Text

2021 Annual Monitoring Report
	ML22104A074
Person / Time
Site:	Point Beach
Issue date:	04/14/2022
From:	Schultz E; Point Beach
To:	; Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Regulatory Research
References
	NRC 2022-0014
	Download: ML22104A074 (162)
	v • d • e

NEXTera ENERGY ~

POINT BEACH April 14, 2022 NRC 2022-0014 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 2021 Annual Monitoring Report Enclosed is the Annual Monitoring Report for PBNP Units 1 and 2, for the period January 1 through December 31 , 2021.

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

Sincerely, NextEra Energy Point Beach, LLC

~ ~ [ir'<:, ::Mctlt Eric Schultz L Licensing Manager Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW American Nuclear Insurers WI Division of Public Health, Radiation Protection Section Office of Nuclear Material Safety and Safeguards, USNRC NextEra Energy Point Beach, LLC 6610 Nuclear Road, Two Rivers, WI 54241

ENCLOSURE ANNUAL MONITORING REPORT 2021 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT DOCKETS 50-266 (UNIT 1), 50-301 (UNIT 2),72-005 (ISFSI)

RENEWED LICENSES DPR-24 and DPR-27 January 1, 2021 through December 31, 2021

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 16 5.0 Nonradioactive Chemical Releases 18 6.0 Circulating Water System Operation 19 Part B: Miscellaneous Reporting Requirements 7.0 Additional Reporting Requirements 20 Part C: Radiological Environmental Monitoring 8.0 Introduction 21 9.0 Program Description 22 10.0 Results 34 11.0 Discussion 39 12.0 REMP Conclusion 54 Part D: Groundwater Monitoring 13.0 Program Description 55 14.0 Results and Discussion 58 15.0 Groundwater Summary 64 Part E: Errata/Corrections to Previous Annual Monitoring Reports 16.0 Corrections to Previous Reports 65 Appendix 1: Environmental, Inc. Midwest Laboratory, "Final Report for Point Beach Nuclear Plant" II

LIST OF TABLES Table 2-1 Comparison of 2021 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 Beach and Subsoil System Drains - Tritium Summary 8 Table 3-1 Comparison of 2021 Airborne Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives 13 Table 3-2 Radioactive Airborne Effluent Release Summary 13 Table 3-3 Isotopic Composition of Airborne Releases 14 Table 3-4 Comparison of Airborne Effluent Doses 15 Table 4-1 Quantities and Types of Waste Shipped from PBNP in 2021 16 Table 4-2 2021 PBNP Radioactive Waste Shipments I 16 Table 4-3 2021 Estimated Solid Waste Major Radionuclide Composition ' 17 Table 6-1 Circulating Water System Operation for 2021 19 Table 9-1 PBNP REMP Sample Analysis and Frequency 24 Table 9-2 PBNP REMP Sampling Locations 25 Table 9-3 ISFSI Sampling Sites 29 Table 9-4 Minimum Acceptable Sample Size 29 Table 9-5 Deviations from Scheduled Sampling and Frequency During 2021 30 Table 9-6 Sample Collection for the State of Wisconsin 30 Table 10-1 Summary of Radiological Environmental Monitoring Results for 2021 36-37 Table 10-2 Average ISFSI Fence TLD Results for 2021 38 Table 11-1 Average Indicator TLD Results from 1993-2021 39 Table 11-2 Average ISFSI Fence TLD Results (mR/7days) 40 Table 11-3 Average TLD Results Surrounding the ISFSI (mR/7days) 42 Table 14-1 Intermittent Streams and Bogs 58 Table 14-2 2021 Beach Drain Tritium 59 Table 14-3 2021 East Yard Area Manhole Tritium (pCi/L) 60 Table 14-4 2021 Fagade Well Water Tritium (pCi/L) 61 Table 14-5 2017-2021 Unit 2 Fagade SSD Sump H-3 (pCi/L) 62 Table 14-6 2021 Potable Well Water Tritium Concentration (pCi/L) 63 Table 14-7 2021 Quarterly Monitoring Well Tritium (pCi/L) 63 LIST OF FIGURES Figure 9-1 PBNP REMP Sampling Sites 26 Figure 9-2 Map of REMP Sampling Sites Located Around PBNP 27 Figure 9-3 Enhanced Map Showing REMP Sampling Sites Closest to PBNP 28 Figure 11-1 ISFSI Area TLD Results (1995-2021) 41 Figure 11-2 Comparison of ISFSI Fence TLDs to Selected REMP TLDs 42 Figure 11-3 Sr-90 Concentration in Milk (1997 - 2021) 44 Figure 11-4 Annual Average Air Gross 13 (1993 - 2021) 44 Figure 11-5 2021 Airborne Gross Beta 45 Figure 11-6 2015 Airborne Gross Beta 45 Figure 11-7 E-01Results1971-2021 51 Figure 11-8 Comparison of E-03 and E-20 Results 1971 - 2021 52 Figure 11-9 Comparison of E-01, E-02, E-03, and E-04 Results 1992 - 2021 52 Figure 11-10 E-03, E-31, and E-44 Background Site E-20 Results 1992 - 2021 53 Figure 13-1 Groundwater Monitoring Locations 57 iii

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SUMMARY

I The Annual Monitoring Report for the period from January 1, 2021, through December 31, 2021, 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 Renewed 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 2021, the following Curies (Ci) of radioactive material were released via the liquid and atmospheric pathways:

Liquid Atmospheric Tritium (Ci) 895 69.1 1

Particulate (Ci) 0.0381 0.0000216 Noble Gas (Ci) 0.00978 0.889 2

C-14 0.0299 10.87 1Atmospheric particulate includes radioiodine (1-131 133).

2 Liquid 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) and comply with the EPA's limits in 40CFR190. 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 Category Calculated Dose Appendix I Dose % Appendix I Whole body dose 0.00196 mrem 6 mrem 0.033 Organ dose 0.00214 mrem 20 mrem 0.011 ATMOSPHERIC RELEASES Dose Category Calculated Dose Appendix I Dose % Appendix I Particulate organ dose 0.00853 mrem 30 mrem 0.0284 Noble gas beta air dose 0.0000509 mrad 40 mrad 0.00013 Noble gas gamma ray air dose 0.000127 mrad 20 mrad 0.00063 Noble gas dose to the skin 0.000177 mrem 30 mrem 0.00059 Noble gas dose to the whole body 0.000120 mrem 10 mrem 0.00120 1

The results show that during 2021, the doses from PBNP effluents were ::>0.033% of the Appendix I design objectives. This is less than the 2020 result of 0.036%. 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 12.2.5 of the PBNP ODCM. As in previous years, no dairy cattle were found to be grazing at the site boundary. Therefore, the assumption that cattle graze at the site boundary used in the evaluation of doses from PBNP effluents remains conservative. Of the sixteen compass sectors around PBNP, six are over Lake Michigan. A land use census (LUC) of the remaining ten sectors over land identifies any changes in the closest garden, occupied dwelling, and dairy in each sector. The 2020 LUC results confirm the assumption that, for the purpose of calculating effluent doses, the maximally exposed person lives at the site boundary remains conservative.

The 2021 Radiological Environmental Monitoring Program (REMP) collected 724 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 12 samples. This yielded a total of 760 samples. The ambient radiation measurements in the vicinity of PBNP and the ISFSI were conducted using 148 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, and fish revealed no buildup of PBNP radionuclides released in liquid effluents. Therefore, the data shows no environmental effect from plant operation.

In 2021, six dry storage units were added to the ISFSI. The total number is 56 dry storage casks: 16 ventilated, vertical storage casks (VSC-24) and 34 NUHOMS, horizontally stacked storage modules, and 6 HOLTEC HI-STORM FW 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 2021 confirmed that the effluent control program at PBNP ensured a minimal impact on the environment.

One-hundred-sixty-one (161) samples were analyzed for tritium as part of the groundwater protection program (GWPP). These samples came from drinking water wells, monitoring wells, yard drain outfalls, yard manholes, surface water on site, the sump for the subsurface drainage system (SSD - located under the plant foundation), and four groundwater foundation integrity monitoring wells located in the facades. The results show no substantial change in tritium from previous years. No drinking water wells (depth >100 feet) have any detectable tritium that is statistically different than zero. 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 tritium. Gamma scans of groundwater samples originating within the power block found no plant related gamma emitters.

Fagade well samples had tritium results within the expected ranges (-200 pCi/L).

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

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I Part A EFFLUENT MONITORING I

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 in line 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. The appropriate portions of the radwaste treatment systems are used as required to keep both liquid and atmospheric 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 ISFSI annual reporting requirement pursuant to 10 CFR 72.44(d)(3) is no longer applicable (

Reference:

64 FR 33178). Any release of radioactive materials from the operation of the ISFSI must 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 MEI is assumed to reside at the site boundary in the highest x!Q sector and is maximized with respect to occupancy, food consumption, and other uses of this area. As such, the MEI represents an individual with reasonable deviations from the average for the general population in the vicinity of PBNP. A comparison of the calculated doses to the 10 CFR 50, Appendix I design objectives is presented in Table 2-1. The conservatively calculated dose to the MEI is a very small fraction of the Appendix I design objective.

Table 2-1 Comparison of 2021 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Annual Limit [mrem] Highest Total Calculated Dose % of Design

[mrem] Objective 6 (whole body) 0.00196 0.033 20 (any organ) 0.00214 0.011 2.2 2021 Circulating Water Radionuclide Release Summary Radioactive liquid releases via the circulating water discharge are summarized by individual source and total curies released on a monthly basis, 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 2021 Isotopic Composition of Circulating Water Discharges The isotopic composition of circulating water discharges during the current reporting period is presented in Table 2-3.

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The 2021 processed waste volume (Table 2-2) decreased from 2020 (7.91 E+05 gallons to 5.33E+05 gallons), which is consistent with water processing requirements during a one outage year. The total isotopic curie distribution of gamma emitters plus hard-to-detects from 2021 was 6.80E-02 Ci, which is lower than the 2020 value of 7.56E-02 Ci. The total antimony in 2021 increased to 5.58E-03 Ci in comparison to 2020 (4.08E-03 Ci). Zr-Nb increased to 6.41 E-04 when compared to the 5.50E-04 Ci totaled in 2020. Tin isotopes (Sn-113/Sn-117m) totals increased to 3.49E-04 Ci in 2021 compared to the 6.72E-05 Ci in 2020. Te-123m was documented at 3.22E-03 in 2021, which is a decrease from the 7.41E-03 Ci observed in 2020. The 2021 C-14 increased to 2.99E-02 Ci from the 2020 value of 2.73E-02 Ci. No strontium isotopes were observed in the 2021 effluent. Tritium increased to 895 Ci in 2021 in comparison to the 823 Ci observed in 2020.

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. These outfalls carry yard and roof drain runoff to the beach. The plant foundation has a subsurface drainage system (SSD) around the external base of the foundation. This SSD relieves hydrostatic pressure on the foundation by draining water away from the foundation. The drainage pipes empty out onto the beach. In 2014, the SSD outfalls, designated as S-12 and S-13, were added to the beach drain sampling program. Their quarterly results are presented with the other beach drains.

The quarterly results from the monthly beach drain and SSD 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 2020, no tritium was observed at the effluent LLDs. Tritium found in the beach drains is not 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 tritium has been determined to be recapture, including beach drain tritium 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 containing recaptured tritium.

During the winter natural melting is the principle source. 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 tritium 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, 2021 through December 31, 2021 Total Total Annual Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec July-Dec Total Total Activity Released (Ci)

Gamma scan(+H 1us) 5.65E-03 3.61E-03 4.33E-03 7.41 E-03 1.42E-03 3.58E-03 2.60E-02 8.01E-03 4.37E-03 7.13E-03 7.74E-03 1.25E-02 2.24E-03 4.20E-02 6.SOE-02 Gross Alpha ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Tritium 2.61E+OO 9.27E+01 5.31E+01 1.60E+02 1.03E+01 9.69E+01 4.15E+02 1.78E+02 5.45E+01 6.26E+01 1.08E+02 4.41E+01 3.19E+01 4.80E+02 8.95E+02 Strontium (89/90/92) ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Noble Gases O.OOE+OO 3.83E-04 3.0SE-04 4.36E-04 O.OOE+OO 2.34E-04 1.36E-03 1.40E-03 2.05E-03 2.85E-04 1.82E-03 2.13E-03 7.31E-04 8.41E-03 9.78E-03 Total Vol Released (gal)

Processed Waste 6.65E+03 3.54E+04 2.06E+04 3.20E+04 1.36E+04 2.91E+04 1.37E+05 4.67E+04 5.30E+04 4.50E+04 1.31 E+05 9.62E+04 2.39E+04 3.95E+05 5.33E+05 Waste Water Effluent 3.66E+06 3.36E+06 3.73E+06 3.73E+06 3.49E+06 3.33E+06 2.13E+07 3.50E+06 3.93E+06 3.65E+06 2.85E+06 3.68E+06 3.90E+06 2.15E+07 4.28E+07 U1 SG Slowdown 6.25E+06 5.63E+06 6.23E+06 5.29E+06 2.68E+06 3.13E+06 2.92E+07 2.66E+06 3.07E+06 2.59E+06 2.77E+06 2.57E+06 2.67E+06 1.63E+07 4.55E+07 U2 SG Slowdown 2.65E+06 2.47E+06 2.68E+06 2.58E+06 2.67E+06 2.70E+06 1.58E+07 2.67E+06 2.67E+06 2.63E+06 7.89E+05 4.82E+06 3.33E+06 1.69E+07 3.27E+07 Total Gallons 1.26E+07 1.15E+07 1.27E+07 1.16E+07 8.86E+06 9.19E+06 6.64E+07 8.87E+06 9.73E+06 8.91E+06 6.53E+06 1.12E+07 9.92E+06 5.51E+07 1.22E+08 Total cc 4.75E+10 4.35E+10 4.79E+10 4.40E+10 3.35E+10 3.48E+10 2.51 E+11 3.36E+10 3.68E+10 3.37E+10 2.47E+10 4.23E+10 3.76E+10 2.09E+11 4.60E+11 u11ut1on vol\ cc,- 7.91E+13 7.14E+13 7.91E+13 1.03E+14 1.27E+14 1.23E+14 5.82E+14 1.27E+14 1.27E+14 1.23E+14 8.41 E+13 1.19E+14 5.93E+13 6.39E+14 1.22E+15 Avg diluted discharge cone (µCi/cc)

Gamma scan (+H 1us) 7.14E-11 5.06E-11 5.47E-11 7.20E-11 1.12E-11 2.92E-11 2.89E-10 6.32E-11 3.44E-11 5.SOE-11 9.21E-11 1.05E-10 3.78E-11 3.90E-10 6.79E-10 Gross Alpha ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Tritium 3.29E-08 1.30E-06 6.71 E-07 1.55E-06 8.13E-08 7.89E-07 4.43E-06 1.41 E-06 4.30E-07 5.10E-07 1.29E-06 3.70E-07 5.37E-07 4.54E-06 8.97E-06 Strontium (89/90/92) ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Noble Gases O.OOE+OO 5.37E-12 3.90E-12 4.24E-12 O.OOE+OO 1.91E-12 1.54E-11 1.10E-11 1.61E-11 2.32E-12 2.16E-11 1.79E-11 1.23E-11 8.13E-11 9.67E-11 Max Batch Discharge Cone (µCi/cc)

Tritium 6.64E-06 3.17E-05 2.98E-05 3.27E-05 7.35E-06 2.75E-05 3.50E-05 3.37E-05 2.10E-05 3.65E-05 1.35E-05 2.51E-05 Gamma Scan 3.29E-11 1.25E-10 6.09E-11 4.96E-11 9.64E-11 3.82E-11 2.85E-10 4.36E-10 2.48E-10 2.29E-09 4.48E-09 4.23E-10 1 HTDs include Fe-55, C-14, Ni-63, and Tc-99. Does not include strontium which is totaled separately.

2 Circulating water discharge from both units.

ND: means that the radionuclide was not identified in any samples and all analyses were performed with instrumentation meeting the lower limit of detection as required by the PBNP Offsite Dose Calculation Manual.

NR: means No Release during that month 6

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

January, 2021 through December 31, 2021 Total Total Annual Nuclide Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec July-Dec Total H-3 2.61E+OO 9.27E+01 5.31 E+01 1.60E+02 1.03E+01 9.69E+01 4.15E+02 1.78E+02 5.45E+01 6.26E+01 1.08E+02 4.41 E+01 3.19E+01 4.80E+02 8.95E+02 C-14 ND 1.47E-03 1.41 E-03 5.09E-03 ND 1.76E-03 9.73E-03 6.37E-03 2.41 E-03 5.62E-03 2.87E-03 2.33E-03 5.96E-04 2.02E-02 2.99E-02 F-18 5.61 E-03 1.77E-03 2.79E-03 2.05E-03 1.24E-03 1.63E-03 1.51 E-02 1.16E-03 1.06E-03 1.06E-03 1.27E-03 1.21 E-03 1.20E-03 6.96E-03 2.20E-02 Cr-51 ND ND ND ND ND ND ND ND ND ND 5.43E-05 2.52E-03 ND 2.57E-03 2.57E-03 Mn-54 ND ND ND ND ND ND ND ND ND ND ND 3.69E-05 ND 3.69E-05 3.69E-05 Fe-55 ND ND ND ND ND ND ND 1.38E-04 ND ND ND ND ND 1.38E-04 1.38E-04 Fe-59 ND ND ND ND ND ND ND ND ND ND ND 5.05E-05 ND 5.05E-05 5.05E-05 Co-57 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Co-58 8.59E-06 5.47E-05 8.63E-06 3.01E-06 1.92E-05 5.97E-06 1.00E-04 6.97E-06 4.67E-06 ND 6.88E-05 1.14E-03 2.22E-05 1.24E-03 1.34E-03 Co-60 7.05E-06 5.90E-05 1.73E-05 1.66E-05 5.94E-05 3.97E-05 1.99E-04 5.02E-05 6.15E-05 4.87E-05 1.65E-04 5.50E-04 3.94E-05 9.15E-04 1.11 E-03 Ni-63 2.47E-05 3.49E-05 ND ND 9.81E-05 5.50E-05 2.13E-04 ND 1.47E-04 ND ND ND ND 1.47E-04 3.59E-04 Zn-65 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Se-75 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND As-76 ND ND ND ND ND ND ND ND ND ND 1.03E-04 1.33E-04 ND 2.36E-04 2.36E-04 Sr-90 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Sr-92 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Nb-95 ND ND ND ND ND ND ND ND ND ND ND 4.04E-04 5.71 E-06 4.10E-04 4.10E-04 Nb-97 ND ND ND ND ND ND ND ND ND ND 4.39E-06 6.77E-06 ND 1.12E-05 1.12E-05 Zr-95 ND ND ND ND ND ND ND ND ND ND ND 2.20E-04 ND 2.20E-04 2.20E-04 Zr-97 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Tc-99 ND 1.07E-05 1.17E-05 9.45E-06 2.38E-06 6.38E-06 4.06E-05 4.42E-05 5.82E-05 2.04E-05 4.94E-05 3.24E-05 5.42E-06 2.10E-04 2.51E-04 Ag-110m ND ND ND ND ND ND ND ND ND ND 3.00E-05 7.32E-05 3.28E-06 1.06E-04 1.06E-04 Sn-113 ND ND ND ND ND ND ND ND ND ND ND 2.87E-04 5.00E-06 2.92E-04 2.92E-04 Sn-117m ND ND ND ND ND ND ND ND ND ND ND 5.63E-05 ND 5.63E-05 5.63E-05 Sb-122 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Sb-124 ND 2.16E-05 6.16E-06 1.49E-05 ND ND 4.27E-05 ND 6.83E-06 ND 6.49E-05 1.35E-04 2.06E-06 2.09E-04 2.51E-04 Sb-125 ND 1.28E-04 6.07E-05 1.68E-04 ND 6.88E-05 4.25E-04 2.33E-04 5.86E-04 3.62E-04 2.81 E-03 8.79E-04 3.04E-05 4.91E-03 5.33E-03 1-131 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND 1-132 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Te-123m ND 6.11E-05 2.41 E-05 5.91 E-05 ND 1.19E-05 1.56E-04 2.02E-05 3.69E-05 2.18E-05 2.49E-04 2.41E-03 3.32E-04 3.07E-03 3.22E-03 Te-132 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Cs-136 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Cs-137 ND 4.88E-06 1.88E-06 ND 5.48E-06 2.68E-06 1.49E-05 ND ND ND ND ND ND ND 1.49E-05 Cs-138 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND La-140 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Xe-131m ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Xe-133 ND 3.83E-04 3.05E-04 4.35E-04 ND 2.33E-04 1.36E-03 1.39E-03 2.00E-03 2.85E-04 1.81 E-03 2.10E-03 7.26E-04 8.32E-03 9.67E-03 Xe-133m ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Xe-135 ND ND 3.41 E-06 1.68E-06 ND 1.40E-06 6.49E-06 8.53E-06 4.58E-05 ND 7.04E-06 3.17E-05 5.29E-06 9.84E-05 1.05E-04 ND: means that the radionuclide was not identified in any samples and all analyses were performed with instrumentation meeting the lower limit of detection as required by the PBNP Offsite Dose Calculation Manual.

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Table 2-4 Beach and Subsoil System Drains - Tritium Summary January 1, 2021 through December 31, 2021 S-1 S-3 S-7 S-8 S-9 S-10 S-12 S-13 1st Qtr H-3 (Ci) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Flow (gal) 2.23E+04 2.68E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2nd Qtr H-3 (Ci) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Flow (gal) 3.96E+05 8.78E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3rd Qtr H-3 (Ci) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Flow (gal) 4.23E+05 3.00E+05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.12E+05 O.OOE+OO 4th Qtr H-3 (Ci) O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Flow (gal) 3.51 E+05 1.00E+05 O.OOE+OO O.OOE+OO 0.00E+OO O.OOE+OO 1.34E+04 O.OOE+OO 2.6 Land Application of Sewage Sludge and Wastewater In 1988, pursuant to 10 CFR 20.302(a), Point Beach received NRC 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 or equalization basin disposals by land application during 2021.

All disposals from the PBNP sewage treatment plant (STP) were done at the Manitowoc Sewage Treatment Plant. A total of 78,600 gallons in 15 shipments were sent to Manitowoc. All sludge and equalization basin discharges were analyzed to environmental LLDs, except for 2 which were analyzed to effluent LLDs and less than detectable. Naturally occurring radionuclides such as Ra-226 and K-40 were present in all samples. For the shipments in 2021 the total Ra-226 and K-40 were 43.6 µCi and 46.2 µCi, respectively. Small concentrations of H-3 (not detectable - 902 pCi/L) were found in thirteen (13) of the shipments for a total of 73.8 µCi. Based on the daily flow at the Manitowoc plant, the H-3 discharge concentration would be on the order of 0.303 pCi/L or 66,000 times lower than the EPA drinking water limit of 20,000 pCi/L.

The STP H-3 is attributable to groundwater in-leakage at the STP lift station whose volume is known to increase after a heavy rain or snow melt event. The STP is in the groundwater flow path from the retention pond area and the lake. The STP H-3 concentrations are comparable to those found in the retention pond area monitoring wells.

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2.7 Carbon-14 Carbon-14 (C-14) is a naturally occurring radionuclide. Nuclear weapons testing in 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 occurs naturally. Based on information from the NRC obtained at industry sponsored workshops, 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.

The NRC requested that all nuclear plants report C-14 emissions beginning with the 2010 monitoring reports. 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, as stated above, Point Beach began C-14 analyses and reporting prior to the issuance of RG 1.21 (Rev 2). 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. In this case, C-14 is compared to other (non-tritium or noble gases) radionuclides discharged in liquids.

For 2021, the monthly and total C-14 (2.99E-02 Ci) in liquid discharges is documented in Table 2-3. The 2021 amount of C-14 released makes up about 38.5% of the non-tritium radionuclides released in liquids (2.99E-02/7.77E-02).

The liquid C-14 dose contribution is included in the doses calculated for the hypothetically, maximally exposed individual (Table 2-1 ). Under the parameters and pathways used for the dose calculations, the C-14 dose contribution to the infant age group ranges from 0.0904 to 0.0906% of the dose to the whole body and the applicable organs except for bone, for which C-14 contributes 57.1 % of the total dose. For the remaining age groups, the C-14 contributes roughly 95.4% of the bone dose and 7.28 - 14.3% of the dose to the whole body and to other organs specified in RG 1.109.

2.8 Abnormal Release One abnormal liquid release occurred in 2021 when a Unit 1 hotwell containing tritium was discharged directly to circulating water on 8/2/2021. A sample had been taken prior to the discharge which identified tritium in the sample, but a permit was not generated prior to release. The sample contained 8.88E-06

µCi/cc tritium prior to dilution, and had a discharge concentration of 1.42E-08

µCi/cc. A total of 4.44E-04 Ci were discharged during this release, which was 0.000815% of the total tritium curies released in August 2021 (54.5 Ci). Based on the sample results obtained before the release, the volume discharged, and amount of time it took to perform the discharge, quantification of the release was possible and no ODCM limits were exceeded or challenged.

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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.

C-14 is not included in the Appendix I calculations 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 8.53E-03 mrem for the child age group thyroid. Had C-14 been included, the child-bone dose would have been the highest at 2.25E-01 mrem. Even with the inclusion of C-14 the doses demonstrate that releases from PBNP to the atmosphere continue to be ALARA at 0.8% of the dose objective.

3.2 Radioactive Airborne Release Summary Radioactivity released in airborne effluents for 2021 is summarized in Table 3-2.

The particulate total increased to 2.16E-05 Ci in 2021 from 1. 76E-05 Ci in 2020.

Tritium decreased in 2021 to 69.1 Ci from 87.1 Ci in 2020. Noble gases increased to 8.89E-01 Ci from 8.85E-01 Ci in 2020 .

3.3 Isotopic Airborne Releases The monthly isotopic airborne releases for 2021, 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.

As in previous years the outage impact of the isotopic mixture is demonstrated in the comparison of the non-outage particulate releases. During the outage in October, eight different particulates were identified in the airborne effluent. Most were released via the open hatches on the 26 and 66-foot elevation of containment. The convective flow through the open hatch during purge is unfiltered. Although the flow is into the fac;ade, there are two circumferential gaps around the fac;ade. It is assumed that the release into fac;ade is transferred 10

to the outside and therefore is treated as a release to the environment. As was stated in Section 3.2, the total particulate curies observed increased in 2021 when compared to 2020.

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, the amount produced by nuclear reactors is much less than that produced by weapons testing or that occur naturally.

The NRC has requested that nuclear plants report C-14 emissions. 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) developed 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 VCTs is used in the C-14 calculation as both gases contribute to the generation of C-14. 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.

The Point Beach C-14 generation for 2021 was calculated using the EPRI guidance and the current core parameters resulting from the power uprate. The calculated amounts were 5.41 Ci for Unit 1 and 5.46 Ci for Unit 2 yielding a total of 10.87 Ci which is lower, but statistically the same as 2016 through 2020. The 2021 calculated total 10.87 Ci is roughly 360 times higher than the 2.99E-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 contribute to the inhalation dose. Only the inorganic 14 C02 species contributes to the dose from the ingestion of photosynthetically incorporated C-14. The organic forms such as methane, CH4, are not photosynthetically active. For PWRs such as PBNP most of the gaseous C-14 occurs as methane, 14 CH4, not as carbon dioxide, 14 C02.

The amount of 14 C02 present in the PBNP airborne effluent has not been measured. However, such measurements have been made at a comparable PWR site 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).

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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 14 C02. Therefore, 10% of the 10.87 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. In 2018 the inhalation dose factors were updated to reflect a change in the x/Q value in the Point Beach ODCM Rev. 20. The inhalation dose was calculated using all forms of C-14. All forms of the C-14 are used because regardless of whether the C-14 is in the form of 14 C0 2 or an organic form, such as CH4, 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 14 C02 and accounts for only 10% 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 are 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 was leased for feed corn by a dairy south of the plant. That dairy is part of the REMP. In an adjacent field soybeans were 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 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).

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Table 3-1 Comparison of 2021 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 0.00853 mrem 0.0284 Noble gas 40 mrad (beta air) 0.0000509 mrad 0.00013 Noble gas 20 mrad (gamma air) 0.000127 mrad 0.00063 Noble gas 30 mrem (skin) 0.000177 mrem 0.00059 Noble qas 1O mrem (whole body) 0.000120 mrem 0.00120 Table 3-2 Radioactive Airborne Effluent Release Summary January 1, 2021 through December 31, 2021 Total Total Annual Jan Feb Mar Apr May Jun Jan-Jun Jul Aug Sep Oct Nov Dec July-Dec Total 1

Total Noble Gas (Ci) 7.19E-02 5.29E-02 5.43E-02 4.87E-02 7.81E-02 5.55E-02 3.61 E-01 7.67E-02 5.70E-02 4.88E-02 1.39E-01 9.23E-02 1.14E-01 5.28E-01 8.89E-01 Total Radioiodines (Ci) 2 ND ND ND ND ND ND ND ND ND ND 9.82E-07 ND ND 9.82E-07 9.82E-07 3

Total Particulate (Ci) ND ND ND ND ND ND ND ND ND ND 2.07E-05 ND ND 2.07E-05 2.07E-05 Alpha (Ci) ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Strontium( Ci) ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND All other beta +gamma (Ci) ND ND ND ND ND ND ND ND ND ND 2.07E-05 ND ND 2.07E-05 2.07E-05 Total Tritium (Ci) 7.17E+OO 5.48E+OO 5.38E+OO 5.66E+OO 3.95E+OO 4.32E+OO 3.20E+01 4.57E+OO 5.30E+OO 7.00E+OO 9.27E+OO 4.34E+OO 6.65E+OO 3.71E+01 6.91E+01 Max NG H'rly Rel.(Ci/sec) 5.14E-08 5.12E-08 5.12E-08 4.86E-08 1.64E-07 7.73E-08 8.51E-08 7.38E-08 5.75E-08 5.87E-08 9.82E-08 1.25E-07 1 Total noble gas (airborne releases) and activation gas Ar-41. It does not include the activation gas F-18 because of its short T11z and because it is not an Appendix I radionuclide.

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.

ND: means that the radionuclide was not identified in any samples and all analyses were performed with instrumentation meeting the lower limit of detection as required by the PBNP Offsite Dose Calculation Manual.

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TABLE 3-3 Isotopic Composition of Airborne Releases January 1, 2021 through December31, 2021 Jan Feb Mar Apr May Jun Total Jul Aug Sep Oct Nov Dec Total Annual Nuclide (Ci) (Ci) (Ci) (Ci) (Ci) (Ci) Jan-Jun (Ci) (Ci) (Ci) (Ci) (Ci) (Ci) July-Dec Total H-3 7.17E+OO 5.48E+OO 5.38E+OO 5.66E+OO 3.95E+OO 4.32E+OO 3.20E+01 4.57E+OO 5.30E+OO 7.00E+OO 9.27E+OO 4.34E+OO 6.65E+OO 3.71 E+01 6.91E+01 F-18 7.33E-07 ND ND ND ND ND 7.33E-07 5.95E-05 1.91 E-09 ND ND 1.38E-06 ND 6.09E-05 6.16E-05 Ar-41 6.10E-02 4.69E-02 4.67E-02 4.20E-02 5.09E-02 3.47E-02 2.82E-01 5.49E-02 4.15E-02 4.03E-02 4.19E-02 5.56E-02 7.20E-02 3.06E-01 5.88E-01 Kr-85 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Kr-85m ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Kr-87 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Kr-88 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Xe-131m ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Xe-133 1.09E-02 6.06E-03 7.59E-03 6.74E-03 2.72E-02 2.08E-02 7.93E-02 2.18E-02 1.54E-02 8.53E-03 9.74E-02 3.66E-02 4.16E-02 2.21 E-01 3.01 E-01 Xe-133m ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Xe-135 ND ND ND ND ND ND ND ND ND ND ND 1.31 E-04 1.11 E-04 2.42E-04 2.42E-04 Xe-135m ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Xe-138 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Na-24 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Cr-51 ND ND ND ND ND ND ND ND ND ND 9.60E-06 ND ND 9.60E-06 9.60E-06 Mn-54 ND ND ND ND ND ND ND ND ND ND 3.32E-07 ND ND 3.32E-07 3.32E-07 Fe-59 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Co-57 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Co-58 ND ND ND ND ND ND ND ND ND ND 4.05E-06 ND ND 4.05E-06 4.05E-06 Co-60 ND ND ND ND ND ND ND ND ND ND 3.53E-06 ND ND 3.53E-06 3.53E-06 Zn-65 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Nb-95 ND ND ND ND ND ND ND ND ND ND 1.82E-06 ND ND 1.82E-06 1.82E-06 Zr-95 ND ND ND ND ND ND ND ND ND ND 1.25E-06 ND ND 1.25E-06 1.25E-06 1-131 ND ND ND ND ND ND ND ND ND ND 9.82E-07 ND ND 9.82E-07 9.82E-07 1-132 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND 1-133 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Sb-124 ND ND ND ND ND ND ND ND ND ND 7.40E-08 ND ND 7.40E-08 7.40E-08 Sb-125 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Cs-137 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Fe-55 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Ni-63 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Tc-99 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Sr-89 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Sr-90 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Sn-113 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Sn-117m ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND Br-82 ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND ND: means that the radionuclide was not identified in any samples and all analyses were performed with instrumentation meeting the lower limit of detection as required by the PBNP Offsite Dose Calculation Manual.

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Table 3-4 Comparison of Airborne Effluent Doses (Appendix I and C-14) 2021 Appendix I (Airborne Particulate+ Tritium) Dose (mrem)

Bone Liver T-WB Thyroid Kidney Lung Gl-LLI Skin Adult 1.47E-05 5.47E-03 5.47E-03 5.47E-03 5.47E-03 5.47E-03 5.47E-03 3.80E-09 Teen 1.47E-05 6.02E-03 6.02E-03 6.03E-03 6.02E-03 6.02E-03 6.02E-03 3.80E-09 Child 1.48E-05 8.51 E-03 8.52E-03 8.53E-03 8.51 E-03 8.52E-03 8.52E-03 3.80E-09 Infant 1.48E-05 3.69E-03 3.69E-03 3.72E-03 3.69E-03 3.69E-03 3.69E-03 3.80E-09 Ann.Limit 3.00E+01

% Ann Lim 2.84E-02 2021 Carbon-14 Dose (mrem)

Bone Liver T.Body Thyroid Kidney Lungs Gl-LLI Skin Adult 6.26E-02 1.24E-02 1.24E-02 1.24E-02 1.24E-02 1.24E-02 1.24E-02 O.OOE+OO Teen 9.80E-02 1.95E-02 1.95E-02 1.95E-02 1.95E-02 1.95E-02 1.95E-02 O.OOE+OO Child 2.25E-01 4.49E-02 4.49E-02 4.49E-02 4.49E-02 4.49E-02 4.49E-02 O.OOE+OO Infant 1.15E-01 2.44E-02 2.44E-02 2.44E-02 2.44E-02 2.44E-02 2.44E-02 O.OOE+OO 2021 Total Airborne Non-Noble Gas Dose [Particulate+ H-3 + C-14 (mremH Bone Liver T-WB Thyroid Kidney Lung Gl-LLI Skin Adult 6.26E-02 1.79E-02 1.79E-02 1.79E-02 1.79E-02 1.79E-02 1.79E-02 3.80E-09 Teen 9.80E-02 2.55E-02 2.55E-02 2.55E-02 2.55E-02 2.55E-02 2.55E-02 3.80E-09 Child 2.25E-01 5.34E-02 5.34E-02 5.34E-02 5.34E-02 5.34E-02 5.34E-02 3.80E-09 Infant 1.15E-01 2.81 E-02 2.81E-02 2.81E-02 2.81E-02 2.81E-02 2.81E-02 3.80E-09 Ann.Limit 3.00E+01

% Limit 7.51 E-01 The percent of limit is calculated using the highest total dose, the Child Age Group.

15

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 2021. No Types C or D wastes were 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 2021 Type of Waste Quantity Activity 3

A. Spent resins, filter sludge, evaporator bottoms, etc. 3.5 m 290.000 Ci 3

125.2 ft 3

B. Dry compressible waste, contaminated equipment, etc 133.7 m 0.123 Ci 4720.0 tt3 3

C. Irradiated components, control rods, etc. 0.00 m N/A Ci ft3 3

D. Other 0.0 m N/A Ci 4.2 Solid Waste Disposition There were three solid waste shipments from PBNP during 2021. The dates and destinations are shown in Table 4-2.

Table 4-2 2021 PBNP Radioactive Waste Shipments Date Destination 01/14/21 Erwin, TN 09/20/21 Oak Ridge, TN 10/28/21 Oak Ridge, TN 4.3 Major Nuclide Composition (by Type of Waste)

The major radionuclide content of the 2021 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.

16

Table 4-3 2021 Estimated Solid Waste Major Radionuclide Composition T~pe A T~pe 8 Activity Percent Activity Percent Nuclide (mCi) Abundance Nuclide (mCi) Abundance Total Activity 2.90E+05 100.00% Total Activity 1.23E+02 100.00%

Co-60 1.41E+05 48.72% Co-60 5.42E+01 44.07%

Ni-63 1.01E+05 34.90% Cr-51 2.24E+01 18.18%

Fe-55 2.69E+04 9.30% Fe-55 1.57E+01 12.77%

Co-58 9.83E+03 3.40% Co-58 7.58E+OO 6.16%

Mn-54 4.87E+03 1.68% Nb-95 6.30E+OO 5.12%

Sb-125 2.55E+03 0.88% Ni-63 4.93E+OO 4.01%

Cs-137 1.37E+03 0.47% Zr-95 2.90E+OO 2.36%

Co-57 8.53E+02 0.29% Ag-110m 2.30E+OO 1.87%

Ni-59 7.60E+02 0.26% Sn-117m 1.84E+OO 1.49%

C-14 1.36E+02 0.05% Sb-125 1.20E+OO 0.98%

Pu-241 6.54E+01 0.02% Sb-124 7.92E-01 0.64%

Sr-90 2.68E+01 0.01% Sn-113 7.48E-01 0.61%

Sr-89 1.00E+01 0.00% Mn-54 7.02E-01 0.57%

Ce-144 2.82E+OO 0.00% H-3 3.47E-01 0.28%

Tc-99 2.68E+OO 0.00% Te-123m 2.35E-01 0.19%

H-3 1.69E+OO 0.00% Ce-144 1.95E-01 0.16%

Am-241 6.66E-01 0.00% Co-57 1.87E-01 0.15%

Pu-238 6.17E-01 0.00% Pu-241 1.59E-01 0.13%

Pu-239 3.17E-01 0.00% Nb-94 9.42E-02 0.08%

Cm-243 2.64E-01 0.00% Tc-99 7.24E-02 0.06%

Cm-242 1.43E-01 0.00% Cs-137 6.97E-02 0.06%

Ni-59 4.48E-02 0.04%

Sr-90 6.08E-03 0.00%

Am-241 5.95E-03 0.00%

C-14 4.70E-03 0.00%

Pu-238 1.64E-03 0.00%

Pu-239 1.58E-03 0.00%

Cm-243 9.75E-04 0.00%

Cm-242 6.40E-04 0.00%

17

5.0 NONRADIOACTIVE CHEMICAL RELEASES 5.1 Scheduled Chemical Waste Releases Scheduled chemical waste releases to the circulating water system from January 1, 2021, to June 30, 2021, included 1.42E+04 gallons of neutralized wastewater. The wastewater contained 1.4 lbs. of suspended solids and 50.5 lbs. of dissolved solids.

There were no scheduled chemical releases of neutralized wastewater to the circulating water system from July 1, 2021, to December 31, 2021.

Scheduled chemical waste releases are based on the 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, 2021, to June 30, 2021, included 2.18E+07 gallons of clarified effluent. The wastewater contained 2.32E+03 lbs. of suspended solids.

Miscellaneous chemical waste releases from the wastewater effluent (based on effluent analyses) to the circulating water for July 1, 2021, to December 31, 2021, included 2.14E+07 gallons of clarified effluent. The wastewater contained 2.27E+03 lbs. of suspended solids.

Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from January 1, 2021, to June 30, 2021, included 5.73+05 lbs. of sodium bisulfite solution (2.18E+05 lbs. sodium bisulfite),

5.11 E+05 lbs. of Sodium Hypochlorite Solution (6.38E+04 lbs. sodium hypochlorite), 1.49E+04 lbs. Acti-Brom 1338 (6. 73E+03 lbs. sodium bromide).

2.59E+03 lbs. of biodetergent, and 4.09E+04 lbs. of silt dispersant.

Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from July 1, 2021, to December 31, 2021, included 7.47E+05 lbs. of sodium bisulfite solution (2.84E+05 lbs. sodium bisulfite),

7.61 E+05 lbs. Sodium Hypochlorite Solution (9.51 E+04 lbs. sodium hypochlorite), 2.17E+04 lbs. Acti-Brom 1338 (9.74E+03 lbs. sodium bromide),

2.63E+03 lbs. of biodetergent, and 3.64E+04 lbs. of silt dispersant.

18

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

Table 6-1 Circulating Water System Operation for 2021 UNIT JAN FEB MAR APR MAY JUN Average Volume Cooling 1 348.5 348.5 348.5 418.6 551.5 551.5 Water Discharge [million gal/day]* 2 348.5 348.5 348.5 510.3 552.9 552.9 Average Cooling Water 1 39 39 40 47 47 53 Intake Temperature [°F] 2 39 40 40 46 48 53 Average Cooling Water 1 66 67 72 71 65 71 Discharge Temperature [°F] 2 71 71 72 66 65 71 Average Ambient Lake Temperature [°F] 36 35 39 43 45 50

For days with cooling water discharge flow.

Table 6-1(continued)

Circulating Water System Operation for 2021 UNIT JUL AUG SEP ocr*** NOV DEC Average Volume Cooling* 1 551.5 551.5 551.5 569.9 551.2 443.9 Water Discharge [million gal/day] 2 552.9 552.9 552.9 170.1 518.0 444.9 Average Cooling Water 1 65 61 62 59 46 38 Intake Temperature [°F] 2 65 62 63 63 47 39 Average Cooling Water 1 85 79 82 79 67 65 Discharge Temperature [°F] 2 84 80 80 73 62 63 Average Ambient Lake Temperature [°F] 63 59 60 59 46 38

For days with cooling water discharge flow.

- - U2 outage 10/10/2021-10/31/2021 19

Part B Miscellaneous Reporting Requirements 7.0 ADDITIONAL REPORTING REQUIREMENTS 7 .1 Revisions to the PBNP Effluent and Environmental Programs No revisions were made to the Offsite Dose Calculation Manual (ODCM) in 2021.

The site operated under the guidance of revision 23 of the Point Beach Nuclear Plant ODCM.

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 several interlaboratory comparison studies including those administered by Environmental Resources Associates (ERA) during 2021. The results of these comparisons can be found in Appendix A of the attached final report for 2021, January - December 2021 from ATI Environmental Inc.

7.3 Special Circumstances No special circumstances to report regarding operation of the explosive gas monitor for the waste gas holdup system was needed during 2021.

20

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 (grasses and weeds), 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, 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. Because of their migratory behavior, fish are wide area integrators. Grab samples of lake water provide a snapshot of radionuclide concentrations at the time the sample is taken; whereas analysis of fish 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.

21

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 12-1 of the ODCM 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 priori concentration 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, if the 95%

confidence interval for a positive does not include zero, the radionuclide is 22

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 12.2.2.e of the ODCM). 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 collect certain environmental samples (Table 9-6) for the State from sites that are near PBNP sampling sites, or are co-located.

9.5 Program Modifications No procedural program modifications were made to the ODCM or REMP in 2021.

In November 2021, the air instrument weather houses were upgraded to incorporate goose neck sample heads as a recommended best practice.

23

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, -16B, -17, -18, 20, -22, -23, -24,

-25, -26B, -27, -28

-29, -30, 31, -32, -38,

-39,-41, -42,-43, -44

-TC Vegetation E-01, -02, -03, -04, -06, Gross Beta 2x/yr as available

-20, Gamma Isotopic Analysis Fish E-13 Gross Beta Quarterly 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 Gross Beta, Sr-89/90, H-3 Monthly I 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 1x/yr

-06, -20 Gamma Isotopic Analysis Shoreline Sediment E-01, -05, -06 Gross Beta 1x/yr Gamma Isotopic Analysis ISFSI Ambient North, East, South, Radiation Exposure West Fence Sections TLD Quarterly 24

Table 9-2 PBNP REMP Samp rmg Loca fions Location Code Location Description E-01 Primary Meteoroloqical Tower South of the Plant E-02 Site Boundary Control Center - East Side of Building E-03 Tapawinqo 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 Telephone E-06 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. Band Zander Road E-09 Nature Conservancy E-10 PBNP Site Well E-11 Dairy Farm about 3. 75 Miles West of Site E-12 Discharge Flume/Pier E-13 Pumphouse E-14 South Boundary, about 0.2 miles East of Site Boundary Control Center E-15 Southwest Corner of Site E-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 Holy Family Convent Property 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 Saxonburq Road E-25 South Side of County Rt. BB, about 0.5 miles West of Norman Road E-26B 804 Tapawinqo 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 Meteoroloqical Tower.

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

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

E-32 On a conduiUpole 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 conduiUpole is about 6 feet hiqh).

E-38 Tree located at the West end of the area previously containinq 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 utility pole south of Elmwood)

E-44 Utility Pole N Side of Tapawingo Rd near house at 5011 E-TC Transportation Control; Reserved for TLDs 25

SANDY BAY AO, FIGURE 2-la KEY

TLD

() TLD A AIR

MILK

.... A OTHER POINT BEACH NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SITES 0 1 MILE J 'j KILOMETER CGS FILE 10749 MAY 2005 Figure 9-1 PBNP REMP Sampling Sites 26

SITE MAP FICiURE 2*1<l POINT BEACH NUCLEAR PLANT r* .. - ..... -. ............................. - .... - ... - .... - .............. _ ... _.. .. . .

.i

.I

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--- SITE 600NOARV 0 800 1600 1

'-___,,_.._,-r-1___.,,---., FEET 400 1200 2000 c:i a:

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- -**-**-**-**-**-**-**-**-** N.JCLEAR RO *

TLD () TLD &. AIR ,&,. OTHE:R Figure 9-2 Map of REMP Sampling Sites Located Around PBNP 27

LME MICHIGAN TAP.I.WI ll<<l RO.

,....._.,........-111TERllH1EMr SlRUll

' .\

I

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EN~ I~U~llEtHllL "81 ITOR ING STAT 11145

TLO ..&. OTUER Figure 9-3 Enhanced Map Showing REMP Sampling Sites Closest to PBNP 28

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 E-44 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 Fish (edible portions) 1000 grams Soil 500-1000 grams Shoreline Sediment 500-1000 grams 29

Table 9-5 Deviations from Scheduled Sampling and Frequency During 2021 Scheduled Sample Reason for not conducting RBVIP Location Collection Plans for Preventing Recurrence Type as required Date Unable to collect water; lake LW E-01 2/9/2021 Seasonal variability frozen Unable to collect water; lake LW E-05 2/9/2021 Seasonal variability frozen Unable to collect water; lake LW E-06 2/9/2021 Seasonal variability frozen Sampler failed; no volume Monitor equipment and replace as AP/Al E-03 4/29/2021 recorded. required.

Monitor equipment and replace as AP/Al E-02 8/12/2021 Power loss at the station.

required.

Monitor equipment and replace as AP/Al E-02 8/31/2021 Power loss at the station.

required.

Unable to collect water due to LW E-06 12f7/2021 Seasonal variability unsafe conditions.

Table 9-6 Sample Collections for State of Wisconsin Sample Type Location Frequency Lake Water E-01 Monthly Fish E-13 Quarterly, As Available Precipitation E-04 Twice a month, E-08 As Available Milk E-11 Monthly E-21 Well Water E-10 Twice per year 30

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 Section 10 (Table 10-1) with the summary of the REMP results. All environmental LLDs listed in Table 12-1 of the ODCM (also in Table 10-1) were achieved during 2021.

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, Tl-208, Ac-228, Be-7, and K-40.

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

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

9.7.4 Air Samples Particulate air filters are allowed to decay at least 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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-134 and Cs-137. Charcoal cartridges for radioiodine are counted as soon as possible so the 1-131 will undergo only minimal decay prior to analyses. The weekly charcoal cartridges are screened for 1-131 by 31

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 2021.

9.7.6 Environmental Radiation Exposure The 2021 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 (UF) 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.

32

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 40CFR 190 compliance demonstration.

33

10.0 RES UL TS 10.1 Summary of 2021 REMP Results Radiological environmental monitoring conducted at PBNP from January 1, 2021, through December 31, 2021, consisted of analysis of air filters, milk, lake water, well water, soil, fish, shoreline sediments, 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 N: Number of samples analyzed LLD: a priori lower limit of detection Average: Average value+/- the standard deviation of N samples High: Highest measured value +/- it's associated 2 sigma counting error Units: Units of measurement For certain analyses, an LLD, which is lower than that required by REMP, is used because the lower value derives from the counting time required to obtain the LLDs for radionuclides that are more difficult to detect. For these analyses, both LLDs are listed with the technical specification required REMP LLD given in parentheses. The results are discussed in the narrative portion of this report (Section 11). Blank values have not been subtracted from the results presented in Table 10-1. A listing of all the individual results obtained from the contracted analytical laboratory and the laboratory's radioanalytical quality assurance results and lnterlaboratory 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 2o counting error is greater than zero (x-2o >O). A "ND" entry in Table 10-1 means that for this radionuclide the criterion was not satisfied for any of the measurements. If one analysis fulfilled the criterion, then all of the reported results, both positive and negative, were used in calculating the average shown in Table 10-1.

The method of determining averages based on "as measured" results follows the recommendations made in NUREG-0475 (1978), "Radiological Environmental 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 N 13.30-1996, "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."

34

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-103, 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 10-3 contains the ISFSI fence TLD results.

35

Table 10-1 S ummarv of R a d"10 Ioa1ca

. IE nv1ronmen t a IM om"torma

. Resu Its f or 2021 Average:!: 1 ~m.

Sample Description N LLD (a) Deviation (b) High +/- 2 sigma Units TLD Environmental Radiation 128 1 mrem 1.21 +/- 0.22 1.72 +/- 0.15 mR/7davs Control (E-20) 4 1 mrem 1.25 +/- 0.19 1.42 +/- 0.10 mR/7days Air Gross Beta 257 0.01 0.025 +/- 0.009 0.055 +/- 0.005 pCi/m3 Control (E-20) Gross beta 52 0.01 0.027 +/- 0.009 0.046 +/- 0.004 pCi/m3 1-131 257 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) ND - pCi/m3 Control (E-20) Cs-137 4 0.01 (0.06) ND - pCi/m3 Other y emitters (Co-60) 20 0.1 ND - pCi/m3 Control (E-20) Other (Co-60) 4 0.1 ND - pCi/m3 Natural Be-7 20 - 0.082 +/- 0.012 0.107 +/- 0.018 pCi/m3 Control (E-20) Natural Be-7 4 - 0.087 +/- 0.015 0.108 +/- 0.015 pCi/m3 Milk Sr-89 36 5 ND - pCi/L Sr-90 36 1 0.4 +/- 0.2 0.9 +/- 0.3 pCi/L 1-131 36 0.5 ND - pCi/L Cs-134 36 5 (15) ND - pCi/L Cs-137 36 5 (18) 0.0 +/- 1.1 2.3 +/- 2.2 pCi/L Ba-La-140 36 5 (15) ND - pCi/L Other qamma emitters(Co-60) 36 15 ND - pCi/L Natural K-40 36 - 1377 +/- 95 1563 +/- 119 pCi/L Well Gross beta 4 4 0.9 +/- 0.3 1.4 +/- 1.1 pCi/L Water 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) ND - pCi/L Fe-59 4 30 ND - pCi/L Co-58 4 10(15) ND - pCi/L Co-60 4 10(15) 0.9 +/- 0.9 2.2 +/- 1.9 pCi/L Zn-65 4 30 ND - 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 NS = No Sample obtained during the year 36

Table 10-1 (continued) s ummary of Ra d"10 Iog1ca . I E nv1ronmen

. ta I M om"tormg R esu Its f or 2021 Average +/- 1 Std.

Sample Description N LLD (a) Deviation (b) High +/- 2 sigma Units Lake Water Gross beta 32 4 1.2 +/- 0.6 3.6 +/- 0.7 pCi/L 1-131 32 0.5 (2) ND - pCi/L Mn-54 32 10 (15) 0.2 +/- 0.9 2.0 +/- 1.6 pCi/L Fe-59 32 30 -0.5 +/- 1.8 3.3 +/- 3.0 pCi/L Co-58 32 10(15) 0.2 +/- 0.9 2.4 +/- 1.6 pCi/L Co-60 32 10(15) 0.2 +/- 0.8 2.2 +/- 2.0 pCi/L Zn-65 32 30 0 +/- 2.3 4.8 +/- 4.6 pCi/L Zr-Nb-95 32 15 ND - pCi/L Cs-134 32 10 (15) -0.5 +/- 1.6 1.9 +/- 1.6 pCi/L Cs-137 32 10 (18) ND - pCi/L Ba-La-140 32 15 -1.5 +/- 3.7 5.1 +/- 1.5 pCi/L Other gamma (Ru-103) 32 30 ND - pCi/L Sr-89 12 5(10) ND - pCi/L Sr-90 12 1 (2) 0.20 +/- 0.13 0.39 +/- 0.28 pCi/L H-3 12 200 (3000) 96 +/- 130 1404 +/- 145.4 pCi/L Fish Mn-54 13 0.13 0.005 +/- 0.007 0.015 +/- 0.010 pCi/g Fe-59 13 0.26 -0.009 +/- 0.018 0.024 +/- 0.022 pCi/g Co-58 13 0.13 0.001 +/- 0.008 0.019 +/- 0.01 pCi/g Co-60 13 0.13 ND - pCi/g Zn-65 13 0.26 ND - pCi/g Cs-134 13 0.13 ND - pCi/g Cs-137 13 0.15 0.009 +/- 0.011 0.030 +/- 0.017 pCi/g Other qamma (Ru-103) 13 0.5 0.000 +/- 0.007 0.012 +/- 0.010 pCi/g Natural K-40 13 - 2.22 +/- 0.69 3.44 +/- 0.44 pCi/g Shoreline Cs-134 3 0.18 ND - pCi/q Sediment Cs-137 3 0.15 0.014 +/- 0.025 0.032 +/- 0.015 pCi/g Natural Be-7 3 - 0.081 +/- 0.042 0.126 +/- 0.058 pCi/g Natural K-40 3 - 6.10+/-2.31 8.379 +/- 0.501 pCi/g Natural Ra-226 3 - 0.40 +/- 0.05 0.461 +/- 0.198 pCi/g Soil Cs-134 6 0.15 ND - pCi/g Cs-137 6 0.15 0.15 +/- 0.15 0.429 +/- 0.04 pCi/g Natural Be-7 6 - 0.213 +/- 0.30 0.795 +/- 0.32 pCi/g Natural K-40 6 - 16.77 +/- 2.14 19.66 +/- 0.97 pCi/g Natural Ra-226 6 - 1.08 +/- 0.42 1.562 +/- 0.30 pCi/g Vegetation 1-131 12 0.06 -0.003 +/- 0.008 0.011 +/- 0.006 pCi/g Cs-134 12 0.06 ND ND pCi/g Cs-137 12 0.08 0.003 +/- 0.009 0.024 +/- 0.011 pCi/g Other gamma emitters (Co-60) 12 0.25 ND ND pCi/g Natural Be-7 12 - 3.14 +/- 3.33 7.85 +/- 0.39 pCi/g Natural K-40 12 - 5.09 +/- 0.90 6.39 +/- 0.52 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 10-2 Average ISFSI Fence TLD Results for 2021 Fence Location Average +/- Standard Deviation Units North 2.33 +/- 0.19 mR/7 days East 3.97 +/- 0.29 mR/7 days South 2.27 +/- 0.91 mR/7 days West 5.89 +/- 2.18 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 4 to 5 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 1.21

+/- 0.22 mR/7-days compared to 1.25 +/- 0.19 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 2020 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. The response difference between the two types of TLDs is evident in Table 11-1. Prior to 2001 all of the annual averages are <1 mrem/7-days. Beginning in 2001, all are >1 mrem/7-days.

Table 11-1 Ave rage Ind'1cator TLD Resu Its f rom 1993 - 2021 Year mR/7-days +/- St. Dev*

1993 0.82 +/- 0.15 1994 0.90 +/- 0.12 1995 0.87 +/- 0.13 1996 0.85 +/- 0.12 1997 0.87 +/- 0.11 1998 0.79 +/- 0.13 1999 0.79 +/- 0.21 2000 0.91 +/- 0.15 2001 1.06 +/- 0.19 2002 1.17 +/- 0.21 2003 1.10 +/- 0.20 2004 1.10 +/- 0.22 2005 1.04 +/- 0.21 2006 1.14 +/- 0.21 2007 1.08 +/- 0.20 2008 1.05 +/- 0.17 2009 1.08 +/- 0.17 2010 1.11 +/- 0.15 2011 1.14 +/- 0.25 2012 1.17 +/- 0.17 2013 1.14 +/- 0.20 2014 1.07 +/- 0.19 2015 1.18 +/- 0.20 2016 1.19 +/- 0.21 2017 1.11 +/- 0.17 2018 1. 11 +/- 0.17 2019 1.10 +/- 0.20 2020 1.16 +/- 0.20 2021 1.21 +/- 0.22

St. Dev = Standard Deviation 39

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

TLD FENCE LOCATION YEAR 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 2.57 3.66 1.15 4.28 2014 2.45 3.35 1.14 4.24 2015 2.31 3.24 1.17 4.36 2016 2.30 3.34 1.33 4.35 2017 2.21 3.84 1.30 4.25 2018 2.24 4.21 1.49 4.32 2019 2.20 4.18 1.57 4.08 2020 2.46 4.19 1. 71 4.2 2021 2.33 3.97 2.27 5.89 There is no significant change in the exposure on the TLD monitoring locations around the ISFSI (Table 11-3). The results at E-03 and E-31 (W of the ISFSI) and E-32 (SW of the ISFSI) are similar to previous years (1.42, 1.26, and 1.45 respectively) and continue to be higher than E-30 (1.05) on the east side and closest to the ISFSI. E-03, about equidistant between the ISFSI and the site boundary location E-31, continues to be slightly higher than the site boundary location but the difference is not statistically different. (See Figs. 9-1 and 9-2 for locations).

Although the mR/7-day results for the three TLD locations nearest the site boundary (E-03 1.42 +/- 0.44; E-31, 1.26 +/- 0.28; E-32, 1.45 +/- 0.28) are higher than at the 40

background site E-20 (1.25 +/- 0.19), 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. In 2018, a TLD monitoring location was added at location E-44 TLD, directly west of E-03 and E-31 , but prior to the nearest resident. The average reading at E-44 (1 .28 +/- 0.45) is similar to the observed readings at E-03, E-31 , and background location E-20 (1.42 , 1.26, and 1.25 respectively).

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 about 14% in the second half of 2001 when the TLD monitoring devices were changed from LiF chips in the first half of 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.

Comparing the ISFSI TLD results to results from surrounding REMP indicator and background TLDs reveals minimal impact of the ISFSI on the surrounding radiation levels (Figure 11 -2). An increase in the 2021 West ISFSI TLD is expected based on the placement of the new casks on the ISFSI pad. 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 in the third quarter of 2001 resulting in a higher measured background values .

Figure 11-1 ISFSI AREA TLD RES UL TS 1995 - 2021 ISFSI AREA TLD RESULTS 1.8 1.6 1.4 >---------~~------,___......,_....,.._ ___ _ ___.

1.2 1---- - - - - ~-----.~~,....,.._,L..'l'-_.__..,,.........-'----1 Ill +E -03

~

'C 1

E-28 t:::: 0. 8 0:: 1---~~~...,._ _ _ .._______ u****-i...r.,. -"1........-~

- '{_,_...,,... E-29

>< E-30 E

0.6 >-------------------------< Jt E-31

E-32 0.4 >-------------------------< + E-20

E-44 0.2 0

1990 1995 2000 2005 2010 2015 2020 2025 YEAR 41

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-44 **** 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 2015 1.36 0.86 0.78 1.07 1.24 1.40 1.20 2016 1.35 0 .85 0 .81 1.06 1.28 1.50 1.25 2017 1.36 0.79 0.80 1.01 1.21 1.44 1.21 2018 1.34 0 .77 0 .80 1.02 1.16 1.46 1.04 1.19 2019 1.27 0 .78 0 .76 1.09 1.17 1.41 0 .99 1.03 2020 1.39 0.84 0.83 1.06 1.18 1.45 1 .07 1.15 2021 1.42 0 .78 0 .8 1.05 1.26 1.45 1 .28 1.25

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.

- - - E-44 Added in 2018 Figure 11-2 Comparison of ISFSI Fence TLDs to Selected REMP TLDs Comparison of Fence and REMP TLDS - North

- East 8.00 - south ell 7.00 - - west

~ 6.00 t:.cc: 5.00 - E-03

......._ E-28 E 4.00

~i~~=~~~~;;~

- E-29

~ 2.00 - E-30 r3.00

<t 1.00 - E-31 0 .00 -+-~~~~~~~~~~~~~~~~~~~~~~~

- E-32 1995 2000 2005 2010 2015 2020

- E-44 YEAR

- E-20 42

11.2 Milk Naturally occurring K-40 (1377 +/- 95 pCi/L) continues to be the most prevalent radionuclide measured in milk at concentrations roughly 1300 times higher than the only potential plant related radionuclide, Sr-90 (0.4 +/- 0.2 pCi/L), detected in milk.

The annual average Sr-90 concentrations in milk continue to be similar to previous years. No positive results for Co-60, 1-131, Cs-134, Ba-La-140, or Sr-89 were obtained in 2021.

One low positive Cs-137 result was obtained in September 2021 and was below the MDC limit and therefore may be false positive. In the last four years, Cs-137 was discharged from PBNP only in March 2016 and October 2017.

The 2021 average Sr-90 concentrations have not changed much over the last few years (Figure 11-3). Over the past twenty years, the average has decreased from 1.2 +/- 0.5 pCi/L in 1997 to 0.4 +/- 0.2 pCi/L in 2021. The graph of the annual averages displays a logarithmic decrease over time (Figure 11-3).

The annual averages are from the monthly Sr-90 measurements from three different dairies (Figure 9-1 ). The only dairy that has been in the monitoring program over the entire 1997 - 2021 timespan under consideration is located at site E-21. It is located south of the plant. The other two, E-40 and E-11, 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.

Point Beach discharged no airborne Sr-90 in 2021. Since 1997, PBNP has discharged airborne Sr-90 only in 3 years: 1999, 2.4E-08 Ci; 2004, 3.2E-08 Ci; and 2011, 1.6 E-08 Ci. It is interesting to note that nine of highest Sr-90 results occur at E-11 located about 4.4 miles west of PBNP (Fig. 9-1 ). If the observed Sr-90 activity were from Point Beach the highest Sr-90 concentrations would occur at E-21, the dairy south of the site boundary in the highest X/Q and D/Q meteorological sector.

This dairy grows feed corn on site and in a field across the road from the site boundary in the highest D/Q sectors. Feed crops are the dominant source of food for dairy cattle. No cattle have been seen grazing neat the site boundary for many years.

The major Sr-90 input to the environment is from fallout from atmospheric weapons testing during the early 1960s with minor inputs during the 50's, 70's and later contributions from the Chernobyl accident in the late 1980s and from Fukushima in 2011. The Sr-90 in milk persists due to its 28.6 year half-life and to cycling in the biosphere. With little or no atmospheric input to the environment, the mode of entry into cattle feed must be root uptake by forage crops and transfer into the milk. Over the time period of this graph ( 1997 - 2021), 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 2021 show no radiological effects of the plant operation.

43

Figure 11-3 Sr-90 Concentration in Milk (1997 - 2021)

Sr-90 in MILK

r

~

u

-c..

1 * ************

0 en V)

0.1 ....____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

1995 2000 2005 2010 2015 2020 2025 VEAR 11 .3 Air The average annual gross beta concentrations (plus/minus the 2a uncertainty) in weekly airborne particulates at the indicator and control locations were 0.025 +/- 0.018 pCi/m 3 and 0.027 +/- 0.018 pCi/m 3 , respectively, and are similar to levels observed from 1993 through 2021 (Figure 11-4) .

The 2021 weekly gross beta concentrations reveal higher winter values and lower summer values (Figure 11-5). This is a repeat of the patterns seen in 2006 - 2020.

The slight September-October peak is similar to what was observed in 2015 (Figure 11 -6) . The August-October peak is observed throughout the US and believed to result from weather patterns impacting with naturally occu rring airborne radionuclides . This would explain why the control and indicators are moving in concert. Therefore, a plant effect can be ruled out.

Fi ure 11-4 Annual Avera e Air Gross 1993 - 2021 Gross 13 Concentration in Air 0.03 - , - - - - - - - - - - - - - - - - - - - -

'f 0.025 l---:::--:---""J~~~£1~~,.=-~1tt.~w.,_--

~

e 0.02 1-~~~~~~__I_~[..!:~!_~

u

..!:!:: 0.015 - + - - - - - - - - - - - - - - - - - - - -

co.

Ill 0.01 -+--------------------

111

~ 0.005 - + - - - - - - - - - - - - - - - - - - --

1990 1995 2000 2005 2010 2015 2020 2025 VEAR 44

Fi ure 11-5 2021 Airborne Gross Beta 2021 Airborne Gross Beta (pCi/mA3) vs. Time 0.060 M

E 0.050

E-02

E-01

~

0 .040 uQ, C!2.

(/)

0.030 x

E-03 XE-04 0

(!)

0.020

t: E-08 0.010

E-20 0.000 1/1/21 2/20/21 4/11/21 5/31/21 7/20/21 9/8/21 10128121 12/17121 DATE Figure 11-6 2015 Airborne Gross Beta 2015 Airborne Gross Beta (pCl/m"3) vs. Time 0.070 ~------------------,

0.060 + - - - - - - - - - - - - - - - - - - !

E-02 r o.o5o + - - - - - -*.*- - - - - -

~

u 0.040 +---~~.,...--------.la.=---tt----1

E-01

a. 0 .030 +-----ii!llJ-l'!U!l.------~~iif'--- E*03 0.020 + - - - - -......- - -

0.010 + - - - - - - --"---' XE*04 0.000 + - - - - - . - - - - - - . - - - - - , - - - . . - - - i

<< E-06 9/18/14 12127/14 4/6/15 7/15/15 10/23/15 1/31/16 DATE No 1-131 was detected during 2021 . 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 0.021 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 45

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 0.004 pCi/m 3 .

At each sampling location, the particulate filters are composited quarterly and analyzed for Cs-134, Cs-137 and any other (Co-60) detectable gamma emitters. As summarized in Table 10-1, none of those nuclides were present in the 2021 samples.

By contrast, naturally occurring Beryllium-? was found in all of the quarterly composites at concentrations ranging from 0.063 to 0.108 pCi/m 3* Be-7 (T 112 = 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 2021 air gamma data from quarterly composites do not indicate a measurable environmental impact from the operation of PBNP.

11 .4 Lake Water For the RE MP-specified gamma emitting radionuclides listed in Table 10-1, the reported concentrations continue to occur as small, negative and positive values scattered around zero, indicating no radiological impact from the operation of PBNP. Only 15 of the results were positive, of which, five are from north of the plant, sites E-33 and E-05 (see Figure 9-1 ).

None of the fifteen slightly positive results were greater than the minimum detectable concentration (MDC). The few indications of positive concentration were found for Mn-54, Fe-59, Co-58, Co-60, Zn-65, Cs-134, and Ba/La-140. Zn-65, Cs-134, and Ba-La-140 were not detected in the PBNP liquid effluent in 2021, concluding that those results were false positives.

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.

Fe-59 was observed in October 2021 in the lake water, but was only quantified as being released from PBNP effluents in November 2021. Mn-54 was identified in the November 2021 lake water sample which was obtained four days after Mn-54 was quantified as being released from Point Beach. Co-58 and Co-60 were observed sporadically in the lake water samples and were released throughout the year in 2021. As was stated above, all isotope values noted were less than the MDC.

Aliquots of the monthly samples are composited quarterly and analyzed for Sr-89/90 and for tritium. Small amounts of Sr-90 were detected in five of the twelve quarterly composites, one north and four south of the plant. All the results were below their statistically calculated MDCs. No Sr-90 was discharged in 2021 or in 2012 - 2015 and 2017-2019. A small amount was discharged in March of 2016. Sr-90 has a 28.6 year half-life and, like Cs-137, is a remnant of atmospheric weapons testing in the '50s and '60s. Therefore, positive Sr-90 concentrations could be indicative of 46

fallout being recycled in Lake Michigan. However, because the concentrations are below their MDCs, they most likely are false positives and there for unlikely to be the result of past PBNP discharges.

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 tritium 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 600 - 1000 Ci of tritium per year.

Twelve quarterly lake water composites were generated from the monthly samples.

Out of the twelve quarterly composites, four had positive tritium indications, and of those four only one was greater than the MDC. The one occurrence was at E-01 the onsite meteorological tower in the 4th quarter of 2021 and had a concentration of 484 +/- 101 pCi/L. The 4th quarter sample from E-01 was analyzed by month and it was shown that the October 2021 sample had a tritium result of 1404.0 +/- 145.4, while November was not detectable and December was 102.9 +/- 93.3 pCi/L.

Point Beach completed a batch liquid discharge approximately 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to obtaining the lake water sample at E-01 in October. The concentration of the Point Beach discharge was 3.65E+04 pCi/L. There is potential that due to the lake current that the Point Beach discharge had an impact on the observed elevated tritium concentration in October 2021, and subsequently the 4th quarter.

In conclusion, the observed tritium concentrations were well below the limit set forth by the EPA for drinking water standards (20,000 pCi/L). As well, based on the results of the gamma scans of Lake Michigan water, there is no measurable impact on the lake from PBNP discharges.

11.5 Fish Thirteen (13) fish were analyzed in 2021 with nine exhibiting detectable amounts of plant related activity. Of these, five were positive for Cs-137 with two Cs-137 results >MDC. The positive Cs-137 concentrations ranged from 0.012 +/- 0.010 to 0.030 +/- 0.017 pCi/g. Cs-137 was released in low levels during 4 months in the first half of 2021. It is likely that the Cs-137 observed is the recycling of Cs-137 that entered Lake Michigan as fallout from atmospheric weapons testing in the '50s and

'60s with lesser amounts from events at Chernobyl and Fukushima.

Positive results below their MDCs were found also for Mn-54, Fe-59, Co-58, and Ru-103.

The highest radionuclide concentration in fish is naturally occurring K-40 with an average concentration of 2.22 +/- 0.69 pCi/g.

Based on these results, it is concluded that there is little impact of PBNP discharges on Lake Michigan fish.

47

11.6 Well Water All tritium results were not detectable for the 2021 well samples. One nuclide, Co-60, was detected in the 3rd quarter 2021 sample. The result was 2.2 +/- 1.9 pCi/L and was less than the MDC of 2.5. There is no pathway for liquid effluents to have interaction with the aquifer that supplies the drinking well. The result was determined to be a false positive, based on no available pathway and no other nuclides being identified in that sample or any others throughout 2021. Therefore, there is no evidence of PBNP effluents getting into the aquifer supplying drinking water to PBNP.

11.7 Soil Cs-137 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-137 concentrations.

In 2021, Cs-137 was detected in five of the six soil samples obtained in September.

The concentrations ranged from not detectable to 0.429 +/- 0.04 and all were >MDC.

The highest value for Cs-137 was found at E-06. No airborne release of Cs-137 occurred in 2021, with the most recent release of airborne Cs-137 occurring approximately three years prior in October 2017 for a total of 0.237 µCi at a concentration of 1.96E-08 pCi/cc.

The values of Cs-137 observed are consistent with years past, therefore it seems unlikely that the observed soil Cs-137 is attributable to PBNP effluent. The most likely source is recycling of fallout from atmospheric weapons testing in the 50s and 60 as well as the Chernobyl and Fukushima events and subsequently being bound to the soil.

By comparison to naturally occurring radionuclides, Cs-137 continues to be present in soil samples at well below the levels of naturally occurring Be-7, K-40, and Ra-226 (see Table 10-1 ).

11.8 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-137. Two of the three samples obtained had Cs-137 concentrations statistically different from zero with both results being >MDC.

Shoreline sediment Cs-137 concentrations continue to be about one-tenth of that found in soils (Table 10-1 ). This is expected because Cs-137 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-137. 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-137 concentrations in beach samples. In contrast 48

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-137 that is attached to particle surfaces. Therefore, it is not surprising that Cs-137 is present at concentrations 1% or less of the naturally occurring concentrations of K-40.

The most likely source of the observed Cs-137 is the cycling of fallout from atmospheric weapons tests and events such as Chernobyl and Fukushiima in the Lake Michigan environment and not current PBNP discharges. As with soil, the naturally occurring radionuclides such as K-40, and Ra-226 are found in the shoreline sediment samples. Therefore, the shoreline sediment data indicate no radiological effects from current plant operation.

11.9 Vegetation The REMP collects general vegetation, non-cultivated plants which would be consumed by grazing cattle.

The naturally occurring radionuclides Be-7 and K-40 were found in all of the general vegetation samples (Table 10-1). 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 in the vegetation samples had an average of 3.14 +/- 3.33 pCi/g. In general vegetation Be-7 concentrations were higher in the fall than in the spring and ranged from 0.25 +/-

0.14 to 7.85 +/- 0.39 pCi/g. The average Be-7 concentrations in the vegetation increased from May (0.39 +/- 0.11 pCi/g) to September (5.89 +/- 2.50). 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 vegetation K-40 concentrations from root uptake are more uniform with a range of 3.52 +/- 0.40 to 6.39 +/- 0.52.

Cs-137 can be present in vegetation via both pathways. Fresh Cs-137 fallout is associated, like Be-7, with deposition on the plant surface. Old fallout from the '50s and '60s is now being incorporated into growing plants in the same manner as potassium because it is in the same chemical family as potassium. This fallout Cs-137 has been found in firewood ash at many locations in the United States that are far from any nuclear plants (S. Farber, "Cesium-137 in Wood Ash, Results of a Nationwide Survey," 5th Ann. Nat. Biofuels Conf., 10/21/1992).

In 2021, three of the twelve vegetation samples had a positive indication for Cs-137 and only one location in September had a result above the MDC. E-06 had a result of 0.024 +/- 0.011 (MDC was 0.020), while the other two positive results were below the MDC and was found at E-02 in September and E-06 in May. Typically, only the vegetation collected at monitoring site E-06, in the Point Beach State Park south of PBNP, has detectable levels of Cs-137, but other slightly positive Cs-137 results have been observed at other locations. These occurrences were attributed to the above described mechanism. The only 2016 airborne Cs-137 discharged by PBNP occurred in March when there was no fresh vegetation. In 2017 the airborne Cs-137 release occurred in October after the vegetation and crops were collected, and in 2018-2021 there was no airborne Cs-137 released in plant effluents. Therefore, 49

the Cs-137 has to be the result of uptake via roots. Therefore, it is unlikely that the Cs-137 results indicate an impact from PBNP releases.

No Cs-134 or Co-60 was detected in the 2021 vegetation samples. One positive 1-131 result was detected in the vegetation sample at E-20, the control location, but was less than the MDC.

Based on the 2021 vegetation sampling results, it is concluded that there is little or no effect from PBNP effluents.

11 .10 Land Use Census In accordance with the requirements of Section 12.2.5 of the ODCM, a visual verification of animals grazing in the vicinity of the PBNP site boundary was completed in 2020. In 2020, changes to the land use surrounding the site due to the installation of solar panels at and around the site boundary were noted. These changes ensure that the use of pasturelands or grazing herds remain conservative, as there is less land near the site boundary for grazing animals and pasture use.

Based on this the existing milk-sampling program continues to be acceptable. The nearest dairy (E-21) lies in the SSE sector and it is one of the Point Beach REMP milk sampling sites. Also, the highest x/Q (1.09E-06) and D/Q (6.23E-09) values occur in these sectors. As demonstrated from the vegetation in the area, there is no measureable plant impact on the environment. 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.

The 2020 LUC revealed that three garden locations within a 5-mile radius of the site in the NNW, WNW, and W sectors required replacement. The garden locations previously identified in 2017 in these sectors were not found in 2020. New garden locations were identified in the 2020 LUC for the NNW, WNW, and W sectors.

None of the changes identified in the 2020 LUC necessitate changes to the current REMP, such as the addition of new sampling locations.

11.11 Long Term TLD Trending To put the 2021 REMP TLD results in perspective, it is instructive to look at long term trends. The following examines the TLD results from 1971 to 2021. The ANSI standard (ANSl/HPS N13.37-2014 "Environmental Dosimetry) states that the data from early vintage dosimetry systems (c. 1970 - 1990) should not be considered comparable to current dosimetry systems in establishing a baseline for environmental TLD results. These problems are evident from the review of our early data as discussed below.

The pre-operational data, 1968 - 1970, are not included. The pre-operational ambient radiation monitoring sites were E-01 (the met tower area) through E-04 (the north boundary). They were monitored using TLDs and ionization chambers. E-04 was used as a background location until E-08 (see Figure 9-1) was added for the operational REMP in 1971. Prior to 1975, a control TLD stored in a lead pig was used for a comparison to those placed in the field. In the pre-operational data, the control TLD could be equal to or higher than the field results and both the field and 50

control TLD results appear erratic compared to the ion-chamber results. Also, the reported TLD results do not have transportation exposures from New Mexico to Wisconsin subtracted. Therefore, only the TLD results beginning in 1971, with the transportation caveat, are used in this analysis of long-term trends.

The trend at E-01 (Figure 11 -7) shows slowly decreasing trend from 1971 to 1979.

This is may be an artifact. The cause is not known. As previously mentioned, no transportation controls were used until the 4th quarter of 1975 so no transport dose corrections were made prior to that quarter. There is a small increase in 1980 when the current contracted REMP lab began. A slowly decreasing exposure rate occurs from 1980 - 1992 except for the 1984 - 1988 time segments. The erratic results from 1984 - 1988 were traced to a faulty connection in the TLD reader.

Figure 11-7 E-01 Results 1971 - 2021 E-01 (mR/7-days) 3 2.5 1.5 0.5 0 __[__ - l_ L_ .J 1/1/ 1971 6/23/1976 12/14/1981 6/6/1987 11/26/1992 5/19/1998 11/9/2003 5/1/ 2009 10/22/2014 4/13/2020 The TLD package from 1980 to 2001 consisted of three LiF chips sealed in a black plastic bag. The magnitude of the error bars indicates the degree of variability of the 1984 - 1988 results from the three chips due to a fault in the TLD reader. The results appear much the same for the E-03 and E-20 results (Figure 11-8). Note that E-20 did not begin until 1976. Again, there is an increase in both the E-20 (the background site) and E-03 (the location nearest the ISFSI) which coincides with the switch from the LiF chips to the Teflon TLD cards . Given that the first twelve casks were loaded December 1995 to September 2000 in which there were no increases in the TLD results, the increase in 2001 indicates that this change is the result of the different response of the new TLDs and not of any effluents or shine from the plant.

51

Figure 11-8 Comparison of E-03 and E-20 Results 1971 - 2021 3.50 3.00 Ill 2.50

~

"tJ 2.00 I

~ 1.50 E i.oo 0.50 0.00 1/1/71 6/23/76 12/14/81 6/6/87 11/26/92 5/19/98 11/9/03 5/1/09 10/22/14 4/13/20 DATE Narrowing the time window for the TLD results from 1992 to the present allows for a comparison among the original four TLD locations since the introduction of the ISFSI (Figure 11-9) without the interference by the faulty TLD reader in the mid-1980s. Sites E-01 and E-02 are about 1 mile south of the ISFSI_. E-03 is 1200 feet west and E-04 is 4300 feet north.

Figure 11 -9 Comparison of E-01, E-02, E-03 and E-04 (1992 -2021) 2.00 1.80 1.60 Ill 1.40

~ 1.20 r!. 1.00

~ 0.80 E 0.60 0.40 0.20 0.00 1/1/92 6/23/ 97 12/14/02 6/ 5/ 08 11/26/ 13 5/19/ 19 DATE

~ E - 01 ~ E-02 ~ E-03 -+- E-04 -+- -+- ~ -+- - -

The comparison shows a definite difference between E-01 and the other three locations. E-01 , although approximately the same distance from the ISFSI as E-02 and further away than either E-03 or E-04, is lower than the other three sites.

Therefore, distance is not the determining factor in the difference among the 52

measured exposures. There are two factors which could cause the observed difference. The first difference is that E-02, E-03, are surrounded by ploughed fields with solar panels, and E-04 is surrounded by plowed fields whereas the area around E-01 is uncultivated . Second, E-01 is within 100 feet of the lake . Therefore, about 50% of the area contributing natural radiation to the location is a combination of sandy soil , beach sand , and lake water. Since E-01 has a combination of different natural radiation contributors (beach sand , lake water, and soil), that could explain the lower results that are observed at E-01.

The impact of the ISFSI on the ambient radiation levels at its nearest site boundary, the west boundary is shown in Figure 11-10. The ISFSI impact on ambient exposure levels was addressed briefly in Section 11 .1 (see Figure 11-2).

Figure 11-10 E-03, E-31, E-44 and Background Site E-20 Results 1992 to 2021 2.50 2.00 VI cu 1.50 "C

I

~ 1.00 E

0.50 0 .00 1/ 1/ 92 6/ 23/ 97 12/ 14/ 02 6/ 5/ 08 11/ 26/ 13 5/ 19/ 19 DATE

-+- E-03 -+- E-20 -+- E-31 -+- E-44 --+- -+-- -+-- __..... -

Figure 11-2 shows that beginning with the use of the Teflon TLD cards in the fourth quarter of 2000, the measured exposure levels at E-03 are 2 - 5 mR/7-days lower than the exposures at the west fence of the ISFSI. Figure 11 -10 shows that although their individual 95% confidence levels overlap indicating no statistical difference, the quarterly exposures at E-03 (about 1200 feet from the ISFSI) are consistently higher than the exposure at E-31 (at the site boundary about 1400 feet west of E-03). Therefore, the lower values at E-31 compared to E-03 appear to be a real difference as the distance from the ISFSI increases at the west boundary.

Because land usage and location are similar at E-03 and E-31, the cause of the previously identified response differences between E-03 and E-01 are not applicable. In 2018, a TLD monitoring location was added at location E-44, directly west of E-03 and E-31 over the site boundary. It can be seen that since 2018, E-44 shows a decreased reading when compared to E-03 and subsequently E-31.

Therefore , the lower results at the site boundary location E-31 and E-44 show that the exposures from the ISFSI are dropping off and approaching the lower readings found at the background site E-20.

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12.0 REMP CONCLUSION Based on the analytical results from the 760 environmental samples (724 individual samples with an additional 24 quarterly air particulate composites and 12 quarterly lake water composites) together with 132 REMP + 16 ISFSI sets of TLDs that comprised the PBNP REMP for 2021, PBNP effluents had no discernable effect on the surrounding environs. The calculated effluent doses are below the 10 CFR 50, Appendix I dose objectives demonstrating 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.

From the long-term analysis of TLD results, there is no evidence of elevated ambient radiation levels from the operation of Point Beach and the ISFSI except for the slightly higher exposures measured at the site boundary (E-31) compared to the background reference site (E-20) [see Figure 11-10].

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I Part D GROUNDWATER MONITORING I 13.0 PROGRAM DESCRIPTION PBNP monitors groundwater for tritium as part of the Groundwater Protection Program (GWPP). The GWPP supports NEI 07-07, the nuclear industry's groundwater protection initiative. The GWPP also fulfills the requirement of 10 CFR 20.1501 (a) to make surveys of areas, including to subsurface in order to comply with Part 20. During 2021 the sampling program consisted of beach drains, intermittent stream and bog locations, drinking water wells, fac;:ade wells, yard electrical manholes, ground water monitoring wells, and the subsurface drainage (SSD) system sump located in the U-2 fac;:ade.

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 tritium 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 tritium, the beach drains are monitored as part of the groundwater monitoring program. In addition to tritium, 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 tritium in the surface groundwater.

The groundwater monitoring program also includes two bogs I ponds on site. One is located about 400 feet SSE of the former retention pond; the other, about 1500 feet N between Warehouses 6 and 7.

In addition to the main plant well, four other drinking water wells 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 tritium. These wells monitor the deeper (200 - 600 feet), drinking water aquifer from 55

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 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 2021.

Due to flooding concerns, man-holes and clean-outs for the SSD were sealed in 2014.

Therefore, only the SSD sump now is used for sampling.

In the 1990s, two wells were sunk in each unit's fac;:ade 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.

Fac;:ade well sampling has been part of the GWPP since 2007. These wells are sampled quarterly.

In November 2019 repairs to the beach drain access and additional wave run up rip-rap was placed around the shoreline to prevent additional high lake level impacts and erosion beach.

These repairs and additions allowed for better access to beach drain sampling in 2020. S-1 and S-3 locations were sampled every month during the year when flow was available, and S-12 was also more accessible throughout the year for sampling. Other beach drain locations were noted as not having flow during the sampling periods.

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

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57 14.0 RESULTS AND DISCUSSION 14.1 Streams and Bogs The results from the surface groundwater monitoring associated with the former retention pond are presented in Table 14-1. For the most part, the creek results are barely above the detection level and less than the MDC. The highest averages are for the East Creek and STP which are in the groundwater flow path from the retention pond area to Lake Michigan. The West Creek is west of the former retention pond, an upstream location with respect to the groundwater flow. The tritium concentration at GW-08, close to the former retention pond, is about one-tenth of the tritium concentrations it had prior to the remediation of the retention pond.

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 +/-

Feb NS +/- NS +/- NS +/- NS +/-

Mar ND +/- 320 +/- 95 ND +/- 255 +/- 92 159 Apr 86 +/- 80 289 +/- 90 118 +/- 81 186 +/- 85 159 May 201 +/- 86 245 +/- 88 100 +/- 80 120 +/- 81 372 +/- 94 100 +/- 80 158 Jun 153 +/- 83 NS +/- 100 +/- 80 NS +/- 158 Jul 123 +/- 82 310 +/- 92 107 +/- 81 208 +/- 87 156 Aug 87 +/- 78 124 +/- 80 ND +/- NS +/- 157 Sep 142 +/- 84 186 +/- 86 138 +/- 84 NS +/- 161 Oct 136 +/- 83 185 +/- 86 136 +/- 83 NS +/- 163 Nov 162 +/- 86 252 +/- 91 118 +/- 84 189 +/- 88 161 Dec ND +/- 122 +/- 94 ND +/- 301 +/- 102 167 Average 116 +/- 56 226 +/- 75 95 +/- 38 210 +/- 62 A blank indicates no sample was scheduled. Streams are sampled monthly; bogs, annually.

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

ND = not statistically different from zero at the 95% confidence level. NS= No sample available The analyses of these surface water samples show low concentrations of tritium, similar to those observed in the beach drains. Small positive tritium concentrations occur in eight of the 10 samples from the confluence of the two creeks (GW-01 ), with only two results being above the MDC. None of the West Creek (GW-03) samples had tritium above its MDC. In contrast, there are more positive results from GW-02 (south end of the East Creek) and GW-17 (located at the north end of the East Creek).

The bog (GW-08) SE of the former retention pond is lower than the bog at GW-07 north of the former retention pond. The GW-08 bog result is down from the 3200 -

3800 pCi/I seen in 1999 before the retention pond was remediated. A gamma analysis of the GW-07 bog sample from May 2021 showed no other detectable 58

isotopes, therefore washout from releases may have attributed to the increased tritium result at GW-07.

14.2 Beach Drains The 2021 results for the beach drains that were sampled are presented in Table 14-

2. 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-1 O are from the turbine building roof. S-12 is a drain from the external SSD which run along the outside northern half of the foundation wall, and S-13 is the south external SSD drain. They are not connected to the internal SSD under the plant which drains to a sump in the U2 fagade.

Table 14-2 2021 Beach Drain H-3 Concentration (pCill)

Month S-1 S-12 S-8 S-9 S-13 S-3 MDC Jan 435 +/- 99 NF +/- NF +/- NF +/- NF +/- NS +/- 166 Feb NS +/- NF +/- NF +/- NF +/- NF +/- NS +/-

Mar NS +/- NF +/- NF +/- NF +/- NF +/- 428 +/- 97 160 Apr 307 +/- 93 NF +/- NF +/- NF +/- NF +/- 311 +/- 93 160 May 221 +/- 86 NF +/- NF +/- NF +/- NF +/- 325 +/- 91 158 Jun 334 +/- 93 NF +/- NF +/- NF +/- NF +/- 331 +/- 93 161 Jul 276 +/- 90 NF +/- NF +/- NF +/- NF +/- 426 +/- 98 156 Aug 246 +/- 89 NF +/- NF +/- NF +/- NF +/- 410 +/- 97 161 Sep 145 +/- 84 246 +/- 89 NF +/- NF +/- NF +/- 310 +/- 93 163 Oct 191 +/- 87 NF +/- NF +/- NF +/- NF +/- 496 +/- 102 159 Nov 153 +/- 84 270 +/- 90 NF +/- NF +/- NF +/- 270 +/- 90 162 Dec 176 +/- 85 NF +/- NF +/- NF +/- NF +/- 275 +/- 91 162 Avg= 248 +/- 91 258 +/- 17 +/- +/- +/- 358 +/- 76 ND= not detected and :o;MDC NS =no sample NF= no sample due to no flow The tritium concentrations at S-1, S-3, and S-12 are consistent with results from previous years. Results are similar to those observed at intermittent streams and in manholes around the site, and like in years prior are attributed to tritium recapture.

Gamma scans were performed on the beach drain samples at the LLD used for lake water. A few indications of small, positive concentration values below their MDCs were found for Mn-54, Cs-137, and Ba-La-140. All the positive results were below their MDCs, except for Cs-137 at S-1 in August 2021 when Cs-137 had a result of 3.4 +/- 1.9 with an MDC of 2.5. This result is likely a false positive since there was no Cs-137 release that could have interacted with this beach drain sample location.

This leaves tritium as the only PBNP radionuclide positively 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 tritium concentrations (Table 14-3). Z-065A and Z-0658 are located on the west side of the pump house. Manholes, Z-066A 59

and Z-067 A through Z-0660 and Z-0670 are between the pump house and the turbine building and 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 EOG building.

Z-068 is located just west of the EOG building and north of Z-066/0670. Each of the two A, B, C, and D vaults is side by side.

Table 14-3 2 021 East Yard Area Manhole Tritium (pCi/I MH 4/29/2021* 10/4/2021 **

Z-065A(M-1) 318 +/- 92 588 +/- 106 Z-0658(M-2) 313 +/- 92 985 +/- 122 Z-066A 193 +/- 85 351 +/- 95 Z-067A 223 +/- 87 280 +/- 91 Z-0668 415 +/- 97 310 +/- 93 Z-0678 403 +/- 96 305 +/- 93 Z-066C 380 +/- 95 317 +/- 93 Z-067C 287 +/- 90 276 +/- 91 Z-0660 280 +/- 90 264 +/- 91 Z-0670 179 +/- 85 262 +/- 91 Z-068 320 +/- 92 293 +/- 92 MDC 158 159

Other sample dates include 05/04/2021

- Other sample dates include 09/29/2021, 09/30/2021, and 10/05/2021 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 fac,;:ade wells were installed to monitor for groundwater conditions which may affect 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 fac.;:ade wells are not located symmetrically in the two units. The Unit 1 fac.;:ade wells are east of the containment in the SE (1Z-361A) and NE (1Z-361B) corners of the fac.;:ade. However, in Unit 2, there is one well in the NW corner (2Z-361A) and the other rotated approximately 180° in the SW corner (2Z-361 B). In each the well cap is level with the floor.

The 2021 fagade well tritium results are shown in Table 14-4. The Unit 1 wells consistently have higher tritium concentrations than the U2 wells with 1Z-361A, in the SE corner of the Unit 1 fagade, on average having the highest tritium concentrations.

In addition to tritium analysis, the fac,;:ade wells were analyzed for gamma isotopic activity. As in lake water samples, small positive values below their calculated, minimum detectable concentrations were found for Mn-54 and Co-58, with one Ba-La-140 analysis was above the MDC of 7.7 pCi/L at 2Z-361A in 3rd quarter 2021 (9.1 +/- 2.8 pCi/L). The Ba-La-140 results from the 22-361 B third quarter fac.;:ade well sample did not achieve the 15 pCi/L Lower Limit of Detection (LLD) for Ba-La-140 60

analysis at the offsite vendor lab. The LLD could not be achieved due to the age and size of the sample, it was obtained in August 2021 but not shipped to the lab for analysis until September 2021. All other isotope LLDs were achieved for this sample. Gamma isotopic analysis for all other isotopes in the samples and hard-to-detect isotopes for 2Z-361 B were less than the minimum detectable concentrations, therefore it can be concluded that there was no groundwater monitoring program impact by not achieving the LLD for Ba-La-140.

Table 14-4 2021 Facade Well Water Tritium (pCi/I)

UNIT 1 UNIT 2 Month 1Z-361A 1Z-361B 2Z-361A 2Z-361B MDC March 219 +/- 87 189 +/- 85 ND +/- ND +/- 161 June 258 +/- 91 176 +/- 87 97 +/- 82 164 +/- 86 160 AUQUSt 175 +/- 88 282 +/- 94 ND +/- 404 +/- 99 163 October 254 +/- 90 167 +/- 85 ND +/- 250 +/- 89 163 ND - Not Detected and <MDC NS - No Sample To relieve hydrostatic pressure on the foundation, Point Beach has an external and an internal subsurface drainage system (SSD) to drain groundwater away from the foundation.

The internal SSD consist of perforated piping which drains groundwater by gravity to a sump located in the Unit 2 fac_;;ade. A comparison of the 2017 through 2021 SSD results is presented in Table 14-5. In 2021, the tritium results were similar as to what was observed in 2019 and 2020. An increase was observed in the last July 2021 because the subsurface drainage sump pump was out of service and the samples obtained were manual grab samples at one time during the month. There were no known system leaks into the system that would cause the increased tritium.

The SSD is discharged via wastewater effluent system. The tritium values then returned to expected concentrations later throughout the rest of 2021.

The SSD sump samples are scanned for gamma emitters. A few slightly positive values were found for Mn-54, Fe-59, Cs-137, and Ba-La-140, and all results were below the MDC.

61

Table 14-5 2017 - 2021 Unit 2 Facade SSD Sump H-3 (pCi/I) 2017 2018 2019 2020 2021 Date pCi/I 20' pCi/I 20' pCi/I 20' pCi/I 20' pCi/I 20' Jan 1058 +/- 122 2634 +/- 168 808 +/- 110 3557 +/- 196 1185 +/- 127 Feb 776 +/- 107 2721 +/- 169 923 +/- 114 3356 +/- 187 1409 +/- 135 Mar 765 +/- 111 2217 +/- 169 924 +/- 116 1915 +/- 150 1605 +/- 148 Apr 1635 +/- 142 1107 +/- 122 1580 +/- 136 1468 +/- 134 1437 +/- 139 May 1503 +/- 134 389 +/- 98 1470 +/- 131 1225 +/- 129 1174 +/- 131 Jun 854 +/- 112 890 +/- 113 1784 +/- 146 1217 +/- 130 806 +/- 114 Jul 907 +/- 115 1225 +/- 127 1681 +/- 144 2136 +/- 157 6496 +/- 257 Aug 1035 +/- 115 1056 +/- 119 1703 +/- 143 1900 +/- 150 2915 +/- 180 Sep 737 +/- 105 803 +/- 110 1412 +/- 132 1621 +/- 141 2714 +/- 175 Oct 8772 +/- 284 1022 +/- 116 8932 +/- 291 1419 +/- 135 2654 +/- 175 Nov 7478 +/- 265 852 +/- 111 10877 +/- 318 1170 +/- 130 2672 +/- 175 Dec 4165 +/- 203 634 +/- 106 5886 +/- 240 1241 +/- 131 2439 +/- 169 Average 2474 +/- 2815 1296 +/- 781 3165 +/- 3444 1852 +/- 814 2292 +/- 1514 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. During 2014, work to mitigate the possibility of external flooding events uncovered the N (S-12) and S (S-13) external SSD outfalls. Both the north and south halves of the external SSD system drain toward the beach. Several samples from SSD S-12 were obtained in 2021 and the results averaged 258 pCi/L, which is lower yet still comparable to the concentrations found in various manholes (Table 14-3) on the east side of the plant during 2021.

14.5 Potable Water and Monitoring Wells Outside of the protected area, ten wells, in addition to the main plant well (Section 11.7), are used for monitoring tritium in groundwater: the four potable water wells, GW-04 (Energy Information Center or EiC), GW-05 (Warehouse 6), GW-18 (Warehouse 7), GW-06 (Site Boundary Control Center), and six tritium groundwater monitoring wells, GW-11 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, clay layer with very low permeability. The potable water wells had no detectable tritium, except for two results at GW-04 in June and December 2021 when the reanalysis showed a not detectable result, and one at GW-18 in October 2021 which was 116 +/- 82 pCi/L and still less than MDC (Table 14-6).

GW-04 is analyzed monthly for gamma, and had three slightly positive results in separate months for Co-58, Co-60, and Zn-65 which were all less than MDC.

62

These are determined to be false positives as there were no other indications of nuclides (gamma or tritium) in the respective months or surrounding months. As well there were no known spills or effluent release pathways that would have interacted with this location.

Starting in late 2021 a gamma analysis was added to GW-18 for monitoring and two slightly positive, but less than MDC results for Co-60 (1.5 +/- 1.4 pCi/L, MDC 1.7 pCi/L) and Ba-La-140 (2.2 +/- 1.4 pCi/L, MDC 7.1 pCi/L) were obtained. There were no known spills or effluent release pathways that would have interacted with this location.

Table 14-6 2021 Potable Well Water Tritium Concentration 'pCi/I) t:IG Warehouse SBCC bvv-Ub, EiC WELL MDC 6Well Well WH7 06, 18 Month GW-04 GW-05 GW-06 GW-18 MDC Jan ND 160 ND ND ND 160 Feb ND 161 Mar ND 159 Apr ND 159 ND ND ND 159 May ND 158 Jun 87 +/- 80 158 Jun* ND 171 Jul ND 156 ND ND ND 156 Aug ND 157 Sep ND 161 Oct ND 163 ND ND 116 +/- 82 163 Nov ND 161 Dec 108 +/- 93 167 Dec* ND 165 ND= not detected

Reanalysis of the same sample The monitoring well results are similar to those obtained in previous years. The two monitoring wells showing higher and consistently detectable tritium (GW-15, GW-

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

however are approaching similar levels as observed at the locations nearest the lake such as GW-11 and GW-14. GW-15 duplicate samples were analyzed for gamma and no additional nuclides were detected.

Table 14-7 2021 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 +/- 128 +/- 82 115 +/- 81 115 +/- 81 160 2 ND+/- ND +/- ND +/- 155 +/- 86 139 +/- 86 246 +/- 94 165 3 136 +/- 83 ND +/- ND +/- 123 +/- 82 143 +/- 83 129 +/- 83 162 4 ND+/- ND +/- 164 +/- 85 166 +/- 85 164 +/- 85 242 +/- 89 163 ND= not stat1st1cally different from zero and <MDC . NS = no sample available

Duplicate samples taken, highest value reported.

63

In summary, the results from monitoring wells GW-15 and GW-16 as well as results from the nearby surface water sample locations (GW-03, the east creek; GW-08, the bog to the SE of the former pond; and GW-17, the surface water on the SE corner of the STP) show that the area around and in the groundwater flow path from the former retention pond remain impacted by the tritium that diffused from the pond into the soil while it was in use.

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 (2011 AMR) show that airborne tritium 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 tritium in precipitation close to the plant. In addition to tritium captured by precipitation, the beach drains also receive the tritium 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 fa9ade wells.

In conclusion, the groundwater tritium 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 tritium 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 results from the two monitoring wells west of the plant (GW-12 and GW-13, Figure 13-1 ). Additionally, because no tritium is detected at a value statistically different than zero in either of the four potable water wells closest to the power block or from the drinking water well at the site boundary, none of the tritium observed in the upper soil layer has penetrated into the drinking water aquifer to impact either on-site or off-site personnel.

64

Part E Errata/Corrections to Previous Annual Monitoring Reports 16.0 Corrections to Previous Reports 16.1 2016 Radioactive Liquid Releases During research to answer a question related to 2016 doses as part of the June 2021 NRC inspection IP 71124.07, Radiological Environmental Monitoring Program, it was identified that the spreadsheet used to total the 2016 Liquid Dose for whole body and organ was not totaling the correct cells from January 2016. Once the spreadsheet was corrected, the total 2016 liquid whole body dose increased to 0.00459 mrem (0.00427 mrem reported) and the organ decreased to 0.00475 mrem (0.00485 mrem reported). The identified error did not cause any Appendix I doses to be exceeded and the 2016 doses still remain ALARA.

The corrected tables from the 2016 Annual Monitoring Report are included below.

SUMMARY

SECTION LIQUID RELEASES Dose Category Calculated Dose Appendix I Dose % Appendix I Whole body dose 0.00459 mrem 6 mrem 0.077 Organ dose 0.00475 mrem 20 mrem 0.024 PART A EFFLUENT MONITORING Table 2-1 Comparison of 2016 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Annual Limit [mrem] Highest Total Calculated % of Design Dose [mrem] Objective 6 (whole body) 0.00459 0.077 %

20 (any organ) 0.00475 0.024 %

65

16.2 2018 Radioactive Solid Waste Shipments A review of past radwaste shipments identified a weight discrepancy in shipment 18-058. Sealand ESUU200848 was characterized using 11,820 lbs for a package weight. The actual package weight was 12,700 lbs. The sealand was characterized with the correct weight and the activity increased from 89.4 mCi to 108 mCi. The error was identified in the Type B category.

The corrected tables from the 2018 Annual Monitoring Report are included below.

Table 4-1 Quantities and Types of Waste Shipped from PBNP in 2018 3

A. Spent resins, filter sludqe, evaporator bottoms, etc. 5.9 m 7.630 Ci 3

207.4 ft 3

B. Dry compressible waste, contaminated equipment, etc 208.2 m 0.409 Ci 3

7354.2 ft C. Irradiated components, control rods, etc. o.oo m3 N/A Ci ft3 3

D. Other 0.0 m N/A Ci 3

0 ft 66

Table 4-3 2018 Estimated Solid Waste Major Radionuclide Composition TYPE A TYPES Activity Percent Activity Percent Nuclide (mCi) Abundance Nuclide (mCi) Abundance Total 7.63E+03 100.00% Total 4.08E+02 100.00%

Co-60 9.43E+02 12.35% Co-60 9.88E+01 24.40%

Co-58 2.85E+03 37.33% Zr-95 7.70E+01 18.71%

Ni-63 2.68E+03 35.10% Fe-55 6.39E+01 15.79%

Sb-125 4.25E+02 5.57% Cr-51 4.46E+01 10.88%

Cs-137 1.17E+02 1.53% Co-58 3.97E+01 9.73%

Fe-55 9.67E+01 1.27% Nb-95 3.30E+01 7.95%

H-3 9.11E+01 1.19% Ni-63 1.78E+01 4.37%

C-14 8.58E+01 1.12% Sb-125 7.43E+OO 1.84%

Co-57 5.98E+01 0.78% Mn-54 4.77E+OO 1.17%

Mn-54 4.92E+01 0.64% Sn-113 4.04E+OO 0.99%

Nb-95 4.36E+01 0.57% Sb-124 3.62E+OO 0.89%

Ni-59 3.80E+01 0.50% Fe-59 2.91 E+OO 0.72%

Sb-124 2.46E+01 0.32% Zn-65 2.30E+OO 0.57%

Ce-144 2.36E+01 0.31% Ni-59 1.79E+OO 0.44%

Zr-95 2.32E+01 0.30% Ag-110m 1.52E+OO 0.37%

Ag-110m 2.07E+01 0.27% Ce-144 1.36E+OO 0.33%

Pu-241 2.03E+01 0.27% Co-57 9.36E-01 0.23%

Cr-51 1.46E+01 0.19% Sn-117m 8.25E-01 0.20%

Zn-65 1.41E+01 0.18% Tc-99 3.64E-01 0.09%

Sn-113 8.28E+OO 0.11% Cs-137 3.36E-01 0.08%

Tc-99 3.98E+OO 0.05% H-3 2.52E-01 0.06%

Sr-90 1.36E+OO 0.02% Te-123m 2.62E-01 0.06%

Am-241 1.80E-01 0.00% Nb-94 1.83E-01 0.05%

Pu-238 7.55E-02 0.00% Pu-241 1.19E-01 0.03%

Pu-239 6.90E-02 0.00% Sr-90 5.63E-02 0.01%

Cm-243 6.72E-02 0.00% C-14 5.32E-02 0.01%

Cm-242 3.95E-02 0.00% Am-241 1.53E-02 0.00%

Pu-239 8.77E-03 0.00%

Pu-238 7.99E-03 0.00%

Cm-243 5.36E-03 0.00%

Cm-242 2.89E-03 0.00%

67

APPENDIX 1 Environmental, Inc. Midwest Laboratory Final Report for the Point Beach Nuclear Plant and Other Analyses Reporting Period: January - December 2021 90 pages follow

~*'All Environmental, Inc.

'+~/-\I Midwest Laboratory 700 Landwehr Road* Northbrook, IL 60062-2310 phone (847) 564-0700 *fax (847) 564-4517 MONTHLY PROGRESS REPORT NextEra Energy RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM THE POINT BEACH NUCLEAR PLANT TWO RIVERS, WISCONSIN PREPARED AND SUBMITTED BY ENVIRONMENTAL INCORPORATED MIDWEST LABORATORY Project Number: 8006 Reporting Period: January-December, 2021 Reviewed and ~- ~

Approved by ------1-__,,,___t?-AI ___:::::_._.__ _ __ Date _:;2..-1--Jq~/1--2_2-_

oanavali, PhD. *. I I Laboratory Manager Distribution: S. Bartels, 1 hardcopy, 1 email

POINT BEACH NUCLEAR PLANT TABLE OF CONTENTS Section Page List of Tables ............................................................................ iii

1.0 INTRODUCTION

...................................................................... iv 2.0 LISTING OF MISSED SAMPLES ............................................. v 3.0 DATA TABLES ........................................................................ vi Appendices A lnterlaboratory Comparison Program Results .......................... A-1 B Data Reporting Conventions .................................................... B-1 C Sampling Program and Locations ............................................ C-1 D Graphs of Data Trends ............................................................. D-1 E Supplemental Analyses ............................................................ E-1 F Special Analyses ...................................................................... F-1 ii

POINT BEACH NUCLEAR PLANT LIST OF TABLES Airborne Particulates and lodine-131 Location E-01, Meteorological Tower.............................................. 1-1 Location E-02, Site Boundary Control Center.................................. 1-2 Location E-03, West 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 Milk........................................................................................................ 3-1 Well Water............................................................................................. 4-1 Lake Water............................................................................................. 5-1 Lake Water, Analyses on Quarterly Composites ............................................... 6-1 Fish .................................................................................................................... 7-1 Shoreline Sediments .......................................................................................... 8-1 Soil ..................................................................................................................... 9-1 Vegetation (Grass) .............................................................................................. 10-1 Gamma Radiation, as Measured byTLDs ........................................................ 11-1 Groundwater Monitoring Program ...................................................................... 12-1 iii

POINT BEACH NUCLEAR PLANT

1.0 INTRODUCTION

The following constitutes the current Monthly Progress Report for the Environmental Radiological Monitoring Program conducted at the Point Beach Nuclear Plant, Two Rivers, Wisconsin.

Results of completed analyses are presented in the attached tables. Missing entries indicate analyses that are not completed. These results will appear in subsequent reports. 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 all gamma isotopic analyses, the spectrum is computer scanned 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, Tl-208, Pb-212, Bi-214, Ra-226 and Ac-228. The results reported under "Other Gammas" may be Co-60, Ru-103 or any other radionuclide which is indicative of other gammas for the sample type. "other Gammas" do not include naturally occuring 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-01 02-09-21 Unable to collect water; lake frozen LW E-05 02-09-21 Unable to collect water; lake frozen LW E-06 02-09-21 Unable to collect water; lake frozen AP/Al E-03 04-29-21 Sampler failed; no volume recorded.

AP/Al E-02 08-12-21 Power loss at the station.

AP/Al E-02 08-31-21 Power loss at the station.

Unable to collect water due to unsafe LW E-06 12-07-21 conditions.

v

POINT BEACH NUCLEAR PLANT 3.0 Data Tables vi

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

Location: E-01, Meteorological Tower 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 01-07-21 304 0.039 +/- 0.004 < 0.010 07-08-21 301 0.016 +/- 0.003 < 0.013 01-13-21 260 0.035 +/- 0.004 < 0.019 07-14-21 260 0.017 +/- 0.004 < 0.008 01-20-21 298 0.029 +/- 0.004 < 0.015 07-22-21 351 0.018 +/- 0.003 < 0.011 01-27-21 302 0.016 +/- 0.003 < 0.007 07-28-21 258 0.028 +/- 0.004 < 0.012 02-03-21 293 0.023 +/- 0.004 < 0.007 08-04-21 306 0.020 +/- 0.003 < 0.010 02-10-21 313 0.033 +/- 0.004 < 0.015 08-12-21 350 0.031 +/- 0.004 < 0.004 02-17-21 303 0.028 +/- 0.004 < 0.013 08-18-21 265 0.024 +/- 0.004 < 0.020 02-25-21 345 0.042 +/- 0.004 < 0.007 08-25-21 305 0.031 +/- 0.004 < 0.010 03-05-21 344 0.026 +/- 0.003 < 0.017 08-31-21 265 0.024 +/- 0.004 < 0.014 03-11-21 259 0.036 +/- 0.004 < 0.015 09-08-21 353 0.024 +/- 0.003 < 0.011 03-17-21 258 0.025 +/- 0.004 < 0.013 09-15-21 310 0.025 +/- 0.003 < 0.009 03-24-21 309 0.023 +/- 0.003 < 0.007 09-22-21 309 0.022 +/- 0.003 < 0.007 04-01-21 346 0.016 +/- 0.003 < 0.011 09-29-21 303 0.027 +/- 0.004 < 0.007 1st Quarter 3rd Quarter Mean+/- s.d. 0.029 +/- 0.008 < 0.012 Mean+/- s.d. 0.024 +/- 0.005 < 0.011 04-08-21 300 0.033 +/- 0.004 < 0.015 10-06-21 305 0.032 +/- 0.004 < 0.005 04-15-21 303 0.009 +/- 0.003 < 0.015 10-13-21 308 0.030 +/- 0.004 < 0.009 04-22-21 301 0.016 +/- 0.003 < 0.009 10-20-21 306 0.030 +/- 0.004 < 0.010 04-29-21 306 0.024 +/- 0.003 < 0.008 10-27-21 314 0.013 +/- 0.003 < 0.010 11-03-21 306 0.017 +/- 0.003 < 0.011 05-06-21 302 0.013 +/- 0.003 < 0.007 05-13-21 305 0.006 +/- 0.003 < 0.007 11-10-21 298 0.040 +/- 0.004 < 0.014 05-20-21 303 0.023 +/- 0.004 < 0.008 11-17-21 305 0.017 +/- 0.003 < 0.009 05-27-21 305 0.021 +/- 0.003 < 0.009 11-24-21 302 0.014 +/- 0.003 < 0.009 06-02-21 261 0.017 +/- 0.003 < 0.018 12-01-21 333 0.023 +/- 0.003 < 0.006 06-10-21 343 0.029 +/- 0.003 < 0.013 12-08-21 309 0.021 +/- 0.003 < 0.013 06-17-21 303 0.017 +/- 0.003 < 0.007 12-15-21 305 0.037 +/- 0.004 < 0.009 06-24-21 297 0.014 +/- 0.003 < 0.008 12-21-21 267 0.037 +/- 0.004 < 0.012 07-01-21 296 0.014 +/- 0.003 < 0.018 12-28-21 303 0.051 +/- 0.005 < 0.007 2nd Quarter 4th Quarter Mean+/- s.d. 0.018 +/- 0.008 < 0.011 Mean+/- s.d. 0.028 +/- 0.011 < 0.010 Cumulative Average 0.025 +/- 0.009 < 0.011 1-1

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

Location: E-02, Site Boundary Control Center 3

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

Date Vol. Date Vol.

Collected {m3) Gross Beta 1-131 Collected 1m3l Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-07-21 303 0.040 +/- 0.004 < 0.010 07-08-21 301 0.019 +/- 0.003 < 0.013 01-13-21 260 0.040 +/- 0.005 < 0.019 07-14-21 262 0.019 +/- 0.004 < 0.008 01-20-21 308 0.029 +/- 0.004 < 0.015 07-22-21 382 0.017 +/- 0.003 < 0.010 01-27-21 308 0.017 +/- 0.003 < 0.006 07-28-21 258 0.031 +/- 0.004 < 0.012 02-03-21 297 0.024 +/- 0.004 < 0.007 08-04-21 309 0.023 +/- 0.003 < 0.010 02-10-21 313 0.029 +/- 0.004 < 0.015 08-12-21 NSb 02-17-21 294 0.034 +/- 0.004 < 0.014 08-18-21 251 0.021 +/- 0.004 < 0.021 02-25-21 345 0.047 +/- 0.004 < 0.007 08-25-21 315 0.031 +/- 0.004 < 0.010 03-05-21 344 0.030 +/- 0.003 < 0.017 08-31-21 NSb 03-11-21 263 0.033 +/- 0.004 < 0.015 09-08-21 349 0.026 +/- 0.003 < 0.012 03-17-21 263 0.021 +/- 0.003 < 0.013 09-15-21 327 0.026 +/- 0.003 < 0.009 03-24-21 304 0.028 +/- 0.004 < 0.007 09-22-21 324 0.024 +/- 0.003 < 0.007 04-01-21 346 0.018 +/- 0.003 < 0.011 09-29-21 294 0.025 +/- 0.004 < 0.008 1st Quarter 3rd Quarter Mean+/- s.d. 0.030 +/- 0.009 < 0.012 Mean+/- s.d. 0.024 +/- 0.005 < 0.011 04-08-21 300 0.035 +/- 0.004 < 0.015 10-06-21 320 0.033 +/- 0.004 < 0.005 04-15-21 301 0.011 +/- 0.003 < 0.015 10-13-21 303 0.031 +/- 0.004 < 0.010 04-22-21 302 0.013 +/- 0.003 < 0.009 10-20-21 323 0.029 +/- 0.004 < 0.010 04-29-21 304 0.023 +/- 0.003 < 0.008 10-27-21 314 0.015 +/- 0.003 < 0.010 11-03-21 324 0.016 +/- 0.003 < 0.010 05-06-21 302 0.016 +/- 0.003 < 0.007 05-13-21 304 0.009 +/- 0.003 < 0.007 11-10-21 301 0.039 +/- 0.004 < 0.014 05-20-21 302 0.027 +/- 0.004 < 0.008 11-17-21 302 0.022 +/- 0.003 < 0.009 05-27-21 302 0.020 +/- 0.003 < 0.009 11-24-21 303 0.024 +/- 0.004 < 0.009 06-02-21 263 0.019 +/- 0.004 < 0.018 12-01-21 323 0.023 +/- 0.004 < 0.007 06-10-21 340 0.031 +/- 0.004 < 0.013 12-08-21 309 0.019 +/- 0.003 < 0.013 06-17-21 297 0.021 +/- 0.004 < 0.008 12-15-21 304 0.041 +/- 0.004 < 0.009 06-24-21 302 0.015 +/- 0.003 < 0.007 12-21-21 271 0.035 +/- 0.004 < 0.011 07-01-21 298 0.021 +/- 0.003 < 0.017 12-28-21 308 0.055 +/- 0.005 < 0.007 2nd Quarter 4th Quarter Mean+/- s.d. 0.020 +/- 0.008 < 0.011 Mean+/- s.d. 0.029 +/- 0.011 < 0.010 Cumulative Average 0.026 +/- 0.009 < 0.011 b No sample; 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-131.

Location: E-03, West Boundary Units: pCi/m 3 Collection: Continuous, weekly exchange.

Date Vol. Date Vol.

Collected {m3) Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Reguired LLD 0.010 0.030 Reguired LLD 0.010 0.030 01-07-21 314 0.040 +/- 0.004 < 0.009 07-08-21 300 0.019 +/- 0.003 < 0.013 01-13-21 256 0.034 +/- 0.004 < 0.019 07-14-21 269 0.016 +/- 0.003 < 0.007 01-20-21 311 0.028 +/- 0.004 < 0.015 07-22-21 294 0.017 +/- 0.003 < 0.014 01-27-21 308 0.016 +/- 0.003 < 0.006 07-28-21 261 0.029 +/- 0.004 < 0.012 02-03-21 296 0.020 +/- 0.003 < 0.007 08-04-21 300 0.028 +/- 0.004 < 0.010 02-10-21 308 0.029 +/- 0.004 < 0.015 08-12-21 345 0.031 +/- 0.004 < 0.004 02-17-21 303 0.023 +/- 0.003 < 0.013 08-18-21 265 0.020 +/- 0.004 < 0.019 02-25-21 345 0.040 +/- 0.004 < 0.007 08-25-21 305 0.031 +/- 0.004 < 0.010 03-05-21 344 0.029 +/- 0.003 < 0.017 08-31-21 265 0.027 +/- 0.004 < 0.014 03-11-21 258 0.034 +/- 0.004 < 0.015 09-08-21 376 0.021 +/- 0.003 < 0.011 03-17-21 262 0.023 +/- 0.003 <0.013 09-15-21 304 0.024 +/- 0.003 < 0.009 03-24-21 304 0.025 +/- 0.003 < 0.007 09-22-21 304 0.020 +/- 0.003 < 0.007 04-01-21 347 0.017 +/- 0.003 < 0.011 09-29-21 293 0.032 +/- 0.004 < 0.008 1st Quarter 3rd Quarter Mean+/- s.d. 0.028 +/- 0.008 < 0.012 Mean+/- s.d. 0.024 +/- 0.006 < 0.011 04-08-21 303 0.034 +/- 0.004 <0.014 10-06-21 282 0.027 +/- 0.004 < 0.006 04-15-21 306 0.009 +/- 0.003 < 0.015 10-13-21 300 0.028 +/- 0.004 < 0.010 04-22-21 302 0.015 +/- 0.003 < 0.009 10-20-21 304 0.030 +/- 0.004 < 0.010 04-29-21 NSb 10-27-21 313 0.014 +/- 0.003 < O.D10 11-03-21 370 0.015 +/- 0.003 < 0.009 05-06-21 305 0.012 +/- 0.003 < 0.007 05-13-21 309 0.008 +/- 0.003 < 0.007 11-10-21 307 0.039 +/- 0.004 < 0.014 05-20-21 301 0.023 +/- 0.004 < 0.008 11-17-21 310 0.017 +/- 0.003 < 0.009 05-27-21 300 0.019 +/- 0.003 < 0.010 11-24-21 296 0.021 +/- 0.004 < 0.009 06-02-21 261 0.020 +/- 0.004 < 0.018 12-01-21 319 0.022 +/- 0.003 < 0.007 06-10-21 339 0.024 +/- 0.003 < 0.013 12-08-21 315 0.019 +/- 0.003 < 0.013 06-17-21 310 0.019 +/- 0.003 < 0.007 12-15-21 263 0.047 +/- 0.005 < 0.011 06-24-21 307 0.013 +/- 0.003 < 0.007 12-21-21 276 0.028 +/- 0.004 < 0.011 07-01-21 299 0.018 +/- 0.003 < 0.017 12-28-21 312 0.050 +/- 0.005 < 0.007 2nd Quarter 4th Quarter Mean+/- s.d. 0.018 +/- 0.007 < 0.011 Mean+/- s.d. 0.028 +/- 0.011 < 0.010 Cumulative Average 0.024 +/- 0.009 < 0.011 0

No sample; see table 2.0 . Listing of Missed Samples.

1-3

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

Location: E-04, North 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 01-07-21 313 0.040 +/- 0.004 < 0.010 07-08-21 303 0.018 +/- 0.003 < 0.013 01-13-21 259 0.032 +/- 0.004 < 0.019 07-14-21 257 0.015 +/- 0.003 < 0.008 01-20-21 304 0.029 +/- 0.004 < 0.015 07-22-21 351 0.014 +/- 0.003 < 0.011 01-27-21 307 0.018 +/- 0.003 < 0.006 07-28-21 258 0.027 +/- 0.004 < 0.012 02-03-21 297 0.023 +/- 0.004 < 0.007 08-04-21 304 0.018 +/- 0.003 < 0.010 02-10-21 313 0.032 +/- 0.004 < 0.015 08-12-21 342 0.032 +/- 0.004 < 0.004 02-17-21 303 0.030 +/- 0.004 < 0.013 08-18-21 269 0.019 +/- 0.003 < 0.019 02-25-21 333 0.041 +/- 0.004 < 0.007 08-25-21 309 0.032 +/- 0.004 < 0.010 03-05-21 344 0.029 +/- 0.003 < 0.017 08-31-21 267 0.031 +/- 0.004 <0.014 03-11-21 266 0.036 +/- 0.004 < 0.014 09-08-21 353 0.023 +/- 0.003 < 0.011 03-17-21 261 0.025 +/- 0.004 < 0.013 09-15-21 309 0.022 +/- 0.003 < 0.009 03-24-21 307 0.025 +/- 0.003 < 0.007 09-22-21 302 0.024 +/- 0.003 < 0.007 04-01-21 345 0.016 +/- 0.003 < 0,011 09-29-21 304 0.032 +/- 0.004 < 0.007 1st Quarter 3rd Quarter Mean+/- s.d. 0.029 +/- 0.008 < 0.012 Mean+/- s.d. 0.024 +/- 0.007 < 0.011 04-08-21 304 0.035 +/- 0.004 <0.014 10-06-21 304 0.032 +/- 0.004 < 0.005 04-15-21 299 0.012 +/- 0.003 < 0.015 10-13-21 304 0.029 +/- 0.004 < 0.010 04-22-21 301 0.014 +/- 0.003 < 0.009 10-20-21 309 0.027 +/- 0.004 < 0.010 04-29-21 301 0.021 +/- 0.003 < 0.008 10-27-21 313 0.016 +/- 0.003 < 0.010 11-03-21 308 0.017 +/- 0.003 < 0.011 05-06-21 301 0.012 +/-0.003 < 0.007 05-13-21 314 0.006 +/- 0.003 < 0.007 11-10-21 305 0.033 +/- 0.004 < 0.014 05-20-21 308 0.025 +/- 0.004 < 0.008 11-17-21 307 0.018 +/- 0.003 < 0.009 05-27-21 313 0.019 +/- 0.003 < 0.009 11-24-21 297 0.022 +/- 0.004 < 0.009 06-02-21 261 0.021 +/- 0.004 < 0.018 12-01-21 318 0.023 +/- 0.004 < 0.007 06-10-21 335 0.026 +/- 0.003 < 0.013 12-08-21 310 0.020 +/- 0.003 < 0,013 06-17-21 297 0.020 +/- 0.004 < 0.008 12-15-21 301 0.046 +/- 0.004 < 0.010 06-24-21 297 0.015 +/- 0.003 < 0.008 12-21-21 271 0.035 +/- 0.004 < 0.011 07-01-21 300 0.018 +/- 0.003 < 0.017 12-28-21 316 0.051 +/- 0.005 < 0.007 2nd Quarter 4th Quarter Mean+/- s.d. 0.019 +/- 0.007 < 0.011 Mean+/- s.d. 0.028 +/- 0,011 < 0.010 Cumulative Average 0.025 +/- 0.009 < 0.011 1-4

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

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

Date Vol. Date Vol.

Collected (m3} Gross Beta 1-131 Collected (m3) Gross Beta 1-131 Required LLD 0.010 0.030 Required LLD 0.010 0.030 01-07-21 316 0.037 +/- 0.004 < 0.009 07-08-21 308 0.021 +/- 0.003 < 0.013 01-13-21 256 0.036 +/- 0.005 < 0.019 07-14-21 260 0.017 +/- 0.004 < 0.008 01-20-21 285 0.028 +/- 0.004 < 0.016 07-22-21 361 0.016 +/- 0.003 < 0.011 01-27-21 316 0.015 +/- 0.003 < 0.006 07-28-21 254 0.030 +/- 0.004 <0.012 02-03-21 297 0.021 +/- 0.003 < 0.007 08-04-21 298 0.025 +/- 0.004 < 0.010 02-10-21 313 0.036 +/- 0.004 < 0.015 08-12-21 352 0.031 +/- 0.004 < 0.004 02-17-21 302 0.027 +/- 0.004 < 0.013 08-18-21 260 0.022 +/- 0.004 < 0.020 02-25-21 339 0.037 +/- 0.004 < 0.007 08-25-21 301 0.032 +/- 0.004 < 0.010 03-05-21 336 0.029 +/- 0.003 < 0.017 08-31-21 263 0.025 +/- 0.004 < 0.014 03-11-21 258 0.030 +/- 0.004 < 0.015 09-08-21 353 0.023 +/- 0.003 < 0.011 03-17-21 257 0.022 +/- 0.004 < O.Q13 09-15-21 302 0.026 +/- 0.004 < 0.009 03-24-21 304 0.023 +/- 0.003 < 0.007 09-22-21 304 0.023 +/- 0.003 < 0.007 04-01-21 347 0.017 +/- 0.003 < 0.011 09-29-21 299 0.026 +/- 0.004 < 0.007 1st Quarter 3rd Quarter Mean+/- s.d. 0.027 +/- 0.008 < 0.012 Mean+/- s.d. 0.024 +/- 0.005 < 0.011 04-08-21 304 0.032 +/- 0.004 < 0.014 10-06-21 303 0.032 +/- 0.004 < 0.005 04-15-21 306 0.010 +/- 0.003 < 0.015 10-13-21 311 0.034 +/- 0.004 < 0.009 04-22-21 308 O.Q13 +/- 0.003 < 0.009 10-20-21 310 0.029 +/- 0.004 <0.010 04-29-21 302 0.023 +/- 0.003 < 0.008 10-27-21 318 0.014 +/- 0.003 < 0.010 11-03-21 312 0.021 +/- 0.003 <0.011 05-06-21 298 0.013 +/- 0.003 < 0.007 05-13-21 304 0.006 +/- 0.003 < 0.007 11-10-21 306 0.040 +/- 0.004 <0.014 05-20-21 297 0.022 +/- 0.004 < 0.009 11-17-21 301 0.020 +/- 0.003 < 0.009 05-27-21 305 0.020 +/- 0.003 < 0.009 11-24-21 298 0.024 +/- 0.004 < 0.009 06-02-21 268 0.020 +/- 0.004 < O.Q18 12-01-21 326 0.022 +/- 0.003 < 0.007 06-10-21 350 0.028 +/- 0.003 < 0.013 12-08-21 314 O.Q18 +/- 0.003 < 0.013 06-17-21 319 0.018 +/- 0.003 < 0.007 12-15-21 305 0.036 +/- 0.004 < 0.009 06-24-21 303 0.015 +/- 0.003 < 0.007 12-21-21 277 0.035 +/- 0.004 < 0.011 07-01-21 296 0.014 +/- 0.003 < 0.017 12-28-21 304 0.045 +/- 0.004 < 0.007 2nd Quarter 4th Quarter Mean+/- s.d. 0.018 +/- 0.007 < 0.011 Mean+/- s.d. 0.028 +/- 0.009 <0.010 Cumulative Average 0.025 +/- 0.008 < 0.011 Indicator Locations Annual Mean+/- s.d. 0.025 +/- 0.009 < 0.011 1-5

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

Location: E-20, Silver Lake 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 01-07-21 309 0.046 +/- 0.004 < 0.010 07-08-21 297 0.020 +/- 0.003 < 0.014 01-13-21 260 0.041 +/- 0.005 < 0.019 07-14-21 260 0.017 +/- 0.004 < 0.008 01-20-21 308 0.029 +/- 0.004 < 0.015 07-22-21 363 O.o18 +/- 0.003 < 0.011 01-27-21 302 0.016 +/- 0.003 < 0.007 07-28-21 257 0.032 +/- 0.004 < 0.012 02-03-21 302 0.028 +/- 0.004 < 0.007 08-04-21 316 0.022 +/- 0.003 < 0.010 02-10-21 313 0.034 +/- 0.004 < 0.015 08-12-21 347 0.032 +/- 0.004 < 0.004 02-17-21 303 0.030 +/- 0.004 < 0.013 08-18-21 264 0.018 +/- 0.003 < 0.020 02-25-21 345 0.042 +/- 0.004 < 0.007 08-25-21 305 0.031 +/- 0.004 < 0.010 03-05-21 344 0.026 +/- 0.003 < 0.017 08-31-21 260 0.029 +/- 0.004 < 0.014 03-11-21 262 0.032 +/- 0.004 <0.015 09-08-21 355 0.030 +/- 0.003 < 0.011 03-17-21 264 0.024 +/- 0.004 < 0.012 09-15-21 309 0.028 +/- 0.004 < 0.009 03-24-21 308 0.025 +/- 0.003 < 0.007 09-22-21 301 0.023 +/- 0.003 < 0.007 04-01-21 343 0.023 +/- 0.003 < 0.011 09-29-21 302 0.032 +/- 0.004 < 0.007 1st Quarter 3rd Quarter Mean+/- s.d. 0.030 +/- 0.009 < 0.012 Mean+/- s.d. 0.025 +/- 0.006 < 0.011 04-08-21 307 0.034 +/- 0.004 <0.014 10-06-21 302 0.029 +/- 0.004 < 0.005 04-15-21 307 0.010 +/- 0.003 < 0.015 10-13-21 307 0.033 +/- 0.004 < 0.009 04-22-21 302 0.016 +/- 0.003 < 0.009 10-20-21 308 0.034 +/- 0.004 <0.010 04-29-21 306 0.023 +/- 0.003 < 0.008 10-27-21 323 0.044 +/- 0.004 < 0.009 11-03-21 310 0.025 +/- 0.004 < 0.011 05-06-21 303 0.016 +/- 0.003 < 0.007 05-13-21 313 0.008 +/- 0.003 < 0.007 11-10-21 306 0.039 +/- 0.004 < 0.014 05-20-21 301 0.027 +/- 0.004 < 0.008 11-18-21 334 0.020 +/- 0.003 < 0.008 05-27-21 305 0.021 +/- 0.003 < 0.009 11-24-21 264 0.027 +/- 0.004 < 0.010 06-02-21 267 0.019 +/- 0.004 < 0.018 12-01-21 328 0.022 +/- 0.003 < 0.007 06-10-21 337 0.026 +/- 0.003 < 0.013 12-08-21 313 0.021 +/- 0.003 < 0.013 06-17-21 301 0.019 +/- 0.003 < 0.007 12-15-21 299 0.041 +/- 0.004 < 0.010 06-24-21 303 0.018 +/- 0.003 < 0.007 12-21-21 261 0.035 +/- 0.004 < 0.012 07-01-21 302 0.017 +/- 0.003 < 0.017 12-28-21 306 0.046 +/- 0.004 < 0.007 2nd Quarter 4th Quarter Mean+/- s.d. 0.020 +/- 0.007 < 0.011 Mean+/- s.d. 0.032 +/- 0.009 < 0.010 Cumulative Average 0.027 +/- 0.009 < 0.011 Control Annual Mean +/- s.d. 0.027 +/- 0.009 < 0.011 1-6

POINT BEACH NUCLEAR PLANT Table 2. Gamma emitters in quarterly composites of air particulate fillers Unils: pCilm 3 (Other) (Other)

Location Lab Code Be-7 Be-7 Cs-134 Cs-134 Cs-137 Cs-137 Co-60 (Co-60) Volume Req. LLD MDC 0.01 MDC 0.01 MDC ( 0.10) MDC ma 1.§1 Quarter E-01 EAP- 1041 0.074 +/- 0.017 0.0001 +/- 0.0005 < 0.0008 -0.0006 +/- 0.0006 < 0.0006 0.0002 +/- 0.0006 < 0.0007 3932 E-02 - 1042 0.082 +/- 0.012 0.0002 +/- 0.0005 < 0.0008 0.0004 +/- 0.0005 < 0.0008 -0.0004 +/- 0.0005 < 0.0004 3947 E-03 - 1043 0.077 +/- 0.014 -0.0002 +/- 0.0004 < 0.0008 -0.0002 +/- 0.0004 < 0.0004 -0.0001 +/- 0.0004 < 0.0003 3955 E-04 - 1044 0.082 +/- 0.015 -0.0004 +/- 0.0005 < 0.0008 0.0002 +/- 0.0004 < 0.0006 -0.0002 +/- 0.0004 < 0.0005 3953 E-08 - 1045 0.070 +/- O.Q15 -0.0005 +/- 0.0006 < 0.0011 0.0004 +/- 0.0005 < 0.0008 0.0001 +/- 0.0005 < 0.0004 3926 E-20

1046 0.076 +/- 0.015 -0.0003 +/- 0.0006 < 0.0010 -0.0002 +/- 0.0006 < 0.0006 0.0003 +/- 0.0007 < 0.0008 3962 2nd Quarter E-01 EAP- 2168 0.085 +/- 0.012 0.0000 +/- 0.0004 < 0.0008 0.0001 +/- 0.0005 < 0.0006 0.0000 +/- 0.0005 < 0.0005 3922 E-02 - 2169 0.087 +/- 0.019 -0.0008 +/- 0.0006 < 0.0009 0.0001 +/- 0.0006 < 0.0010 -0.0003 +/- 0.0006 < 0.0004 3919 E-03

2170 0.089 +/- 0.014 -0.0004 +/- 0.0005 < 0.0010 *0.0001 +/- 0.0005 < 0.0009 -0.0004 +/- 0.0006 < 0.0006 3642 E-04

2171 0.074 +/- 0.021 -0.0004 +/- 0.0006 < 0.0011 -0.0002 +/- 0.0005 < 0.0006 -0.0002 +/- 0.0006 < 0.0007 3931 E-08 - 2172 0.091 +/- 0.014 0.0001 +/- 0.0004 < 0.0009 0.0002 +/- 0.0005 < 0.0008 0.0004 +/- 0.0004 < 0.0006 3958 E-20 - 2173 0.108 +/-0.015 -0.0001 +/- 0.0005 < 0.0009 0.0000 +/- 0.0005 < 0.0007 *0.0001 +/- 0.0003 < 0.0004 3953 3rd Quarter E-01 EAP- 3395 0.107 +/-O.Q18 0.0000 +/- 0.0005 < 0.0010 *0.0002 +/- 0.0005 < 0.0005 -0.0001 +/- 0.0006 < 0.0006 3936 E-02

3396 0.090 +/- 0.019 -0.0011 +/- 0.0007 < 0.0012 *0.0001 +/- 0.0006 < 0.0008 0.0003 +/- 0.0007 < 0.0009 3372 E-03 - 3397 0.101 +/- 0.017 -0.0003 +/- 0.0005 < 0.0010 0.0003 +/- 0.0006 < 0.0010 0.0004 +/- 0.0005 < 0.0005 3880 E-04

3398 0.093 +/- 0.018 -0.0004 +/- 0.0005 < 0.0009 0.0000 +/- 0.0006 < 0.0010 0.0002 +/- 0.0005 < 0.0007 3927 E-08 - 3399 0.091 +/- 0.016 -0.0002 +/- 0.0005 < 0.0009 *0.0002 +/- 0.0005 < 0.0005 -0.0001 +/- 0.0006 < 0.0008 3916 E-20

3400 0.083 +/- 0.017 -0.0006 +/- 0.0005 < 0.0008 0.0004 +/- 0.0006 < 0.0007 0.0004 +/- 0.0007 < 0.0008 3935 41h Quarter E-01 EAP- 4366 0.076 +/- 0.017 -0.0021 +/- 0.0007 < 0.0011 0.0001 +/- 0.0006 < 0.0008 0.0002 +/- 0.0006 < 0.0007 3961 E-02 - 4367 0.072 +/- 0.024 -0.0024 +/- 0.0007 < 0.0013 -0.0003 +/- 0.0008 < 0.0013 -0.0003 +/- 0.0010 < 0.0014 4005 E-03 - 4368 0.063 +/- 0.016 -0.0006 +/- 0.0005 < 0.0009 0.0004 +/- 0.0005 < 0.0008 0.0001 +/- 0.0006 < 0.0006 3965 E-04

4369 0.066 +/- 0.019 0.0002 +/- 0.0006 < 0.0011 0.0000 +/- 0.0006 < 0.0009 -0.0003 +/- 0.0005 < 0.0005 3963 E-08 - 4370 O.Q70 +/- 0.016 *0.0001 +/- 0.0004 < 0.0008 0.0002 +/- 0.0005 < 0.0009 0.0003 +/- 0.0004 < 0.0005 3985 E-20 - 4371 0.080 +/- 0.013 0.0002 +/- 0.0004 < 0.0010 0.0000 +/- 0.0005 < 0.0006 *0.0004 +/- 0.0005 < 0.0004 3960 Annual Mean+/-s.d. 0.083 +/- 0.012 *0.0004 +/- 0.0007 < 0.0009 0.0000 +/- 0.0003 < 0.0008 0.0000 +/- 0.0003 < 0.0006 2-1

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

E-11 Lambert Dairy Farm MDC MDC MDC Required Collection Date 01-13-21 02-10-21 03-10-21 LLD Lab Code EMI- 82 EMI- 351 EMI- 597 Sr-89 -0.7 +/- 0.9 < 0.9 -0.4 +/- 0.7 < 0.8 0.3 +/- 0.9 < 0.9 5.0 Sr-90 0.8 +/- 0.4 < 0.7 0.5 +/- 0.3 < 0.6 0.5 +/- 0.4 < 0.7 1.0 1-131 0.05+/-0.15 < 0.28 -0.02 +/- 0.10 < 0.19 0.14 +/- 0.17 < 0.29 0.5 K-40 1361+/-111 1322 +/- 118 1353 +/- 114 Cs-134 -2.6 +/- 2.0 < 3.6 -0.4 +/- 2.5 < 4.4 -2.1 +/- 2.3 < 4.2 5.0 Cs-137 0.4 +/- 2.3 < 4.2 -0.6 +/- 2.6 < 3.4 -1.6+/-2.7 < 3.9 5.0 Ba-La-140 0.6 +/- 2.0 < 3.7 -2.0 +/- 2.5 < 2.7 0.5 +/- 2.3 < 4.2 5.0 Other (Co-60) 0.7 +/- 2.4 < 3.4 0.9 +/- 2.0 < 2.9 0.1 +/-2.4 < 3.0 15.0 MDC MDC MDC Required Collection Date 04-14-21 05-12-21 06-09-21 LLD Lab Code EMI- 1004 EMI- 1397 EMI- 1705 Sr-89 0.3 +/- 0.5 < 0.5 0.1 +/- 0.7 < 0.8 0.2 +/- 0.7 < 0.7 5.0 Sr-90 0.4 +/- 0.3 < 0.5 0.4 +/- 0.3 < 0.5 0.4 +/- 0.3 < 0.5 1.0 1-131 0.04 +/- 0.19 < 0.37 0.01 +/- 0.18 < 0.37 -0.07 +/- 0.21 < 0.47 0.5 K-40 1360 +/- 104 1306 +/- 95 1316+/-89 Cs-134 -1.4 +/- 1.8 < 3.1 -1.0 +/- 1.6 < 3.0 -1.4 +/- 1.8 < 3.6 5.0 Cs-137 0.3 +/- 2.3 < 4.6 0.0 +/- 1.9 < 3.5 -0.1 +/- 2.0 < 3.3 5.0 Ba-La-140 -1.8 +/- 6.2 < 2.2 -2.1+/-1.7 < 3.0 1.5 +/- 1.6 < 2.7 5.0 Other (Co-60) -0.5 +/- 2.2 < 2.3 1.2 +/- 1.8 < 3.2 0.8 +/- 1.7 < 2.9 15.0 3-1

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

E-11 Lambert Dairy Farm MDC MDC MDC Required Collection Date 07-14-21 08-11-21 09-08-21 LLD Lab Code EMI- 2183 EMI- 2556 EMI- 2883 Sr-89 -0.1 +/- 0.7 < 0.8 0.3 +/- 0.7 < 0.7 0.0 +/- 0.6 < 0.7 5.0 Sr-90 0.4 +/- 0.3 < 0.5 0.5 +/- 0.3 < 0.5 0.5 +/- 0.3 < 0.5 1.0 1-131 0.00 +/- 0.12 < 0.21 0.11 +/- 0.20 < 0.38 0.13 +/- 0.15 < 0.27 0.5 K-40 1224 +/- 94 1137 +/- 93 1563 +/- 119 Cs-134 0.5 +/- 1.8 < 3.0 -0.2 +/- 1.9 < 3.3 0.4 +/- 2.6 < 5.0 5.0 Cs-137 -0.6 +/- 2.0 < 2.7 1.7 +/- 1.9 < 3.6 -1.4 +/- 2.5 < 2.8 5.0 Ba-La-140 -0.2 +/- 1.8 < 1.8 -0.3 +/- 1.7 < 3.0 -5.2 +/- 9.2 < 2.3 5.0 Other (Co-60) -0.4 +/- 2.0 < 3.0 -0.2 +/- 1.7 < 2.7 -1.5+/-2.5 < 2.5 15.0 MDC MDC MDC Required Collection Date 10-13-21 11-10-21 12-08-21 LLD Lab Code EMI- 3320 EMI- 3790 EMI- 4006 Sr-89 0.1 +/- 0.6 < 0.7 0.4 +/- 0.7 < 0.8 -0.2 +/- 0.7 < 0.7 5.0 Sr-90 0.4 +/- 0.3 < 0.5 0.4 +/- 0.3 < 0.6 0.9 +/- 0.3 < 0.5 1.0 1-131 0.03 +/- 0.21 < 0.43 -0.01 +/- 0.15 < 0.27 -0.03 +/- 0.17 < 0.31 0.5 K-40 1229 +/- 95 1413 +/- 106 1524 +/- 123 Cs-134 1.0 +/- 1.6 < 2.9 0.4 +/- 1.9 < 3.4 0.9 +/- 2.3 < 4.7 5.0 Cs-137 0.3 +/- 2.0 < 3.1 -1.8 +/- 2.3 < 3.4 1.4+/-2.6 < 4.4 5.0 Ba-La-140 0.6 +/- 1.4 < 4.9 -1.4 +/- 1.8 < 1.5 -0.9 +/- 2.0 < 2.6 5.0 Other (Co-60) 1.2 +/- 1.9 < 3.4 -1.2 +/- 2.1 < 2.9 0.2 +/- 2.8 < 2.4 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 DaiIY. Farm MDC MDC MDC Required Collection Date 01-13-21 02-10-21 03-10-21 LLD Lab Code EMI- 83 EMI- 352 EMI- 598 Sr-89 0.3 +/- 0.6 < 0.7 0.0 +/- 0.5 < 0.7 0.4 +/- 0.6 < 0.7 5.0 Sr-90 0.4 +/- 0.3 < 0.6 0.1 +/- 0.2 < 0.5 0.4 +/- 0.3 < 0.7 1.0 1-131 -0.08 +/- 0.21 < 0.45 0.02+/-0.11 < 0.19 -0.10 +/- 0.19 < 0.39 0.5 K-40 1373 +/- 111 1473 +/- 108 1326 +/- 109 Cs-134 -1.0+/-2.0 < 3.4 -0.6 +/- 2.1 < 4.2 -1.2 +/- 2.1 < 3.5 5.0 Cs-137 -0.4 +/- 2.2 < 3.3 0.5 +/- 2.5 < 4.6 0.1 +/- 1.9 < 3.2 5.0 Ba-La-140 -0.3 +/- 1.9 < 4.2 0.6 +/- 2.2 < 3.0 0.2 +/- 1.6 < 4.3 5.0 Other (Co-60) -1.6+/-2.4 < 2.9 0.3 +/- 2.4 < 3.7 -0.5 +/- 2.1 < 2.1 15.0 MDC MDC MDC Required Collection Date 04-14-21 05-12-21 06-09-21 LLD Lab Code EMI- 1005 EMI- 1398 EMI- 1706 Sr-89 0.4 +/- 0.5 < 0.6 -0.4 +/- 0.9 < 0.7 0.3 +/- 0.7 < 0.9 5.0 Sr-90 0.2 +/- 0.3 < 0.6 0.5 +/- 0.4 < 0.7 0.3 +/- 0.3 < 0.5 1.0 1-131 0.03 +/- 0.14 < 0.25 -0.06 +/- 0.13 < 0.24 0.04 +/- 0.22 < 0.47 0.5 K-40 1364 +/- 107 1428 +/- 92 1290 +/- 96 Cs-134 -1.6 +/- 1.8 < 3.3 -0.9 +/- 1.5 < 2.9 -4.8 +/- 2.2 < 3.6 5.0 Cs-137 -2.0 +/- 2.5 < 3.3 0.2 +/- 1.7 < 3.7 -2.2 +/- 2.1 < 2.3 5.0 Ba-La-140 -0.9 +/- 1.5 < 1.5 -0.4 +/- 1.4 < 2.8 1.5 +/- 1.7 < 3.3 5.0 other (Co-60) -2.2 +/- 2.0 < 1.6 1.3 +/- 1.6 < 2.1 0.1 +/- 2.3 < 3.5 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 07-14-21 08-11-21 09-08-21 LLD Lab Code EMI- 2184 EMI- 2557 EMI- 2884 Sr-89 -0.1 +/- 0.8 < 0.8 0.2 +/- 0.7 < 0.8 -0.6 +/- 0.7 < 0.7 5.0 Sr-90 0.5 +/- 0.3 < 0.6 0.4 +/- 0.3 < 0.5 0.5 +/- 0.3 < 0.6 1.0 1-131 0.00 +/- 0.15 < 0.29 0.06 +/- 0.22 < 0.47 0.05 +/- 0.20 < 0.40 0.5 K-40 1471 +/- 100 1382 +/- 106 1330 +/- 112 Cs-134 0.9 +/- 1.7 < 2.9 0.6 +/- 1.9 < 3.8 0.9 +/- 2.2 < 3.4 5.0 Cs-137 0.7+/-1.8 < 3.5 -1.7 +/- 2.1 < 3.3 0.9 +/- 2.3 < 4.1 5.0 Ba-La-140 0.2 +/- 1.2 < 1.2 0.7+/-2.1 < 2.7 0.3 +/- 2.2 < 3.7 5.0 Other (Co-60) 0.4 +/- 1.9 < 2.9 -0.2 +/- 2.5 < 1.7 -1.0+/-2.6 < 3.4 15.0 MDC MDC MDC Required Collection Date 10-13-21 11-10-21 12-08-21 LLD Lab Code EMI- 3321 EMI- 3791 EMI- 4007 Sr-89 -0.2 +/- 0.6 < 0.7 -0.2 +/- 0.7 < 0.8 0.0 +/- 0.7 < 0.9 5.0 Sr-90 0.4 +/- 0.3 < 0.5 0.5 +/- 0.3 < 0.6 0.3 +/- 0.3 < 0.6 1.0 1-131 0.08 +/- 0.23 < 0.43 0.03 +/- 0.18 < 0.32 -0.02 +/- 0.16 < 0.29 0.5 K-40 1360 +/- 106 1267 +/- 108 1295 +/- 112 Cs-134 -0.1 +/- 1.7 < 3.2 -1.4 +/- 2.0 < 3.7 -1.7 +/- 1.8 < 3.1 5.0 Cs-137 -0.6 +/- 1.9 < 2.6 0.8 +/- 2.2 < 3.2 -0.2 +/- 2.4 < 3.0 5.0 Ba-La-140 -0.7 +/- 2.0 < 3.2 -0.8 +/- 2.3 < 3.3 -1.3 +/- 2.0 < 2.9 5.0 other (Co-60) 0.0 +/- 2.2 < 3.3 1.0 +/- 2.0 < 4.1 -0.3 +/- 2.2 < 3.5 15.0 3-4

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

E-40 Barta MDC MDC MDC Required Collection Date 01-13-21 02-10-21 03-10-21 LLD Lab Code EMI- 84 EMI- 353 EMI- 599 Sr-89 0.2 +/- 0.5 < 0.6 -0.3 +/- 0.6 < 0.6 0.1 +/- 0.6 < 0.6 5.0 Sr-90 0.3 +/- 0.3 < 0.5 0.5 +/- 0.3 < 0.5 0.5 +/- 0.3 < 0.5 1.0 1-131 -0.20 +/- 0.19 < 0.42 -0.05 +/- 0.10 < 0.19 -0.53 +/- 0.14 < 0.27 0.5 K-40 1450 +/- 114 1458 +/- 110 1437 +/- 125 Cs-134 0.7 +/- 2.0 < 3.5 -0.1 +/- 2.1 < 3.5 -3.3 +/- 2.5 < 4.7 5.0 Cs-137 -1.2 +/- 2.3 < 3.3 1.5+/-2.1 < 4.0 0.3 +/- 2.4 < 3.2 5.0 Ba-La-140 -1.4 +/- 1.9 < 4.2 0.9 +/- 1.9 < 4.6 -1.5+/-2.1 < 4.6 5.0 Other (Co-60) -0.9 +/- 2.2 < 3.3 0.3 +/- 2.4 < 3.8 0.3 +/- 2.9 < 3.6 15.0 MDC MDC MDC Required Collection Date 04-14-21 05-12-21 06-09-21 LLD Lab Code EMI- 1006 EMI- 1399 EMI- 1707 Sr-89 0.3 +/- 0.5 < 0.5 -0.2 +/- 0.5 < 0.7 -0.4 +/- 0.7 < 0.7 5.0 Sr-90 0.4 +/- 0.3 < 0.5 0.2 +/- 0.2 < 0.4 0.5 +/- 0.3 < 0.5 1.0 1-131 -0.10 +/- 0.18 < 0.38 0.00 +/- 0.13 < 0.24 0.06 +/- 0.14 < 0.24 0.5 K-40 1356 +/- 110 1499 +/- 98 1445 +/- 81 Cs-134 0.1 +/- 1.8 < 3.1 0.7 +/- 1.8 < 3.7 -1.1+/-1.4 < 2.8 5.0 Cs-137 0.6 +/- 2.2 < 3.5 0.4+/-2.1 < 3.5 0.3 +/- 1.6 < 2.8 5.0 Ba-La-140 0.3+/- 1.7 < 1.3 -0.9 +/- 6.3 < 4.6 0.6 +/- 1.3 < 3.8 5.0 Other (Co-60) 0.5 +/- 2.0 < 2.8 1.8 +/- 2.0 < 3.1 -0.8 +/- 1.5 < 1.6 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 07-14-21 08-11-21 09-08-21 LLD Lab Code EMI- 2185 EMI- 2558 EMI- 2885 Sr-89 -0.3 +/- 0.6 < 0.7 0.5 +/- 0.6 < 0.7 0.4 +/- 0.5 < 0.6 5.0 Sr-90 0.5 +/- 0.3 < 0.5 0.2 +/- 0.3 < 0.5 0.1 +/- 0.3 < 0.5 1.0 1-131 0.09 +/- 0.16 < 0.30 -0.05 +/- 0.13 < 0.24 0.12 +/- 0.18 < 0.31 0.5 K-40 1440 +/- 112 1299 +/- 105 1429 +/- 116 Cs-134 -0.6 +/- 2.0 < 3.1 -0.4 +/- 1.8 < 3.6 0.5 +/- 2.1 < 3.7 5.0 Cs-137 0.3 +/- 2.3 < 4.0 0.3 +/- 2.4 < 2.9 2.3 +/- 2.2 < 3.6 5.0 Ba-La-140 1.0 +/- 2.0 < 2.9 -0.1 +/- 1.6 < 1.7 -1.3+/-2.1 < 3.4 5.0 Other (Co-60) 0.4+/-2.1 < 3.4 -1.4 +/- 2.2 < 1.9 0.2 +/- 2.5 < 4.0 15.0 MDC MDC MDC Required Collection Date 10-13-21 11-10-21 12-08-21 LLD Lab Code EMI- 3322 EMI- 3792 EMI* 4008 Sr-89 -0.2 +/- 0.5 < 0.6 0.3 +/- 0.7 < 0.7 -0.7 +/- 0.8 < 0.8 5.0 Sr-90 0.3 +/- 0.3 < 0.5 0.2 +/- 0.3 < 0.6 0.6 +/- 0.4 < 0.6 1.0 1-131 -0.06 +/- 0.21 < 0.43 0.11 +/- 0.18 < 0.32 0.00+/-0.19 < 0.35 0.5 K-40 1469 +/- 107 1543 +/- 118 1298 +/- 114 Cs-134 -1.0 +/- 1.9 < 3.3 -1.5 +/- 2.3 < 4.6 -1.7 +/- 2.0 < 3.7 5.0 Cs-137 0.8 +/- 1.8 < 3.3 0.8 +/- 2.6 < 4.9 -0.2 +/- 2.5 < 3.4 5.0 Ba-La-140 0.7 +/- 1.2 < 2.0 -2.0 +/- 2.6 < 3.1 0.8 +/- 1.8 < 2.5 5.0 Other (Co-60) 1.2 +/- 2.0 < 2.8 -0.6 +/- 2.7 < 2.6 2.3 +/- 2.3 < 3.7 15.0 Sr-89 Annual Mean+ s.d. 0.0 +/- 0.3 Sr-90 Annual Mean+ s.d. 0.4 +/- 0.2 1-131 Annual Mean+ s.d. -0.01 +/- 0.12 K-40 Annual Mean + s.d. 1377+/-95 Cs-134 Annual Mean+ s.d. -0.7 +/- 1.3 Cs-137 Annual Mean+ s.d. 0.0 +/- 1.1 Ba-La Annual Mean+ s.d. -0.4 +/- 1.3 Co-60 Annual Mean + s.d. 0.1 +/- 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.

LLD Collection Date 01-21-21 04-16-21 07-21-21 10-14-21 Lab Code EWW- 179 EWW- 1063 EWW- 2332 EWW- 3319 Gross Beta 0.9 +/- 1.1 0.7 +/- 1.0 0.8 +/- 1.1 1.4 +/- 1.1 4.0 0.9 +/- 0.3 H-3 -32 +/- 72 -18 +/- 74 61 +/- 79 81 +/- 81 500 22.8 +/- 56.2 Sr-89 0.2 +/- 0.4 -0.2 +/- 0.4 0.3 +/- 0.3 0.1 +/- 0.4 5.0 0.1 +/- 0.2 Sr-90 0.0 +/- 0.2 0.0 +/- 0.2 -0.2 +/- 0.2 -0.1 +/- 0.2 1.0 -0.1 +/- 0.1 1-131 -0.11 +/-0.21 -0.05 +/- 0.20 0.18 +/- 0.21 -0.15 +/- 0.18 0.5 -0.03 +/- 0.15 Mn-54 -0.8 +/- 3.1 0.7 +/- 2.6 -1.3 +/- 1.8 -0.6 +/- 1.4 10 -0.5 +/- 0.8 Fe-59 -1.5 +/- 1.4 3.4 +/- 4.4 0.9 +/- 3.5 0.2 +/- 2.4 30 0.8 +/- 2.0 Co-58 1.3 +/- 2.3 -0.8 +/- 2.2 -1.9 +/- 1.8 0.0 +/- 1.5 10 -0.3 +/- 1.4 Co-60 0.7 +/- 3.2 0.9 +/- 2.9 2.2 +/- 1.9 -0.1 +/- 1.7 10 0.9 +/- 0.9 Zn-65 -14.5 +/- 7.2 -4.5 +/- 6.3 -4.1 +/- 4.0 -2.1 +/- 3.1 30 -6.3 +/- 5.6 Zr-Nb-95 -0.9 +/- 3.2 -1.6 +/- 2.5 -0.3 +/- 1.7 -0.1 +/- 1.6 15 -0.7 +/- 0.7 Cs-134 -4.3 +/- 3.2 -0.6 +/- 2.2 -0.2 +/- 2.0 -0.1 +/- 1.5 10 -1.3 +/- 2.0 Cs-137 -3.1 +/- 3.0 -4.2 +/- 2.5 -1.7 +/- 2.0 1.7 +/- 1.7 10 -1.8 +/- 2.5 Ba-La-140 -1.0 +/- 3.3 -0.8 +/- 2.6 -0.8 +/- 2.1 0.1 +/- 4.7 15 -0.6 +/- 0.5 Other (Ru-103) -0.9 +/- 2.7 1.8 +/- 2.5 0.5 +/- 1.9 -0.7 +/- 1.5 30 0.2 +/- 1.2 MDC Data Collection Date 01-21-21 04-16-21 07-21-21 10-14-21 Lab Code EWW- 179 EWW- 1063 EWW- 2332 EWW- 3319 Gross Beta < 2.0 < 1.9 < 2.0 < 1.9 4.0 < 2.0 H-3 < 160 < 159 < 156 < 159 500 < 158.2 Sr-89 < 0.6 < 0.5 < 0.4 < 0.6 5.0 < 0.5 Sr-90 < 0.5 < 0.5 < 0.5 < 0.5 1.0 < 0.5 1-131 < 0.39 < 0.41 < 0.37 < 0.33 0.5 < 0.37 Mn-54 < 5.6 < 4.4 < 2.2 < 1.5 10 < 3.4 Fe-59 < 5.3 < 7.0 < 6.9 < 5.1 30 < 6.1 Co-58 < 3.5 < 3.7 < 2.3 < 2.4 10 < 3.0 Co-60 < 4.7 < 2.2 < 2.5 < 2.7 10 < 3.0 Zn-65 < 10.6 < 7.1 < 2.9 < 4.0 30 < 6.1 Zr-Nb-95 < 4.2 < 3.1 < 4.6 < 2.6 15 < 3.6 Cs-134 < 5.8 < 4.3 < 3.9 < 2.7 10 < 4.2 Cs-137 < 3.8 < 2.9 < 2.8 < 3.4 10 < 3.2 Ba-La-140 < 2.9 < 1.8 < 3.4 < 3.6 15 < 2.9 Other (Ru-103) < 5.6 < 5.0 < 3.9 < 2.1 30 < 4.1 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 ELW- 77 NS" ELW- 600 ELW- 1012 Date Collected 01-12-21 02-09-21 03-10-21 04-14-21 Req. LLD Gross beta 1.6 +/- 0.6 < 0.9 1.7 +/- 0.6 < 0.9 1.1 +/- 0.6 < 0.9 4.0 1-131 -0.02 +/-0.12 < 0.22 0.12 +/- 0.14 < 0.24 -0.13 +/- 0.13 < 0.24 0.5 Be-7 33.6 +/- 18.6 < 41.1 0.8 +/- 19.5 < 26.6 -3.1 +/- 19.2 < 43.3 Mn-54 0.4 +/- 1.6 < 1.9 -0.6 +/- 2.1 < 2.5 -1.4 +/- 1.9 < 3.0 10 Fe-59 -2.3 +/- 4.4 < 4.5 0.2 +/- 4.5 < 9.2 -1.0 +/- 3.6 < 6.7 30 Co-58 2.2 +/- 2.1 < 4.4 0.6 +/- 1.9 < 3.8 -1.9 +/- 1.6 < 2.7 10 Co-60 0.2 +/- 2.3 < 2.4 1.0 +/- 1.9 < 3.1 -0.1 +/- 2.0 < 2.0 10 Zn-65 -8.6 +/- 5.4 < 10.8 4.8 +/- 4.6 < 5.7 1.2 +/- 4.4 < 6.6 30 Zr-Nb-95 0.1 +/- 2.7 < 4.5 -0.6 +/- 2.0 < 3.9 -0.5 +/- 1.6 < 2.7 15 Cs-134 -6.4 +/- 2.9 < 3.7 0.3 +/- 2.0 < 4.0 -0.5 +/- 2.3 < 4.7 10 Cs-137 -2.6 +/- 2.6 < 2.7 -1.4 +/- 2.1 < 2.3 1.8 +/- 2.2 < 3.9 10 Ba-La-140 -5.0 +/- 2.6 < 11.9 -0.7 +/- 2.0 < 7.1 -3.2 +/- 2.2 < 8.3 15 Other (Ru-103) -3.3 +/- 2.2 < 3.4 -2.5 +/- 2.3 < 6.2 1.3 +/- 2.1 < 5.2 30 Lab Code ELW- 1405 ELW- 1708 ELW- 2177 ELW- 2545 Date Collected 05-12-21 06-08-21 07-13-21 08-11-21 Req. LLD Gross beta 1.0 +/- 0.5 < 0.9 0.7 +/- 0.5 < 0.9 1.1 +/- 0.5 < 0.8 1.4 +/- 0.6 < 0.9 4.0 1-131 -0.19 +/- 0.13 < 0.26 0.03 +/- 0.14 < 0.24 -0.07 +/- 0.14 < 0.26 -0.12 +/- 0.15 < 0.29 0.5 Be-7 7.7 +/- 10.8 < 24.3 -5.7 +/- 11.5 < 30.9 -4.5 +/- 14.0 < 29.3 2.5 +/- 17.9 < 28.9 Mn-54 2.0 +/- 1.3 < 2.7 -0.7 +/- 1.6 < 1.7 0.7 +/- 1.4 < 2.8 -0.4 +/- 1.9 < 3.0 10 Fe-59 0.1 +/- 2.4 < 5.8 -2.4 +/- 2.9 < 4.8 -2.7 +/- 2.9 < 4.5 2.5 +/- 3.6 < 9.0 30 Co-58 0.6 +/- 1.1 < 3.0 -0.9 +/- 1.6 < 1.8 1.1 +/- 1.5 < 2.0 -0.9 +/- 1.7 < 3.7 10 Co-60 -0.6 +/- 1.4 < 1.2 -0.5 +/- 1.7 < 2.6 -1.3 +/- 1.8 < 1.9 1.1 +/- 2.3 < 2.8 10 Zn-65 1.1 +/- 2.5 < 4.8 0.9 +/- 2.8 < 5.3 -1.2 +/- 3.4 < 5.8 2.6 +/- 3.6 < 6.1 30 Zr-Nb-95 0.9 +/- 1.1 < 3.8 -2.9 +/- 1.4 < 2.5 0.9 +/- 1.8 < 4.3 -1.8 +/- 1.7 < 3.3 15 Cs-134 -1.0 +/- 1.2 < 2.4 0.6 +/- 1.4 < 2.9 0.8 +/- 1.6 < 3.0 1.2 +/- 1.7 < 3.5 10 Cs-137 -0.3 +/- 1.3 < 2.2 -0.5 +/- 1.8 < 2.4 0.8 +/- 1.9 < 2.7 0.6 +/- 1.9 < 2.9 10 Ba-La-140 1.2 +/- 1.4 < 5.1 0.9 +/- 1.5 < 5.3 -2.1 +/- 2.0 < 3.1 -5.7 +/- 2.3 < 2.7 15 Other (Ru-103) 1.0 +/- 1.2 < 3.1 -1.2 +/- 1.4 < 3.4 -0.4 +/- 1.6 < 3.8 -0.2 +/- 1.9 < 4.6 30 Lab Code ELW- 2886 ELW- 3328 ELW- 3793 ELW- 4013 Date Collected 09-07-21 10-12-21 11-10-21 12-07-21 Req. LLD Gross beta 0.5 +/- 0.5 < 0.9 1.1 +/- 0.5 < 0.9 1.3 +/- 0.6 < 0.9 0.7 +/- 0.6 < 1.0 4.0 1-131 -0.05 +/- 0.14 < 0.27 -0.10+/-0.15 < 0.29 0.12 +/- 0.17 < 0.30 -0.03 +/- 0.21 < 0.43 0.5 Be-7 -18.8 +/- 11.9 < 24.1 -17.4 +/- 13.0 < 33.9 2.4 +/- 5.3 < 16.8 19.7 +/- 14.0 < 33.2 Mn-54 1.4 +/- 1.6 < 2.7 -1.8 +/- 1.7 < 1.5 0.8 +/- 0.6 < 1.3 0.9 +/- 1.7 < 2.8 10 Fe-59 -2.1 +/- 2.9 < 5.3 3.3 +/- 3.0 < 7.1 0.6 +/- 1.0 < 3.6 -1.3 +/- 2.8 < 3.6 30 Co-58 1.8 +/- 1.3 < 2.3 0.7 +/- 1.6 < 2.8 0.8 +/- 0.6 < 1.7 0.7 +/- 1.4 < 2.0 10 Co-60 -0.1 +/- 1.5 < 1.5 1.3 +/- 1.8 < 2.3 0.0 +/- 0.7 < 1.3 -1.0 +/- 1.8 < 2.7 10 Zn-65 -0.3 +/- 2.6 < 3.8 2.2 +/- 3.5 < 7.8 0.4 +/- 1.2 < 2.6 -1.6 +/- 3.1 < 3.5 30 Zr-Nb-95 0.8 +/- 1.5 < 2.8 -6.1 +/- 2.2 < 3.3 0.2 +/- 0.7 < 2.3 -0.7 +/- 1.9 < 4.2 15 Cs-134 0.9 +/- 1.6 < 2.7 1.9 +/- 1.6 < 3.0 -1.0 +/-0.7 < 1.2 -0.8 +/- 1.8 < 3.3 10 Cs-137 -1.5 +/- 1.7 < 2.3 -0.1 +/- 2.0 < 3.5 0.9 +/- 0.8 < 1.4 -1.0 +/- 1.8 < 2.4 10 Ba-La-140 -0.9 +/- 1.4 < 3.8 -4.1 +/- 1.g < 6.4 -4.1 +/- 0.7 < 7.7 0.7 +/- 1.2 < 1.7 15 Other (Ru-103) -0.8 +/- 1.4 < 2.5 0.0 +/- 1.6 < 3.3 0.1 +/- 0.6 < 2.6 -0.4 +/- 1.6 < 3.5 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 ELW- 78 NS" ELW- 601 ELW- 1013 Date Collected 01-12-21 02-09-21 03-10-21 04-14-21 Req. LLD Gross beta 1.1 +/- 0.5 < 0.9 3.6 +/- 0.7 < 0.9 1.3 +/- 0.6 < 0.9 4.0 1-131 0.11 +/- 0.13 < 0.23 0.06 +/- 0.13 < 0.24 -0.05 +/- 0.12 < 0.23 0.5 Be-7 18.9 +/- 20.0 < 47.6 8.5 +/- 16.4 < 41.3 32.0 +/- 17.2 < 36.3 Mn-54 1.3 +/- 2.1 < 1.8 1.2 +/- 1.7 < 3.2 -1.8 +/- 2.1 < 2.4 10 Fe-59 0.5 +/- 4.2 < 5.6 -1.3 +/- 3.4 < 3.7 -5.1 +/- 4.1 < 3.9 30 Co-58 -0.2 +/- 2.1 < 2.8 -0.9 +/- 2.2 < 3.3 0.3 +/- 1.7 < 2.4 10 Co-60 -0.8 +/- 1.9 < 2.5 1.5 +/- 2.1 < 3.0 -1.1 +/- 2.4 < 2.1 10 Zn-65 -4.7 +/- 5.3 < 4.4 -1.6 +/- 4.2 < 5.6 -2.9 +/- 4.7 < 5.6 30 Zr-Nb-95 -1.8 +/- 2.3 < 3.3 -3.0 +/- 2.1 < 3.2 -2.2 +/- 2.2 < 5.0 15 Cs-134 -1.5 +/- 2.4 < 3.9 -4.9 +/- 2.3 < 3.5 -4.3 +/- 2.5 < 4.1 10 Cs-137 -0.9 +/- 2.7 < 2.5 0.6 +/- 2.3 < 3.8 1.8 +/- 2.4 < 3.9 10 Ba-La-140 -19.1 +/- 7.4 < 13.8 0.6 +/- 2.2 < 13.0 -0.3 +/- 2.2 < 7.8 15 Other (Ru-103} -1.3 +/- 2.2 < 2.7 -2.9 +/- 2.1 < 3.2 -0.2 +/- 2.3 < 4.5 30 Lab Code ELW- 1406 ELW- 1709 ELW- 2178 ELW- 2546 Date Collected 05-12-21 06-08-21 07-13-21 08-11-21 Req. LLD Gross beta 0.8 +/- 0.5 < 0.9 0.5 +/- 0.5 < 0.8 1.8 +/- 0.6 < 0.9 0.9 +/- 0.5 < 0.9 4.0 1-131 -0.06 +/- 0.14 < 0.26 0.02 +/- 0.23 < 0.48 -0.07 +/- 0.12 < 0.23 -0.15 +/- 0.15 < 0.28 0.5 Be-7 -4.4 +/- 11.6 < 33.2 -5.3 +/- 16.0 < 28.1 -4.7 +/- 18.1 < 34.1 9.4 +/- 17.3 < 31.2 Mn-54 -0.1 +/- 1.2 < 1.9 1.4 +/- 1.4 < 2.7 0.2 +/- 1.8 < 3.2 1.2 +/- 1.8 < 3.5 10 Fe-59 1.2+/-2.5 < 3.6 2.9 +/- 3.0 < 3.9 -3.8 +/- 3.6 < 3.0 2.3 +/- 3.6 < 4.7 30 Co-58 -1.2 +/- 1.3 < 1.5 2.4+/-1.6 < 3.6 -0.5 +/- 1.7 < 2.9 1.6 +/- 1.5 < 3.3 10 Co-60 0.8 +/- 1.8 < 2.5 -0.1 +/- 1.8 < 2.5 -0.5 +/- 1.7 < 1.6 -0.6 +/- 1.7 < 2.3 10 Zn-65 1.5 +/- 3.0 < 5.1 -1.5 +/- 3.3 < 3.3 4.1 +/- 3.5 < 4.8 1.2 +/- 4.2 < 3.5 30 Zr-Nb-95 -1.3 +/- 1.5 < 2.6 -0.8 +/- 1.8 < 4.1 0.7 +/- 1.9 < 4.8 -1.7 +/- 1.4 < 2.2 15 Cs-134 -0.5 +/- 1.3 < 2.5 -0.1 +/- 1.9 < 3.9 -0.9 +/- 1.8 < 3.8 0.8 +/- 2.0 < 3.7 10 Cs-137 -0.2 +/- 1.7 < 2.6 0.3 +/- 1.9 < 2.7 0.4 +/- 2.2 < 3.9 -2.8 +/- 2.3 < 1.7 10 Ba-La-140 5.1 +/- 1.5 < 6.2 -1.8 +/- 1.8 < 6.7 0.6 +/- 2.0 < 5.8 -2.3 +/- 1.9 < 4.8 15 Other (Ru-103) 1.0 +/- 1.5 < 4.0 0.5 +/- 2.0 < 5.5 -0.1 +/- 2.3 < 4.5 -1.3+/-2.1 < 3.8 30 Lab Code ELW- 2887 ELW- 3329 ELW- 3794 ELW- 4014 Date Collected 09-07-21 10-12-21 11-10-21 12-07-21 Req. LLD Gross beta 0.9 +/- 0.5 < 0.9 1.4 +/- 0.6 < 0.9 0.9 +/- 0.5 < 0.9 1.5 +/- 0.6 < 0.9 4.0 1-131 0.12 +/- 0.15 < 0.25 -0.02 +/- 0.16 < 0.30 0.02 +/- 0.14 < 0.25 0.04 +/- 0.16 < 0.29 0.5 Be-7 4.5 +/- 11.4 < 24.8 9.4 +/- 12.3 < 36.0 -3.0 +/- 8.1 < 23.3 25.1 +/- 16.3 < 37.0 Mn-54 0.8 +/- 1.4 < 2.4 -0.3 +/- 1.4 < 2.1 -0.2 +/- 0.8 < 1.5 -0.6 +/- 2.0 < 2.8 10 Fe-59 -1.0 +/- 2.5 < 4.3 -3.0 +/- 2.6 < 4.4 0.1 +/- 1.6 < 3.5 -2.9 +/- 3.4 < 5.7 30 Co-58 1.0 +/- 1.4 < 2.4 1.0 +/- 1.4 < 2.4 -0.6 +/- 0.8 < 1.8 0.0 +/- 1.8 < 3.8 10 Co-60 0.3 +/- 1.7 < 2.6 1.2 +/- 1.6 < 2.5 0.5 +/- 0.8 < 1.6 -1.3 +/- 2.2 < 1.9 10 Zn-65 0.3 +/- 2.7 < 3.9 3.8 +/- 2.8 < 5.2 -0.6 +/- 1.8 < 3.4 -1.0 +/- 3.9 < 3.8 30 Zr-Nb-95 0.3 +/- 1.5 < 3.8 0.2 +/- 1.5 < 4.9 0.0 +/- 0.8 < 2.6 0.0 +/- 1.7 < 4.1 15 Cs-134 0.1 +/- 1.4 < 2.4 -0.7 +/- 1.5 < 2.8 -0.5 +/- 0.8 < 1.8 0.9 +/- 1,8 < 3.8 10 Cs-137 1.4 +/- 1.5 < 2.8 0.7 +/- 1.6 < 3.1 0.2 +/- 1.0 < 1.5 0.7 +/- 1.9 < 3.9 10 Ba-La-140 0.2 +/- 1.6 < 6.5 0.3 +/- 1. 7 " 9.3 -4.9 +/- 0.9 < 6.5 -2.9 +/- 2.2 < 2.1 15 Other (Ru-103) -0.4 +/- 1.4 < 4.0 -0.4 +/- 1.3 < 3.5 -1.3 +/- 1.0 < 3.5 -2.8 +/- 1.9 < 3.7 30 a "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 ELW- 79 Ns* ELW- 602 ELW- 1014 Date Collected 01-12-21 02-09-21 03-10-21 04-14-21 Req.LLD Gross beta 1.1 +/- 0.6 < 0.9 2.0 +/- 0.6 < 0.9 1.4 +/- 0.6 < 0.9 4.0 1-131 0.12 +/- 0.21 < 0.42 -0.01 +/- 0.12 < 0.21 0.18+/-0.19 < 0.36 0.5 Be-7 -1.7 +/- 11.7 < 18.5 -3.5 +/- 10.9 < 24.9 2.3 +/- 13.9 < 44.0 Mn-54 1.0 +/- 1.3 < 3.0 1.0 +/- 1.6 < 2.8 2.0 +/- 1.6 < 2.2 10 Fe-59 0.2 +/- 2.3 < 5.8 -1.0 +/-3.1 < 4.4 1.2 +/- 3.1 < 5.8 30 Co-58 0.1 +/- 1.3 < 2.7 -0.3 +/- 1.5 < 2.8 -0.3 +/- 1.7 < 2.4 10 Co-60 -0.9 +/- 1.4 < 1.9 0.4 +/- 1.6 < 2.4 0.7 +/- 1.6 < 2.4 10 Zn-65 -0.8 +/- 2.5 < 3.3 -2.8 +/- 3.6 < 4.5 -1.8 +/- 3.4 < 4.2 30 Zr-Nb-95 0.7 +/- 1.6 < 4.4 -1.6 +/- 1.9 < 3.2 -0.1 +/- 1.7 < 5.3 15 Cs-134 -1.9 +/- 1.5 < 2.6 -0.8 +/- 1.7 < 3.2 0.6 +/- 1.8 < 3.1 10 Cs-137 -0.6 +/- 1.5 < 2.1 -0.3 +/- 1.8 < 2.6 1.2 +/- 1.9 < 4.1 10 Ba-La-140 0.2 +/- 1.3 < 6.0 -0.6 +/- 1.9 < 7.2 -10.1 +/- 2.0 < 3.7 15 Other (Ru-103) -0.4 +/- 1.3 < 3.2 -0.5 +/- 1.5 < 3.9 -1.7 +/- 1.5 < 2.7 30 Lab Code ELW- 1407 ELW- 1710 ELW- 2179 ELW- 2547 Date Collected 05-12-21 06-08-21 07-13-21 08-11-21 Req. LLD Gross beta 1.4 +/- 0.6 < 0.9 1.1 +/- 0.6 < 0.9 1.2 +/-0.6 <1.0 0.8 +/- 0.5 < 0.9 4.0 1-131 -0.04 +/- 0.20 < 0.42 -0.03 +/- 0.12 < 0.23 0.10 +/- 0.12 < 0.21 -0.05 +/- 0.18 < 0.32 0.5 Be-7 2.5 +/- 16.4 < 35.7 5.6 +/- 18.2 < 37.2 -12.3 +/- 15.4 < 28.3 9.0 +/- 12.4 < 32.4 Mn-54 -0.3 +/- 1.8 < 3.3 -0.6 +/- 1.6 < 2.7 -0.3 +/- 1.4 < 2.0 0.1 +/- 1.6 < 1.5 10 Fe-59 -2.0 +/- 2.9 < 4.9 -2.1 +/- 3.2 < 4.9 -0.3 +/- 3.0 < 3.2 -2.9 +/- 2.6 < 3.2 30 Co-58 -0.2 +/- 1.5 < 1.8 1.0 +/- 1.6 < 4.1 -0.7 +/- 1.5 < 2.5 0.2 +/- 1.7 < 2.6 10 Co-60 1.1 +/- 1.7 < 2.2 1.6 +/- 1.6 < 2.0 0.3 +/- 1.5 < 2.1 2.2 +/- 2.0 < 3.1 10 Zn-65 3.1 +/- 3.3 < 3.9 2.1 +/- 3.6 < 5.1 0.2 +/- 3.0 < .3.4 -1.5 +/- 2.8 < 3.8 30 Zr-Nb-95 -1.7 +/- 1.9 < 4.5 -0.5 +/- 1.9 < 3.0 -0.8 +/- 1.5 < 3.2 -3.3 +/- 1.8 < 1.9 15 Cs-134 -1.4 +/-2.0 <3.1 0.6 +/- 1.9 < 3.8 0.2 +/- 1.5 < 3.1 -0.3 +/- 1.7 < 2.8 10 Cs-137 -0.3 +/- 2.1 < 2.1 0.3 +/- 1.9 < 1.6 0.2 +/- 1.8 < 2.0 -0.3 +/- 1.9 < 2.7 10 Ba-La-140 -3.3 +/- 2.2 < 7.8 -3.8 +/- 1.9 < 7.4 -1.0 +/- 2.0 < 5.5 1.8 +/-1.9 <5.1 15 Other (Ru-103) -1.3 +/- 1.9 < 3.1 -1.2 +/- 1.9 < 4.0 -0.1 +/- 1.7 < 3.5 0.3 +/- 1.4 < 4.0 30 Lab Code ELW- 2888 ELW- 3330 ELW- 3796 NS a Date Collected 09-07-21 10-12-21 11-10-21 12-07-21 Req. LLD Gross beta 0.7 +/- 0.5 < 0.9 1.5 +/- 0.6 < 0.9 0.8 +/- 0.5 < 0.8 4.0 1-131 0.12 +/- 0.19 < 0.36 0.04 +/- 0.15 < 0.27 0.01 +/- 0.14 < 0.25 0.5 Be-7 -3.0 +/- 16.2 < 28.5 12.4 +/- 13.3 < 28.7 -17.6 +/- 19.6 < 30.3 Mn-54 -1.7 +/- 1.7 < 2.0 -0.3 +/- 1.4 < 1.5 1.5 +/- 2.0 < 3.8 10 Fe-59 0.9 +/- 3.1 < 5.5 1.6 +/- 2.9 < 5.7 -0.9 +/- 3.2 < 8.2 30 Co-58 -0.7 +/- 1.6 < 2.7 -0.3 +/- 1.6 < 2.2 1.6 +/- 1.9 < 4.3 10 Co-60 0.6 +/- 1.7 < 2.1 -1.0 +/- 1.7 < 2.1 1.7 +/- 2.2 < 2.4 10 Zn-65 1.9 +/- 3.2 < 4.6 -0.1 +/- 2.8 < 6.5 -1.5 +/- 4.9 < 6.0 30 Zr-Nb-95 -0.4 +/- 1.9 < 2.7 0.4 +/- 2.9 < 5.3 -0.6 +/- 1,9 < 5.1 15 Cs-134 0.4 +/- 1.6 < 3.5 -1.4 +/- 1.5 < 2.8 -2.4 +/- 1.9 < 4.0 10 Cs-137 0.6 +/- 2.0 < 3.7 -0.8 +/- 2.2 < 2.5 -0.9 +/- 2.2 < 2.8 10 Ba-La-140 -0.2 +/- 1.7 < 5.6 1.5 +/- 1.8 < 12.2 0.2 +/- 2.2 < 9.9 15 Other (Ru-103) -1.1 +/- 1.9 < 3.8 -0.8 +/- 1.6 < 3.5 0.2 +/- 2.1 < 4.0 30 a "NS"= No sample; see Table 2.0, Listing of Missed Samples.

5-3

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

Gross Beta 1.2 +/- 0.6 1-131 0.00 +/- 0.09 Co-58 0.2 +/- 0.9 Cs-134 -0.5 +/- 1.6 Be-7 2.4 +/- 11.1 Co-60 0.2 +/- 0.8 Cs-137 0.0 +/- 0.9 Mn-54 0.2 +/- 0.9 Zn-65 0,0 +/- 2.3 Ba-La-140 -1.5 +/- 3.7 Fe-59 -0.5 +/- 1.8 Zr-Nb-95 -0.6 +/- 1.4 Ru-103 -0.5 +/- 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 {Meteorolo_gical Tower}

Period 1st Qtr. MDC 2nd Qtr. MDC 3rd Qtr. MDC 4thQtr. MDC Lab Code ELW- 647 ELW- 1735 ELW- 2952 ELW- 4237 H-3 45 +/-76 < 158 73 +/-79 < 161 59 +/- 81 < 162 484+/-101 < 157 Sr-89 0.53 +/-0.66 < 0.77 -0.21 +/- 0.48 < 0.56 -0.05 +/- 0.48 < 0.62 -0.11 +/-0.63 < 0.73 Sr-90 -0.02 +/-0.28 < 0.61 0.39 +/- 0.28 < 0.51 0.13+/-0.25 < 0.50 0.29 +/-0.28 < 0.54 a Monthly tritium analyses in App. F Location E-05 (Two Creeks Park Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4th Qtr.

Lab Code ELW- 648 ELW- 1736 ELW- 2953 ELW- 4238 H-3 67 +/-77 < 158 114 +/- 81 < 161 50 +/- 81 < 162 52 +/-79 < 157 Sr-89 -0.17 +/-0.54 < 0.74 0.21 +/- 0.46 < 0.61 -0.41 +/- 0.51 < 0.66 -0.04 +/- 0.63 < 0.79 Sr-90 0.14 +/-0.26 < 0.52 -0.01 +/- 0.26 < 0.56 0.29 +/- 0.28 < 0.52 0.18 +/-0.28 < 0.56 Location E-06 {Coast Guard Station Period 1st Qtr. 2nd Qtr. 3rd Qtr. 4thQtr.

Lab Code ELW- 649 ELW- 1737 ELW- 2954 ELW- 4239 H-3 -36 +/- 71 < 158 3 +/-75 < 161 117 +/- 85 < 162 125 +/- 83 < 158 Sr-89 -0.01 +/- 0.54 < 0.62 0.12 +/- 0.47 < 0.51 -0.06 +/- 0.46 < 0.56 0.18 +/-0.89 < 1.01 Sr-90 0.27 +/-0.26 < 0.50 0.34 +/-0.27 < 0.49 0.20 +/- 0.25 < 0.48 0.20 +/-0.27 < 0.54 Tritium Annual Mean+/- s.d. 96 +/- 130 Sr-89 Annual Mean +/- s.d. 0.00 +/- 0.24 Sr-90 Annual Mean+/- s.d. 0.20 +/- 0.13 6-1

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

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

MDC MDC MDC LLD Collection Date 01-20-21 01-10-21 02-05-21 Lab Code EF- 477 EF- 478 EF- 479 Type Brown trout Burbot Burbot K-40 2.20 +/- 0.33 1.92 +/- 0.294 0.95 +/- 0.22 Mn-54 0.003 +/- 0.008 < 0.017 -0.003 +/- 0.008 < 0.018 -0.001 +/- 0.007 < 0.012 0.13 Fe-59 0.023 +/- 0.015 < 0.081 -0.031 +/- 0.018 < 0.058 -0.022 +/- 0.013 < 0.024 0.26 Co-58 0.006 +/- 0.007 < 0.023 0.004 +/- 0.009 < 0.032 -0.004 +/- 0.007 < 0.017 0.13 Co-60 -0.007 +/- 0.009 < 0.013 0.000 +/- 0.009 < 0.013 -0.003 +/- 0.008 < 0.011 0.13 Zn-65 0.011 +/- 0.019 < 0.043 -0.069 +/- 0.024 < 0.039 -0.018 +/- 0.014 < 0.022 0.26 Cs-134 -0.011 +/- 0.008 < 0.015 -0.025 +/- 0.011 < 0.020 -0.028 +/- 0.009 < 0.013 0.13 Cs-137 0.012 +/- 0.010 < 0.018 0.026 +/- 0.013 < 0.019 -0.006 +/- 0.008 < 0.007 0.15 Other (Ru-103) 0.006 +/- 0.007 < 0.053 -0.012 +/- 0.008 < 0.051 0.003 +/- 0.006 < 0.034 0.5 Collection Date 06-01-21 05-12-21 05-02-21 Lab Code EF- 1702 EF- 1703 EF- 1704 Type Lake Trout Burbot Salmon K-40 2.38 +/- 0.38 1.81 +/- 1.81 1.46 +/- 0.29 Mn-54 0.012 +/- 0.009 <0.016 0.015 +/- 0.010 < 0.021 0.007 +/- 0.009 < 0.020 0.13 Fe-59 0.024 +/- 0.022 < 0.054 -0.013 +/- 0.017 < 0.065 -0.013 +/- 0.018 < 0.030 0.26 Co-58 -0.001 +/- 0.008 < 0.015 -0.008 +/- 0.011 < 0.033 0.015 +/- 0.008 < 0.025 0.13 Co-60 0.001 +/- 0.012 <0.013 -0.002 +/- 0.009 < 0.014 0.006 +/- 0.008 < 0.010 0.13 Zn-65 0.007 +/- 0.020 < 0.033 0.011 +/- 0.023 < 0.042 -0.008 +/- 0.023 < 0.036 0.26 Cs-134 -0.001 +/- 0.010 < 0.020 0.001 +/- 0.009 < 0.021 -0.011 +/- 0.008 < 0.017 0.13 Cs-137 0.005 +/- 0.012 < 0.018 0.010 +/- 0.013 < 0.022 0.000 +/- 0.010 < 0.012 0.15 Other (Ru-103) O.Q12 +/- 0.010 < 0.035 0.005 +/- 0.009 < 0.057 0.000 +/- 0.009 < 0.039 0.5 7-1

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

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

MDC MDC MDC LLD Collection Date 08-31-21 07-21-21 08-22-21 Lab Code EF- 2777 EF- 2778 EF- 2779 Type Lake Trout Chinook Salmon Salmon K-40 3.44 +/- 0.44 2.28 +/- 0.35 2.03 +/- 2.03 Mn-54 0.000 +/- 0.008 < 0.012 -0.007 +/- 0.008 < 0.013 -0.004 +/- 0.011 < 0.013 0.13 Fe-59 0.001 +/- 0.016 < 0.048 -0.025 +/- 0.017 < 0.087 0.007 +/- 0.019 < 0.057 0.26 Co-58 0.001 +/- 0.008 < 0.018 -0.004 +/- 0.008 < 0.029 -0.004 +/- 0.010 < 0.024 0.13 Co-60 -0.003 +/- 0.010 < 0.014 0.000 +/- 0.009 < 0.010 -0.005 +/- 0.011 < 0.011 0.13 Zn-65 0.008 +/- 0.018 < 0.032 -0.009 +/- 0.018 < 0.025 -0.007 +/- 0.023 < 0.026 0.26 Cs-134 -0.003 +/- 0.008 < 0.015 -0.002 +/- 0.008 < 0.016 0.001 +/- 0.009 < 0.019 0.13 Cs-137 0.016 +/- 0.011 < 0.020 0.002 +/- 0.010 < 0.014 0.004 +/- 0,012 < 0.017 0.15 Other (Ru-103) -0.002 +/- 0.008 < 0.027 -0.002 +/- 0.011 < 0.056 -0.004 +/- 0.009 < 0.029 0.5 Collection Date 08-22-21 08-28-21 Lab Code EF- 2780 EF- 2781 Type Burbot Burbot K-40 2.53 +/- 0.37 1.88 +/- 0.34 Mn-54 0.012 +/- 0.008 < 0.013 0.013 +/- 0.008 < 0.015 0.13 Fe-59 -0.016 +/- 0.019 < 0.076 -0.013 +/- 0.016 < 0.052 0.26 Co-58 0.005 +/- 0.009 < 0.020 -0.007 +/- 0.009 < 0.019 0.13 Co-60 0.005 +/- 0.010 < 0.015 0.000 +/- 0.009 < 0.012 0.13 Zn-65 -0.011 +/- 0.019 < 0.024 0.002 +/- 0.018 < 0.028 0.26 Cs-134 -0.002 +/- 0.010 < 0.017 -0.001 +/- 0.008 < 0.016 0.13 Cs-137 0.019 +/- 0.012 < 0.022 0.030 +/- 0.017 < 0.019 0.15 Other (Ru-103) 0.007 +/- 0.008 < 0.033 0.003 +/- 0.006 < 0.025 0.5 7-2

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

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

MDC MDC MDC LLD Collection Date 10-22-21 11-26-21 Lab Code EF- 3928 EF* 3929 Type Salmon Lake Trout K-40 3.34 +/- 0.40 2.68 +/- 0.35 Mn-54 0.007 +/- 0.010 < 0.020 0.006 +/- 0.007 < 0.011 0.13 Fe-59 -0.017 +/- 0.021 < 0.084 *0.020 +/- 0.014 < 0.029 0.26 Co-58 0.019 +/- 0.010 < 0.036 *0.002 +/- 0.007 < 0.014 0.13 Co-60 -0.004 +/- 0.012 < 0.015 0.002 +/- 0.009 < 0.015 0.13 Zn-65 -0.032 +/- 0.028 < 0.041 -0.007 +/- 0.019 < 0.016 0.26 Cs-134 *0.010 +/- 0.009 < 0.020 0.006 +/- 0.008 < 0.015 0.13 Cs-137 -0.005 +/- 0.011 < 0.015 0.008 +/- 0.009 < 0.014 0.15 Other (Ru-103) *0.012 +/- 0.010 < 0.073 0.000 +/- 0.006 < 0.024 0.5 Annual Mn-54 0.005 +/- 0.007 Fe-59 *0.009 +/- 0.018 Co-58 0.001 +/- 0.008 Co-60 *0.001 +/- 0.004 Zn-65 *0.009 +/- 0.022 Cs-134 *0.007 +/- 0.010 Cs-137 0.009 +/- 0.011 Other (Ru* 103) 0.000 +/- 0.007 7.3

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

MDC MDC MDC Collection Date 10/19/2021 10/19/2021 10/19/2021 Lab Code ESS- 3453 ESS- 3455 ESS- 3456 LLD Location E-01 E-05 E-06 Be-7 0.126 +/-0.058 < 0.186 0.044 +/- 0.076 < 0.204 0.073 +/- O.Q75 < 0.256 K-40 3.763 +/- 0.335 6. 169 +/- 0.454 8.379 +/- 0.501 Cs-134 -0.004 +/- 0.007 < 0.010 -0.004 +/- 0.009 < 0.019 -0.003 +/- 0.008 < 0.015 0. 15 Cs-137 0.032 +/- 0.015 < 0.013 -0.015 +/- 0.011 < 0.014 0.024 +/- 0.010 < O.Q17 0.15 Tl-208 0.057 +/- O.Q15 0.059 +/- 0.028 0.043 +/- 0.017 Pb-212 0.141 +/- 0.021 0.102 +/- 0.023 0.124 +/- 0.022 Bi-214 0.206 +/- 0.030 0.182 +/- 0.Q38 0.177 +/- 0.034 Ra-226 0.461 +/- 0.198 0.363 +/- 0.182 0.385 +/- 0.215 Ac-228 0.131 +/- 0.054 0.171 +/- 0.087 0.192 +/- 0.062 Annual Mean +/-s.d.

Be-7 0.081 +/- 0.042 K*40 6.10 +/- 2.31 Cs-134 0.00 +/- 0.00 Cs-137 0.014 +/- 0.025 Tl-208 0.05 +/- 0.01 Pb-212 0.12 +/- 0.02 Bi-214 0.19 +/- 0.02 Ra-226 0.40 +/- 0.05 Ac-228 0.16 +/- 0.03 8-1

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

MDC MDC MDC Collection Date 9/23/2021 9/23/2021 9/23/2021 Req.

Lab Code ESO- 3080 ESO- 3081 ESO- 3082 LLD Location E-01 E-02 E-03 Be-7 0.029 +/- 0.09 < 0.22 0.096 +/- 0.14 < 0.37 0.103 +/- 0.11 < 0.26 K-40 17.03 +/- 0.79 15.87 +/- 0.93 19.66 +/- 0.97 Cs-134 -0.005 +/- O.D1 < 0.02 0.001 +/- 0.01 < 0.03 0.001 +/- O.D1 < 0.02 0.15 Cs-137 0.162 +/- 0.03 < 0.03 0.042 +/- 0.02 < 0.03 0.100 +/- 0.10 < 0.03 0.15 Tl-208 0.187 +/- 0.03 0.153 +/-0.04 0.203 +/- 0.04 Pb-212 0.527 +/- 0.04 0.364 +/- 0.05 0.517 +/- 0.05 Bi-214 0.447 +/- 0.05 0.323 +/- 0.06 0.443 +/- 0.06 Ra-226 1.562 +/- 0.30 1.371 +/- 0.42 1.445 +/- 0.53 Ac-228 0.563 +/- 0.08 0.405 +/- 0.11 0.647 +/-0.12 Collection Date 9/23/2021 9/21/2021 9/23/2021 Lab Code ESQ- 3083 ESO- 3084 ESO- 3086 Location E-04 E-06 E-20 Be-7 0.008 +/- 0.10 < 0.32 0.795 +/- 0.32 < 0.28 0.246 +/- 0.13 < 0.30 K-40 18.13 +/- 0.97 13.35 +/- 0.74 16.55 +/- 0.91 Cs-134 0.000 +/- 0.01 < 0.02 0.000 +/- 0.01 < 0.02 -0.020 +/- 0.01 < 0.03 0.15 Cs-137 0.122 +/-0.03 < 0.03 0.429 +/- 0.04 < 0.03 0.025 +/- 0.02 < 0.03 0.15 Tl-208 0.147 +/-0.04 0.063 +/- 0.03 0.206 +/- 0.04 Pb-212 0.412 +/-0.04 0.139 +/- 0.03 0.444 +/- 0.05 Bi-214 0.289 +/- 0.06 0.127 +/- 0.04 0.458 +/- 0.06 Ra-226 0.716 +/- 0.35 0.579 +/- 0.22 0.829 +/- 0.35 Ac-228 0.555 +/- 0.11 0.227 +/- 0.11 0.479+/-0.11 Annual Mean +/- s.d.

Be-7 0.213 +/- 0.30 K-40 16.77 +/- 2.14 Cs-134 -0.004 +/- 0.01 0.15 Cs-137 0.15 +/- 0.15 0.15 Tl-208 0.16 +/- 0.05 Pb-212 0.40 +/- 0.14 Bi-214 0.35 +/- 0.13 Ra-226 1.08 +/- 0.42 Ac-228 0.48 +/- 0.15 9-1

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

MDC MDC MDC Location E-01 E-02 E-03 Collection Date 05-26-21 05-26-21 05-26-21 Lab Code EG- 1542 EG- 1543 EG- 1544 Req. LLD Be-7 0.25 +/-0.14 0.40 +/- 0.12 0.48 +/- 0.21 K-40 5.76 +/- 0.46 4.76 +/-0.41 6.39 +/- 0.52 1-131 -0.006 +/- 0.012 < 0.027 -0.003 +/- 0.007 < 0.031 -0.010 +/-0.009 < 0.019 0.060 Cs-134 0.001 +/- 0.008 < 0.017 -0.003 +/- 0.007 < 0.013 -0.003 +/- 0.008 < 0.015 0.060 Cs-137 0.003 +/- 0.010 < 0.020 -0.002 +/- 0.009 < 0.011 -0.007 +/- 0.009 < 0.009 0.080 Other (Co-60) -0.003 +/- 0.010 < 0.013 0.005 +/- 0.007 < 0.009 0.000 +/- 0.009 < 0.011 0.060 Location E-04 E-06 E-20 Collection Date 05-26-21 05-26-21 05-26-21 Lab Code EG- 1545 EG- 1546 EG- 1547 Req. LLD Be-7 0.35 +/- 0.13 0.55 +/- 0.17 0.29 +/- 0.11 K-40 5.17 +/- 0.41 3.92 +/- 0.39 5.26 +/- 0.37 1-131 -0.001 +/- 0.009 < 0.020 0.008 +/- 0.007 < 0.016 0.011 +/- 0.006 < 0.025 0.060 Cs-134 -0.006 +/- 0.008 < 0.015 -0.009 +/- 0.009 < 0.015 0.000 +/- 0.007 < 0.012 0.060 Cs-137 -0.010 +/- 0.008 < 0.009 0.013 +/- 0.010 < 0.015 0.004 +/- 0.007 < 0.015 0.080 Other (Co-60) -0.004 +/- 0.008 < 0.009 0.002 +/- 0.008 < 0.006 -0.008 +/- 0.008 < 0.008 0.060 10-1

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

MDC MDC MDC Location E-01 E-02 E-03 Collection Date 09-21-21 09-21-21 09-21-21 Lab Code EG- 3074 EG- 3075 EG- 3076 Req. LLD Be-7 7.85 +/- 0.39 4.48 +/- 0.29 7.69 +/- 0.36 K-40 3.52 +/- 0.40 5.41 +/- 0.44 5.85 +/- 0.44 1-131 -0.015 +/- 0.009 < 0.030 -0.001 +/- 0.008 < 0.023 0.002 +/- 0.008 < 0.031 0.060 Cs-134 -0.002 +/- 0.009 < 0.017 -0.005 +/- 0.008 < 0.014 0.004 +/- 0.008 < 0.015 0.060 Cs-137 -0.003 +/- 0.010 < 0.018 0.013 +/- 0.009 < 0.016 0.001 +/- 0.009 < 0.012 0.080 Other (Co-60) -0.011 +/- 0.010 < 0.008 0.005 +/- 0.008 < 0.013 -0.008 +/- 0.010 < 0.016 0.060 Location E-04 E-06 E-20 Collection Date 09-21-21 09-21-21 09-21-21 Lab Code EG- 3077 EG- 3078 EG- 3079 Req.LLD Be-7 7.14 +/- 0.36 6.73 +/- 0.37 1.44 +/- 0.19 K-40 4.92 +/- 0.40 4.04 +/- 0.39 6.08 +/- 0.42 1-131 -0.004 +/- 0.007 < 0.021 0.001 +/- 0.012 < 0.039 -0.015 +/- 0.007 < 0.023 0.060 Cs-134 -0.006 +/- 0.007 < 0.012 0.006 +/- 0.009 < 0.017 -0.002 +/- 0.006 < 0.012 0.060 Cs-137 0.000 +/- 0.009 < 0.013 0.024 +/- 0.011 < 0.020 -0.003 +/- 0.007 < 0.011 0.080 other (Co-60) -0.002 +/- 0.008 < 0.010 -0.003 +/- 0.008 < 0.009 0.001 +/- 0.008 < 0.010 0.060 Be-7 Annual Mean +/- s.d. 3.14 +/- 3.33 K-40 Annual Mean +/- s.d. 5.09 +/- 0.90 1-131 Annual Mean+/- s.d. -0.003 +/- 0.008 Cs-134 Annual Mean+/- s.d. -0.002 +/- 0.004 Cs-137 Annual Mean +/- s.d. 0.003 +/- 0.009 Co-60 Annual Mean +/- s.d. -0.002 +/- 0.005 10-2

POINT BEACH NUCLEAR PLANT Table 11. Ambient Gamma Radiation

LLD/7days: < 1mRITLD 1st. Quarter, 2021 Date Annealed: 12-03-20 Days in the field 88 Date Placed: 01-08-21 Days from Annealing Date Removed: 04-06-21 to Readout: 133 Date Read: 04-15-21 Days in mR/Stnd Qtr Location Field Total mR NetmR (91 da~s) Net mR ~er 7 da~s Indicator E-1 88 20.6 +/- 1.3 12.8 +/- 1.5 13.2 +/-1.6 1.02 +/-0.12 E-2 88 23.0 +/- 1.6 15.1+/-1.7 15.6+/-1.7 1.20 +/-0.13 E-3 88 22.6 +/-1.7 14.8+/-1.7 15.3 +/- 1.8 1.17+/-0.14 E-4 88 20.4+/-1.3 12.5+/-1.4 12.9 +/-1.4 0.99 +/-0.11 E-5 88 22.3 +/- 0.8 14.4 +/- 0.9 14.9 +/- 0.9 1.15 +/- 0.07 E-6 88 19.9 +/- 0.6 12.0 +/-0.7 12.4 +/-0.7 0.95 +/- 0.06 E-7 88 20.2 +/- 0.8 12.3 +/- 0.9 12.7+/-0.9 0.98 +/- 0.07 E-8 88 20.6+/-1.4 12.7+/-1.5 13.2 +/-1.5 1.01 +/-0.12 E-9 88 23.9 +/- 0.4 16.1 +/-0.6 16.6 +/- 0.6 1.28 +/- 0.04 E-12 88 16.7 +/- 0.6 8.8 +/-0.7 9.1 +/- 0.7 0.70 +/- 0.06 E-14 88 21.9+/-0.7 14.0 +/- 0.8 14.5 +/- 0.8 1.12 +/-0.06 E-15 88 22.9 +/- 0.5 15.1 +/- 0.6 15.6 +/-0.7 1.20 +/- 0.05 E-168 88 22.8 +/- 0.7 15.0 +/- 0.8 15.5 +/- 0.8 1.19 +/- 0.08 E-17 88 22.7 +/- 0.9 14.9+/-1.0 15.4 +/-1.0 1.18 +/-0.08 E-18 88 23.9 +/- 0.9 16.0+/-1.0 16.6+/-1.0 1.27 +/- 0.08 E-22 88 21.7+/-1.2 13.8 +/-1.3 14.3+/-1.3 1.10 +/-0.10 E-23 88 22.3 +/- 0.4 14.5 +/- 0.6 15.0 +/-0.6 1.15 +/-0.05 E-24 88 22.7 +/- 1.1 14.8 +/- 1.2 15.3+/-1.3 1.18 +/- 0.10 E-25 88 21.1 +/- 0.6 13.3 +/-0.7 13.7 +/- 0.7 1.06 +/- 0.06 E-268 88 23.2 +/-0.7 15.3 +/- 0.8 15.8 +/- 0.8 1.22 +/-0.06 E-27 88 22.9 +/- 0.3 15.0 +/- 0.5 15.5 +/- 0.6 1.20 +/- 0.04 E-28 89 17.5 +/- 0.5 9.6 +/- 0.7 9.9 +/- 0.7 0.76 +/- 0.05 E-29 88 18.2 +/- 0.8 10.3 +/- 0.9 10.7+/-1.0 0.82 +/- 0.07 E-30 88 20.1+/-1.1 12.3 +/- 1.2 12.7+/-1.2 0.98 +/- 0.10 E-31 88 21.8+/-0.7 13.9 +/-0.8 14.4 +/- 0.8 1.11 +/- 0.06 E-32 89 25.1+/-1.0 17.2 +/-1.1 17.6+/-1.1 1.35 +/- 0.08 E-38 88 21.9+/-1.1 14.0+/-1.2 14.5 +/-1.2 1.12 +/- 0.09 E-39 88 21.5+/-0.6 13.6 +/- 0.7 14.1 +/- 0.7 1.08 +/- 0.06 E-41 88 20.7 +/- 0.5 12.8 +/- 0.7 13.3 +/- 0.7 1.02 +/- 0.05 E-42 88 23.6 +/- 0.9 15.7+/-1.0 16.2+/-1.0 1.25 +/- 0.08 E-43 88 22.0+/-1.3 14.1+/-1.3 14.6+/-1.4 1.12 +/- 0.10 E-44 88 21.2+/-1.0 13.3 +/- 1.1 13.8+/-1.1 1.06 +/- 0.08 Control E-20 90 22.8 +/- 1.3 14.9 +/- 1.3 15.1 +/- 1.3 1.16 +/-0.10 Mean+/-s.d. 21.7+/-1.8 13.8 +/- 1.8 14.2+/-1.9 1.10 +/-0.15 In-Transit Exposure Date Annealed Date Read ITC-1 ITC-2 12-03-20 01-13-21 7.0 +/- 0.5 7.1 +/- 0.3 03-04-21 04-15-21 7.5 +/- 0.3 7.4 +/- 0.4

The CaS0 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 Some TLOs removed on 4/7 or 4/8, as indicated.

11-1

POINT BEACH NUCLEAR PLANT Table 11. Ambient Gamma Radiation a LLD/7days: < 1mR/TLD 2nd Quarter, 2021 Date Annealed: 03-04-21 Days in the field 86 Date Placed: 04-06-21 Days from Annealing Date Removed: 07-01-21 to Readout: 127 Date Read: 07-09-21 Days in mR/Stnd Qtr Location Field Total mR NetmR (91 days) Net mR per 7 days Indicator E-1 86 18.8 +/- 0.3 13.4+/-0.7 14.1+/-0.7 1.09 +/- 0.06 E-2 86 22.1 +/- 1.4 16.7 +/- 1.5 17. 7 +/- 1.6 1.36 +/- 0.12 E-3 86 25.0 +/- 1.5 19.6 +/- 1.6 20.7+/-1.7 1.59 +/- 0.13 E-4 86 20.3 +/- 0.7 14.9+/-1.0 15.8 +/- 1.0 1.21 +/- 0.08 E-5 86 21.5 +/- 0.5 16.0 +/- 0.8 17.0 +/- 0.8 1.31 +/- 0,07 E-6 86 19.3 +/- 1.1 13.9+/-1.2 14.7 +/-1.3 1.13 +/- 0.10 E-7 86 18.8 +/- 0.6 13.4 +/- 0.9 14.2 +/- 0.9 1.09 +/- 0.07 E-8 86 19.4 +/- 0.6 14.0 +/- 0.8 14.8 +/- 0.9 1.14 +/- 0.07 E-9 86 23.3 +/- 0.7 17.8+/-0.9 18.9+/-1.0 1.45 +/- 0.08 E-12 86 17.1 +/-1.3 11.7+/-1.5 12.4+/-1.6 0.95+/-0.12 E-14 86 24.7 +/- 0.4 19.3 +/- 0.7 20.5 +/- 0.8 1.57 +/- 0.06 E-15 86 22.8 +/- 1.4 17.3 +/-1.5 18.4+/-1.6 1.41 +/-0.12 E-168 86 21.9+/-0.8 16.5+/-1.0 17.5 +/- 1.1 1.35 +/- 0.08 E-17 86 22.2 +/- 0.9 16.8 +/- 1.0 17.8 +/- 1.1 1.37 +/- 0.09 E-18 86 25.8 +/- 1.9 20.4 +/- 2.0 21.6+/-2.1 1.66 +/-0.16 E-22 86 21.0 +/- 0.5 15.6 +/- 0.8 16.5 +/- 0.9 1.27 +/- 0.07 E-23 86 23.4 +/- 0.6 17.9 +/- 0.8 19.0 +/- 0.9 1.46 +/- 0.07 E-24 86 22.6+/-1.0 17.2 +/- 1.2 18.1 +/- 1.3 1.40 +/- 0.10 E-25 86 23.8 +/- 0.5 18.4 +/- 0.8 19.5 +/- 0.8 1.50 +/- 0.06 E-268 86 20.3 +/- 0.6 14.9 +/- 0.8 15.8 +/- 0.9 1.22 +/- 0.07 E-27 86 24.1 +/- 0.7 18.7+/-1.0 19.7 +/- 1.0 1.52 +/- 0.08 E-28 85 16.6 +/- 0.6 11.2 +/-0.9 12.0 +/- 0.9 0.92 +/- 0.07 E-29 86 16.5 +/- 0.2 11.1+/-0.6 11.7 +/- 0.7 0.90 +/- 0.05 E-30 86 19.1 +/- 0.8 13.7+/-1.0 14.5+/-1.1 1.11 +/-0.08 E-31 86 22.2+/-1.5 16.8 +/- 1.6 17.8+/-1.7 1.37 +/- 0.13 E-32 85 25.5 +/- 0.9 20.0 +/- 1.1 21.5 +/- 1.2 1.65 +/- 0.09 E-38 86 22.9 +/- 0.7 17.5 +/- 0.9 18.5+/-1.0 1.42 +/- 0.07 E-39 86 23.4 +/- 0.7 17.9 +/- 0.9 19.0 +/- 1.0 1.46 +/- 0.08 E-41 86 21.2 +/- 0.6 15.8 +/- 0.9 16.7 +/- 0.9 1.28 +/- 0.07 E-42 86 24.0 +/- 1.4 18.5+/-1.5 19.6 +/- 1.6 1.51 +/-0.12 E-43 86 24.7+/-1.0 19.2 +/- 1.1 20.4+/-1.2 1.57 +/- 0.09 E-44 86 23.7 +/- 0.4 18.3 +/- 0.7 19.4 +/- 0.8 1.49 +/- 0.06 Control E-20 84 22.2 +/- 0.9 16.8+/-1.1 18.2+/-1.2 1.40 +/- 0.09 Mean+/-s.d. 21.8 +/- 2.5 16.4+/-2.5 17.4 +/-2.7 1.34 +/- 0.21 In-Transit ExQosur e Date Annealed Date Read ITC-1 ITC-2 03-04-21 04-15-21 5.9 +/- 0.3 5.7 +/- 0.4 06-03-21 07-09-21 5.0 +/- 0.3 5.1 +/- 0.2

' The CaS04 :Dy dosimeter cards provide four separate readout areas. Values listed represent the mean and standard deviation of the average of the four readings.

0 Some samples placed on 4/7 or 4/8 as indicated 11-2

POINT BEACH NUCLEAR PLANT Table 11. Ambient Gamma Radiation a LLD/7days: < 1mR/TLD 3rd Quarter, 2021 Date Annealed: 06-03-21 Days in the field 94 Date Placed: 07-01-21 Days from Annealing Date Removed: 10-03-21 to Readout: 126 Date Read: 10-07-21 Days in mR/Stnd Qtr Location Field Total mR NetmR (91 days) Net mR per 7 days Indicator E-1 94 18.9 +/- 1.2 13.9+/-1.3 13.4 +/- 1.3 1.03 +/- 0.10 E-2 94 21.0 +/- 1.3 16.0+/-1.4 15.4+/-1.4 1.19 +/- 0.10 E-3 94 22.5 +/- 1.6 17.5+/-1.7 16.9+/-1.6 1.30 +/-0.12 E-4 94 18.6+/-1.2 13.5+/-1.3 13.1 +/- 1.2 1.01 +/- 0.09 E-5 94 20.9 +/- 0.5 15.8 +/- 0.7 15.3 +/- 0.7 1.18 +/- 0.05 E-6 94 19.0 +/- 0.7 13.9 +/- 0.9 13.5 +/- 0.8 1.04 +/- 0.06 E-7 94 18.3 +/- 1.0 13.3 +/- 1.1 12.9 +/- 1.1 0.99 +/- 0.08 E-8 94 18.2 +/- 0.9 13.2+/-1.1 12.7+/-1.0 0.98 +/- 0.08 E-9 94 22.3 +/- 0.6 17.3 +/- 0.8 16.7 +/- 0.7 1.29 +/- 0.06 E-12 94 14.0 +/- 0.4 9.0 +/- 0.6 8.7 +/- 0.6 0.67 +/- 0.05 E-14 94 20.0 +/- 0.6 14.9 +/- 0.8 14.5 +/- 0.8 1. 11 +/- 0.06 E-15 94 21.7 +/- 0.8 16.7+/-0.9 16.2 +/- 0.9 1.24 +/- 0.07 E-16B 94 20.2 +/- 0.3 15.2 +/- 0.6 14.7 +/- 0.6 1.13 +/- 0.04 E-17 94 17.5 +/- 0.6 12.5 +/- 0.8 12.1 +/- 0.8 0.93 +/- 0.06 E-18 94 23.3 +/- 1.0 18.3+/-1.1 17.7+/-1.0 1.36 +/- 0.08 E-22 94 19.8 +/- 0.9 14.8+/-1.0 14.3+/-1.0 1.10+/-0.07 E-23 94 21.9 +/- 0.6 16.9 +/- 0.7 16.3 +/- 0.7 1.26 +/- 0.06 E-24 94 19.2 +/- 0.8 14.1 +/-1.0 13.7 +/- 0.9 1.05 +/- 0.07 E-25 94 19.5 +/-0.7 14.5 +/- 0.9 14.0 +/- 0.9 1.08 +/- 0.07 E-26B 94 18.5 +/- 0.6 13.5 +/- 0.8 13.1 +/- 0.8 1.00 +/- 0.06 E-27 94 21.5 +/- 0.6 16.5 +/- 0.8 16.0 +/- 0.7 1.23 +/- 0.06 E-28 94 14.6 +/- 0.5 9.6 +/- 0.7 9.2 +/- 0.7 0.71 +/- 0.05 E-29 94 15.5 +/- 0.9 10.5 +/- 1.1 10.1 +/- 1.0 0.78 +/- 0.08 E-30 94 18.1+/-0.9 13.1 +/- 1.0 12.7+/-1.0 0.97 +/- 0.08 E-31 94 21.0 +/- 0.5 15.9 +/- 0.7 15.4 +/- 0.7 1.19 +/- 0.05 E-32 94 24.2 +/- 1.0 19.2+/-1.1 18.6 +/-1.0 1.43 +/- 0.08 E-38 94 21.5+/-1.8 16.5+/-1.9 15.9+/-1.8 1.23 +/- 0.14 E-39 94 20.9 +/- 1.6 15.9+/-1.6 15.4 +/- 1.6 1.18 +/- 0.12 E-41 94 19.8 +/- 0.9 14.8 +/- 1.0 14.3 +/- 1.0 1.10 +/-0.08 E-42 94 22.1 +/-0.7 17.0 +/- 0.9 16.5 +/- 0.9 1.27 +/- 0.07 E-43 94 21.3 +/- 1.3 16.3 +/- 1.4 15.8 +/- 1.4 1.21 +/- 0. 11 E-44 94 19.9 +/- 1.0 14.9 +/- 1.1 14.4 +/- 1.1 1.11+/-0.09 Control E-20 94 19.0 +/- 1.0 14.0 +/- 1.1 13.5 +/- 1.1 1.04 +/- 0.08 Mean+/-s.d. 19.8 +/- 2.3 14.8 +/- 2.3 14.3 +/- 2.2 1.10 +/- 0.18 In-Transit Exposure Date Annealed Date Read ITC-1 .ITC-2 06-03-21 07-09-21 5.0 +/- 0.3 5.1 +/- 0.2 09-07-21 10-07-21 4.7 +/- 0.2 5.3 +/- 0.3

The CaS0 4 :Dy dosimeter cards provide four separate readout areas. Values listed represent the mean and standard deviation of the average of the four readings.

11-3

POINT BEACH NUCLEAR PLANT Table 11. Ambi Ent Gamma Radi ai on a LLD/7days: < 1mR/TLD 4th Quarter, 2021 Date Annealed: 09-07-21 Daysi nthe field 93 Date Placed: 10-03-21 Days from Annealing Date Removed: 01-04-22 to Readout: 122 Date Read: 01-07-22 Daysi n mR/Stnd Qtr Location Field Total mR NetmR (91 days) Net mR per 7 days I ndi cater E-1 93 20.1 +/- 0.3 14.4 +/-0.7 14.1 +/- 0.6 1.09 +/- 0.05 E-2 93 23.7 +/- 0.8 18.0 +/- 1.0 17.6+/-1.0 1.36 +/- 0.07 E-3 93 27.1 +/-1.2 21.4 +/- 1.4 21.0+/-1.3 1.61 +/- 0.10 E-4 93 22.5 +/- 0.8 16.9+/-1.0 16.5 +/- 1.0 1.27 +/- 0.08 E-5 93 23.7 +/- 0.3 18.0 +/- 0.7 17.6 +/-0.7 1.35 +/- 0.05 E-6 93 20.3 +/- 1.2 14.6+/-1.3 14.3+/-1.3 1.10+/-0.10 E-7 93 18.7 +/- 0.7 13.1+/-0.9 12.8 +/- 0.9 0.98 +/- 0.07 E-8 93 21.4 +/- 1.0 15.7 +/- 1.1 15.4 +/- 1.1 1.18+/-0.08 E-9 93 25.3 +/- 0.7 19.6 +/- 0.9 19.2 +/- 0.9 1.47 +/- 0.07 E-12 93 18.4+/-1.5 12.7 +/- 1.6 12.4 +/- 1.5 0.96 +/- 0.12 E-14 93 22.7+/-1.6 17.1 +/-1.7 16.7+/-1.7 1.28+/-0.13 E-15 93 22.1 +/-1.4 16.4 +/- 1.5 16.1 +/- 1.5 1.23 +/- 0.11 E-168 93 24.6+/-1.9 18.9 +/- 2.0 18.5+/-1.9 1.42+/-0.15 E-17 93 23.7+/-1.0 18.0 +/- 1.1 17.7+/-1.1 1.36 +/- 0.08 E-18 93 28.5 +/- 1.9 22.8 +/- 2.0 22.3+/-1.9 1.72 +/- 0.15 E-22 93 23.2 +/- 0.7 17.6 +/- 0.9 17.2 +/- 0.9 1.32 +/- 0.07 E-23 93 25.4 +/- 0.5 19.7 +/- 0.8 19.3 +/- 0.7 1.48 +/- 0.06 E-24 93 24.2+/-1.0 18.5+/-1.2 18.1+/-1.2 1.39 +/- 0.09 E-25 93 25.7 +/- 0.5 20.1 +/- 0.8 19.6 +/- 0.7 1.51 +/- 0.06 E-268 93 19.9 +/- 0.4 14.2 +/- 0.7 13.9 +/- 0.7 1.07 +/- 0.05 E-27 93 25.3 +/- 0.8 19.6+/-1.0 19.2+/-1.0 1.48 +/- 0.08 E-28 93 15.5 +/- 0.8 9.8 +/- 1.0 9.6+/-1.0 0.74 +/- 0.07 E-29 93 15.2 +/- 0.2 9.5 +/- 0.6 9.3 +/- 0.6 0.71 +/- 0.05 E-30 93 20.9 +/- 0.9 15.2 +/- 1.1 14.9+/-1.1 1.15+/-0.08 E-31 93 24.2 +/- 1.3 18.5 +/-1.5 18.1 +/-1.4 1.39 +/- 0.11 E-32 93 23.8 +/- 0.8 18.2+/-1.0 17.8 +/- 1.0 1.37 +/- 0.07 E-38 93 24.3 +/- 0.6 18.6 +/- 0.8 18.2 +/- 0.8 1.40 +/- 0.06 E-39 93 25.2 +/- 0.9 19.5+/-1.1 19.1 +/- 1.1 1.47 +/- 0.08 E-41 93 22.5 +/- 0.7 16.8 +/- 0.9 16.5 +/- 0.9 1.27 +/- 0.07 E-42 93 26.1 +/- 1.3 20.5 +/- 1.5 20.0+/-1.4 1.54 +/- 0.11 E-43 93 26.8+/-1.0 21.1 +/- 1.1 20.7+/-1.1 1.59 +/- 0.08 E-44 93 24.9 +/- 0.5 19.2 +/- 0.8 18.8 +/- 0.7 1.45 +/- 0.06 Control E-20 93 24.6+/-1.1 18.9+/-1.3 18.5 +/- 1.3 1.42+/-0.10 Mean+/-s.d. 23.0 +/- 3.1 17.4 +/-3.1 17.0 +/- 3.0 1.31 +/- 0.24 IrrTransi tExposure Date Annealed Date Read ,ITC-1 ITC-2 09-07-21 10-07-21 4.7 +/- 0.2 5.3 +/- 0.3 12-06-21 01-07-22 6.3 +/- 0.4 6.5 +/- 0.3

The CaS0 4 :0y dosimeter cards provide four separate readout areas. Values listed represent the mean and standard deviation of the average of the four readings.

Annual I ndi catorMean+/-s.d. 21.6 +/- 2.7 15.6 +/- 2.8 15.7 +/- 2.9 1.2 +/- 0.2 Annual Control Mean+/-s.d. 22.1 +/- 2.3 16.1+/-2.2 16.3 +/- 2.4 1.3 +/- 0.2 Annual I ndi cator/Cmtrol Mean+/-s.d. 21.6 +/- 2.7 15.6 +/- 2.8 15.7 +/- 2.9 1.2 +/- 0.2 11-4

POINT BEACH NUCLEAR PLANT Table 12. Groundwater Tritium Monitoring Program (Monthly Collections)

Units= Ci/L Intermittent Streams Samele ID GW-01 GW-02 Collection Collection Dale Lab Code Tritium MDC Dale Lab Code Tritium MDC 3 3 01-21*21 NS 01-21-21 NS 3

02-17-21 NS 02-17-21 NS" 03-25*21 EWW-778 11 +/- 79 < 159 03-25-21 EWW-779 320 +/- 95 < 159 04-23-21 EWW-1198 86 +/- 80 < 159 04-23-21 EWW-1199 289 +/- 90 < 159 05-19-21 EWW-1484 201 +/- 86 < 158 05-19-21 EWW-1485 245 +/- 88 < 158 06-18-21 EWW-1904 153 +/- 83 < 158 06-18*21 NFb 07*21*21 EWW-2327 123 +/- 82 < 156 07-21-21 EWW-2328 310 +/- 92 < 156 08-19-21 EWW-2641 87 +/- 78 < 157 08-19-21 EWW-2643 124 +/- 80 < 157 09-16-21 EWW-2988 142 +/- 84 < 161 09-16-21 EWW-2990 186 +/- 86 < 161 10-19-21 EWW-3461 136 +/- 83 < 163 10-19*21 EWW-3462 185 +/- 86 < 163 11-18-21 EWW-3901 162 +/- 86 < 161 11-18-21 EWW-3903 252 +/- 91 < 161 12-16-21 EWW-4090 59 +/- 91 < 167 12*16-21 EWW-4091 122 +/- 94 < 167 Mean+/- s.d. 116 +/- 56 Mean+/- s.d. 226 +/- 75 Sample ID GW-03 GW-17 Collection Collection Dale Lab Code Tritium MDC Dale Lab Code Tritium MDC 3

01-21-21 NS 01-21-21 NS 3 3

02-17-21 NS" 02-17-21 NS 03-25-21 EWW-780 38 +/- 81 < 159 03-25-21 EWW-782 255 +/- 92 < 159 04-23-21 EWW-1200 118 +/- 81 < 159 04-23-21 EWW-1202 186 +/- 85 < 159 05-19-21 EWW-1487 100 +/- 80 < 158 05-19-21 EWW-1491 120 +/- 81 < 158 06*18-21 EWW-1905 100 +/- 80 < 158 06-18-21 NFb 07-21-21 EWW-2329 107 +/- 81 < 156 07-21-21 EWW-2331 208 +/- 87 < 156 08-19-21 EWW-2644 50 +/- 76 < 157 08-19-21 NFb 09-16-21 EWW-2991 138 +/- 84 < 161 09*16-21 NFb 10*19-21 EWW-3463 136 +/- 83 < 163 10-19-21 NFb 11-18-21 EWW-3904 118 +/- 84 < 161 11-18-21 EWW-3906 189 +/- 88 < 161 12*16*21 EWW-4092 41 +/- 90 < 167 12-16-21 EWW-4094 301 +/- 102 < 167 Mean+/- s.d. 95 +/- 38 Mean+/- s.d. 210 +/- 62 Wells Sam.e.le ID GW-04 (EiC Well Collection Dale Lab Code Tritium MDC 01-21-21 EWW-180 -43 +/- 71 < 160 02-17-21 EWW-400 .44 +/- 72 < 161 03-25-21 EWW-781 -45 +/- 76 < 159 04-23-21 EWW-1201 25 +/- 76 < 159 05-19-21 EWW-1488 -13 +/- 73 < 158 06-17-21 EWW-1906 87 +/- 80 < 158 07-21-21 EWW-2330 61 +/- 79 < 156 08-19-21 EWW-2645 -5 +/- 73 < 157 09*16-21 EWW-2992 -6 +/- 75 < 161 10-20-21 EWW-3464 65 +/- 79 < 163 11-18-21 EWW-3905 58 +/- 81 < 161 12-16-21 EWW-4093 108 +/- 93 < 167 Mean+/- s.d. 21 +/- 54

=

"NS" No sample; creeks frozen. Recount =40 +/- 102 pCi/l, MDC < 165

=

b "NF" No flow.

'Recount= -11+/-89 pCilL, MDC <171 12-1

POINT BEACH NUCLEAR PLANT Table 12. Groundwater Tritium Monitoring Program (Monthly Collections)

Units= Gill Beach Drains Sam le ID S-1 S-3 Collection Collection Date Lab Code Tritium MOC Dale Lab Code Tritium MOC 3

01-06-21 ESW- 63 435 +/- 99 < 166 01-06-21 NF 02-04-21 NF 3 02-04-21 NF a 03-01-21 NF 3 03-01-21 ESW- 472 428 +/- 97 < 160 04-07-21 ESW- 922 307 +/- 93 < 160 04-07-21 ESW- 924 311 +/- 93 < 160 05-05-21 ESW- 1332 221 +/- 86 < 158 05-05-21 ESW- 1334 325 +/- 91 < 158 06-02-21 ESW- 1659 334 +/- 93 < 161 06-02-21 ESW- 1660 331 +/- 93 < 161 07-08-21 ESW- 2180 276 +/- 90 < 156 07-08-21 ESW- 2182 426 +/- 98 < 156 08-04-21 EWW-2484 246 +/- 89 < 161 08-04-21 ESW- 2485 410 +/- 97 < 161 08-31-21 EWW-2769 145 +/- 84 < 163 08-31-21 ESW- 2770 310 +/- 93 < 163 10-05-21 EWW-3260 191 +/- 87 < 159 10-05-21 ESW- 3261 496 +/- 102 < 159 11-02-21 EWW-3673 153 +/- 84 < 162 11-02-21 ESW- 3674 270 +/- 90 < 162 12-02-21 EWW-3968 176 +/- 85 < 162 12-02-21 EWW-3969 275 +/- 91 < 162 Mean+/- s.d. 248 +/- 91 Mean+/- s.d. 358 +/- 76 Sam le ID S-7 S-8 Collection Collection Dale Lab Code Tritium MOC Dale Lab Code Tritium MOC 3 3 01-06-21 NF 01-06-21 NF 0 3 02-04-21 NF 02-04-21 NF 3 0 03-01-21 NF 03-01-21 NF 04-07-21 NF" 04-07-21 NF" 3

05-05-21 NF 05-05-21 NF" 06-02-21 NF" 06-02-21 NF" 3

07-08-21 NF" 07-08-21 NF 08-04-21 NF 0

08-04-21 NF 3 08-31-21 NF' 08-31-21 NF 3 0

11-02-21 NF' 11-02-21 NF 0

12-02-21 NF 12-02-21 NF" Mean+/- s.d. Mean+/- s.d.

Sam le ID S-9 S-10 Collection Collection Date Lab Code Tritium MOC Dale Lab Code Tritium MOC 3 3 01-06*21 NF 01-06-21 NF 02-04-21 NFa 02-04-21 NF' 3

03-01-21 NF 03*01-21 NF' 04-07-21 NF' 04-07-21 NF' 0

05-05-21 NF 05-05-21 NF' 06-02-21 NF 0 06-02*21 NF' 07-08-21 NF' 07-08-21 NF' 08-04-21 NF' 08-04-21 NF' 3

08-31-21 NF 08-31-21 NF' 0

10-05-21 NF 10-05-21 NF' 11-02-21 NF' 11-02-21 NF' 0

12-02-21 NF 12-02-21 NF' Mean+/- s.d. Mean+/- s.d.

a "NF" =No flow.

12-2

POINT BEACH NUCLEAR PLANT Table 12. Groundwater Tritium Monitoring Program (Monthly Collections)

Units= Ci/L Beach Drains (cont.)

Sam le ID S-12 S-13 Collection Collection Date Lab Code Tritium MOC Date Lab Code Tritium MOC 01-06-21 NF" 01-06-21 NF" 02-04-21 NF" 02-04-21 NF" 03-01-21 NF" 03-01-21 NF" 04-07-21 NF" 04-07-21 NF" 05-05-21 NF" 05-05-21 NF" 06-02-21 NF" 06-02-21 NF" 07-08-21 NF" 07-08-21 NF" 08-04-21 NF" 08-04-21 NF" 08-31-21 EWW-2772 246 +/- 89 < 163 08-31-21 NF" 10-05-21 NF 0 10-05-21 NF" 11-02-21 EWW-3675 270 +/- 90 < 162 11-02-21 NF" 12-02-21 NF" 12-02-21 NF" Mean+/- s.d. 258 +/- 17 Mean+/- s.d.

Sample ID U2 Fa ade Subsurface Drain Sump Collection Date Lab Code Tritium MOC 01-31*21 EW* 471 1185 +/- 127 < 161 02-28*21 EW- 685 1409 +/- 135 < 162 03-31-21 EW- 1251 1605 +/- 148 < 160 04-30-21 EW- 1413 1437 +/- 139 < 158 05-31-21 EW- 2025 1174 +/- 131 < 161 06-30-21 EW- 2325 806 +/- 114 < 157 07-31-21 EW- 2573 6496 +/- 257 < 164 08-31-21 EW- 3072 2915 +/- 180 < 161 09-30-21 EW- 3256 2714 +/- 175 < 159 10-31-21 EW* 3898 2654 +/- 175 < 162 11-30-21 EW- 4132 2672 +/- 175 < 157 12-31-21 EW* 4389 2439 +/- 169 163 Mean+/- s.d. 2292 +/- 1514 a "NF" = No now.

12-3

POINT BEACH NUCLEAR PLANT Beach Drains Units: = pCi/L Gamma isotopic analysis Location S-1 S-3 S-7 S-8 Collection Date 01-06-21 01-06-21 01-06-21 01-06-21 Lab Code EW- 63 MDC NF" MDC NF" MDC NF" MDC Be-7 7.6 +/- 20.3 < 43.2 Mn-54 0.4 +/- 2.0 < 3.3 Fe-59 -0.2 +/- 3.5 < 5.7 Co-58 -2.6 +/- 2.0 < 2.4 Co-60 -0.4 +/- 2.1 < 3.4 Zn-65 -1.2 +/-4.4 < 7.8 Zr-Nb-95 1.5 +/- 1.9 < 4.0 Cs-134 0.6 +/- 2.2 < 3.8 Cs-137 2.3 +/- 2.5 < 4.4 Ba-La-140 0.7 +/- 1.8 < 4.9 Location S-9 S-10 S-12 S-13 Collection Date 01-06-21 01-06-21 01-06-21 01-06-21 Lab Code NF" MDC NF" MDC NF" MDC NF" MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-1 S-3 S-7 S-8 Collection Date 02-04-21 02-04-21 02-04-21 02-04-21 Lab Code NF" MDC NF" MDC NF" MDC NF" MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140

"NF"= No flow.

12-4

POINT BEACH NUCLEAR PLANT Beach Drains (cont.)

Units: = pCi\L Gamma isotopic analysis Location S-9 S-10 S-12 S-13 Collection Date 02-04-21 02-04-21 02-04-21 02-04-21 Lab Code NFa MDC NFa MDC NF" MDC NFa MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-1 S-3 S-7 S-8 Collection Date 03-01-21 03-01-21 03-01-21 03-01-21 Lab Code NFa MDC EW- 472 MDC NFa MDC NF" MDC Be-7 17.6 +/- 19.2 < 37.7 Mn-54 -1.3+/-1.9 < 2.1 Fe-59 -0.6 +/- 3.8 < 4.0 Co-58 -0.2 +/- 1.8 < 2.7 Co-60 0.2 +/- 2.3 < 2.4 Zn-65 1.3 +/- 3.3 < 3.7 Zr-Nb-95 0.3 +/- 2.0 < 2.7 Cs-134 0.3 +/- 2.1 < 3.7 Cs-137 0.5 +/- 2.6 < 4.7 Ba-La-140 2.0 +/- 2.6 < 6.1 Location S-9 S-10 S-12 S-13 Collection Date 03-01-21 03-01-21 03-01-21 03-01-21 Lab Code NF" MDC NF" MDC NF" MDC NFa MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 a "NF"= No flow.

12-5

POINT BEACH NUCLEAR PLANT Beach Drains (cont.)

Units: ::: pCi\L Gamma isotopic analysis Location S-1 S-3 S-7 S-8 Collection Date 04-07-21 04-07-21 04-07-21 04-07-21 Lab Code EW- 922 MDC EW- 924 MDC NF" MDC NF" MDC Be-7 -1.9 +/- 13.6 < 41.6 -23.6 +/- 21.0 < 38.5 Mn-54 0.1 +/- 1.6 < 2.1 0.0 +/- 2.3 < 4.4 Fe-59 1.1 +/- 2.8 < 4.8 0.4 +/- 4.0 < 4.9 Co-58 -0.1 +/- 1.3 < 2.4 -0.2 +/- 2.0 < 2.8 Co-60 -0.8 +/- 1.8 < 1.8 0.6 +/- 1.9 < 2.2 Zn-65 0.9 +/- 2.6 < 4.1 1.4 +/-4.8 < 6.7 Zr-Nb-95 -1.0 +/- 1.8 < 3.7 -2.3 +/- 2.4 < 3.1 Cs-134 -0.1 +/- 1.6 < 3.1 0.5 +/- 2.1 < 3.8 Cs-137 0.9 +/- 1.7 < 3.3 -0.9 +/- 2.4 < 2.9 Ba-La-140 1.8 +/- 1.6 < 3.1 -0.4 +/- 1.9 < 4.5 Location S-9 S-10 S-12 S-13 Collection Date 04-07-21 04-07-21 04-07-21 04-07-21 Lab Code NF" MDC NF" MDC NF" MDC NF" MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-1 S-3 S-7 S-8 Collection Date 05-05-21 05-05-21 05-05-21 05-05-21 Lab Code EW- 1332 MDC EW- 1334 MDC NF" MDC NF" MDC Be-7 -0.7 +/- 4.8 < 13.0 -2.2 +/- 7.2 < 20.9 Mn-54 -0.6 +/- 0.6 < 1.3 -1.2 +/- 0.7 < 1.1 Fe-59 -2.1 +/- 1.1 < 2.8 -1.0 +/- 1.4 < 1.9 Co-58 0.5 +/- 0.6 < 1.3 0.1+/-0.7 < 1.8 Co-60 0.2 +/- 0.7 < 1.2 -1.2 +/-0.7 < 0.9 Zn-65 -1.4 +/- 1.1 < 1.8 0.6 +/- 1.6 < 2.4 Zr-Nb-95 -0.1 +/- 0.6 < 1.6 0.1 +/- 0.8 < 2.4 Cs-134 0.0 +/- 0.6 < 1.2 -0.7 +/- 0.7 < 1.6 Cs-137 0.9 +/- 0.7 < 1.4 0.0 +/- 0.9 < 1.8 Ba-La-140 0.9 +/- 0.7 < 5.4 -0.5 +/- 0.8 < 6.2 a "NF"::: No flow.

12-6

POINT BEACH NUCLEAR PLANT Beach Drains (cont.)

Units: =pCi\L Gamma isotopic analysis Location S-9 S-10 S-12 S-13 Collection Date 05-05-21 05-05-21 05-05-21 05-05-21 0

Lab Code NF 0 MDC NF 0 MDC NF MDC NF 0 MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-1 S-3 S-7 S-8 Collection Dale 06-02-21 06-02-21 06-02-21 06-02-21 0 0 Lab Code EW- 1659 MDC EW- 1660 MDC NF MDC NF MDC Be-7 -27.3 +/- 24.8 < 48.7 13.7 +/- 21.3 < 53.2 Mn-54 -0.4 +/- 2.6 < 3.8 -1.3 +/- 2.5 < 3.6 Fe-59 2.4 +/- 4.5 < 5.1 -2.0 +/- 5.2 < 8.9 Co-58 -0.4 +/- 2.4 < 3.9 0.9 +/- 2.5 < 2.2 Co-60 -0.7 +/- 2.3 < 3.6 -0.4 +/- 2.6 < 3.6 Zn-65 -0.6+/-5.1 < 6.4 1.7 +/- 5.1 < 7.7 Zr-Nb-95 -3.4 +/- 2.6 < 3.1 -0.1 +/- 2.7 < 5.2 Cs-134 -0.6 +/- 2.8 < 4.5 0.5 +/- 2.6 < 5.2 Cs-137 -0.6 +/- 2.9 < 4.1 -0.5 +/- 3.2 < 5.2 Ba-La-140 -3.7 +/- 2.4 < 4.6 0.5 +/- 3.0 < 2.7 Location S-9 S-10 S-12 S-13 Collection Date 06-02-21 06-02-21 06-02-21 06-02-21 Lab Code NF" MDC NF" MDC NF 0 MDC NF 0 MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 a "NF" =No flow.

12-7

POINT BEACH NUCLEAR PLANT Beach Drains (cont.)

Units: =pCi\L Gamma isotopic analysis Location S-1 S-3 S-7 S-8 Collection Date 07-08-21 07-08-21 07-08-21 07-08-21 Lab Code EW- 2180 MDC EW- 2181 MDC NF" MDC NF" MDC Be-7 -3.8 +/- 15.9 < 32.9 -1.1 +/- 10.7 < 24.8 Mn-54 0.3 +/- 1.4 < 2.0 -0.7 +/- 1.3 < 1.6 Fe-59 -0.3 +/- 2.5 < 2.6 -1.2+/-2.3 < 2.4 Co-58 -0.6 +/- 1.4 < 2.3 -1.5+/-1.1 < 1.1 Co-60 -1.4 +/- 1.4 < 1.6 0.5 +/- 1.3 < 1.8 Zn-65 -2.3 +/- 3.6 < 4.0 -2.2 +/- 2.5 < 3.8 Zr-Nb-95 -0.8 +/- 1.7 < 2.6 -0.6 +/- 1.2 < 2.2 Cs-134 -0.8 +/- 1.7 < 3.4 -0.1+/-1.5 < 2.6 Cs-137 -0.8 +/- 1.8 < 1.8 1.1 +/- 1.4 < 2.9 Ba-La-140 -2.5 +/- 1.8 < 6.2 -1.9 +/- 1.4 < 2.7 Location S-9 S-10 S-12 S-13 Collection Date 07-08-21 07-08-21 07-08-21 07-08-21 Lab Code NF" MDC NF" MDC NF" MDC NF" MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-1 S-3 S-7 S-8 Collection Date 08-04-21 MDC 08-04-21 MDC 08-04-21 MDC 08-04-21 MDC Lab Code EW- 2484 EW- 2485 NF" NF" Be-7 11.6 +/- 13.8 < 25.4 -9.7 +/- 9.7 < 23.7 Mn-54 0.2 +/- 1.3 < 2.2 0.6 +/- 1.0 < 1.5 Fe-59 -3.5 +/- 2.9 < 5.2 -0.9 +/- 1.7 < 2.2 Co-58 -0.6 +/- 1.3 < 2.5 0.7 +/- 1.3 < 2.2 Co-60 0.7 +/- 1.5 < 1.8 -0.4 +/- 1.2 < 1.5 Zn-65 1.3 +/- 2.6 < 4.5 -2.7 +/- 2.5 < 4.6 Zr-Nb-95 -1.5 +/- 1.4 < 2.8 -1.3 +/- 1.4 < 2.5 Cs-134 1.4 +/- 1.4 < 3.0 0.4 +/- 1.2 < 2.4 Cs-137 3.4 +/- 1.9 < 2.5 0.8 +/- 1.6 < 3.3 Ba-La-140 -4.7 +/- 1.5 < 3.2 0.3 +/- 1.6 < 3.0

"NF" = No flow.

12-8

POINT BEACH NUCLEAR PLANT Beach Drains (cont.)

Units: = pCi\L Gamma isotopic analysis Location S-9 S-10 S-12 S-13 Collection Date 08-04-21 08-04-21 08-04-21 08-04-21 Lab Code NF" MDC NF" MDC NF" MDC NF" MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-1 S-3 S-7 S-8 Collection Date 08-31-21 08-31-21 08-31-21 08-31-21 Lab Code EW- 2769 MDC EW- 2770 MDC NF" MDC NF" MDC Be-7 6.0 +/- 16.5 < 35.8 -3.0 +/- 14.6 < 28.8 Mn-54 -0.6 +/- 2.2 < 2.3 0.2 +/- 2.1 < 2.6 Fe-59 2.2 +/- 3.5 < 6.0 1.8 +/- 3.5 < 6.6 Co-58 -0.1 +/- 1.9 < 2.8 -1.5+/-1.6 < 2.0 Co-60 -2.7 +/- 2.1 < 2.4 2.1 +/- 2.3 < 3.5 Zn-65 0.1+/-4.1 < 5.3 2.4 +/- 3.7 < 6.7 Zr-Nb-95 -3.8 +/- 2.3 < 4.2 -4.6 +/- 2.3 < 2.8 Cs-134 -0.9 +/- 1.9 < 3.5 1.8 +/- 2.2 < 4.1 Cs-137 -1.1 +/- 2.1 < 3.2 0.2 +/- 2.1 < 3.3 Ba-La-140 1.1 +/- 2.2 < 2.3 0.4 +/- 2.4 < 5.5 Location S-9 S-10 S-12 S-13 Collection Date 08-31-21 08-31-21 08-31-21 08-31-21 Lab Code NF* MDC NF" MDC EW- 2772 MDC NFa MDC Be-7 0.2 +/- 22.1 < 37.6 Mn-54 1.5 +/-2.7 < 4.4 Fe-59 -0.2 +/- 5.2 < 10.0 Co-58 -3.0 +/- 2.3 < 2.3 Co-60 -2.3 +/- 2.8 < 2.5 Zn-65 -7.8 +/- 6.6 < 8.9 Zr-Nb-95 0.0 +/- 3.0 < 4.9 Cs-134 -1.5 +/- 2.5 < 4.9 Cs-137 2.7 +/- 2.8 < 5.5 Ba-La-140 -1.1 +/- 3.4 < 5.6 a "NF"= No flow.

12-9

POINT BEACH NUCLEAR PLANT Beach Drains (cont.)

Units: = pCi\L Gamma isotopic analysis Location S-1 S-3 S-7 S-8 Collection Date 10-05-21 10-05-21 10-05-21 10-05-21 Lab Code EW- 3260 MDC EW- 3261 MDC NF" MDC NF" MDC Be-7 -0.6 +/- 9.6 < 20.6 7.5 +/- 8.0 < 16.2 Mn-54 0.1 +/- 1.2 < 1.4 -0.4 +/- 0.9 < 1.2 Fe-59 -0.7 +/- 2.0 < 4.9 -0.1 +/- 1.8 < 4.0 Co-58 0.1 +/- 1.0 < 1.4 -0.5 +/- 1.0 < 1.8 Co-60 0.9 +/- 1.1 < 1.8 -0.4 +/- 1.0 < 1.6 Zn-65 0.6 +/- 2.2 < 3.2 -0.1 +/- 1.8 < 2.9 Zr-Nb-95 0.8 +/- 1.2 < 3.0 -0.8 +/- 1.0 < 2.2 Cs-134 -0.2 +/- 1.2 < 2.2 -0.5 +/- 1.0 < 1.9 Cs-137 0.9 +/- 1.3 < 2.5 -0.6 +/- 1.1 < 1.2 Ba-La-140 -0.9 +/- 1.4 < 6.9 -0.3 +/- 1.3 < 8.2 Location S-9 S-10 S-12 S-13 Collection Date 10-05-21 10-05-21 10-05-21 10-05-21 Lab Code NF" MDC NF" MDC NF" MDC NF" MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 Location S-1 S-3 S-7 S-8 MDC MDC MDC MDC Collection Date 11-02-21 11-02-21 11-02-21 11-02-21 Lab Code EW- 3673 EW- 3674 NF" NF" Be-7 -4.4 +/- 7.0 < 15.6 -3.8 +/- 4.8 < 14.3 Mn-54 -0.2 +/- 0.7 < 1.3 0.9 +/- 0.5 < 1. 1 Fe-59 -0.4 +/- 1.4 < 2.1 -1.7 +/-1.1 < 3.3 Co-58 0.0 +/- 0.7 < 1.2 -0.2 +/- 0.6 < 1.1 Co-60 0.0 +/- 0.7 < 1.4 -0.7 +/- 0.7 < 0.9 Zn-65 -2.0 +/- 1.5 < 2.3 0.1 +/- 1.1 < 2.3 Zr-Nb-95 -2.4 +/- 0.8 < 2.7 -1.2 +/- 0.6 < 2.0 Cs-134 -0.7 +/- 0.7 < 1.6 0.0 +/- 0.6 < 1. 1 Cs-137 -0.8 +/- 0.8 < 1.0 0.5 +/- 0.7 < 1.4 Ba-La-140 0.5 +/- 0.8 < 11.6 -3.9 +/- 2.0 < 11.7 a "NF" = No flow.

12-10

POINT BEACH NUCLEAR PLANT Beach Drains (cont.)

Units: "' pCi\L Gamma isotopic analysis Location S-9 S-10 S-12 S-13 Collection Date 11-02-21 11-02-21 11-02-21 11-02-21 Lab Code NF" MDC NF" MDC MDC NF" MDC Be-7 5.0 +/- 8.0 < 24.2 Mn-54 -0.5 +/- 0.9 < 1.7 Fe-59 1.5 +/- 1.6 < 6.0 Co-58 -0.2 +/- 0.8 < 1.9 Co-60 0.2 +/- 0.9 < 1.4 Zn-65 -1.8+/-1.9 < 3.4 Zr-Nb-95 -0.7 +/- 0.8 < 3.6 Cs-134 -0.1 +/- 0.9 < 1.7 Cs-137 -0.2 +/- 0.9 < 1.7 Ba-La-140 -7.4 +/- 1.0 < 9.5 Location S-1 S-3 S-7 S-8 Collection Date 12-02-21 12-02-21 12-02-21 12-02-21 Lab Code EW- 3968 MDC EW- 3969 MDC NF" MDC NF" MDC Be-7 12.7 +/- 22.0 < 43.4 13.7 +/- 21.1 < 42.4 Mn-54 2.1+/-2.4 < 3.8 1.3 +/- 2.0 < 3.4 Fe-59 1.6 +/- 3.7 < 7.3 -1.5+/-4.2 < 7.7 Co-58 0.8 +/- 2.0 < 4.0 -1.4 +/- 2.0 < 2.5 Co-60 -1.7 +/- 2.6 < 1.9 0.2 +/- 3.0 < 4.3 Zn-65 -1.7 +/- 5.3 < 4.9 3.1 +/- 4.3 < 7.6 Zr-Nb-95 0.8 +/- 2.4 < 4.7 0.4 +/- 2.5 < 4.8 Cs-134 -0.6 +/- 2.5 < 4.5 -1.0+/-2.3 < 4.3 Cs-137 -0.2 +/- 2.4 < 3.3 0.3 +/- 2.6 < 4.1 Ba-La-140 -0.4 +/- 2.4 < 3.1 0.7 +/- 2.4 < 3.3 Location S-9 S-10 S-12 S-13 Collection Date 12-02-21 12-02-21 12-02-21 12-02-21 Lab Code NF" MDC NF" MDC NF" MDC NF" MDC Be-7 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-Nb-95 Cs-134 Cs-137 Ba-La-140 "NF" := No flow.

12-11

POINT BEACH NUCLEAR PLANT Table 12. Groundwater Tritium Monitoring Program (Quarterly Collections)

Units= Ci/L Quarterly Wells Sam12le ID GW-05 (WH 6 Weill GW-06 iSBCC Weill Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-21-21 EWW- 181 -7 +/- 74 < 160 01-21-21 EWW- 182 22 +/- 75 < 160 04-16-21 EWW- 1064 16 +/- 76 < 159 04-16-21 EWW- 1065 -11 +/- 74 < 159 07-27-21 EWW- 2333 24 +/- 76 < 156 07-21-21 EWW- 2334 51 +/- 78 < 156 10-12-21 EWW- 3439 -43 +/- 73 < 163 10-12-21 EWW- 3440 1 +/- 76 < 163 Mean+/- s.d. -3 +/- 30 Mean+/- s.d. 16 +/- 27 Sam12le ID GW-11 (MW-11 GW-12iMW-2)

Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-14-21 EWW- 215 52 +/- 77 < 160 01-14-21 EWW- 216 -32 +/- 72 < 160 05-14-21 EWW- 1560 76 +/- 82 < 165 05-14-21 EWW- 1561 -63 +/- 74 < 165 07-22-21 EWW- 2476 136 +/- 83 < 162 07-22-21 EWW- 2477 -2 +/- 75 < 162 10-17-21 EWW- 3499 1 +/- 76 < 163 10-17-21 EWW- 3500 47 +/- 78 < 163 Mean+/- s.d. 66 +/- 56 Mean+/- s.d. -13 +/- 47 Sam.12.le ID GW-13 iMW-61 GW-14A iMW-05A Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-14-21 EWW- 217 43 +/- 77 < 160 01-14-21 EWW- 218 128 +/- 82 < 160 05-14-21 EWW- 1562 34 +/- 80 < 165 05-14-21 EWW- 1563 155 +/- 86 < 165 07-22-21 EWW- 2478 19 +/- 76 < 162 07-22-21 EWW- 2479 123 +/- 82 < 162 10-17-21 EWW- 3501 164 +/- 85 < 163 10-17-21 EWW- 3502 166 +/- 85 < 163 Mean+/- s.d. 65 +/- 67 Mean+/- s.d. 143 +/- 21 Sam.12.le ID GW-15A (MW-4) GW-158 iMW-4)

Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-14-21 EWW- 219 115 +/- 81 < 160 01-14-21 EWW- 220 97 +/- 80 < 160 05-14-21 EWW- 1564 104 +/- 84 < 165 05-14-21 EWW- 1565 139 +/- 86 < 165 07-22-21 EWW- 2480 40 +/- 77 < 162 07-22-21 EWW- 2481 143 +/- 83 < 162 10-17-21 EWW- 3503 164 +/- 85 < 163 10-17-21 EWW- 3504 127 +/- 83 < 163 Mean+/- s.d. 106 +/- 51 Mean+/- s.d. 126 +/- 21 Sam.12.le ID GW-16AiMW-3l Collection Date Lab Code Tritium MDC 01-14-21 EWW- 221 115 +/- 81 < 160 05-14-21 EWW- 1566 246 +/- 91 < 165 07-22-21 EWW- 2482 129 +/- 83 < 162 10-17-21 EWW- 3505 242 +/- 89 < 163 Mean+/- s.d. 183 +/- 70 12- 12

POINT BEACH NUCLEAR PLANT Table 12. Groundwater Tritium Monitoring Program (Quarterly Collections)

Units= Ci/L Quarterly Wells (cont.)

Sample ID GW-18 (WH 7 Well)

Collection Date Lab Code Tritium MDC 01-21-21 EWW- 183 6 +/- 74 < 160 04-16-21 EWW- 1066 -34 +/- 73 < 159 07-21-21 EWW- 2335 -16 +/- 74 < 156 10-12-21 EWW- 3441 116 +/- 82 < 163 Mean+/- s.d. 18 +/- 67 Fa~ade Wells Sample ID GW-09 12-361A GW-09 12-3618 Collection MDC Collection MDC Date Lab Code Tritium Date Lab Code Tritium 03-16-21 EWW- 687 219 +/- 87 < 161 03-16-21 EWW- 688 189 +/- 85 < 161 06-04-21 EWW- 1907 258 +/- 91 < 160 06-04-21 EWW- 1908 176 +/- 87 < 160 08-07-21 EWW- 2773 175 +/- 88 < 163 08-07-21 EWW- 2774 282 +/- 94 < 163 10-16-21 EWW- 3457 254 +/- 90 < 163 10-16-21 EWW-.3458 167 +/- 85 < 163 Mean+/- s.d. 227 +/- 39 Mean+/- s.d. 203 +/- 53 Sample ID GW-10 22-361A GW-10 22-361B Collection MDC Collection MDC Date Lab Code Tritium Date Lab Code Tritium 03-16-21 EWW- 689 32 +/- 77 < 161 03-16-21 EWW- 690 34 +/- 77 < 161 06-04-21 EWW- 1910 97 +/- 82 < 160 06-04-21 EWW- 1911 164 +/- 86 < 160 08-07-21 EWW- 2775 43 +/- 81 < 163 08-07-21 EWW- 2776 404 +/- 99 < 163 10-16-21 EWW- 3459 -44 +/- 73 < 163 10-16-21 EWW- 3460 250 +/- 89 < 163 Mean+/- s.d. 32 +/- 58 Mean+/- s.d. 213 +/- 155 (Annual Collections)

Units= Ci/L Bogs Sample ID GW-07 (North Bog) GW-08 EiC Bog Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MOC 05-19-21 a EWW- 1489 372 +/- 94 < 158 05-19-21 EWW- 1490 100 +/- 80 < 158 Gamma scan in App. E 12- 13

POINT BEACH NUCLEAR PLANT Table 12. Groundwater Tritium Monitoring Program Units = pCi/L Manholes Sample ID MH Z-065A MH Z-0658 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 04-29-21 EW- 1420 318 +/- 92 < 158 04-29-21 EW- 1421 313 +/-92 < 158 09-29-21 EW- 3262 588 +/- 106 < 159 09-30-21 EW- 3263 985 +/- 122 < 159 Mean+/- s.d. 453+/-191 Mean+/- s.d. 649 +/- 475 Sample ID MH Z-065C MH Z-065D Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L)

Mean+/- s.d. Mean+/- s.d.

Sample ID MH Z-066A MH Z-0668 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 04-29-21 EW- 1422 193 +/- 85 < 158 05-04-21 EW- 1424 415 +/- 97 < 158 10-05-21 EW- 3264 351 +/- 95 < 159 10-04-21 EW- 3265 310 +/- 93 < 159 Mean+/- s.d. 272 +/- 112 Mean+/- s.d. 362 +/- 74 Sample ID MH Z-066C MH Z-066D Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 05-04-21 EW- 1425 380 +/- 95 < 153 05-04-21 EW- 1426 280 +/- 90 < 158 10-04-21 EW- 3266 317 +/- 93 < 159 10-05-21 EW- 3267 264 +/- 91 < 159 Mean+/- s.d. 348 +/- 44 Mean+/- s.d. 272 +/- 11 Sample ID MH Z-067A MH Z-0678 Collection MDC Collection MDC Lab Code Tritium (pCi/L)

Lab Code Tritium Date Date (pCi/L) 04-29-21 EW- 1427 223 +/- 87 < 158 05-04-21 EW- 1428 403 +/- 96 < 158 10-05-21 EW- 3268 280 +/- 91 < 159 10-04-21 EW- 3269 305 +/- 93 < 159 Mean+/- s.d. 251 +/- 41 Mean+/- s.d. 354 +/- 69 12-14

POINT BEACH NUCLEAR PLANT Manholes (cont.)

Sample ID MH Z-067C MH Z-067D Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 05-04-21 EW- 1429 287 +/- 90 < 158 05-04-21 EW- 1430 179 +/- 85 < 158 10-04-21 EW- 3270 276 +/- 91 < 159 10-05-21 EW- 3271 262 +/- 91 < 159 Mean+/- s.d. 281 +/- 8 Mean+/- s.d. 220 +/- 59 SamEle ID MH Z-068 MH-1 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L) 05-04-21 EW- 1431 320 +/- 92 < 158 10-05-21 EW- 3497 293 +/- 92 < 163 Mean+/- s.d. 306 +/- 19 Mean+/- s.d.

Sample ID MH-4 MH-6 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L)

Mean+/- s.d. Mean+/- s.d.

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

Mean+/- s.d. Mean+/- s.d.

Sample ID MH-16 MH-2 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L)

Mean+/- s.d. Mean+/- s.d.

Sample ID MH-5A MH-9 Collection MDC Collection MDC Lab Code Tritium Lab Code Tritium Date (pCi/L) Date (pCi/L)

Mean+/- s.d. Mean+/- s.d.

12-15

~*L All Environmental, Inc.

7+~/-'\I Midwest Laboratory 700 Landwehr Road

Northbrook, IL 60062-2310 phone (847) 564-0700

fax (847) 564-45 t 7 APPENDIX A INTERLABORATORY AND INTRALABORATORY COMPARISON PROGRAM RES ULTS NOTE: Appendix A is updated four times a year. The complete appendix is included in March, June, September and December monthly progress reports only.

October, 2020 through September, 2021

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

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

Results in Table A-1 were obtained through participation in the RAD PT Study Proficiency Testing Program administered by Environmental Resource Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.

Results in Table A-2 were obtained through participation in the New York Department of Health Environmental Laboratory Approval Program (ELAP) PT.

Table A-3 lists results for thermoluminescent dosimeters (TLDs), via irradiation and evaluation by the University of Wisconsin-Madison Radiation Calibration Laboratory at the University of Wisconsin Medical Radiation Research Center.

Table A-4 lists results of the analyses on intralaboratory "spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.

Table A-5 lists results of the analyses on intralaboratory "blank" samples for the past twelve months. Data for previous years available upon request.

Table A-6 lists analytical results from the intralaboratory "duplicate" program for the past twelve months. Acceptance is based on each result being within 25% of the mean of the two results or the two sigma uncertainties of each result overlap.

The results in Table A-7 were obtained through participation in the Mixed Analyte Performance Evaluation Program.

Results in Table A-8 were obtained through participation in the MRAD PT Study Proficiency Testing Program administered by Environmental Resource Associates, serving as a replacement for studies conducted previously by the Environmental Measurement Laboratory Quality Assessment Program (EML).

Attachment A lists the laboratory acceptance criteria for various analyses.

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

A-1

Attachment A ACCEPTANCE CRITERIA FOR INTRALABORATORY "SPIKED" SAMPLES Analysis Ratio of lab result to known value.

Gamma Emitters 0.8to1.2 Strontium-89, 0.8to1.2 Strontium-90 Potassium-40 0.8 to 1.2 Gross alpha 0.5 to 1.5 Gross beta 0.8to1.2 Tritium 0.8 to 1.2 Radium-226, 0.7 to 1.3 Radium-228 Plutonium 0.8 to 1.2 lodine-129, 0.8to1.2 lodine-131 Nickel-63, 0.7 to 1.3 Technetium-99, Uranium-238 lron-55 0.8 to 1.2 Other Analyses 0.8to1.2 A-2

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

RAD study Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Result Result Limits Acceptance RAD-124 Study ERW-94 1/11/2021 Ba-133 24.1 +/- 3.5 23.8 18.4 - 27.4 Pass ERW-94 1/11/2021 Cs-134 46.1 +/- 3.1 42.8 34.2 -47.1 Pass ERW-94 1/11/2021 Cs-137 154 +/- 6.0 148 133 - 165 Pass ERW-94 1/11/2021 Co-60 39.4 +/- 3.2 34.6 30.8 - 40.8 Pass ERW-94 1/11/2021 Zn-65 66.2 +/- 6.3 61.6 54.6 - 75.0 Pass ERDW-96 1/11/2021 Gr. Alpha 58.4 +/- 2.6 63.3 33.2 - 78.5 Pass ERDW-96 1/11/2021 Gr. Beta 38.1 +/- 1.3 39.8 26.4 -47.3 Pass ERDW-98 1/11/2021 Ra-226 16.3 +/- 0.5 15.5 11.5-17.8 Pass ERDW-98 1/11/2021 Ra-228 12.3 +/- 1.2 12.9 8.54 - 15.8 Pass ERDW-98 1/11/2021 Uranium 33.2 +/- 1.8 30.1 24.4 - 33.4 Pass ERW-100 1/11/2021 H-3 2,100 +/- 160 2,120 1,750 - 2,350 Pass RAD-126 Study ERDW-2194 7/12/2021 Ba-133 44.1 +/- 4.0 45.5 37.2 - 50.6 Pass ERDW-2194 7/12/2021 Cs-134 85.2 +/- 3.9 87.5 71.8 - 96.2 Pass ERDW-2194 7/12/2021 Cs-137 218 +/- 8 208 187 - 230 Pass ERDW-2194 7/12/2021 Co-60 91.7 +/- 4.0 87.1 78.4 - 98.1 Pass ERDW-2194 7/12/2021 Zn-65 114 +/- 9 102 91.8 - 122.0 Pass ERDW-2196 7/12/2021 Gr. Alpha 61.5 +/- 2.9 49.1 25.6 - 61.7 Pass ERDW-2196 7/12/2021 Gr. Beta 31.7+/-1.3 31.5 20.3 - 39.2 Pass ERDW-2200 7/12/2021 Ra-226 16.5 +/- 0.5 13.4 10.0 - 15.4 Failb ERDW-2200 7/12/2021 Ra-228 8.7 +/- 1.0 7.6 4.81 - 9.7 Pass ERDW-2200 7/12/2021 Uranium 71.7 +/- 2.3 62.3 50.9 - 68.5 Failc ERDW-2202 7/12/2021 H-3 11,300 +/- 300 10,400 9,050 - 11,400 Pass ERDW-2198 7/12/2021 1-131 22.3 +/- 1.1 20.8 17.2 - 25.0 Pass

Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resource Associates (ERA).

b The radium-226 result did not meet ERA acceptance criteria.

c The uranium result did not meet ERA acceptance criteria.

A-3

TABLE A-2. lnterlaboratory Comparison Crosscheck program, New York Department of Health (ELAP) 8

Concentration (pCi/L)

Lab Code Date Analysis Laboratory Assigned Acceptance Result Value Limits Acceptance Shipment 437R NYW-3307 9/15/2020 H-3 11,500 +/- 465 11,208 9760 - 12,300 Pass NYW-3331 9/15/2020 Gross Alpha 43.7 +/- 2.5 64.9 34.0 - 80.4 Pass NYW-3331 9/15/2020 Gross Beta 11.1+/-1.1 8.85 3.62-17.4 Pass NYW-3335 9/15/2020 1-131 14.1+/-1.4 12.6 10.3 - 16.0 Pass NYW-3333 9/15/2020 Ra-226 2.24 +/- 0.27 2.63 2.06 - 3.44 Pass NYW-3333 9/15/2020 Ra-228 4.91 +/-1.12 5.41 3.27 - 7.18 Pass NYW-3333 9/15/2020 Uranium 42.8 +/- 1.94 37.1 30.1 -41.0 Failb NYW-3337 9/15/2020 Co-60 46.4 +/- 3.8 42.3 38.1 - 49.2 Pass NYW-3337 9/15/2020 Zn-65 133 +/-9 116 104 - 138 Pass NYW-3337 9/15/2020 Ba-133 49.5 +/- 4.1 46.4 38.0 - 51.6 Pass NYW-3337 9/15/2020 Cs-134 32.5 +/- 3.1 33.0 26.0 - 36.3 Pass NYW-3337 9/15/2020 Cs-137 147 +/-7 134 121 -150 Pass

" Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by the New York Department of Health Laboratory Approval Program(NY ELAP).

b Lab passed all ERA and MAPEP studies for uranium in 2020.(See tables A-1, A-7 and A-8) Uncertainty overlapped upper acceptance limit.

A-4

TABLE A-3. Thermoluminescent Dosimetry, (TLD, CaS0 4 : Dy Cards)."

mrem Lab Code Irradiation Delivered Reportedb Performancec Date Description Dose Dose Quotient (P)

Environmental. Inc. Group 1 2020-1 10/28/2020 Spike 1 172.0 180.0 0.05 2020-1 10/28/2020 Spike 2 172.0 174.5 0.01 2020-1 10/28/2020 Spike 3 172.0 174.3 0.01 2020-1 10/28/2020 Spike 4 172.0 174.0 0.01 2020-1 10/28/2020 Spike 5 172.0 167.1 -0.03 2020-1 10/28/2020 Spike 6 172.0 161.9 -0.06 2020-1 10/28/2020 Spike 7 172.0 167.9 -0.02 2020-1 10/28/2020 Spike 8 172.0 171.0 -0.01 2020-1 10/28/2020 Spike 9 172.0 170.7 -0.01 2020-1 10/28/2020 Spike 10 172.0 170.1 -0.01 2020-1 10/28/2020 Spike 11 172.0 173.8 0.01 2020-1 10/28/2020 Spike 12 172.0 178.3 0.04 2020-1 10/28/2020 Spike 13 172.0 178.2 0.04 2020-1 10/28/2020 Spike 14 172.0 171.9 0.00 2020-1 10/28/2020 Spike 15 172.0 190.4 0.11 2020-1 10/28/2020 Spike 16 172.0 170.9 -0.01 2020-1 10/28/2020 Spike 17 172.0 183.3 0.07 2020-1 10/28/2020 Spike 18 172.0 170.6 -0.01 2020-1 10/28/2020 Spike 19 172.0 164.9 -0.04 2020-1 10/28/2020 Spike 20 172.0 175.7 0.02 Mean (Spike 1-20) 173.5 0.01 Pass ct Standard Deviation (Spike 1-20) 6.5 0.04 Pass ct a TLD's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison lo the delivered dose.

b Reported dose was converted from exposure (R) to Air Kerma (cGy) using a conversion of 0.876. Conversion from air kerma to ambient dose equivalent for Cs-137 at the reference dose point H*(1 O)Ka = 1.20 . mrem/cGy = 1000.

c Performance Quotient (P) is calculated as ((reported dose - conventionally true value) +conventionally true value) where the conventionally true value is the delivered dose.

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

A-5

TABLE A-3. Thermoluminescent Dosimetry, (TLD, CaS0 4 : Dy Cards)."

mrem Lab Code Irradiation Delivered Reportedb Performancec Date Description Dose Dose Quotient (P)

Environmental, Inc. Group 2 2020-2 10/28/2020 Spike 21 114.0 117.3 0.03 2020-2 10/28/2020 Spike 22 114.0 103.3 -0.09 2020-2 10/28/2020 Spike 23 114.0 106.2 -0.07 2020-2 10/28/2020 Spike 24 114.0 110.1 -0.03 2020-2 10/28/2020 Spike 25 114.0 114.9 0.01 2020-2 10/28/2020 Spike 26 114.0 115.5 0.01 2020-2 10/28/2020 Spike 27 114.0 110.4 -0.03 2020-2 10/28/2020 Spike 28 114.0 111.7 -0.02 2020-2 10/28/2020 Spike 29 114.0 111.3 -0.02 2020-2 10/28/2020 Spike 30 114.0 113.1 -0.01 2020-2 10/28/2020 Spike 31 114.0 116.4 0.02 2020-2 10/28/2020 Spike 32 114.0 111.8 -0.02 2020-2 10/28/2020 Spike 33 114.0 112.6 -0.01 2020-2 10/28/2020 Spike 34 114.0 105.7 -0.07 2020-2 10/28/2020 Spike 35 114.0 104.5 -0.08 2020-2 10/28/2020 Spike 36 114.0 103.6 -0.09 2020-2 10/28/2020 Spike 37 114.0 104.4 -0.08 2020-2 10/28/2020 Spike 38 114.0 104.5 -0.08 2020-2 10/28/2020 Spike 39 114.0 106.4 -0.07 2020-2 10/28/2020 Spike 40 114.0 107.7 -0.06 Mean (Spike 21-40) 109.6 -0.04 Passd Standard Deviation (Spike 21-40) 4.6 0.04 Passd a TL D's were irradiated by the University of Wisconsin-Madison Radiation Calibration Laboratory following ANSI N 13.37 protocol from a known air kerma rate. TLD's were read and the results were submitted by Environmental Inc. to the University of Wisconsin-Madison Radiation Calibration Laboratory for comparison to the delivered dose.

b Reported dose was converted from exposure (R) to Air Kerma (cGy) using a conversion of 0.876. Conversion from air kerma to ambient dose equivalent for Cs-137 at the reference dose point H*(1 O)Ka =1.20 . mrem/cGy =1000.

c Performance Quotient (P) is calculated as ((reported dose - conventionally true value) +conventionally true value) where the conventionally true value is the delivered dose.

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

A-6

TABLE A-4. lntralaboratory "Spiked" Samples Concentration° Lab Codeb Date Analysis Laboratory results Known Control Ratio 2s, n=1c Activity Limits ct Acceptance Lab/Known SPW-3482 10/2/2020 H-3 1,984 +/- 154 2,110 1,688 - 2,532 Pass 0.94 SPW-3624 10/9/2020 H-3 1,924 +/- 152 2,110 1,688 - 2,532 Pass 0.91 SPW-3794 10/16/2020 H-3 2,109+/-156 2,110 1,688 - 2,532 Pass 1.00 SPW-3836 10/20/2020 Sr-90 16.8 +/- 1.1 17.9 14.3 - 21.5 Pass 0.94 SPW-4043 10/23/2020 H-3 1893 +/- 149 2,110 1,688 - 2,532 Pass 0.90 SPW-4179 10/28/2020 Ra-228 15.4 +/- 2.4 12.1 8.5 -15.7 Pass 1.27 SPW-4422 10/30/2020 Ra-226 12.3 +/- 0.3 12.3 8.6 -16.0 Pass 1.00 SPW-4234 11/11/2020 H-3 2,008 +/- 154 2,110 1,688 - 2,532 Pass 0.95 SPW-4634 11 /23/2020 Ra-226 11.4 +/- 0.3 12.3 8.6 -16.0 Pass 0.93 SPW-4509 12/4/2020 H-3 1,873 +/- 149 2,110 1,688 - 2,532 Pass 0.89 SPW-4625 12/18/2020 H-3 1,940 +/- 152 2,110 1,688 - 2,532 Pass 0.92 SPW-4741 12/18/2020 Ra-226 12.5 +/- 0.4 12.3 8.6 - 16.0 Pass 1.02 SPW-55 1/8/2021 H-3 1,889 +/- 150 2,110 1,688 - 2,532 Pass 0.90 SPDW-62 1/11/2021 Gr. Alpha 34.3 +/- 1.7 64.9 34.0 - 80.4 Pass 0.53 SPDW-62 1/11/2021 Gr. Beta 9.2 +/- 0.8 8.9 3.6 -17.4 Pass 1.04 SPW-131 1/19/2021 Sr-90 18.0 +/- 1.1 17.9 14.3 - 21.5 Pass 1.00 SPW-133 1/19/2021 H-3 1,842 +/- 150 2,110 1,688 - 2,532 Pass 0.87 SPW-188 1/18/2021 Ra-228 14.2+/-1.7 14.9 10.4-19.3 Pass 0.96 SPW-236 1/26/2021 Ra-228 12.2+/-1.9 15.3 10.7 - 19.9 Pass 0.80 SPW-305 2/5/2021 H-3 1,785 +/- 147 2,110 1,688 - 2,532 Pass 0.85 SPW-372 2/12/2021 H-3 1,742 +/- 145 2,110 1,688 - 2,532 Pass 0.83 SPW-526 3/5/2021 H-3 1,899 +/- 150 2,110 1,688 - 2,532 Pass 0.90 SPW-692 3/19/2021 H-3 1,953+/-151 2,110 1,688 - 2,532 Pass 0.93 SPW-694 1/4/2021 Ra-226 9.7 +/- 0.4 12.3 8.6 -16.0 Pass 0.79 SPW-800 3/30/2021 Ra-228 15.8 +/- 2.0 15.3 10.7 -19.9 Pass 1.03 SPW-802 3/31/2021 H-3 1,878 +/- 150 2,110 1,688 - 2,532 Pass 0.89 SPW-810 3/19/2021 Ra-226 11.4 +/- 0.3 12.3 8.6 -16.0 Pass 0.93 SPDW-30103 3/31/2021 Ra-226 13.5+/-0.4 12.3 8.6 - 16.0 Pass 1.10 SPW-812 4/1/2021 H-3 2,005 +/- 155 2,110 1,688 - 2,532 Pass 0.95 SPW-919 4/7/2021 H-3 1,877 +/- 149 2,110 1,688 - 2,532 Pass 0.89 SPW-944 4/9/2021 Gr. Alpha 56.7 +/- 2.5 58.4 29.2 - 87.6 Pass 0.97 SPW-944 4/9/2021 Gr. Beta 35.1 +/- 1.3 38.1 30.5 - 45.7 Pass 0.92 SPW-1048 4/15/2021 H-3 1,915+/-152 2,110 1,688 - 2,532 Pass 0.91 SPW-1250 4/30/2021 H-3 2,015 +/- 154 2,110 1,688 - 2,532 Pass 0.95 SPW-1373 5/11/2021 Gr. Alpha 63.5 +/- 2.9 58.4 29.2 - 87.6 Pass 1.09 SPW-1373 5/11/2021 Gr. Beta 38.5 +/- 1.3 38.1 30.5 - 45.7 Pass 1.01 SPW-1377 5/11/2021 Sr-90 17.4+/-1.2 17.9 14.3 - 21.5 Pass 0.97 SPDW-30108 5/28/2021 H-3 2,222 +/- 161 2,110 1,688 - 2,532 Pass 1.05 SPDW-30125 5/13/2021 Ra-226 10.9 +/- 0.3 12.3 8.6 - 16.0 Pass 0.89 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 & SPW (Water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).

c Results are based on single determinations.

ct Acceptance criteria are listed in Attachment A of this report.

A-7

TABLE A-4. lntralaboratory "Spiked" Samples Concentration*

Lab Codeb Date Analysis Laboratory results Known Control Ratio 2s, n=1° Activity Limitsd Acceptance Lab/Known SPDW-30118 6/4/2021 H-3 2,230 +/- 163 2,110 1,688 - 2,532 Pass 1.06 SPMl-1672 6/8/2021 Sr-90 14.2 +/- 0.9 13.6 10.9 -16.3 Pass 1.04 SPDW-30160 6/11/2021 Ra-226 11.4+/-0.3 12.3 8.6 -16.0 Pass 0.93 SPDW-30129 6/15/2021 H-3 2,238 +/- 162 2,110 1,688 - 2,532 Pass 1.06 SPDW-30134 6/18/2021 Gr. Alpha 17.9+/-1.4 23.5 11.8 - 35.3 Pass 0.76 SPDW-30134 6/18/2021 Gr. Beta 60.9 +/- 1.6 67.6 54.1 - 81.1 Pass 0.90 SPDW-30148 6/25/2021 Ra-228 15.1+/-2.9 15.3 10.7 - 19.9 Pass 0.98 SPDW-30206 7/8/2021 Ra-226 12.7 +/- 0.4 12.3 8.6 -16.0 Pass 1.03 SPDW-3001 7/29/2021 Ra-226 11.6 +/- 0.3 12.3 8.6 -16.0 Pass 0.95 SPDW-30224 8/2/2021 Gr. Alpha 38.6 +/- 2.1 49.1 24.6 - 73.7 Pass 0.79 SPDW-30224 8/2/2021 Gr. Beta 27.8+/-1.2 31.5 25.2 - 37.8 Pass 0.88 SPDW-30226 8/13/2021 H-3 2,074 +/- 157 2,110 1,688 - 2,532 Pass 0.98 SPDW-30231 8/18/2021 Ra-228 14.5 +/- 2.2 15.3 10.7 - 19.9 Pass 0.95 SPW-2783 9/3/2021 Sr-90 18.9+/-1.2 17.1 13.7 -20.5 Pass 1.10 SPDW-2785 9/3/2021 H-3 2,135 +/- 158 2,110 1,688 - 2,532 Pass 1.01 SPDW-2891 9/10/2021 H-3 2,159+/-160 2,110 1,688 - 2,532 Pass 1.02 SPDW-3115 9/17/2021 Ra-226 11.3 +/- 0.3 12.3 8.6 - 16.0 Pass 0.92 SPDW-3036 9/23/2021 Ra-228 18.0 +/- 2.6 15.3 10.7 -19.9 Pass 1.17 SPDW-3223 9/28/2021 Ra-228 16.6 +/- 2.5 15.3 10.7 -19.9 Pass 1.08 SPDW-3288 9/29/2021 U-234 29.2+/-1.6 23.0 16.1 - 29.9 Pass 1.27 SPDW-3288 9/29/2021 U-238 28.2 +/- 1.6 23.2 16.3 - 30.2 Pass 1.21 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 & SPW (Water), Ml (milk), AP (air filter), SO (soil), VE (vegetation), CH (charcoal canister), F (fish), U (urine).

0 Results are based on single determinations.

d Acceptance criteria are listed in Attachment A of this report.

A-8

TABLE A-5. lntralaboratory "Blank" Samples 8

Concentration 0

Lab Codeb Sample Date Analysis Laboratory results (4.66cr) Acceptance Type LLD Activity Criteria (4.66 cr)

SPW-3481 Water 10/2/2020 H-3 154 63 +/- 80 200 SPW-3623 Water 10/9/2020 H-3 156 57 +/- 81 200 SPW-3793 Water 10/16/2020 H-3 157 3 +/- 73 200 SPW-3835 Water 10/20/2020 Sr-89 0.55 -0.10+/-0.43 5 SPW-3835 Water 10/20/2020 Sr-90 0.59 0.09 +/- 0.28 1 SPW-4042 Water 10/23/2020 H-3 155 -6 +/- 72 200 SPW-4178 Water 10/28/2020 Ra-228 1.04 0.33 +/- 0.52 2 SPW-4421 Water 10/30/2020 Ra-226 0.03 0.07 +/- 0.03 2 SPW-4233 Water 11/11/2020 H-3 155 78 +/- 79 200 SPW-4356 Water 11/20/2020 H-3 157 52 +/- 76 200 SPW-4633 Water 11/23/2020 Ra-226 0.05 0.04+/-0.11 2 SPW-4508 Water 12/4/2020 H-3 159 -68 +/- 69 200 SPW-4624 Water 12/18/2020 H-3 160 8 +/- 77 200 SPW-4740 Water 12/18/2020 Ra-226 0.04 0.02 +/- 0.03 2 SPW-54 Water 1/8/2021 H-3 153 24 +/- 77 200 SPDW-61 Water 1/11/2021 Gr. Alpha 0.56 -0.32 +/- 0.37 2 SPDW-61 Water 1/11/2021 Gr. Beta 0.73 -0.11+/-0.49 4 SPW-130 Water 1/19/2021 Sr-89 0.66 -0.12+/-0.49 5 SPW-130 Water 1/19/2021 Sr-90 0.68 -0.02 +/- 0.31 SPW-132 Water 1/19/2021 H-3 165 38 +/- 79 200 SPW-4923 Water 1/26/2021 1-131 0.28 0.26 +/- 0.16 1 SPW-187 Water 1/18/2021 Ra-228 1.44 0.81 +/- 0.76 2 SPW-235 Water 1/26/2021 Ra-228 1.54 0.94 +/- 0.82 2 SPW-254 Water 2/2/2021 1-131 0.29 -0.06 +/- 0.13 SPW-304 Water 2/5/2021 H-3 159 6 +/- 74 200 SPW-372 Water 2/12/2021 H-3 154 -37 +/- 70 200 SPW-525 Water 3/5/2021 H-3 160 97 +/- 80 200 SPW-691 Water 3/19/2021 H-3 158 -38 +/- 71 200 SPW-693 Water 1/4/2021 Ra-226 0.03 -0.01 +/- 0.01 2 SPW-799 Water 3/30/2021 Ra-228 1.03 0.06 +/- 0.48 2 SPW-809 Water 3/19/2021 Ra-226 0.04 0.01 +/- 0.03 2 SPDW-30102 Water 3/31/2021 Ra-226 0.03 0.00 +/- 0.03 2 SPW-811 Water 4/1/2021 H-3 158 -29 +/- 77 200 SPW-918 Water 4/7/2021 H-3 156 93 +/- 79 200 SPW-943 Water 4/9/2021 Gr. Alpha 0.39 -0.08 +/- 0.27 2 SPW-943 Water 4/9/2021 Gr. Beta 0.73 0.04 +/- 0.51 4 SPW-1047 Water 4/15/2021 H-3 160 -51 +/- 74 200 SPW-1249 Water 4/30/2021 H-3 158 109 +/- 81 200 a Liquid sample results are reported in pCi/Liter, air filters ( pCi/m'), charcoal (pCi/charcoal canister), and solid samples (pCi/g).

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

0 l-131(G); iodine-131 as analyzed by gamma spectroscopy.

d Activity reported is a net activity result.

A-9

TABLE A-5. lntralaboratory "Blank" Samples Concentration" Lab Codeb Sample Date Analysisc Laboratory results (4.66a) Acceptance Type LLD Activity Criteria (4.66 cr)

SPW-1372 Water 5/11/2021 Gr. Alpha 0.35 0.27 +/- 0.27 2 SPW-1372 Water 5/11/2021 Gr. Beta 0.68 0.27 +/- 0.49 4 SPW-1376 Water 5/11/2021 Sr-89 0.52 0.23 +/- 0.39 5 SPW-1376 Water 5/11/2021 Sr-90 0.51 -0.06 +/- 0.23 SPDW-30124 Water 5/13/2021 Ra-226 0.03 -0.02 +/- 0.03 2 SPDW-30104 Water 5/26/2021 Ra-228 1.30 -0.04 +/- 0.60 2 SPDW-30107 Water 5/28/2021 H-3 157 33 +/- 76 200 SPDW-30117 Water 6/4/2021 H-3 165 67 +/- 81 200 SPMl-1671 Milk 6/8/2021 Sr-89 0.46 0.23 +/- 0.42 5 SPMl-1671 Milk 6/8/2021 Sr-90 0.45 0.23 +/- 0.24 SPDW-30159 Water 6/11/2021 Ra-226 0.04 -0.02 +/- 0.04 2 SPDW-30128 Water 6/15/2021 H-3 161 17 +/- 76 200 SPDW-30133 Water 6/17/2021 1-131 0.20 0.06 +/-0.12 1 SPDW-30134 Water 6/18/2021 Gr. Alpha 0.46 -0.11 +/- 0.32 2 SPDW-30134 Water 6/18/2021 Gr. Beta 0.70 -0.10 +/-0.49 4 SPDW-30147 Water 6/25/2021 Ra-228 1.76 -0.15 +/-0.80 2 SPDW-30205 Water 7/8/2021 Ra-226 0.03 0.02 +/- 0.03 2 SPDW-3000 Water 7/29/2021 Ra-226 0.03 0.03 +/- 0.03 2 SPDW-30223 Water 8/2/2021 Gr. Alpha 0.46 -0.13 +/-0.31 2 SPDW-30223 Water 8/2/2021 Gr. Beta 0.70 0.16 +/-0.49 4 SPDW-30225 Water 8/13/2021 H-3 161 -2 +/- 75 200 SPDW-30230 Water 8/18/2021 Ra-228 1.02 0.47 +/- 0.53 2 SPW-2782 Water 9/3/2021 Sr-89 0.60 -0.16 +/-0.48 5 SPW-2782 Water 9/3/2021 Sr-90 0.63 0.20 +/- 0.32 1 SPDW-2784 Water 9/3/2021 H-3 157 -50 +/- 69 200 SPDW-2890 Water 9/10/2021 H-3 163 -59 +/- 72 200 SPDW-2981 Water 9/17/2021 H-3 162 11 +/- 78 200 SPDW-3114 Water 9/17/2021 Ra-226 0.03 0.04 +/- 0.03 2 SPDW-3035 Water 9/23/2021 Ra-228 1.15 0.10 +/- 0.55 2 SPDW-3222 Water 9/28/2021 Ra-228 1.37 -0.30 +/- 0.60 2 SPDW-3287 Water 9/29/2021 U-234 0.22 0.19 +/-0.23 SPDW-3287 Water 9/29/2021 U-238 0.38 -0.05 +/- 0.21 a Liquid sample results are reported in pCi/Liter, air filters ( pCi/m 3 ), charcoal (pCi/charcoal canister), and solid samples (pCi/g).

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

c l-131(G); iodine-131 as analyzed by gamma spectroscopy.

d Activity reported is a net activity result.

A-10

TABLE A-6. lntralaboratory "Duplicate" Samples Concentration" Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance SW-3515,3516 10/1/2020 H-3 154 +/- 86 111 +/- 84 133 +/- 60 Pass DW-20141,20142 10/1/2020 Ra-226 1.34 +/- 0.16 1.39 +/-0.16 1.37 +/- 0.11 Pass DW-20141,20142 10/1/2020 Ra-228 1.74 +/-0.62 2.09 +/- 0.64 1.92 +/- 0.45 Pass SW-3536,3537 10/5/2020 H-3 376 +/- 97 378 +/- 97 377 +/- 68 Pass WW-3727,3728 10/8/2020 H-3 152 +/- 82 190 +/- 84 171 +/- 59 Pass VE-37 48,37 49 10/12/2020 K-40 3.07 +/- 0.25 2.88 +/- 0.26 2.98 +/-0.18 Pass VE-3769,3770 10/12/2020 Be-7 0.80 +/- 0.31 0.51 +/- 0.15 0.66+/-0.17 Pass VE-3769,3770 10/12/2020 K-40 5.69 +/- 0.61 5.79 +/- 0.39 5.74 +/-0.36 Pass WW-4092,4093 10/13/2020 H-3 6,484 +/- 252 6,275 +/- 248 6,380 +/- 177 Pass WW-3838,3839 10/14/2020 H-3 313 +/- 90 263 +/- 88 288 +/- 63 Pass WW-4394,4395 11/3/2020 H-3 161 +/- 83 199 +/- 85 180 +/- 60 Pass WW-4587,4588 11/4/2020 H-3 6,468 +/- 252 6,638 +/- 255 6,553+/-179 Pass WW-4524,4525 11/5/2020 H-3 160 +/- 86 131 +/- 84 145 +/- 60 Pass VE-4415,4416 11/24/2020 Be-7 0.28 +/- 0.08 0.22 +/- 0.07 0.25 +/- 0.05 Pass VE-4415,4416 11/24/2020 K-40 2.25 +/- 0.21 2.20 +/-0.19 2.23 +/- 0.14 Pass AP-4845,4846 12/31/2020 Be-7 0.07 +/- 0.01 0.06 +/- 0.02 0.06 +/- 0.01 Pass WW-4566,4567 12/8/2020 Gr. Beta 2.79 +/- 1.13 3.52 +/- 1.26 3.15 +/- 0.84 Pass WW-4654,4655 12/14/2020 H-3 3,250 +/- 188 3,250 +/- 188 3,250 +/- 133 Pass S-4608,4609 12/9/2020 K-40 20.8+/-1.0 22.1 +/- 3.0 21.4+/-1.6 Pass AP-4803,4804 12/29/2020 Be-7 0.072 +/- 0.009 0.080 +/- 0.009 0.076 +/- 0.006 Pass SWU-4717,4718 12/29/2020 Gr. Beta 0.88 +/- 0.53 1.43 +/- 0.57 1.15 +/- 0.39 Pass AP-4824,4825 12/30/2020 Be-7 0.075 0.009 0.080 +/- 0.009 0.078 +/- 0.006 Pass AP-4908,4909 12/30/2020 Be-7 0.066 0.011 0.056 +/- 0.010 0.061 +/- 0.007 Pass AP-4845,4846 12/31/2020 Be-7 0.052 0.014 0.058 +/- 0.012 0.055 +/- 0.009 Pass S-20,21 1/5/2021 K-40 23.3 +/- 0.6 22.6+/-1.6 23.0 +/- 0.9 Pass XW-295,296 1/13/2021 H-3 245 +/- 87 288 +/- 89 267 +/- 62 Pass S-143,144 1/14/2021 K-40 7.47 +/- 0.76 8.38 +/- 0.22 7.93 +/- 0.40 Pass S-360,361 2/10/2021 K-40 9.23 +/- 0.54 9.00 +/- 0.68 9.12 +/- 0.43 Pass S-406,407 2/15/2021 K-40 2.92 +/- 0.28 2.94 +/- 0.94 2.93 +/- 0.49 Pass W-469,470 2/22/2021 Ra-226 0.75 +/- 0.21 0.87 +/- 0.22 0.81 +/- 0.15 Pass W-448,449 2/25/2021 Gr. Alpha 3.52 +/- 1.84 3.72 +/- 1.87 3.62 +/- 1.31 Pass W-448,449 2/25/2021 Gr. Beta 8.71 +/- 1.36 8.91 +/- 1.40 8.81 +/- 0.98 Pass W-448,449 2/25/2021 Ra-226 1.87 +/- 0.25 1.82 +/- 0.28 1.85 +/- 0.19 Pass W-448,449 2/25/2021 Ra-228 2.65 +/- 1.26 2.53 +/- 1.35 2.59 +/- 0.92 Pass P-511,512 3/2/2021 H-3 198 +/- 85 202 +/- 86 200 +/- 60 Pass WW-630,631 3/10/2021 H-3 144 +/- 82 148 +/- 82 146 +/- 58 Pass WW-743,744 3/16/2021 H-3 183 +/- 85 167 +/- 84 175 +/- 60 Pass S-785,786 3/25/2021 Pb-214 0.59 +/- 0.08 0.34 +/- 0.05 0.47 +/- 0.05 Pass S-785,786 3/25/2021 Ac-228 0.61 +/- 0.12 0.58 +/- 0.13 0.60 +/- 0.09 Pass A-11

TABLE A-6. lntralaboratory "Duplicate" Samples Concentrationa Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance AP-1052, 1053 3/30/2021 Be-7 0.081 +/- 0.010 0.075 +/- 0.011 0.078 +/- 0.007 Pass AP-966,967 3/30/2021 Be-7 0.080 +/- 0.010 0.085 +/- 0.009 0.083 +/- 0.007 Pass SWU-835,836 3/30/2021 Gr. Beta 1.22 +/- 0.56 1.27 +/- 0.55 1.24 +/- 0.39 Pass AP-1204,1205 3/30/2021 Be-7 0.187 +/- 0.102 0.160 +/- 0.088 0.173 +/- 0.067 Pass AP-1029, 1030 4/2/2021 Be-7 0.067 +/- 0.012 0.079 +/- 0.012 0.073 +/- 0.009 Pass SW-922,923 4/7/2021 H-3 440 +/- 99 307 +/- 93 373 +/- 68 Pass WW-987,988 4/12/2021 H-3 190 +/- 87 284 +/- 92 237 +/- 63 Pass F-1246,1247 4/22/2021 K-40 3.26 +/- 0.66 2.83 +/- 0.46 3.04 +/- 0.40 Pass SWT-1311,1312 4/27/2021 Gr. Beta 1.05 +/- 0.52 1.16+/-0.55 1.10 +/-0.38 Pass WW-1401, 1402 5/5/2021 Gr. Alpha 1.10+/-1.00 2.50 +/- 1.20 1.80 +/- 0.78 Pass WW-1401,1402 5/5/2021 K-40 126 +/- 15 105 +/- 30 115+/-17 Pass DW-30071.,30072 5/6/2021 Ra-226 0.98 +/- 0.15 0.67 +/-0.13 0.83 +/-0.10 Pass DW-30071.,30072 5/6/2021 Ra-228 0.83 +/- 0.51 1.21 +/- 0.54 1.02 +/- 0.37 Pass DW-30078,30079 5/10/2021 Gr. Alpha 4.90 +/- 0.92 5.92 +/- 0.99 5.41 +/- 0.68 Pass AP-051120A,B 5/11/2021 Gr. Beta 0.006 +/- 0.002 0.005 +/- 0.002 0.005 +/- 0.002 Pass DW-30083,30084 5/11/2021 Ra-226 0.34+/-0.13 0.19 +/- 0.20 0.27 +/- 0.12 Pass DW-30083,30084 5/11/2021 Ra-228 0.98 +/- 0.60 0.15 +/- 0.56 0.57 +/- 0.41 Pass S-1506, 1507 5/18/2021 K-40 10.1 +/- 0.8 14.9 +/- 1.2 12.5 +/- 0.7 Pass DW-30092,30093 5/20/2021 Gr. Alpha 2.86 +/- 0.85 2.40 +/- 0.90 2.63 +/- 0.62 Pass DW-30095,30096 5/21/2021 Ra-226 1.18 +/- 0.16 0.73 +/- 0.15 0.96 +/-0.11 Pass DW-30095,30096 5/21/2021 Ra-228 1.44 +/- 0.63 0.61 +/- 0.59 1.03 +/- 0.43 Pass AP-052521A,B 5/25/2021 Gr. Beta 0.021 +/- 0.003 0.022 +/- 0.003 0.021 +/- 0.002 Pass S-1589, 1590 5/28/2021 Pb-214 1.16+/-0.08 1.06 +/- 0.09 1.11 +/- 0.06 Pass S-1589,1590 5/28/2021 Ac-228 1.17 +/-0.18 1.08 +/- 0.14 1.13+/-0.11 Pass AP-060121A,B 6/1/2021 Gr. Beta 0.015 +/- 0.003 0.013 +/- 0.003 0.014 +/- 0.002 Pass DW-30113,30114 6/1/2021 Ra-226 2.00 +/- 0.34 2.64 +/- 0.26 2.32 +/- 0.21 Pass DW-30113,30114 6/1/2021 Ra-228 2.50 +/- 0.78 3.13 +/- 0.82 2.82 +/- 0.57 Pass PS-1631,1632 6/2/2021 K-40 21.1 +/- 0.8 20.4 +/- 0.8 20.7 +/- 0.6 Pass DW-30119,30120 6/3/2021 Gr. Alpha 1.18+/-0.75 0.66 +/- 0.64 0.92 +/- 0.49 Pass WW-1908,1909 6/4/2021 H-3 150 +/- 85 176 +/- 87 163 +/- 61 Pass VE-1717,1718 6/7/2021 Be-7 0.50 +/- 0.19 0.38 +/- 0.14 0.44 +/- 0.12 Pass VE-1717,1718 6/7/2021 K-40 5.26 +/- 0.47 5.45 +/- 0.44 5.35 +/- 0.32 Pass AP-060821A,B 6/8/2021 Gr. Beta 0.030 +/- 0.004 0.028 +/- 0.004 0.029 +/- 0.003 Pass AP-1822, 1823 6/10/2021 Be-7 0.23 +/-0.12 0.22 +/-0.12 0.22 +/- 0.08 Pass CF-1844, 1845 6/14/2021 K-40 8.37 +/- 0.44 8.33 +/- 0.35 8.35 +/- 0.28 Pass AP-061521A,B 6/15/2021 Gr. Beta 0.020 +/- 0.004 0.017 +/- 0.003 0.019 +/- 0.002 Pass DW-30131,30132 6/17/2021 Ra-226 0.41 +/- 0.21 0.34 +/- 0.23 0.38 +/- 0.16 Pass DW-30131,30132 6/17/2021 Ra-228 0.42 +/- 0.85 0.52 +/- 0.74 0.47 +/- 0.56 Pass DW-30138,30139 6/17/2021 Gr. Alpha 1.59 +/- 0.84 2.21 +/- 0.95 1.90 +/- 0.63 Pass A-12

TABLE A-6. lntralaboratory "Duplicate" Samples Concentration" Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance S-1929, 1930 6/22/2021 K-40 19.4+/-1.0 19.2+/-1.1 19.3 +/- 0.7 Pass AP-062221A,B 6/22/2021 Gr. Beta 0.014 +/- 0.003 0.012 +/- 0.028 0.013 +/- 0.014 Pass DW-30150,30151 6/28/2021 Ra-226 0.53+/-0.15 0.55 +/-0.19 0.54 +/-0.12 Pass DW-30150,30151 6/28/2021 Ra-228 0.76 +/- 0.54 0.52 +/- 0.52 0.64 +/- 0.37 Pass AP-2160,2161 6/28/2021 Be-7 0.11 +/- 0.01 0.11 +/- 0.01 0.11 +/- 0.01 Pass DW-30150,30151 6/28/2021 Ra-226 0.53 +/-0.15 0.55 +/- 0.19 0.54 +/- 0.12 Pass DW-30150,30151 6/28/2021 Ra-228 0.76 +/- 0.54 0.52 +/- 0.52 0.64 +/- 0.37 Pass AP-2218,2119 6/29/2021 Be-7 0.11+/-0.01 0.12 +/- 0.01 0.11 +/- 0.01 Pass AP-2235,2236 6/30/2021 Be-7 0.10 +/- 0.01 0.11 +/- 0.01 0.10 +/- 0.01 Pass CF-2139,2140 7/12/2021 Be-7 0.49 +/- 0.12 0.65 +/- 0.20 0.57 +/-0.12 Pass CF-2139,2140 7/12/2021 K-40 8.25 +/- 0.41 7.94 +/- 0.46 8.10 +/- 0.31 Pass VE-2214,2215 7/12/2021 K-40 3.26+/-0.11 3.41 +/- 0.25 3.34 +/- 0.14 Pass DW-30169,30170 7/12/2021 Gr. Alpha 2.61 +/- 0.87 2.09 +/- 0.84 2.35 +/- 0.60 Pass DW-30169,30170 7/12/2021 Gr. Beta 2.09 +/- 0.67 2.52 +/- 0.60 2.31 +/- 0.45 Pass DW-30169,30170 7/12/2021 Ra-226 0.84 +/- 0.24 0.82 +/- 0.20 0.83 +/-0.16 Pass DW-30169,30170 7/12/2021 Ra-228 0.80 +/- 0.54 0.84 +/- 0.50 0.82 +/- 0.37 Pass AP-71320,71321 7/13/2021 Gr. Beta 0.015 +/- 0.003 0.010 +/- 0.003 0.013 +/- 0.002 Pass XW-2424,2425 7/16/2021 H-3 193 +/- 86 104 +/- 81 149 +/- 59 Pass DW-30183,30184 7/19/2021 Ra-226 1.37 +/- 0.18 1.21 +/- 0.27 1.29 +/-0.16 Pass DW-30183,30185 7/19/2021 Ra-228 1.51 +/- 0.69 1.52 +/- 0.68 1.52 +/- 0.48 Pass AP-71920,71921 7/19/2021 Gr. Beta 0.021 +/- 0.004 0.020 +/- 0.003 0.021 +/- 0.002 Pass S-2277,2278 7/20/2021 K-40 13.6 +/- 0.9 12.3 +/- 0.9 12.9 +/- 0.6 Pass DW-30191,30192 7/20/2021 Gr. Alpha 3.88 +/- 0.94 3.66 +/- 94.00 3.77 +/- 47.00 Pass SG-2382,2383 7/23/2021 Pb-214 1.88 +/- 0.21 1.94 +/- 0.21 1.91 +/- 0.15 Pass SG-2382,2383 7/23/2021 Ac-228 1.69 +/- 0.28 1.96 +/- 0.33 1.83 +/- 0.22 Pass DW-30207,30208 7/26/2021 Gr. Alpha 5.47 +/- 1.29 5.20 +/- 1.24 5.34 +/- 0.89 Pass DW-30207,30208 7/26/2021 Gr. Beta 5.89 +/- 0.77 6.11 +/- 0.73 6.00 +/- 0.53 Pass DW-30210,30211 7/28/2021 Ra-226 0.48+/-0.13 0.62 +/- 0.11 0.55 +/- 0.09 Pass DW-30210,30211 7/28/2021 Ra-228 0.45 +/- 0.53 0.73 +/- 0.65 0.59 +/- 0.42 Pass S-2509,2510 8/1/2021 K-40 14.2 +/- 0.5 13.7 +/- 1.0 14.0 +/- 0.6 Pass S-2509,2510 8/1/2021 Be-7 7.27 +/- 0.29 7.97 +/- 0.69 7.62 +/- 0.37 Pass DW-30221,30222 8/6/2021 Gr. Alpha 2.19 +/- 1.55 2.08 +/- 1.54 2.14+/-1.09 Pass DW-30221,30222 8/6/2021 Gr. Beta 1.19+/-1.04 2.76 +/- 1.08 1.98 +/- 0.75 Pass DW-30221,30222 8/6/2021 Ra-226 2.00 +/- 0.22 1.58 +/- 0.26 1.79+/-0.17 Pass DW-30221,30222 8/6/2021 Ra-228 1.69 +/- 0.56 1.75 +/- 0.54 1.72 +/- 0.39 Pass VE-2551,2552 8/11/2021 K-40 2.68 +/- 0.20 2.61 +/- 0.27 2.64 +/-0.17 Pass VE-2551,2552 8/11/2021 Be-7 0.16+/-0.08 0.18+/-0.08 0.17 +/-0.05 Pass AP-2578,2579 8/12/2021 Be-7 0.18+/-0.09 0.20 +/- 0.11 0.19 +/- 0.07 Pass AP-082421A,B 8/24/2021 Gr. Beta 0.032 +/- 0.004 0.028 +/- 0.004 0.030 +/- 0.003 Pass AP-083121A,B 8/24/2021 Gr. Beta 0.027 +/- 0.004 0.029 +/- 0.004 0.028 +/- 0.003 Pass VE-2684,2685 8/25/2021 K-40 2.15 +/- 0.26 1.92 +/- 0.27 2.03 +/-0.19 Pass VE-2684,2685 8/25/2021 Be-7 0.20+/-0.10 0.26 +/- 0.11 0.23 +/- 0.07 Pass VE-2728,2729 8/25/2021 K-40 2.34 +/- 0.41 2.27 +/- 0.40 2.31 +/- 0.29 Pass A-13

TABLE A-6. lntralaboratory "Duplicate" Samples Concentration*

Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance DW-30238,30239 8/25/2021 Gr. Alpha 3.94 +/- 0.91 2.43 +/- 0.86 3.185 +/-0.63 Pass DW-30238,30239 8/25/2021 Ra-226 2.57 +/- 0.24 1.83 +/- 0.24 2.20 +/-0.17 Pass DW-30238,30239 8/25/2021 Ra-228 2.86 +/- 0.83 2.52 +/- 0.66 2.69 +/- 0.53 Pass SW-2641,2642 8/31/2021 H-3 289 +/- 92 310 +/- 93 300 +/- 65 Pass VE-2858,2859 9/2/2021 K-40 8.36 +/- 0.41 8.02 +/- 0.47 8.19 +/- 0.31 Pass SG-2934,2935 9/13/2021 Pb-214 2.72 +/- 0.22 2.54 +/- 0.27 2.63 +/- 0.17 Pass SG-2934,2935 9/13/2021 Ac-228 3.16 +/- 0.39 3.22 +/- 0.58 3.19 +/- 0.35 Pass DW-30249,30250 9/17/2021 Ra-226 0.70 +/- 0.18 1.00 +/- 0.17 0.85 +/- 0.12 Pass S-3042,3043 9/22/2021 K-40 7.55 +/- 0.80 7.57 +/-0.81 7.56 +/- 0.57 Pass DW-30249,30250 9/17/2021 Ra-226 0.70 +/-0.18 1.00 +/- 0.17 0.85 +/- 0.12 Pass S-3042,3043 9/22/2021 K-40 7.55 +/- 0.80 7.57 +/-0.81 7.56 +/- 0.57 Pass Note: Duplicate analyses are performed on every twentieth sample received. Results are not listed for those analyses with activities that measure below the LLD.

a Results are reported in units of pCi/L, except for air filters (pCi/Filter or pCi/m3), food products, vegetation, soil and sediment (pCi/g).

AP (Air Particulate), AV (Aquatic Vegetation), BS (Bottom Sediment), CF (Cattle Feed), CH (Charcoal Canister),

DW (Drinking Water), E (Egg), F (Fish), G (Grass), LW (Lake Water), Ml (Milk), P (Precipitation), PM (Powdered Milk),

S (Solid), SG (Sludge), SO (Soil), SS (Shoreline Sediment), SW (Surface Water), SWT (Surface Water Treated),

SWU (Surface Water Untreated), VE (Vegetation), W (Water), WW (Well Water).

A-14

TABLE A-7. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).

Concentration a Reference Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAAP-3181 8/1/2020 Gross Alpha 0.45 +/- 0.06 0.528 0.158 -0.898 Pass MAAP-3181 8/1/2020 Gross Beta 0.97 +/- 0.04 0.915 0.458 - 1.373 Pass MADW-3101 8/1/2020 Gross Alpha 0.57 +/- 0.04 0.62 0.19 - 1.05 Pass MADW-3101 8/1/2020 Gross Beta 0.75 +/- 0.04 0.83 0.42 - 1.25 Pass MAS0-3179 8/1/2020 Cs-134 599 +/- 7 710 497 - 923 Pass MAS0-3179 8/1/2020 Cs-137 3.33 +/- 4.81 0 NA c Pass MAS0-3179 8/1/2020 Co-57 1145 +/- 8 1100 770 - 1430 Pass MAS0-3179 8/1/2020 Co-60 965 +/- 9 1000 700 - 1300 Pass MAS0-3179 8/1/2020 Mn-54 651 +/- 11 610 427 - 793 Pass MAS0-3179 8/1/2020 Zn-65 524 +/- 14 470 329 - 611 Pass MAS0-3179 8/1/2020 K-40 684 +/- 58 622 435 - 809 Pass MAW-3175 8/1/2020 Cs-134 13.9 +/- 0.3 15.2 10.6 -19.8 Pass MAW-3175 8/1/2020 Cs-137 15.4 +/- 0.4 14.3 10.0 - 18.6 Pass MAW-3175 8/1/2020 Co-57 0.10 +/- 0.16 0 NA c Pass MAW-3175 8/1/2020 Co-60 12.5 +/- 0.3 12.2 8.5 - 15.9 Pass MAW-3175 8/1/2020 Mn-54 0.07 +/-0.17 0 NA c Pass MAW-3175 8/1/2020 Zn-65 18.3 +/- 0.6 16.9 11.8 - 22.0 Pass MAW-3175 8/1/2020 K-40 1.06 +/- 1.65 0 NA c Pass MAAP-3177 8/1/2020 Cs-134 1.28 +/- 0.05 1.83 1.28 - 2.38 Fail d MAAP-3177 8/1/2020 Cs-137 0.981 +/- 0.068 0.996 0.697 - 1.295 Pass MAAP-3177 8/1/2020 Co-57 0.020 +/- 0.027 0 NA c Pass MAAP-3177 8/1/2020 Co-60 1.57 +/- 0.06 1.73 1.21 - 2.25 Pass MAAP-3177 8/1/2020 Mn-54 0.751 +/- 0.077 1.400 0.98 - 1.82 Fail e MAAP-3177 8/1/2020 Zn-65 2.07 +/-0.15 2.00 1.40 - 2.60 Pass MAVE-3185 8/1/2020 Cs-134 4.73 +/- 0.10 4.94 3.46 - 6.42 Pass MAVE-3185 8/1/2020 Cs-137 0.03 +/- 0.06 0 NA c Pass MAVE-3185 8/1/2020 Co-57 7.83 +/-0.12 6.67 4.67 - 8.67 Pass MAVE-3185 8/1/2020 Co-60 4.41 +/- 0.10 4.13 2.89 - 5.37 Pass MAVE-3185 8/1/2020 Mn-54 6.52 +/- 0.18 5.84 4.09 - 7.59 Pass MAVE-3185 8/1/2020 Zn-65 7.26 +/- 0.19 6.38 4.47 - 8.29 Pass MAAP-594 2/1/2021 Gross Alpha 1.30 +/- 0.08 1.77 0.53 - 3.01 Pass MAAP-594 2/1/2021 Gross Beta 0.81 +/- 0.04 0.649 0.325 - 0.974 Pass MADW-571 2/1 /2021 Gross Alpha 0.73 +/- 0.06 0.87 0.26 - 1.48 Pass MADW-572 2/1/2021 Gross Beta 2.38 +/- 0.06 2.50 1.25 - 3.75 Pass A-15

TABLE A-7. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP).

Concentration*

Reference Known Control Lab Code b Date Analysis Laboratory result Activity Limits c Acceptance MAS0-591 2/1/2021 Cs-134 -2.57 +/- 2.21 0 NA c Pass MAS0-591 2/1/2021 Cs-137 1700 +/- 20 1550 1085 -2015 Pass MAS0-591 2/1/2021 Co-57 977 +/- 7 920 644 - 1196 Pass MAS0-591 2/1/2021 Co-60 1360 +/- 10 1370 959 - 1781 Pass MAS0-591 2/1/2021 Mn-54 0.91 +/- 2.85 0 NA c Pass MAS0-591 2/1/2021 Zn-65 687 - 17 604 423 - 785 Pass MAS0-591 2/1/2021 K-40 682 +/- 53 618 433 - 803 Pass MAW-569 2/1/2021 Cs-134 10.5 +/- 0.3 11.5 8.1 -15.0 Pass MAW-569 2/1 /2021 Cs-137 8.53 +/- 0.32 7.9 5.5 - 10.3 Pass MAW-569 2/1/2021 Co-57 12.2 +/- 0.3 11.4 8.0 - 14.8 Pass MAW-569 2/1/2021 Co-60 0.03 +/- 0.05 0 NA c Pass MAW-569 2/1/2021 Mn-54 16.5 +/- 0.4 15.5 10.9 - 20.2 Pass MAW-569 2/1/2021 Zn-65 11.5 +/- 0.5 10.5 7.40-13.7 Pass 1

MAW-569 2/1/2021 K-40 9.93 +/- 1.42 0 NA c Fail MAAP-592 2/1/2021 Cs-134 1.54 +/- 0.06 2.14 1.50 - 2.78 Pass MAAP-592 2/1/2021 Cs-137 -0.011 +/- 0.020 0 NA c Pass MAAP-592 2/1/2021 Co-57 0.636 +/- 0.042 0.69 0.480 - 0.892 Pass NA c 9 MAAP-592 2/1/2021 Co-60 -0.64 +/- 0.02 0 Fail MAAP-592 2/1/2021 Mn-54 0.312 +/- 0.058 0.312 0.218 - 0.406 Pass MAAP-592 2/1 /2021 Zn-65 0.41 +/- 0.07 0.352 0.246 - 0.458 Pass MAVE-588 2/1/2021 Cs-134 3.73 +/- 0.09 3.60 2.50 4.70 Pass MAVE-588 2/1/2021 Cs-137 5.69 +/- 0.10 4.69 3.28 - 6.10 Pass MAVE-588 2/1/2021 Co-57 6.23 +/- 0.07 5.05 3.54 - 6.57 Pass MAVE-588 2/1/2021 Co-60 3.29 +/- 0.06 2.99 2.09 - 3.89 Pass MAVE-588 2/1/2021 Mn-54 6.17 +/- 0.16 5.25 3.68 - 6.83 Pass MAVE-588 2/1/2021 Zn-65 -0.04 +/- 0.08 0 NA c Pass a Results are reported in units of Sq/kg (soil), Sq/L (water) or Sq/total sample (filters, vegetation).

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

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

d Analysis was run in duplicate. Results were (1.18 Sq/sample and 1.37 Sq/sample). The submitted result was the mean of the two results (1.28 +/- 0.05 Sq/sample).

0 A data transcription error resulted in an erroneous reported value. The actual result (1.36 +/- 0.08 Sq/L) passes.

1 The sample spectrum was reanalyzed utilizing the minimum data point background width method. The result was 1.59 +/- 1. 77 Sq/L which satisfies MAPEP criteria for a false positive test.

9 A decimal was misplaced in one of two cobalt-60 results while calculating a mean result causing MAPEP to fail the result as a statistically significant negative value at 3 standard deviations. The correct mean result (-0.0004 +/- 0.0186) is not a statistically significant negative value and would not have failed.

A-16

TABLE A-8. lnterlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA)*.

MRAD-30 Study Concentration a Lab Code b Date Analysis Laboratory ERA Control 0

Result Value Limits d Acceptance ERAP-722 3/22/2021 Cs-134 898 1030 668 - 1260 Pass ERAP-722 3/22/2021 Cs-137 181 163 134 - 214 Pass ERAP-722 3/22/2021 Co-60 1270 1220 1040 - 1550 Pass ERAP-722 3/22/2021 Mn-54 < 4.3 < 50.0 0.00 - 50.0 Pass ERAP-722 3/22/2021 Zn-65 908 771 632 - 1180 Pass ERAP-722 3/22/2021 Sr-90 184 189 120 - 257 Pass ERAP-724 3/22/2021 Gross Alpha 88.4 96.1 50.2 - 158 Pass ERAP-724 3/22/2021 Gross Beta 74.1 62.6 38.0 - 94.6 Pass a Results obtained by Environmental, Inc., Midwest Laboratory (EIML) as a participant in the crosscheck program for proficiency testing administered by Environmental Resource Associates, serving as a replacement for studies conducted previously by the Environmental Measurements Laboratory Quality Assessment Program (EML).

b Laboratory code ERAP (air filter). Results are reported in units of (pCi/Filter).

0 The ERA Assigned values for the air filter standards are equal to 100% of the parameter present in the standard as determined by the gravimetric and/or volumetric measurements made during standard preparation as applicable.

d The acceptance limits are established per the guidelines contained in the Department of Energy (DOE) report EML-564, Analysis of Environmental Measurements Laboratory (EML) Quality Assessment Program (QAP)

Data Determination of Operational Criteria and Control Limits for Performance Evaluation Purposes or ERA's SOP for the generation of Performance Acceptance Limits.

A-17

APPENDIX B DATA REPORTING CONVENTIONS B-1

Data ReQortjng 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 :t s where: x = value of the measurement; s = 2o counting uncertainty (corresponding to the 95% confidence level).

In CC\!Ses 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 4.660' uncertainty for a background sample.

3.0. Ouplictf!te ~nalyses If duplicate analyses are reported, the convention is as follows. :

3.1 lndividu~I results: For two analysis results; x1 ;1; s1 and "2 +/- s2 Reported result: x :t: s; where x = (1/2) (x 1 +Xi) ands= (1/2) fs~ + si 3.2. Individual results: < L1 , < ~ Reported result: < L, where L =lower of L1 and 1-;i 3.3. Individual results: x +/- s, < L Reported result: x +/- s if x i:!! L; < l otherwise.

4.0. C9mputation of Averages and Stand.ard Deviation§ 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for exa~ple, an annual standard deviation would not be the average of quarterly standard deviations. The avera1;1e x and standard deviation "s" of a set of n numbers x1, x2 . . . xn i:ire defined as follows:

rx s---~

1 x :;;ii '\j-n:1 4.2 Values below the highest lowE;Jr limit of detection are not included in the average.

4.3 If all value11 in the averaging group are less than the highest LLO, 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 assc;>ciated two sigma error is reported.

4.5 In rounding off, the following rules !;tre followed:

4.5.1. If the number following those to be retained is less than 5, the number i11 dropped, and the retaine>d numbers are kept unchanged. As !iln example, 11.443 is roundeq off to 11.44.

4.5.2. If I.ha number following those to be retained is t:1qual 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.

8-2

POINT BEACH NUCLEAR PLANT APPENDIX C Sampling Program and Locations

,POINT BEACH NUCLEAR PLANT Locations Collection Type Analysis Sample Type No. Codes (and Type)" (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 (TL D'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 E-10 Quarterly GB, GS, H-3, Sr-89-90, 1-131 Vegetation 8 E-1-4, 6, 20 2x I year GS as available Shoreline Silt 5 E-1, 5, 6 Annual GS Soil 8 E-1-4, 6, 20 Annual GS Milk 3 E-11,40,21 Monthly GS, 1-131, Sr-89-90 Fish E-13 2x I year GS (in edible portions) as available

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 0-1

POINT BEACH Air Particulates - Gross Beta Location E-1, monthly averages 2017-2021 0.050 -

I

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i ~

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J 0.000 + +-1+1-t-H-H++-t-H-H+t-t- 1-H +H-I -H++-H -H-t+H+H--+-t t-H-H+H+++i 2017 2018 2019 2020 2021 2022 Year Location E-2, monthly averages 2017-2021 0.050 -

I 0.030 0.000 --t-t+H+H-++-H -1 I I 1! i I i++-H -H l-H H- I l+t-H+f- I H - H l l i l i l l f 2017 2018 2019 2020 2021 2022 Year D-2

POINT BEACH Air Particulates - Gross Beta Location E-3, monthly averages 2017-2021 0.050 0.040

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POINT BEACH Air Particulates - Gross Beta Location E-8, monthly averages 2017-2021 0.050 -

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H~ *-+-H--t--l *--I +-H 2017 2018 2019 2020 2021 2022 Year D-4

POINT BEACH NUCLEAR PLANT APPENDIX E Supplemental Analyses E-1

POINT BEACH NUCLEAR PLANT Facade Wells Units: =pCi\L Gamma isotopic analysis Location GW-09 12-361A GW-0912-3618 GW-10 22*361A GW-10 22-3618 Collection Date 03-16-21 03-16-21 03-16-21 03-16-21 Lab Code EWW- 687 MDC EWW- 688 MDC EWW- 689 MDC EWW- 690 MDC 8e-7 36.3 +/- 11.9 < 28.4 14.7 +/- 13.1 < 29.2 29.0 +/- 17.4 < 33.1 5.9 +/- 10.7 < 24.1 Mn-54 -0.1+/-1.3 < 2.4 0.2 +/- 1.3 < 2.6 2.3 +/- 2.0 < 4.0 0.5 +/- 1.3 < 2.8 Fe-59 -1.8+/-2.3 < 4.5 -0.7 +/- 2.6 < 3.3 -4.1 +/- 3.6 < 7.1 1.5 +/- 2.3 < 5.4 Co-58 0.0 +/- 1.3 < 2.3 -0.3 +/- 1.3 < 2.1 -0.9 +/- 1.7 < 2.9 0.4 +/- 1.2 < 2.7 Co-60 -0.9 +/- 1.5 < 1.9 -0.3 +/- 1.3 < 3.1 0.0 +/- 2.1 < 3.7 0.8 +/- 1.4 < 2.1 2n-65 1.9+/-2.4 < 4.8 0.2 +/- 2.8 < 4.0 -6.8 +/- 4.0 < 6.3 -1.4+/-2.8 < 4.7 2r*Nb-95 -2.8 +/- 1.4 < 2.8 0.8 +/- 1.5 < 3.5 0.3 +/- 1.8 < 4.3 -1.6 +/- 1.5 < 3.4 Cs-134 *0.1 +/- 1.4 < 2.3 -1.2 +/- 1.4 < 2.8 0.6 +/- 1.8 < 3.6 0.9+/-1.4 < 2.5 Cs-137 -0.5 +/- 1.5 < 2.8 0.4 +/- 1.6 < 2.7 1.3 +/- 1.9 < 3.5 1.0 +/- 1.6 < 2.9 8a-La-140 -1.4+/-1.4 < 3.4 0.6 +/- 1.6 < 4.5 -0.9 +/- 2.1 < 3.4 -1.0 +/- 1.5 < 3.6 Location GW-09 12-361A GW-0912-3618 GW-10 2Z*361A GW-10 22-3618 Collection Date 06-04-21 06-04-21 06-04-21 06-04-21 Lab Code EWW- 1907 MDC EWW- 1908 MDC EWW- 1910 MDC EWW- 1911 MDC 8e-7 3.1 +/- 14.1 < 28.8 -7.5 +/- 13.4 < 31.2 6.6 +/- 11.0 < 28.1 5.2 +/- 10.5 < 30.3 Mn-54 0.0 +/- 1.5 < 1.6 1.1 +/- 1.4 < 2.2 -0.2 +/- 1.4 < 1.7 -1.0 +/- 1.2 < 2.0 Fe-59 *2.9 +/- 2.8 < 3.9 -1.6+/-2.9 < 5.6 -1.0+/-2.3 < 5.6 0.7 +/- 2.2 < 5.6 Co-58 -0.5 +/- 1.4 < 3.2 -1.1 +/- 1.4 < 1.7 0.1 +/- 1.4 < 2.8 -0.7 +/- 1.3 < 3.2 Co-60 -0.6 +/- 1.7 < 3.4 0.7+/-1.4 < 2.5 *1.0 +/- 1.5 < 2.5 -0.6 +/- 1.4 < 2.8 2n-65 2.0 +/- 3.1 < 6.0 0.8 +/- 3.0 < 5.7 2.1 +/- 2.8 < 5.8 1.8 +/- 2.2 < 3.7 2r-Nb-95 -3.9 +/- 1.5 < 5.0 -1.1 +/- 1.4 < 4.0 -6.6 +/- 1.5 < 4.2 -2.3 +/- 1.4 < 3.5 Cs-134 0.4+/-1.5 < 3.1 -2.1 +/- 1.5 < 3.1 0.5 +/- 1.4 < 2.6 0.2 +/- 1.3 < 2.6 Cs-137 0.8 +/- 1.7 < 3.3 0.5 +/- 1.6 < 2.9 0.5 +/- 1.6 < 2.8 0.7 +/- 1.5 < 2.8 8a-La-140 -2.2 +/- 1.6 < 7.0 -3.1 +/- 1.7 < 8.9 -4.9 +/- 1.6 < 7.7 -8.4 +/- 1.5 < 5.2 GW-09 12-361A GW-09 12-3618 GW-10 22*361A GW-10 22-3618 Collection Date 08-07-21 08-07-21 08-08-21 08-08-21 Lab Code EWW- 2773 MDC EWW- 2774 MDC EWW- 2775 MDC EWW- 2776 MDC 8e-7 -12.2 +/-9.8 < 18.1 -3.9 +/- 7.5 < 18.3 -22.6 +/- 22.2 < 44.7 25.5 +/- 13.5 < 30.1 Mn-54 1.0+/-1.0 < 2.0 0.1 +/- 0.9 < 1.6 0.7 +/- 2.8 < 4.7 0.6 +/- 1.4 < 2.5 Fe-59 2.0 +/- 2.0 < 6.4 -3.6 +/- 1.6 < 4.7 1.0 +/- 4.6 < 13.3 -2.0 +/- 2.6 < 7.0 Co-58 -0.4+/-1.0 < 2.4 0.5 +/- 0.9 < 2.2 1.1 +/- 2.8 < 6.9 0.4 +/- 1.3 < 3.2 Co-60 0.1 +/- 1.1 < 1.3 0.6 +/- 0.9 < 1.7 -0.6 +/- 2.7 < 4.8 1.4 +/- 1.5 < 3.0 2n-65 -1.1 +/- 2.1 < 3.3 0.5 +/- 1.9 < 3.7 4.3 +/- 4.4 < 9.6 -1.1 +/- 2.8 < 4.1 2r-Nb-95 -1.8 +/- 1.1 < 4.3 -1.6 +/- 1.0 < 3.8 -2.6 +/- 2.9 < 9.5 -2.7+/-1.5 < 5.7 Cs-134 -0.3 +/- 1.0 < 2.2 0.1 +/-1.0 < 1.8 -0.1 +/- 2.8 < 5.1 -0.3 +/- 1.5 < 3.1 Cs-137 0.8 +/- 1.1 < 2.4 0.0 +/- 1.1 < 1.8 -0.5 +/- 2.9 < 4.8 0.9 +/- 1.6 < 3.0 8a-La-140 -14.3 +/- 1.2 < 7.5 0.8 +/- 1.0 < 11.1 9.1 +/- 2.8 < 7.7 -8.2 +/- 1.6 < 15.7 "

. TITiilolreacliooaue!OTiite arnvaraiiasmall samp es ze.

E-2

POINT BEACH NUCLEAR PLANT Location GW-091Z-361A GW-09 12-3618 GW-10 2Z-361A GW-10 22-3618 Collection Date 10-16-21 10-16-21 10-16-21 10-16-21 Lab Code EWW- 3457 MOC EWW- 3458 MOC EWW- 3459 MOC EWW- 3460 MDC 8e-7 -3.9 +/- 14.3 < 22.2 -3.9 +/- 10.5 < 14.8 -14.4 +/- 9.9 < 17.7 -16.8 +/- 13.8 < 27.7 Mn-54 -0.9 +/- 1.4 < 2.3 0.0 +/- 1.4 < 2.6 1.2 +/- 1.3 < 2.7 0.1 +/- 1.4 < 2.8 Fe-59 -0.5 +/- 2.8 < 3.1 -0.1 +/- 2.2 < 5.2 -1.0+/-2.4 < 3.6 -2.0 +/- 3.0 < 6.3 Co-58 1.8 +/- 1.4 <: 3.2 0.2 +/- 1.3 < 2.5 0.0 +/- 1.3 < 2.8 -0.1 +/- 1.4 < 3.2 Co-60 1.1 +/- 1.6 < 3.1 1.0 +/- 1.5 < 3.1 -0.4 +/- 1.4 < 2.0 -0.2 +/- 1.4 < 2.5 Zn-65 -1.3 +/- 3.4 < 4.8 1.4+/-2.6 < 4.4 0.5 +/- 2.6 < 3.9 -1.2+/-3.4 < 4.9 Zr-Nb-95 -0.3 +/- 1.6 < 2.9 -1.5 +/- 1.5 < 2.6 -0.3 +/- 1.4 < 3.5 -3.6 +/- 1.5 < 4.3 Cs-134 -0.6 +/- 1.6 < 3.1 -0.8 +/- 1.4 < 2.6 -0.6 +/- 1.4 < 2.6 -2.0+/-1.5 < 3.1 Cs-137 -0.8 +/- 1.7 < 2.6 1.5+/-1.5 < 2.8 0.5 +/- 1.5 < 2.9 -0.1 +/- 1.6 < 2.5 Ba-La-140 -3.0 +/- 1.8 < 2.7 1.7+/-4.2 < 2.7 -0.3 +/- 1.5 < 4.6 -4.1 +/- 1.8 < 4.0 E-3

POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: ::: pCi/L Gamma isotopic analysis Location GW-04 U2FSSDS GW-15A.B Collection Date 01-21-21 01-31-21 01-28-21 Lab Code EW- 180 MDC EW- 471 MDC EW- 222 MDC Be-7 7.5 +/- 18.3 < 41.4 0.6 +/- 10.8 < 34.7 -5.0 +/- 12.9 < 32.3 Mn-54 0.0 +/- 2.0 < 3.7 0.1 +/-1.3 < 2.4 0.5 +/- 1.6 < 3.3 Fe-59 -1.1 +/- 3.8 < 6.3 -1.6 +/- 2.3 < 7.2 -0.6 +/- 2.6 < 4.0 Co-58 1.1 +/- 1.7 < 2.1 -0.4 +/- 1.4 < 4.3 -0.3 +/- 1.4 < 3.0 Co-60 0.8 +/- 2.0 < 2.9 0.2 +/- 1.5 < 2.0 0.3 +/- 1.7 < 3.3 Zn-65 -5.6 +/- 4.5 < 5.9 0.3 +/- 2.6 < 4.2 0.9 +/- 3.1 < 6.4 Zr-Nb-95 -5.7 +/- 2.4 < 5.4 -1.8 +/- 1.5 < 3.0 -2.5 +/- 1.7 < 4.5 Cs-134 -0.8 +/- 2.1 < 3.7 -0.8 +/- 1.3 < 2.4 -0.1 +/- 1.5 < 2.9 Cs-137 0.1 +/- 2.0 < 2.5 -0.9 +/- 1.5 < 2.3 1.5 +/- 1.8 < 3.2 Ba-La-140 -3.0 +/- 2.0 < 3.9 -1.2 +/- 1.5 < 12.4 -1.6+/-1.8 < 6.8 Location U2FSSDS GW-04 GW-04 Collection Date 02-28-21 02-17-21 03-25-21 Lab Code EW- 685 MDC EW- 400 MDC EW- 781 MDC Be-7 1.7 +/- 10.7 < 29.4 -6.8 +/- 18.4 < 20.8 -8.0 +/- 19.6 < 28.8 Mn-54 1.0 +/- 1.3 < 2.3 0.7 +/- 1.7 < 3.0 -0.9 +/- 2.2 < 2.9 Fe-59 -0.7 +/- 2.2 < 4.4 1.3 +/-3.7 < 3.6 -2.4 +/- 4.5 < 6.2 Co-58 0.2 +/- 1.2 < 2.9 -0.4 +/- 1.8 < 2.1 0.3 +/- 1.9 < 2.3 Co-60 0.7 +/- 1.3 < 2.5 0.1 +/- 2.0 < 2.4 0.9 +/- 2.3 < 2.4 Zn-65 -0.6 +/- 2.6 < 4.8 -2.1 +/- 4.0 < 2.9 3.2 +/- 4.5 < 5.2 Zr-Nb-95 -0.4 +/- 1.5 < 4.1 0.2 +/- 2.2 < 4.5 -3.7 +/- 2.7 < 2.2 Cs-134 -0.3 +/- 1.3 < 2.5 -1.6 +/- 2.0 < 3.9 -5.5 +/- 2.6 < 3.9 Cs-137 -0.6 +/- 1.5 < 2.1 -0.4 +/- 2.4 < 4.5 -0.8 +/- 2.1 < 2.2 Ba-La-140 0.3 +/- 1.4 < 7.0 -1.4 +/- 2.3 < 3.4 1.8 +/- 2.5 < 5.1 Location U2FSSDS GW-04 U2FSSDS Collection Date 03-31-21 MDC 04-23-21 MDC 04-30-21 MDC Lab Code EWW- 1251 EWW- 1201 EWW- 1413 Be-7 9.7 +/- 12.0 < 31.3 13.3 +/- 10.7 < 35.6 -0.6 +/- 10.1 < 25.5 Mn-54 2.4 +/- 1.3 < 3.1 0.1+/-1.4 < 2.0 -0.6 +/- 1.3 < 2.6 Fe-59 4.5 +/- 2.6 < 8.1 -3.3 +/- 1.8 < 2.6 -2.0 +/- 2.2 < 3.7 Co-58 0.9 +/- 1.2 < 2.4 -0.1 +/- 1.2 < 1.5 0.0 +/- 1.2 < 2.5 Co-60 0.4 +/- 1.3 < 2.4 -0.3 +/- 1.3 < 2.2 -0.5 +/- 1.3 < 2.5 Zn-65 -3.0 +/- 2.9 < 4.2 2.5 +/- 2.4 < 4.2 -1.6 +/- 2.5 < 4.1 Zr-Nb-95 -3.3 +/- 2.3 < 4.5 1.0 +/- 1.3 < 3.7 -0.4 +/- 1.3 < 3.7 Cs-134 0.2 +/- 1.4 < 2.9 0.2 +/- 1.2 < 2.6 -0.7+/-1.3 < 2.5 Cs-137 0.8 +/- 1.5 < 2.7 -0.1 +/- 1.4 < 2.0 0.1 +/- 1.5 < 2.6 Ba-La-140 -1.2 +/- 1.6 < 13.2 -1.8 +/- 1.5 < 8.5 -1.1 +/- 1.5 < 4.9 E-4

POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: =pCi\L Gamma isotopic analysis Location GW-15A,8 GW-04 U2FSSDS Collection Date 05-14-21 05-19-21 05-31-21 Lab Code EW- 1567 MDC EW- 1488 MDC EW- 2025 MDC Be-7 -5.5 +/- 14.9 < 29.5 -2.5 +/- 15.0 < 36.3 4.2 +/- 10.7 < 38.4 Mn-54 -0.7 +/- 1.6 < 3.6 -0.9 +/- 1.7 < 2.4 0.6 +/- 1.3 < 2.7 Fe-59 -5.2 +/- 3.1 < 4.5 -2.4 +/- 2.8 < 3.8 3.4 +/- 2.5 < 8.7 Co-58 1.0 +/- 1.5 < 2.8 0.5 +/- 1.7 < 2.5 0.4 +/- 1.3 < 3.0 Co-60 -0.3 +/- 1.6 < 2.1 0.3 +/- 1.9 < 2.5 -0.9 +/- 1.4 < 2.1 Zn-65 -0.1 +/- 3.5 < 6.2 -0.5 +/- 2.8 < 3.6 0.5 +/- 2.6 < 4.6 Zr-Nb-95 0.1 +/- 1.5 < 3.7 0.4 +/- 1.7 < 4.6 -5.2 +/- 1.5 < 5.9 Cs-134 1.2 +/- 1.6 < 3.2 -0.6+/-1.8 < 3.4 0.8 +/- 1.4 < 2.6 Cs-137 -0.2 +/- 1.8 < 2.2 -0.5 +/- 1.9 < 3.2 0.1 +/- 1.6 < 2.8 Ba-La-140 -5.4 +/- 1.8 < 3.8 -7.0 +/- 6.4 < 2.5 -19.4 +/- 1.5 < 9.1 Location GW-07 (North Bog) GW-04 U2FSSDS Collection Date 05-19-21 06-17-21 06-30-21 Lab Code EW- 1489 MDC EW- 1906 MDC EW- 2325 MDC Be-7 4.9 +/- 4.6 < 23.1 -5.5 +/- 11.1 < 22.6 -10.1 +/- 13.6 < 33.5 Mn-54 -0.1 +/- 0.5 < 0.9 0.7 +/- 1.4 < 2.4 0.3 +/- 1.4 < 3.2 Fe-59 -0.6 +/- 0.9 < 3.5 -0.3 +/- 2.6 < 5.9 2.3 +/- 2.7 < 8.2 Co-58 0.2 +/- 0.5 < 1.4 -0.6 +/- 1.2 < 1.3 -1.4 +/- 1.4 < 1.7 Co-60 -0.3 +/- 0.5 < 0.6 0.3 +/- 1.0 < 2.0 0.6+/-1.5 < 2.4 Zn-65 0.1 +/- 1.0 < 2.3 0.1 +/- 2.6 < 4.9 -0.7 +/- 3.2 < 6.3 Zr-Nb-95 -0.7 +/- 0.6 < 2.3 -1.7 +/- 1.5 < 3.2 0.1 +/- 1.5 < 4.8 Cs-134 -0.2 +/- 0.6 < 1.0 0.7+/-1.3 < 2.5 0.9 +/- 1.5 < 3.0 Cs-137 0.0 +/- 0.6 < 1.2 1.2 +/- 1.3 < 2.7 -0.3 +/- 1.7 < 2.7 Ba-La-140 -2.2 +/- 0.6 < 14.7 -1.6 +/- 4.3 < 4.8 2.6 +/- 1.6 < 13.5 Location GW-04 GW-15A,8 U2FSSDS Collection Date 07-21-21 07-22-21 07-31-21 Lab Code EW- 2330 MDC EW- 2483 MDC EW- 2573 MDC Be-7 -9.9 +/- 10.9 < 27.4 -5.2 +/- 12.4 < 27.9 -4.0 +/- 9.9 < 19.3 Mn-54 -1.1 +/- 1.3 < 1.4 0.3 +/- 1.6 < 3.8 0.8 +/- 1.3 < 2.3 Fe-59 -1.2 +/- 2.7 < 2.8 -2.3 +/- 2.8 < 6.9 -0.1+/-2.3 < 5.2 Co-58 0.4 +/- 1.3 < 2.6 -0.5 +/- 1.5 < 2.7 0.1 +/- 1.3 < 2.6 Co-60 -0.8 +/- 1.1 < 1.3 -0.6 +/- 1.6 < 3.3 0.7+/-1.3 < 2.7 Zn-65 1.3 +/- 2.2 < 3.0 -4.0 +/- 2.9 < 4.8 -2.4 +/- 2.3 < 3.6 Zr-Nb-95 -1.4 +/- 1.4 < 2.0 -3.4 +/- 1.7 < 4.1 0.1 +/- 1.3 < 3.5 Cs-134 -0.6 +/- 1.5 < 2.7 1. 1 +/- 1.5 < 2.9 -0.4 +/- 1.4 < 2.6 Cs-137 -1.2 +/- 1.6 < 2.7 -0.6+/-1.7 < 2.4 -1.0+/-1.4 < 2.6 Ba-La-140 -2.5 +/- 2.0 < 5.4 0.2 +/- 1.8 < 11.4 -1.8 +/- 1.4 < 7.9

HTD analyses in app. F E-5

POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: =pCi\L Gamma isotopic analysis Location U2FSSDS GW-04 U2FSSDS Collection Date 08-31-21 08-19-21 09-30-21 Lab Code EW- 3072 MDC EW- 2645 MDC EW- 3256 MDC Be-7 3.8 +/- 9.9 < 27.4 -5.8 +/- 10.7 < 18.5 -8.7 +/- 10.1 < 18.4 Mn-54 1.3 +/- 1.3 < 3.0 -1.3 +/- 1.2 < 1.6 -0.5 +/- 1.3 < 2.1 Fe-59 -3.7 +/- 2.4 < 4.6 -1.7+/-2.5 < 4.3 -0.1 +/- 2.3 < 5.4 Co-58 0.7 +/- 1.2 < 3.0 0.7 +/- 1.2 < 1.9 0.0 +/- 1.3 < 2.8 Co-60 -1.1 +/- 1.4 < 2.7 -0.1 +/- 1.1 < 1.7 0.4 +/- 1.3 < 2.7 Zn-65 -0.9 +/- 2.7 < 5.7 0.1 +/- 2.3 < 3.9 0.8 +/- 2.4 < 4.4 Zr-Nb-95 -2.4 +/- 1.4 < 4.7 0.1 +/- 1.3 < 2.0 0.9+/-1.4 < 2.7 Cs-134 0.0 +/- 1.4 < 2.5 -0.1 +/- 1.2 < 2.3 -1.1 +/- 1.3 < 2.5 Cs-137 0.4+/-1.5 < 2.5 0.7 +/- 1.5 < 3.0 -0.8 +/- 1.5 < 2.3 Ba-La-140 -0.7 +/- 1.4 < 8.3 -0.3 +/- 1.4 < 2.2 -2.3 +/- 1.5 < 2.9 Location GW-04 GW-18 GW-04 Collection Date 09-16-21 10-12-21 10-19-21 Lab Code EW- 2992 MDC EW* 3441 MDC EW- 3464 MDC Be-7 -2.4 +/- 4.5 < 7.5 6.3 +/- 17.6 < 24.5 7.6 +/- 13.2 < 36.2 Mn-54 0.1 +/- 0.6 < 1.0 -0.1 +/- 1.9 < 2.8 -0.3 +/- 1.8 < 3.4 Fe-59 -0.5 +/- 1.0 < 2.0 -3.5 +/- 3.3 < 4.6 -0.2 +/- 3.1 < 5.4 Co-58 0.4 +/- 0.6 < 1.2 0.4 +/- 2.0 < 5.1 -0.8 +/- 1.5 < 2.6 Co-60 -0.1 +/- 0.6 < 0.9 1.5 +/- 1.4 < 1.7 1.9 +/- 1.6 < 2.7 Zn-65 -0.4 +/- 1.1 < 2.3 1.8 +/- 4.0 < 4.4 1.3 +/- 2.5 < 5.8 Zr-Nb-95 -0.2 +/- 0.6 < 1.5 -3.2 +/- 1.9 < 5.0 -1.8+/-1.6 < 3.3 Cs-134 -0.3 +/- 0.6 < 1.1 -1.9 +/- 2.0 < 4.0 0.1 +/- 1.5 < 2.9 Cs-137 0.4 +/- 0.7 < 1.2 1.1 +/- 2.1 < 3.9 -1.4 +/- 2.0 < 2.1 Ba-La-140 0.3 +/- 0.6 < 2.6 2.2 +/- 1.4 < 7.1 -3.5 +/- 1.6 < 7.1 Location GW-15A,B U2FSSDS GW-04 Collection Date 10-17-21 10-31-21 11-18-21 Lab Code EW- 3506 MDC EW- 3898 MDC EW- 3905 MDC Be-7 -3.3 +/- 13.8 < 24.3 *0.7 +/- 11.0 < 33.0 6.8 +/- 14.1 < 34.3 Mn-54 0.0 +/- 1.4 < 2.5 2.0 +/- 1.4 < 2.8 -0.4+/-1.3 < 1.7 Fe-59 0.1 +/- 2.9 < 4.1 -0.9 +/- 2.4 < 5.8 -1.8 +/- 2.3 < 5.6 Co-58 0.1 +/- 1.4 < 3.1 0.2 +/- 1.4 < 3.7 2.4 +/- 1.4 < 2.6 Co-60 *0.7 +/- 1.4 < 2.1 0.0 +/- 1.4 < 2.1 -0.4 +/- 1.5 < 2.0 Zn-65 -2.9 +/- 3.1 < 4.1 -1.6 +/- 2.6 < 5.4 0.8 +/- 3.3 < 6.2 Zr-Nb-95 -0.1 +/- 1.4 < 2.6 -0.7 +/- 1.5 < 4.3 -0.9 +/- 1.7 < 2.8 Cs-134 0.2 +/- 1.5 < 3.0 -0.8 +/- 1.4 < 2.6 0.2 +/- 1.5 < 2.9 Cs-137 -0.5 +/- 1.6 < 2.1 -0.6 +/- 1.5 < 2.1 -0.2 +/- 1.7 < 2.5 Ba-La-140 -2.2 +/- 1.6 < 3.5 -1.8 +/- 1.7 < 9.2 1.4 +/- 2.0 < 9.1 E-6

POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: =pCi\L Gamma isotopic analysis Location U2FSSDS GW-04 U2FSSDS Collection Date 11-30-21 12-16-21 12-31-21 Lab Code EW- 4132 MDC EW- 4093 MDC EW- 4389 MDC Be-7 -9.6 +/- 9.8 < 30.6 -6.0 +/- 19.1 < 39.2 2.5 +/- 10.4 < 28.3 Mn-54 0.3 +/- 1.2 < 2.4 1.6 +/- 1.8 < 2.9 -0.8 +/- 1.3 < 2.2 Fe-59 0.6 +/- 2.2 < 7.7 -0.7 +/- 3.7 < 4.8 -1.1 +/-2.3 < 6.0 Co-58 0.8 +/- 1.2 < 3.6 0.9 +/- 1.9 < 2.9 -1.3 +/- 1.3 < 2.1 Co-60 0.2 +/- 1.3 < 2.3 0.5 +/- 1.8 < 2.3 -0.8 +/- 1.2 < 2.3 Zn-65 -3.5 +/- 2.3 < 4.3 -0.5 +/- 4.0 < 3.1 -2.4 +/- 2.7 < 4.4 Zr-Nb-95 -1.9 +/- 1.4 < 5.4 -0.1 +/-1.7 < 3.5 -1.5+/-2.1 < 3.7 Cs-134 -0.8 +/- 1.3 < 2.4 0.6 +/- 2.0 < 3.8 -1.1 +/- 1.3 < 2.5 Cs-137 -0.1 +/- 1.4 < 2.2 1.7 +/- 2.0 < 4.0 1.8 +/- 1.5 < 2.9 Ba-La-140 -0.2 +/- 1.4 < 11.9 -0.2 +/- 2.5 < 7.2 0.5 +/- 4.3 < 6.5 E-7

POINT BEACH NUCLEAR PLANT APPENDIX F Special Analyses F-1

POINT BEACH NUCLEAR PLANT Additional Analyses Location U2FSSDS MDC Collection Date 07-31-21 Lab Code EW- 2573 Fe-55 -65.4 +/- 337.6 < 562.2 Ni-63 23.90 +/- 42.2 < 68.8 Sr-89 -2.51 +/- 3.9 < 4.50 Sr-90 1.26 +/- 1.4 < 2.66 Tc-99 0.0 +/- 6.7 < 10.98 Location: E-01 (Meteorological Tower) MDC pCi/L Collection Date 10-12-21 Lab Code ELW- 3328 H-3 1404.0 +/- 145.4 < 169 Location: E-01 (MeteorologicalTower) MDC pCi/L Collection Date 11-10-21 Lab Code ELW- 3793 H-3 65.8 +/- 145.4 < 168 Location: E-01 (Meteorological Tower) MDC pCi/L Collection Date 12-07-21 Lab Code ELW- 4013 H-3 102.9 +/- 93.3 < 167 F-2

J!+!L ATI Environmental, Inc.

"+~/"\I Midwest Laboratory 700 Landwehr Road* Northbrook, IL 60062-2310 phone (847) 564-0700 *fox (847) 564-4517 Amended Report*

Jerri Walters LABORATORY REPORT NO.: 8006-100-1422-A Radiation Protection Mgr. SAMPLES RECEIVED: 04-09-21 Point Beach Nuclear Plant PURCHASE ORDER NO.:

NextEraEnergy 6610 Nuclear Road Two Rivers, WI 54241 Below are the results of the readout of supplemental TLDs deployed during the first quarter, 2021.

Period: 1st Quarter, 2021 Date Annealed: 12/03/20 Date Placed: 01/08/21 Date Removed:(SGSF-N/S/E/W, ISFSl-N/S/E/W) 04/06/21 Date Removed:(Control) 04/08/21 Date Read: 04/14/21 Days in the Field:(SGSF-N/S/E/W, ISFSl-N/S/E/W) 88 Days in the Field:{Control) 90 Days from Annealing to Readout: 132 In-transit exposure: 7.56 +/- 0.51 NetmR NetmR Location Total mR NetmR Std Qtr per 7 days SGSF-North 19.4 +/- 1.0 11.9+/-1.1 12.3 +/- 1.2 0.94 +/- 0.09 SGSF-East 20.6+/-1.0 13.0+/-1.1 13.5+/-1.1 1.04 +/- 0.09 SGSF-South 20.3 +/- 0.5 12.7+/-0.7 13.1 +/- 0.7 1.01 +/- 0.05 SGSF-West 20.4 +/- 1.4 12.8+/-1.5 13.3 +/- 1.6 1.02 +/- 0.12 ISFSl-North 37.3 +/- 0.7 29.8 +/- 0.8 30.8 +/- 0.9 2.37 +/- 0.07 ISFSl-East 57.4 +/- 1.3 49.8+/-1.4 51.5 +/- 1.4 3.96 +/- 0.11 ISFSl-South 25.2 +/- 0.9 17.7 +/- 1.0 18.3+/-1.0 1.41 +/- 0.08 ISFSl-West 54.0 +/- 2.0 46.4 +/- 2.1 48.0 +/- 2.2 3.69 +/- 0.17 Control 25.2 +/- 0.9 17.6 +/- 1.1 17.8+/-1.1 1.37 +/- 0.08

The report approved 5/11/21 had incorrect quarterly and weekly values for SGSF and ISFSI locations due to erroneous removal dates.

Forrest G. Shaw Ill

-==-----~-~ 5f<1fr1 Ashok Banavali, Ph.D.

Quality Assurance Laboratory Manager

!l+L. All Environmental, Inc.

~~/'"\I Midwest Laboratory 700 Landwehr Road* Northbrook. IL 60062-2310 phone (847) 564-0700 *fax (847) 564-4517 Darren Peterson LABORATORY REPORT NO.: 8006-100-1427 Radiation Protection Mgr. SAMPLES RECEIVED: 07-06-21 Point Beach Nuclear Plant PURCHASE ORDER NO.:

NextEraEnergy 6610 Nuclear Road Two Rivers, WI 54241 Below are the results of the readout of supplemental TLDs deployed during the second quarter, 2021.

Period: 2nd Quarter, 2021 Date Annealed: 03/04/21 Date Placed:(SGSF-N/S/E/W. ISFSl-N/S/E/W) 04/06/21 Date Placed:(Control) 04/08/21 Date Removed: 07/01/21 Date Read: 07/09/21 Days in the Field:(SGSF-N/S/E/W, ISFSl-N/S/E/W) 86 Days in the Field:(Control) 84 Days from Annealing to Readout: 127 In-transit exposure: 6.98 +/- 0.42 NetmR NetmR Location Total mR Net mR Std Qtr per 7 days SGSF-North 18.3 +/- 0.8 11.4 +/- 0.9 12.0 +/- 0.9 0.93 +/- 0.07 SGSF-East 19.0 +/- 0.4 12.0 +/- 0.6 12.7 +/- 0.6 0.98 +/- 0.05 SGSF-South 19.5 +/- 0.9 12.5+/-1.0 13.2 +/- 1.1 1.02 +/- 0.08 SGSF-West 19.3 +/- 0.9 12.3+/-1.0 13.0+/-1.1 1.00 +/- 0.08 ISF SI-North 32.3 +/- 2.0 25.3 +/- 2.0 26.8+/-2.1 2.06 +/- 0.16 ISF SI-East 54.1+/-1.5 47.1+/-1.5 49.8 +/- 1.6 3.83 +/- 0.13 ISFSl-South 26.6+/-1.4 19.6 +/- 1.5 20.8+/-1.5 1.60+/-0.12 ISFSl-West 60.5 +/- 2.4 53.5 +/- 2.4 56.7 +/- 2.6 4.36 +/- 0.20 Control 23.6 +/- 1.3 16.6+/-1.4 18.0+/-1.5 1.39+/-0.11 Ashok Banavali, Ph.D.

Quality Assurance Laboratory Manager

~*L.

7+~r'\I Al"I Midwest El}vironmental, Inc.

Laboratory 700 Landwehr Rood* Northbrook. IL 60062-2310 phono (847) 564-0700 *Ito: (847) 564-*1!517 Jerri Walters LABORATORY REPORT NO.: 8006-100-1440 Radiation Protection Mgr. SAMPLES RECEIVED: 10-05-21 Point Beach Nuclear Plant PURCHASE ORDER NO.:

NextEraEnergy 661 O Nuclear Road Two Rivers, WI 54241 Below are the results of the readout of supplemental TLDs deployed during the third quarter, 2021.

Period: 3rd Quarter, 2021 Date Annealed: 06/03/21 Date Placed: 07/01/21 Date Removed: 10/03/21 Date Read: 10/07/21 Days in the Field: 94 Days from Annealing to Readout: 126 In-transit exposure: 5.10 +/-0.36 NetmR NetmR Location Total mR NetmR Std Qtr per7 days SGSF-North 17.3 +/- 0.8 12.2 +/- 0.9 11.8 +/- 0.9 0.91 +/-0.07 SGSF-East 17.3 +/- 0.7 12.2 +/- 0.8 11.8 +/- 0.8 0.91 +/-0.06 SGSF-South 18.4 +/- 0.6 13.3 +/-0.7 12.9 +/- 0.6 0.99 +/- 0.05 SGSF-West 17.6 +/- 0.6 12.5 +/- 0.7 12.1 +/-0.7 0.93 +/- 0.05 ISFSl-North 38.6 +/-2.8 33.5 +/-2.8 32.4 +/-2.7 2.50 +/-0.21 ISFSJ-East 54.9 +/- 1.5 49.8+/-1.6 48.2+/-1.5 3.71 +/- 0.12 JSFSJ-Soulh 42.5 +/- 1.5 37.4+/-1.6 36.2+/-1.5 2.78 +/-0.12 JSFSl-West 104.5 +/- 5.5 99.4 +/- 5.5 96.2 +/- 5.4 7.40 +/- 0.41 Control 22.6+/-1.0 17.5+/-1.1 16.9 +/- 1.1 1.30 +/-0.08 APPROVED ~* ~1~J~Jz1 Forrest G. Shaw Ill Ashok Banavali, Ph.D.

Quality Assurance Laboratory Manager

~*IL._ A-rl Environmental, 7+~J"""\.I Midwest Laboratory Inc.

700 Landwehr Road* Northbrook, IL 60062~23 to phone (847) 564-0700 *fax (847) 56*1-4517 Darren Peterson LABORATORY REPORT NO.: 8006-100-1454 Radiation Protection Mgr. SAMPLES RECEIVED: 01-06-22 Point Beach Nuclear Plant PURCHASE ORDER NO.:

NextEraEnergy 6610 Nuclear Road Two Rivers, WI 54241 Below are the results of the readout of supplemental TLDs deployed during the fourth quarter, 2021.

Period: 4th Quarter, 2021 Date Annealed: 09/07/21 Date Placed: 10/03/21 Date Removed: 01/03/22 Date Read: 01/07/22 Days in the Field: 92 Days from Annealing to Readout: 122 In-transit exposure: 5.63 +/- 0.39 NetmR NetmR Location Total mR NetmR Std Qtr per 7 days SGSF-North 19.4 +/- 0.9 13.8 +/- 1.0 13.7+/-1.0 1.05 +/- 0.08 SGSF-East 19.7 +/-0.4 14.1 +/- 0.6 14.0 +/- 0.6 1.07 +/- 0.04 SGSF-South 20.3 +/- 1.1 14.7+/-1.2 14.6 +/- 1.2 1.12 +/- 0.09 SGSF-West 20.2+/-1.0 14.6+/-1.1 14.4 +/- 1.1 1.11 +/-0.08 ISFSl-North 37.1 +/-2.3 31.5 +/-2.4 31.2 +/-2.4 2.40+/-0.18 ISFSl-East 63.2+/-1.9 57.6+/-1.9 57.0+/-1.9 4.38 +/- 0.15 ISFSl-South 48.7 +/-2.0 43.1 +/-2.1 42.6 +/-2.0 3.28+/-0.16 ISFSl-West 111.9 +/- 3.4 106.3 +/- 3.4 105.1 +/-3.4 8.09 +/- 0.26 Control 24.6+/-1.5 19.0+/-1.6 18.8+/-1.6 1.44+/-0.12 APPAOV~Jl//"J-f/2-2/

Ashok Banavall, Ph.D.

Quality Assurance Laboratory Manager

NRC 2022-0014, 2021 Annual Monitoring Report

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NRC 2022-0014, 2021 Annual Monitoring Report

Text

SUMMARY

1.0 INTRODUCTION

Reference:

8.0 INTRODUCTION

Description:

SUMMARY

SUMMARY

1.0 INTRODUCTION

1.0 INTRODUCTION

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