013 < 0.017 0.15 Other (Ru-103) -0.015 +/- 0.006 < 0.026 0.013 +/- 0.009 < 0.043 -0.003 t 0.008 < 0.015 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 08-04-14 07-23-14 08-11-14 Lab Code EF- 4186 EF- 4187 EF- 4188 Type Brown Trout Brown Trout Lake Trout Ratio (wet/dry wt.) 3.83 4.00 4.84 Gross Beta 4.10 +/- 0.08 <0.027 3.97 +/- 0.08 < 0.026 3.43 +/- 0.07 < 0.019 0.5 K-40 2.92 +/- 0.14 3.05 +/- 0.42 - 2.82 +/- 0.38 Mn-54 -0.005 +/- 0.009 <0.013 -0.003 +/- 0.010 < 0.018 0.009 +/- 0.009 < 0.014 0.13 Fe-59 -0.015 +/- 0.017 <0.025 0.004 +/- 0.021 < 0.051 0.001 +/- 0.015 < 0.021 0.26 Co-58 -0.001 +/- 0.009 <0.011 -0.003 +/- 0.010 < 0.019 -0.007 +/- 0.007 < 0.006 0.13 Co-60 0.008 +/- 0.011 <0.019 0.006 +/- 0.012 < 0.021 0.003 +/- 0.010 < 0.013 0.13 Zn-65 0.003 +/- 0.022 < 0.020 -0.007 +/- 0.027 < 0.022 0.014 +/- 0.018 < 0.018 0.26 Cs-1 34 -0.004 +/- 0.010 < 0.014 -0.003 +/- 0.009 < 0.020 -0.003 +/- 0.009 < 0.017 0.13 Cs-137 0.025 +/- 0.012 < 0.018 0.021 +/- 0.013 < 0.021 0.041 +/- 0.018 < 0.014 0.15 Other (Ru-103) -0.006 +/- 0.008 < 0.014 -0.014 +/- 0.010 < 0.024 -0.005 +/- 0.008 < 0.011 0.5 Collection Date 08-11-14 08-16-14 Lab Code EF- 4189 EF- 6132 Annual Type Burbot Chinook Salmon Ratio (wet/dry wt.) 4.99 4.60 Mean +/- s.d.

Gross Beta 2.60 +/- 0.06 < 0.018 3.81 +/- 0.07 < 0.022 3.47 +/- 0.60 0.5 K-40 2.57 +/- 0.46 2.78 +/- 0.38 2.79 + 0.47 Mn-54 0.010 +/- 0.011 < 0.019 0.004 +/- 0.008 < 0.019 0.000 +/- 0.005 0.13 Fe-59 0.015 +/- 0.023 < 0.023 0.016 +/- 0.018 < 0.107 -0.003 +/- 0.021 0.26 Co-58 0.006 +/- 0.011 < 0.018 0.005 +/- 0.006 < 0.020 0.000 +/- 0.005 0.13 Co-60 0.007 +/- 0.013 < 0.023 0.004 +/- 0.009 < 0.014 0.002 + 0.005 0.13 Zn-65 -0.003 +/- 0.026 < 0.029 -0.019 +/- 0.018 < 0.015 -0.004 +/- 0.013 0.26 Cs-1 34 0.000 +/- 0.011 < 0.021 -0.002 +/- 0.006 < 0.014 -0.001 + 0.005 0.13 Cs-137 0.018 +/- 0.015 < 0.024 0.050 +/- 0.020 < 0.019 0.031 +/- 0.021 0.15 Other (Ru-103) 0.003 +/- 0.012 < 0.026 0.034 +/- 0.008 < 0.081 0.001 +/- 0.011 0.5 7-3

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

MDC MDC MDC Collection Date 4/16/2014 4/17/2014 4/17/2014 Lab Code ESS- 1558 ESS- 1559 ESS- 1560 LLD Location E-01 E-05 E-06 Gross Beta 10.86 +/- 0.91 < 1.04 8.33 +/- 0.83 < 0.98 7.93 +/- 0.88 < 1.06 2.0 Be-7 0.006 +/- 0.054 < 0.09 0.061 +/- 0.052 < 0.11 0.046 +/- 0.056 < 0.10 K-40 7.43 +/- 0.46 6.23 +/- 0.40 2.59 +/- 0.42 - -

Cs-134 0.000 +/- 0.006 < 0.009 -0.002 +/- 0.005 < 0.008 0.001 +/- 0.006 < 0.011 0.15 Cs-137 0.024 +/- 0.014 < 0.012 0.014 +/- 0.008 < 0.010 0.033 +/- 0.016 < 0.013 0.15 TI-208 0.041 +/- 0.023 0.040 +/- 0.012 0.085 +/- 0.017 - -

Pb-212 0.18 +/- 0.054 0.16 +/- 0.051 0.30 +/- 0.062 Bi-214 0.11 +/- 0.024 0.11 +/- 0.025 0.17 +/- 0.029 Ra-226 0.36 +/- 0.15 < 0.26 0.30 +/- 0.14 < 0.26 0.42 +/- 0.17 Ac-228 0.15 +/- 0.054 0.12 +/- 0.057 0.25 +/- 0.053 Collection Date 4/1712014 4/17/2014 Lab Code ESS- 1561 ESS- 1562 Location E-12 E-33 Gross Beta 6.54 +/- 0.78 < 0.94 9.04 +/- 0.90 < 1.07 2.0 Be-7 0.077 +/- 0.050 < 0.08 0.11 +/- 0.054 < 0.10 K-40 4.70 +/- 0.36 6.03 +/- 0.41 Cs-134 0.006 +/- 0.005 < 0.009 -0.004 +/- 0.006 < 0.009 0.15 Cs-137 0.031 +/- 0.015 < 0.012 0.015 +/- 0.009 < 0.013 0.15 TI-208 0.045 +/- 0.017 0.046 +/- 0.019 Pb-212 0.10 +/- 0.018 0.17 +/- 0.055 Bi-214 0.079 +/- 0.023 0.099 +/- 0.025 Ra-226 0.32 +/- 0.13 < 0.26 0.46 +/- 0.15 < 0.27 Ac-228 0.15 +/- 0.047 0.19 +/- 0.062 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 10/26/2014 10/26/2014 10/26/2014 Req.

Lab Code ESS- 6187 ESS- 6188 ESS- 6189 LLD Location E-01 E-05 E-06 Gross Beta 6.89 +/- 1.07 < 1.50 8.96** 1.12 < 1.47 10.08 +/- 1.25 < 1.67 2.0 Be-7 0.082 +/- 0.047 < 0.11 -0.027 +/- 0.054 < 0.14 0.026 +/- 0.049 < 0.11 K-40 4.59 +/- 0.37 - 7.56 +/- 0.47 8.14 +/- 0.48 Cs-134 0.003 +/- 0.006 < 0.011 0.001 +/- 0.006 < 0.012 0.006 +/- 0.006 < 0.012 0.15 Cs-137 0.007 +/- 0.008 -c 0.013 0.013 +/- 0.009 < 0.015 0.022 +/- 0.011 < 0.011 0.15 TI-208 0.058 +/- 0.014 - 0.047 +/- 0.017 0.036 +/- 0.010 Pb-212 0.19 +/- 0.057 0.18 +/- 0.058 0.12 +/- 0.025 Bi-214 0.16 +/- 0.027 0.13 +/- 0.027 0.093 +/- 0.026 Ra-226 0.29 +/- 0.16 0.53 +/- 0.15 < 0.28 0.48 +/- 0.14 < 0.27 Ac-228 0.19 + 0.055 0.20 +/- 0.050 0.17 +/- 0.050 Collection Date 10/31/2014 10/31/2014 Lab Code ESS- 6190 ESS- 6191 Annual Location E-12 E-33 Mean +/-s.d.

Gross Beta 7.25 +/- 1.17 < 1.68 10.63 +/- 1.22 < 1.58 2.0 8.65 +/- 1.54 Be-7 0.085 +/- 0.049 < 0.10 -0.057 + 0.058 < 0.10 0.041 +/- 0.053 K-40 4.39 +/- 0.35 8.15 +/- 0.49 - 5.98 +/- 1.88 Cs-134 0.001 +/- 0.006 < 0.010 0.002 +/- 0.007 < 0.014 0.15 0.00 + 0.00 Cs-137 0.007 +/- 0.008 < 0.010 0.024 +/- 0.012 < 0.012 0.15 0.019 +/- 0.009 TI-208 0.041 +/- 0.012 0.052 +/- 0.014 - 0.05 +/- 0.01 Pb-212 0.17 +/- 0.052 0.091 +/- 0.022 - 0.17 +/- 0.06 Bi-214 0.11 +/- 0.026 0.10 +/- 0.026 - 0.12 +/- 0.03 Ra-226 0.32 + 0.13 < 0.23 0.28 +/- 0.17 - 0.38 +/- 0.09 Ac-228 0.14 + 0.052 0.15 +/- 0.059 - 0.17 +/- 0.04 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 5/29/2014 5/29/2014 5/29/2014 Rea.

Lab Code ESO- 2433 ESO- 2434 ESO- 2435 LLD Location E-01 E-02 E-03 Gross Beta 26.48 +/- 1.08 < 0.96 30.07 +/- 1.17 < 1.06 23.00 +/- 1.02 < 0.94 2.0 Be-7 0.091 +/- 0.095 < 0.23 0.068 +/- 0.099 < 0.18 -0.052 +/- 0.096 < 0.14 K-40 15.75 +/- 0.84 - 19.32 +/- 0.90 - 14.85 +/- 0.82 - -

Cs-134 -0.001 +/- 0.012 < 0.023 -0.010 +/- 0.012 < 0.017 -0.005 +/- 0.012 < 0.023 0.15 Cs-137 0.18 +/- 0.034 < 0.025 0.12 +/- 0.035 < 0.028 0.087 +/- 0.035 < 0.027 0.15 TI-208 0.18 +/- 0.037 - 0.23 +/- 0.034 - 0.14 +/- 0.037 - -

Pb-212 0.48 +/- 0.042 - 0.75 +/- 0.12 - 0.42 +/- 0.048 - -

Bi-214 0.35 +/- 0.054 - 0.37 +/- 0.054 - 0.27 +/- 0.049 - -

Ra-226 1.25 +/- 0.44 - 1.36 +/- 0.33 - 0.67 +/- 0.30 - -

Ac-228 0.51 +/- 0.091 < 0.22 0.67 +/- 0.14 - 0.40 +/- 0.097 - -

Collection Date 5/29/2014 5/29/2014 5/29/2014 Lab Code ESO- 2436 ESO- 2438 ESO- 2439 Location E-04 E-06 E-08 Gross Beta 13.23 +/- 0.90 < 0.96 19.35 +/- 0.98 < 0.95 23.40 +/- 1.02 < 0.93 2.0 Be-7 -0.041 +/- 0.070 < 0.094 0.090 +/- 0.087 < 0.20 -0.094 +/- 0.093 < 0.19 K-40 7.08 +/- 0.52 - 11.17 +/- 0.67 - 14.79 +/- 0.81 Cs-134 -0.001 +/- 0.009 < 0.016 0.001 +/- 0.009 < 0.013 0.010 +/- 0.010 < 0.015 0.15 Cs-137 0.041 +/- 0.017 < 0.016 0.35 +/- 0.043 < 0.025 0.16 +/- 0.028

• 0.016 0.15 TI-208 0.10 +/- 0.025 - 0.079 +/- 0.026 - 0.10 +/- 0.031 Pb-212 0.25 +/- 0.077 0.22 +/- 0.036 0.31 +/- 0.097 Bi-214 0.17 +/- 0.037 - 0.14 +/- 0.038 - 0.25 +/- 0.046 Ra-226 0.67 +/- 0.20 < 0.38 0.66 +/- 0.21 < 0.43 0.51 +/- 0.28 Ac-228 0.21 +/- 0.072 - 0.30 +/- 0.081 - 0.35 +/- 0.10 Collection Date 5/29/2014 5/29/2014 Lab Code ESO- 2440 ESO- 2441 Location E-09 E-20 Gross Beta 30.63 +/- 1.18 < 1.06 28.03 +/- 1.15 < 1.07 2.0 Be-7 0.12 +/- 0.12 < 0.30 0.03 +/- 0.12 < 0.25 K-40 20.12 +/- 1.07 18.46 +/- 0.92 Cs-134 -0.003 +/- 0.013 < 0.024 -0.007 +/- 0.012 < 0.018 0.15 Cs-137 0.074 +/- 0.031 < 0.028 0.13 +/- 0.037 < 0.028 0.15 TI-208 0.22 +/- 0.046 0.20 +/- 0.037 Pb-212 0.70 +/- 0.13 0.76 +/- 0.13 Bi-214 0.49 +/- 0.070 0.40 +/- 0.063 Ra-226 0.95 +/- 0.37 0.82 +/- 0.35 Ac-228 0.61 +/- 0.15 0.70 +/- 0.14 9-1

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

MDC MDC MDC Collection Date 10/29/2014 10/29/2014 10/29/2014 Req.

Lab Code ESO- 6178 ESO- 6179 ESO- 6180 LLD Location E-01 E-02 E-03 Gross Beta 21.47 +/- 1.30 < 1.39 19.16 +/- 1.22 < 1.30 27.73 +/- 1.41 < 1.37 2.0 Be-7 0.12 +/- 0.084 < 0.18 -0.082 +/- 0.096 < 0.18 0.006 +/- 0.079 < 0.22 K-40 16.21 +/- 0.78 14.01 +/- 0.79 - 18.60 +/- 0.77 Cs-1 34 -0.017 +/- 0.010 < 0.014 0.003 +/- 0.012 < 0.018 -0.003 +/- 0.010 < 0.016 0.15 Cs-137 0.18 +/- 0.033 < 0.023 0.084 +/- 0.028 < 0.022 0.10 +/- 0.025 < 0.024 0.15 TI-208 0.19 +/- 0.034 0.16 +/- 0.029 - 0.18 +/- 0.031 Pb-212 0.55 +/- 0.038 0.44 +/- 0.040 - 0.48 +/- 0.033 Bi-214 0.53 +/- 0.051 0.45 +/- 0.057 - 0.44 +/- 0.046 Ra-226 1.21 +/- 0.40 0.69 +/- 0.31 - 1.29 +/- 0.28 Ac-228 0.62 +/- 0.10 0.57 +/- 0.099 - 0.54 +/- 0.074 Collection Date 10/29/2014 10/29/2014 10/29/2014 Lab Code ESO- 6181 ESO- 6182 ESO- 6183 Location E-04 E-06 E-08 Gross Beta 16.86 +/- 1.15 < 1.23 11.66 +/- 1.03 < 1.22 17.59 +/- 1.23 < 1.37 2.0 Be-7 0.067 +/- 0.066 < 0.14 0.069 +/- 0.061 < 0.16 0.050 +/- 0.088 < 0.15 K-40 12.82 +/- 0.64 7.83 +/- 0.47 12.80 +/- 0.72 Cs-1 34 0.000 +/- 0.009 < 0.013 0.006 +/- 0.007 < 0.011 -0.004 +/- 0.009 < 0.018 0.15 Cs-1 37 0.083 +/- 0.019 < 0.018 0.14 +/- 0.026 < 0.018 0.20 +/- 0.029 < 0.019 0.15 TI-208 0.13 +/- 0.024 0.065 +/- 0.021 0.10 +/- 0.033 Pb-212 0.34 +/- 0.028 0.25 +/- 0.066 0.34 +/- 0.094 Bi-214 0.26 +/- 0.037 0.26 +/- 0.037 0.28 +/- 0.046 Ra-226 0.77 +/- 0.24 0.39 +/- 0.16 < 0.31 0.78 +/- 0.25 < 0.46 Ac-228 0.37 +/- 0.062 0.23 +/- 0.067 0.29 +/- 0.083 Collection Date 10/29/2014 10/29/2014 Lab Code ESO- 6184 ESO- 6186 Annual E-09 E-20 Location Mean +/- s.d.

Gross Beta 34.27 +/- 1.77 < 1.65 21.88 +/- 1.54 < 1.67 22.80 +/- 6.41 2.0 Be-7 0.15 +/- 0.11 < 0.29 -0.092 +/- 0.083 < 0.15 0.031 +/- 0.08 K-40 21.07 +/- 0.89 14.19 +/- 0.70 14.94 +/- 4.07 Cs-134 -0.007 +/- 0.012 < 0.017 -0.003 +/- 0.009 < 0.015 0.019 +/- 0.09 0.15 Cs- 137 0.12 +/- 0.035 < 0.032 0.083 +/- 0.021 < 0.017 0.13 +/- 0.07 0.15 TI-208 0.16 +/- 0.037 0.16 +/- 0.028 0.15 +/- 0.05 Pb-212 0.49 +/- 0.040 0.46 +/- 0.034 0.45 +/- 0.17 Bi-214 0.51 +/- 0.054 0.39 +/- 0.042 0.35 +/- 0.12 Ra-226 1.25 +/- 0.37 0.93 +/- 0.26 0.89 +/- 0.30 Ac-228 0.58 +/- 0.11 0.57 +/- 0.11 0.47 +/- 0.16 9-2

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

MDC MDC MDC Location E-01 E-02 E-03 Collection Date 5/27/2014 5/27/2014 5/27/2014 Lab Code EG- 2323 EG- 2303 EG- 2304 Req. LLD Ratio (wet/dry) 6.24 4.49 5.33 Gross Beta 5.88 +/- 0.11 < 0.032 5.65 +/- 0.12 < 0.042 6.25 +/- 0.12 < 0.036 0.25 Be-7 0.26 +/- 0.14 0.53 +/- 0.14 0.11 +/- 0.06 < 0.12 K-40 5.18 +/- 0.40 4.84 +/- 0.41 5.44 +/- 0.41 1-131 -0.007 +/- 0.007 < 0.017 0.001 +/- 0.007 < 0.016 0.007 +/- 0.007 < 0.024 0.060 Cs-1 34 -0.005 +/- 0.007 < 0.013 -0.001 +/- 0.007 < 0.012 0.000 +/- 0.007 < 0.014 0.060 Cs-1 37 0.001 +/- 0.008 < 0.012 0.009 +/- 0.008 < 0.014 0.001 +/- 0.007 < 0.013 0.080 Other (Co-60) 0.001 +/- 0.010 < 0.014 0.006 +/- 0.008 < 0.012 0.000 +/- 0.007 < 0.009 0.060 Location E-04 E-06 E-08 Collection Date 5/27/2014 5/27/2014 5/27/2014 Lab Code EG- 2305 EG- 2306 EG- 2307 Req. LLD Ratio (wet/dry) 5.69 4.46 7.28 Gross Beta 5.70 +/- 0.11 < 0.038 4.81 +/- 0.10 < 0.031 5.57 +/- 0.11 < 0.036 0.25 Be-7 0.14 +/- 0.07 < 0.14 0.51 +/- 0.56 0.058 +/- 0.045 < 0.079 K-40 4.71 +/- 0.39 4.91 +/- 0.60 3.81 +/- 0.27 1-131 0.003 +/- 0.006 < 0.021 0.006 +/- 0.019 < 0.050 -0.003 +/- 0.005 < 0.015 0.060 Cs-134 -0.004 +/- 0.007 < 0.011 0.008 +/- 0.016 < 0.033 0.001 +/- 0.005 < 0.009 0.060 Cs-137 0.001 +/- 0.008 < 0.013 0.015 +/- 0.019 < 0.030 0.006 +/- 0.005 < 0.009 0.080 Other (Co-60) -0.004 +/- 0.009 < 0.013 0.010 +/- 0.017 < 0.024 0.002 +/- 0.005 < 0.006 0.060 Location E-09 E-20 Collection Date 5/27/2014 5/27/2014 Lab Code EG- 2308 EG- 2309 Req. LLD Ratio (wet/dry) 4.95 7.95 Gross Beta 4.30 +/- 0.11 < 0.043 3.74 +/- 0.08 < 0.028 0.25 Be-7 0.17 +/- 0.09 0.11 +/- 0.06 < 0.11 K-40 5.96 +/- 0.36 3.61 +/- 0.30 1-131 0.002 +/- 0.005 0.012 0.000 +/- 0.005 < 0.013 0.060 Cs-134 0.002 +/- 0.005 0.010 0.002 +/- 0.006 < 0.010 0.060 Cs-137 -0.001 +/- 0.006 0.008 0.005 +/- 0.007 < 0.013 0.080 Other (Co-60) -0.002 +/- 0.007 0.010 0.006 +/- 0.007 < 0.013 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 07-23-14 07-23-14 07-23-14 Lab Code EG- 3623 EG- 3624 EG- 3625 Req. LLD Ratio (wet/dry) 3.67 3.97 4.13 Gross Beta 6.84 +/- 0.18 < 0.075 6.57 +/- 0.16 < 0.059 5.71 +/- 0.14 < 0.058 0.25 Be-7 0.98 +/- 0.15 0.64 +/- 0.15 0.63 +/- 0.11 K-40 4.73 +/- 0.33 5.12 +/- 0.39 6.08 +/- 0.31 1-131 0.001 +/- 0.005 < 0.020 0.004 +/- 0.007 < 0.024 0.001 +/- 0.006 < 0.019 0.060 Cs-134 0.002 +/- 0.005 < 0.010 -0.004 +/- 0.007 < 0.013 -0.002 +/- 0.004 < 0.009 0.060 Cs-137 0.013 +/- 0.007 < 0.012 0.008 +/- 0.008 < 0.013 0.003 +/- 0.005 < 0.009 0.080 Other (Co-60) 0.000 +/- 0.007 < 0.011 -0.003 +/- 0.007 < 0.012 0.000 +/- 0.005 < 0.007 0.060 Location E-04 E-06 E-08 Collection Date 07-23-14 07-23-14 07-23-14 Lab Code EG- 3626 EG- 3627 EG- 3628 Req. LLD Ratio (wet/dry) 4.21 3.16 3.34 Gross Beta 6.95 +/- 0.16 < 0.053 4.95 +/- 0.10 < 0.031 7.37 +/- 0.15 < 0.050 0.25 Be-7 0.53 +/- 0.11 0.59 +/- 0.11 0.69 +/- 0.11 K-40 5.17 +/- 0.26 3.91 +/- 0.30 4.02 +/- 0.25 1-131 0.005 +/- 0.005 < 0.022 -0.004 +/- 0.005 < 0.015 0.009 +/- 0.004 < 0.015 0.060 Cs-134 -0.007 +/- 0.005 < 0.009 -0.003 +/- 0.005 < 0.010 0.000 +/- 0.004 < 0.008 0.060 Cs-137 0.015 +/- 0.006 < 0.013 0.009 +/- 0.007 < 0.012 0.001 +/- 0.005 < 0.010 0.080 Other (Co-60) -0.001 +/- 0.006 < 0.013 0.001 +/- 0.007 < 0.009 0.001 +/- 0.005 < 0.008 0.060 Location E-09 E-20 Collection Date 07-23-14 07-23-14 Lab Code EG- 3629 EG- 3630 Req. LLD Ratio (wet/dry) 3.43 3.56 Gross Beta 8.33 +/- 0.18 < 0.064 8.24 +/- 0.18 < 0.062 0.25 Be-7 0.67 +/- 0.11 1.15 +/- 0.15 K-40 5.45 +/- 0.29 6.19 +/- 0.34 1-131 -0.001 +/- 0.004 < 0.018 0.000 +/- 0.006 < 0.020 0.060 Cs-134 0.002 +/- 0.004 < 0.008 -0.003 +/- 0.006 < 0.010 0.060 Cs-1 37 0.001 +/- 0.005 < 0.009 0.001 +/- 0.006 < 0.010 0.080 Other (Co-60) -0.001 +/- 0.005 < 0.007 0.004 +/- 0.007 < 0.013 0.060 10-2

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 10/1/2014 10/1/2014 10/1/2014 Lab Code EG- 5254 EG- 5255 EG- 5256 Req. LLD Ratio (wet/dry) 3.00 3.46 2.80 Gross Beta 7.31 +/- 0.19 < 0.085 4.51 +/- 0.11 < 0.044 6.71 +/- 0.20 < 0.097 0.25 Be-7 4.10 +/- 0.32 3.33 +/- 0.30 4.15 +/- 0.36 K-40 5.67 +/- 0.49 4.18 +/- 0.43 5.40 +/- 0.50 1-131 0.020 +/- 0.010 < 0.040 -0.010 +/- 0.008 < 0.026 0.005 +/- 0.012 < 0.029 0.060 Cs-134 0.001 +/- 0.010 < 0.019 -0.003 +/- 0.007 < 0.014 0.014 +/- 0.009 < 0.018 0.060 Cs-137 0.007 +/- 0.011 < 0.020 -0.001 +/- 0.009 < 0.015 0.000 +/- 0.011 < 0.020 0.080 Other (Co-60) 0.006 +/- 0.012 < 0.014 0.004 +/- 0.010 < 0.015 -0.002 +/- 0.010 < 0.012 0.060 Location E-04 E-06 E-08 Collection Date 10/1/2014 10/1/2014 10/1/2014 Lab Code EG- 5257 EG- 5259 EG- 5260 Req. LLD Ratio (wet/dry) 3.49 2.72 2.95 Gross Beta 4.59 +/- 0.15 < 0.070 4.43 +/- 0.11 < 0.042 3.36 +/- 0.11 < 0.063 0.25 Be-7 3.11 +/- 0.23 3.04 +/- 0.32 6.01 +/- 0.37 K-40 3.25 +/- 0.30 3.79 +/- 0.46 1.77 +/- 0.30 1-131 -0.015 +/- 0.006 < 0.015 -0.006 +/- 0.010 < 0.024 0.002 +/- 0.009 < 0.032 0.060 Cs-1 34 -0.001 +/- 0.006 < 0.010 -0.003 +/- 0.010 < 0.019 0.001 +/- 0.009

• 0.014 0.060 Cs-137 -0.003 +/- 0.007 < 0.012 0.037 +/- 0.020 < 0.021 0.002 +/- 0.008 < 0.015 0.080 Other (Co-60) 0.006 +/- 0.006 < 0.010 -0.001 +/- 0.011 < 0.008 0.000 +/- 0.010 < 0.013 0.060 Location E-09 E-20 Collection Date 10/1/2014 10/1/2014 Lab Code EG- 5261 EG- 5262 Req. LLD Ratio (wet/dry) 2.46 3.02 Gross Beta 6.12 +/- 0.20 < 0.098 9.55 +/- 0.21 < 0.076 0.25 Be-7 5.75 +/- 0.34 3.64 +/- 0.29 K-40 4.53 +/- 0.41 6.12 +/- 0.47 1-131 0.011 +/- 0.008 < 0.030 0.000 +/- 0.008 < 0.032 0.060 Cs-134 0.000 +/- 0.007 < 0.013 -0.005 +/- 0.008 < 0.014 0.060 Cs-137 0.003 +/- 0.009 < 0.016 0.002 +/- 0.008 < 0.016 0.080 Other (Co-60) 0.007 +/- 0.009 < 0.011 -0.001 +/- 0.010 < 0.009 0.060 Beta Annual Mean +/- s.d. 5.98 +/- 1.53 Be-7 Annual Mean +/- s.d. 1.70 +/- 1.89 K-40 Annual Mean +/- s.d. 4.74 +/- 1.06 1-131 Annual Mean +/- s.d. 0.001 +/- 0.007 Cs-134 Annual Mean +/- s.d. 0.000 +/- 0.004 Cs-1 37 Annual Mean +/- s.d. 0.006 +/- 0.008 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 07-24-14 MDC 07-24-14 MDC Req.

Lab Code ESL- 3617 ESL- 3618 LLD Location E-05 E-12 Ratio (wet wt./dry wt.) 5.11 5.96 Gross Beta 3.57 +/- 0.13 < 0.11 3.73 +/- 0.13 < 0.11 0.25 Be-7 0.85 +/- 0.07 0.57 +/- 0.07 K-40 3.44 +/- 0.11 1.78 +/- 0.11 Co-58 0.002 +/- 0.002 < 0.005 0.000 +/- 0.002 < 0.006 0.25 Co-60 0.005 +/- 0.003 < 0.006 0.001 +/- 0.003 < 0.007 0.25 Cs-134 0.000 +/- 0.002 < 0.004 -0.001 +/- 0.003 < 0.005 0.25 Cs-137 0.018 +/- 0.004 < 0.009 0.010 +/- 0.003 < 0.007 0.25 Collection Date 08-05-14 08-06-14 Lab Code ESL- 4027 ESL- 4028 Location E-05 E-12 Ratio (wet wt./dry wt.) 6.88 2.83 Gross Beta 2.33 +/- 0.11 < 0.11 6.43 +/- 0.25 < 0.22 0.25 Be-7 0.49 +/- 0.09 0.34 +/- 0.06 K-40 1.98 +/- 0.11 4.50 +/- 0.10 Co-58 0.001 +/- 0.003 < 0.007 0.001 +/- 0.002 < 0.004 0.25 Co-60 0.000 +/- 0.003 < 0.007 0.003 +/- 0.002 < 0.004 0.25 Cs-134 0.003 +/- 0.003 < 0.005 -0.003 +/- 0.002 < 0.003 0.25 Cs-137 0.013 +/- 0.006 < 0.007 0.021 +/- 0.003 < 0.003 0.25 Collection Date 10-08-14 10-08-14 Lab Code ESL- 5449 ESL- 5450 Annual Location E-05 E-12 Mean +/- s.d.

Ratio (wet wt./dry wt.) 10.11 6.67 Gross Beta 1.65 +/- 0.05 < 0.04 2.79 +/- 0.12 < 0.10 0.25 3.42 +/- 1.67 Be-7 0.21 +/- 0.09 0.52 +/- 0.19 0.49 +/- 0.22 K-40 4.13 +/- 0.16 2.89 +/- 0.28 3.12 +/- 1.11 Co-58 -0.001 +/- 0.003 < 0.007 -0.007 +/- 0.007 < 0.017 0.25 -0.001 +/- 0.003 Co-60 -0.001 +/- 0.003 < 0.007 0.000 +/- 0.008 < 0.012 0.25 0.001 +/- 0.002 Cs-134 -0.007 +/- 0.003 < 0.005 0.002 +/- 0.008 < 0.015 0.25 -0.001 +/- 0.004 Cs-1 37 0.007 +/- 0.004 < 0.006 0.023 +/- 0.009 < 0.018 0.25 0.015 +/- 0.006 11-1

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation a Po LLD/7days: < 1mRJTLD 1st. Quarter, 2014 Date Annealed: 12-10-13 Days in the field 88 Date Placed: 01-03-14 Days from Annealing Date Removed: 04-01-14 to Readout: 119 Date Read: 04-08-14 Days in mR/Stnd Qtr Location Field Total mR Net mR (91 days) Net mR per 7 days Indicator E-1 88 14.8 +/- 0.6 9.3 +/- 0.9 9.6 +/- 0.9 0.74 +/- 0.07 E-2 88 21.7 +/- 0.4 16.2 +/- 0.6 16.8 +/- 0.6 1.29 +/- 0.04 E-3 88 20.1 +/- 1.4 14.6 +/- 1.4 15.1 +/- 1.5 1.16 +/- 0.11 E-4 88 17.7 +/- 2.0 12.2 +/- 2.0 12.6 +/- 2.1 0.97 +/- 0.16 E-5 88 18.2 +/- 1.1 12.7 +/- 1.2 13.1 +/- 1.2 1.01 +/-_0.09 E-6 88 16.6 +/- 1.0 11.1 +/- 1.1 11.5 +/- 1.1 0.88 +/--0.09 E-7 88 15.8 +/- 0.5 10.3 +/- 0.6 10.6 +/- 0.7 0.82 +/- 0.05 E-8 88 21.6 +/- 1.0 16.1 +/- 1.1 16.7 +/- 1.1 1.28 +/- 0.09 E-9 88 21.5 +/- 0.6 15.9 +/- 0.7 16.5 +/- 0.7 1.27 +/- 0.05 E-12 88 18.2 +/- 1.2 12.7 +/- 1.3 13.1 +/- 1.3 1.01 +/- 0.10 E-14 88 18.4 +/- 0.3 12.9 +/- 0.5 13.3 +/- 0.5 1.02 +/- 0.04 E-15 88 18.5 +/-0.2 13.0 +/-_0.4 13.4 +/-_0.4 1.03 +/- 0.03 E-16 88 18.5 +/- 0.1 13.0 +/- 0.4 13.4 +/- 0.4 1.03 +/- 0.03 E-16B 88 14.2 +/- 0.5 8.7 +/- 0.6 10.5 +/- 0.7 0.81 +/- 0.05 b E-17 88 20.3 +/-0.5 14.8 +/-_0.6 15.3 +/-_0.6 1.18 +/- 0.05 E-18 88 17.9 +/- 1.0 12.4 +/- 1.1 12.8 +/- 1.1 0.99 +/- 0.09 E-22 88 17.4 +/- 1.4 11.9 +/- 1.5 12.3 +/- 1.5 0.95 +/- 0.12 E-23 88 16.8 +/- 0.7 11.3 +/- 0.8 11.7 +/- 0.8 0.90 +/- 0.06 E-24 88 16.5 +/- 0.7 10.9 +/- 0.8 11.3 +/- 0.8 0.87 +/- 0.06 E-25 88 16.4 +/- 0.8 10.9 +/- 0.9 11.3 +/- 0.9 0.87 +/- 0.07 E-26 88 16.8 +/- 1.1 11.2 +/- 1.1 11.6 +/- 1.2 0.89 +/- 0.09 E-26B 88 13.1 +/-0.4 7.6 +/-_0.5 9.2 +/-_0.6 0.71 +/-_0.05 b E-27 88 20.3 +/- 0.6 14.7 +/- 0.7 15.2 +/- 0.7 1.17 +/- 0.06 E-28 88 14.8 +/- 0.8 9.3 +/- 0.9 9.6 +/- 0.9 0.74 +/- 0.07 E-29 88 15.5 +/- 1.3 10.0 +/- 1.4 10.3 +/- 1.4 0.79 +/--0.11 E-30 88 17.4 +/- 1.0 11.9 +/- 1.1 12.3 +/- 1.1 0.94 +/-_0.08 E-31 88 19.2 +/- 0.7 13.6 +/- 0.8 14.1 +/- 0.8 1.09 +/- 0.06 E-32 88 18.8 +/- 0.5 13.3 +/- 0.6 13.8 +/- 0.6 1.06 +/- 0.05 E-38 88 16.4 +/- 0.9 10.9 +/- 1.0 11.3 +/- 1.0 0.87 +/- 0.08 E-39 88 17.9 +/- 1.0 12.4 +/- 1.1 12.8 +/- 1.1 0.98 +/- 0.09 E-41 88 14.6 +/- 0.8 9.1 +/- 0.9 9.4 +/- 0.9 0.72 +/- 0.07 E-42 88 18.9 +/- 0.7 13.3 +/- 0.8 13.8 +/- 0.8 1.06 +/- 0.06 E-43 88 14.8 +/- 1.2 9.3 +/- 1.2 9.6 +/- 1.3 0.74 +/- 0.10 Control E-20 88 21.8 +/- 1.8 16.3 +/- 1.8 16.8 +/- 1.9 1.30 +/- 0.14 Mean+/-s.d. 17.7 +/-_2.3 12.2 +/-_2.3 12.6 +/-_2.4 0.97 +/- 0.16 In-Transit Exposure Date Annealed Date Read ITC-1 ITC-2 12-10-13 01-15-14 6.6 +/- 0.3 6.7 +/- 0.4 03-11-14 04-08-14 5.1 +/- 0.3 4.5 +/- 0.4 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.

b TLDs in field 75 days; placed 01-16-14.

12-1

POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation" LLD/7days: < 1mRITLD 2nd Quarter, 2014 Date Annealed: 03-11-14 Days in the field 93 Date Placed: 04-01-14 Days from Annealing Date Removed: 07-03-14 to Readout: 122 Date Read: 07-11-14 Days in mR/Stnd Qtr Location Field Total mR Net mR (91 days) Net mR per 7 days Indicator E-1 93 15.9 +/- 0.9 11.3 +/- 1.1 11.1 +/-1.1 0.85 +/- 0.08 E-2 93 19.1 +/- 1.1 14.5 +/- 1.3 14.2 +/- 1.3 1.09 +/- 0.10 E-3 93 19.3 +/- 1.4 14.7 +/- 1.5 14.4 +/- 1.5 1.11 +/- 0.12 E-4 93 18.4 +/- 0.6 13.9 +/- 0.9 13.6 +/- 0.9 1.04 +/- 0.07 E-5 93 19.4 +/- 0.5 14.8 +/- 0.9 14.5 +/- 0.8 1.12 +/- 0.06 E-6 93 16.0 +/- 0.7 11.5 +/- 1.0 11.2 +/- 0.9 0.86 +/- 0.07 E-7 93 17.1 +/- 0.2 12.5 +/- 0.7 12.2 +/- 0.7 0.94 +/- 0.05 E-8 93 15.8 +/- 0.7 11.3 +/-0.9 11.0 +/-0.9 0.85 +/- 0.07 E-9 93 19.3 +/- 0.9 14.7 1.1 14.4 +/- 1.1 1.11 +/- 0.08 E-112 93 16.2 +/- 0.8 11.6 +/- 1.0 11.4 +/- 1.0 0.88 +/- 0.08 E-14 93 19.9 +/- 1.7 15.3 +/- 1.8 14.9 +/- 1.8 1.15 +/- 0.14 E-15 93 22.5 +/- 1.7 17.9 + 1.8 17.5 +/- 1.8 1.35 +/- 0.14 E-16 93 21.4 +/- 0.6 16.8 + 0.9 16.5 +/- 0.9 1.27 +/- 0.07 E-16B 93 19.5 +/- 0.9 14.9 +/- 1.1 14.6 +/- 1.1 1.12 +/- 0.09 E-1 7 93 17.8 +/- 1.1 13.2 +/- 1.3 12.9 +/- 1.3 0.99 +/- 0.10 E-1 8 93 24.5 +/- 0.8 19.9 +/- 1.1 19.5 +/- 1.0 1.50 +/- 0.08 E-22 93 21.3 +/- 0.9 16.7 +/- 1.1 16.3 +/- 1.1 1.26 +/- 0.08 E-23 93 22.8 +/- 0.6 18.2 +/- 0.9 17.8 +/-0.9 1.37 +/- 0.07 E-24 93 18.1 +/- 0.5 13.5 +/- 0.8 13.2 +/- 0.8 1.02 +/- 0.06 E-25 93 22.4 +/- 0.5 17.8 +/- 0.8 17.4 +/- 0.8 1.34 +/- 0.06 E-26 93 17.5 +/- 1.3 12.9 +/- 1.5 12.7 +/- 1.4 0.97 +/- 0.11 E-26B 93 17.2 +/- 0.3 12.6 +/- 0.7 12.3 +/- 0.7 0.95 +/- 0.05 E-27 93 22.2 +/- 0.8 17.6 +/- 1.0 17.2 +/- 1.0 1.32 +/- 0.08 E-28 93 15.7 +/- 0.2 11.2 +/-0.7 10.9 +/- 0.7 0.84 +/- 0.05 E-29 93 15.1 +/- 0.7 10.5 +/- 1.0 10.3 +/- 0.9 0.79 +/- 0.07 E-30 93 17.7 +/- 0.6 13.1 +/- 0.9 12.8 +/- 0.9 0.99 +/- 0.07 E-31 93 22.8 +/- 1.9 18.3 +/- 2.0 17.9 +/- 2.0 1.38 +/- 0.15 E-32 93 22.3 +/- 0.2 17.7 +/- 0.7 17.3 +/- 0.7 1.33 +/- 0.05 E-38 93 19.3 +/- 0.5 14.7 +/- 0.8 14.4 +/- 0.8 1.11 +/- 0.06 E-39 93 19.4 +/- 0.5 14.8 +/- 0.8 14.5 +/- 0.8 1.12 +/- 0.06 E-41 93 18.0 +/- 0.5 13.4 +/- 0.8 13.1 +/- 0.8 1.01 +/- 0.06 E-42 93 21.2 +/- 0.5 16.6 +/- 0.9 16.2 +/- 0.8 1.25 +/- 0.06 E-43 93 20.0 +/- 0.9 15.5 +/- 1.1 15.1 +/- 1.1 1.16 +/- 0.08 Control E-20 92 19.8 +/- 1.5 15.2 +/- 1.6 15.0 +/- 1.6 1.15 +/- 0.12 Mean+/-s.d. 19.3 +/- 2.4 14.7 +/- 2.4 14.4 +/-2.4 1.11 +/- 0.18 In-Transit Exposure Date Annealed Date Read ITC-1 ITC-2 03-11-14 04-08-14 5.1 +/-0.3 4.5 +/- 0.4 06-13-14 07-11-14 4.2 +/- 0.3 4.5 +/-0.3 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.

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POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation a LLD/7days: <IlmR/TLD 3rd Quarter, 2014 Date Annealed: 06-13-14 Days in the field 93 Date Placed: 07-03-14 Days from Annealing Date Removed: 10-04-14 to Readout: 122 Date Read: 10-13-14 Days in mR/Stnd Qtr Location Field Total mR Net mR (91 days) Net mR per 7 days Indicator E-1 93 16.8 + 0.7 12.8 +/--0.9 12.5 +/- 0.9 0.96 +/- 0.07 E-2 93 21.0 -0.1 17.0 +/- 0.6 16.6 +/- 0.6 1.28 +/- 0.04 E-3 93 22.7 + 0.4 18.7 +/- 0.7 18.3 +/- 0.7 1.41 +/- 0.05 E-4 93 17.6 +/- 1.6 13.6 +/- 1.7 13.3 +/- 1.7 1.02 +/-0.13 E-5 93 19.1 +/-1.2 15.1 +/- 1.4 14.8 +/- 1.3 1.14 +/- 0.10 E-6 93 16.3 +/- 0.9 12.3 +/- 1.0 12.0 +/- 1.0 0.92 +/- 0.08 E-7 93 17.1 +/- 0.4 13.0 +/-0.7 12.7 +/- 0.7 0.98 +/- 0.05 E-8 93 18.4 +/- 1.5 14.4 +/- 1.6 14.1 +/- 1.6 1.08 +/- 0.12 E-9 93 22.5 t 1.3 18.5 +/- 1.4 18.1 +/- 1.4 1.39 +/- 0.10 E-12 93 15.3 +/- 0.8 11.2 +/- 1.0 11.0 +/- 1.0 0.85 +/- 0.07 E-1 4 93 19.4 +/- 1.4 15.4 +/- 1.5 15.0 +/- 1.5 1.16 +/- 0.11 E-1 5 93 21.6 +/- 0.4 17.6 +/- 0.7 17.2 +/--0.7 1.32 +/- 0.05 E-16 93 19.9 +/- 0.5 15.9 +/- 0.7 15.5 +/-0.7 1.19 +/- 0.05 E-16B 93 21.5 +/- 0.3 17.5 +/- 0.6 17.1 +/-0.6 1.31 +/- 0.05 E-17 93 20.0 +/- 1.1 16.0 +/- 1.2 15.6 +/- 1.2 1.20 +/- 0.09 E-18 93 22.3 +/- 1.1 18.3 +/- 1.2 17.9 +/- 1.2 1.38 +/- 0.09 E-22 93 20.8 +/- 1.5 16.8 1 1.6 16.4 +/- 1.6 1.26 +/- 0.12 E-23 93 20.6 +/- 0.7 16.6 +/- 0.9 16.3 +/- 0.9 1.25 +/- 0.07 E-24 93 18.7 +/- 0.6 14.7 +/- 0.8 14.4 +/- 0.8 1.10 +/-0.06 E-25 93 18.3 +/- 0.4 14.3 +/- 0.7 14.0 +/- 0.7 1.07 +/- 0.05 E-26 93 17.0 +/- 0,9 13.0 +/- 1.1 12.7 +/- 1.1 0.98 +/- 0.08 E-26B 93 19.4 +/- 0.7 15.4 +/--0.9 15.0 +/- 0.8 1.16 +/- 0.07 E-27 93 21.4 +/- 0.4 17.4 +/- 0.7 17.0 +/- 0.7 1.31 +/- 0.05 E-28 93 13.5 +/- 0.6 9.5 +/- 0.8 9.3 +/- 0.8 0.71 +/- 0.06 E-29 93 14.5 +/- 1.1 10.5 + 1.2 10.3 +/- 1.2 0.79 +/- 0.09 E-30 93 17.3 +/- 1.0 13.3 +/- 1.2 13.0 +/- 1.1 1.00 +/- 0.09 E-31 93 20.8 +/- 0.5 16.8 +/- 0.7 16.4 +/- 0.7 1.26 +/- 0.05 E-32 93 21.9 +/- 0.7 17.8 +/- 0.9 17.5 +/--0.9 1.34 +/- 0.07 E-38 93 18.3 +/- 0.9 14.3 +/- 1.0 13.9 +/- 1.0 1.07 +/- 0.08 E-39 93 19.9 +/- 1.2 15.9 +/- 1.3 15.5 +/- 1.3 1.20 +/- 0.10 E-41 93 19.1 +/-0.9 15.1 +/- 1.1 14.8 +/- 1.0 1.14 +/- 0.08 E-42 93 24.1 +/- 0.9 20.1 +/- 1.1 19.6 +/-1.0 1.51 +/- 0.08 E-43 93 20.8 +/- 1.2 16.8 +/- 1.4 16.4 +/- 1.3 1.26 +/- 0.10 Control E-20 93 18.6 +/- 1.3 14.6 +/- 1.4 14.3 +/-1.4 1.10 +/- 0.11 Mean+/-s.d. 19.3 +/- 24 15.3 +/- 2.4 15.0 +/-2.4 1,15 +/- 0.18 In-Transit Exposure Date Annealed Date Read ITC-1 ITC-2 06-13-14 07-11-14 4.2 +/-0.3 4.5 +/-0.3 09-16-14 10-14-14 4.0 +/- 0.2 3.4 +/-0.3

' 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.

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POINT BEACH NUCLEAR PLANT Table 12. Ambient Gamma Radiation a LLDf7days: < lmRITLD 4th Quarter, 2014 Date Annealed: 09-16-14 Days in the field 90 Date Placed: 10-04-14 Days from Annealing Date Removed: 01-02-15 to Readout: 113 Date Read: 01-07-15 Days in mR/Stnd Qtr Location Field Total mR Net mR (91 days) Net mR per 7 days Indicator E-1 90 14.2 +/- 1.1 9.9 +/- 1.3 10.0 +/- 1.3 0.77 +/- 0.10 E-2 90 18.6 +/- 0.9 14.4 +/- 1.1 14.5 +/- 1.1 1.12 +/- 0.09 E-3 90 20.2 +/- 1.0 16.0 +/- 1.2 16.2 +/- 1.2 1.24 +/- 0.09 E-4 90 17.4 +/- 0.7 13.1 +/-0.9 13.3 +/- 1.0 1.02 +/- 0.07 E-5 90 18.5 +/-0 .5 14.3 +/-0.8 14.4 +/- 0.8 1.11 +/- 0.06 E-6 90 15.2 +/- 0.5 11.0 +/--0.8 11.1 +/-0.8 0.85 +/- 0.06 E-7 90 16.2 +/- 0.2 12.0 +/- 0.7 12.1 +/-0.7 0.93 +/- 0.05 E-8 90 16.7 +/- 0.8 12.5 +/- 1.0 12.6 +/- 1.1 0.97 +/- 0.08 E-9 90 18.1 +/-_0.8 13.9 +/- 1.0 14.0 +/- 1.0 1.08 +/- 0.08 E-12 90 14.4 +/- 0.6 10.1 +/- 0.8 10.2 +/- 0.8 0.79 +/- 0.06 E-14 90 18.3 +/- 1.2 14.1 +/- 1.4 14.2 +/- 1.4 1.09 +/- 0.11 E-1 5 90 20.9 +/- 1.6 16.7 +/- 1.7 16.9 +/- 1.7 1.30 +/- 0.13 E-16 90 20.2 +/- 0.8 16.0 +/- 0.9 16.2 +/- 0.9 1.24 +/- 0.07 E-16B 90 17.1 +/-0.2 12.8 +/- 0.6 13.0 +/- 0.6 1.00 +/- 0.05 E-1 7 90 19.6 +/-0.9 15.4 +/- 1.1 15.5 +/-1.1 1.20 +/- 0.08 E-18 90 22.3 +/- 0.6 18.0 +/- 0.9 18.2 +/- 0.9 1.40 +/- 0.07 E-22 90 19.3 +/-0.7 15.1 +/- 0.9 15.2 +/- 0.9 1.17 +/--0.07 E-23 90 21.3 +/-0.6 17.0 +/- 0.9 17.2 +/-0.9 1.33 +/- 0.07 E-24 90 17.0 +/-0.3 12.8 +/- 0.7 12.9 +/-_0.7 0.99 +/- 0.05 E-25 90 20.5 +/- 0.3 16.2 +/- 0.7 16.4 +/-0.7 1.26 +/- 0.05 E-26 90 15.1 +/-0.7 10.8 +/-0.9 10.9 +/-0.9 0.84 +/- 0.07 E-26B 90 16.2 +/- 0.2 12.0 +/- 0.6 12.1 +/-0.7 0.93 +/- 0.05 E-27 90 19.8 +/- 0.7 15.6 +/- 0.9 15.7 +/-0.9 1.21 +/- 0.07 E-28 90 14.4 +/- 0.3 10.1 +/-_0.7 10.2 +/- 0.7 0.79 +/- 0.05 E-29 90 14.4 +/- 0.7 10.1 +/-1.0 10.2 +/- 1.0 0.79 +/- 0.07 E-30 90 16.5 +/- 0.4 12.3 +/-0.7 12.4 +/- 0.7 0.95 +/- 0.06 E-31 90 20.5 +/- 1.6 16.2 +/- 1.7 16.4 +/- 1.7 1.26 +/-0.13 E-32 90 20.3 +/- 0.3 16.0 +/-0.7 16.2 +/- 0.7 1.24 +/- 0.05 E-38 90 17.5 +/- 0.1 13.3 +/-0.6 13.4 +/-0.6 1.03 +/- 0.05 E-39 9o 18.0 +/- 0.7 13.7 +/-1.0 13.9 +/- 1.0 1.07 +/- 0.07 E-41 90 15.9 +/- 0.2 11.6 +/-0.7 11.8 +/-0.7 0.91 +/- 0.05 E-42 90 19.1 +/-0.4 14.9 +/- 0.8 15.0 +/--0.8 1.16 +/- 0.06 E-43 90 18.7 + 0.7 14.5 +/- 0.9 14.6 +/- 0.9 1.13 +/- 0.07 Control E-20 90 17.8 +/- 1.2 13.6 +/- 1.4 13.7 +/- 1.4 1.06 +/- 0.11 Mean_+s.d. 20.1 +/- 1.5 13.7 +/- 2.2 19.7 +/-1.5 1.07 +/- 0.17 In-Transit Exposure Date Annealed Date Read ITC-1 ITC-2 09-16-14 10-14-14 4.0 +/-0.2 3.4 +/- 0.3 12-11-14 01-07-15 4.6 +/-0.4 5.0 +/- 0.3 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.

Annual Indicator Meants.d. 18.5 +/- 2.5 13.9 +/- 2.6 13.9 +/- 2.5 1.1 +/- 0.2 Annual Control Mean+/-s.d. 19.5 +/- 1.7 14.9 +/- 1.1 15.0 +/- 1.3 1.2 +/- 0.1 Annual Indicator/Control Mean+/-s.d. 18.5 +/-2.5 13.9 +/-2.6 13.9 +/-2.5 1.1 +/-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 Collection Date Lab Code Tritium Moc Date Lab Code Tritium MDC 01-22-14 NSa 01-22-14 NSa 02-26-14 NSa 02-26-14 NSa 03-27-14 NSa 03-27-14 EWW- 1193 230 +/- 86 < 143 04-30-14 EWW-1858 117 +/- 76 < 145 04-30-14 EWW-1859 254 +/- 83 <145 05-29-14 EWW- 2366 101 +/- 77 < 143 05-29-14 EWW- 2367 246 +/- 84 < 143 06-26-14 EWW- 2994 86 +/- 79 < 142 06-26-14 EWW- 2995 266 + 68 < 142 07-24-14 EWW- 3653 98 +/- 78 < 138 07-24-14 EWW- 3654 110 +/- 78 < 138 08-28-14 EWW- 4514 230 +/- 94 < 155 08-28-14 EWW- 4515 168 +/- 91 < 155 10-01-14 EWW- 5273 119 +/- 84 < 156 10-01-14 EWW- 5274 133 +/- 85 < 156 10-26-14 EWW-6173 14 +/- 88 < 176 10-26-14 EWW-6174 165 +/- 93 < 176 11-25-14 NS' 11-25-14 EWW- 6672 148 +/- 106 < 186 12-30-14 EWW- 7200 95 + 93 < 169 12-30-14 NSO Mean +/- s.d. 108 +/-59 Mean +/- s.d. 191 +/- 58 Sample ID GW-03 GW-17 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-22-14 NSa 01-22-14 NS8 02-26-14 NSa 02-26-14 NSa 03-27-14 NSa 03-27-14 NSa 04-30-14 EWW- 1860 154 +/- 78 < 145 04-30-14 EWW- 1862 254 +/- 83 < 145 05-29-14 EWW- 2368 65 +/- 75 < 143 05-29-14 NSb 06-26-14 EWW- 2996 105 +/- 80 < 142 06-26-14 EWW- 2998 231 +/- 87 < 142 07-24-14 EWW- 3655 71 +/- 77 < 138 07-24-14 EWW- 3657 110 +/- 78 < 138 08-28-14 EWW- 4516 98 +/- 87 < 155 08-28-14 NSb 10-01-14 EWW- 5275 29 +/- 79 < 156 10-01-14 EWW-5277 167 +/--87 < 156 10-26-14 EWW-6175 49 +/- 89 < 176 10-26-14 EWW-6177 190 +/- 94 < 176 11-25-14 EWW-6673 18 +/- 99 < 186 11-25-14 EWW-6675 178 +/- 108 < 186 12-30-14 EWW- 7201 102 +/- 93 < 169 12-30-14 EWW- 7203 233 +/- 98 < 169 Mean +/- s.d. 77 +/- 42 Mean +/- s.d. 195 +/- 49 Wells Sample ID GW-04 (EIC Well)

Collection Date Lab Code Tritium MDC 01-22-14 EWW-248 -19 +/- 79 < 151 02-26-14 EWW-722 16 +/- 74 < 139 03-27-14 EWW- 1194 -30 +/- 73 < 143 04-30-14 EWW-1861 17 +/- 71 < 145 05-29-14 EWW- 2369 45 +/- 73 < 143 06-26-14 EWW-2997 68 +/- 78 < 142 07-24-14 EWW- 3656 55 +/- 76 < 138 08-28-14 EWW- 4517 48 +/- 84 < 155 10-01-14 EWW-5276 -5 +/- 77 < 156 10-26-14 EWW-6176 -39 +/- 85 < 175 11-25-14 EWW- 6674 -54 +/- 94 < 186 12-30-14 EWW-7202 99 +/- 93 < 169 Mean +/- s.d. 17 +/- 47 aWater frozen.

b No sample received.

13-1

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

Units = pCi/L Beach Drains Sample ID S-1 S-3 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-10-14 NFa 01-10-14 NFa 02-10-14 NFa 02-10-14 NF8 03-10-14 NFa 03-10-14 NFa 04-09-14 EWW- 1440 339 +/- 92 < 143 04-09-14 EWW- 1441 333 +/- 91

• 143 05-08-14 EWW- 2033 245 +/- 82 144 05-08-14 EWW- 2034 261 +/- 83 < 144 06-05-14 EWW- 2588 207 +/- 81 140 06-05-14 EWW- 2589 228 +/- 82 < 140 06-30-14 EWW- 3110 203 +/- 81 142 06-30-14 EWW- 3111 287 +/- 85 < 142 08-05-14 EWW- 4025 256 +/- 110 193 08-05-14 EWW- 4026 332 +/- 114 < 193 09-11-14 EWW- 4798 110 +/- 86 152 09-11-14 EWW- 4799 235 +/- 92 < 152 10-08-14 EWW- 5446 73 +/- 82 158 10-08-14 EWW- 5447 252 +/- 92 < 158 11-05-14 EWW- 6337 155 +/- 117 179 11-05-14 EWW- 6338 255 +/- 122 < 179 12-11-14 EWW- 6983 195 +/- 100 177 12-11-14 EWW- 6985 237 t 102 < 177 Mean +/- s.d. 198 +/- 80 Mean +/- s.d. 269 +/- 40 Samole ID S-7 S-8 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-10-14 NF8 01-10-14 NFa 02-10-14 NF8 02-10-14 NF8 03-10-14 NF8 03-10-14 NFa 8

04-09-14 NF 04-09-14 NP8 05-08-14 NFO 05-08-14 NF" 06-05-14 NFO 06-05-14 NFO 06-30-14 NFa 06-30-14 NFE 08-05-14 NFa 08-05-14 NFO 09-11-14 NF2 09-11-14 NF8 8

10-08-14 NFa 10-08-14 NF 11-05-14 NFO8 11-05-14 NFE NF 12-11-14 NFa 12-11-14 Mean +/- s.d. Mean +/- s.d.

Sample ID S-9 S-10 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-10-14 NFa 01-10-14 NF8 02-10-14 NFa 02-10-14 NFa 03-10-14 NF88 03-10-14 NFO 04-09-14 NF 04-09-14 NFa 05-08-14 NF8 05-08-14 NFa 06-05-14 NFO 06-05-14 NFa 06-30-14 NFa 06-30-14 NF8 08-05-14 NF8 08-05-14 NFE 09-11-14 NF 09-11-14 NFa 10-08-14 NFa 10-08-14 NFE 11-05-14 NF8 11-05-14 NFE 12-11-14 NF 12-11-14 NF Mean +/- s.d. Mean +/- s.d.

"NF" = No flow.

13-2

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

Units = pCi/L Beach Drains (cont.)

Sample ID S-11 EX-SSD-N Collection Date Lab Code Tritium MDC 01-10-14 NFa 10-08-14 EWW- 5448 131 + 86 < 158 02-10-14 NFa 03-10-14 NFO 04-09-14 EWW- 1442 310 +/- 90 < 143 05-08-14 EWV- 2035 157 +/- 78 < 140 06-05-14 EWW- 2590 98 +/- 75 < 140 06-30-14 NFa 08-05-14 NFO 09-11-14 NFa 10-08-14 NFa 11-05-14 NFO 12-11-14 NFa Mean +/- s.d. 188 +/- 110 Sample ID U2 Facade Subsurface Drain Sump Collection Collection Date Lab Code Date Lab Code Trtium MDC Tritium MDC 02-03-14 EW- 420 657 +/- 101 < 144 02-28-14 EW- 863 697 +/- 107 < 146 04-05-14 EW- 3131 1029 +/- 112 < 136 05-06-14 EW- 3132 688 +/- 103 < 145 05-15-14 EW- 2892 466 +/- 94 < 142 06-23-14 EW- 3209 1091 +/- 117 < 144 07-14-14 EW- 3484 482 +/- 90 < 137 08-28-14 EW- 4598 626 +/- 111 < 177 09-26-14 EW- 5268 524 +/- 101 < 149 10-24-14 EW- 6142 1120 +/- 124 < 176 11-20-14 EW- 6932 518 +/- 114 < 172 12-26-14 EW- 7368 789 +/- 133 < 173 Mean +/- s.d. 724 +/- 236 a "NF"= No flow.

13-3

POINTBEACH NUCLEAR PLANT Beach Drains Units: = pCi\L Gamma isotopic analysis Location S-1 S-3 S-7 S-8 Collection Date 01-10-14 01-10-14 01-10-14 01-10-14 Lab Code NFa MDC NFa MDC NFa MDC NFa MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-1 34 Cs-1 37 Ba-La-140 Location S-9 S-10 S-11 S-1 Collection Date 01-10-14 01-10-14 01-10-14 02-10-14 Lab Code NF8 NFa NFa NFa Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-1 34 Cs-1 37 Ba-La-140 Location S-3 S-7 S-8 S-9 Collection Date 02-10-14 02-10-14 02-10-14 02-10-14 Lab Code NFa NFa NF8 NFa Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-1 37 Ba-La-140 a "NF" =No flow.

13-4

POINT BEACH NUCLEAR PLANT Beach Drains (cont.)

Units: = pCi\L Gamma isotopic analysis Location S-10 S-11 S-1 S-3 Collection Date 02-10-14 02-10-14 03-10-14 03-10-14 Lab Code NFa MDC NFa MDC NFa MDC NF8 MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs- 134 Cs-1 37 Ba-La-140 Location S-7 S-8 S-9 S-10 Collection Date 03-10-14 03-10-14 03-10-14 03-10-14 Lab Code NFa NFa NFa NFO Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-1 34 Cs-1 37 Ba-La-140 Location S-11 S-1 S-3 S-7 Collection Date 03-10-14 04-09-14 04-09-14 03-10-14 Lab Code NFa EW- 1440 EW- 1441 NFO Be-7 2.0 +/- 12.7 < 33.4 11.3 +/- 12.6 < 30.2 Mn-54 -0.2 +/- 1.6 < 2.8 -0.8 +/- 1.6 < 2.0 Fe-59 -0.2 +/- 2.7 < 2.9 -0.2 +/- 2.6 < 3.0 Co-58 -0.1 + 1.2 < 1.5 -0.2 +/- 1.5 <2.1 Co-6O 0.2 + 1.4 < 1.5 -0.6 +/- 1.6 < 1.6 Zn-65 -1.0 +/- 2.2 < 2.3 -1.1 +/- 2.7 < 3.7 Zr-Nb-95 1.9 + 1.5 < 3.0 0.1 +/- 1.7 < 2.6 Cs-1 34 -0.4 + 1.7 <3.1 -1.7 +/- 1.6 < 3.1 Cs-i 37 -0.3 + 1.5 < 2.4 0.0 +/- 1.9 < 2.8 Ba-La-140 -1.9 +/- 2.0 < 2.9 -0.9 +/- 2.1 < 3.0 a "NF" = No flow.

13-5

POINT BEACH NUCEinAR PLANT Beach Drains (cont.)

Units: = pCi\L Gamma isotopic analysis Location S-8 S-9 S-10 S-11 MDC Collection Date 04-09-14 04-09-14 04-09-14 04-09-14 Lab Code NFa MDC NFa MDC NFa MDC EW- 1442 MDC Be-7 -2.0 +/- 11.7 < 27.7 Mn-54 1.2 +/- 1.4 < 2.6 Fe-59 0.6 +/- 2.5 <4.1 Co-58 1.1 +/- 1.3 < 2.4 Co-60 0.2 t 1.7 < 1.8 Zn-65 -2.8 +/- 3.1 < 2.8 Zr-Nb-95 0.9 +/- 1.5 < 2.8 Cs- 134 0.7 +/- 1.5 < 2.5 Cs-1 37 -0.2 +/- 1.5 < 2.4 Ba-La-140 -0.9 +/- 1.5 < 1.6 Location S-1 S-3 S-7 S-8 Collection Date 05-08-14 05-08-14 05-08-14 05-08-14 Lab Code EW- 2033 EW- 2034 NFa NFa Be-7 16.4 +/- 16.0 < 30.7 11.2 +/- 9.7 < 20.3 Mn-54 1.0 +/- 1.6 < 3.1 0.3 +/- 1.2 < 2.4 Fe-59 0.5 +/- 3.4 < 3.8 -1.6 +/- 1.9 < 2.9 Co-58 -1.4 +/- 1.5 < 1.9 0.4 +/- 1.2 < 2.0 Co-60 0.3 + 1.8 < 2.1 0.3 +/- 1.2 < 2.2 Zn-65 -1.1 +/- 3.5 < 2.7 -0.4 +/- 2.3 < 3.3 Zr-Nb-95 0.4 +/- 1.7 < 4.5 -0.1 +/- 1.2 < 2.4 Cs-1 34 -0.9 +/- 1.6 < 3.4 0.2 +/- 1.1 < 2.1 Cs-137 0.1 +/- 1.9 < 3.3 -0.2 +/- 1.2 < 2.0 Ba-La-140 -1.7 +2.2 < 3.6 -1.5 +/- 1.1 < 3.0 Location S-9 S-10 S-11 S-1 Collection Date 05-08-i14 05-08-14 05-08-14 06-05-14 Lab Code NFa NFa EW- 2035 EW- 2588 Be-7 11.5 +/- 19.9 < 42.0 -3.6 +/- 12.1 < 32.8 Mn-54 -0.4 +/- 1.9 < 2.7 0.1 +/-1.3 < 1.8 Fe-59 3.3 +/- 4.1 < 8.2 -0.9 +/-2.2 < 2.7 Co-58 0.1 +/- 1.9 <4.1 -1.7 +/-1.3 < 1.8 Co-60 -0.4 +/- 1.9 < 1.3 1.1 +/-1.4 < 2.6 Zn-65 1.2 +/- 4.5 < 7.0 -1.1 +/-2.5 < 2.2 Zr-Nb-95 0.4 +/- 1.9 < 4.7 0.9 +/-1.5 < 2.1 Cs- 134 0.6 +/- 2.0 < 4.2 0.8 +/-1.4 < 2.9 Cs-137 -0.6 +/- 2.3 < 3.2 -0.1 +/-1.4 < 2.3 Ba-La-140 -2.6 +/- 2.1 < 2.1 -0.9 +/-1.4 < 4.4 a "NF"= No flow.

13-6

POINT BEACH NUCLEAR PLANT Beach Drains (cont.)

Units: = pCi\L Gamma isotopic analysis Location S-3 S-7 S-8 S-9 Collection Date 06-05-14 06-05-14 06-05-14 06-05-14 Lab Code EW- 2589 MDC NFa MDC NFa MDC NFa MDC Be-7 -3.3 +9.1 < 18.7 Mn-54 -0.1 + 1.1 < 1.8 Fe-59 1.1 + 2.0 < 4.5 Co-58 -0.4 +1.1 < 2.4 Co-60 1.2 + 1.2 < 2.2 Zn-65 -0.8 +2.1 < 3.7 Zr-Nb-95 -1.1 +/- 1.1 < 2.0 Cs- 134 0.0 +1.1 < 2.3 Cs- 137 -0.1 + 1.3 < 2.0 Ba-La-1 40 -2.9 + 1.2 < 3.8 Location S-10 S-11 S-1 S-3 Collection Date 06-05-14 06-05-14 06-30-14 06-30-14 Lab Code NFa .EW- 2590 EW- 3110 EW- 3111 Be-7 -3.7 +/- 8.8 < 18.2 -2.0 +/- 13.0 < 26.1 2.3 +/- 11.7 < 28.2 Mn-54 0.8 +/- 1.2 < 2.1 0.1 +/- 1.5 < 2.8 0.2 +/- 1.8 < 2.5 Fe-59 1.6 +/- 2.1 < 5.1 1.1 +/-2.8 < 4.5 -1.0 +/- 2.8 < 4.4 Co-58 -1.3 +/- 1.2 < 1.6 -0.5 +/- 1.5 < 2.3 -0.3 +/- 1.5 < 2.4 Co-60 0.3 +/- 1.0 < 1.9 1.3 +/- 1.9 < 2.6 -0.6 +/- 1.5 < 2.5 Zn-65 0.2 +/- 2.2 < 2.2 -2.0 +/- 3.2 < 4.6 0.1 +/- 3.3 < 5.5 Zr-Nb-95 -0.1 +/- 1.2 < 2.4 -0.7 +/- 1.6 <2.1 1.7 +/- 1.7 < 3.8 Cs-134 -0.9 +/- 1.1 < 2.2 -1.6 +/- 1.8 < 3.4 1.0 + 1.6 < 3.0 Cs- 137 -0.2 +/- 1.3 < 1.9 0.5 +/- 1.9 < 2.9 1.5 + 1.9 < 3.5 Ba-La-140 -1.4 +/- 1.1 < 4.4 -0.7 +/- 1.7 < 3.4 -0.2 +/- 2.1 < 4.7 Location S-7 S-8 S-9 S-10 Collection Date 06-30-14 06-30-14 06-30-14 06-30-14 Lab Code NFa NFa NFa NFa Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-1 34 Cs-i 37 Ba-La-140 a "'NF"= No flow.

13-7

POINT BEACH NUCLEAR PLANT Beach Drains (cont.)

Units: = pCi\L Gamma isotopic analysis Location S-11 S-1 S-3 S-7 Collection Date 06-30-14 08-05-14 08-05-14 08-05-14 Lab Code NFa MDC EW- 4025 MDC EW- 4026 MDC NFa MDC Be-7 -7.3 +/- 18.8 < 41.1 14.1 +/- 19.6 < 54.3 Mn-54 0.2 +/- 2.0 < 2.9 -1.1 +/- 2.0 < 2.7 Fe-59 4.1 +/-3.5 < 5.9 -6.3 +/- 3.8 < 2.1 Co-58 -1.6 +/- 2.2 < 2.3 0.0 +/- 2.2 < 3.6 Co-60 0.2 +/- 2.2 < 2.7 0.7 +/- 2.0 < 1.4 Zn-65 -3.5 +/- 5.0 < 7.2 2.0 +/- 4.8 < 6.3 Zr-Nb-95 -2.4 +/- 2.2 < 4.5 1.7 +/- 2.1 < 5.1 Cs-134 0.8 +/- 1.9 < 3.9 1.1 +/-2.0 < 4.6 Cs-1 37 0.0 +/- 2.2 < 3.8 -0.4 +/- 2.7 < 3.0 Ba-La-140 1.2 +/- 1.7 < 3.1 -3.2 +/- 2.5 < 3.1 Location S-8 S-9 S-10 S-11 Collection Date 08-05-14 08-05-14 08-05-14 08-05-14 Lab Code NFa NFa NF" NFa Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-1 34 Cs-137 Ba-La-140 Location S-1 S-3 S-7 S-8 Collection Date 09-11-14 09-11-14 09-11-14 09-11-14 Lab Code EW- 4798 EW- 4799 NFa NFa Be-7 -5.3 +/- 16.3 < 31.2 -3.5 +/- 16.8 < 32.6 Mn-54 0.3 +/- 1.7 < 3.2 -0.5 +/- 1.6 < 2.3 Fe-59 -3.0 +/- 3.6 < 4.6 1.4 +/- 3.5 < 4.3 Co-58 -1.2 +/- 1.8 < 2.7 1.2 +/- 1.6 < 1.6 Co-60 -0.1 +/- 1.8 <2.1 -1.6 +/- 1.9 < 2.4 Zn-65 -3.3 +/- 3.9 < 4.9 -3.2 +/- 4.1 < 6.4 Zr-Nb-95 0.1 +/- 1.7 < 3.8 1.2 +/- 1.7 < 3.7 Cs-134 0.3 +/- 1.9 < 3.7 0.3 +/- 1.8 < 3.5 Cs-1 37 -0.7 +/- 2.0 < 2.8 1.0 +/-2.1 < 4.5 Ba-La-140 -1.3 +/- 1.7 < 2.9 3.4 1.9 < 5.2 aIINF' = No flow.

13-8

POINT BEACH NUCLEAR PLANT Beach Drains (cont.)

Units: = pCi\L Gamma isotopic analysis Location S-9 S-10 S-l1 S-1 Collection Date 09-11-14 09-11-14 09-11-14 10-08-14 Lab Code NF` MDC NFa MDC NFa MDC EW- 5446 MDC Be-7 2.3 +/- 4.4 < 12.7 Mn-54 -0.3 +/- 0.6 < 0.9 Fe-59 -0.4 +/- 1.0 < 2.8 Co-58 0.7 +/- 0.5 < 1.3 Co-60 -0.2 +/- 0.6 < 1.1 Zn-65 0.1 +/- 1.1 < 1.8 Zr-Nb-95 -0.7 +/- 0.6 < 1.6 Cs-1 34 -0.3 +/- 0.6 < 1.1 Cs-137 0.1 +/- 0.7 < 1.1 Ba-La-140 0.1 +/- 0.6 < 4.0 Location S-3 S-7 S-8 S-9 Collection Date 10-08-14 10-08-14 10-08-14 10-08-14 Lab Code EW- 5447 NFa NFa NFa Be-7 1.2 +/- 4.6 < 11.5 Mn-54 -0.5 +/- 0.6 < 0.8 Fe-59 -0.6 +/- 0.9 < 2.4 Co-58 0.6 +/- 0.5 < 1.5 Co-60 0.0 + 0.6 < 0.9 Zn-65 0.1 +/- 1.1 <2.1 Zr-Nb-95 -0.3 + 0.6 < 2.0 Cs-1 34 0.4 +/- 0.6 < 1.1 Cs-I 37 0.3 +/- 0.7 < 1.3 Ba-La-140 -1.8 +/- 0.7 < 2.7 Location S-10 S-11 EX-SSD-N S-1 Collection Date 10-08-14 10-08-14 10-08-14 11-05-14 Lab Code NFa NFa EW- 5448 EW- 6337 Be-7 -4.1 + 10.6 < 27.5 -8.7 +/- 16.3 16.0 Mn-54 0.1 +/- 1.3 < 1.6 -0.7 +/- 1.4 1.9 Fe-59 -0.7 +/- 2.6 < 3.6 -1.2 +/- 3.5 5.6 Co-58 0.6  : 1.3 < 2.5 0.4 +/- 1.6 2.6 Co-60 1.2 +/- 1.1 < 1.9 -0.3 +/- 1.7 1.8 Zn-65 -1.0 +/- 2.8 < 4.5 -0.6 +/- 4.1 5.1 Zr-Nb-95 -1.2 +/- 1.3 < 3.3 -1.2 +/- 1.8 3.2 Cs-134 0.6 +/- 1.2 < 2.2 0.6 +/- 1.7 3.4 Cs-137 0.1 +/- 1.6 < 2.7 1.0 +/- 1.7 2.7 Ba-La-140 -4.0 +/- 1.6 < 6.8 -1.4 +/- 1.5 1.3 a "NPF= No flow.

13-9

POINT BEACH NUCLEAR PLANT Beach Drains (cont.)

Units: = pCi\L Gamma isotopic analysis Location S-3 S-7 S-8 S-9 Collection Date 11-05-14 11-05-14 11-05-14 11-05-14 Lab Code EW- 6338 MDC NFa NFa NFa Be-7 8.4 +/- 13.4 < 29.7 Mn-54 -0.1 +/- 1.8 < 3.2 Fe-59 -0.3 +/- 3.1 < 5.7 Co-58 0.2 +/- 1.7 < 2.2 Co-60 0.5 +/- 1.7 < 2.4 Zn-65 -1.4 +/- 3.4 < 4.6 Zr-Nb-95 -2.5 +/- 1.9 <2.1 Cs- 134 -0.4 +/- 1.6 < 2.8 Cs-137 -0.2 +/- 1.9 < 3.0 Ba-La-140 -0.6 +/- 1.9 < 1.8 Location S-10 S-11 S-1 S-3 Collection Date 11-05-14 11-05-14 12-11-14 Z" 12-11-14 Lab Code NFa NFa EW- 6983 MDC EW- 6985 MDC Be-7 -3.6 +/- 12.3 < 24.3 11.4 +/- 14.3 < 28.9 Mn-54 -0.2 +/- 1.3 < 1.3 -1.3 +/- 1.6 <2.1 Fe-59 0.6 +/- 2.2 < 2.9 4.0 +/- 3.0 < 6.7 Co-58 -0.5 +/- 1.0 < 1.9 0.3 +/- 1.4 < 2.1 Co-60 -0.6 +/- 1.4 < 0.8 0.9 + 1.1 < 1.8 Zn-65 -1.4 +/- 2.4 < 1.4 -1.7 +/- 3.5 < 3.3 Zr-Nb-95 -0.4 +/- 1.5 < 3.1 0.3 +/- 1.5 < 3.6 Cs- 134 -0.9 +/- 1.3 < 2.0 0.1 +/- 1.6 < 3.1 Cs-1 37 -0.1 +/- 1.7 < 2.2 0.0 +/- 1.8 < 3.5 Ba-La-140 -0.5 +/- 1.3 < 3.4 0.5 +/- 1.6 < 3.7 Location S-7 S-8 S-9 S-10 Collection Date 12-11-14 12-11-14 12-11-14 12-11-14 Lab Code NFa NFa NFa NFa Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-I 34 Cs-i 37 Ba-La-I 40 a "NF = No flow.

13-10

POINT BEACH NUCLEAR PLANT Beach Drains (cont.)

Units: = pCi\L Gamma isotopic analysis Location S-11 Collection Date 12-11-14 NFa Lab Code Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-1 34 Cs-1 37 Ba-La-140 Annual All locations Mean +/- s.d. Mean t s.d. Mean i s.d. Mean + s.d.

Be-7 2.3 +/- 7.7 Co-58 -0.2 +/- 0.9 Zr/Nb-95 0.0 + 1.2 Ba/La-140 -0.9 + 1.5 Mn-54 -0.1 +/- 0.6 Co-60 0.1 +/- 0.7 Cs-134 0.0 - -0.8 Fe-59 0.1 +/- 2.2 Zn-65 -1.0 +/- 1.4 Cs-137 0.1 + 0.5 13-11

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

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

Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-09-14 EWW- 80 14 +/- 94 < 153 01-09-14 EWW- 81 30 +/- 94 < 153 04-16-14 EWW- 1525 -36 +/- 74 < 144 04-16-14 EWW- 1526 -6 +/- 75 < 144 07-10-14 EWW- 3294 -17 +/- 70 < 143 07-10-14 EWW- 3295 -21 +/- 70 < 143 10-15-14 EWW- 5689 -21 +/- 82 < 158 10-15-14 EWW- 5690 -28 +/- 81 < 158 Mean +/- s.d. -15 +/- 21 Mean +/- s.d. -6 +/- 26 Sample ID GW-11 (MW-1) GW-12 (MW-2)

Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 02-04-14 EWW- 3134 66 +/- 70 < 137 04-08-14 EWW- 3140 -8 +/- 65 < 136 06-30-14 EWW- 3139 133 +/- 72 < 134 07-22-14 EWW- 3660 -61 +/- 69 < 138 07-22-14 EWW- 3659 61 +/- 76 < 138 10-21-14 EWW- 6167 49 +/- 89 < 176 10-21-14 EWW- 6166 66 +/- 90 < 176 Mean +/- s.d. 82 +/- 34 Mean +/- s.d. -7 +/- 55 Sample ID GW-13 (MW-6) GW-14A (MW-05A)

Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 02-04-14 EWW- 3135 32 +/- 68 < 137 02-04-14 EWW- 3136 96 +/- 72 < 137 04-08-14 EWW- 3141 69 +/- 69 < 136 04-08-14 EWW- 3142 83 +/- 70 < 136 07-22-14 EWW- 3661 81 +/- 77 < 138 07-22-14 EWW- 3662 112 +/- 79 < 138 10-21-14 EWW- 6168 38 +/- 89 < 176 10-21-14 EWW- 6169 148+/-:93 /< 176 Mean +/- s.d. 55 +/-24 Mean +/- s.d. 110 +/-28 Sample ID GW-15 (MW-4) GW-1 5A (MW-4)

Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 02-04-14 EWW- 3137 253 +/- 80 < 137 02-04-14 EWW- 3138 243 +/- 79 < 137 04-08-14 EWW- 3143 171 +/- 75 < 136 04-08-14 EWW- 3144 250 +/- 79 < 136 07-22-14 EWW- 3663 191 +/- 82 '.< 138 10-21-14 EWW- 6170 208 +/- 95 < 176 10-21-14 EWW- 6171 229 +/- 96 / < 176 (15B)

Mean +/- s.d. 211 +/- 37 Mean +/- s.d. 234 +/-23 Sample ID GW-16A (MW-3) GW-16B (MW-3)

Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 06-30-14 EWW- 3145 206 +/- 76 < 134 07-22-14 EWW- 3665 222 +/- 84 < 138 07-22-14 EWW- 3664 234 +/- 85 < 138 10-21-14 EWW- 6172 195 +/- 95 < 176 Mean +/- s.d. 212 +/- 20 Mean +/- s.d.

13-12

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

Units = pCi/L Quarterly Wells (cont.)

Sample ID GW-18 (WH 7 Well) Sample ID GW-14B (MW-05B)

Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-09-14 EWW- 82 38 +/- 95 < 153 04-16-14 EWW- 1527 -30 +/- 74 < 144 07-10-14 EWW- 3296 19 +/- 72 < 143 10-15-14 EWW- 5691 -61 +/- 79 < 158 Mean +/- s.d. -9 +/-46 Mean +/- s.d.

Fa(cade Wells Sample ID GW-09 IZ-361A GW-09 1Z-361 B Collection MDC Collection MDC Date Lab Code Tritium Date Lab Code Tritium 03-15-14 EWW- 1253 325 +/- 91 < 143 03-15-14 EWW- 1254 143 +/- 83 < 143 04-06-14 EWW- 1568 28 +/- 72 < 146 04-06-14 EWW- 1569 131 +/- 77 < 146 06-25-14 EWW- 3210 258 +/- 84 < 144 06-25-14 EWW- 3211 328 +/- 88 < 144 07-16-14 EWW- 3480 301 +/- 83 < 136 07-16-14 EWW- 3481 224 +/- 80 < 136 08-19-14 EWW- 4519 322 +/- 96 < 151 08-19-14 EWW- 4520 82 +/- 84 < 151 11-17-14 EWW- 6644 375 +/- 106 < 170 11-17-14 EWW- 6645 219 +/- 96 < 170 Mean +/- s.d. 268 +/- 124 Mean +/- s.d. 188 +/- 88 Sample ID GW-10 2Z-361A GW-10 2Z-361B Collection MDC Collection MDC Date Lab Code Tritium Date Lab Code Tritium 03-15-14 NSa 03-15-14 EWW- 1255 119 +/- 81 < 143 04-06-14 EWW- 1570 -14 +/- 69 < 146 04-06-14 EWW- 1571 270 +/- 84 < 146 06-25-14 EWW- 3212 431 +/- 92 < 144 06-25-14 EWW- 3213 202 +/- 82 < 144 07-16-14 EWW- 3482 8 +/- 68 < 136 07-16-14 EWW- 3483 87 +/- 72 < 136 08-19-14 EWW- 4521 -14 +/- 78 < 151 08-19-14 EWW- 4523 145 +/- 87 < 151 11-17-14 EWW- 6646 -51 +/- 78 < 170 11-17-14 EWW- 6647 87 +/- 88 < 170 Mean +/- s.d. 72 +/- 219 Mean +/- s.d. 152 +/- 72 (Annual Collections)

Units = pCi/L Bogs Sample ID GW-07 (North Bog) GW-08 EIC Bog Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 05-08-14 EWW- 2041 73 +/- 73 < 144 05-08-14 EWW- 2042 393 +/- 89 < 144 aWater frozen.

13-13

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

NSa 05-01-14 NSa 05-01-14 11-19-14 NSa 11-19-14 NSa Mean +/- s.d. Mean +/- s.d.

Sample ID MH Z-065C MH Z-065D Collection Lab Code Tritium MDC Collection Lab Code Tritium MDC Date (pCi/L) Date (pCi/L) 05-01-14 NSa 05-01-14 NSa 11-19-14 NSa 11-19-14 NSa Mean +/- s.d. Mean +/- s.d.

Sample ID MH Z-066A MH Z-066B Collection Lab Code Tritium MDC Collection Lab Code Tritium MDC Date (pCi/L) Date (pCi/L) 05-01-14 EW- 2047 331 +/- 86 < 145 05-01-14 EW- 2048 29 +/- 71 < 145 11-19-14 EW- 7478 133 +/- 101 < 186 11-19-14 NS" Mean +/- s.d. 232 +/- 140 Mean +/- s.d.

Sample ID MH Z-066C MH Z-066D Collection Lab Code Tritium MDC Collection Lab Code Tritium MDC Date (pCi/L) Date (pCi/L) 05-01-14 EW- 2049 25 +/- 71 < 145 05-01-14 EW- 2050 215 +/- 81 < 145 11-19-14 NSa 11-19-14 NSa Mean +/- s.d. Mean +/- s.d.

Sample ID MH Z-067A MH Z-067B Collection Lab Code Tritium MDC Collection Lab Code Tritium MDC Date (pCi/L) Date (pCi/L) 05-01-14 EW- 2051 253 +/- 83 < 145 05-01-14 EW- 2052 37 +/- 72 < 145 11-19-14 EW- 7479 272 +/- 109 < 186 11-19-14 NSa Mean +/- s.d. 263 +/- 13 Mean +/- s.d.

a "NS"= No sample; not sent.

13-14

POINT BEACH NUCLEAR PLANT Manholes (cont.)

Sample ID MH Z-067C MH Z-067D Collection Lab Code Tritium MDC Collection Lab Code Tritium MDC Date (pCi/L) Date (pCi/L) 05-01-14 EW- 2053 205 + 80 < 145 05-01-14 EW- 2054 51 +/- 72 < 145 11-19-14 NSa 11-19-14 NSa Mean +/- s.d. Mean +/- s.d.

Sample ID MH Z-068 MH-1 Collection Lab Code Tritium MDC Collection Lab Code Tritium MDC Date (pCi/L) Date (pCi/L) 05-01-14 EW- 2055 243 +/- 82 < 145 05-01-14 NSa 11-19-14 EW- 7480 219 +/- 106 < 186 11-19-14 NSa Mean +/- s.d. 231 +/- 17 Mean +/- s.d.

Sample ID MH-4 MH-6 Collection Lab Code Tritium MDC Collection Lab Code Tritium MDC Date MDC Cate (pCilL) 05-01-14 NSa 05-01-14 NSa 11-19-14 NSa 11-19-14 NSa Mean +/- s.d. Mean +/- s.d.

Sample ID MH-7 MH-8 Collection Lab Code Tritium MDC Collection Lab Code Tritium MDC Date (pCi/L) Date (pCi/L) 05-01-14 NSa 05-01-14 NSa 11-19-14 NSa 11-19-14 NSa Mean +/- s.d. Mean +/- s.d.

Sample ID MH-16 MH-2 Collection LiMDC Collection LiMDC Date Lab Code Tritium (pCi/L) Date Lab Code Tritium (pCi/L) 05-01-14 NSa 05-01-14 NSa 11-19-14 NSa 11-19-14 NSa Mean +/- s.d. Mean +/- s.d.

Sample ID MH-5A MH-9 Collection Lab Code Tritium MDC Collection Lab Code Tritium MDC Date (pCi/L) Date (pCi/L) 05-01-14 NSa 05-01-14 NS" 11-19-14 NSa 11-19-14 NSa Mean + s.d. Mean +/- s.d.

a "NS" = No sample; not sent.

13-15

• ATI Midwest Environmental, Laboratory Inc.

700 Landwehr Road - Northbrook, IL 60062-23 10 phone (847) 564-0700

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

January, 2014 through December, 2014

Appendix A Interlaboratory Comparison 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.

Al

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

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

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

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

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

> 100 pCi/liter 5% of known value Tritium < 4,000 pCi/liter +/- 1a =

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-131, -<55 pCi/liter 6 pCi/liter Iodine-1 2 9 b > 55 pCi/liter 10% of known value Uranium-238, < 35 pCi/liter 6 pCi/liter Nickel-63b > 35 pCi/liter 15% of known value Technetiu M~99b Iron-55 b 50 to 100 pCi/liter 10 pCi/liter

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

b Laboratory limit.

A2

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result b Result C Limits Acceptance ERW-1384 417/2014 Sr-89 40.29 +/- 5.76 36.70 27.50 +/- 43.60 Pass ERW-1384 4/7/2014 Sr-90 24.08 +/- 2.35 26.50 19.20 +/- 30.90 Pass ERW-1385 4/7/2014 Ba-133 78.23 +/- 3.93 87.90 74.00 +/- 96.70 Pass ERW-1385 4/7/2014 Co-60 62.75 +/- 3.53 64.20 57.80 +/- 73.10 Pass ERW-1385 4/7/2014 Cs-134 44.97 +/- 3.99 44.30 35.50 +/- 48.70 Pass ERW-1385 4/7/2014 Cs-137 88.54 +/- 4.93 89.10 80.20 +/- 101.00 Pass ERW-1385 4/7/2014 Zn-65 249.1 +/- 10.4 235.0 212.0 - 275.0 Pass ERW-1388 4/7/2014 Gr. Alpha 56.70 +/- 2.47 61.00 31.90 +/- 75.80 Pass ERW-1388 4/7/2014 Gr. Beta 32.10 +/- 1.20 33.00 21.40 +/- 40.70 Pass ERW-1391 4/7/2014 1-131 25.52 +/- 1.12 25.70 21.30 +/- 30.30 Pass ERW-1394 4/7/2014 Ra-226 12.30 +/- 0.61 12.40 9.26 +/- 14.30 Pass ERW-1394 4/7/2014 Ra-228 5.08 +/- 1.16 4.26 2.46 +/- 5.86 Pass ERW-1394 4/7/2014 Uranium 10.76 +/- 0.74 10.20 7.95 +/- 11.80 Pass ERW-1397 4/7/2014 H-3 8982 +/- 279 8770 7610 -9650 Pass ERW-5382 10/6/2014 Sr-89 29.40 +/- 5.32 31.40 22.80 +/- 38.10 Pass ERW-5382 10/6/2014 Sr-90 19.19 +/- 1.85 21.80 15.60 +/- 25.70 Pass ERW-5385 10/6/2014 Ba-133 43.54 +/- 4.54 49.10 40.30 +/- 54.50 Pass ERW-5385 10/6/2014 Cs-134 81.95 +/- 7.49 89.80 73.70 +/- 98.80 Pass ERW-5385 10/6/2014 Cs-137 95.76 +/- 5.50 98.80 88.90 +/- 111.00 Pass ERW-5385 10/6/2014 Co-60 90.25 +/- 2.77 92.10 82.90 +/- 104.00 Pass ERW-5385 10/6/2014 Zn-65 327.4 +/- 23.3 310.0 279.0 - 362.0 Pass ERW-5388 10/6/2014 Gr. Alpha 30.88 +/- 8.05 37.60 19.40 +/- 46.10 Pass ERW-5388 10/6/2014 G. Beta 20.47 +/- 4.75 27.40 17.30 +/- 35.30 Pass ERW-5392 10/6/2014 1-131 19.58 +/- 2.35 20.30 16.80 +/- 24.40 Pass ERW-5394 10/6/2014 Ra-226 15.10 +/- 1.81 14.70 11.00 +/- 16.90 Pass ERW-5394 10/6/2014 Ra-228 4.42 +/- 0.86 4.31 2.50 +/- 5.92 Pass ERW-5394 10/6/2014 Uranium 5.51 +/- 0.37 5.80 4.34 +/- 6.96 Pass ERW-5397 10/6/2014 H-3 6876 +/- 383 6880 5940 - 7570 Pass a Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing indrinking 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.

Al-1

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

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

2014-1 5/15/2014 50 cm. 26.83 34.43 +/- 3.76 18.78 -34.88 Pass 2014-1 5/15/2014 60 cm. 18.63 22.20 +/- 1.16 13.04 - 24.22 Pass 2014-1 5/15/2014 70 cm. 13.69 14.74 +/- 0.80 9.58 - 17.80 Pass 2014-1 5/15/2014 75 cm. 11.93 12.68 +/- 1.05 8.35 - 15.51 Pass 2014-1 5/15/2014 80 cm. 10.48 11.81 +/- 0.91 7.34 - 13.62 Pass 2014-1 5115/2014 90 cm. 8.28 7.72 +/- 0.71 5.80 - 10.76 Pass 2014-1 5/15/2014 100 cm. 6.71 6.46 +/- 0.71 4.70 - 8.72 Pass 2014-1 5/15/2014 110 cm. 5.54 5.25 +/- 1.03 3.88 - 7.20 Pass 2014-1 5/15/2014 120 cm. 4.66 4.76 +/- 0.48 3.26 - 6.06 Pass 2014-1 5/15/2014 135 cm. 3.68 2.87 +/- 0.46 2.58 - 4.78 Pass 2014-1 5/15/2014 150 cm. 2.98 2.30 +/- 0.15 2.09 - 3.87 Pass 2014-1 5/15/2014 165 cm. 2.46 2.09 +/- 0.28 1.72 -3.20 Pass 2014-1 5/15/2014 180 cm. 2.07 1.75 +/- 0.21 1.45-2.69 Pass Environmental, Inc.

2014-2 12/9/2014 30 cm. 77.04 84.03 +/- 8.47 53.90 - 100.20 Pass 2014-2 12/9/2014 30 cm. 77.04 83.74 +/- 12.02 53.90 - 100.20 Pass 2014-2 12/9/2014 60 cm. 19.26 20.39 +/- 2.37 13.50 - 25.00 Pass 2014-2 12/9/2014 60 cm. 19.26 20.33 +/- 1.19 13.50 - 25.00 Pass 2014-2 12/9/2014 120 cm. 4.82 5.15 +/- 0.20 3.40 - 6.30 Pass 2014-2 12/9/2014 120 cm. 4.82 5.20 +/- 0.45 3.40 - 6.30 Pass 2014-2 12/9/2014 150 cm. 3.08 3.84 +/- 0.61 2.20 - 4.00 Pass 2014-2 12/9/2014 150 cm. 3.08 3.17 +/- 0.38 2.20 - 4.00 Pass 2014-2 12/9/2014 150 cm. 3.08 3.31 +/- 0.32 2.00 - 4.00 Pass 2014-2 12/9/2014 180 cm. 2.14 2.27 +/- 0.51 1.50 -2.80 Pass 2014-2 12/9/2014 180 cm. 2.14 2.23 +/- 0.12 1.50 -2.80 Pass 2014-2 12/9/2014 180 cm. 2.14 2.74 +/- 0.48 1.50 -2.80 Pass 2014-2 12/9/2014 180 cm. 2.14 1.97 +/- 0.41 1.50 -2.80 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 c Activity Limits d Acceptance SPW-1011 1/13/2014 Ra-228 35.47 +/- 2.55 30.85 21.60 - 40.11 Pass SPAP-103 1/13/2014 Gr. Beta 43.91 +/- 0.34 44.82 26.89 - 62.75 Pass SPAP-105 1/13/2014 Cs-134 2.46 +/- 0.67 2.82 1.69 -3.95 Pass SPAP-105 1/13/2014 Cs-137 102.4 +/- 2.7 99.9 89.9 - 109.9 Pass SPW-107 1/13/2014 H-3 62,380 +/- 707 62,246 49,797 - 74,695 Pass SPW-129 1/15/2014 Cs-134 69.90 +/- 3.71 78.00 68.00 - 88.00 Pass SPW-129 1/15/2014 Cs-137 84.36 +/- 7.06 75.77 65.77 - 85.77 Pass SPW-129 1/15/2014 Sr-90 39.48 +/- 1.52 39.20 31.36 - 47.04 Pass SPW-130 1/15/2014 Ni-63 255.8 +/- 3.8 204.0 142.8 - 265.2 Pass SPW-133 1/15/2014 C-14 3153 +/- 15 4737 2842 - 6632 Pass SPMI-135 1/15/2014 Cs-134 76.80 +/- 4.04 78.00 68.00 - 88.00 Pass SPMI-135 1/15/2014 Cs-137 80.44 + 6.63 75.80 65.80 - 85.80 Pass W-12014 1/20/2014 Gr. Alpha 19.69 _ 0.41 20.00 10.00 -30.00 Pass W-12014 1/20/2014 Gr. Beta 30.35 +/- 0.33 30.90 20.90 - 40.90 Pass SPW-297 1/29/2014 Tc-99 104.2 + 1.7 107.8 75.5 - 140.2 Pass SPW-657 2/25/2014 Ra-226 15.84 +/- 0.45 16.70 11.69 - 21.71 Pass SPW-1 127 3/26/2014 U-238 43.28 + 2.56 41,72 29.20 - 54.24 Pass SPW-1917 3/28/2014 Pu-238 27.37 + 2.13 23.80 14.28 - 33.32 Pass SPW-1786 4/25/2014 Tc-99 531.1 +/-8.7 539.15 377.41 - 700.90 Pass SPW-2168 5/21/2014 Cs-134 70.90 +/- 5.81 69.50 59.50 - 79.50 Pass SPW-2168 5/21/2014 Cs-1 37 79.72 _ 6.49 75.17 65.17 - 85.17 Pass SPW-2168 5/21/2014 Sr-89 83.35 + 5.05 72.85 58.28 - 87.42 Pass SPW-2168 5/21/2014 Sr-90 33.37 + 1.52 38.87 31.10 - 46.64 Pass SPMI-2170 5/21/2014 Cs-134 64.15 +/- 4.93 69.50 59.50 - 79.50 Pass SPMI-2170 5/21/2014 Cs-137 76.21 +/- 6.91 75.17 65.17 - 85.17 Pass SPMI-2170 5/21/2014 Sr-89 65.82 +/- 4.89 72.85 58.28 - 87.42 Pass SPMI-2170 5/21/2014 Sr-90 40.90 +/- 1.59 38.87 31.10 - 46.64 Pass SPW-2792 6/18/2014 U-238 44.80 +/- 1.54 41.70 29.19 - 54.21 Pass SPW-2796 6/18/2014 C-14 3495 +/-9 4,737 2,842 - 6632 Pass WW-2836 6/30/2014 Co-60 131.8 +/- 6.9 140.90 126.81 - 154.99 Pass WW-2836 6/30/2014 Cs-137 143.8 +/- 9.1 145.60 131.04 - 160.16 Pass WW-2836 6/30/2014 H-3 6220 +/- 238 6,361 5,089 - 7633 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 ' Activity Limits d Acceptance SPW-3486 7/17/2014 Fe-55 2211 +/- 72 2319 1855 -2783 Pass SPW-080714 8/7/2014 Gr. Alpha 18.42 +/- 0.40 20.10 10.05 - 30.15 Pass SPW-080714 8/7/2014 Gr. Beta 31.70 +/- 0.40 32.40 22.40 - 42.40 Pass SPW-081214 8/12/2014 Pu-238 22.59 +/- 2.15 22.70 18.16- 27.24 Pass SPW-4093 8/13/2014 1-131(G) 59.95 +/- 6.17 59.62 49.62 - 69.62 Pass SPW-4093 8/13/2014 Sr-90 39.46 +/- 1.55 38.65 28.65 - 48.65 Pass SPW-4093 8/13/2014 Sr-89 105.5 +/- 4.9 115.0 92.0 - 149.5 Pass SPMI-4095 8/13/2014 1-131(G) 59.92 +/- 6.17 59.62 49.62 - 69.62 Pass SPMI-4095 8/1312014 1-131 60.05 +/- 0.72 59.62 47.70 - 71.54 Pass SPW-4104 8/13/2014 Ni-63 200.1 +/- 3.4 203.2 142.2 -264.1 Pass SPW-4106 8/13/2014 H-3 59,597 +/- 695 60,261 48209 - 72313 Pass SPW-4108 8/13/2014 Cs-134 2.45 +/- 0.81 2.32 0.00 - 12.32 Pass SPW-4108 8/13/2014 Cs-137 90.20 +/- 3.74 98.56 88.56 - 108.56 Pass SPAP-41 10 8/13/2014 Gr. Beta 43,65 +/- 0.11 44.19 34.19 - 54.19 Pass SPF-4112 8/13/2014 1-131 2.64 +/- 0.38 2.86 0.00'- 12,86 Pass SPF-4112 8/13/2014 Cs-134 0.91 +/- 0.03 1.03 0.00-11.03 Pass SPF-4112 8/13/2014 Cs-1 37 2.61 +/- 0.06 2.39 0.00 - 12.39 Pass SPW-081414 8/14/2014 H-3 14,663 + 788 17,700 14160 - 21240 Pass W081614 8/16/2014 Ra-226 14.30 +/- 0,37 16.70 11.69 - 21.71 Pass W082614 8/26/2014 Ra-228 27.18 +/-2.13 30.49 20.49 - 40.49 Pass SPW-090414 9/4/2014 Gr. Alpha 17.85 +/- 0.39 20,10 10.05 - 30.15 Pass SPW-090414 9/4/2014 Gr. Beta 30.03 +/- 0.33 30.90 20.90 - 40.90 Pass SPW-5124 9/29/2014 Ra-228 32.93 +/- 2.38 31.94 21.94 - 41.94 Pass W100714 10/7/2014 Gr. Alpha 18.56 +/- 0.40 20.10 10.05 - 30.15 Pass W100714 1017/2014 Gr. Beta 27.71 +/- 0.32 30.90 20.90 -40.90 Pass W111014 11/10/2014 Gr. Alpha 17.84 +/- 0.38 20.10 10.05 -30.15 Pass W111014 11/10/2014 Gr. Beta 30.12 +/- 0.33 30.90 20.90 - 40.90 Pass W112514 11/25/2014 Ra-226 16.63 +/- 0.41 16.70 11.69 -21.71 Pass W120814 12/8/2014 Gr. Alpha 19.29 +/- 0.41 20.10 10.05 -30.15 Pass W120814 12/8/2014 Gr. Beta 27.93 +/- 0.32 30.90 20.90 - 40.90 Pass SPW-7149 12/26/2014 Ni-63 217.53 +/- 3.25 203.10 142.17 - 264.03 Pass a Liquid sample results are reported in pCi/Liter, air filters( pCi/m3), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

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

c Results are based on single determinations.

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

NOTE: For fish, Jello is used for the spike matrix. For vegetation, cabbage is used for the spike matrix.

A3-2

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

SPW-1001 Water 1/13/2014 Ra-228 0.74 0.39 +/- 0.39 2 SPAP-102 Air Particulate 1/13/2014 Gr. Beta 0.003 0.015 +/- 0.003 0.01 SPAP-104 Air Particulate 1/13/2014 Cs-134 0.006 0.005 +/- 0.005 0.05 SPAP-104 Air Particulate 1/13/2014 Cs-137 0.004 -0.002 +/- 0.005 0.05 SPW-106 Water 1/13/2014 H-3 151.0 115.0 +/- 97.0 200 SPW-128 Water 1/15/2014 Cs- 134 2.85 0.59 +/- 1.46 10 SPW-128 Water 1/15/2014 Cs-137 2.52 0.68 +/- 1.64 10 SPW-128 Water 1/15/2014 Sr-90 0.61 0.74 +/- 0.36 1 SPW- 130 Water 1/15/2014 Ni-63 10.85 1.57 +/- 6.60 20 SPW-133 Water 1/15/2014 C-14 13.51 3.10 +/- 8.27 200 SPMI-134 Milk 1/15/2014 Cs- 134 4.43 0.14 +/- 2.46 10 SPMI-134 Milk 1/15/2014 Cs-137 1.92 -2.07 +/- 2.48 10 W-12014 Water 1/20/2014 Gr. Alpha 0.48 -0.31 +/- 0.31 2 W-12014 Water 1/20/2014 Gr. Beta 0.78 -0.24 +/- 0.54 4 SPW-297 Water 1/29/2014 Tc-99 5.63 -4.42 +/- 3.34 10 SPW-656 Water 2/25/2014 Ra-226 0.03 0.01 +/- 0.02 1 SPW-1 126 Water 3/26/2014 U-238 0.13 0.08 +/- 0.12 1 SPW-1 127 Water 3/26/2014 U-233/234 0.13 0.11 +/- 0.13 1 SPW-1 127 Water 3/26/2014 U-238 0.00 0.08 +/- 0.12 1 SPW-1917 Water 3/28/2014 Pu-238 0.02 0.01 +/- 0.01 1 SPW-1785 Water 4/25/2014 Tc-99 5.61 -4.33 + 3.33 10 SPW-1831 Water 4/30/2014 1-131 0.21 0.07 + 0.12 0.5 SPW-2167 Water 5/21/2014 Cs-134 2.29 -0.79 +/- 1.35 10 SPW-2167 Water 5/21/2014 Cs-137 2.46 0.36 +/- 1.48 10 SPW-2167 Water 5/21/2014 1-131(G) 2.77 0.25 +/- 1.53 20 SPW-2167 Water 5/21/2014 Sr-89 0.81 0.01 +/- 0.62 5 SPW-2167 Water 5/21/2014 Sr-90 0.52 0.03 + 0.24 1 SPMI-2169 Milk 5/21/2014 Cs-134 4.45 -0.55 +/- 2.39 10 SPMI-2169 Milk 5121/2014 Cs-137 3.91 -0.52 +/- 2.60 10 SPMI-2169 Milk 5/21/2014 1-131(G) 4.31 2.57 +/- 2.21 20 SPMI-2169 Milk 5/21/2014 Sr-89 0.98 -0.02 +/- 0.83 5 SPMI-2169 Milk 5/21/2014 Sr-90 0.61 0.35 +/- 0.32 1 SPW-2793 Water 6/18/2014 U-238 0.08 0.02 +/- 0.06 1 A4-1

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

SPW-3485 Water 7/17/2014 Fe-55 597.6 10.3 +/- 363.3 1000 SPW-4092 Water 8/13/2014 1-131(G) 3.59 0.91 +/- 1.95 20 SPW-4092 Water 8/13/2014 Cs- 134 3.71 -0.31 +/- 1.77 10 SPW-4092 Water 8/13/2014 Cs-137 2.71 -2.20 +/- 1.98 10 SPW-4092 Water 8/13/2014 Sr-89 0.89 0.11 +/- 0.63 5 SPW-4092 Water 8/13/2014 Sr-90 0.52 -0.05 +/- 0.23 1 SPMI-4094 Milk 8/13/2014 1-131 0.35 0.03 +/- 0.20 0.5 SPMI-4094 Milk 8/13/2014 1-131(G) 4.50 -0.41 +/- 2.44 20 SPMI-4094 Milk 8/13/2014 Cs-1 34 4.30 -0.84 +/- 2.02 10 SPMI-4094 Milk 8/13/2014 Cs- 137 3.45 0.96 +/- 2.51 10 SPMI-4094 Milk 8/13/2014 Sr-89 0.80 -0.19 +/- 0.79 5 SPMI-4094 Milk 8/13/2014 Sr-90 0.47 0.71 +/- 0.30 1 SPW-4103 Water 8/1312014 Ni-63 0.12 0.02 +/- 0.07 20 SPW-4105 Water 811312014 H-3 138.1 104.1 +/- 78.1 200 SPW-4107 Water 8/13/2014 1-131(G) 3.21 -3.68 +/- 1.33 20 SPW-4107 Water 8/13/2014 Cs-134 2.72 -0.62 +/- 1.49 10 SPW-4107 Water 8/13/2014 Cs-1 37 2.56 0.75 +/- 1.62 10 SPAP-41 09 Air Particulate 8/1312014 Gr. Beta 0.004 -0.003 +/- 0.00 0.01 SPF-4 111 Fish 8/13/2014 Cs-134 0.01 0.00 +/- 0.01 100 SPF-4111 Fish 8/13/2014 Cs-137 0.01 -0.01 +/- 0.01 100 SPF-4 111 Fish 8/13/2014 Co-60 0.01 0.00 +/- 0.01 100 W-081614 Water 8/16/2014 Ra-226 0.04 0.05 +/- 0.03 1 W-082614 Water 8/16/2014 Ra-228 0.62 0.29 +/- 0.40 2 W-092314 Water 9/23/2014 Ra-226 0.02 0.04 +/- 0.02 1 W-5123 Water 9/29/2014 Ra-228 0.70 0.43 +/- 0.38 2 W-100714 Water 10/7/2014 Gr. Alpha 0.39 0.04 +/- 0.28 2 W-100714 Water 10/7/2014 Gr. Beta 0.76 -0.06 +/- 0.53 4 W-111014 Water 11/10/2014 Gr. Alpha 0.39 0.01 +/- 0.28 2 W-111014 Water 11/10/2014 Gr. Beta 0.75 -0.25 _+0.52 4 W-1 12514 Water 11/25/2014 Ra-226 0.05 0.02 +/- 0.03 2 W-120814 Water 12/8/2014 Gr. Alpha 0.42 0.04 +/- 0.30 2 W-120814 Water 12/8/2014 Gr. Beta 0.74 -0.42 +/- 0.51 4 SPW-7148 Water 12/26/2014 Ni-63 10.80 -1.80 +/- 6.50 20

" Liquid sample results are reported in pCi/Liter, air filters( pCi/rn3), charcoal (pCi/charcoal canister), and solid samples (pCi/kg).

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

c Activity reported is a net activity result.

A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance AP-7829, 7830 1/2/2014 Be-7 0.08 +/- 0.02 0.06 +/- 0.01 0.07 +/- 0.01 Pass AP-7913, 7914 1/2/2014 Be-7 0.07 +/- 0.01 0.06 +/- 0.01 0.06 +/- 0.01 Pass AP-7871, 7872 1/3/2014 Be-7 0.05 +/- 0.02 0.06 +/- 0.01 0.06 +/- 0.01 Pass S-43, 44 1/9/2014 K-40 19.28 +/- 0.57 19.24 +/- 0.57 19.26 +/- 0.40 Pass SG-64, 65 1/9/2014 Gr. Alpha 686.08 +/- 69.97 642.46 +/- 65.59 664.27 +/- 47.95 Pass SG-64, 65 119/2014 Ra-226 97.30 +/- 9.78 92.20 +/- 9.27 94.75 +/- 6.74 Pass SG-64, 65 1/9/2014 Ra-228 91.90 +/- 9.30 97.10 +/- 9.87 94.50 +/- 6.78 Pass S-136, 137 1/13/2014 Be-7 14.90 +/- 0.39 14.88 +/- 0.38 14.89 +/- 0.27 Pass S-136, 137 1/13/2014 K-40 3.29 +/- 0.36 3.93 +/- 0.36 3.61 +/- 0.25 Pass WW-220,221 1/13/2014 H-3 231.85 +/- 80.45 273.46 + 82.47 252.66 +/- 57.60 Pass WW-262,263 1/21/2014 H-3 294.80 +/- 89.80 265.00 +/- 88.47 279.90 +/- 63.03 Pass WW-346, 347 1/24/2014 H-3 934.97 +/- 118.47 965.59 +/- 119.52 950.28 +/- 84.14 Pass SWU-367, 368 1/29/2014 Gr. Beta 0.74 +/- 0.38 1.31 +/- 0.42 1.02 +/- 0.28 Pass F-409, 410 212/2014 Cs- 137 0.05 +/- 0.02 0.05 +/- 0.02 0.05 +/- 0.01 Pass F-409, 410 2/2/2014 Gr. Beta 3.60 +/- 0.07 3.72 +/- 0.07 3.66 +/- 0.05 Pass AP-7829, 7830 1/2/2014 Be-7 0.08 +/- 0.02 0.06 +/- 0.01 0.07 +/- 0.01 Pass AP-7913, 7914 1/2/2014 Be-7 0.07 +/- 0.01 0.06 +/- 0.01 0.06 +/- 0.01 Pass AP-7871, 7872 1/3/2014 Be-7 0.05 +/- 0.02 0.06 +/- 0.01 0.06 +/- 0.01 Pass S-43, 44 119/2014 K-40 19.28 +/- 0.57 19.24 + 0.57 19.26 +/- 0.40 Pass SG-64, 65 1/9/2014 Gr. Alpha 686.08 +/- 69.97 642.46 +/- 65.59 664.27 +/- 47.95 Pass SG-64, 65 1/9/2014 Ra-226 97.30 +/- 9.78 92.20 +/- 9.27 94.75 +/- 6.74 Pass SG-64, 65 1/9/2014 Ra-228 91.90 +/- 9.30 97.10 +/- 9.87 94.50 +/- 6.78 Pass S-136, 137 1/13/2014 Be-7 14.90 +/- 0.39 14.88 +/- 0.38 14.89 +/- 0.27 Pass S-136, 137 1/13/2014 K-40 3.29 +/- 0.36 3.93 +/- 0.36 3.61 +/- 0.25 Pass WW-220, 221 1/13/2014 H-3 231.85 +/- 80.45 273.46 +/- 82.47 252.66 +/- 57.60 Pass WW-262, 263 1/21/2014 H-3 294.80 +/- 89.80 265.00 +/- 88.47 279.90 +/- 63.03 Pass WW-346, 347 1/24/2014 H-3 934.97 +/- 118.47 965.59 +/- 119.52 950.28 +/- 84.14 Pass SWU-367, 368 1/29/2014 Gr. Beta 0.74 +/- 0.38 1.31 00.42 1.02 +/- 0.28 Pass F-409, 410 2/2/2014 Cs-1 37 0.05 +/- 0.02 0.05 +/- 0.02 0.05 +/- 0.01 Pass F-409, 410 2/2/2014 Gr. Beta 3.60 +/- 0.07 3.72 +/- 0.07 3.66 +/- 0.05 Pass WW-491, 492 2/612014 H-3 474.00 +/- 101.10 583.10 +/- 105.30 528.55 +/- 72.99 Pass WW-575, 576 2/13/2014 H-3 196.69 +/- 82.94 154.68 +/- 80.89 175.69 +/- 57.93 Pass W-617, 618 2/14/2014 H-3 526.29 +/- 97.65 579.51 +/- 99.77 552.90 +/- 69.80 Pass SWU-743, 744 2/25/2014 Gr. Beta 1.61 +/- 0.65 1.73 +/- 0.71 1.67 +/- 0.48 Pass S-700, 701 2/26/2014 K-40 21.32 +/- 0.64 21.15 +/- 0.59 21.24 +/- 0.44 Pass S-806, 807 3/4/2014 K-40 24.79 +/- 0.57 24.17 +/- 0.59 24.48 +/- 0.41 Pass SG-928, 929 3/11/2014 Ac-228 6.78 +/- 0.34 6.94 +/- 0.35 6.86 +/- 0.24 Pass SG-928, 929 3/11/2014 Bi-214 5.32 +/- 0.20 5.34 +/- 0.22 5.33 +/- 0.15 Pass SG-928, 929 3/11/2014 K-40 4.79 +/- 0.80 6.24 +/- 1.01 5.52 +/- 0.64 Pass SG-928, 929 3/11/2014 Pb-212 2.70 +/- 0.09 2.75 +/- 0.09 2.73 +/- 0.06 Pass SG-928, 929 3/11/2014 Pb-214 5.39 + 0.17 5.53 +/- 0.17 5.46 +/- 0.12 Pass SG-928, 929 3/11/2014 Th-228 6.10 +/- 2.07 4.76 +/- 1.93 5.43 +/- 1.42 Pass SG-928, 929 3/11/2014 T1-208 0.92 +/- 0.06 0.91 +/- 0.06 0.92 +/- 0.04 Pass A5-1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance S-2119, 2120 3/12/2014 Ac-228 0.76 +/- 0.20 0.73 +/- 0.21 0.75 +/- 0.15 Pass S-2119, 2120 3/12/2014 Cs-137 0.13 +/-0.05 0.11 +/- 0.05 0.12 +/- 0.04 Pass S-2119, 2120 3/12/2014 K-40 17.48 +/- 1.48 18.39 +/- 1.53 17.94 +/- 1.06 Pass S-2119, 2120 3/12/2014 Pb-214 0.73 +/- 0.18 0.63 +/- 0.12 0.68 +/- 0.11 Pass F-1594, 1595 3/16/2014 Cs- 137 0.02 +/- 0.01 0.03 +/- 0.02 0.03 +/- 0.01 Pass SO-1115,1116 3/1812014 Cs-1 37 0.06 +/- 0.01 0.06 +/- 0.00 0.06 +/- 0.00 Pass SO-1115, 1116 3/18/2014 Gr. Beta 23.30 +/- 2.10 24.40 +/- 2.20 23.85 +/- 1.52 Pass SO-1115, 1116 3/18/2014 K-40 12.63 +/-0.18 12.84 +/-0.15 12.74 +/-0.12 Pass SO-1115, 1116 3/18/2014 U-233/4 0.11 +/- 0.02 0.12 +/- 0.02 0.12 +/- 0.01 Pass SO-1115, 1116 3/18/2014 U-238 0.13 +/- 0.02 0.14 +/- 0.02 0.14 +/- 0.01 Pass S-1033,1034 3/19/2014 Ac-228 0.99 +/- 0.20 1.13 +/- 0.26 1.06 +/- 0.16 Pass S-1033,1034 3/19/2014 Bi-214 1.02 +/- 0.18 0.98 +/- 0.16 1.00 +/- 0.12 Pass S-1033,1034 3/19/2014 Cs-137 0.15 +/- 0.04 0.14 +/- 0.04 0.15 +/- 0.03 Pass S-1033,1034 3/19/2014 K-40 15.39 +/- 1.19 15.13 +/- 1.19 15.26 +/- 0.84 Pass S-1033,1034 3/19/2014 Pb-214 1.09 +/- 0.13 0.88 +/- 0.17 0.99 +/- 0.11 Pass S-1 033, 1034 3/19/2014 TI-208 0.36 +/- 0.05 0.31 +/- 0.05 0.34 +/- 0.04 Pass W-1094,1095 3/23/2014 Ra-226 0.30 +/- 0.20 0.70 +/- 0.20 0.50 +/- 0.14 Pass W-1094,1095 3/23/2014 Ra-228 1.10 +/- 0.79 1.13 +/- 0.86 1.12 +/-0.58 Pass AP-1197, 1198 3/27/2014 Be-7 0.17 +/- 0.08 0.14 +/--0.08 0.15 +/- 0.05 Pass AP-1698,1699 3/31/2014 Be-7 0.06 +/- 0.02 0.07 +/- 0.02 0.07 +/- 0.01 Pass E-1218,1219 4/1/2014 Gr. Beta 1.57 +/- 0.04 1.57 +/- 0.04 1.57 +/- 0.03 Pass E-1218,1219 4/1/2014 K-40 1.26 +/- 0.14 1.31 +/- 0.18 1.29 +/-0.11 Pass SWU-1260,1261 4/11/2014 Gr. Beta 2.81 +/- 0.51 2.94 +/- 0.50 2.88 +/- 0.36 Pass AP-1615,1616 4/1/2014 Be-7 0.07 +/- 0.01 0.07 +/- 0.02 0.07 +/- 0.01 Pass AP-1657,1658 4/2/2014 Be-7 0.07 +/- 0.01 0.08 +/- 0.01 0.07 +/- 0.01 Pass AP-1804,1805 4/3/2014 Be-7 0.05 +/- 0.02 0.06 +/- 0.01 0.06 +/- 0.01 Pass P-1489,1490 4/7/2014 H-3 582.31 +/- 101.85 505.07 +/- 98.72 543.69 +/- 70.92 Pass BS-1531, 1532 4/16/2014 K-40 0.51 +/- 0.19 0.58 +/- 0.23 0.54 +/- 0.15 Pass S-1909,1910 4/22/2014 K-40 14.71 +/- 0.54 14.78 +/- 0.53 14.75 +/- 0.38 Pass SWU-1867,1868 4/29/2014 Gr. Beta 2.28 +/- 0.40 1.67 +/- 0.35 1.98 +/- 0.27 Pass AP-1930, 1931 5/1/2014 Be-7 0.16 +/-0.09 0.19 +/- 0.11 0.17 +/- 0.07 Pass SL-1888, 1889 5/1/2014 Be-7 0.80 +/- 0.04 0.76 +/- 0.08 0.78 +/- 0.05 Pass SL-1888, 1889 5/1/2014 Cs-137 0.01 +/- 0.00 0.01 +/- 0.00 0.01 +/- 0.00 Pass SL-1888, 1889 5/11/2014 Gr. Beta 11.57 +/- 0.72 12.67 +/- 0.78 12.12 +/- 0.53 Pass SL-1888, 1889 5/112014 K-40 1.04 +/- 0.05 1.00 +/- 0.09 1.02 +/- 0.05 Pass SO-1972, 1973 5/1/2014 Cs- 137 0.12 +/- 0.03 0.10 +/- 0.02 0.11 +/- 0.02 Pass SO-1972, 1973 5/112014 Gr. Alpha 7.51 +/- 3.24 9.09 +/- 3.63 8.30 +/- 2.43 Pass SO-1972, 1973 5/1/2014 Gr. Beta 29.89 +/- 3.25 31.42 +/- 3.04 30.66 +/- 2.23 Pass SO-1972,1973 5/1/2014 K-40 20.45 +/- 0.85 20.88 +/- 0.76 20.66 +/- 0.57 Pass W-617, 618 5/8/2014 H-3 175.13 +/- 83.82 177.17 +/- 83.92 176.15 +/- 59.31 Pass AP-2077, 2078 5/8/2014 Be-7 0.23 +/- 0.11 0.18 +/- 0.11 0.20 +/- 0.08 Pass A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance S-2205, 2206 5/15/2014 Be-7 0.50 +/- 0.19 0.70 +/- 0.18 0.60 +/- 0.13 Pass S-2205, 2206 5/15/2014 K-40 33.60 +/- 0.79 33.52 +/- 0.70 33.56 +/- 0.53 Pass VE-2184, 2185 5/19/2014 Be-7 0.62 +/- 0.18 0.53 +/-0.17 0.58 +/- 0.12 Pass VE-2184, 2185 5/19/2014 K-40 5.30 +/- 0.44 5.14 +/- 0.44 5.22 +/- 0.31 Pass DW-50102, 50103 5/20/2014 Ra-226 7.07 +/- 0.76 8.31 +/- 0.90 7.69 +/- 0.59 Pass DW-50102, 50103 5/20/2014 Ra-228 5.44 +/- 0.85 6.02 +/- 0.67 5.73 +/- 0.54 Pass SW-2226,2227 5/21/2014 H-3 14318.00 +/- 347.00 14350.00 +/- 347.00 14334.00 +/- 245.37 Pass DW-50087, 50088 5/21/2014 Gr. Alpha 1.76 +/- 1.09 2.67 +/- 1.01 2.22 +/- 0.74 Pass DW-50090, 50091 5/21/2014 Ra-226 0.61 +/- 0.09 0.47 +/- 0.09 0.54 +/- 0.06 Pass DW-50090, 50091 5/2112014 Ra-228 0.97 +/- 0.41 1.26 +/- 0.52 1.12 +/-0.33 Pass DW-50098, 50099 5/21/2014 Gr. Alpha 13.04 +/- 1.36 10.76 +/- 1.26 11.90 +/- 0.93 Pass AP-2289, 2290 5/22/2014 Be-7 0.14 +/- 0.08 0.24 +/-0.10 0.19 +/- 0.06 Pass PM-3174, 3175 5/28/2014 K-40 30.68 +/- 1.30 32.64 +/- 1.24 31.66 +/- 0.90 Pass G-2415, 2416 6/2/2014 Be-7 0.73 +/- 0.16 0.62 +/- 0.28 0.68 +/- 0.16 Pass G-2415, 2416 6/2/20 14 Gr. Beta 5.89 +/- 0.09 5.90 +/- 0.09 5.89 +/- 0.06 Pass G-2415, 2416 6/2/2014 K-40 5.30 +/- 0.49 5.19 +/- 0.65 5.25 +/- 0.41 Pass WW-2541, 2542 6/4/2014 H-3 5107.00 +/- 223.00 5029.00 +/- 222.00 5068.00 +/- 157.33 Pass SW-2817, 2818 6/16/2014 H-3 13303.00 +/- 336.00 13130.00 +/- 334.00 13216.50 +/- 236.88 Pass SS-2943, 2944 6/24/2014 K-40 11.49 +/- 0.79 11.81 +/- 0.70 11.65 +/- 0.53 Pass S-3048, 3049 612712014 K-40 42.51 +/- 1.31 40.04 +/- 1.39 41.28 +/- 0.95 Pass SWT-3216, 3217 7/1/2014 Gr. Beta 2.27 +/- 0.94 2.53 +/- 1.05 2.40 +/- 0.70 Pass AP-3699,3700 7/3/2014 Be-7 0.06 +/- 0.01 0.07 +/- 0.02 0.07 +/- 0.01 Pass S-3300, 3301 7/8/2014 K-40 4.85 +/- 0.97 5.91 +/- 1.17 5.38 +/- 0.76 Pass S-3300,3301 7/8/2014 Ac-228 10.23 +/- 0.43 10.18 +/- 0.32 10.21 +/- 0.27 Pass S-3300, 3301 7/8/2014 Ra-226 70.14 +/- 2.37 72.01 +/- 2.38 71.08 +/- 1.68 Pass VE-3237,3238 7/8/2014 K-40 2.54 +/- 0.27 2.63 +/- 0.24 2.59 +/- 0.18 Pass CF-3384,3385 7/14/2014 K-40 11.10 +/- 0.58 10.69 +/- 0.60 10.90 +/- 0.42 Pass S-3447,3448 7/16/2014 K-40 19.63 +/- 0.64 21.03 +/- 0.96 20.33 +/- 0.58 Pass WW-3573,3574 7/18/2014 H-3 381.58 +/- 85.76 401.30 +/- 86.67 391.44 +/- 60.96 Pass VE-3594,3595 7122/2014 K-40 3.04 +/- 0.19 3.21 +/- 0.15 3.13 +/- 0.12 Pass WW-3762,3763 7/25/20 14 H-3 315.47 +/- 87.02 327.30 +/- 87.56 321.39 +/- 61.72 Pass SWT-3867, 3868 7/29/2014 Gr. Beta 1.10 +/- 0.53 1.51 +/- 0.58 1.31 +/- 0.39 Pass S-3804,3805 7/30/2014 Ac-228 0.67 +/- 0.11 0.61 +/-0.10 0.64 +/- 0.07 Pass S-3804, 3805 7/30/2014 Pb-214 0.56 +/- 0.05 0.51 +/- 0.04 0.54 +/- 0.03 Pass LW-3931, 3932 7/31/2014 Gr. Beta 1.04 +/- 0.40 0.95 +/- 0.41 1.00 +/- 0.29 Pass A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result Acceptance G-3952,3953 8/4/2014 K-40 5.42 +/- 0.42 5.35 +/- 0.34 5.38 +/- 0.27 Pass G-3952,3953 8/4/2014 Be-7 1.29 +/- 0.19 1.24 +/- 0.16 1.27 +/- 0.13 Pass G-3952,3953 8/4/2014 Gr. Beta 8.53 +/- 0.20 8.63 - 0.20 8.58 +/- 0.14 Pass G-3952,3953 8/4/2014 H-3 140.16 +/- 93.50 127.25 + 92.99 133.70 +/- 65.94 Pass WW-4036, 4037 8/5/2014 H-3 190.60 +/- 82.60 164.70 - 81.30 177.65 +/- 57.95 Pass VE-4204,4205 8/11/2014 K-40 6.28 +/- 0.38 6.60 - 0.37 6.44 +/- 0.27 Pass WW-4394,4395 8/13/2014 H-3 1540.26 +/- 136.52 1499.15 + 135.43 1519.71 +/- 96.15 Pass VE-4183,4184 8/14/2014 K-40 5.70 +/- 0.41 5.73 +/- 0.34 5.72 +/- 0.27 Pass AV-4455, 4456 8/22/2014 Be-7 286.67 +/- 102.30 251.99 +/- 98.94 269.33 +/- 71.16 Pass AV-4455, 4456 8/22/2014 K-40 2547.90 +/- 255.70 2201.40 +/- 203.90 2374.65 +/- 163.52 Pass WW-4500, 4501 8/26/2014 H-3 347.00 +/- 100.00 321.00 +/- 98.00 334.00 +/- 70.01 Pass AP-090214AiB 9/2/2014 Gr. Beta 0.03 +/- 0.04 0.03 +/- 0.04 0.03 +/- 0.00 Pass SG-5089, 5090 9/19/2014 Ac-228 8.26 +/- 0.63 9.48 +/- 0.68 8.87 +/- 0.46 Pass SG-5089, 5090 9/19/2014 Bi-214 4.71 +/- 0.29 4.41 +/- 0.31 4.56 +/- 0.21 Pass SG-5194,5 10/1/2014 Gr. Alpha 276.20 +/- 9.51 258.60 +/- 9.26 267.40 +/- 6.64 Pass SG-5194,5 10/1/2014 Pb-214 43.56 +/- 0.73 43.94 +/- 0.78 43.75 +/- 0.53 Pass SG-5194,5 10/11/2014 Ac-228 59.90 +/- 1.37 62.80 +/- 1.73 61.35 +/- 1.10 Pass S-5632,3 10/8/2014 K-40 19.28 +/- 0.88 17.94 +/- 0.89 18.61 - 0.63 Pass S-5632,3 10/8/2014 Cs-137 0.15 +/- 0.03 0.13 +/- 0.03 0.14 +0.02 Pass S-5632,3 10/8/2014 TI-208 0.32 +/- 0.03 0.34 +/- 0.03 0.33 + 0.02 Pass S-5632,3 10/8/2014 Pb-212 0.92 +/- 0.05 0.92 +/- 0.05 0.92 _ 0.03 Pass S-5632,3 10/8/2014 Pb-214 1.25 +/- 0.08 1.09+/- 0.09 1.17 +/- 0.06 Pass S-5632,3 10/8/2014 Bi-212 1.25 +/- 0.29 1.34 +/- 0.47 1.29 - 0.27 Pass S-5632,3 10/8/2014 Ac-228 1,08 +/- 0.14 1.10 +/-.0.14 1.09 + 0.10 Pass DW-50243,4 10/13/2014 Gr. Alpha 2.99 +/- 0.94 4.98 + 1.17 3.99 +/- 0.75 Pass AP-101414A/B 10/14/2014 Gr. Beta 0.02 +/- 0.00 0.02 +/- 0.00 0.02 +/- 0.00 Pass SG-5590,1 10/15/2014 Pb-214 80.30 +/- 8.08 73.40 +/- 7.51 76.85 +/- 5.52 Pass SG-5590,1 10/15/2014 Ac-228 64.50 +/- 1.87 62.80 1.15 63.65 + 1.10 Pass DW-50251,2 10/16/2014 Ra-226 0.55 +/- 0.13 0.32 +/-.0.10 0.44 +/- 0.08 Pass U-5842,3 10/20/2014 H-3 7376 +/- 949 7342 +/-947 7359 +/- 670 Pass CF-6074,5 10/21/2014 H-3 7509 +/-283 7969 +/- 291 7739 +/- 203 Pass CF-6074,5 10/21/2014 K-40 3.09 +/- 0.31 3.30 +/- 0.38 3.20 +/- 0.25 Pass A5-4

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

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

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits C Acceptance MAW-1140 2/1/2014 Gr. Alpha 0.77 +/- 0.06 0.85 0.26 - 1.44 Pass MAW-1140 2/1/2014 Gr. Beta 4.31 +/- 0.08 4.19 2.10 - 6.29 Pass MAW-1142 2/1/2014 1-129 -0.01 +/- 8.00 0.00 NA Pass MAW-1184 2/1/2014 Fe-55 0.40 +/- 3.20 0.00 -0.01 - 2.00 Pass MAW-1184 2/1/2014 H-3 345.10 +/- 10.60 321.00 225.00 - 417.00 Pass MAW-1184 2/1/2014 Ni-63 32.40 +/- 3.20 34.00 23.80 - 44.20 Pass MAW-i 184 e 2/1/2014 Pu-238 1.28 +/- 0.12 0.83 0.58 - 1.08 Fail MAW-1184 2/1/2014 Pu-239/240 0.91 +/- 0.10 0.68 0.47 - 0.88 Fail MAW-1184 2/1/2014 Sr-90 7.00 +/- 0.70 8.51 5.96-11.06 Pass MAW-1184 2/1/2014 Tc-99 8.10 +/- 0.60 10.30 7.20 - 13.40 Pass MAW-1 184 2/1/2014 U-233/234 0.20 +/- 0.07 0.23 0.16 -0.29 Pass MAW-1184 2/1/2014 U-238 1.25 +/- 0.18 1.45 1.02 -1.89 Pass MAW-1184 2/1/2014 Co-57 27.86 +/- 0.38 27.50 19.30 - 35.80 Pass MAW-1 184 2/1/2014 Co-60 15.99 +/- 0.27 16.00 11.20 - 20.80 Pass MAW-1184 2/1/2014 Cs-134 21.85 +/- 0.54 23.10 16.20 - 30.00 Pass MAW-1184 2/1/2014 Cs-137 28.74 +/- 0.49 28.90 20.20 - 37.60 Pass MAW-1184 2/1/2014 K-40 1.80 +/- 2.00 0.00 0.00 - 10.00 Pass MAW-1 184 2/1/2014 Mn-54 14.06 +/- 0.40 13.90 9.70 - 18.10 Pass MAW-1184 2/1/2014 Zn-65 0.00 +/- 0.19 0.00 -0.01 - 0.00 Pass MAVE-1 148 2/1/2014 Co-57 11.63 +/- 0.19 10.10 7.10 - 13.10 Pass MAVE-1 148 2/1/2014 Co-60 7.28 +/- 0.18 6.93 4.85 - 9.01 Pass MAVE-1 148 2/1/2014 Cs-134 6.29 +/- 0.29 6.04 4.23 - 7.85 Pass MAVE-1 148 2/1/2014 Cs-I 37 5.18 +/- 0.20 4.74 3.32 -6.16 Pass MAVE-1 148 2/1/2014 Mn-54 9.22 +/- 0.26 8.62 6.03 - 11.21 Pass MAVE-1 148 2/1/2014 Zn-65 8.59 +/- 0.40 7.86 5.50 - 10.22 Pass MAAP-1 151 2/1/2014 Am-241 0.09 +/- 0.02 0.09 0.06 -0.12 Pass MAAP-1151 d 2/1/2014 Co-57 1.60 +/- 0.05 0.00 NA Fail MAAP-1 151 2/1/2014 Co-60 1.38 +/- 0.08 1.39 0.97 - 1.81 Pass MAAP-1 151 2/1/2014 Cs-1 34 1.75 +/-0.11 1.91 1.34 - 2.48 Pass MAAP-1 151 2/1/2014 Cs-1 37 1.81 +/- 0.10 1.76 1.23 -2.29 Pass MAAP-1 151 2/1/2014 Mn-54 0.01 +/- 0.03 0.00 NA Pass MAAP-1151 2/1/2014 Pu-238 0.08 +/- 0.02 0.00 NA Fail MAAP-1 151 2/1/2014 Pu-239/240 0.10 +/- 0.02 0.08 0.05 -0.10 Pass MAAP-1 151 2/1/2014 Zn-65 -0.24 +/- 0.09 0.00 -0.50 - 1.00 Pass A6-1

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

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits C Acceptance MAAP-1151 2/1/2014 U-233/234 0.03 +/- 0.01 0.02 0.01 - 0.03 Pass MAAP-1 151 2/1/2014 U-238 0.13 +/- 0.02 0.13 0.09 -0.17 Pass MAAP-1 151 2/1/2014 Sr-90 1.11 +/- 0.14 1.18 0.83 -1.53 Pass MAAP-1 154 2/1/2014 Gr. Alpha 0.56 +/- 0.06 1.77 0.53 - 3.01 Pass MAAP-1 154 2/1/2014 Gr. Beta 0.98 +/- 0.06 0.77 0.39-1.16 Pass MASO-1 146 2/1/2014 Co-57 1064.50 +/- 3.60 966.00 676.00 - 1256.00 Pass MASO-1 146 2/1/2014 Co-60 1.70 +/- 0.50 1.22 NA d Pass MASO-1 146' 2/1/2014 Cs-1 34 6.10 +/- 1.80 0.00 NA Fail MASO-1 146 2/1/2014 Cs-1 37 1364.30 +/- 5.30 1238.00 867.00 - 1609.00 Pass MASO-1 146 2/1/2014 K-40 728.90 +/- 15.90 622.00 435.00 - 809.00 Pass MASO-1 146 2/1/2014 Mn-54 1588.00 +/- 6.00 1430.00 1001.00 - 1859.00 Pass MASO-1 146 2/1/2014 Zn-65 763.50 +/- 6.80 695.00 487.00 - 904.00 Pass MASO-1 146 2/1/2014 Am-241 68.20 +/- 9.00 68.00 47.60 - 88.40 Pass MASO-1 146 2/1/2014 Ni-63 4.80 +/- 15.30 0.00 NA Pass MASO-1146 a 2/1/2014 Pu-238 140.60 +/- 15.50 96.00 67.00 - 125.00 Fail MASO-1 146 " 2/1/2014 Pu-239/240 102.00 +/- 13.10 76.80 53.80 - 99.80 Fail MASO-1 146 2/1/2014 Sr-90 1.23 +/- 1.37 0.00 NA Pass MASO-1 146 2/1/2014 Tc-99 -0.30 +/- 12.00 0.00 NA Pass MASO-1 146 2/11/2014 U-233/234 22.90 +/- 3.00 81.00 57.00 - 105.00 Fail MASO-1146 9 2/11/2014 U-238 32.00 +/- 3.60 83.00 58.00 - 108.00 Fail MASO-4439 8/1/2014 Am-241 65.90 +/- 6.70 85.50 59.90 - 111.20 Pass MASO-4439 8/1/2014 Ni-63 771.62 +/- 23.29 980.00 686.00 - 1274.00 Pass MASO-4439 8/1/2014 Pu-239/240 55.63 +/- 5.81 58.60 41.00 - 76.20 Pass MASO-4439 8/1/2014 Sr-90 778.34 +/- 17.82 858.00 601.00 - 1115.00 Pass MASO-4439 8/11/2014 Tc-99 458.20 +/- 9.20 589.00 412.00 - 766.00 Pass MASO-4439 8/1/2014 Cs-134 520.60 +/- 7.09 622.00 435.00 - 809.00 Pass MASO-4439 8/1/2014 Co-57 1135.00 +/- 7.40 1116.00 781.00 - 1451.00 Pass MASO-4439 8/1/2014 Co-60 768.20 +/- 7.70 779.00 545.00 - 1013.00 Pass MASO-4439 8/1/2014 Mn-54 1050.70 +/- 12.60 1009.00 706.00 - 1312.00 Pass MASO-4439 8/1/2014 Zn-65 407.89 +/- 15.03 541.00 379.00 - 703.00 Pass MAW-4431 8/1/2014 Am-241 0.79 +/- 0.08 0.88 0.62-1.14 Pass MAW-4431 8/11/2014 Cs-137 18.62 +/- 0.54 18.40 12.90 - 23.90 Pass MAW-4431 8/1/2014 Co-57 24.85 +/- 0.42 24.70 17.30 - 32.10 Pass MAW-4431 8/1/2014 Co-60 12.27 +/- 0.38 12.40 8.70 -16.10 Pass MAW-4431 8/1/2014 H-3 207.20 +/- 10.60 208.00 146.00 - 270.00 Pass h

MAW-4431 8/1/2014 Fe-55 55.10 +/- 14.80 31.50 22.10 - 41.00 Fail MAW-4431 8/1/2014 Mn-54 14.36 +/- 0.53 14.00 9.80 - 18.20 Pass MAW-4431 8/1/2014 Zn-65 11.46 +/- 0.78 10.90 7.60 - 14.20 Pass A6-2

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

Concentration a Known Control Lab Code b Date Analysis Laboratory result Activity Limits C Acceptance MAW-4431 8/1/2014 Tc-99 6.10 +/- 0.50 6.99 4.89 - 9.09 Pass MAW-4431 8/1/2014 Pu-238 0.59 +/- 0.07 0.62 0.43 - 0.80 Pass MAW-4431 8/1/2014 U-233/234 0.22 +/- 0.04 0.21 0.14 - 0.27 Pass MAW-4431 8/1/2014 U-238 1.25 +/- 0.10 1.42 0.99 -1.85 Pass MAW-4493 8/1/20114 Gr. Alpha 0.93 +/- 0.07 1.40 0.42 - 2.38 Pass MAW-4493 8/1/2014 Gr. Beta 6.31 +/- 1.35 6.50 3.25 -9.75 Pass MAAP-4433 8/1/2014 Am-241 0.06 +/- 0.02 0.07 0.05 - 0.09 Pass MAAP-4433 8/1/2014 Pu-238 0.10 +/- 0.03 0.11 0.08 - 0.14 Pass MAAP-4433 8/1/2014 Pu-239/240 0.04 +/- 0.02 0.05 0.03 - 0.06 Pass MAAP-4433 8/1/2014 Sr-90 0.74 +/- 0.10 0.70 0.49 - 0.91 Pass MAAP-4433 8/1/20114 U-233/234 0.03 +/- 0.01 0.04 0.03 - 0.05 Pass MAAP-4433 8/1/2014 U-238 0.21 +/- 0.03 0.25 0.18 - 0.33 Pass MAAP-4444 8/1/2014 Sr-89 7.82 +/- 0.52 9.40 6.60 - 12.20 Pass MAAP-4444 8/1/2014 Sr-90 0.76 +/- 0.10 0.76 0.53 - 0.99 Pass MAVE-4436 811/2014 Cs-134 7.49 +/- 0.18 7.38 5.17 -9.59 Pass MAVE-4436 8/1/2014 Co-57 11.20 +/- 0.19 9.20 6.40-12.00 Pass MAVE-4436 8/1/2014 Co-60 6.84 +/- 0.17 6.11 4.28 -7.94 Pass MAVE-4436 8/1/2014 Mn-54 8.11 +/- 0.26 7.11 4.97 - 9.23 Pass MAVE-4436 8/1/2014 Zn-65 7.76 +/- 0.43 6.42 4.49 - 8.35 Pass a Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

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

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

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

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

The results of reanalysis with replacement tracer purchased from NIST:

MAW-1184 Pu-238 0.68 +/- 0.10 Bq / L MAW-1184 Pu-239/240 0.66 +/- 0.10 Bq / L MASO-1146 Pu-238 95.15 +/- 8.98 Bq / kg MASO-1146 Pu-239/240 67.21 +/- 7.54 Bq / kg Insufficient sample remained to reanalyze the Air filter sample(MAAP-1151). High bias results due to same contaminated tracer f Cs-1 34 was positively identified in both library peaks, calculation on the second peak; 2.78 +/- 0.93 Bq/kg.

g 80% of participating laboratories were outside the acceptable range, Parallel reanalysis was run on ERA spiked sample with acceptable results.

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

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

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result C Result d Limits Acceptance ERAP-1044 3/17/2014 Am-241 54.2 + 3.0 59.7 36.8 - 80.8 Pass ERAP-1044 3/1712014 Co-60 1177.9 + 14.3 1120.0 867.0 - 1400.0 Pass ERAP-1044 3/17/2014 Cs-134 1010.5 +/- 15.8 1010.0 643.0 - 1250.0 Pass ERAP-1044 3/17/2014 Cs-137 938.3 +/- 45.7 828.0 622.0 - 1090.0 Pass ERAP-1044 3/17/2014 Fe-55 142.3 + 87.3 240.0 74.4 - 469.0 Pass ERAP-1044 3/17/2014 Gr. Alpha 52.3 + 0.5 46.0 15.4 -71.4 Pass ERAP-1044 3/17/2014 Gr. Beta 64.4 +/-2.6 53.8 34.0 - 78.4 Pass ERAP-1044 3/17/2014 Mn-54 < 4.9 0.0 NA Pass ERAP-1044 3/17/2014 Pu-238 63.0 +/- 2.6 56.3 38.6 - 74.0 Pass ERAP-1044 3/17/2014 Pu-239/240 52.8 +/- 1.9 48.6 35.2 - 63.5 Pass ERAP-1044 3/17/2014 Sr-90 81.4 +/- 1.6 78.9 38.6 - 118.0 Pass ERAP-1044 3/17/2014 U-233/234 30.4 +/- 1.7 36.4 22.6 - 54.9 Pass ERAP-1044 3/17/2014 U-238 30.4 +/- 1.4 36.1 23.3 -49.9 Pass ERAP-1044 3/17/2014 Uranium 62.0 +/- 3.5 74.3 41.1 -113.0 Pass ERAP-1044 3/17/2014 Zn-65 852.2 +/- 26.1 667.0 478.0 -921.0 Pass ERSO-1050 3/17/2014 Am-241 426.6 +/- 155.5 399.0 233.0 -518.0 Pass ERSO-1050 3/17/2014 Ac-228 1260.0 +/- 107.0 1240.0 795.0 - 1720.0 Pass ERSO-1050 3/17/2014 Bi-212 1331.9 +/- 309.7 1240.0 330.0 - 1820.0 Pass ERSO-1050 3/17/2014 Bi-214 1804.5 +/- 50.4 1960.0 1180.0 -2820.0 Pass ERSO-1050 3/17/2014 Co-60 6738.8 +/- 167.6 6830.0 4620.0 - 9400.0 Pass ERSO-1050 3/17/2014 Cs-134 3262.9 +/- 108.8 3390.0 2220.0 - 4070.0 Pass ERSO-1050 3/17/2014 Cs-137 8538.6 +/- 55.0 8490.0 6510.0 -10900.0 Pass ERSO-1050 3/17/2014 K-40 11241.3 _ 296.6 10500.0 7660.0 - 14100.0 Pass ERSO-1050 3/17/2014 Mn-54 < 21.6 0.0 NA Pass ERSO-1050 3/17/2014 Pb-212 1119.6 +/-_26.1 1240.0 812.0 - 1730.0 Pass ERSO-1050 3/17/2014 Pb-214 1861.7 +/- 54.9 2070.0 1210.0 - 3090.0 Pass ERSO-1050 e 3/17/2014 Pu-238 1085.5 +/- 167.7 578.0 348.0 - 797.0 Fail ERSO-1050 3/17/2014 Pu-239/240 681.6 +/- 128.6 471.0 308.0 -651.0 Fail ERSO-1050 3/17/2014 Sr-90 2338.0 +/- 144.0 2780.0 1060.0 -4390.0 Pass ERSO-1050 3/17/2014 Th-234 3474.9 t 226.0 3360.0 1060.0 - 6320.0 Pass ERSO-1050 3/17/2014 U-233/234 3319.5 +/- 250.2 2780.0 1060.0 - 4390.0 Pass ERSO-1050 3/17/2014 U-238 3375.6 +/- 252.6 3360.0 2080.0 - 4260.0 Pass ERSO-1050 3/17/2014 Uranium 6810.6 +/- 551.1 6910.0 3750.0 - 9120.0 Pass ERSO-1050 3/17/2014 Zn-65 5968.0 +/- 226.1 5400.0 4300.0 - 7180.0 Pass A7-1

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

Concentration (pCi/L) b Lab Code b Date Analysis Laboratory ERA Control Result C Result d Limits Acceptance ERVE-1051 3/17/2014 Am-241 1532.0 +/- 149.5 1490.0 911.0 - 1980.0 Pass ERVE-1051 3/17/2014 Cm-244 519.8 +/- 94.6 516.0 253.0 - 804.0 Pass ERVE-1051 3/17/2014 Co-60 981.2 +/- 41.8 926.0 639.0 - 1290.0 Pass ERVE-1051 3/17/2014 Cs-134 701.4 +/- 58.6 646.0 415.0 - 839.0 Pass ERVE-1051 3/17/2014 Cs-137 961.9 +/- 46.3 880.0 638.0 - 1220.0 Pass ERVE-1051 3/17/2014 K-40 32789.7 +/- 758.2 31900.0 23000.0 - 44800.0 Pass ERVE-1051 3/17/2014 Mn-54 < 25.9 0.0 NA Pass ERVE-1051 3/17/2014 Pu-238 2724.1 +/- 259.4 2110.0 1260.0 -2890.0 Pass ERVE-1051 3/17/2014 Pu-239/240 4361.4 +/- 323.4 3740.0 2300.0 -5150.0 Pass ERVE-1051 3/17/2014 Sr-90 2405.7 +/- 263.2 2580.0 1470.0 - 3420.0 Pass ERVE-1051 3/17/2014 U-233/234 1612.2 +/- 162.0 1760.0 1160.0 - 2260.0 Pass ERVE-1051 3/17/2014 U-238 1574.3 +/- 159.6 1750.0 1170.0 - 2220.0 Pass ERVE-1051 3/17/2014 Uranium 3255.4 +/- 356.7 3580.0 2430.0 - 4460.0 Pass ERVE-1051 3/17/2014 Zn-65 1124.1 +/- 101.2 919.0 663.0 - 1290.0 Pass ERW-1054 3/17/2014 Am-241 104.6 +/- 3.4 114.0 76.8 - 153.0 Pass ERW-1054 3/17/2014 Co-60 1195.2 +/- 18.9 1270.0 1100.0 - 1490.0 Pass ERW-1054 3/17/2014 Cs-134 1474.9 +/- 47.5 1660.0 1220.0 - 1910.0 Pass ERW-1054 3/17/2014 Cs-137 2591.0 +/- 23.4 2690.0 2280.0 - 3220.0 Pass ERW-1054 3/17/2014 Mn-54 < 4.3 0.0 NA Pass ERW-1054 3/17/2014 Pu-238 54.1 +/- 3.6 44.1 32.6 - 54.9 Pass ERW-1054 3/17/2014 Pu-239/240 185.9 +/- 17.6 160.0 124.0 - 202.0 Pass ERW-1054 3/17/2014 U-233/234 74.8 +/- 6.3 82.4 61.9-106.0 Pass ERW-1054 3/17/2014 U-238 76.4 +/- 7.8 81.8 62.4 - 100.0 Pass ERW-1054 3/17/2014 Uranium 154.3 +/- 14.6 168.0 123.0 - 217.0 Pass ERW-1054 3/17/2014 Zn-65 1818.5 +/- 56.4 1800.0 1500.0 - 2270.0 Pass ERW-1055 3/17/2014 Fe-55 636.3 +/- 176.0 1200.0 716.0 - 1630.0 Fail ERW-1055 3/17/2014 Gr. Alpha 120.9 +/- 3.5 133.0 47.2 - 206.0 Pass ERW-1055 3/17/2014 Gr. Beta 141.6 +/- 2.3 174.0 99.6 - 258.0 Pass ERW-1 055 3/17/2014 Sr-90 873.9 +/- 56.9 890.0 580.0 - 1180.0 Pass ERW-1060 3/17/2014 H-3 5818.0 +/- 230.0 5580.0 3740.0 - 7960.0 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: ERW (water), ERAP (air filter), ERSO (soil), ERVE (vegetation). Results are reported in units of pCi/L, except for air filters (pCi/Filter), vegetation and soil (pCi/kg).

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

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

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

The results of reanalysis with replacement tracer purchased from NIST:

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

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

A7-2

APPENDIX B DATA REPORTING CONVENTIONS 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 4.66o 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 +/- S, and x2 +/- s 2 Reported result: x +/- s; where x = (112) (x, + x2) and s = (1/2) S 2 3.2. Individual results: < L , < L2 Reported result: < L, where L = lower of L, and L2 3.3. Individual results: x +/- s, < L Reported result: x+/- s if x > L; < L otherwise.

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

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

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

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

4.5 In rounding off, the following rules are followed:

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

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

B-2

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 1 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 I 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-131. 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 Location E-1, monthly averages 2010-2014 0.050 0.040 ce) 0.030 E

0L 0.020 0.010 0.000 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I ii 2(010 2011 2012 2013 2014 2015 Year Location E-2, monthly averages 2010-2014 0.050 0.040 0.030 M

E-0.020 0.010 0.000 ++

2010 2011 2012 2013 2014 2015 Year D-2

POiNT BEACH Air Particulates - Gross Beta Location E-3, monthly averages 2010-2014 0.050 0.040 0.030 E

CY2 0.

0.020 0.010 0.000 +,'

2010 2011 2012 2013 2014 2015 Year Location E-4, monthly averages 2010-2014 0.050 0.040 -

cr) 0.030 ,

E 0 0.020 .

CL 0.010 0.00 2011 2 2 2014 2010 2011 2012 2013 2014 2015 Year D-3

POINT BEACH Air Particulates - Gross Beta Location E-8, monthly averages 2010-2014 0.050 0.040 ,

C) 0.030 - .

0.010 .

0.000 2010 2011 2012 2013 2014 2015 Year Location E-20, monthly averages 2010-2014 0.050 0.040 - 4 cn 0.030 A U 0.020 '* l 0.010 0 .0 0 0 I I ' ' ' I , , I, I IIII I I I', I, I' ',I ',

2010 2011 2012 2013 2014 2015 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 U2FSSDS U2FSSDS U2FSSDS Collection Date 02-03-14 02-28-14 04-05-14 Lab Code EWW- 420 MDC EW- 863 MDC EW- 3131 MDC Be-7 3.8 +/- 9.3 19.3 17.6 +/- 12.5 < 27.5 5.5 + 9.7 66.3 Mn-54 1.5 +/- 1.1 2.1 -0.1 +/- 1.5 < 2.6 -0.6 1.3 2.0 Fe-59 0.6 +/- 1.9 3.7 0.6 +/- 2.5 < 3.9 -1.2 2.1 11.9 Co-58 -1.1 +/- 1.0 1.7 0.1 +/- 1.4 < 2.4 -1.1 +/- 1.2 6.2 Co-60 0.4 +/- 1.3 2.5 2.2 +/- 1.5 < 2.3 1.1 + 1.3 2.9 Zn-65 -0.3 +/- 2.2 3.8 2.4 +/- 3.0 < 5.0 1.0 2.2 5.8 Zr-Nb-95 0.9 +/- 1.3 2.4 -1.4 +/- 1.5 < 3.0 -3.0 +/- 1.3 16.7 a Cs-134 0.2 +/- 1.1 2.1 0.1 +/- 1.3 <2.1 -0.1 +/- 1.2 2.5 Cs- 137 2.2 +/- 1.3 2.9 1.2 + 1.5 < 2.6 0.7 +/- 1.4 2.8 Ba-La-140 -2.4 +/- 1.5 3.0 -1.3 +/- 1.8 < 3.1 -184.7 +/- 1.4 313.0 a Location U2FSSDS U2FSSDS U2FSSDS Collection Date 05-06-14 05-15-14 06-23-14 Lab Code EW- 3132 EW- 2892 EW- 3209 Be-7 -9.8 +/- 10.3 50.8 8.4 +/- 8.4 30.8 2.4 +/- 8.6 20.8 Mn-54 0.9 +/- 1.2 2.7 0.2 +/- 1.0 2.1 0.2 +/- 1.2 2.2 Fe-59 1.8 +/- 2.4 11.6 -1.2 +/- 1.8 5.5 0.4 +/- 2.2 4.3 Co-58 1.3 +/- 1.2 4.6 2.1 +/- 1.0 2.5 -0.7 +/-

1.1 1.9 Co-60 0.1 +/- 1.3 2.2 0.0 +/- 1.1 2.2 -1.1 +/- 1.2 2.2 Zn-65 3.6 +/- 2.3 5.4 -1.0 +/- 2.0 4.6 -1.4 +/- 2.0 3.6 Zr-Nb-95 2.3 +/- 1.4 10.1 -0.6 +/- 1.2 4.1 1.1 +/- 1.2 3.7 Cs- 134 -0.3 +/- 1.3 2.3 -0.7 +/- 1.1 2.0 -0.4 +/- 1.2 2.1 Cs- 137 1.1 +/- 1.5 3.3 2.2 +/- 1.3 2.6 0.9 +/- 1.4 2.7

-34.9 +/- 1.4 a -3.7 +/- 1.3 +/-

Ba-La-140 39.2 12.2 1.9 1.5 7.4 Location U2FSSDS U2FSSDS U2FSSDS Collection Date 07-14-14 08-28-14 09-26-14 Lab Code EW- 3484 EW- 4598 EWW- 5268 Be-7 7.4 +/- 11.8 < 23.7 7.3 +/- 13.5 < 26.7 1.9 +/- 9.8 < 24.0 Mn-54 -0.2 +/- 1.5 < 3.0 0.2 +/- 1.6 < 2.9 -0.6 +/- 1.3 < 2.0 Fe-59 -1.0 +/- 2.7 < 4.1 0.4 +/- 3.1 < 5.7 -0.6 +/- 2.3 < 3.4 Co-58 -0.1 +/- 1.4 < 1.8 0.0 +/- 1.5 < 3.0 1.9 +/- 1.3 < 2.4 Co-60 0.5 +/- 1.5 < 2.5 -0.8 +/- 1.7 < 3.0 0.5 +/- 1.4 < 2.5 Zn-65 -6.2 +/- 3.2 < 5.0 3.5 +/- 3.2 < 5.4 -1.4 +/- 2.4 < 5.1 Zr-Nb-95 -0.2 +/- 1.5 < 1.8 -2.5 +/- 1.7 < 2.8 -1.8 +/- 1.3 < 3.0 Cs-134 0.4 + 1.4 < 2.8 0.5 +/- 1.5 < 3.0 -1.3 +/- 1.3 < 2.3 Cs-137 2.2 +/- 1.4 < 3.0 0.2 +/- 1.7 < 3.1 0.3 +/- 1.5 < 2.8 Ba-La-140 -0.7 +/- 1.7 < 1.9 -1.5 +/- 1.8 < 2.5 -0.7 +/- 1.3 < 2.7 a LLDs not reached due to age of sample; sample counted 07-09-14.

E-2

POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: = pCi\L Gamma isotopic analysis Location U2FSSDS U2FSSDS U2FSSDS Collection Date 10-24-14 11-20-14 12-26-14 Lab Code EWW- 6142 MDC EWW- 6932 EWW- 7368 Be-7 12.9 +/- 13.2 < 24.8 -2.4 +/- 9.7 < 22.5 1.1 +/- 11.4 < 24.1 Mn-.54 1.1 + 1.6 2.5 1.1 +/- 1.2 < 2.4 1.7 +/- 1.4 < 3.3 Fe-59 -3.5 +/- 3.2 5.7 -3.5 +/- 2.2 < 4.0 -1.1 +/- 2.5 < 3.7 1.2 +/-! 1.5 2.9 0.2 +/- 1.2 < 2.6 -1.1 Co-58 +/- 1.4 < 2.7 Co-60 0.1 +/- 1.8 2.6 -0.6 +/- 1.3 < 1.7 -0.1 +/- 1.5 < 2.1 Zn-65 1.7 +/- 3.2 3.5 -1.7 +/- 2.3 < 4.2 0.1 +/- 2.8 <4.1 Zr-Nb-95 0.6 +/- 1.5 2.5 -0.2 +/- 1.4 <4.1 -0.5 +/- 1.5 < 4.7 Cs-134 0.8 +/- 1.6 3.1 -0.6 +/- 1.3 < 2.4 -0.2 +/- 1.4 < 2.7 1.5 +/- 1.6 3.4 0.4 +/- 1.5 Cs-1 37 < 2.4 1.4 +/- 1.6 < 3.5

-1.1 +/- 1.8 4.8 -9.0 +/- 1.4 < 4.6 +/- 1.8 Ba-La-140 -3.6 < 7.6 E-3

POINT BEACH NUCLEAR PLANT Facade Wells Units: = pCi\L Gamma isotopic analysis Location GW-09 1Z-361A GW-09 1Z-361B GW-10 2Z-361A GW-10 2Z-361B Collection Date 03-15-14 03-15-14 03-15-14 03-15-14 Lab Code EWW- 1253 a MDC EVWW- 1254 a MDC NDb MDC EWW- 1255 a MDC Be-7 20.0 +/- 16.6 < 58.4 -11.9 +/- 14.2 < 40.3 16.8 +/- 13.7 < 58.0 Mn-54 0.0 +/- 1.7 < 3.0 2.0 +/- 1.8

• 3.8 0.7 +/- 1.7 < 3.4 Fe-59 -0.4 +/- 3.0

• 7.8 3.7 +/- 3.4 < 15.0 -4.1 +/-3.2 < 11.2 Co-58 1.1 +/- 1.7 < 5.2 -1.7 +/- 1.8 < 4.3 3.3 +/- 1.7 < 5.5 Co-60 0.2 +/- 2.0

• 2.7 -0.2 +/- 1.9 < 2.5 0.4 +/- 2.0 < 3.9 Zn-65 0.6 +/- 3.3 <7.1 0.8 +/- 3.5 <6.1 4.3 +/- 3.4 < 7.4 Zr-Nb-95 -2.7 +/- 1.8

• 7.3 -5.3 +/- 2.0 < 9.3 -3.0 +/- 1.9 < 5.2 Cs-1 34 -0.7 +/- 1.7 < 3.5 -3.2 +/- 1.8 < 3.4 1.6 +/- 1.8 < 3.5 Cs-137 1.3 +/- 2.0 < 3.5 -0.1 +/- 2.1 <3.1 2.4 +/- 2.0 < 3.9 Ba-La-140 -12.6 +/- 1.9 < 28.2 5.7 +/- 1.9 < 24.2 -20.4 +/- 2.2 < 41.3 Location GW-09 1Z-361A GW-09 IZ-361 B GW-10 2Z-361A GW-10 2Z-361B Collection Date 04-06-14 04-06-14 04-06-14 04-06-14 Lab Code EWW- 1568 EWW- 1569 EWW- 1570 EWW- 1571 Be-7 -28.6 +/- 17.6 < 34.1 11.0 +/- 14.8 < 30.1 -4.6 +/- 12.5 < 27.6 2.8 +/- 12.5 < 29.7 Mn-54 -0.4 +/- 1.8 < 3.5 2.1 +/-1.6 < 3.4 -0.9 +/- 1.6 < 3.2 1.7 +/- 1.6 < 2.3 Fe-59 -1.7 +/- 3.7 <8.1 -0.5 +/- 2.9 < 4.2 0.6 +/- 2.8 < 8.0 2.0 +/- 3.0 < 8.0 Co-58 0.3 +/- 1.7 < 3.4 0.1 +/-1.5 < 2.9 -2.7 +/- 1.6

• 2.2 -0.6 +/- 1.5 < 2.9 Co-60 1.7 +/-2.0 < 3.9 3.4 +/- 1.9 < 3.4 0.8 +/- 1.9 < 3.3 -0.5 +/- 1.7 < 3.0 Zn-65 -6.8 +/- 3.9 < 6.5 0.5 +/- 3.2 < 5.7 -2.7 +/- 3.2 < 6.6 -2.6 +/- 3.1 < 6.0 Zr-Nb-95 -1.7 +/- 1.9 < 4.7 0.4 +/- 1.6 < 4.0 2.1 +/- 1.7 < 4.3 0.9 +/- 1.8 < 5.3 Cs- 134 0.7 +/- 1.8 < 3.8 -0.5 +/- 1.7 < 3.4 -0.2 +/- 1.7 < 3.0 0.3 +/- 1.7 < 3.0 Cs-137 0.0 +/- 2.1 <4.1 2.7 +/- 1.7 < 3.5 1.4 +/- 1.9 < 3.3 1.4 +/- 1.9 < 3.9 Ba-La-140 -7.8 +/- 2.3 <5.1 0.4 +/- 2.0

• 5.2 1.2 +/- 1.9 < 9.5 3.5 +/- 1.7 < 3.8 Location GW-09 1Z-361A GW-09 1Z-361 B GW-10 2Z-361A GW-10 2Z-361B Collection Date 07-16-14 07-16-14 07-16-14 07-16-14 Lab Code EWW- 3480 EWW- 3481 c EWW- 3482 c EWW- 3483 c Be-7 -1.9 +/- 9.2 < 13.4 -2.3 +/- 9.6 < 25.7 -1.7 +/- 12.1 < 23.4 1.0 +/-8.5 < 21.2 Mn-54 0.0 +/- 1.2 < 2.3 -0.6 +/- 1.2

• 1.6 -0.1 +/- 1.3

• 2.5 0.8 +/- 1.2 < 2.4 Fe-59 -0.2 +/- 2.0 < 3.5 0.3 +/-2.1 < 4.2 -1.2 +/-2.7

• 2.7 1.5 +/-2.2 < 4.9 Co-58 -0.1 +/-1.1 < 1.6 -0.2 +/- 1.1 < 1.5 1.0 +/- 1.2 < 2.4 -0.3 +/- 1.0 < 1.4 Co-60 -0.4 +/-1.2 <2.1 0.4 +/- 1.3 < 2.9 -0.1 +/- 1.3 < 2.0 1.6 +/- 1.1 < 2.7 Zn-65 -2.4 +/-2.2

• 3.8 1.0 +/-2.2 < 3.9 -0.6 +/- 3.0 < 4.5 -0.9 +/- 2.1 < 3.3 Zr-Nb-95 -0.4 +/-1.2 < 2.0 0.1 +/-1.3 < 2.6 -0.8 +/- 1.3 < 2.0 -0.9 +/- 1.2 < 2.6 Cs-134 -1.0 +/-1.2 < 2.1 -0.7 +/- 1.2

• 2.2 -0.8 +/- 1.3 < 2.6 0.3 +/- 1.1 <2.1 Cs-137 0.2 +/-1.4 < 2.7 1.2 +/- 1.4 < 2.6 -0.3 +/- 1.5 < 2.6 0.6 +/- 1.4 < 2.6 Ba-La-140 1.5 +/-1.4 < 2.7 -0.7 +/- 1.5 < 2.5 0.0 +/- 1.5 < 2.7 -1.0 +/- 1.5 < 2.7 8 Sample counted 04-26-2014; Ba/La LLD not reached due to age of sample.

D "ND" = No data; water frozen.

CResults of confirmatory sampling. See Appendix F for explanation.

E-4

POINT BEACH NUCLEAR PLANT Facade Wells Units: = pCi\L Gamma isotopic analysis Location GW-09 1Z-361A GW-09 1Z-361B GW-10 2Z-361A GW-10 2Z-361B Collection Date 08-19-14 08-19-14 08-19-14 08-19-14 Lab Code EWW- 4519 MDC EWW- 4520 MDC EWW- 4521 MDC EWW- 4523 MDC Be-7 -3.9 +/- 12.5 < 26.3 -4.9 +/- 9.9 < 23.7 10.4 +/- 8.9 < 23.6 11.1 +/- 12.8 < 34.7 Mn-54 0.3 +/- 1.3 < 2.7 0.2 +/- 1.3 < 2.5 -0.9 +/- 1.2 < 2.3 0.7 +/- 1.3 < 2.7 Fe-59 -2.3 +/- 2.6 < 3.1 -2.3 +/- 2.3 < 3.7 -3.5 +/- 2.1 < 4.9 -3.8 +/- 2.7 < 2.8 Co-58 -0.6 +/- 1.2 < 2.6 0.9 +/- 1.2 < 2.2 0.3 +/- 1.2 < 2.0 -0.2 +/- 1.3 < 2.5 Co-60 0.1 +/- 1.3 < 2.2 1.2 +/- 1.4 < 2.5 0.4 +/- 1.2 < 2.4 0.9 +/- 1.4 < 2.8 Zn-65 -4.3 +/- 3.1 < 5.7 -0.8 +/- 2.4 < 4.9 -0.5 +/- 2.2 < 4.6 -4.3 +/- 2.9 < 4.6 Zr-Nb-95 -1.2 +/- 1.4 < 1.9 -2.1 +/- 1.4 < 2.9 0.8 +/- 1.2 < 2.7 -1.0 +/- 1.4 < 3.2 Cs-1 34 0.1 +/-1.4 < 2.7 -1.9 +/- 1.3 < 2.4 -0.9 +/- 1.1 <2.1 0.3 +/- 1.3 < 2.7 Cs- 137 -0.3 +/- 1.5 < 2.3 0.3 +/- 1.4 < 2.7 1.3 +/- 1.4 < 2.9 1.1 +/- 1.5 < 3.2 Ba-La-140 -1.9 +/- 1.4 < 4.9 -2.9 +/- 1.4 < 2.5 -2.5 +/- 1.4 < 3.1 1.9 +/- 1.5 < 5.2 Location GW-09 1Z-361A GW-09 1Z-361B GW-10 2Z-361A GW-1 0 2Z-361 B Collection Date 11-17-14 11-17-14 11-17-14 11-17-14 Lab Code EWW- 6644 EWW- 6645 EWW- 6646 EWW- 6647 Be-7 -6.9 +/- 13.7 < 34.8 -3.8 +/- 12.8 < 29.9 -10.6 +/- 13.5 < 35.7 -0.5 +/- 15.6 < 23.6 Mn-54 1.0 +/- 1.7 < 3.5 -0.7 +/- 1.7 < 3.0 1.1 +/- 1.7 < 3.7 -0.5 +/- 1.7 < 3.3 Fe-59 -0.8 +/- 3.2 < 9.6 0.3 +/- 3.0 < 5.9 -3.0 +/- 2.9 < 6.1 -0.5 +/- 3.6 < 6.0 Co-58 -0.9 +/- 1.6 < 2.5 0.3 +/- 1.6 < 3.2 0.5 +/- 1.7 < 3.9 -0.9 +/- 1.6 < 2.7 Co-60 -0.5 +/- 2.0 < 3.2 -1.1 +/- 1.8 < 3.1 0.1 +/- 1.7 < 2.4 1.1 +/- 1.8 < 3.6 Zn-65 -0.1 +/- 3.4 < 6.6 -1.7 +/-3.3 < 6.3 -1.8 +/- 3.2 < 4.8 -1.1 +/-3.7 < 5.5 Zr-Nb-95 1.7 +/- 1.9 < 5.1 0.9 +/- 1.7 < 4.5 -2.0 +/- 1.8 < 4.2 1.5 +/- 1.7 <4.1 Cs-134 0.9 +/- 1.7 < 3.2 0.6 +/- 1.7 < 3.0 -1.3 +/- 1.7 < 2.9 -0.8 +/- 1.6 < 3.3 Cs-137 2.1 +/- 2.0 < 3.6 1.6 +/- 2.0 <4.1 -1.2 +/- 2.0 < 3.2 1.1 +/- 1.9 < 3.7 Ba-La-140 -3.5 +/- 1.9 < 4.7 -4.8 +/- 2.0 < 4.6 -5.0 +/- 1.9 < 4.3 0.6 +/- 1.8 < 5.2 E-5

POINT BEACH NUCLEAR PLANT APPENDIX F Special Analyses F-1

• ATI-*ATIMidwetst Environmenta, Laboratory Inc.

700 Landwehr Road - Nonthbrook. IL 60062-2310 phone (847) 564-0700 - fax f847) 564-4517 Dr. Kjell Johansen NextEra Energy LABORATORY REPORT NO.: 8006-100-1118 Point Beach Nuclear Plant DATE: 09-12-2014 6610 Nuclear Road SAMPLES RECEIVED: 09-04-2014 Two Rivers, Wisconsin 54241 PURCHASE ORDER NO.:

Below are the results of the analyses for tritium in six air condensate samples collected September 3, 2014.

Sample Lab Concentration / MDC (pCi/L)

Description Code H-3 NSB EW-4592 328 +/- 101 / < 177 SSB EW-4593 2690 +/- 166 / < 177 Control Room EW-4594 527 +/- 108 / < 177 Training Bldg EW-4595 57 +/- 90 / < 177 South Gatehouse EW-4596 173 +/- 95 / < 177 Ops Office Area EW-4597 874 +/- 119/ < 177 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: kjell.iohansencWNextERAEnergy.com APPROVED BY:ýý ~z)ý0ý ý ForrestG.Shaw 1I1, U Quality Assurance

• A'I'IEnvironmental, Inc.

• ATIMidwest Laboratory 700 Landwehr Roa.d Northbroo. IL 60062-2310 phone (847) 564-0700

• fox (847) 564-4517 Mr. Jeremy Keltner - Chemistry Manager LABORATORY REPORT NO. 8006-100-1108 NextEra Energy - Point Beach Plant DATE: 11/3/2014 6610 Nuclear Road SAMPLES RECEIVED: 7/7/2014 Two Rivers, WI 54241 PURCHASE ORDER NO.:

Enclosed are the results of the analyses for tritium and gamma emitting isotopes in four fagade samples collected June 25, 2014.

The sample GW-09-2Z-361A was filtered through a membrane filter as requested.

Enclosed are the results of the gamma scan of the filter and the results of the analyses for iron-55, nickel-63 and strontium -90 on both the filter and the filtrate.

cc: Kjell Johansen Forrest G. Shaw Ill, Quality Assurance

Report 8006-100-1108 Page 1 of 2 Table 1. Results of the analyses for gross tritium and gamma emitting isotopes.

Location GW-09-1Z-361A GW-09-1Z-361 B GW-09-2Z-361 B Collection Date 6/25/2014 6/25/2014 6/25/2014 Lab Code EWW-3210 MDC EWW-3211 MDC EWW-3213 MDC Isotope Units = pCi/L H-3 258 +/- 84 < 144 328 +/- 88 < 144 202 +/- 82 < 144 Be-7 507.0 +/- 56.6 208.2 +/- 50.2 160.3 +/- 45.6 Mn-54 0.9 +/- 1.8 < 3.1 3.2 +/- 1.8 < 3.7 12.7 +/- 4.4 Fe-59 -0.2 +/- 3.5 < 3.9 1.8 +/- 2.9 < 7.6 1.0 +/- 2.8 < 6.7 Co-58 2.0 +/- 1.7 < 4.3 10.5 +/- 4.2 40.4 +/- 5.6 Co-60 -0.1 +/- 1.9 < 3.9 3.0 +/- 1.5 < 3.3 0.1 +/- 1.9 < 3.8 Zn-65 -7.7 +/- 4.2 < 5.6 1.4 +/- 3.2 < 5.6 0.5 +/- 3.3 < 5.0 Zr-Nb-95 -2.0 +/- 2.0 < 4.8 0.5 +/- 1.8 < 5.3 -1.8 +/- 1.7 < 4.1 1-131 24.5 +/- 2.6 < 19.9 43.3 +/- 16.7 18.4 +/- 1.7 < 12.2 Cs-134 -1.7 +/- 2.0 < 3.7 -0.9 +/- 1.7 < 3.2 -1.2 +/- 1.8 < 3.3 Cs-137 -1.1 +/- 2.1 < 3.9 0.4 +/- 2.0 < 3.8 2.5 +/- 1.9 < 4.0 Ba-La-140 -5.6 +/- 2.4 < 9.3 7.6 +/- 2.0 < 9.0 0.8 +/- 1.9 < 9.3 The error given is the probable counting error at the 95% confidence level.

Less than (<), value is based on a 4.66 sigma counting error for the background sample and represents MDC for this measurement.

Report 8006-100-1108 Page 2 of 2 Table 1. Results of the analyses for gross tritium and gamma emitting isotopes.

Location GW-09-2Z-361A GW-09-2Z-361A Collection Date 6/25/2014 6/25/2014 Lab Code EWW-3212 EWW-3212F a MDC MDC Isotope Units = pCi/L H-3 431 +/- 92 < 144 Be-7 745.8 +/- 48.9 .... 701.6 +/- 41.4 Mn-54 45.2 +/- 5.5 43.5 +/- 2.5 Fe-59 1.0 +/- 2.8 < 6.7 -1.8 +/- 1.9 < 4.9 Co-58 241.6 +/- 9.3 . 166.7 +/- 5.3 Co-60 3.3 +/- 2.1 < 3.2 4.0 +/- 1.3 < 2.6 Zn-65 0.5 +/- 3.3 < 5.0 -2.5 +/- 2.3 < 3.5 Zr-Nb-95 -1.8 +/- 1.7 < 4.1 -1.1 +/- 1.0 < 2.2 1-131 44.9 +/-21.2 -1.1 +/- 1.1 < 11.8 Cs-134 -1.2 +/- 2.1 < 3.9 -6 +/- 1.2 < 2.4 Cs-137 0.9 +/- 2.2 < 3.9 1.4 +/- 1.2 < 2.6 Ba-La-140 0.8 +/- 1.9 < 9.3 3.3 +/- 1.2 < 6.4 Fe-55 148 +/- 429.9 < 695.4 -120.4 +/- 230.7 < 390.8 Ni-63 22.3 +/- 72.1 < 118.2 12.8 +/- 14.9 < 24.2 Sr-90 0.2 +/- 0.8 < 1.8 1.1 +/- 3.2 < 6.6 a 450mL of sample was filtered through 0.8V.m membrane filter. The filter was gamma scanned for 60,000 sec.

The error given is the probable counting error at the 95% confidence level.

Less than (<), value is based on a 4.66 sigma counting error for the background sample and represents MDC for this measurement.

f A-I-I Environmental, Inc.

S0*A oMidwest Laboratory 00L Ro R- - N.nohbl.A ~I. 60062 :J I Mr. Richard Welty LABORATORY REPORT NO.: 8006-100-1099 Radiation Protection Mgr. DATE: 04-16-14 Point Beach Nuclear Plant SAMPLES RECEIVED: 04-03-14 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, 2014.

Period: 1st Quarter, 2014 Date Annealed: 12/10/13 Date Placed: 01/03/14 Date Removed: 04/01/14 Date Read: 04/08/14 Days in the Field: 88 Days from Annealing to Readout: 119 In-transit exposure: 5.75 + 0.32 Net mR Net mR Location Total mR Net mR Std Qtr // per 7 days -7 SGSF-North 18.6 +/- 0.8 12.8 +/- 0.9 13.2 +/- 0.9 1.02 +/- 0.07 SGSF-East 16.5 +/- 1.0 10.7 +/- 1.0 11.1 +/- 1.1 0.85 +/- 0.08 SGSF-South 20.0 +/- 0.5 14.3 +/- 0.6 14.7 +/- 0.6 1.13 +/- 0.05 SGSF-West 19.3 +/- 1.1 13.5 +/- 1.1 14.0.+/- 1.1 1.08 +/- 0.09 ISFSI-North 33.8 +/- 0.8 28.0 +/- 0.9 29.0 +/- 0.9 2.23 +/- 0.07 ISFSI-East 53.3 +/- 1.1 47.5 +/- 1.1 49.1 +/- 1.2 3.78 +/- 0.09 ISFSI-South 23.1 +/- 0.9 17.4 +/- 0.9 18.0 +/- 1.0 1.38 +/- 0.07 ISFSI-West 63.3 +/- 3.7 57.5 +/- 3.8 59.5 +/- 3.9 4.58 +/- 0.30 Control 20.8 +/- 0.9 15.1 +/- 1.0 15.6 +/- 1.0 1.20 +/- 0.08 SA Coodim, Quality Assurance APPROVED cc: K. Johansen

],** ATI Environmental, Inc.

Midwest Laboratory T'00 L0 -U.1" Ro-O

• t b*foo,: V.

... ' '..,, ':.. S .. . '

Mr. Richard Welty LABORATORY REPORT NO.: 8006-100-1110 Radiation Protection Mgr. DATE: 07-23-14 Point Beach Nuclear Plant SAMPLES RECEIVED: 07-07-14 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, 2014.

Period: 2nd Quarter, 2014 Date Annealed: 03/11/14 Date Placed: 04/01/14 Date Removed: 07/02/14 Date Read: 07/14114 Days in the Field: 92 Days from Annealing to Readout: 125 In-transit exposure: 5.57 +/- 0.32 Net mR Net mR Location Total mR Net mR Std Qtr - per 7 days SGSF-North 19.7 + 0.8 14.1 +/- 0.8 14.0 +/- 0.8 1.08 +/- 0.06' SGSF-East 15.8 +/- 0.5 10.3 +/- 0.6 10.2 +/- 0.6 0.78 +/- 0.04 SGSF-South 17.6 +/- 0.6 12.1 +/- 0.6 11.9 +/- 0.6 0.92 +/- 0.05 SGSF-West 23.0 + 1.0 17.4 +/- 1.1 17.2 +/- 1.1 1.32 +/- 0.08 ISFSI-North 40.4 +/- 2.2 34.8 +/- 2.2 34.4 +/- 2.2 2.65 +/- 0.17 ISFSI-East 47.7 +/- 1.4 42.2 +/- 1.4 41.7 +/- 1.4 3.21 +/- 0.11 ISFSI-South 19.1 :l: 1.0 13.6 +/- 1.1 13.4 +/- 1.1 1.03 +/- 0.08 ISFSI-West 56.2 +/- 2.0 50.7 +/- 2.0 50.1 +/- 2.0 3.85 +/- 0.15 Control 18.5 +/- 1.0 12.9 +/- 1.1 12.8 +/- 1.0 0.98 +/- 0.08 A SA Coodim, Quality Assurance APPI Manager cc: K. Johansen

Environmental, Inc.

V* I Midwest -Laboratory 700 L -,-wh, F.-o

• 1o4trok 600(,' :- 16, Mr. Richard Welty LABORATORY REPORT NO.: 8006-100-1127 Radiation Protection Mgr. DATE: 11-03-14 Point Beach Nuclear Plant SAMPLES RECEIVED: 10-09-14 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, 2014.

Period: 3rd Quarter, 2014 Date Annealed: 06/13/14 Date Placed: 07/02/14 Date Removed: 10/04/14 Date Read: 10/13/14 Days in the Field: 94 Days from Annealing to Readout: 122 In-transit exposure: 4.13 t 0.28 Net mR X Net mR Location Total mR Net mR Std Qtr per 7 days SGSF-North 18.4 t 1.0 14.3 +/- 1.0 13.8 +/- 1.0 1.06 +/- 0.07 SGSF-East 15.3 +/- 0.8 11.2 +/- 0.9 10.8 +/- 0.8 0.83 +/- 0.06 SGSF-South 16.9 +/- 0.5 12.8 +/- 0.6 12.3 +/- 0.6 0.95 +/- 0.05 SGSF-West 16.4 +/- 0.6 12.3 +/- 0.7 11.9 +/- 0.7 0.92 +/- 0.05 ISFSI-North 36.8 +/- 0.8 32.7 +/- 0.9 31.6 +/- 0.8 2.43 +/- 0.06 ISFSI-East 49.5 +/- 1.1 45.4 +/- 1.1 43.9 +/- 1.1 3.38 +/- 0.08 ISFSI-South 19.1 +/- 0.9 15.0 +/- 0.9 14.5 +/- 0.9 1.12 +/- 0.07 ISFSI-West 59.3 +/- 3.2 55.2 +/- 3.2 53.4 +/- 3.1 4.11 +/- 0.24 Control 22.6 +/- 1.2 18.4 +/- 1.3 17.8 +/- 1.2 1.37 +/- 0.09

?Forrest G. Shaw III Quality Assurance cc: K. Johansen

• ATI Environmental, Midwest Laboratory Inc.

700 Lanoweh, Ro0o

• No"Mt?04 , L 60062 2- 10

'A'n7" 5.,1 0700 . 0

'F-Mr. Richard Welty LABORATORY REPORT NO.: 8006-100-1135 Radiation Protection Mgr. DATE: 01-29-15 Point Beach Nuclear Plant SAMPLES RECEIVED: 01-06-15 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, 2014.

Period: 4th Quarter, 2014 Date Annealed: 09/16/14 Date Placed: 10/04/14 Date Removed: 01/02/15 Date Read: 01/07/15 Days in the Field: 90 Days from Annealing to Readout: 113 In-transit exposure: 3.78 +/- 0.20 Net mR Net mR i/

Location Total mR Net mR Std Qtr 7 per 7 days SGSF-North 16.1 +/- 0.3 12.3 +/- 0.4 12.4 +/- 0.4 0.96 +/- 0.03 SGSF-East 13.7 +/- 0.3 10.0 +/- 0.4 10.1 +/- 0.4 0.77 +/- 0.03 SGSF-South 14.4 +/- 0.3 10.6 +/- 0.3 10.7 +/- 0.3 0.82 +/- 0.03 SGSF-West 15.6 +/- 0.8 11.8 +/- 0.8 11.9 +/- 0.8 0.92 +/- 0.06 ISFSI-North 35.9 +/- 1.7 32.1 +/- 1.7 32.5 +/- 1.7 2.50 +/- 0.13 ISFSI-East 42.8 +/- 1.1 39.1 +/- 1.1 39.5 +/- 1.1 3.04 +/- 0.08 ISFSI-South 17.0 +/- 0.7 13.2 +/- 0.8 13.3 +/- 0.8 1.03 +/- 0.06 ISFSI-West 57.0 +/- 2.0 53.2 +/- 2.0 53.8 +/- 2.0 4.14 +/- 0.15 Control 15.8 +/- 0.6 12.0 +/- 0.6 12.2 +/- 0.6 0.94 +/- 0.05

( Forrest G. Shaw III Quality Assurance Manager cc: K. Johansen

I APPENDIX 2 I Environmental Manual Revision 25 February 11, 2014 62

EM ENVIRONMENTAL MANUAL DOCUMENT TYPE: Controlled Reference CLASSIFICATION: N/A REVISION: 25 EFFECTIVE DATE: February 11, 2014 REVIEWER: Plant Operations Review Committee (PORC)

APPROVAL AUTHORITY: Plant Manager (PORC Chair)

PROCEDURE OWNER (title): Group Head OWNER GROUP: Chemistry

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL TABLE OF CONTENTS SECTION TITLE PAGE 1.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ADMINISTRATION ........................................................................... 3 1.1 D efi nition and B asis ................................................................................................... 3 1.2 Responsibilities for Program Implementation .......................................................... 4 1.3 Quality Assurance/Quality Control ........................................................................... 7 1.4 Program R evisions ................................................................................................... .. 8 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING ....................................... 8 2.1 Program O verview ..................................................................................................... 8 2.2 Program Param eters ................................................................................................... 9 2.3 Assistance to the State of Wisconsin ......................................................................... 14 2.4 Specification of Sampling Procedures ...................................................................... 15 2.5 M ilk S u rvey ................................................................................................................... 24 Table 2-1 Recommended Minimum Sample Sizes ................................................................. 25 Table 2-2 Sample Types And Associated Lower Level Of Detection (Lid) And Notification Level Values ......................................................................................... 26 Table 2-3 Radiological Environmental Sampling Locations .................................................... 28 Table 2-4 PBNP Radiological Environmental Sample Collection And Analysis Frequency ....... 30 Table 2-5 Samples Collected For State Of Wisconsin ............................................................. 31 Figure 2-1 a Radiological Environmental Sampling Locations .................................................... 32 Figure 2-1 b Radiological Environmental Sampling Locations .................................................... 33 Figure 2-1 c Radiological Environmental Sampling Locations .................................................... 34 Page 2 of 34 IN FORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL 1.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ADMINISTRATION 1.1 Definition and Basis 1.1.1 Definition Radiological environmental monitoring is the measurement of radioactivity in samples collected from the atmospheric, aquatic and terrestrial environment around the Point Beach Nuclear Plant (PBNP). Monitoring radioactivity in effluent streams at or prior to the point of discharge to the environment is not part of the Radiological Enviromnental Monitoring Program (REMP).

1.1.2 Basis The REMP is designed to fulfill the requirements of 10 CFR 20.1302, PBNP GDC 17, and Sections IV.B.2 and IV.B.3 of Appendix I to 10 CFR 50.

Technical Specification 5.5.1 .b requires the Offsite Dose Calculation Manual (ODCM) to contain the radiological environmental monitoring activities. A complete description of the PBNP radiological environmental monitoring program, including procedures and responsibilities, is contained in the Environmental Manual (EM). The EM is incorporated into the ODCM by reference (ODCM, Section 6.0).

No significant radionuclide concentrations of plant origin are expected in the plant environs because radioactivity in plant effluent is continuously monitored to ensure that releases are well below levels which are considered safe upper limits. The REMP is conducted to demonstrate compliance with applicable standards, to assess the radiological environmental impact of PBNP operations, and to monitor the efficacy of in plant effluent controls. The REMP, as outlined in Tables 2-2 through 2-4 is designed to provide sufficient sample types and locations to detect and to evaluate changes in environmental radioactivity.

Radioactivity is released in liquid and gaseous effluents. Air samplers and thermoluminescent dosimeters placed at various locations provide means of detecting changes in environmental radioactivity as a result of plant releases to the atmosphere. Because the land area around PBNP is used primarily for farming and dairy operations, sampling of vegetation is conducted to detect changes in radiological conditions at the base of the food chain. Sampling of area-produced milk is conducted because dairy farming is a major industry in the area.

Page 3 of 34 IN FORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL Water, periphyton., and fish are analyzed to monitor radionuclide levels in Lake Michigan in the vicinity of PBNP. Periphyton, attached algae, along with lake water samples, provide a means of detecting changes which may have a potential impact on the radionuclide concentrations in Lake Michigan fish. Because of the migratory behavior of fish, fish sampling is of minimal value for determining radiological impact specifically related to the operation of the Point Beach Nuclear Plant. However, fish sampling is carried out as a conservative measure with emphasis on species which are of intermediate trophic level and which exhibit minimal migration in order to monitor the status of radioactivity in fish.

Vegetation, algae, and fish sampling frequencies are qualified on an "as available" basis recognizing that certain biological samples may occasionally be unavailable due to environmental conditions.

1.2 Responsibilities for Program Implementation 1.2.1 Chemistry Functions Chemistry together with Regulatory Affairs (RA) provides the Plant Manager with the technical, regulatory, licensing, and administrative support necessary for the implementation of the program. The Chemistry administrative functions relating to the REMP fall into the six broad areas outlined below.

a. Program scope The scope of the REMP is determined by the cognizant Chemist based on radiological principles for the fulfillment of PBNP Technical Specifications (TS) and the applicable Federal Regulations. Based on the scope, the Environmental Manual (EM) is written to accomplish the collection and analyses of the necessary environmental samples. The EM is revised as necessary to conform to changes in procedures and scope.

Chemistry monitors the REMP effectiveness and compliance with TS and with the procedures and directives in the EM. In order to verify compliance with TS, Nuclear Oversight arranges for program audits and Supplier Assessments of the contracted radioanalytical laboratory.

Chemistry reviews the EM annually via the Annual Monitoring Report.

b. Record keeping The monthly radioanalytical results from the contracted laboratory are reviewed by Chemistry and one copy of the monthly radioanalytical results from the contracted laboratory is kept for the lifetime of the plant.

The vendors monthly reports are cumulative (e.g. The September report contains all the results from January-September). The cognizant Chemist reviews the current months results, signs and dates the cover page, and sends the reviewed report to plants records for retention.

Page 4 of 34 IN FORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL

c. Data monitoring Chemistry reviews the monthly analytical results from the vendor.

Trends, if any, are noted. Any resulting corrections, modifications and additions to the data are made by Chemistry. The review is documented and sent to records, as noted in Section 1.2.1 .b. Inconsistencies are investigated by Chemistry with the cooperation of Radiation Protection (RP) and contractor personnel, as required. Radioactivity levels in excess of administrative notification levels would be evaluated and notifications made, as appropriate, in accordance with LI-AA-102-1001, Regulatory Reporting, and applicable fleet policies and procedures.

d. Data summary REMP results shall be summarized annually for inclusion in the PBNP Annual Monitoring Report. This summary advises the Plant Manager of the radiological status of the environment in the vicinity of PBNP. The summary shall include the numbers and types of samples as well as the averages, statistical confidence limits and the ranges of analytical results.

Methods used in summarizing data are at the discretion of Chemistry.

e. Contractor communications Communication with the contractor regarding data, analytical procedures, lower limits of detection, notification levels and contractual matters are normally conducted by Chemistry. Communication regarding sample shipment may be done by either RP or Chemistry as appropriate.

f. Reportable items

1. Chemistry shall generate reports related to the operation of the REMP. The material included shall be sufficient to fulfill the objectives outlined in Sections IV.B.2 and IV.B.3 of Appendix I to 10 CFR 50. The following items and occurrences, are required to be reported in the PBNP Annual Monitoring Report:

(a) Summary and discussion of monitoring results including number and type of samples and measurements, and all detected radionuclides, except for naturally occurring radionuclides; (b) Unavailable, missing, and lost samples and plans to prevent recurrence and comments on any significant portion of the REMP not conducted as indicated in Tables 2-3 through 2-4.

(c) New or relocated sampling locations and reason for change; Page 5 of 34 IN FORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL (d) LLDs that are higher than specified in Table 2-2 and factors contributing to inability to achieve specified LLDs; (e) Notification that the analytical laboratory does not participate in an interlaboratory comparison program and corrective action taken to preclude a recurrence; and (f) Results of the annual milk sampling program land use census "milk survey" to visually verify that the location of grazing animals in the vicinity of the PBNP site boundary so as to ensure that the milk sampling program remains as conservative as practicable.

(g) The annual results from the contracted REMP analytical laboratory as well as the laboratory's analytical QA/QC results, in-house blanks, interlaboratory comparisons, etc., shall be submitted to the NRC, via the Annual Monitoring Report.

(h) The Annual Monitoring Report for the previous 12 month period, or fraction thereof, ending December 31, shall be submitted to the NRC by April 30 of the following year.

1.2.2 Non-Chemistry Functions The primary responsibility for the implementation of the PBNP REMP and for any actions to be taken at PBNP, based on the results of the program, resides with the Plant Manager.

a. Manual control and distribution The distribution of the PBNP Environmental Manual is the responsibility of Document Control.

b. Program coordination The daily operation of the program is conducted by PBNP Radiation Protection personnel, and other qualified personnel as required, under the supervision of an RP staff member who consults, as needed, with Chemistry. The daily administrative functions of the RP Management Employee address those functions required for the effective operation of the PBNP Radiological Environmental Monitoring Program. These administrative functions include the following:

1. Ensuring that samples are obtained in accordance with the type and frequency in Table 2-4 following procedures outlined in this manual; Page 6 of 34 IN FORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL

2. Ensuring adequate sampling supplies and calibrated, operable equipment are available at all times;

3. Ensuring that air sampling pumps are maintained, repaired and calibrated as required and that an adequate number of backup pumps are readily available at all times;

4. Reporting lost or unavailable samples as well as other potential deviations from the sampling regime in Table 2-4 via the Corrective Action Program (CAP) and notifying the cognizant Chemist.

5. Assisting the State of Wisconsin in obtaining samples at co-located and other sampling sites based upon a yearly, renewable agreement; and

6. Assisting Chemistry, as necessary, with investigations into elevated radioactivity levels in environmental samples.

1.3 Quality Assurance/Quality Control Quality assurance considerations are an integral part of PBNP's Radiological Environmental Monitoring Program. The program involves the interaction of Chemistry, site quality assurance and the contracted analytical vendor. The contracted vendor shall participate in an interlaboratory comparison program. The laboratory is audited periodically, either by PBNP or by an independent third party.

Quality control for the PBNP portion of the Radiological Environmental Monitoring Program is achieved by following the procedures contained in this manual. Radiation Protection Technologists (RPTs) collect, package and ship environmental samples under the supervision of Radiation Protection supervisors. They are advised by Radiation Protection Management who has immediate responsibility for the overall technical operation of the environmental sampling functions. The RPTs receive classroom training as well as on-the-job training in carrying out these procedures.

An audit of the PBNP Radiological Environmental Monitoring Program and its results shall be completed periodically as a means of monitoring program effectiveness and assuring compliance with program directives. The audit shall be performed in accordance with Section 1.4 of the ODCM.

Page 7 of 34 IN FORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL 1.4 Program Revisions This manual describes the current scope of the PBNP Radiological Environmental Monitoring Program. Program items or procedures periodically may be updated or changed, consistent with good radiologically monitoring practices, either to reflect new conditions or to improve program effectiveness. Technical and program features described in this manual shall be reviewed by PORC pursuant to the requirements stated in the ODCM.

2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 2.1 Program Overview 2.1.1 Purpose No significant or unexpected radionuclide concentrations of plant origin are expected because each normal effluent pathway at PBNP is monitored at or before the release point. However, the REMP is conducted to verify that plant operations produce no significant radiological impact on the environment and to demonstrate compliance with applicable standards.

2.1.2 Samples Samples for the REMP are obtained from the aquatic, terrestrial and atmospheric environment. The sample types represent key indicators or critical pathways which have been identified by applying radiological principles from NRC and other guidance documents to the PBNP environment.

2.1.3 Monitoring sensitivity The effectiveness of the REMP in fulfilling its purpose depends upon the ability to accurately determine the nature and origins of fluctuations in low levels of environmental radioactivity. This requires a high degree of sensitivity so that it is possible to correctly discriminate between fluctuations in background radiation levels and levels of radioactivity that may be attributable to the operation of PBNP. Therefore, personnel actively participating in the monitoring program should make every effort to minimize the possibility of contaminating environmental samples and to obtain samples of the appropriate size.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL 2.2 Program Parameters 2.2.1 Contamination avoidance Contamination prevents the accurate quantification of environmental radioactivity and the correct differentiation between fluctuating background radioactivity and levels of radioactivity attributable to the operation of PBNP.

Therefore, it is necessary that all persomnel associated with collecting and handling radiological environmental samples take the appropriate precautions to minimize the possibility of contaminating the samples. Some of the precautions that should be taken and which will help to minimize contamination are listed below:

a. Equipment which has been on the controlled side, even if released clean, should not normally be used in conjunction with radiological environmental monitoring. An exception to this is the Health Physics Test Instrument (HPTI) equipment used to calibrate the air flow calibrator.

b. Store sampling equipment in radiologically clean areas only;

c. Store radiological environmental samples only in radiologically clean areas when samples cannot be shipped to the contractor on the same day they are collected;

d. Treat each sample as a possible source of contamination for other samples so as to minimize the possibility of cross-contamination;

e. Radiological environmental monitoring equipment should be repaired in clean-side shops;

f. Contamination avoidance for environmental TLDs is covered in Section 2.4.2; and

g. Avoid entering contaminated areas prior to collecting enviromnental samples.

2.2.2 Sample size Sample size affects the sensitivity achievable in quantifying low levels of environmental radioactivity. Therefore, sampling personnel must attempt to attain the quantities of sample specified in Table 2-1. When a range is given, every effort should be made to obtain a quantity at the upper part of the range.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL 2.2.3 Lower limit of detection The sensitivity required for a specific analysis of an environmental sample is defined in terms of the lower limit of detection (LLD). The LLD is the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with a 95% probability and have only a 5% probability of falsely concluding that a blank observation represents a real signal. Mathematically, the LLD is defined by the formula LLDLLD

=4.66 Sb E x V x 2.22 x Y x EXP(-)XA T)

Where LLD the a priori lower limit of detection in picocuries per unit volume or mass, as applicable; Sb the standard deviation of the background counting rate or the counting rate of a blank sample, as appropriate, in counts per minutes; E counting efficiency in counts per disintegration; V = sample size in units of volume or mass, as applicable; 2.22 = number of disintegrations per minute per picocurie; Y the fractional chemical yield as applicable;

= the radioactive decay constant for the particular radionuclide; and AT the elapsed time between sample collection, or the end of the collection period, and the time of counting.

Typical values of E, V, Y, and AT are used to calculate the LLD. As defined, the LLD is an a priori limit representing the capability of a measuring system and not an a posteriori limit for a particular measurement.

The required analysis for each environmental sample and the highest acceptable LLD associated with each analysis are listed in Table 2-2.

Whenever LLD values lower than those specified in Table 2-2 are reasonably achievable, the analytical contractor for the radiological environmental samples will do so. When the LLDs listed in Table 2-2 are not achieved, a description of the factors contributing to the higher LLD shall be reported in the next PBNP Annual Monitoring Report.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL 2.2.4 Notification levels The Notification Level (NL) is that measured quantity of radioactivity in an environmental sample which, when exceeded, requires a notification of such an occurrence be made to the appropriate party. Regulatory and administrative notification levels are listed in Table 2-2.

a. Regulatory notification levels The regulatory notification levels listed in Table 2-2 represent the concentration levels at which NRC notification is required. If a measured level of radioactivity in any radiological environmental monitoring program sample exceeds the regulatory notification level listed in Table 2-2, resampling and/or reanalysis for confirmation shall be completed within 30 days of the determination of the anomalous result. If the confirmed measured level of radioactivity remains above the notification level, a written report shall be submitted to the NRC. If more than one of the radionuclides listed in Table 2-2 are detected in any environmental medium, a weighted sum calculation shall be performed if the measured concentration of a detected radionuclide is greater than 25%

of the notification levels. For those radionuclides with LLDs in excess of 25% of the notification level, a weighted sum calculation needs to be performed only if the reported value exceeds the LLD. Radionuclide concentration levels, called Weighted Sum Action Levels, which trigger a weighted sum calculation are listed in Table 2-2.

The weighted sum is calculated as follows:

concentration (1) + concentration (2) + =weightedsum notification level (1) notification level (2)

If the calculated weighted sum is equal to or greater than 1, resampling and/or reanalysis for confirmation shall be completed within 30 days of the determination of the anomalous result. If the confirmed calculated weighted sum remains equal to or greater than 1, see Section 1.2.1 .c for notification guidance. This calculation requirement and report is not required if the measured level of radioactivity was not the result of plant effluents.

b. Administrative notification levels The administrative notification levels are the concentration levels at which the contracted analytical laboratory promptly notifies the cognizant Chemistry Specialist by phone, followed by a formal written communication. The administrative notification levels are lower than the NRC regulatory notification levels and lower than, or equal to, the weighted sum action levels so the nature and origin of the increased level of environmental radioactivity may be ascertained and corrective actions taken, if required.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL 2.2.5 Sampling locations A list of sampling locations and the conresponding location codes appear in Table 2-3. The locations also are shown in Figures 2-la, 2-1b, and 2-1c. It is conceivable that samples may become unavailable from specified sample locations. If this were to occur, new locations for obtaining replacement samples shall be identified and added to the Radiological Environmental Monitoring Program. If milk or vegetation samples become unavailable from the specified sampling locations, new sampling locations will be identified within 30 days. The specific locations where samples were unavailable may be deleted from the monitoring program in accordance with established provisions for assessing changes. Any significant changes in existing sampling location and the criteria for the change shall be reported in the Annual Monitoring Report for the period in which the change occurred.

Additional sampling locations may be designated if deemed necessary by cognizant company personnel. Figures and tables in this manual shall be revised to reflect the changes.

2.2.6 Sampling media and frequency The sampling frequency for the environmental media required by the PBNP REMP is found in Table 2-4. In addition to samples required by the former Technical Specifications, the Radiological Environmental Monitoring Program also includes the sampling of soil and shoreline sediment. To ensure that all samples are obtained at the appropriate times, a checklist is used. The checklist provides a month-by-month indication of all samples, to be obtained at each sampling location (PBF-4121a through 41211). These checklists also identify the schedule for the annual milk survey and provides space for recording the date samples were shipped offsite for analysis. In addition, the checklist lists each sampling location to identify all samples, to be obtained and the collection date. Because the weekly air samples require additional information, a separate checklist is used for each individual air sampling location for calculations and other information as shown in PBF-4078.

It is recognized that on occasions samples will be lost or that samples cannot be collected at the specified frequency because of hazardous conditions, seasonable unavailability, automatic sampling equipment malfunctions and other legitimate reasons. Reasonable efforts will be made to recover lost or missed samples if warranted and appropriate. If samples are not obtained at the indicated frequency or location, the reasons or explanations for deviations from the sampling frequency specified in Table 2-4 shall be documented in a CAP.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL 2.2.7 Sample labeling All samples must be properly labeled to ensure that the necessary information is conveyed to the analytical contractor and that the results are associated with the correct geographical location. Each label (PBF-4026) must contain the following:

a. Sample type;

b. Sample location from Table 2-3;

c. Date and time (as appropriate) collected;

d. Air samples must show the total volume in mi3 ; volumes for water and milk are in gallons; vegetation, sediment, soil, and algae are indicated as

• 1000 grams; and fish Ž1000 grams;

e. Analyses for routine samples are indicated as "per contract." For special samples, the Radiation Protection manager or another Radiation Protection Management Employee will designate the analyses required; and

f. Name of person collecting the sample.

A permanent or indelible ink type felt-tip marker shall be used.

A separate sample label is needed for each sample type and location.

Labels are securely attached to each sample container. In addition to sample labels, other identifying markings may be placed on sample containers as appropriate.

2.2.8 Sample shipping All environmental samples are shipped to a contractor for analysis. The samples shall be packaged and shipped in such a way as to minimize the possibility of cross-contamination, loss, spoilage and leakage. Each sample shipment shall have a typed cover letter and, when appropriate, a contractor data collection sheet. Included in the letter shall be the same information required for the sample labels as well as the specific analyses required. The original cover letter and data collection sheet shall be sent to the contractor under separate cover; one copy of each is to be used as a packing list and a copy of each shall be kept in the appropriate PBNP file. The data collection sheet (PBF-4140a) also serves as the Chain of Custody fonn, so it is required that the collector, packer, and shipper sign the form.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL 2.2.9 Sample analyses and frequency The PBNP REMP samples shall be analyzed for designated parameters at the frequency listed in Table 2-4. Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to effluents from PBNP. Typically, this entails the scanning of the spectrum from 80 to 2048 keV and decay correcting identified radionuclides to the time of collection. The analysis specifically includes, but is not limited to, Mn-54, Fe-59, Zn-65, Co-58, Co-60, Zr-Nb-95, Ru-103, 1-131, Cs-134, Cs-137, Ba-La-140, Ce-141, and Ce-144.

2.2.10 Analytical laboratory The analyses shall be performed by a laboratory that participates in an interlaboratory crosscheck program. If the laboratory is not participating in such a program, a report shall be made pursuant to 1.2.1 .f.1.(e). The current laboratory is:

Environmental Incorporated Midwest Laboratory 700 Landwehr Road Northbrook, IL 60062-4517 (847) 564-0700 This laboratory performs the analyses in such a manner as to attain the desired LLDs. The contracted laboratory participates in an inter-laboratory comparison crosscheck program.

The contractor is responsible for providing prompt notification to the cognizant Chemist regarding any samples found to exceed the administrative notification levels as identified in Table 2-2.

2.3 Assistance to the State of Wisconsin As a courtesy and convenience, PBNP personnel obtain certain environmental samples for the Section of Radiation Protection, Department of Health and Family Services of the State of Wisconsin as listed in Table 2-5. A checklist is used. In addition, a State of Wisconsin air sampling data sheet is submitted with each sample obtained at Wisconsin air sampling locations serviced by PBNP personnel.

State of Wisconsin precipitation samples collected twice a month (or as available) require a state sample tag to be placed in a box with the quart cubitainer. State supplied labels for air particulate filters require start and stop time, date and beginning and ending volume. Fish sent to the state identify only the quarter and the year using a PBNP label (PBF-4026). The monthly lake water sample may be picked up by state personnel and in which case these samples require only that the date and location be written on the box for the cubitainer. The well water samples, 2 times/year, may be picked similar to lake water samples.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL Samples obtained for the State of Wisconsin are either given directly to state personnel or shipped as required. The department address is:

State Lab of Hygiene Radiochemistry Unit 2601 Agriculture Dr.

PO Box 7996 Madison, Wisconsin 53707-7996 2.4 Specification of Sampling Procedures General radiological environmental sampling procedures follow the directives presented in Sections 2.1 and 2.2. Specific information for handling individual sample types follow.

2.4.1 Vegetation Vegetation samples consist of green, growing grasses and weeds and are obtained three times per year, as available, from specified locations. New growth, not dead vegetation, should be used because these samples are indicators of recent atmospheric deposition. Use a scissors or other sharp cutting tool to cut the grasses and weeds off as close to the ground as possible.

Do not include plant roots and take care not to contaminate the sample with soil. Total sample collected should exceed 500 grams and ideally should be 1000 grams. Place entire sample in an appropriate container, such as a plastic bag (tape the bag shut) and label the container as described in Section 2.2.7.

2.4.2 Thermoluminescent dosimeters (TLDs)

TLDs capable of multiple, independent measurements of the same exposure are posted at locations specified in Table 2-4 and are changed quarterly. The utmost care in handling is required to minimize unnecessary exposure during transit, storage and posting because the TLDs begin recording all radiation from the moment they are annealed (heated to rezero) at the contractor's laboratory. Packages of TLDs in transit should be marked "DO NOT X-RAY."

Transportation control (TLDs) shall accompany the new batch in transit from the contractor's laboratory to the plant. The control TLDs shall accompany the batch during brief storage and subsequent posting. The same control TLDs shall accompany the "old" or exposed batch on its way back to the contractor. Therefore, each control represents the sum of approximately half the in-transit exposure of the two batches. This control system is able to identify any unusual in-transit exposure.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL Enviromnental TLDs should never be brought into the plant RCA or any other area with elevated radiation, but may be stored for brief periods in a shielded enclosure in the RP Office Area or other low background area, such as the Energy Information Center or the Site Boundary Control Center. The contractor is to time shipments to coincide as closely as possible with the beginning of a calendar quarter. TLDs should be shipped back to the contractor immediately or within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of removal. The contractor is instructed to process the samples irmnediately upon receipt. The contractor shall report removal data and cumulative readings in mR for all locations and control, correct for in-transit exposure and express results in net mR/7 days.

Labels of the exposed set for shipment to contractor should show both posting and removal dates.

2.4.3 Lake water Lake water samples are obtained monthly at specified locations. The contractor is responsible for the compositing for quarterly analyses. Collect approximately 8000 ml (2 gallons) of lake water in the required number of cubitainers, or other appropriate containers, at each location and label as directed in Section 2.2.7.

Also, lake water is collected for the State of Wisconsin pursuant to Table 2-5.

The sample is collected, labeled, and forwarded to the appropriate State agency.

2.4.4 Well water Well water samples are obtained quarterly from the single onsite well.

Sample should be obtained from PW-80, T-90 Hydro-pneumatic Tank Drain.

After purging 8 gallons, collect approximately 8000 ml (2 gallons) of well water using the required number of cubitainers or other appropriate containers. Label as directed in Section 2.2.7.

2.4.5 Air

a. Sample collection Air filters are changed weekly at specified locations and placed in glassine envelopes for shipment to the vendor for analyses. Take precautions to avoid loss of collected material and to avoid contamination when handling filters. Washing hands before leaving the plant to change filters is a recommended practice.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL Both particulate filters and charcoal cartridges are employed at each sampling location. Particulate filters are analyzed for gross beta activity after waiting for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to allow for the decay of short-lived radon and thoron daughter products. The contractor makes quarterly composites of the weekly particulate samples for gamma isotopic analyses.

A regulated pump (Eberline Model RAS-1 or equivalent) is used at each air sampling location. Because of the automatic flow regulation, flow meter readings at the beginning and ending of the sampling period should be nearly identical. Substantial differences in readings usually require some investigation to determine the cause. The flow meter attached to the pumps are calibrated in liters per minute. When new filters are installed, flow rate should be about 28-30 1pm. Flow rates less than 26 1pm or greater than 32 1pm require that the pump regulator be readjusted.

Pertinent air sampling data for each location is recorded on PBF-4078, Air Sampling Data Sheet. At a normal filter change, the following procedure will apply:

NOTE: Environmental flow rates should be approximately 30 1pm.

NOTE: The correction factor for the digital flow meter is always 1.0 similar to that of a Hi Vol air sampler.

1. Ensure unit is in flow mode.

2. Read and record the current flow rate (R,).

3. Press the RESET button while the pump is operating. This turns the pump OFF and preserves the elapsed time and total time values.

4. Record Date Off and time off (t2).

5. Press the UNITS button to read elapsed time (T) and total volume (mi3 ) and record.

NOTE: Always write data on the envelope before inserting the particulate filter in the envelope.

6. Label the sample envelope as directed in Section 2.2.7. Also enter any other pertinent information at this time.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL NOTE: Do NOT fold filter. Folding and unfolding may dislodge material from the filter and make a reproducible geometry impossible to achieve.

7. Remove particulate filter being careful to handle it only by the edges and place in the glassine envelope.

8. Remove charcoal cartridge, place in plastic bag, and label as directed in Section 2.2.7.

NOTE: Check the charcoal cartridge for breaks and the particulate filter for holes in the filter surface prior to installation.

Discard unacceptable filter media.

9. Install new charcoal cartridge and particulate filter.

10. Press the UNITS button until the time is displayed and time indicator is lit up.

11. Press the RESET button to zero the time.

12. Press the UNITS button until the total volume is displayed and total volume indicator is lit up.

13. Press the RESET button to zero the total volume.

14. Press the UNITS button until the flow is displayed and the flow indicator is lit up.

15. Press the RESET button to start the sample pump.

16. Record Date On and time on (tI).

17. Perform the weekly gross check by blocking the air flow with a large rubber stopper and verifying the displayed flow reads zero. Record test result.

18. Read and record the current flow rate (RI).

19. Compare current flow rate (RI) to previous ending flow rate (R2 ).

NOTE: The regulator will generally maintain a constant flow regardless of filter loading.

(a) If a substantial difference is found, investigate and identify cause. If condition can not be resolved, take the unit out of service and replace.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL

20. Calculate total volume for the sampling period and record, if required.

21. Record any unusual conditions or observations in the space provided at the bottom of the form.

Air samples are collected for the State of Wisconsin at two locations, one of which is co-located with a PBNP air sampling site. The State of Wisconsin samples are handled in a manner similar to the PBNP samples except that no charcoal cartridges are involved. State of Wisconsin samplers are equipped with volume integrating meters. Therefore, clock time must be recorded in addition to the ending and beginning volumes.

Label and forward all applicable air samples to the State of Wisconsin.

b. Air sampling system description The air monitoring equipment for the PBNP air sampling program consists of a Regulated Rate Control System. The Regulated Rate Control System is used at PBNP because of its simplicity and reliability. It is designed to minimize both calibration difficulties and the potential for leaks. The regulated rate control system includes a pump, a flow regulator, the appropriate filter holders and a minimum of tubing. Also, it may include an elapsed time meter. In this system, the total volume sampled can be calculated simply and accurately from the elapsed time and the flow rate which is kept constant by the regulator regardless of filter loading.

The air samplers are Eberline Model RAS-1 (or equivalent) and have built-in flow meters which read in liters per minute. The systems also include an Eberline WPH-1 (or equivalent) weatherproof housing and an iodine cartridge holder and mounting kit and may include an electric hour meter. Glass fiber, 47 mm diameter, particulate filters capable of collecting 95% of 1 micron diameter particles and iodine impregnated charcoal cartridges (Scott or equivalent) constitute the filter media.

c. Calibration Calibrate the pump flow meters at initial installation and at yearly intervals thereafter by connecting a laboratory-quality reference flow meter with NIST traceable calibration to the filter face with the particulate filter and charcoal cartridge in position. Upon completion, a calibration sticker is affixed to, or near, the flow meter. The results are recorded on Form PBF-4020.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL

d. Inspection and maintenance Weekly gross leak checks shall be accomplished as indicated in the appropriate PBNP procedure.

For normal operation, the regulators should be adjusted to maintain a true flow rate of 28-30 liters per minute. Adjustments are made by turning the screw marked FLOW ADJ located on the side of the regulator body:

counterclockwise increases flow, clockwise decreases flow. Flow rates should be observed at all filter changes. Flow rates less than 26 1pm or more than 32 1pm require readjustment of the regulator. Particular attention should be paid to flow rate readings with the "old," loaded filter and with new, unused filters in position. Because of the regulator, the difference in flow should be barely perceptible, perhaps no more than one 1pm. Significant differences in flow rates require further investigation to determine the cause.

Preventive maintenance shall be performed as indicated in the appropriate PBNP procedure on all environmental air samplers and the results recorded on Form PBF-4020.

e. Pump repair and replacement The pumps can operate for long periods of time with minimal or no maintenance. The vane assembly of the pump is most susceptible to failure, indicated by excessive noise or inability to maintain sufficient flow across loaded filters. At least one standby pump should be available for temporary service during the repair period. In the event of motor failures due to causes other than defective connections, complete replacement of the unit may be necessary. All pump repairs should be done in a clean-side shop with clean tools.

2.4.6 Milk Because of iodine decay and protein binding of iodine in aging milk samples, speed is imperative in processing and samples must be kept cool to avoid degradation and spoilage of the samples. Milk samples are obtained monthly in conjunction with the State of Wisconsin Milk Sampling Program from three individual dairy farmers located north, south, and west of the site. Milk sampling data can also be obtained from the Kewaunee Power Station (KPS),

whose radiological environmental monitoring program includes samples taken from a dairy in Green Bay, WI. This location could act as a control location.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL Because two of the three sites are co-located, the PBNP pickup is coordinated to coincide with the State arranged schedule. The pickup usually will be the second Wednesday of the month.

The following sequence should be followed:

a. After verifying the State milk pickup date with the Manitowoc Public Health Department (Mr. Mark Chatenka, phone number 683-4454), notify dairies of pickup date.

b. Because the milk must be kept cool, but not frozen, fill enough cubitainers, or other appropriate containers, with water and freeze to be able to put one in each shipping container. Fill the containers with water and freeze the day preceding the pickup or use ice packs.

c. The milk from the Strutz farm (E-2 1) must be picked up before 0900 because that is the time the Strutz milk is shipped. A late arrival may mean a missed sample. Milk from sites E-1 1 and E-40 may be picked up any time after the Strutz pickup.

d. Identify yourself and the nature of your business at each milk pickup site.

Collect two one-gallon samples from each site, using a funnel if necessary.

If shipment cannot occur on the collection day, store the milk in the environmental refrigerator at the SBCC overnight. DO NOT FREEZE.

e. Complete a PBNP sample tag according to Section 2.2.7 for each gallon sample and place in the box with the sample and ice or ice packs. Do not seal the box. Place the samples in insulated containers and turn them over to Ready Stores personnel for shipment. Make sure that the cover letter and, as appropriate, the contractor data collection sheets are sent according to Section 2.2.8 of this manual.

2.4.7 Algae Filamentous algae are collected from pilings or rocks three times per year, as available, from two locations. The long, grassy, dark green algae can normally be cut with scissors. The shorter, light green algae normally must be scraped from rocks or pilings. When scraping algae, be careful not to include pieces of rock in the sample. The sample can be lightly rinsed in the same medium in which it is growing. This rinse will help rid the sample of pieces of rock and gravel that may have been inadvertently collected with the sample. Because rocks and sediment contain naturally occurring radioactive materials, their inclusion may give false sample results. Collect between 100 and 1000 gm of algae. A sample greater than 500 gm is preferred. Place the algae in a wide-mouth poly bottle or other appropriate container and label the container as director in Section 2.2.7. The algae must be kept cool to prevent spoilage.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL 2.4.8 Fish The fish for the Point Beach REMP are obtained from either the traveling screens as washed into the fish baskets or by other methods, as required. The two-fold objective of fish sampling is to obtain commercially and recreationally important fish (game fish) that occur in the vicinity of the plant and to determine if there is evidence of PBNP released radionuclides in the fish.

There are three confounding factors affecting this objective. The first is the recycling of non-PBNP sources such as fallout from atmospheric weapons testing in the 1950s and 1960s and subsequent Chinese tests, fallout from the Chemobyl accident, and release from other plants on Lake Michigan. Due to the long residence time of water in Lake Michigan (about 200 years),

radionuclides entering Lake Michigan remain in the lake for a long time. This means that a long half life radionuclide such as Cs-137 is still present in the lake and in the fish.

The second confounding factor is the migratory behavior of the fish. In addition to moving around the lake, fish move from deep water to the shallower, inshore areas. It is only when the fish are in the inshore area that they are susceptible to being drawn into the PBNP water intake. Therefore, the radioactivity in the fish so caught may not originate from PBNP but from any of the above named sources.

In addition to the migratory behavior of fish, fish sampling also is effected by the fish deterrent system used at the PBNP water intake. The purpose of this system is to prevent schools of fish from being sucked into the cooling water intake.

As a result of all these factors, the availability of fish is not uniform throughout the year. Based on experience, the period from late Spring to early Fall appears to be the best period for obtaining game fish. Therefore, fish for the PBNP REMP will be sent for analysis at least twice a year based on seasonal availability. Fish also are supplied to the State of Wisconsin at the same frequency. (Fish may be sent more frequently if available.)

Operations removes the fish from the fish basket pursuant to 01 38 Attachment D. Each game fish is identified, placed in a clear plastic bag and the bag sealed, and the collection date and fish name written on the bag. The fish are placed in the game fish freezer in the pump house. Trash fish, such as carp are bagged and placed in the trash fish freezer.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL Because individual fish are analyzed, emphasis is placed on large fish which will yield at least 1000 grams (2.2 lbs.) of fillets in order to easily achieve the required LLD. Because of the aforementioned factors, it may not be possible to have enough large fish to fulfill the 1000 gram requirement. When this occurs, the lab will adjust count time on the available fish in order to achieve the required LLD.

1. Obtain the game fish from the freezer and package for shipment to the PBNP contracted radioanalytical lab and to the State. (If no game fish are available, trash fish from the larger freezer in the pump house may be used.)

2. Pack fish in an insulated container with ice or other similar cold media, as necessary, to prevent spoilage of the fish during transit. To aid in preventing the fish from thawing during transit, fish should be shipped so that they will arrive on or before Friday. If this is not possible, include enough cooling material so that the fish will not spoil if sitting on a loading dock over the weekend.

3. Send fish at the end of May and the end of August.

4. Divide the available fish approximately in half for shipment with PBNP contracted radioanalytical lab receiving the larger portion when an odd number of fish are available. If additional game fish are available later in the year, they will be sent during the fourth quarter.

5. The cognizant Chemist will make the final decision should fish sampling questions arise.

2.4.9 Soil Soil integrates atmospheric deposition and acts as a reservoir for long-lived radionuclides. Although soil sampling is a poor technique for assessing small incremental releases and for monitoring routine releases, it does provide a means of monitoring long-term trends in atmospheric deposition in the vicinity of PBNP. Therefore, soil samples are obtained two times per year from specified locations.

Clear the vegetation from a 6" x 6" area, being careful to leave the top layer of soil relatively intact. Remove root bound soil by shaking the soil onto the cleared area or into the sample container before discarding the roots. When necessary, it is preferable to leave some roots in the soil rather than to lose the top layer of soil.

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POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL Remove the soil to a depth of three inches. If necessary, expand the area, instead of digging deeper, to obtain the required amount of sample. If an area larger than 6" x 6" is used, notify Chemistry of the area used. The minimum acceptable quantity is 500 grams. Place the entire soil sample in a wide-mouth poly bottle or another appropriate container. If a plastic bag is used, seal the bag with tape. Label the sample as directed in Section 2.2.7.

This procedure assumes that the samples are obtained from undisturbed land; land that has not been plowed within approximately the last 25 years. If the land has been plowed, the soil should be sampled to the plow depth which typically is eight inches. Place the soil in a clean bucket or appropriate size plastic bag, homogenize the soil and place 1000 grams of the well mixed soil sample in a plastic bag, or other appropriate container, and label as described above.

2.4.10 Shoreline Sediment Shoreline sediment consisting of sand and smaller grain size material is sampled two times per year from specified locations. The 1000 gram sample is collected, from beach areas near the water ridge. At each location collect representative samples of sediment types roughly in proportion to their occurrence. For example, at E-06 avoid collecting a sample which consists exclusively of the dark-brown to black sediments which occur in layers up to several inches thick. Package the sample in a wide-mouth poly bottle or other appropriate container and label as described in Section 2.2.7.

2.5 Milk Survey The milk sampling program is reviewed annually, including a visual verification of animal grazing in the vicinity of the site boundary, to ensure that sampling locations remain as conservative as practicable. The verification is conducted each summer by cognizant PBNP personnel. Because it is already assumed that milk animals may graze up to the site boundary, it is only necessary to verify that these animals have not moved onto the site. No animal census is required. Upon completion of the visual check, a memo will be generated to document the review and the memo sent to file. To ensure perfornance of the annual verification, "milk review" is identified on the sampling checklist (i.e., the PBF-4121a-1 series).

Page 24 of 34 IN FORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL TABLE 2-1 TABLE 2-1 RECOMMENDED MINIMUM SAMPLE SIZES Sample Type Size Vegetation 100 -1000 gm Lake Water 8 liters (2 gal) 3 Air Filters 250 m Well Water 8 liters (2 gal)

Milk 8 liters (2 gal)

Algae 100-1000 gm Fish (edible portions) 1000 gm.

Soil 500-1000 gm Shoreline Sediment 500-1000 gm Page 25 of 34 IN FORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL TABLE 2-2 SAMPLE TYPES AND ASSOCIATED LOWER LEVEL OF DETECTION (LLD) AND NOTIFICATION LEVEL VALUES NOTIFICATION LEVELS WEIGHTED SAMPLE REPORTING NRC PBNPtb) SUM TYPE UNIT PARAMETER LLD(a) (Regulatory) (Admin.) ACTION LEVEL Vegetation pCi/g wet Gross Beta(0 0.25 60 Cs-137 0.08 2 0.40 0.50 Cs-134 0.06 1 0.20 0.25 1-131 0.06 0.1 0.06 0.06 Other(c) 0.25 2.0 Shoreline pCi/g dry Gross Beta 2.0 100 Sediment (sed.) Cs-134 (sed.) 0.15 (sed.) 20 (sed.)

and Soilt0 Cs-137 0.15 20 Other'c) 0.15 20 0

Algae( pCi/g wet Gross Beta 0.25 12 Cs-137 0.25 10 1 2.5 Cs- 134 0.25 10 1 2.5 Co-58 0.25 10 1 2.5 Co-60 0.25 10 1 2.5 Other(c) 0.25 1 Fish pCi/g wet Gross Betat0 0.5 125 Cs-137 0.15 2 0.40 0.50 Cs- 134 0.13 1 0.20 0.25 Co-58 0.13 30 3 7.5 Co-60 0.13 10 1 2.5 Mn-54 0.13 30 3 7.5 Fe-59 0.26 10 1 2.5 Zn-65 0.26 20 2 5.0 Other(c) 0.5 6 TLDs mR/7 days Gamma Exposure ImR/TLD 5mR/7 days Lakewater(e) Gross Beta 4 100 and Well Water pCi/L Cs-134 15 (10) 30 15 15 Cs-137 18 (10) 50 18 18 Fe-59 30 400 40 100 Zn-65 30 300 30 75 Zr-Nb-95 15 400 40 100 Ba-La-140 15 200 20 50 Co-58 15 (10) 1,000 100 250 Co-60 15 (10) 300 30 75 Page 26 of 34 IN FORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL TABLE 2-2 SAMPLE TYPES AND ASSOCIATED LOWER LEVEL OF DETECTION (LLD) AND NOTIFICATION LEVEL VALUES Lakewater pCiIL-T.S."(d Mn-54 15 (10) 1,000 100 250 and Well Water 1-131 1 (0.5) 2 2 (Continued) Other~c) 30 100 H-3 (Lakewater) 3,000 (200) 30,000 3,000 7,500 H-3 (Well Water) 2,000 (200) 20,000 2,000 7,500 Sr-89(o 10(5) 50 Sr-90tf 2(1) 20 Milk pCi/L Sr-89(" 5 100 Sr-90(o 1 100 0.5(g) 1-131 3 0.5 0.75 Cs-134 15 (5) 60 15 15 Cs-137 18 (5) 70 18 18 Ba-La- 140 15(5) 300 30 75 Other'c) 15 30 3

Air Filter pCi/m Gross Beta 0.01 1.0 1-131 0.07 (0.03) 0.9 0.09 0.2 Cs-137 0.06 20 2.0 5.0 Cs- 134 0.05 10 1.0 2.5 Other(cJ 0.1 1.0 (a) The LLDs in this column are the maximum acceptable values. The values in parentheses are the LLDs currently used (see Section 2.2.3)

(b) The values in this column are not technical specifications.

(c) Other refers to non-specified identifiable gamma emitters, resulting from the operation of PBNP. Naturally occurring radionuclides are not included.

(d) T.S. = total solids, applies only to Gross Beta, all others to gamma scan of liquid.

(e) No drinking water (f) These items or analyses are not in NUREG-1301 (g) Lower than NUREG-1301 value of I pCi/L to support PBNP's sampling frequency.

Page 27 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL TABLE 2-3 RADIOLOGICAL ENVIRONMENTAL 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, the TLD is on South side of Two Creeks Road, West of Lakeshore Road on first pole West of Lakeshore.

E-06 Point Beach State Park - Water and shoreline sediment samples at the Coast Guard Station; soil and vegetation from the Point Beach State Park campground area N of the Coast Guard Station and on the West side of County Road 0; TLD located South of lighthouse on telephone pole.

E-07 WPSC Substation on County Rt. V, about 0.5 Miles West of Hwy. 42 E-08 G. J. Francar Property, at the SE Corner of the Intersection of Cty. B and Zander Road E-09 Nature Conservancy, East side of Hwy 42. Comer of Hwy 42 and Cty. BB. On pole North side of Entrance.

E-10 PBNP Site Well E-1 I Lambert Dairy Farm, 1523 Tapawingo Road, 0.5 miles West of Saxonburg Road E-12 Discharge Flume / Pier, U-I side E- 13 Pumphouse E-14 South Boundary, about 0.2 miles East of Site Boundary Control Center E-15 SW Corner of Site, N side of Nuclear Rd at junction with Twin Elder Rd.

E-16 WSW, Hwy. 42, Residence, about 0.25 miles North of Nuclear Road E-17 North of Mishicot, Cty. B and Assman Road, NE Corner of Intersection E-1 8 NW of Two Creeks at Zander and Tannery Roads E-20 Reference Location, 17 miles SW, at Silver Lake College E-21 Local Dairy Farm just South of Site (R. Strutz) 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/Saxonberg Road E-26 804 Tapawingo Road, about 0.4 miles East of Cty. B. North Side of Road E-27 NE corner of Saxonburg and Nuclear Roads, about 4 Miles WSW E-28 TLD on westernmost pole between the 2nd and 3rd parking lots, E-29 On microwave tower fence 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 Page 28 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL TABLE 2-3 RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS E-32 On a conduit/pole located near the junction of property lines, about 500 feet east of the west gate in line with first designated treeline 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. (The conduit/pole is about 6 feet high).

E-33 Lake Michigan shoreline accessed from area just S of KPS discharge.

E-38 On tree West of former Retention Pond site E-39 On tree East of former Retention Pond site E-40 Local Dairy Farm (Barta), about 1.8 miles north of intersection of Highway 42 and Nuclear Road (Manitowoc County), on West side of Highway 42.

E-41 NW corner of Woodside and Nuclear Roads (Kewaunee Co.)

E-42 NW corner of Church and Division, East of Mishicot E-43 West Side of Tannery Road South of Elmwood (7th pole South of Elmwood)

E-TC Transportation Control; Reserved for TLDs Page 29 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL TABLE 2-4 PBNP RADIOLOGICAL ENVIRONMENTAL SAMPLE COLLECTION AND ANALYSIS 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 2x/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 (on total solids)

Lake Water E-01, -05, -06, Gross Beta Monthly

-33 H-3, Sr-89, 90 Quarterly composite of monthly collections 1-131 Monthly Gamma Isotopic Analysis Monthly (on total solids)

Milk E-ll, -21,-40 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, Gross Beta 2x/yr

-33 Gamma Isotopic Analysis Page 30 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL TABLE 2-5 SAMPLES COLLECTED FOR STATE OF WISCONSIN Sample Type Location Frequency

1. Lake Water E-01 Monthly

2. Air Filters E-07 Weekly E-08

3. Fish E-13 Semiannuall' Y, As Available

4. Precipitation E-04 Twice a month, E-08 As Available

5. Milk E-2 1 Monthly E-40

6. Well Water E-10 2 times/year Page 31 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL FIGURE 2-1 a RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Page 32 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL FIGURE 2-lb RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Page 33 of 34 INFORMATION USE

POINT BEACH NUCLEAR PLANT EM ENVIRONMENTAL MANUAL Revision 25 February 11, 2014 ENVIRONMENTAL MANUAL FIGURE 2-1 c RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Page 34 of 34 INFORMATION USE