Text

Annual Monitoring Report
	ML24117A243
Person / Time
Site:	Point Beach
Issue date:	04/26/2024
From:	Rasmus P; Point Beach
To:	; Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk
References
	L-2024-067
	Download: ML24117A243 (1)
	v • d • e

NEXTera ENERGYe April 26, 2024 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 2023 Annual Monitoring Report POINT BEACH L-2024-067 10 CFR 72.44 TS 5.6.2 Enclosed is the Annual Monitoring Report for PBNP Units 1 and 2, for the period January 1 through December 31, 2023.

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

Should you have any questions regarding this submission, please contact Mr. Kenneth Mack, Fleet Licensing Manager, at 561-904-3635.

Sincerely, Paul Rasmus General Manager, Regulatory Affairs

Enclosure:

Annual Monitoring Report 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 661 O Nuclear Road, Two Rivers, WI 54241

ENCLOSURE ANNUAL MONITORING REPORT 2023 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, 2023 through December 31, 2023

TABLE OF CONTENTS Summary Part A: Effluent Monitoring Introduction 1.0 2.0 3.0 4.0 5.0 6.0 Radioactive Liquid Releases Radioactive Airborne Releases Radioactive Solid Waste Shipments Nonradioactive Chemical Releases Circulating Water System Operation Part B: Miscellaneous Reporting Requirements 7.0 Additional Reporting Requirements Part C: Radiological Environmental Monitoring 8.0 Introduction 9.0 Program Description 10.0 Results 11.0 Discussion 12.0 REMP Conclusion Part D: Groundwater Monitoring 13.0 Program Description

14. 0 Results and Discussion 15.0 Groundwater Summary 1

3 4

10 17 19 20 21 22 23 35 40 55 56 59 66 Appendix 1: Microbac Laboratories Inc., "Final Report for Point Beach Nuclear Plant and Other Analyses" Reporting Period: January - December 2023 ii

Table 2-1 Table 2-2 Table 2-3 Table 2-4 Table 3-1 Table 3-2 Table 3-3 Table 3-4 Table 3-5 Table 4-1 Table 4-2 Table 4-3 Table 6-1 Table 9-1 Table 9-2 Table 9-3 Table 9-4 Table 9-5 Table 9-6 Table 10-1 Table 10-2 Table 11-1 Table 11-2 Table 11-3 Table 14-1 Table 14-2 Table 14-3 Table 14-4 Table 14-5 Table 14-6 Table 14-7 Table 14-8 LIST OF TABLES Comparison of 2023 Liquid Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives 4

Summary of Circulating Water Discharge 6

Isotopic Composition of Circulating Water Discharges 7

Beach and Subsoil System Drains - Tritium Summary 8

Curies Released and Dose Calculations from Abnormal Gaseous Release 13 Comparison of 2023 Airborne Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives 14 Radioactive Airborne Effluent Release Summary 14 Isotopic Composition of Airborne Releases 15 Comparison of Airborne Effluent Doses 16 Quantities and Types of Waste Shipped from PBNP in 2023 17 2023 PBNP Radioactive Waste Shipments 17 2023 Estimated Solid Waste Major Radionuclide Composition 18 Circulating Water System Operation for 2023 20 PBNP REMP Sample Analysis and Frequency 25 PBNP REMP Sampling Locations 26 ISFSI Sampling Sites 30 Minimum Acceptable Sample Size 30 Deviations from Scheduled Sampling and Frequency During 2023 31 Sample Collection for the State of Wisconsin 31 Summary of Radiological Environmental Monitoring Results for 2023 37-38 Average ISFSI Fence TLD Results for 2023 39 Average Indicator TLD Results from 1993-2023 40 Average ISFSI Fence TLD Results (mR/7days) 41 Average TLD Results Surrounding the ISFSI (mR/7days) 43 Intermittent Streams and Bogs 59 2023 Beach Drain Tritium 60 2023 East Yard Area Manhole Tritium (pCi/L) 61 2023 Fagade Well Water Tritium (pCi/L) 62 2018-2023 Unit 2 Fagade SSD Sump H-3 (pCi/L) 62 2023 Potable Well Water Tritium Concentration (pCi/L) 64 2023 Quarterly Monitoring Well Tritium (pCi/L) 64 2022 Air Conditioning Tritium Concentration (pCi/L) 65 iii

Figure 9-1 Figure 9-2 Figure 9-3 Figure 11-1 Figure 11-2 Figure 11-3 Figure 11-4 Figure 11-5 Figure 11-6 Figure 11-7 Figure 11-8 Figure 11-9 Figure 11-10 Figure 13-1 LIST OF FIGURES PBNP REMP Sampling Sites Map of REMP Sampling Sites Located Around PBNP Enhanced Map Showing REMP Sampling Sites Closest to PBNP ISFSI Area TLD Results (1995 - 2023)

Comparison of ISFSI Fence TLDs to Selected REMP TLDs Sr-90 Concentration in Milk (1997 - 2023)

Annual Average Air Gross j3 (1993 - 2023) 2023 Airborne Gross Beta 2015 Airborne Gross Beta E-01 Results 1971 - 2023 Comparison of E-03 and E-20 Results 1971 - 2023 Comparison of E-01, E-02, E-03, and E-04 Results 1992 - 2023 E-03, E-31, and E-44 Background Site E-20 Results 1992 - 2023 Groundwater Monitoring Locations iv 27 28 29 42 43 45 45 46 46 52 52 53 54 58

I

SUMMARY

The Annual Monitoring Report for the period from January 1, 2023, through December 31, 2023, 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 2023, the following Curies (Ci) of radioactive material were released via the liquid and atmospheric pathways:

Liquid Atmospheric Tritium (Ci) 890 90.9 1 Particulate (Ci) 0.0822 0.000056 Noble Gas (Ci) 0.165 14.600 C-142 0.0135 11.08 1Atmospheric particulate includes radioiodine (1-131 133).

2Liquid is measured, atmospheric is calculated.

For the purpose of compliance with the effluent design objectives of Appendix I to 10 CFR 50, doses from effluents are calculated for the hypothetical maximally exposed individual (MEI) for each age group and compared to the Appendix I objectives. Doses less than or equal to the Appendix I values are considered to be evidence that PBNP releases are as low as reasonably achievable (ALARA) 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 Whole body dose Organ dose ATMOSPHERIC RELEASES Dose Category Particulate organ dose Noble gas gamma ray air dose Noble gas beta air dose Noble gas dose to the whole body Noble gas dose to the skin Calculated Dose 0.00652 mrem 0.00764 mrem Calculated Dose 0.0195 mrem 0.000383 mrad 0.000582 mrad 0.000344 mrem 0.000631 mrem Appendix I Dose 3 mrem 10 mrem Appendix I Dose 30 mrem 20 mrad 40 mrad 10 mrem 30 mrem

% Appendix I 0.22 0.0764

% Appendix I 0.065 0.00192 0.00146 0.00344 0.00210 The results show that during 2023, the doses from PBNP effluents were :50.22% of the Appendix I design objectives. This is greater than the 2022 result of 0.17%. The increase is expected due to Point Beach having a two-outage year in 2023 and producing 1.41 E5 more gallons of batch releases compared to 2022. However, operation of the PBNP radwaste treatment system continues to be ALARA.

1 I

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 2023 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 2023 Radiological Environmental Monitoring Program (REMP) collected 721 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 757 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, 5 surrounding the plant and a control location, 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 2023, there were no new storage casks added to the ISFSI. The total number of existing dry storage casks is 56: 16 ventilated, vertical storage casks (VSC-24) and 34 NUHOMS, horizontally stacked storage modules, and 6 HOL TEC 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 2023 confirmed that the effluent control program at PBNP ensured a minimal impact on the environment.

One-hundred-eighty-six (186) 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.

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

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I

1.0 INTRODUCTION

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

10 CFR 20.1302 directs PBNP to make the appropriate surveys of radioactive materials in effluents released to unrestricted and controlled areas. Liquid wastes are monitored by inline radiation monitors as well as by isotopic analyses of samples of the waste stream prior to discharge from PBNP. Airborne releases of radioactive wastes are monitored in a similar manner. 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 50616). 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 is 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 2023 Liquid Effluent Calculated Doses to 10 CFR 50 A d" ID Ob" f

ppen 1x es1gn Jee 1ves Annual Limit [mrem]

Highest Total Calculated Dose

% of Design

[mrem]

Objective 3 (whole body) 0.00652 0.22 10 (any organ) 0.00764 0.0764 2.2 2.3 2023 Circulating Water Radionuclide Release Summary Radioactive liquid releases via the circulating water discharge are summarized by individual source and total curies released on a quarterly and annual basis (Table 2-2). These releases are composed of batch releases (processed waste and steam generators) and continuous releases (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.

2023 Isotopic Composition of Circulating Water Discharges The isotopic composition of circulating water discharges during the current reporting period is presented in Table 2-3. The 2023 liquid batch release of 6.69E+05 gallons (Table 2-2) was an increase from 2022 processed waste released (5.28E+05 gallons), which is consistent with water processing 4

2.4 requirements during a two-outage year. The total isotopic curie distribution of fission and activation products released in 2023 was 9.57E-2 Ci which was higher than the 2022 value of gamma emitters and hard-to-detects 7.69E-02 Ci.

The total antimony (Sb) in 2023 increased to 4.60e-2 Ci in comparison to the 2022 value of 1.40E-03 Ci, while subsequently the Zr-Nb decreased slightly to 1.32E-03 Ci released when compared to the 2022 total of 1.92E-03 curies. Tin isotope (Sn-113/Sn-11 ?m/Sn-125) totals decreased from the 3.35E-04 Ci identified in 2022 to 2.04E-04 Ci in 2023, though Sn-125 was only present in 2022 releases. Te-123m was documented at 9.10E-03 Ci in 2023, which is an increase from the 2.59E-03 Ci observed in 2022. The 2023 C-14 decreased to 1.35E-02 Ci in 2023 from the 2.46E-02 Ci observed in 2022. Sr-92, which was not detected in 2022, but was present in the 2023 effluent at 1. 78E-6 Ci. Tritium increased to 890 Ci in 2023 in comparison to the 644 Ci documented in 2022 which can again be attributed to having a two-outage year in 2023.

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 2023, 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 principal 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 principal 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, 2023 through December 31, 2023 1st QTR 2nd QTR 3rd QTR Total Activity Released (Ci)

Fission & Activation Products 1 1.70E-02 2.12E-02 9.75E-03 Gross Alpha ND ND ND Tritium 2.92E+02 1.83E+02 2.62E+02 Noble Gases 7.58E-03 6.36E-03 1.39E-02 Total Vol Released (gal)

Liquid Batch Releases 2 1.78E+05 1.59E+05 1.01E+05 Continuous Releases 3 3.24E+07 2.71E+07 2.49E+07 Total Gallons 3.26E+07 2.73E+07 2.50E+07 Total cc 1.23E+11 1.03E+11 9.46E+10 Unit 1 Circ Water Dilution Volume (gal) 2.37E+10 4.42E+10 4.97E+10 Unit 2 Circ Water Dilution Volume (gal) 2.36E+10 4.43E+10 4.98E+10 Total of Both Units Circ Water Dilution Volume (gal) 4.72E+10 8.85E+10 9.95E+10 Dilution volume used (cc)4 8.93E+13 1.67E+14 1.88E+14 Avg diluted discharge cone (µCi/cc)

Gamma Scan (+HTDs)1 1.90E-10 1.27E-10 5.19E-11 Gross Alpha ND ND ND Tritium 3.27E-06 1.09E-06 1.39E-06 Noble Gases 8.49E-11 3.80E-11 7.39E-11 1 HTDs include Fe-55, C-14, Ni-63, Sr-90, and Tc-99.

2 Liquid Batch Releases are the processed waste tanks and steam generator releases 3 Continuous Batch Releases include Steam Generator Slowdown Filter Outlet, Wastewater Effluent, and Subsurface Drainage Annual 4th QTR Totals 4.77E-02 9.57E-02 ND ND 1.53E+02 8.90E+02 1.37E-01 1.65E-01 2.31E+05 6.69E+05 2.58E+07 1.10E+08 2.60E+07 1.11 E+08 9.85E+10 4.20E+11 4.05E+10 1.58E+11 4.82E+10 1.66E+11 8.87E+10 3.24E+11 1.53E+14 5.98E+14 3.11E-10 6.80E-10 ND ND 9.99E-07 6.76E-06 8.94E-10 1.09E-09 4 Circulating water discharge from the Unit that was overboard for the month or with the lowest dilution flow used for average estimated diluted discharge concentration.

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

January 1, 2023 through December 31, 2023 Nuclide 1st QTR 2nd QTR 3rd QTR 4th QTR Annual (Ci)

(Ci)

Total (Ci)

H-3 2.92E+02 1.83E+02 2.62E+02 1.53E+02 8.90E+02 C-14 5.63E-03 2.59E-03 2.21E-03 3.08E-03 1.35E-02 Ag-110m 7.17E-05 5.61 E-05 4.15E-05 2.68E-04 4.37E-04 As-76 1.36E-05 1.36E-05 Co-58 1.44E-04 7.63E-04 3.08E-05 2.69E-03 3.63E-03 Co-60 4.30E-04 9.99E-04 2.44E-04 1.78E-03 3.45E-03 Cr-51 1.06E-04 1.47E-03 1.07E-03 2.65E-03 Cs-137 3.04E-05 1.52E-05 4.56E-05 Cs-138 1.33E-05 1.33E-05 F-18 2.59E-03 2.39E-03 2.83E-03 2.61E-03 1.04E-02 Fe-55 1.73E-04 5.02E-04 6.27E-04 1.30E-03 Fe-59 1.67E-04 2.31E-03 2.48E-03 1-132 9.01E-06 4.15E-05 5.0SE-05 La-140 1.41 E-05 1.41 E-05 Mn-54 1.04E-06 3.56E-05 7.54E-06 4.42E-05 Na-24 2.92E-06 2.92E-06 Nb-95 2.46E-05 4.92E-04 3.17E-04 8.34E-04 Nb-97 9.0SE-06 2.17E-05 2.55E-06 3.33E-05 Ni-63 1.40E-04 7.02E-05 4.12E-04 6.22E-04 Sb-124 9.84E-05 1.29E-04 8.51 E-04 6.15E-03 7.23E-03 Sb-125 6.12E-03 5.58E-03 3.28E-03 2.38E-02 3.88E-02 Sn-113 8.09E-05 1.23E-04 2.04E-04 Sn-125 ND Sr-92 1.78E-06 1.78E-06 Tc-99 1.59E-04 6.08E-05 4.55E-05 7.42E-05 3.40E-04 Te-123m 1.27E-03 5.55E-03 1.48E-04 2.13E-03 9.10E-03 Zn-65 1.13E-05 1.13E-05 Zr-95 2.87E-04 1.71 E-04 4.58E-04 Kr-85 1.45E-03 1.45E-03 Xe-131 m 2.40E-04 4.78E-03 5.02E-03 Xe-133 7.47E-03 6.32E-03 1.37E-02 1.30E-01 1.57E-01 Xe-133m 2.84E-05 1.71 E-05 3.65E-04 4.11E-04 Xe-135 7.82E-05 3.79E-05 4.00E-04 5.16E-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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1st Qtr H-3 (Ci)

Flow (gal) 2nd Qtr H-3 (Ci)

Flow (gal) 3rd Qtr H-3 (Ci)

Flow (gal) 4th Qtr H-3 (Ci)

Flow (gal) 2.6 S-1 O.OOE+OO 2.62E+06 O.OOE+OO 1.49E+06 O.OOE+OO 1.02E+06 O.OOE+OO 8.17E+05 Table 2-4 Beach and Subsoil System Drains - Tritium Summary January 1, 2023 through December 31, 2023 S-3 S-7 S-8 S-9 S-10 S-12 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.10E+06 1.74E+05 O.OOE+OO 4.46E+04 1.79E+05 8.00E+03 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 3.75E+05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.42E+05 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 1.77E+06 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 4.13E+04 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 6.74E+05 O.OOE+OO O.OOE+OO O.OOE+OO 4.32E+04 1.31 E+05 Land Application of Sewage Sludge and Wastewater S-13 O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 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 2023.

All disposals from the PBNP sewage treatment plant (STP) were done at the Manitowoc Sewage Treatment Plant. A total of 99,000 gallons in 19 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 2023 the total Ra-226 and K-40 were 51.7 µCi and 79.6 µCi, respectively. Small concentrations of H-3 (64 - 660 pCi/L) were found in all of the shipments for a total of 107.2 µCi. Based on the daily flow at the Manitowoc plant, the H-3 discharge concentration would be on the order of 0.221 pCi/L or 90,500 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 2023, the annual total of C-14 (1.35E-02 Ci) in liquid discharges is documented in Table 2-3. The 2023 amount of C-14 released makes up about 14% of the non-tritium radionuclides released in liquids (1.35E-02/9.57E-02).

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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 3.2 3.3 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 3-2.

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 3-5. The highest Appendix I dose is 1.95e-02 mrem for the child age group thyroid. Had C-14 been included, the child-bone dose would have been the highest at 1.56E-01 mrem. Even with the inclusion of C-14 the doses demonstrate that releases from PBNP to the atmosphere continue to be ALARA at 0.52% of the dose objective. This percentage is exactly the same as the 2022 result.

Radioactive Airborne Release Summary Radioactivity released in airborne effluents for 2023 is summarized in Table 3-3.

The particulate total decreased to 3.33E-05 Ci in 2023 from 1. 7 4E-04 Ci in 2022.

This decrease is attributed to a decrease in F-18 (3.06E-06 2023 compared to 1.62E-04 in 2022). Tritium increased in 2023 to 90.9 Ci from 79.7 in 2022. Noble gases increased to 14.6 Ci in 2023 from 1.30 Ci in 2022. This increase is directly due to the identification of failed fuel in the Unit 2 reactor which started trending in June of 2023.

Isotopic Airborne Releases The monthly isotopic airborne releases for 2023, from which the airborne doses were calculated, are presented in Table 3-4. Carbon-14 is not included in Table 3-4 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 March-April, ten different particulates were identified in the airborne effluent. In October-November eleven different particulates were identified. Most were 10

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 fagade, there are two circumferential gaps around the fagade.

It is assumed that the release into fagade is transferred to the outside and therefore is treated as a release to the environment.

As was noted in Section 3.2, the total particulate curies observed decreased in 2023 when compared to 2022, the decline is attributed to the decrease in F-18 in 2023.

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 2023 was calculated using the EPRI guidance and the current core parameters resulting from the power uprate. The calculated amounts were 5.55 Ci for Unit 1 and 5.53 Ci for Unit 2 yielding a total of 11.08 Ci which is statistically the same as 2016 through 2022. The 2023 calculated total 11.08 Ci is roughly 820 times higher than the 1.35E-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 14C02 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, 14CH4, not as carbon dioxide, 14C02.

11

The amount of 14C02 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).

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 14C02. Therefore, 10% of the 11.08 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. 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 14C02 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 14C02 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.

In 2022 the C-14 dose calculation methodology was changed in the PBNP ODCM to reflect changes in a new software that was implemented. The new changes use the NUREG-0133 methodology for C-14 calculation of dose. The calculations used to determine the dose were updated for the annual C-14 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 3-5.

12

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).

3. 7 Abnormal Release An abnormal gaseous release occurred in July 2023. The abnormal release involved a gaseous leak on the Point Beach waste gas system, resulting in the loss of gaseous effluent from the C and D gas decay tanks. The release began on July 5 at 22:00 when the C-GDT was in service. On July 8 at 15:50, D-GDT was placed in service until July 10 at 18:46, when the leak

was discovered due to a loss of volume. A sample of the in service C-GDT was taken on July 11 at 04:05 and contained Xe-131 m, Xe-133, and Xe-133m. Permits were generated using the RADEAS software by inputting the isotopic results and the release durations which were calculated from the loss of gaseous effluent based on Operations logs. The total curie (Ci) of isotopes released and doses due to the abnormal release is presented in Table 3.1. Based on the sample results obtained, 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.

Table 3-1 Curies Released and Dose Calculations from Abnormal Gaseous Release C-GDT D-GDT 23-00081GB 23-00082GB SamQle Results {lJCi/cc}

Ci Released Ci Released Total Ci Released Xe-131 m 1.53E-05 7.89E-04 1.11 E-03 1.90E-03 Xe-133 7.27E-04 3.75E-02 5.26E-02 9.01 E-02 Xe-133m 2.42E-06 1.25E-04 1.75E-04 3.00E-04 Annual Limit C-GDT D-GDT Total Dose 23-00081GB 23-00082GB Gamma Air Dose (mrad) 10 4.63E-07 6.49E-07 1.11 E-06 Beta Air Dose (mrad) 20 1.40E-06 1.96E-06 3.36E-06 Total Body Dose (mrem) 5 3.84E-07 5.39E-07 9.23E-07 Skin Dose (mrem) 15 9.23E-07 1.29E-06 2.21 E-06 13

Table 3-2 Comparison of 2023 Airborne Effluent Calculated Doses to 10 CFR 50 Appendix I Design Objectives Category Particulate Noble gas Noble gas Noble gas Noble gas Annual Appendix I Design January-December Percent of Appendix I Objective Calculated Dose Design Objective 30 mrem/organ 0.0195 mrem 0.065 20 mrad (gamma air) 0.000383 mrad 0.00192 40 mrad (beta air) 0.000582 mrad 0.00146 1 O mrem (whole body) 0.000344 mrem 0.00344 30 mrem (skin) 0.000631 mrem 0.00210 Table 3-3 Radioactive Airborne Effluent Release Summary Januarv 1. 2023 throuqh December 31. 2023 Annual 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Total Total Noble Gas (Ci)1 2.46E-01 1.73E-01 6.26E+OO 7.97E+OO 1.46E+01 Total Radioiodines (Ci)2 4.29E-08 O.OOE+OO 4.27E-06 1.83E-05 2.26E-05 Total Particulate (Ci)3 5.67E-06 7.52E-07 3.0?E-06 2.38E-05 3.33E-05 Alpha (Ci)

ND ND ND ND ND All other beta+ gamma (Ci) 5.67E-06 7.52E-07 3.0?E-06 2.38E-05 3.33E-05 Total Tritium (Ci) 2.34E+01 1.78E+01 1.83E+01 3.14E+01 9.09E+01 Avg. Rel. Rate (µCi/sec)4 5.86E-01 5.24E-01 6.34E-01 9.51 E-01 1 Total noble gas (airborne releases) and activation gas Ar-41.

2 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 is calculated for the year and no monthly values are available.

4 Average release rate is based off the average tritium release rates.

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.

14

TABLE 3-4 Isotopic Composition of Airborne Releases January 1, 2023 through December 31, 2023 1st QTR 2nd QTR 3rd QTR 4th QTR Annual Nuclide (Ci)

(Ci)

Total H-3 2.34E+01 1.78E+01 1.83E+01 3.14E+01 9.09E+01 Ar-41 1.64E-01 1.67E-01 1.71E-01 1.61 E-01 6.63E-01 Kr-85m ND ND ND 1.SOE-04 1.SOE-04 Xe-131m 1.54E-04 ND 1.90E-03 6.44E-03 8.49E-03 Xe-133 8.23E-02 6.14E-03 6.08E+OO 7.80E+OO 1.40E+01 Xe-133m 1.53E-04 ND 3.00E-04 5.53E-04 1.01 E-03 Xe-135 ND ND 4.34E-04 1.71 E-03 2.14E-03 1-131 4.29E-08 ND 4.65E-07 5.33E-06 5.84E-06 1-133 ND ND 3.80E-06 1.29E-05 1.67E-05 Br-82 9.35E-09 ND ND ND 9.35E-09 Co-57 ND ND ND 1.48E-08 1.48E-08 Co-58 8.13E-07 ND ND 6.76E-06 7.57E-06 Co-60 1.25E-06 ND ND 4.34E-06 5.59E-06 Cr-51 1.22E-06 ND ND 7.83E-07 2.00E-06 Cs-137 ND ND ND 1.36E-10 1.36E-10 F-18 1.10E-06 7.52E-07 1.21 E-06 ND 3.06E-06 Fe-55 ND ND ND ND ND Mn-54 1.22E-07 ND ND 1.83E-07 3.0SE-07 Nb-95 7.51 E-07 ND ND 2.06E-06 2.81 E-06 Ni-63 ND ND 1.86E-06 8.33E-06 1.02E-05 Sr-89 ND ND ND ND ND Sr-90 ND ND ND ND ND Tc-99 ND ND ND ND ND Sb-125 6.0SE-09 ND ND ND 6.0SE-09 Zr-95 4.04E-07 ND ND 1.37E-06 1.77E-06 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.

15

Table 3-5 Comparison of Airborne Effluent Doses (Appendix I and C-14) 2023 Appendix I (Airborne Particulate + Tritium) Dose (mrem)

Bone Adult 5.45E-05 Teen 7.16E-05 Child 1.40E-04 Infant 7.08E-05 Ann.Limit 3.00E+01

% Ann Lim 6.SOE-02 Bone Adult 4.25E-02 Teen 6.88E-02 Child 1.56E-01 Infant 1.30E-01 Liver 1.21 E-02 1.36E-02 1.93E-02 8.SOE-03 Liver 8.41 E-03 1.36E-02 3.10E-02 2.77E-02 T-WB Thyroid Kidney Lung GI-LLI 1.21 E-02 1.22E-02 1.21 E-02 1.21 E-02 1.21 E-02 1.36E-02 1.37E-02 1.36E-02 1.36E-02 1.36E-02 1.93E-02 1.95E-02 1.93E-02 1.93E-02 1.93E-02 8.SOE-03 8.79E-03 8.49E-03 8.49E-03 8.49E-03 2023 Carbon-14 Dose (mrem)

T.Body Thyroid Kidney Lungs GI-LLI 8.41E-03 8.41 E-03 8.41 E-03 8.41 E-03 8.41E-03 1.36E-02 1.36E-02 1.36E-02 1.36E-02 1.36E-02 3.1 OE-02 3.10E-02 3.10E-02 3.10E-02 3.1 OE-02 2.77E-02 2.77E-02 2.77E-02 2.77E-02 2.77E-02 2023 Total Airborne Non-Noble Gas Dose [Particulate+ H-3 + C-14 (mrem)]

Bone Liver T-WB Thyroid Kidney Lung GI-LLI Adult 4.26E-02 2.05E-02 2.05E-02 2.06E-02 2.0SE-02 2.05E-02 2.0SE-02 Teen 6.89E-02 2.72E-02 2.72E-02 2.73E-02 2.72E-02 2.72E-02 2.72E-02 Child 1.56E-01 5.03E-02 5.03E-02 5.05E-02 5.03E-02 5.03E-02 5.03E-02 Infant 1.30E-01 3.62E-02 3.62E-02 3.65E-02 3.62E-02 3.62E-02 3.62E-02 Ann.Limit 3.00E+01

% Limit 5.21 E-01 The percent of limit is calculated using the highest total dose, the Child Age Group.

16 Skin 2.94E-05 2.94E-05 2.94E-05 2.94E-05 Skin O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Skin 2.94E-05 2.94E-05 2.94E-05 2.94E-05

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 2023. 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 2023 Type of Waste Quantity Activity A Spent resins, filter sludge, evaporator bottoms, etc.

7.93 m 3

122.5 Ci 280.0 ft3 B. Dry compressible waste, contaminated equipment, etc 234.0 m3 0.402 Ci 8260.0 ft3 C. Irradiated components, control rods, etc.

0.00 m3 N/A Ci D. Other 4.2 4.3 ft 3

0.0 m3 N/A Ci Solid Waste Disposition There were six solid waste shipments from PBNP during 2023. The dates and destinations are shown in Table 4-2.

Table 4-2 2023 PBNP Radioactive Waste Shipments 3/10/2023 Oak Ridge, TN 3/30/2023 Oak Ridge, TN 6/6/2023 Clive, UT 7/26/2023 Erwin, TN 9/25/2023 Oak Ridge, TN 11/17/2023 Oak Ridge, TN Major Nuclide Composition (by Type of Waste)

The major radionuclide content of the 2023 solid waste was determined by gamma isotopic analysis and the application of scaling factors for certain indicator radionuclides based on the measured isotopic content of representative waste stream samples. The estimated isotopic content is presented in Table 4-3. Only those radionuclides with detectable activity are listed.

17

Table 4-3 2023 Estimated Solid Waste Major Radionuclide Composition T~~e A T~~e B Activi!Y Percent Activi!Y Percent Nuclide (mCi)

Abundance Nuclide (mCi)

Abundance Total Activity 4.91E+OO 1.00E+OO Total Activity 1.18E+02 99.99%

H-3 4.08E-03 0.08%

H-3 1.34E-03 0.00%

C-14 2.26E-02 0.46%

C-14 3.52E-03 0.00%

Cr-51

1. 78E-02 0.36%

Mn-54 2.19E+OO 1.85%

Mn-54 1.53E-02 0.31%

Fe-55 4.14E+OO 3.50%

Fe-55 9.50E-02 1.93%

Co-57 3.21 E-01 0.27%

Fe-59 4.52E-03 0.09%

Co-58 1.47E+OO 1.24%

Co-57 3.32E-03 0.07%

Co-60 5.61E+01 47.36%

Co-58 5.74E-02 1.17%

Ni-59 2.69E-01 0.23%

Co-60 2.07E+OO 42.10%

Ni-63 5.11 E+01 43.15%

Ni-59 3.01 E-02 0.61%

Sr-89 2.21 E-03 0.00%

Ni-63 2.36E+OO 48.13%

Sr-90 1.61 E-02 0.01%

Zn-65 8.40E-04 0.02%

Tc-99 2.48E-03 0.00%

Sr-90 5.32E-04 0.01%

Sb-125 1.78E+OO 1.51%

Zr-95 3.25E-02 0.66%

Cs-137 8.38E-01 0.71%

Nb-95 6.23E-02 1.27%

Ce-144 9.46E-04 0.00%

Tc-99 1.23E-04 0.00%

Pu-238 2.33E-04 0.00%

Ag-110m

1. 77E-02 0.36%

Pu-239 1.06E-04 0.00%

Sn-113 1.98E-03 0.04%

Pu-241 1.94E-01 0.16%

Sb-124 1.59E-03 0.03%

Am-241 2.21E-04 0.00%

Sb-125 7.32E-02 1.49%

Cm-242 1.18E-05 0.00%

1-129 2.51 E-05 0.00%

Cm-243 1.00E-04 0.00%

Cs-137 3.44E-02 0.70%

Ce-144 6.20E-04 0.01%

Pu-238 4.90E-05 0.00%

Pu-239 2.45E-05 0%

Pu-241 3.38E-03 0.07%

Am-241 1.54E-04 0%

Cm-242 4.23E-06 0%

Cm-243 5.38E-05 0%

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5.0 NONRADIOACTIVE CHEMICAL RELEASES 5.1 Scheduled Chemical Waste Releases There were no scheduled chemical waste releases of neutralized wastewater to the circulating water system from January 1, 2023 through December 31, 2023.

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, 2023, to June 30, 2023, included 2.38E+07 gallons of clarified effluent. The wastewater contained 3.57E+03 lbs. of suspended solids.

Miscellaneous chemical waste releases from the wastewater effluent (based on effluent analyses) to the circulating water for July 1, 2023, to December 31, 2023, included 1.94E+07 gallons of clarified effluent. The wastewater contained 1.62E+03 lbs. of suspended solids.

Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from January 1, 2023, to June 30, 2023, included 4.23+05 lbs. of sodium bisulfite solution (1.61 E+05 lbs. sodium bisulfite),

3.11 E+05 lbs. of Sodium Hypochlorite Solution (3.89E+04 lbs. sodium hypochlorite), 1.54E+04 lbs. Acti-Brom 1338 (6. 75E+03 lbs. sodium bromide).

3.01 E+03 lbs. of biodetergent, and 3.91 E+04 lbs. of silt dispersant.

Miscellaneous chemical waste released directly to the circulating water, based on amount of chemicals used from July 1, 2023, to December 31, 2023, included 6.58E+05 lbs. of sodium bisulfite solution (2.50E+05 lbs. sodium bisulfite),

4.57E+05 lbs. Sodium Hypochlorite Solution (5. 71 E+04 lbs. sodium hypochlorite), 1.83E+04 lbs. Acti-Brom 1338 (8.24E+03 lbs. sodium bromide),

4.32E+03 lbs. of biodetergent, and 2.03E+04 lbs. of silt dispersant.

19

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 2023 Average Volume Cooling Water Discharge [million gal/day]*

Average Cooling Water Intake Temperature [°F]

Average Cooling Water Discharge Temperature [°F]

Average Ambient Lake Temperature [°F]

For days with cooling water discharge flow.

- - U2 outage 3/12/23-3/31 /23 UNIT JAN FEB 1

348.5 348.5 2

348.5 348.5 1

37 36 2

37 36 1

69 69 2

68 68 35 34 Table 6-1(continued)

MAR***

APR 363.3 389.0 123.7 387.3 36 44 37 44 65 55 68 65 38 41 Circulating Water System Operation for 2023 Average Volume Cooling*

Water Discharge [million gal/day]

Average Cooling Water Intake Temperature [°F]

Average Cooling Water Discharge Temperature [°F]

Average Ambient Lake Temperature [°F]

For days with cooling water discharge flow.

- - U1 outage 10/8/23-10/28/23 UNIT JUL 1

551.5 2

552.9 1

61 2

62 1

74 2

73 52 20 AUG SEP OCT***

551.5 551.5 155.4 552.9 552.9 574.2 64 62 55 64 63 55 84 83 72 82 81 70 62 62 51 MAY JUN 551.5 551.5 552.9 552.9 48 60 49 60 67 67 65 66 46 46 NOV DEC 539.9 476.2 552.0 476.8 46 40 46 40 64 65 62 64 44 37

Part B Miscellaneous Reporting Requirements 7.0 ADDITIONAL REPORTING REQUIREMENTS 7.1 Revisions to the PBNP Effluent and Environmental Programs Revision 24 of the Offsite Dose Calculation Manual (ODCM) was issued in February 2022. The site operated under the guidance of this revision for the entirety of 2023.

The ODCM was revised to align with the standard methodologies in NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, as are implemented in the Radiological Effluent Administrative System (RADEAS) software design. Point Beach transitioned to RADEAS for generating all liquid and gaseous effluent releases in 2022.

Equations in the ODCM reflect some of the nomenclature from the RADEAS software design description and utilize NUREG-0133 methodology. Pre-calculated dose parameters (Aio and Rio) and pre-calculated dose conversion factors were replaced with the basis document dose factors for each applicable organ/age as can be found in NUREG-0172 (Age-Specific Radiation Dose Commitment Factors For A One-Year Chronic Intake), Reg. Guide 1.109 (Calculation of Annual Doses To Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I), and other regulatory guides as applicable.

Additional changes include updating the tritium (H-3) and strontium-90 (Sr-90) dose factors from the NRC LADTAP values to the NUREG-0172 values which are more conservative. As well, to align with effluent reporting performed by the RADEAS software changes to the Annual Monitoring Report section of the ODCM were updated.

7.2 lnterlaboratory Comparison Program ATI Environmental transitioned to Microbac Laboratories Inc. on June 1, 2023.

Microbac Labs Inc., 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 2023. The results of these comparisons can be found in Appendix A of the attached final report for 2023, January - December 2022 from Microbac Labs, which is located in Appendix 1 of this report.

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 2023.

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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, as well as TLDs, provide the means to measure changes in the ambient environmental radiation levels at sites near the ISFSI and at the PBNP site boundary. This is 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.

22

9.0 PROGRAM DESCRIPTION 9.1 Results Reporting Convention The vendor used by PBNP to analyze the environmental samples is directed to report analysis results as measured by a detector, which can meet the required lower limit of detection (LLD) as specified in Table 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 is 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 the exact 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 23

9.2 9.3 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.

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.

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 REMP in 2023.

24

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

-06, -07, -08, -09, -12

-14, -15, -168, -17, -18, 20, -22, -23, -24,

-25, -268, -27, -28

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

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

-TC Vegetation E-01, -02, -03, -04, -06, Gamma Isotopic Analysis 2x/yr as available

-20, Fish E-13 Gamma Isotopic Analysis 4x/yr as available (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/ 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, Gamma Isotopic Analysis 1x/yr

-06, -20 Shoreline Sediment E-01, -05, -06 Gamma Isotopic Analysis 1x/yr ISFSI Ambient North, East, South, Radiation Exposure West Fence Sections TLD Quarterly 25

Table 9-2 PBNP REMP S r

L amp mg ocat1ons 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 Tapawingo Road, about 0.4 Miles West of Lakeshore Road E-04 North Boundary E-05 Two Creeks Park Point Beach State Park - Coast Guard Station; TLD located South of the Lighthouse on 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. Band 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 Meteorological Tower.

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

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

E-32 On a 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 high).

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

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

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

E-42 NW corner of Church and Division, East of Mishicot E-43 West side of Tannery Rd south of Elmwood (7th 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 26

J KEY TLD

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~ KILOMETER CGS FILE 10749 MAY 2005 Figure 9-1 PBNP REMP Sampling Sites 27

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

Table 9-3 ISFSI Sampling Sites Ambient Radiation Monitoring (TLD)

Soil, Vegetation and Airborne Monitoring E-03 E-02 E-28 E-03 E-29 E-04 E-30 E-31 E-32 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 30

Table 9-5 Deviations from Scheduled Sampling and Frequency During 2023 Scheduled Reason for not conducting REMP as Sample Type Location Collection Plans for Preventing Recurrence Date required 6-01 E-02 Samples were misplaced by the Communicate with lab vendor to Al E-03 6-04 05-24-23 shipping company, arrived on 7/7/23.

ensure samples arrive and are analyzed E-08 E-20 Unable to reach M DA.

in timely manner AP/Al E-08 06-07-23 Sampler found not running due to a Monitor equipment and work through tripped fuse. Very low sample volume Sampler found not running due to a maintenance work process to correct AP/Al E-08 06-28-23 tripped fuse. Very low sample volume issue.

AP/Al E-01 07-05-23 Sampler found not running due to a Monitor equipment and work through tripped fuse. Very low sample volume Sampler found not running due to a maintenance work process to correct AP/Al E-01 07-12-23 tripped fuse. Very low sample volume issue.

AP/Al E-01 08-30-23 Sampler found not running due to a Monitor equipment and work through power outage.

maintenance work process to correct Sampler found not running due to a AP/Al E-01 09-07-23 power outage.

issue.

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 31

9.6 Analytical Parameters 9.7 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 2023.

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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> before gross beta measurements are made in order for naturally occurring radionuclides to become a negligible part of the total activity. Gross beta measurements serve as a quick check for any unexpected activity that may require immediate investigation. Quarterly composites of the particulate air filters are analyzed for long-lived radionuclides such as Cs-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 32

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

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

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

No special vegetation samples were obtained for C-14 analyses in 2023.

9.7.6 Environmental Radiation Exposure The 2023 environmental radiation exposure measurements were made using TLD cards. The TLD card is a small passive detector, which integrates radiation exposure. Each TLD consists of a Teflon sheet coated with a crystalline, phosphorus material ( calcium sulfate containing dysprosium) which absorbs the gamma ray energy deposited in them.

Each TLD is read in four distinct areas to yield four exposure values which are averaged. Prior to the third quarter of 2001, exposure data was obtained using three lithium fluoride (LiF) TLD chips sealed in black plastic. The difference in material types can impact the amount of exposure measured. An evaluation of the response difference between the two types of TLD in 2001 demonstrated that the TLD cards produced a 14% higher response than the LiF chips (2011 AMR, Table 9-7, p. 36).

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

33

9.7.7 ISFSI Ambient Radiation Exposure The ISFSI fence TLDs are part of the 1 OCFR72.44 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.

34

10.0 RES UL TS 10.1 Summary of 2023 REMP Results Radiological environmental monitoring conducted at PBNP from January 1, 2023, through December 31, 2023, 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:

==

Description:==

N:

LLD:

Average:

High:

Units:

Type of the sample medium Type of measurement Number of samples analyzed a priori lower limit of detection Average value +/- the standard deviation of N samples Highest measured value +/- it's associated 2 sigma counting error 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 2cr counting error is greater than zero (x-2cr >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 N13.30-1996, "Performance Criteria for Radiobioassay;" DE91-013607, "Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance" and NUREG-1576, "Multi-Agency Radiological Laboratory Analytical Protocols Manual."

35

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 10-2 contains the ISFSI fence TLD results.

36

Table 10-1 S

f R d" I I E t I M

t.

R It f 2023 ummary o a 10 og1ca nv1ronmen a om ormg esu s or Average :t 1 ~ta.

Sample Description N

LLD (a)

Deviation (b)

High+/- 2 sigma TLD Environmental Radiation 128 1 mrem 1.14 +/- 0.21 1.64 +/- 0.04 Control (E-20) 4 1 mrem 1.11 +/- 0.07 1.16 +/- 0.09 Air Gross Beta 254 0.01 0.026 +/- 0.010 0.054 +/- 0.005 Control (E-20) Gross beta 52 0.01 0.027 +/- 0.010 0.053 +/- 0.005 1-131 254 0.030 (0.07)

ND Control (E-20) 1-131 52 0.030 (0.07)

ND Cs-134 20 0.01 (0.05)

ND Control (E-20) Cs-134 4

0.01 (0.05)

ND Cs-137 20 0.01(0.06)

ND Control (E-20) Cs-137 4

0.01(0.06)

ND Other v emitters (Co-60) 20 0.1 ND Control (E-20) Other (Co-60) 4 0.1 ND Natural Be-7 20 0.065 +/- 0.014 0.086 +/- 0.017 Control (E-20) Natural Be-7 4

0.061 +/- 0.016 0.072 +/- 0.015 Milk Sr-89 36 5

ND Sr-90 36 1

0.4 +/- 0.2 0.7 +/- 0.3 1-131 36 0.5 ND Cs-134 36 5 (15)

ND Cs-137 36 5 (18) 0.4 +/- 1.3 2.6 +/- 0.9 Ba-La-140 36 5 (15)

ND Other Qamma emitters(Co-60) 36 15 ND Natural K-40 36 1334 +/- 67 1481 +/- 73 Well Gross beta 4

4

+/-

Water H-3 4

500 (3000) 80 +/- 99 137 +/- 83 Sr-89 4

5(10)

ND Sr-90 4

1 (2)

ND 1-131 4

0.5 (2)

ND Mn-54 4

10 (15)

ND Fe-59 4

30 ND Co-58 4

10(15)

ND Co-60 4

10(15)

ND Zn-65 4

30 ND Zr-Nb-95 4

15 ND Cs-134 4

10(15)

ND Cs-137 4

10(18) 0.2 +/- 2.2 3.1 +/-2.6 Ba-La-140 4

15 ND Other gamma emitters(Ru-103) 4 30 ND NS = No Sample obtained during the year (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 Units mR/7days mR/7days pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/m3 pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L

Table 10-1 (continued) s ummary o f R d" I I E I M a 10 og1ca nv1ronmenta omtormg R It f 2023 esu s or Average +/- 1 Std.

Sample Description N

LLD (a)

Deviation (b)

High +/- 2 sigma Lake Water Gross beta 36 4

1.2 +/- 0.5 2.7 +/- 0.7 1-131 36 0.5 (2) 0.02 +/- 0.22 1.21 +/- 0.11 Mn-54 36 10 (15) 0.3 +/- 1.2 4.3 +/- 3.1 Fe-59 36 30

-0.8 +/- 2.4 2.0 +/- 1.3 Co-58 36 10(15) 0.0 +/- 1.3 2.7 +/- 2.7 Co-60 36 10(15) 0.3 +/- 1.2 2.9 +/- 2.8 Zn-65 36 30

-1.9 +/- 4.4 1.6 +/- 1.1 Zr-Nb-95 36 15 ND Cs-134 36 10 (15)

-0.3 +/- 1.7 1.5 +/- 1.3 Cs-137 36 10 (18) 0.2 +/- 1.0 2.5 +/- 1.9 Ba-La-140 36 15 ND Other gamma (Ru-103) 36 30 ND Sr-89 12 5(10) 0.05 +/- 0.28 0.39 +/- 0.38 Sr-90 12 1 (2) 0.15 +/- 0.17 0.38 +/- 0.37 H-3 12 200 (3000) 67 +/- 83 187 +/- 89 Fish Mn-54 12 0.13 ND Fe-59 12 0.26

-0.005 +/- 0.018 0.012 +/- 0.011 Co-58 12 0.13 ND Co-60 12 0.13 ND Zn-65 12 0.26 ND Cs-134 12 0.13 ND Cs-137 12 0.15 0.016 +/- 0.007 0.030 +/- 0.017 Other gamma (Ru-103) 12 0.5 0.001 +/- 0.023 0.058 +/- 0.012 Natural K-40 12 2.46 +/- 0.47 3.20 +/- 0.41 Shoreline Cs-134 3

0.18 ND Sediment Cs-137 3

0.15 0.016 +/- 0.007 0.020 +/- 0.009 Natural Be-7 3

0.052 +/- 0.042 0.101 +/- 0.038 Natural K-40 3

6.21 +/- 0.83 7.042 +/- 0.295 Natural Ra-226 3

0.36 +/- 0.03 0.394 +/- 0.15 Soil Cs-134 6

0.15 ND Cs-137 6

0.15 0.20 +/- 0.12 0.422 +/- 0.04 Natural Be-7 6

0.115 +/- 0.18 0.457 +/- 0.26 Natural K-40 6

16.57 +/- 2.93 20.60 +/- 0.84 Natural Ra-226 6

1.16 +/- 0.42 1.658 +/- 0.35 Vegetation 1-131 12 0.06

-0.002 +/- 0.009 0.018 +/- 0.011 Cs-134 12 0.06 ND Cs-137 12 0.08 0.011 +/- 0.018 0.063 +/- 0.007 Other gamma emitters (Co-60) 12 0.25 0.002 +/- 0.005 0.006 +/- 0.003 Natural Be-7 12 0.80 +/- 0.76 2.13 +/- 0.33 Natural K-40 12 5.26 +/- 1.29 6.65 +/- 0.42 (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.

38 Units pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/L pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g pCi/g

Table 10-2 Average ISFSI Fence TLD Results for 2023 Fence Location Average

+/-

Standard Deviation Units North 2.13

+/-

0.25 mR/7 days East 3.34

+/-

0.18 mR/7 days South 2.62

+/-

0,06 mR/7 days West 6.49

+/-

0.21 mR/7 days 39

11.0 DISCUSSION 11. 1 TLD Cards The ambient radiation was measured in the general area of the site boundary, at an outer ring 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 1.14

+/- 0.19 mR/7-days compared to 1.11 +/- 0.07 mR/7-days at the background location.

These two values are not significantly different from each other. Neither of the indicator TLD values are significantly different from those observed from 2001 through 2022 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 I d.

t TLD R It f rage n,ca or esu s rom 1993 2023 Year Average 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 2022 1.23

+/-

0.21 2023 1.14

+/-

0.21

St. Dev = Standard Deviation 40

Table 11-2 Av erage ISFSI F TLD R It ( R/7 d s) ence esu s m av 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 2022 2.33 3.95 3.07 7.43 2023 2.13 3.34 2.62 6.49 There is no significant change in the exposure in 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 (1.31, 1.27, and 1.40 respectively) and continue to be higher than E-30 (1.04) 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 41

(E-03 1.31 +/- 0.021; E-31, 1.27+/- 0.28; E-32, 1.40 +/- 0.32) are higher than at the background site E-20 (1.11 +/- 0.15), 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 (1.22 +/- 0.24) is similar to the observed readings at E-03, E-31, and background location E-20 (1.31, 1.27, and 1.11 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). All ISFSI TLD levels slightly decreased in 2023. As reported last year, an increase in the 2022 West ISFSI TLD was expected based on the placement of the new casks on the ISFSI pad in 2021. As previously discussed, the small increase in 2001 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.

1.80 1.60 1.40 1.20

(/)

~ 1.00

~ 0.80 E 0.60 0.40 0.20 0.00 1990 Figure 11-1 ISFSI AREA TLD RESULTS 1995 - 2023 ISFSI AREA TLD RESULTS w-- '"!_~'ff' '~

1995 2000 2005 2010 2015 2020 YEAR 42 2025

E-03

E-28 E-29 X E-30

a: E-31 e E-32

+ E-20

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****

Pre-Operation' 0.93 0.87 0.87 0.81 0.93 0.98 1996 0.87 0.78 0.81 0.79 0.93 1.00 1997 0.91 0.89 0.84 0.84 0.89 0.97 1998 0.82 0.68 0.80 0.82 0.91 0.85 1999 0.88 0.83 0.76 0.80 0.90 0.99 2000 0.98 0.88 0.92 0.99 0.98 1.06 2001 1.31 0.95 1.07 1.02 1.10 1.04 2002 1.45 0.91 1.22 1.10 1.26 1.25 2003 1.29 0.82 0.94 1.02 1.20 1.15 2004 1.35 0.80 0.96 1.05 1.23 1.18 2005 1.30 0.72 0.96 0.98 1.15 1.04 2006 1.44 0.80 1.19 1.07 1.21 1.07 2007 1.37 0.78 1.07 1.05 1.18 0.97 2008 1.33 0.75 0.81 1.00 1.12 1.03 2009 1.39 0.82 0.85 1.01 1.17 1.05 2010 1.41 0.84 0.89 1.07 1.21 1.24 2011 1.46 0.85 0.90 1.06 1.25 1.32 2012 1.54 0.87 0.91 1.10 1.21 1.39 2013 1.23 0.87 0.77 1.00 1.40 1.38 2014 1.23 0.77 0.79 0.97 1.25 1.25 2015 1.36 0.86 0.78 1.07 1.24 1.40 2016 1.36 0.85 0.81 1.06 1.28 1.50 2017 1.36 0.79 0.80 1.01

1.21 1.44 2018 1.34 0.77 0.80 1.02 1.16 1.46 1.04 2019 1.27 0.79 0.76 1.09 1.17 1.41 0.99 2020 1.40 0.84 0.83 1.06 1.18 1.45 1.07 2021 1.42 0.78 0.80 1.05 1.26 1.45 1.28 2022 1.41 0.74 0.88 1.11 1.35 1.47 1.33 2023 1.31 0.65 0.81 1.04 1.27 1.40 1.22

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 E-20***

0.88 0.78 0.79 0.77 0.78 0.90 1.03 1.14 0.99 1.06 1.00 1.11 1.05 1.00 1.09 1.10

1. 11 1.14 1.22 1.15 1.20 1.29 1.21 1.19 1.03 1.15 1.25 1.34 1.11 Figure 11-2 Comparison of ISFSI Fence TLDs to Selected REMP TLDs ISFSI FENCE TLDS "in' 7.00 -----------------------------

~ 6.00 -t----------,~ -

~=-=------------...P-------

r,..

~ 5.00 +--------1<:----_.:...:,~llioa:::;.i;~-----1-------

, 4.00 +------I------:_:__-~ ~~---.- -----

~ 3.00 ni g 2.00

~ 1.00 1990 1995 2000 2005 43 2010 VEAR 2015 2020 2025 2030 North East sout h w est

11.2 Milk Naturally occurring K-40 (1334 +/- 67 pCi/L) continues to be the most prevalent radionuclide measured in milk at concentrations roughly 3330 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. Co-60 revealed four low positive results with all being <MDA. No positive results for 1-131, Cs-134, Ba-La-140, or Sr-89 were obtained in 2023.

There was a total of six low positive Cs-137 results obtained in 2023. Five were below the MDC lim.it and therefore may be false positives. One sample showed slightly higher than the lab MDA (2.6 +/-__0.9, MDA 2.3). In the last five years, Cs-137 was discharged from PBNP airborne effluents only in March 2016 and October 2017. In 2023, one release contained Cs-137 and occurred in November. This was after the samples had been collected and would not have accounted for the results.

The 2023 average Sr-90 concentrations have not changed much over the last few years (Figure 11-3). Over the past twenty-one years, the average has decreased from 1.2 +/- 0.5 pCi/L in 1997 to 0.4 +/- 0.2 pCi/L in 2023. 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 - 2023 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 2023. 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 near 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 SO's, ?O'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 - 2023), 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 2023 show no radiological effects of the plant operation.

44

11.3 Air Figure 11-3 Sr-90 Concentration in Milk (1997 - 2023)

Sr-90 in MILK

......... u E; 1 +---.9t.-l!f4~~~~:-::--------

o en L v, 0.1 ------,.------------.--------,

1990 2000 2010 YEAR

+ Sr-90 2020 2030 The average annual gross beta concentrations (plus/minus the 2cr uncertainty) in weekly airborne particulates at the indicator and control locations were 0.026 +/- 0.021 pCi/m3 and 0.027 +/- 0.019 pCi/m3, respectively, and are similar to levels observed from 1993 through 2022 (Figure 11-4).

The 2023 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 - 2022.

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 occurring 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 - 2023 Gross f3 Concentration in Air 0.03....--------------------

f 0.025 1----~~:::.:::::::.:-11n~ta~n~Ara:~.. ~

E

~ 0.02 u

,E: 0.015 ------------------

co..

en 0.01 ------------------

(/)

~ 0.005 o --~-------~--~----------

1990 1995 2000 2005 2010 2015 2020 2025 YEAR 45

Figure 11-5 2023 Airborne Gross Beta 2023 Airborne Gross Beta (pCi/mAJ) vs. Time 0.060....------------------------,

M° o.o5o ------------------- -------

~ 0.040 -t-----:.,------- ------------ ---,......... --!

~ 0.030 -f-"'=.i~ ------~~----i6-

~ -

---ili-__.;;.;.;1=-"--i

~

e 0.020 +---- --c----- -------,-1__.t!f_~*:11!!-~ -__JL,.~- --l t.,

0.010 --------..r-- --'l--------, - ---------1 0.000...---....----...-----.-----.-----.----.-----.---

1/1/23 2120123 4/ 11/23 5/31/23 7120/23 9/8/23 10/28/23 12/17 /23 DATE Figure 11-6 2015 Airborne Gross Beta 2015 Airborne Gross Beta (pCi/m"3) vs. Time 0.070 0.060

(")

0.050

-E 0.040 0 a. 0.030 0.020 0.010 0.000 9/18/ 14 12/27/14 4 /6/ 15 7/ 15/ 15 10/23/15 1/31/ 16 DATE

+ E-01

E-02 E-03 x E-04 XE-08

E-20

E-02 E-03 x E-04

>t: E-08

E-20 No 1-131 was detected during 2023. 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 0.006 to 0.027 pCi/m3. 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 46

desired LLD for only one sample, the actual LLD is about six times lower than the programmatic value given in Table 10-1. Similarly, the actual MDA is about one-sixth of that reported, in the range of 0.001 to 0.004 pCi/m3.

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. There was one sample at E-03 in the 3rd quarter that had a positive result, 0.0005 + 0.0004 with an MDC of 0.0003 pCi/m3.

By contrast, naturally occurring Beryllium-7 was found in all of the quarterly composites at concentrations ranging from 0.038 to 0.086 pCi/m3. Be-7 (T112 = 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 2023 air gamma data from quarterly composites do not indicate a measurable environmental impact from the operation of PBNP.

11.4 Lake Water For the REMP-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 10 of the results were positive, of which, three are from north of the plant, at site E-05 (see Figure 9-1 ). May samples at E-05 and E-06 were unable to achieve the LLD (15 pCi/L) due to a vendor error. The laboratory inadvertently placed the samples into storage without ever counting them. When the mistake was discovered, the lab counted the samples, but were unable to attain the LLD.

One of the ten positive results was greater than the minimum detectable concentration (MDC) in April at E-06 (1-131, 1.21 +/- 0.11 pCi/L, MDC= 0.11 pCi/L).

1-131 was not discharged in any of PBNP's liquid discharges in 2023.

The other few indications of positive concentrations were found for Mn-54, Co-58, Fe-59, Co-60, Zn-65, Cs-134 and Cs-137, but were all found to be less than the MDC. Cs-134 was not identified in the PBNP effluent this year and is therefore determined to be false positive.

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 two of the twelve quarterly composites. One site located south of the plant, and one in a sample from north of the plant. Both results were below the statistically calculated MDC. No Sr-90 was discharged in 2023 or in 2012 - 2015 and 2017-2022. A small amount was discharged in March of 2016. Sr-90 has a 28.6 year half-life and, like Cs-137, it is a remnant of atmospheric weapons testing in the '50s and '60s. Therefore, positive Sr-90 concentrations could be indicative of fallout being recycled in Lake Michigan.

However, because the concentrations are below their MDCs, they most likely are false positives and therefore 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 47

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, six had positive tritium indications, and of those, two were greater than the MDC (1st quarter E-01; 181+/-89, MDC= 164, and 1st quarter E-05; 187+89, MDC=164) All results are in pCi/L.

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 Twelve (12) fish were analyzed in 2023 with nine exhibiting detectable amounts of plant related activity. Of these, seven were positive for Cs-137 with two Cs-137 results >MDC. The positive Cs-137 concentrations ranged from 0.012 +/- 0.005 to 0.030 +/- 0.017 pCi/g. Cs-137 was released in low levels during the first and second quarters. 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 Fe-59 and Ru-103. All three positive hits were below the MDC. Fe-59 was discharged in the 2nd and 4th quarters during 2023. Ru-103 was not in any effluent release in 2023.

The highest radionuclide concentration in fish is naturally occurring K-40 with an average concentration of 3.20 +/- 0.41\\pCi/g.

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

11.6 Well Water All tritium results were less than the MDC for the 2023 well samples. One nuclide, Cs-137, was detected in the 1st quarter 2023 sample. The result was 3.1 +/- 2.6 pCi/L and was less than the MDC of 6.6. 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 2023. 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 48

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 2023, Cs-137 was detected in all six of the soil samples obtained in September.

The concentrations ranged from 0.077 +/- 0.03 to 0.422 +/- 0.04 pCi/g and all were

>MDC. The highest value for Cs-137 was found at E-02. There was one U2 containment forced vent airborne release from November 3 through November 6, 2023 which contained Cs-137. Activity from the release measured 1.36E-04 µCi at a concentration of 4. 78E-08 pCi/cc. This release would have been after the soil samples were collected and would not have accounted for these soil results.

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. All three samples obtained had Cs-137 concentrations statistically different from zero with one sample below the MDC, and two above. All three were well below the LLD of 0.15.

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 sorted from the beach leaving the heavier sand; hence the lower Cs-137 concentrations in beach samples. In contrast to Cs-137, K-40, which is actually part of the minerals making up the clay and sand, is at a concentration about several hundred times higher than the Cs-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.

49

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 0.80 +/- 0. 76 pCi/g. In general vegetation Be-7 concentrations were higher in the fall than in the spring and ranged from 0.08 +/- 0.12 to 2.13 +/- 0.33 pCi/g. The average Be-7 concentrations in the vegetation increased from May (0.17 +/- 0.10 pCi/g) to September (1.43+/- 0.56). 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 2.66 +/- 0.12 to 6.65 +/- 0.42.

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 2023, three of the twelve vegetation samples had a positive indication for Cs-137.

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. From 2018-2022 there was no airborne Cs-137 released in plant effluents. 2023 had one Cs-137 that occurred in November.

This was after the samples had been collected and would not have accounted for the results. Therefore, 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.

There was no positive sample results for Cs-134 in vegetation samples. One positive Co-60 at E-06 was detected in the 2023 vegetation samples. One positive 1-131 result was detected in the vegetation samples at E-04. All identified isotopes were less than the MDC.

Based on the 2023 vegetation sampling results, it is concluded that there is little or no effect from PBNP effluents.

11.10 Land Use Census (LUC)

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 50

completed in 2023. 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 2023 LUC revealed that one garden location within a 5-mile radius of the site in the N sector required replacement. This garden location was not previously identified in 2020 either. The 2023 LUC also revealed a milking animals location within a 5-mile radius of the site in the NNW sector required replacement. Again, this location was identified in 2020. Two new garden locations were identified in the 2023 LUC for the WNW and W sectors. None of the changes identified in the 2023 LUC necessitate changes to the current REMP, such as the addition of new sampling locations.

11.11 Long Term TLD Trending To put the 2023 REMP TLD results in perspective, it is instructive to look at long term trends. The following examines the TLD results from 1971 to 2023. The ANSI standard (ANSI/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 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 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.

51

2 1.5 1

0.5 F_igure 11-7 E-01 Results 1971 - :?02~

E-01 (mR/7-days) 0....._ __

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.

3.50 3.00 0.50 0.00 Figure 11-8 Comparison of E-03 a_nd E-20 Results 1971 - 2023

- --- - _ _) ____ - ---

i i

- -~--

l

- --- ---- -- --- -r- -- -

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

--- E E-20 ---* _._ -+-

--+-

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.

52

Figure 11-9 Comparison _of E-01, E-02, _E-03 and E-04 (1992 -2023) _

2.00 1.80 1.60 en 1.40

~ 1.20

,.:_ 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 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).

53

Figure 11-10 E-03, E-31, E-44 and Background Site E-20 Results 1992 to 2023 2.00 1.80 1.60

.,, 1.40 ta 1.20 I' 1.00 ix- 0.80 E 0.60 0.40 0.20 0.00 i

l !

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

_._ E-01 _._ 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.

54

12.0 REMP CONCLUSION Based on the analytical results from the 757 environmental samples (721 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 2023, 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 into 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 11-1 O].

55

I Part D GROUNDWATER MONITORING 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 2023 the sampling program consisted of beach drains, intermittent stream and bog locations, drinking water wells, fagade wells, yard electrical manholes, ground water monitoring wells, and the subsurface drainage (SSD) system sump located in the U-2 fa9ade.

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/ 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 56 I

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 2023.

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

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

In the 1990s, two wells were sunk in each unit's fagade to monitor the groundwater levels and look for evidence of concrete integrity as part of the ISi IWE Containment Inspection Program. These wells are stand pipes which are sampled periodically for chemical analyses.

Fagade well sampling has been part of the GWPP since 2007. These wells are sampled 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 beach erosion.

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.

57

Figure 13-1 Groundwater Monitoring Locations 58

14.0 RESULTS AND DISCUSSION 14.1 Streams and Bogs Month Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Average 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 near the MDC and lower than the results in the beach drain run-off samples. 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/1)

GW-01 (E-01)

GW-02 GW-03 GW-17 Creek Confluence E. Creek W. Creek STP 80

+/-

84 218

+/- 91 153

+/- 88 319

+/- 96 113

+/-

79 327

+/- 91 106

+/- 79 475

+/- 99 156

+/-

88 306

+/- 95 92

+/- 84 370

+/- 98 227

+/-

88 235

+/- 88 168

+/- 85 388

+/- 96 BOGS GW-07 GW-08 187

+/-

91 214

+/- 92 199

+/- 91 332

+/- 98 344 +/- 99 501 +/- 106 215

+/-

88 288

+/- 92 153

+/- 85 246

+/- 90 226

+/-

89 226

+/- 89 148

+/- 85 260

+/- 91 217

+/-

92 207

+/- 92 89

+/- 85 270

+/- 95 98

+/-

82 82

+/- 81 114

+/- 83 239

+/- 89 NS

+/-

NS NS

+/- NS NS

+/- NS 85

+/-

87 187

+/- 93 43

+/- 85 237

+/- 95 68

+/-

83 169

+/- 89 143

+/- 87 262

+/- 93 152

+/-

65 224

+/- 68 128

+/- 44 309

+/- 76 MDC 160 154 164 161 161 163 162 161 163 172 171 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. The West Creek (GW-03) samples had tritium results right at the MDC in most cases. Small positive tritium concentrations occurred in the samples from the confluence of the two creeks (GW-01 ), which again are similar to the West Creek concentrations. 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 higher than the bog at GW-07 north of the former retention pond. The GW-08 bog result is increased a little from 2022, but is down from the 3200 - 3800 pCi/1 seen in 1999 before the retention pond was remediated. A gamma analysis of the GW-07 bog sample from May 2023 showed no positive isotopes. Previous years' gamma scans did not show any 59

indications of isotopes either, and the increased tritium result at GW-07 may be attributed to washout/snowmelt during the spring from previous releases.

14.2 Beach Drains The 2023 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-10 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 fac;ade. Sample points S-8 and S-13 did not have analyzes due to no flow during sample collection. These points are excluded from Table 14-2.

Table 14-2 2023 Beach Drain H-3 Concentration (pCi/h Month S-1 S-3 Jan 415 +/- 95 178 +/- 83 Feb 358 +/- 98 1716 +/- 153 Mar 386 +/- 97 436 +/- 99 Apr 470 +/- 100 381 +/- 96 May 435 +/- 100 171 +/- 86 Jun 443 +/- 98 281 +/- 90 Jul 288 +/- 90 317 +/- 91 Aug 381 +/- 97 245 +/- 90 Sep 287 +/- 92 80 +/- 81 Oct 369 +/- 97 211 +/- 89 Nov 322 +/- 96 985 +/- 125 Dec 331 +/- 98 111 +/- 87 Avg= 374 +/- 60 397 +/- 214 ND= not detected and ~MDC NF = no sample due to no flow NF 1407 281 NF NF NF NF NF NF NF NF NF 844 S-7 S-9 S-10

+/-

NF +/-

NF

+/-

+/- 139 NF +/-

NF

+/-

+/- 92 283 +/- 92 655 +/-

+/-

NF +/-

NF

+/-

NF +/-

NF

+/-

NF +/-

NF

+/-

NF +/-

NF

+/-

NF +/-

NF

+/-

NF +/-

NF

+/-

NF +/-

NF

+/-

NF +/-

589 +/-

+/-

NF +/-

NF

+/-

+/- 797 283 +/- 92 622 +/-

NS = no sample

MDC=165 for S-3 in April 92 109 47 S-12 MDC 294

+/-

89 157 287

+/-

94 159 290

+/-

92 163 276

+/-

91 161 500 +/- 103 162 NF

+/-

157 NF

+/-

158 338

+/-

95 159 237

+/-

90 163 NF

+/-

167 244

+/-

93 171 134 +/- 88 171 289

+/- 43 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, Co-58, Co-60, Fe-59, Cs-134, Cs-137, and Ba/La-140. Co-58 was found in the S-9 March sample to be above the MDC (2.9.+/- 1.5 MDC 2.7).

Gaseous effluents would be the most likely cause of a positive hit. There were no gaseous releases with Co-58 in February (sample was from 3/1/23), therefore Co-58 was considered a false positive. Fe-59 was present in S-12 March sample (7.3

+5.4 MDC 4.0). There were no liquid or air releases of Fe-59 in February 2023, therefore it is considered a false positive in the S-12 March 1, 2023, sample.

Recapture could have contributed to the observed positive values, though tritium can be concluded as only PBNP radionuclide positively found in the beach drains.

14.3 Electrical Vaults and Other Manholes 60

Manholes for access to below ground electrical facilities are susceptible to groundwater in-leakage. The manholes on the 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 and Z-067 A through Z-066D and Z-067D 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-066/067D.

Each of the two A, B, C, and D vaults are side by side.

Table 14-3 2023 East Yard Area Manhole Tritium (pCi/1)

MH Spring Fall Z-065A(M-1) 402 +/- 98 320 +/- 97 Z-065B(M-2) 506 +/- 103 325 +/- 97 Z-066A 377 +/- 97 246 +/- 93 Z-067A 334 +/- 95 225 +/- 92 Z-066B 382 +/- 97 146 +/- 88 Z-067B 448 +/- 101 237 +/- 93 Z-066C 453 +/- 101 310 +/- 96 Z-067C 421 +/- 99 237 +/- 94 Z-066D 358 +/- 96 206 +/- 91 Z-067D 256 +/- 91 108 +/- 86 Z-068 603 +/- 108 189 +/- 90 MDC 162 172 Elevated tritium could be attributed to washout from rain/snowmelt as the manholes are outside. Tritium results are similar to what is observed in the subsurface drainage system with no isotopes present.

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 fa9ade. The other is a subsurface drainage system (SSD). The fa9ade 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 fa9ade wells are not located symmetrically in the two units. The Unit 1 fa9ade wells are east of the containment in the SE (1Z-361A) and NE (1Z-361 B) corners of the fa9ade. 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 2023 fa9ade 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 fa9ade, on average having the highest tritium concentrations.

61

Date Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec In addition to tritium analysis, the fagade wells were analyzed for gamma isotopic activity. As in lake w\\ater samples, small positive values below their calculated, minimum detectable concentrations were found for Mn-54, Co-58, Fe-59, Co-60, Cs-137, and Ba-La-140. The 15 pCi/L Lower Limit of Detection (LLD) for Ba-La-140 analysis at the offsite vendor lab was not achieved in 4th quarter for all samples.

The LLD could not be achieved due to the age of sample when received by the laboratory. All other isotope LLDs were achieved for these sample.

Table 14-4 2023 Facade Well Water Tritium (pCi/1)

UNIT 1 UNIT2 Month 12-361A 12-3618 22-361A 22-3618 MDC March 288

+/- 92 221

+/- 89 ND 138 +/- 84 163 May 229

+/- 89 174

+/- 86 91

+/- 82 353 +/- 96 162 Julv 261

+/- 95 230

+/- 93 ND 286 +/- 96 162 October 310

+/- 97 200

+/- 91 88

+/- 85 291 +/- 96 173 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 fagade. A comparison of the 2018 through 2023 SSD results is presented in Table 14-5. In 2023, the tritium results were similar as to what was observed in 2019-2022.

The SSD samples are scanned for gamma emitters. A few slightly positive values were found for Mn-54, Co-58, Fe-59, Co-60, Zn-65, and Cs-137, Ba-La-140 and all results were below the MDC. The 15 pCi/L Lower Limit of Detection (LLD) for Ba-La-140 analysis at the offsite vendor lab was not achieved in the June, September, October, and November samples. The 15 pCi/L LLD was not achieved for Zr-Nb-95 in September. The LLDs were all missed due to untimely shipping of the collected samples.

Table 14-5 2018 - 2023 Unit 2 Facade SSD Sump H-3 (pCi/1) 2019 2020 2021 2022 2023 oCi/1 20' oCi/1 20' oCi/1 20' pCi/1 20" pCi/1 20" 808

+/-

110 3557 +/-

196 1185

+/-

127 2547

+/-

170 1697

+/-

146 923

+/-

114 3356 +/-

187 1409

+/-

135 2939

+/-

186 1805

+/-

149 924

+/-

116 1915 +/-

150 1605

+/-

148 1820

+/-

155 1072

+/-

132 1580 +/-

136 1468 +/-

134 1437

+/-

139 1112

+/-

129 1384

+/-

138 1470 +/-

131 1225 +/-

129 1174

+/-

131 NS 1392

+/-

136 1784 +/-

146 1217 +/-

130 806

+/-

114 962

+/-

128 2339

+/-

169 1681

+/-

144 2136 +/-

157 6496

+/-

257 1473

+/-

147 1120

+/-

131 1703 +/-

143 1900 +/-

150 2915

+/-

180 2642

+/-

174 1004

+/-

123 1412 +/-

132 1621

+/-

141 2714

+/-

175 1219

+/-

132 1391

+/-

140 8932 +/-

291 1419 +/-

135 2654

+/-

175 1611

+/-

149 462

+/-

104 10877 +/-

318 1170 +/-

130 2672

+/-

175 1197

+/-

128 792

+/-

117 5886

+

240 1241

+

131 2439

+

169 1110

+/-

129 870

+/-

120 Average 3165 +/-

3444 1852 +/-

814 2292

+/-

1514 1694

+/-

703 1277

+/-

507 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 62

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 2023 and the results averaged 289 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 2023.

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 three results at GW-04 in April, May, and June 2023.

These results were almost statistically no different than zero, and all were <MDC.

GW-18 had a detection in the 3rd quarter 2023 which was 124 +/- 83 pCi/L and still less than MDC of 162 (Table 14-6).

GW-04 is analyzed monthly for gamma, and had two slightly positive results each for Co-58 and Cs-137. Both were less than the MDC. This was determined to be false positives as there were no known spills or effluent release pathways that would have interacted with this location.

GW-18 completed its second full year of monitoring and had 3 quarters with no detectable gamma scans and one that contained two slightly positive, but less than MDC results for Co-60 (3.8 +/- 2. 7 pCi/L, MDC 6.5 pCi/L) and Cs-137 (4.1 +/- 2.4 pCi/L, MDC 5.6 pCi/L). There were no known spills or effluent release pathways that would have interacted with this location.

Table 14-6 2023 Potable Well Water Tritium Concentration (pCi/1) 63

Q 1

2 3

4 t:I Warehouse SBCC Gvv-uo, 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 154 Mar ND 164 Apr 108 +/-

81 161 ND ND ND 161 May 88

+/-

85 161 Jun 93

+/-

79 158 Jul ND 162 ND ND 124

+/- 83 162 Aug ND 161 Sep ND 163 Oct ND 169 ND 170 Nov ND 172 Dec ND 171 ND ND ND= not detected 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 2023 Quarterly Monitoring Well Tritium (pCi/1)

MW-01 MW-02 MW-06 MW-05 MW-04 MW-03 GW-11 GW-12 GW-13 GW-14

GW-15 GW-16 93

+/-

84 ND 100

+/-

85 219

+/-

91 245

+/-

92 245

+/-

92 164

+/-

86 ND 118

+/-

83 273

+/-

92 193

+/-

87 285

+/-

92 214

+/-

88 ND ND 155

+/-

85 200

+/-

88 314

+/-

94 ND ND ND 106

+/-

85 122

+/-

86 134

+/-

87 ND= not statistically different from zero and <MDC.

Duplicate samples taken, highest value reported.

NS= no sample available 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.

14.6 Air Conditioning Condensate Samples 64 MDC 159 162 162 171

The results from the airborne tritium recapture study presented in the 2011 AMR demonstrated that the tritium via precipitation was higher close to the plant than away from the plant. Additionally, it was shown that the condensate from AC units located on building roofs and within the plant contained high concentrations of H-3.

Similar results for AC condensate were demonstrated in 2012, 2013, 2014, and 2016. Based on this information AC Condensate samples were moved to a three year periodicity and were obtained in 2022 showing similar results as were previously observed. A comparison of the results is shown in Table 14-8.

Table 14-8 2022 Air Conditioning Tritium Concentration (pCi/1)

Location 2012 H-3 2013 H-3 2014 H-3 2016 H-3 2019 H-3 2022 H-3 (pCi/1) 2cr (pCi/1) 2a (pCi/1) 2cr (pCi/1) 2cr ( pCi/1) 2cr (pCi/1)

NSB (4th floor) 557 +/- 102 478 +/- 102 328 +/- 101 NS NS NS Turbine Bldg 66' 998 +/- 118 757 +/- 112 527 +/- 108 6096 +/- 240 NS 2625 S Service Bldg Roof 5822 +/- 231 2606 +/- 166 2690 +/- 166 2911 +/- 174 920 +/- 114 900 South Gate Roof 473 +/- 99 217 +/- 91 173 +/- 95 171 +/- 85 ND 121 Turbine Bldg 8' 602 +/- 104 1055 +/- 123 874 +/- 119 NS ND 1054 Training Bldg Roof 185 +/- 86 203 +/- 90 ND

+/-

ND ND 138 NS= no sample ND= not detected, measured value - 2a:::;; o These results show that the H-3 concentrations continue to be higher in the immediate vicinity of Units 1 and 2 (S. Service Building and Turbine Building) than at the Training Building, which is some 800 feet south. The higher concentrations occurring within the area of the yard drains feeding beach drains support the conclusion that precipitation scavenging and roof drains continue to be a source for the H-3 found in the beach drains. This was taken from 2022 AMR 65 2cr

+/-

+/- 175

+/- 120

+/- 84

+/- 126

+/- 86

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 fac;ade 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.

66

APPENDIX 1 Microbac Laboratories Inc.

Final Report for the Point Beach Nuclear Plant and Other Analyses Reporting Period: January - December 2023 87 pages follow

@ MICROBAC

MONTHLY PROGRESS REPORT NextEra Energy RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM THE POINT BEACH NUCLEAR PLANT TWO RIVERS, WISCONSIN PREPARED AND SUBMITTED BY Microbac Laboratories Inc.

Project Number: 8006 Reporting Period: January-December, 2023 Reviewed and o,.....>J~

Approved by ___________

~...;;_';::?"_., __

A. Banavali, PhD.

Laboratory Director Distribution:

R. Prucha, 1 email, 1 hardcopy Date

J. 11612-lf-

Section POINT BEACH NUCLEAR PLANT TABLE OF CONTENTS 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 by TLDs........................................................ 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

Sample Type Al AP/Al AP/Al AP/Al AP/Al AP/Al AP/Al

.POINT BEACH NUCLEAR PLANT 2.0 _LISTING OF MISSED SAMPLES Expected Collection Location Date Reason E-01, E-02, Samples were mispladed by the E-03, E-04, 05-24-23 shipping company, arrived on 7/7/23.

E-08, E-20 Unable to reach MDA.

Sampler found not running due to a E-08 06-07-23 tripped fuse. Very low sample volume.

Sampler found not running due to a E-08 06-28-23 tripped fuse. Very low sample volume.

Sampler found not running due to a E-01 07-05-23 tripped fuse. Very low sample volume.

Sampler found not running due to a E-01 07-12-23 tripped fuse. Very low sample volume.

E-01 08-30-23 Sampler found not running due to a power outage.

E-01 09-07-23 Sampler found not running due to a power outage.

V

POINT BEACH NUCLEAR PLANT 3.0 Data Tables vi

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

Location: E-01, Meteorological Tower Units: pCi/m3 Collection: Continuous, weekly exchange.

Date Vol.

Collected (m3)

Required LLD 01-04-23 01-11-23 01-18-23 01-26-23 02-01-23 02-08-23 02-15-23 02-21-23 02-28-23 03-08-23 03-15-23 03-22-23 03-28-23 1st Quarter Mean+/- s.d.

04-06-23 04-13-23 04-19-23 04-25-23 05-03-23 05-09-23 05-17-23 05-24-23 05-31-23 06-07-23 06-13-23 06-21-23 06-28-23 2nd Quarter Mean+/- s.d.

298 313 304 346 272 294 306 271 305 348 303 309 251 386 300 270 255 344 257 356 298 293 311 256 341 306 Gross Beta 1-131 0.010 0.030 0.049 +/- 0.005 < 0.019 0.033 +/- 0.004 < 0.007 0.032 +/- 0.004 < 0.011 0.025 +/- 0.004 < 0.012 0.025 +/- 0.004 < 0.016 0.036 +/- 0.004 < 0.018 0.030 +/- 0.004 < 0.016 0.031 +/- 0.004 < 0.015 0.021 +/- 0.004 < 0.010 0.029 +/- 0.004 < 0.014 0.022 +/- 0.004 < 0.012 0.027 +/- 0.004 < 0.011 0.037 +/- 0.005 < 0.008 0.031 +/- 0.008 < 0.013 0.027 +/- 0.003 < 0.007 0.035 +/- 0.004 < 0.013 0.023 +/- 0.004 < 0.013 0.017 +/- 0.004 < 0.017 0.008 +/- 0.003 < 0.012 0.014 +/- 0.003 < 0.012 0.025 +/- 0.003 < 0.010 0.024 +/- 0.003 NS 8

0.020 +/- 0.003 < 0.019 0.030 +/- 0.004 < 0.017 0.011 +/- 0.003 < 0.011 0.014 +/- 0.003 < 0.011 0.022 +/- 0.003 < 0.009 0.021 +/- 0.008 < 0.013 a "NS" = No sample; see Table 2.0, Listing of Missed Samples.

1-1 Date Vol.

Collected (m3)

Required LLD 07-05-23 07-12-23 07-19-23 07-26-23 08-02-23 08-09-23 08-16-23 08-22-23 08-30-23 09-07-23 09-13-23 09-20-23 09-27-23 10-03-23 3rd Quarter Mean+/- s.d.

10-11-23 10-18-23 10-25-23 11-01-23 11-07-23 11-15-23 11-21-23 11-29-23 12-06-23 12-14-23 12-20-23 12-27-23 01-03-24 4th Quarter Mean+/- s.d.

263 305 309 304 307 265 252 294 307 261 351 306 312 310 293 298 263 354 298 342 253 298 302 Gross Beta 1-131 0.010 0.030 NS 8

NS 8

0.018 +/- 0.004 < 0.013 0.023 +/- 0.003 < 0.027 0.018 +/- 0.003 < 0.016 0.023 +/- 0.004 < 0.017 0.020 +/- 0.003 < 0.020 0.022 +/- 0.004 < 0.015 NS 8

NS 8

0.012 +/- 0.004 < 0.011 0.023 +/- 0.003 < 0.022 0.047 +/- 0.004 < 0.009 0.047 +/- 0.005 < 0.008 0.025 +/- 0.012 < 0.016 0.008 +/- 0.004 < 0.009 0.013 +/- 0.003 < 0.013 0.027 +/- 0.004 < 0.008 0.022 +/- 0.003 < 0.009 0.044 +/- 0.004 < 0.015 0.019 +/- 0.003 < 0.008 0.035 +/- 0.004 < 0.010 0.025 +/- 0.003 < 0.009 0.033 +/- 0.004 < 0.011 0.034 +/- 0.004 < 0.010 0.040 +/- 0.005 < 0.009 0.050 +/- 0.005 < 0.014 0.021 +/- 0.004 < 0.007 0.028 +/- 0.012 < 0.010 Cumulative Average 0.026 +/- 0.01 O < 0.013

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 Units: pCi/m3 Collection: Continuous, weekly exchange.

Date Vol.

Collected (m3)

Required LLD 01-04-23 01-11-23 01-18-23 01-26-23 02-01-23 02-08-23 02-15-23 02-21-23 02-28-23 03-08-23 03-15-23 03-22-23 03-28-23 1st Quarter Mean+/- s.d.

04-06-23 04-13-23 04-19-23 04-25-23 05-03-23 05-09-23 05-17-23 05-24-23 05-31-23 06-07-23 06-13-23 06-21-23 06-28-23 2nd Quarter Mean+/- s.d.

305 312 308 348 265 305 305 269 310 356 304 304 257 390 300 270 256 339 256 355 296 291 306 255 344 304 Gross Beta 1-131 0.010 0.030 0.054 +/- 0.005 < 0.019 0.034 +/- 0.004 < 0.007 0.027 +/- 0.004 < 0.011 0.029 +/- 0.004 < 0.012 0.024 +/- 0.004 < 0.016 0.035 +/- 0.004 < 0.018 0.029 +/- 0.004 < 0.016 0.025 +/- 0.004 < 0.015 0.019 +/- 0.003 < 0.010 0.030 +/- 0.004 < 0.014 0.023 +/- 0.004 < 0.012 0.027 +/- 0.004 < 0.011 0.035 +/- 0.005 < 0.008 0.030 +/- 0.008

< 0.013 0.027 +/- 0.003 < 0.007 0.039 +/- 0.004 < 0.013 0.020 +/- 0.004 < 0.013 0.017 +/- 0.004 < 0.017 0.007 +/- 0.003

< 0.012 0.017 +/- 0.004 < 0.012 0.019 +/- 0.003 < 0.010 0.017 +/- 0.003 NS 8

0.025 +/- 0.004 < 0.019 0.026 +/- 0.004 < 0.018 0.012 +/- 0.003 < 0.011 0.016 +/- 0.003 < 0.011 0.024 +/- 0.003 < 0.009 0.020 +/- 0.008 < 0.013 Date Vol.

Collected (m3)

Required LLD 07-05-23 07-12-23 07-19-23 07-26-23 08-02-23 08-09-23 08-16-23 08-22-23 08-30-23 09-07-23 09-13-23 09-20-23 09-27-23 10-03-23 3rd Quarter Mean+/- s.d.

10-11-23 10-18-23 10-25-23 11-01-23 11-07-23 11-15-23 11-21-23 11-29-23 12-06-23 12-14-23 12-20-23 12-27-23 01-03-24 4th Quarter Mean+/- s.d.

297 313 305 302 299 302 307 265 345 341 266 297 300 259 357 311 307 308 298 302 264 343 303 340 255 297 303 Gross Beta 1-131 0.010 0.030 0.031 +/- 0.004 < 0.006 0.018 +/- 0.003 < 0.013 0.021 +/- 0.003 < 0.011 0.021 +/- 0.003 < 0.022 0.020 +/- 0.003 < 0.017 0.029 +/- 0.004 < 0.016 0.023 +/- 0.004 < 0.022 0.024 +/- 0.004 < 0.019 0.023 +/- 0.003 < 0.012 0.027 +/- 0.004 < 0.016 0.012 +/- 0.003 < 0.011 0.027 +/- 0.004 < 0.021 0.049 +/- 0.005 < 0.009 0.047 +/- 0.005 < 0.008 0.026 +/- 0.010 < 0.015 0.006 +/- 0.004 < 0.009 0.010 +/- 0.003 < 0.013 0.029 +/- 0.004 < 0.008 0.025 +/- 0.004 < 0.009 0.042 +/- 0.004 < 0.014 0.018 +/- 0.003 < 0.008 0.040 +/- 0.005 < 0.010 0.028 +/- 0.003 < 0.009 0.038 +/- 0.004 < 0.011 0.033 +/- 0.004 < 0.010 0.044 +/- 0.005 < 0.009 0.048 +/- 0.005 < 0.014 0.018 +/- 0.004 < 0.007 0.029 +/- 0.013 < 0.010 Cumulative Average 0.026 +/- 0.01 O < 0.013 a "NS" = 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/m3 Collection: Continuous, weekly exchange.

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 01-04-23 309 0.048 +/- 0.005 < 0.018 07-05-23 310 0.025 +/- 0.003 < 0.006 01-11-23 309 0.031 +/- 0.004 < 0.008 07-12-23 310 0.016 +/- 0.003 < 0.014 01-18-23 311 0.025 +/- 0.004 < 0.011 07-19-23 309 0.018 +/- 0.003 < 0.011 01-26-23 350 0.024 +/- 0.003 < 0.012 07-26-23 305 0.025 +/- 0.004 < 0.025 02-01-23 266 0.029 +/- 0.004 < 0.016 08-02-23 305 0.019 +/- 0.003 < 0.016 02-08-23 294 0.041 +/- 0.004 < 0.018 08-09-23 298 0.024 +/- 0.004 < 0.012 02-15-23 307 0.029 +/- 0.004 < 0.016 08-16-23 306 0.020 +/- 0.003 < 0.021 02-21-23 265 0.026 +/- 0.004 < 0.015 08-22-23 259 0.024 +/- 0.004 < 0.016 02-28-23 304 0.021 +/- 0.004 < 0.010 08-30-23 348 0.019 +/- 0.003 < 0.012 03-08-23 351 0.032 +/- 0.004 < 0.014 09-07-23 340 0.026 +/- 0.004 < 0.016 03-15-23 304 0.022 +/- 0.004 < 0.012 09-13-23 267 0.015 +/- 0.004 < 0.011 03-22-23 303 0.029 +/- 0.004 < 0.011 09-20-23 302 0.025 +/- 0.003 < 0.021 03-28-23 253 0.039 +/- 0.005 < 0.008 09-27-23 307 0.043 +/- 0.004 < 0.009 10-03-23 259 0.047 +/- 0.005 < 0.008 1st Quarter 3rd Quarter Mean+/- s.d.

0.030 +/- 0.008 < 0.013 Mean+/- s.d.

0.025 +/- 0.009 < 0.014 04-06-23 389 0.028 +/- 0.003 < 0.007 10-11-23 364 0.005 +/- 0.004 < 0.009 04-13-23 296 0.034 +/- 0.004 < 0.013 10-18-23 309 0.012 +/- 0.003 < 0.013 04-19-23 267 0.022 +/- 0.004 < 0.013 10-25-23 310 0.029 +/- 0.004 < 0.008 04-25-23 253 0.019 +/- 0.004 < 0.017 11-01-23 315 0.025 +/- 0.003 < 0.008 05-03-23 341 0.010 +/- 0.003 < 0.012 11-07-23 296 0.043 +/- 0.004 < 0.015 05-09-23 257 0.015 +/- 0.003 < 0.012 11-15-23 302 0.019 +/- 0.003 < 0.008 05-17-23 354 0.024 +/- 0.003 < 0.010 11-21-23 262 0.036 +/- 0.005 < 0.010 05-24-23 298 0.020 +/- 0.003 NS 8

11-29-23 355 0.023 +/- 0.003 < 0.009 05-31-23 298 0.022 +/- 0.003 < 0.019 12-06-23 300 0.036 +/- 0.004 < 0.011 06-07-23 314 0.032 +/- 0.004 < 0.017 12-14-23 348 0.033 +/- 0.004 < 0.010 06-13-23 253 0.013 +/- 0.003 < 0.011 12-20-23 256 0.041 +/- 0.005 < 0.009 06-21-23 343 0.016 +/- 0.003 < 0.011 12-27-23 299 0.047 +/- 0.005 < 0.014 06-28-23 290 0.028 +/- 0.004 < 0.010 01-03-24 308 0.017 +/- 0.004 < 0.007 2nd Quarter 4th Quarter Mean+/- s.d.

0.022 +/- 0.007 < 0.013 Mean+/- s.d.

0.028 +/- 0.013 < 0.010 Cumulative Avera~e 0.026 +/- 0.010 < 0.013 a "NS" = 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 Units: pCi/m3 Collection: Continuous, weekly exchange.

Date Vol.

Collected (m3)

Required LLD 01-04-23 01-11-23 01-18-23 01-26-23 02-01-23 02-08-23 02-15-23 02-21-23 02-28-23 03-08-23 03-15-23 03-22-23 03-28-23 1st Quarter Mean+/- s.d.

04-06-23 04-13-23 04-19-23 04-25-23 05-03-23 05-09-23 05-17-23 05-24-23 05-31-23 06-07-23 06-13-23 06-21-23 06-28-23 2nd Quarter Mean+/- s.d.

307 308 304 348 267 300 307 261 306 345 298 311 259 394 302 269 253 340 256 354 297 291 307 257 343 297 Gross Beta 1-131

.0.010

.0.030 0.049 +/- 0.005 < 0.018 0.031 +/- 0.004 < 0.008 0.026 +/- 0.004 < 0.011 0.029 +/- 0.004 < 0.012 0.030 +/- 0.004 < 0.016 0.038 +/- 0.004 < 0.018 0.026 +/- 0.004 < 0.016 0.026 +/- 0.004 < 0.015 0.018 +/- 0.003 < 0.010 0.031 +/- 0.004 < 0.014 0.020 +/- 0.004 < 0.012 0.025 +/- 0.004 < 0.011 0.034 +/- 0.005 < 0.008 0.030 +/- 0.008 < 0.013 0.028 +/- 0.003 < 0.007 0.030 +/- 0.004 < 0.013 0.019 +/- 0.004 < 0.013 0.012 +/- 0.004 < 0.017 0.009 +/- 0.003 < 0.012 0.015 +/- 0.004 < 0.012 0.023 +/- 0.003 < 0.010 0.017 +/- 0.003 NS 8

0.023 +/- 0.004 < 0.019 0.030 +/- 0.004 < 0.017 0.013 +/- 0.003 < 0.011 0.015 +/- 0.003 < 0.011 0.026 +/- 0.004 < 0.010 0.020 +/- 0.007 < 0.013 a "NS" = No sample; see Table 2.0, Listing of Missed Samples.

1-4 Date Vol.

Collected (m3)

Required LLD 07-05-23 07-12-23 07-19-23 07-26-23 08-02-23 08-09-23 08-16-23 08-22-23 08-30-23 09-07-23 09-13-23 09-20-23 09-27-23 10-03-23 3rd Quarter Mean+/- s.d.

10-11-23 10-18-23 10-25-23 11-01-23 11-07-23 11-15-23 11-21-23 11-29-23 12-06-23 12-14-23 12-20-23 12-27-23 01-03-24 4th Quarter Mean+/- s.d.

306 316 311 309 301 301 311 255 347 342 277 303 316 258 372 307 314 319 297 302 267 357 298 346 260 299 308 Gross Beta 1-131 0.010 0.030 0.025 +/- 0.003 < 0.006 0.019 +/- 0.003 < 0.017 0.016 +/- 0.003 < 0.011 0.020 +/- 0.003 < 0.022 0.020 +/- 0.003 < 0.014 0.028 +/- 0.004 < 0.016 0.019 +/- 0.003 < 0.024 0.022 +/- 0.004 < 0.015 0.020 +/- 0.003 < 0.012.

0.026 +/- 0.004 < 0.016 0.012 +/- 0.003 < 0.010 0.026 +/- 0.004 < 0.021 0.042 +/- 0.004 < 0.008 0.053 +/- 0.005 < 0.008 0.025 +/- 0.011

< 0.014 0.005 +/- 0.004 < 0.009 0.009 +/- 0.003 < 0.013 0.026 +/- 0.003 < 0.008 0.025 +/- 0.003 < 0.008 0.042 +/- 0.004 < 0.014 0.020 +/- 0.003 < 0.008 0.034 +/- 0.004 < 0.010 0.027 +/- 0.003 < 0.009 0.042 +/- 0.005 < 0.011 0.034 +/- 0.004 < 0.010 0.045 +/- 0.005 < 0.009 0.046 +/- 0.005 < 0.014 0.019 +/- 0.004 < 0.007 0.029 +/- 0.013 < 0.010 Cumulative Average 0.025 +/- 0.01 O < 0.013

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/m3 Collection: Continuous, weekly exchange.

Date Collected Reguired LLD 01-04-23 01-11-23 01-18-23 01-26-23 02-01-23 02-08-23 02-15-23 02-21-23 02-28-23 03-08-23 03-15-23 03-22-23 03-28-23 1st Quarter Mean+/- s.d.

04-06-23 04-13-23 04-19-23 04-25-23 05-03-23 05-09-23 05-17-23 05-24-23 05-31-23 06-07-23 06-13-23 06-21-23 06-28-23 2nd Quarter Mean+/- s.d.

Vol.

(m3) 307 308 304 350 269 299 304 261 307 340 309 300 268 387 295 270 252 347 254 351 302 293 255 344 Gross Beta 1-131 0.010 0.030 0.049 +/- 0.005 < 0.018 0.034 +/- 0.004 < 0.008 0.025 +/- 0.004 < 0.011 0.021 +/- 0.003 < 0.012 0.033 +/- 0.004 < 0.016 0.035 +/- 0.004 < 0.018 0.031 +/- 0.004 < 0.016 0.027 +/- 0.004 < 0.015 0.022 +/- 0.004 < 0.010 0.032 +/- 0.004 < 0.014 0.026 +/- 0.004 < 0.011 0.027 +/- 0.004 < 0.012 0.033 +/- 0.005 < 0.008 0.030 +/- 0.007 < 0.013 0.026 +/- 0.003 < 0.007 0.030 +/- 0.004 < 0.013 0.021 +/- 0.004 < 0.013 0.013 +/- 0.004 < 0.018 0.007 +/- 0.003 < 0.012 0.013 +/- 0.003 < 0.012 0.024 +/- 0.003 < 0.010 0.023 +/- 0.003 NS 8

0.022 +/- 0.003 < 0.019 NS 8

0.011 +/- 0.003 < 0.011 0.018 +/- 0.003 < 0.011 NS 8

0.019 +/- 0.007 < 0.013 Date Collected Reguired LLD b 07-03-23 07-12-23 07-19-23 07-25-23 08-02-23 08-09-23 08-16-23 08-22-23 08-30-23 09-07-23 09-13-23 09-20-23 09-27-23 10-03-23 3rd Quarter Mean+/- s.d.

10-11-23 10-18-23 10-25-23 11-01-23 11-07-23 11-15-23 11-21-23 11-29-23 12-06-23 12-14-23 12-20-23 12-27-23 01-03-24 4th Quarter Mean+/- s.d.

Vol.

(m3) 227 298 306 263 341 292 310 263 349 329 271 300 289 263 348 311 311 312 287 304 259 353 300 339 256 297 304 Cumulative Average Indicator Locations Annual Mean+/- s.d.

a "NS"= No sample; see Table 2.0, Listing of Missed Samples.

0 Sampler found not running due to a tripped fuse.

1-5 Gross Beta 1-131 0.010 0.030 0.028 +/- 0.004 < 0.009 0.018 +/- 0.003 < 0.019 0.018 +/- 0.003 < 0.011 0.021 +/- 0.004 < 0.020 0.022 +/- 0.003 < 0.017 0.027 +/- 0.004 < 0.016 0.021 +/- 0.003 < 0.021 0.024 +/- 0.004 < 0.017 0.018 +/- 0.003 < 0.012 0.028 +/- 0.004 < 0.017 0.016 +/- 0.004 < 0.010 0.022 +/- 0.003 < 0.021 0.041 +/- 0.004 < 0.009 0.051 +/- 0.005 < 0.008 0.025 +/- 0.010 < 0.015 0.003 +/- 0.004 < 0.010 0.011 +/- 0.003 < 0.013 0.030 +/- 0.004 < 0.008 0.023 +/- 0.003 < 0.009 0.044 +/- 0.005 < 0.015 0.019 +/- 0.003 < 0.008 0.032 +/- 0.004 < 0.010 0.028 +/- 0.003 < 0.009 0.033 +/- 0.004 < 0.011 0.035 +/- 0.004 < 0.011 0.044 +/- 0.005 < 0.009 0.048 +/- 0.005 < 0.014 0.019 +/- 0.004 < 0.007 0.028 +/- 0.013 < 0.010 0.025 +/- 0.010 < 0.013 0.026 +/- 0.010

< 0.013

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

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

Date Vol.

Collected (m3)

Required LLD 01-04-23 01-11-23 01-18-23 01-26-23 02-01-23 02-08-23 02-15-23 02-21-23 02-28-23 03-08-23 03-15-23 03-22-23 03-28-23 1st Quarter Mean+/- s.d.

04-06-23 04-13-23 04-19-23 04-25-23 05-03-23 05-09-23 05-17-23 05-24-23 05-31-23 06-07-23 06-13-23 06-21-23 06-28-23 2nd Quarter Mean+/- s.d.

316 319 307 349 272 303 317 268 304 362 313 312 267 400 301 278 255 340 258 350 295 295 319 262 351 308 Gross Beta 1-131 0.010 0.030 0.053 +/- 0.005

< 0.018 0.037 +/- 0.004 < 0.007 0.026 +/- 0.004 < 0.011 0.024 +/- 0.004 < 0.012 0.028 +/- 0.004 < 0.016 0.037 +/- 0.004 < 0.018 0.027 +/- 0.004 < 0.015 0.026 +/- 0.004 < 0.015 0.022 +/- 0.004 < 0.010 0.025 +/- 0.003 < 0.013 0.021 +/- 0.004 < 0.011 0.027 +/- 0.004 < 0.011 0.032 +/- 0.005 < 0.008 0.030 +/- 0.009 < 0.013 0.025 +/- 0.003 < 0.007 0.031 +/- 0.004 < 0.013 0.020 +/- 0.004 < 0.013 0.017 +/- 0.004 < 0.017 0.025 +/- 0.004 < 0.012 0.017 +/- 0.004 < 0.012 0.020 +/- 0.003 < 0.010 0.018 +/- 0.003 NS 8

0.020 +/- 0.003 < 0.019 0.029 +/- 0.004 < 0.017 0.013 +/- 0.003 < 0.011 0.021 +/- 0.003 < 0.011 0.024 +/- 0.003 < 0.009 0.021 +/- 0.005 < 0.012 Date Collected Required LLD 07-05-23 07-12-23 07-19-23 07-26-23 08-02-23 08-09-23 08-16-23 08-22-23 08-30-23 09-07-23 09-13-23 09-20-23 09-27-23 10-03-23 3rd Quarter Mean+/- s.d.

10-11-23 10-18-23 10-25-23 11-01-23 11-07-23 11-15-23 11-21-23 11-29-23 12-06-23 12-14-23 12-20-23 12-27-23 01-03-24 4th Quarter Mean+/- s.d.

Vol.

(m3) 303 308 303 298 307 296 309 260 348 331 270 300 305 258 362 302 307 319 303 307 263 345 301 341 260 299 309 Gross Beta 1-131 0.010 0.030 0.028 +/- 0.004 < 0.006 0.015 +/- 0.003 < 0.017 0.018 +/- 0.003 < 0.011 0.026 +/- 0.004 < 0.018 0.021 +/- 0.003 < 0.015 0.029 +/- 0.004 < 0.015 0.023 +/- 0.004 < 0.023 0.028 +/- 0.004 < 0.016 0.023 +/- 0.003 < 0.012 0.029 +/- 0.004 < 0.017 0.013 +/- 0.003 < 0.010 0.025 +/- 0.003 < 0.021 0.046 +/- 0.004 < 0.009 0.044 +/- 0.005 < 0.008 0.026 +/- 0.009 < 0.014 0.005 +/- 0.004 < 0.009 0.014 +/- 0.003 < 0.014 0.028 +/- 0.004 < 0.008 0.026 +/- 0.003 < 0.008 0.039 +/- 0.004 < 0.014 0.018 +/- 0.003 < 0.008 0.038 +/- 0.005 < 0.010 0.025 +/- 0.003 < 0.009 0.040 +/- 0.004 < 0.011 0.034 +/- 0.004 < 0.010 0.042 +/- 0.005 < 0.009 0.047 +/- 0.005 < 0.014 0.017 +/- 0.004 < 0.007 0.029 +/- 0.013 < 0.010 Cumulative Average 0.026 +/- 0.009 < 0.012 Control Annual Mean+/- s.d.

0.027 +/- 0.010 < 0.012 a "NS" = No sample; see Table 2.0, Listing of Missed Samples.

1-6

POINT BEACH NUCLEAR PLANT Table 2. Gamma emitters in quarterly composites of air particulate filters Units: pCi/m 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 m3 1st quarter E-01 EAP-822 0.058 +/- 0.013

-0.0003 +/- 0.0005

< 0.0009 0.0000 +/- 0.0006 < 0.0009 0.0004 +/- 0.0006 < 0.0009 3919 E-02

- 823 0.059 +/- 0.011

-0.0004 +/- 0.0003

< 0.0006 0.0002 +/- 0.0003 < 0.0006 0.0001 +/- 0.0004 < 0.0006 3947 E-03

- 824 0.056 +/- 0.009

-0.0030 +/- 0.0005

< 0.0007

-0.0003 +/- 0.0004 < 0.0006 0.0004 +/- 0.0004 < 0.0007 3926 E-04

- 825 0.043 +/- 0.008 0.0000 +/- 0.0003

< 0.0006 0.0001 +/- 0.0004 < 0.0008

-0.0004 +/- 0.0004 < 0.0005 3920 E-08

- 826 0.077 +/- 0.012

-0.0003 +/- 0.0004

< 0.0007 -0.0001 +/- 0.0005 < 0.0007 0.0002 +/- 0.0005 < 0.0006 3925 E-20

- 827 0.063 +/- 0.009

-0.0003 +/- 0.0003

< 0.0006 0.0004 +/- 0.0004 < 0.0005

-0.0001 +/- 0.0004 < 0.0004 4008 2nd Quarter E-01 EAP-2066 0.081 +/- 0.016 0.0001 +/- 0.0005

< 0.0009 0.0001 +/- 0.0005 < 0.0007 0.0000 +/- 0.0006 < 0.0005 3971 E-02

- 2067 0.082 +/- 0.017 0.0002 +/- 0.0006

< 0.0008 0.0001 +/- 0.0005 < 0.0007

-0.0001 +/- 0.0006 < 0.0005 3961 E-03

- 2068 0.072 +/- 0.016 0.0004 +/- 0.0005

< 0.0011

-0.0002 +/- 0.0005 < 0.0007 0.0005 +/- 0.0006 < 0.0008 3951 E-04

- 2069 0.076 +/- 0.017 0.0003 +/- 0.0004

< 0.0007

-0.0002 +/- 0.0005 < 0.0004

-0.0002 +/- 0.0006 < 0.0008 3959 E-08

- 2070 0.073 +/- 0.019 0.0003 +/- 0.0006

< 0.0010 0.0002 +/- 0.0006 < 0.0008

-0.0001 +/- 0.0006 < 0.0008 3350 E-20

- 2071 0.072 +/- 0.015 0.0000 +/- 0.0006

< 0.0009 -0.0001 +/- 0.0005 < 0.0006 0.0001 +/- 0.0004 < 0.0005 4012 3rd Quarter E-01 EAP-3147 0.086 +/- 0.017

-0.0002 +/- 0.0004

< 0.0009 0.0003 +/- 0.0005 < 0.0014

-0.0008 +/- 0.0008 < 0.0019 2866 E-02

- 3148 0.071 +/- 0.008

-0.0001 +/- 0.0002

< 0.0005 0.0003 +/- 0.0003 < 0.0008 0.0002 +/- 0.0003 < 0.0010 4198 E-03

- 3149 0.o75 +/- 0.003 0.0001 +/- 0.0001

< 0.0002 0.0005 +/- 0.0004 < 0.0003 0.0003 +/- 0.0005 < 0.0005 4225 E-04

- 3150 0.072 +/- 0.014 0.0000 +/- 0.0003

< 0.0007 0.0003 +/- 0.0004 < 0.0011 0.0001 +/- 0.0004 < 0.0015 4253 E-08

- 3151 0.077 +/- 0.013

-0.0002 +/- 0.0004

< 0.0006 -0.0008 +/- 0.0006 < 0.0010

-0.0001 +/- 0.0006 < 0.0013 4099 E-20

- 3152 0.072 +/- 0.013 0.0000 +/- 0.0003

< 0.0007 0.0001 +/- 0.0004 < 0.0010 0.0003 +/- 0.0004 < 0.0013 4195 4th Quarter E-01 EAP-4107 0.049 +/- 0.013

-0.0002 +/- 0.0005

< 0.0008 0.0001 +/- 0.0006 < 0.0007 0.0006 +/- 0.0006 < 0.0007 3980 E-02

- 4108 0.044 +/- 0.011 0.0002 +/- 0.0006

< 0.0012 0.0002 +/- 0.0006 < 0.0010 0.0001 +/- 0.0006 < 0.0008 3987 E-03

- 4109 0.046 +/- 0.012

-0.0002 +/- 0.0006

< 0.0010 0.0000 +/- 0.0005 < 0.0006

-0.0001 +/- 0.0005 < 0.0006 4023 E-04

- 4110 0.051 +/- 0.012 0.0002 +/- 0.0005

< 0.0010 -0.0002 +/- 0.0005 < 0.0007 0.0002 +/- 0.0004 < 0.0008 4045 E-08

- 4111 0.054 +/- 0.013

-0.0006 +/- 0.0005

< 0.0010 -0.0002 +/- 0.0005 < 0.0007 0.0004 +/- 0.0005 < 0.0009 3980 E-20

- 4112 0.038 +/- 0.011

- 0.0000 +/- 0.0005

< 0.0011

-0.0001 +/- 0.0006 < 0.0007 0.0001 +/- 0.0006 < 0.0007 4015 Annual Mean+/-s.d.

0.064 +/- 0.014

-0.0002 +/- 0.0006

< 0.0008 0.0000 +/- 0.0003 < 0.0007 0.0001 +/- 0.0003 < 0.0008 2-1

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

E-11 Lambert Dai(Y Farm MDC MDC MDC Required Collection Date 01-11-23 02-09-23 03-08-23 LLD Lab Code EMI-43 EMI-271 EMI-505 Sr-89 0.2 +/- 0.7

< 0.7

-0.5 +/- 0.5

< 0.5 0.0 +/- 0.6

< 0.7 5.0 Sr-90 0.4 +/- 0.3

< 0.5 0.7 +/- 0.3

< 0.6 0.5 +/- 0.3

< 0.5 1.0 1-131 0.06 +/- 0.15

< 0.29

-0.13 +/- 0.19

< 0.44 0.10 +/- 0.17

< 0.29 0.5 K-40 1371 +/- 110 1298 +/- 49 1410 +/- 45 Cs-134

-0.5 +/- 1.9

< 3.4

-0.3 +/- 0.8

< 1.7

-0.4 +/- 0.6

< 1.2 5.0 Cs-137

-1.0+/-2.1

< 3.3 0.3 +/- 1.0

< 1.8 1.6 +/- 0.8

< 1.6 5.0 Ba-La-140 0.6 +/- 1.7

< 2.0 0.0 +/- 1.0

< 2.1 0.0 +/- 0.7

< 1.4 5.0 Other ( Co-60) 1.4 +/- 2.4

< 3.2 0.4 +/- 1.1

< 2.0 0.3 +/- 0.9

< 1.5 15.0 MDC MDC MDC Required Collection Date 04-12-23 05-10-23 06-15-23 LLD Lab Code EMI-859 EMI-1179 EMI-1570 Sr-89 0.5 +/- 0.6

< 0.7

-0.1 +/- 0.6

< 0.6 0.2 +/- 0.7

< 0.7 5.0 Sr-90 0.3 +/- 0.3

< 0.5 0.7 +/- 0.3

< 0.5 0.5 +/- 0.5

< 0.8 1.0 1-131 0.01 +/- 0.11

< 0.19 0.01 +/- 0.12

< 0.22

-0.02 +/- 0.13

< 0.25 0.5 K-40 1420 +/- 113 1424 +/- 106 1321 +/- 68 Cs-134

-1.7 +/- 1.8

< 3.4

-1.1 +/- 1.5

< 2.8

-0.7 +/- 1.3

< 2.5 5.0 Cs-137

-1.0 +/- 2.4

< 3.6 2.5 +/- 1.7

< 3.3 0.6 +/- 1.5

< 2.3 5.0 Ba-La-140

-2.7 +/- 2.0

< 2.5

-1.8 +/- 1.4

< 0.9

-1.6 +/- 1.6

< 2.5 5.0 Other ( Co-60) 0.8 +/- 2.9

< 3.6

-0.2 +/- 2.1

< 2.7

-2.0 +/- 1.6

< 1.9 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 Dai[Y Farm MDC MDC MDC Required Collection Date 07-12-23 08-09-23 09-13-23 LLD Lab Code EMI-1933 EMI-2379 EMI-2686 Sr-89 0.2 +/- 0.7

< 0.7 0.3 +/- 0.6

< 0.7 0.1 +/- 0.9

< 1.2 5.0 Sr-90 0.5 +/- 0.3

< 0.6 0.3 +/- 0.3

< 0.5

-0.1 +/- 0.3

< 0.8 1.0 1-131 0.04+/-0.11

< 0.20 0.04 +/- 0.17

< 0.31 0.05 +/- 0.19

< 0.38 0.5 K-40 1302 +/- 42 1358 +/- 86 1277 +/- 84 Cs-134

-0.1 +/- 0.7

< 1.5 0.0 +/- 0.7

< 2.7

-1.4 +/- 1.5

< 3.0 5.0 Cs-137 2.6 +/- 0.9

< 2.3 2.1 +/- 0.9

< 4.3 1.1 +/- 1.9

< 4.7 5.0 Ba-La-140 0.5 +/- 0.9

< 1.9 0.0 +/- 0.7

< 1.9 0.4 +/- 1.6

< 1.8 5.0 Other (Co-60) 2.3 +/- 0.9

< 2.6 1.5 +/- 1.0

< 5.2 1.9 +/- 1.8

< 5.1 15.0 MDC MDC MDC Required Collection Date 10-11-23 11-08-23 12-13-23 LLD Lab Code EMI-3059 EMI-3448 EMI-3875 Sr-89

-0.4 +/- 0.7

< 0.7 0.1 +/- 0.7

< 0.7 0.4 +/- 0.8

< 0.7 5.0 Sr-90 0.7 +/- 0.3

< 0.5 0.4 +/- 0.3

< 0.6 0.5 +/- 0.4

< 0.7 1.0 1-131 0.00 +/- 0.22

< 0.41

-0.14 +/- 0.13

< 0.25 0.04 +/- 0.13

< 0.23 0.5 K-40 1247 +/- 39 1278 +/- 66 1277 +/- 90 Cs-134 0.4 +/- 0.8

< 1.3

-0.7+/-1.3

< 2.5

-0.7 +/- 1.7

< 3.0 5.0 Cs-137

.:3.8 +/- 3.2

< 2.1

-0.3 +/- 1.5

< 2.0 0.8 +/- 2.0

< 3.5 5.0 Ba-La-140 0.2 +/- 0.6

< 0.7

-1.0+/-1.5

< 2.4

-1.6 +/- 1.6

< 2.1 5.0 Other (Co-60)

-0.1 +/- 3.3

< 2.3 0.6 +/- 1.6

< 2.9 1.5 +/- 1.8

< 2.3 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 Daii:y Farm MOC MOC MOC Required Collection Date 01-11-23 02-08-23 03-08-23 LLD Lab Code EMI-44 EMI-241 EMI-506 Sr-89

-0.4 +/- 0.6

< 0.7 0.1 +/- 0.4

< 0.5 0.1 +/- 0.5

< 0.7 5.0 Sr-90 0.6 +/- 0.3

< 0.5 0.2 +/- 0.3

< 0.5 1.0 1-131 0.08 +/- 0.18

< 0.33

-0.14+/-0.11

< 0.21 0.02 +/- 0.20

< 0.40 0.5 K-40 1351 +/- 96 1169 +/- 41 1350 +/- 68 Cs-134

-0.4 +/- 1.4

< 2.5 0.2 +/- 0.8

< 1.5

-1.7 +/- 1.3

< 2.6 5.0 Cs-137 2.0 +/- 1.8

< 3.2 0.5 +/- 0.8

< 2.6 0.1 +/- 1.5

< 3.0 5.0 Ba-La-140 0.4+/-1.7

< 2.5 0.0 +/- 0.7

< 1.4

-0.7 +/- 4.7

< 2.8 5.0 Other (Co-60)

-1.6 +/- 1.9

< 2.2 0.0 +/- 1.0

< 3.0

-1.5 +/- 1.6

< 1.9 15.0 MDC MDC MDC Required Collection Date 04-12-23 05-10-23 06-14-23 LLD Lab Code EMI-860 EMI-1180 EMI-1565 Sr-89 0.3 +/- 0.6

< 0.7 0.1 +/- 0.6

< 0.6

-0.1 +/- 0.5

< 0.5 5.0 Sr-90 0.3 +/- 0.3

< 0.5 0.2 +/- 0.3

< 0.6 0.5 +/- 0.3

< 0.6 1.0 1-131

-0.01 +/- 0.11

< 0.20 0.02 +/- 0.13

< 0.23 0.04 +/- 0.15

< 0.27 0.5 K-40 1481 +/- 73 1301 +/- 110 1357 +/- 66 Cs-134 0.0+/-1.1

< 1.8

-0.5 +/- 1.3

< 2.2 0.0 +/- 1.3

< 2.4 5.0 Cs-137 0.9 +/- 1.2

< 2.2

-1.0 +/- 1.8

< 3.2 0.7 +/- 1.5

< 2.7 5.0 Ba-La-140

-1.2 +/- 1.2

< 1.6

-2.1 +/- 1.9

< 1.5

-1.9 +/- 1.5

< 2.1 5.0 Other (Co-60) 0.1 +/- 1.5

< 2.2 1.7 +/- 2.3

< 2.4 1.2 +/- 1.6

< 2.9 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 07-12-23 08-09-23 09-13-23 LLD Lab Code EMI-1934 EMI-2380 EMI-2687 Sr-89

-0.1 +/- 0.7

< 0.8 0.2 +/- 0.6

< 0.8

-0.2 +/- 0.8

< 1.0 5.0 Sr-90 0.4 +/- 0.3

< 0.6 0.1 +/- 0.3

< 0.5 0.2 +/- 0.3

< 0.7 1.0 1-131

-0.02 +/- 0.10

< 0.19 0.00 +/- 0.13

< 0.24 0.01 +/- 0.23

< 0.49 0.5 K-40 1346 +/- 69 1249 +/- 65 1234 +/- 121 Cs-134

-1.3 +/- 1.3

< 2.5 0.2 +/- 1.3

< 2.4

-3.6 +/- 2.6

< 4.6 5.0 Cs-137

-0.8 +/- 1.5

< 2.0 0.9 +/- 1.6

< 3.0

-0.6 +/- 2.9

< 4.1 5.0 Ba-La-140

-2.9 +/- 1.4

< 2.8

-0.1 +/- 1.5

< 3.0 1.3 +/- 2.9

< 1.9 5.0 Other (Co-60) 0.7+/-1.4

< 2.8 0.0 +/- 1.6

< 2.6

-0.6 +/- 3.2

< 3.4 15.0 MDC MDC MDC Required Collection Date 10-11-23 11-08-23 12-13-23 LLD Lab Code EMI-3060 EMI-3449 EMI-3876 Sr-89

-0.4 +/- 0.7

< 0.8

-0.4 +/- 0.8

< 0.8 0.1 +/- 0.7

< 0.8 5.0 Sr-90 0.6 +/- 0.3

< 0.5 0.7 +/- 0.4

< 0.6 0.1 +/- 0.3

< 0.7 1.0 1-131 0.12 +/- 0.19

< 0.36

-0.25 +/- 0.13

< 0.25

-0.04 +/- 0.17

< 0.35 0.5 K-40 1310 +/- 76 1285 +/- 69 1313 +/- 42 Cs-134

-0.4 +/- 1.4

< 2.6

-1.9 +/- 1.3

< 2.3

-0.7 +/- 0.7

< 1.4 5.0 Cs-137 2.3 +/- 1.6

< 4.2 0.1 +/-1.4

< 1.8

-0.2 +/- 0.5

< 2.2 5.0 Ba-La-140

-1.4 +/- 1.2

< 1.5

-0.2 +/- 1.1

< 1.3 0.1 +/- 0.7

< 1.0 5.0 Other (Co-60) 1.4 +/- 1.7

< 4.3

-0.5 +/- 1.4

< 1.2 0.2 +/- 0.5

< 2.3 15.0 3-4

Table 3. Radioactivity in milk samples Collection: Monthly

,POINT BEACH NUCLEAR PLANT Sample Description and Concentration (pCi/L)

E-40 Barta MDC MDC Collection Date 01-11-23 02-08-23 Lab Code EMI-46 EMI-242 Sr-89

-0.1 +/- 0.6

< 0.6

-0.2 +/- 0.5

< 0.6 Sr-90 0.4 +/- 0.3

< 0.4 0.2 +/- 0.3

< 0.6 1-131

-0.07 +/- 0.10

< 0.18

-0.12 +/- 0.11

< 0.21 K-40 1471 +/- 91 1341 +/- 69 Cs-134

-1.6+/-1.3

< 2.1

-0.6 +/- 1.4

< 2.5 Cs-137 0.8 +/- 4.2

< 3.2 0.0 +/- 1.6

< 1.8 Ba-La-140 0.5+/-1.6

< 2.0

-3.5 +/- 1.7

< 1.6 Other (Co-60)

-0.4 +/- 1.9

< 2.4 1.2 +/- 1.6

< 3.2 MDC MDC Collection Date 04-12-23 05-10-23 Lab Code EMI-861 EMI-1181 Sr-89 0.1+/-0.5

< 0.6 0.2 +/- 0.5

< 0.5 Sr-90 0.3 +/- 0.3

< 0.5 0.6 +/- 0.3

< 0.4 1-131

-0.04 +/- 0.12

< 0.22 0.12 +/- 0.21

< 0.40 K-40 1412 +/- 79 1389 +/- 78 Cs-134 1.1 +/- 1.3

< 2.7

-0.7 +/- 1.1

< 2.0 Cs-137 0.8+/-1.7

< 3.5

-1.3 +/- 1.5

< 2.6 Ba-La-140 0.4 +/- 1.2

< 2.4 0.3+/-1.2

< 1.8 Other (Co-60) 0.3 +/- 1.8

< 2.8.

-0.3 +/- 1.5

< 2.9 3-5 03-08-23 EMI-507

-0.4 +/- 0.6 0.5 +/- 0.3

-0.10 +/- 0.22 1339 +/- 46 0.1 +/- 0.8 0.6 +/- 0.9

-1.1 +/- 0.9 0.2 +/- 1.1 06-14-23 EMI-1566 0.3 +/- 0.6 0.3 +/- 0.4

-0.12 +/- 0.14 1346 +/- 69 0.1 +/- 1.3

-0.8 +/- 1.5

-2.7 +/- 1.4

-1.9 +/- 1.7 MDC Required LLD

< 0.6 5.0

< 0.5 1.0

< 0.41 0.5

< 1.7 5.0

< 1.9 5.0

< 1.6 5.0

< 1.7 15.0 MDC Required LLD

< 0.6 5.0

< 0.7 1.0

< 0.28 0.5

< 2.5 5.0

< 2.3 5.0

< 2.8 5.0

< 2.9 15.0

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 07-12-23 08-09-23 09-13-23 LLD Lab Code EMI-1935 EMI-2381 EMI-2688 Sr-89 0.2 +/- 0.6

< 0.6 0.0 +/- 0.6

< 0.7 0.7+/-1.1

< 1.3 5.0 Sr-90 0.1 +/- 0.3

< 0.5 0.1 +/- 0.3

< 0.5

-0.2 +/- 0.4

< 0.9 1.0 1-131

-0.01 +/- 0.13

< 0.27

-0.02 +/- 0.13

< 0.23 0.19 +/- 0.20

< 0.38 0.5 K-40 1344 +/- 71 1358 +/- 86 1232 +/- 84 Cs-134

-0.1 +/- 1.3

< 2.5

-0.1 +/- 1.4

< 2.7

-0.9 +/- 1.3

< 2.4 5.0 Cs-137 0.6 +/- 1.6

< 3.2 1.7 +/- 1.9

< 4.3 1.1 +/- 1.5

< 3.3 5.0 Ba-La-140 0.8 +/- 4.9

< 4.2

-0.8 +/- 1.4

< 1.9

-1.2 +/- 1.4

< 1.6 5.0 Other (Co-60)

-0.5 +/- 1.8

< 3.6 2.1 +/- 1.7

< 5.2 0.1 +/- 1.6

< 2.9 15.0 MDC MDC MDC Required Collection Date 10-11-23 11-08-23 12-13-23 LLD Lab Code EMI-3061 EMI-3450 EMI-3877 Sr-89 0.3 +/- 0.7

< 0.7 0.2 +/- 0.8

< 0.9

-0.1 +/- 0.6

< 0.6 5.0 Sr-90 0.3 +/- 0.3

< 0.6 0.2 +/- 0.4

< 0.8 0.5 +/- 0.3

< 0.6 1.0 1-131 0.13 +/- 0.22

< 0.41

-0.15 +/- 0.13

< 0.26

-0.03 +/- 0.17

< 0.35 0.5 K-40 1350 +/- 115 1354 +/- 79 1351 +/- 36 Cs-134

-2.3 +/- 2.5

< 4.6 0.1 +/- 1.1

< 2.0

-0.3 +/- 0.6

< 1.1 5.0 Cs-137 0.4 +/- 2.9

< 2.8 0.3 +/- 1.4

< 2.3 0.6 +/- 0.7

< 1.3 5.0 Ba-La-140

-0.8 +/- 2.5

< 2.1

-0.3 +/- 1.0

< 1.9

-0.6 +/- 0.6

< 1.0 5.0 Other (Co-60)

-1.8 +/- 2.8

< 2.8 0.4+/-1.7

< 3.1 0.2 +/- 0.7

< 1.1 15.0 Sr-89 Annual Mean + s.d.

0.1 +/- 0.3 Sr-90 Annual Mean + s.d.

0.4 +/- 0.2 1-131 Annual Mean+ s.d.

-0.01 +/- 0.09 K-40 Annual Mean + s.d.

1334 +/- 67 Cs-134 Annual Mean+ s.d.

-0.6 +/- 0.9 Cs-137 Annual Mean+ s.d.

0.4 +/- 1.3 Ba-La Annual Mean + s.d.

-0.7 +/- 1.2 Co-60 Annual Mean + s.d.

0.3 +/- 1.1 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 01-18-23 04-12-23 07-19-23 10-10-23 Lab Code EWW-114 EWW-880 EWW-2085 EWW-3071 Gross Beta 1.4 +/- 1.2 0.7 +/- 1.0 1.8 +/- 1.1 1.2 +/- 0.7 4.0 H-3 120 +/- 86 8

137 +/- 83 131 +/- 84

-68 +/- 74 500 Sr-89 0.3 +/- 0.4

-0.1 +/- 0.4

-0.4 +/- 0.4 0.3 +/- 0.4 5.0 Sr-90

-0.1 +/- 0.2 0.0 +/- 0.2 0.0 +/- 0.2

-0.5 +/- 0.2 1.0 1-131 0.04 +/- 0.18

-0.02 +/- 0.18

-0.06 +/- 0.15 0.10 +/- 0.20 0.5 Mn-54

-2.8 +/- 3.2 0.9 +/- 1.7

-3.7 +/- 2.1

-0.5 +/- 4.8 10 Fe-59

-6.3 +/- 6.4 0.5 +/- 3.7

-2.6 +/- 5.2 7.8 +/- 10.3 30 Co-58

-2.1 +/- 3.6

-0.7 +/- 1.5 0.7 +/- 2.2

-2.8 +/- 4.5 10 Co-60 0.9 +/- 3.1 1.5 +/- 1.9 1.4 +/- 3.0

-1.4+/-6.4 10 Zn-65

-18.5 +/- 10.3

-2.2 +/- 4.6 2.7 +/- 5.0

-26.2 +/- 18.2 30 Zr-Nb-95

-1.6 +/- 4.2

-3.3 +/- 1.9

-3.5 +/- 2.9 1.7+/-6.1 15 Cs-134

-5.9 +/- 3.5

-0.5 +/- 1.6

-1.2+/-2.3

-22.0 +/- 7.5 10 Cs-137 0.6 +/- 3.7

-1.9 +/- 2.0 3.1 +/- 2.6

-1.1 +/- 5.9 10 Ba-La-140 1.9 +/- 3.2 0.4 +/- 2.3 0.5 +/- 2.5

-7.1 +/- 16.0 15 Other (Ru-103) 0.5 +/- 2.9

-0.3 +/- 1.8

-0.4 +/- 2.3

-2.5 +/- 4.5 30 8Tritium recount = 86 +/- 81 pCi/L. MDA < 164 pCi/L.

MDC Data Collection Date 01-18-23 04-12-23 07-19-23 10-10-23 Lab Code EWW-114 EWW-880 EWW-2085 EWW-3071 Gross Beta

< 2.1

< 1.8

< 2.0

< 1.1 4.0 H-3

< 160

< 161

< 162

< 170 500 Sr-89

< 0.5

< 0.6 5.0 Sr-90

< 0.5

< 0.4

< 0.6 1.0 1-131

< 0.36

< 0.37

< 0.28

< 0.36 0.5 Mn-54

< 4.9

< 2.3

< 1.8

< 7.2 10 Fe-59

< 4.7

< 5.3

< 5.5

< 11.9 30 Co-58

< 4.8

< 2.4

< 2.2

< 5.7 10 Co-60

< 4.1

< 3.2

< 8.3

< 9.4 10 Zn-65

< 12.5

< 5.6

< 7.9

< 16.7 30 Zr-Nb-95

< 6.8

< 2.6

< 4.2

< 8.9 15 Cs-134

< 6.2

< 3.2

< 4.6

< 9.4 10 Cs-137

< 6.6

< 2.6

< 6.6

< 7.1 10 Ba-La-140

< 2.9

< 3.3

< 3.8

< 4.4 15 Other (Ru-103)

< 5.0

< 3.1

< 3.9 30 4-1

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

Location: E-01 (Meteorological Tower)

Collection: Monthly composites Units: pCi/L MDC MDC MDC MDC Lab Code ELW-38 ELW-269 ELW-517 ELW-862 Date Collected 01-10-23 02-08-23 03-08-23 04-12-23 Req.LLD Gross beta 1.7 +/- 0.6

< 1.0 2.0 +/- 0.6

< 0.8 1.9 +/- 0.6

< 0.9 1.4 +/- 0.6

< 0.9 4.0 1-131

-0.03 +/-0.11

< 0.20

-0.09 +/- 0.21

< 0.47 0.00 +/- 0.16

< 0.28

-0.05 +/- 0.11

< 0.20 0.5 Be-7

-2.4 +/- 10.4

< 18.3 4.8 +/- 12.0

< 15.6

-5.2 +/- 7.6

< 12.3

-0.7 +/- 10.4

< 18.1 Mn-54 1.8 +/- 1.6

< 2.3 0.9 +/- 1.5

< 3.1

-0.3 +/- 1.1

< 1.8

-1.0 +/- 1.7

< 2.1 10 Fe-59

-0.8 +/- 2.6

< 4.0

-0.3 +/- 2.8

< 4.4

-1.6 +/- 2.2

< 2.8

-2.0 +/- 3.2

< 5.7 30 Co-58

-1.7 +/- 1.8

< 2.1 0.9 +/- 1.5

< 2.4

-0.5 +/- 1.0

< 1.5 0.7 +/- 1.8

< 3.2 10 Co-60 1.3 +/- 1.6

< 1.7 0.7+/-1.2

< 2.1 0.5 +/- 1.4

< 2.3

-1.4 +/- 1.8

< 1.6 10 Zn-65

-1.6 +/- 3.0

< 4.1 0.7 +/- 3.3

< 4.1 0.5 +/- 2.2

< 4.0 1.3 +/- 3.3

< 4.5 30 Zr-Nb-95

-0.7 +/- 1.8

< 2.6

-0.6 +/- 1.5

< 2.9

-1.2 +/- 1.2

< 1.8

-0.3 +/- 1.8

< 2.8 15 Cs-134

-0.5 +/- 1.6

< 2.5 0.1 +/- 1.3

< 2.8

-0.3 +/- 1.1

< 2.0 1.5 +/- 1.3

< 1.8 10 Cs-137 0.8 +/- 1.9

< 2.9 0.4 +/- 1.7

< 2.9 1.1 +/- 1.2

< 2.1 1.6 +/- 1.7

< 2.8 10 Ba-La-140 0.9 +/- 2.1

< 2.1

-1.9 +/- 1.8

< 4.0

-0.8 +/- 1.4

< 1.9 1.5 +/- 1.7

< 2.0 15 Other (Ru-103)

-0.9 +/- 1.1

< 2.0

-2.1 +/- 1.5

< 1.9

-0.3 +/- 0.9

< 1.6 0.5 +/- 1.3

< 1.8 30 Lab Code ELW-1169 ELW-1562 ELW-1936 ELW-2339 Date Collected 05-09-23 06-13-23 07-12-23 08-08-23 Req.LLD Gross beta 1.0 +/- 0.5

< 0.9 1.3 +/- 0.6

< 0.9 1.1 +/- 0.5

< 0.9 0.6 +/- 0.5

< 0.8 4.0 1-131 0.00 +/- 0.11

< 0.20

-0.08 +/- 0.13

< 0.24

-0.03 +/- 0.12

< 0.22 0.06 +/-0.12

< 0.21 0.5 Be-7

-6.4 +/- 9.9

< 19.8 4.9 +/- 10.4

< 14.2 8.4 +/- 18.6

< 25.0

-3.8 +/- 23.2

< 35.5 Mn-54 0.6 +/- 1.6

< 2.6 0.9 +/- 1.3

< 1.5 2.5 +/- 2.0

< 2.7 2.5 +/- 2.9

< 4.0 10 Fe-59 1.4 +/- 2.8

< 7.5

-1.9 +/- 2.4

< 5.0

-0.7 +/- 4.4

< 7.9

-9.9 +/- 6.5

< 5.0 30 Co-58

-1.0 +/- 1.4

< 2.7 0.2 +/- 1.0

< 1.4

-0.4 +/- 2.1

< 2.9

-0.6 +/- 2.6

< 3.0 10 Co-60

-0.4 +/- 1.6

< 2.2 0.6 +/- 1.2

< 1.5

-1.9 +/-2.6

< 2.8

-0.2 +/- 3.3

< 8.6 10 Zn-65

-1.5 +/- 3.5

< 4.9 0.4 +/- 2.8

< 3.4

-0.2 +/- 4.2

< 4.5

-4.2 +/- 7.2

< 7.2 30 Zr-Nb-95

-2.3 +/- 1.5

< 2.4

-1.4 +/- 1.2

< 1.9

-3.4 +/- 2.3

< 3.2

-4.6 +/- 2.9

< 2.6 15 Cs-134

-0.1 +/- 1.3

< 2.7 0.8 +/- 1.3

< 2.4

-1.3 +/- 2.3

< 2.4 1.8 +/- 2.5

< 5.1 10 Cs-137 1.3 +/- 1.8

< 3.1

-0.4 +/- 1.3

< 1.5

-0.4 +/- 2.4

< 2.8 0.0 +/- 3.2

< 6.9 10 Ba-La-140

-1.7+/-1.4

< 3.1

-0.5 +/- 1.6

< 3.0 1.1 +/- 2.9

< 4.6 0.7 +/-2.1

< 4.3 15 Other (Ru-103) 0.3 +/- 1.1

< 2.9

-0.4 +/- 1.1

< 2.2 0.4 +/- 2.0

< 3.5

-1.2 +/- 2.8

< 3.4 30 Lab Code ELW-2677 ELW-3068 ELW-3444 ELW-3872 Date Collected 09-12-23 10-10-23 11-07-23 12-13-23 Req. LLD Gross beta 0.7 +/- 0.5

< 0.9 1.1 +/- 0.5

< 0.9 1.5 +/- 0.6

< 0.9 0.7 +/- 0.5

< 1.0 4.0 1-131 0.01 +/- 0.15

< 0.26 0.24 +/- 0.25

< 0.46

-0.26 +/- 0.14

< 0.28

-0.02 +/- 0.15

< 0.27 0.5 Be-7

-27.9 +/- 38.2

< 3.8

-35.5 +/- 25.3

< 22.3

-8.8 +/- 24.9

< 27.4 14.5 +/- 14.2

< 27.8 Mn-54 0.3 +/- 5.7

< 7.8

-2.4 +/- 3.3

< 4.4 2.2 +/- 3.5

< 6.6

-0.1 +/- 1.4

< 2.1 10 Fe-59

-3.7 +/- 1.3

< 11.3

-2.4 +/- 5.5

< 3.2 4.8 +/- 6.4

< 6.9

-1.4+/-3.1

< 2.3 30 Co-58

-1.1 +/- 5.0

< 5.2 1.0 +/- 2.3

< 2.2

-2.4 +/- 3.1

< 4.7 0.3 +/- 1.9

< 3.5 10 Co-60 2.6 +/- 5.0

< 4.9 1.1 +/- 2.9

< 7.7

-0.6 +/- 3.5

< 3.9 1.2 +/- 2.1

< 5.4 10 Zn-65

-20.0 +/- 12.5

< 6.5

-4.5 +/- 6.3

< 3.5

-9.5 +/- 8.5

< 8.3 1.1 +/- 3.7

< 6.7 30 Zr-Nb-95

-0.9 +/- 7.3

< 6.5 1.3 +/- 3.1

< 3.8

-0.8 +/- 3.1

< 3.5

-1.6 +/- 1.7

< 2.9 15 Cs-134

-8.4 +/- 4.5

< 8.1 2.1 +/- 3.2

< 4.6

-3.9 +/- 3.6

< 6.2

-0.2 +/- 1.5

< 2.7 10 Cs-137 0.5 +/- 5.5

< 6.1 1.9 +/- 3.1

< 7.9

-2.7 +/- 3.6

< 4.4 2.5 +/- 1.9

< 4.7 10 Ba-La-140

-5.0 +/- 6.5

< 7.1

-1.2 +/- 2.0

< 2.7 1.5 +/- 4.0

< 3.8

-0.6 +/- 1.4

< 1.8 15 Other (Ru-103)

-4.8 +/- 4.3

< 4.5

-0.7 +/- 2.7

< 2.8

-0.2 +/- 2.8

< 3.1

-0.9 +/- 1.6

< 1.8 30 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-39 ELW-228 ELW-518 ELW-863 Date Collected 01-10-23 02-07-23 03-08-23 04-12-23 Req.LLD Gross beta 1.2 +/- 0.5

< 0.9 1.1 +/- 0.6

< 0.9 1.4 +/- 0.6

< 0.9 1.1 +/- 0.5

< 0.9 4.0 1-131

-0.15 +/- 0.12

< 0.23

-0.05 +/- 0.12

< 0.21 0.16 +/- 0.21

< 0.37 0.01 +/- 0.10

< 0.18 0.5 Be-7

-6.3 +/- 4.1

< 15.2 16.8 +/- 7.4

< 15.9

-7.5 +/- 1.8

< 19.2

-3.4 +/- 12.6

< 25.0 Mn-54 0.2 +/- 0.6

< 1.1 0.7+/-1.2

< 2.0 0.4 +/- 2.3

< 3.7

-1.0 +/- 2.0

< 3.6 10 Fe-59

-1.4+/-1.1

< 3.7 1.0 +/- 2.2

< 4.5

-0.4 +/- 4.9

< 6.8

-2.5 +/- 3.1

< 4.5 30 Co-58 0.2 +/- 0.6

< 1.7

-0.7 +/- 1.1

< 1.5

-1.2 +/- 2.4

< 3.1 1.0 +/- 1.7

< 2.5 10 Co-60 0.0 +/- 0.7

< 1.2 0.7 +/- 1.5

< 2.7

-1.8 +/- 2.8

< 3.7

-0.4 +/- 1.9

< 2.4 10 Zn-65

-0.9 +/- 1.3

< 3.0

-0.3 +/- 2.3

< 2.8

-2.1 +/- 5.0

< 6.2 1.3 +/- 3.6

< 5.4 30 Zr-Nb-95

-1.8 +/- 0.6

< 3.5

-0.7 +/- 1.3

< 1.7

-0.9 +/- 4.0

< 3.9 0.1 +/- 1.7

< 3.9 15 Cs-134

-0.1 +/- 0.6

< 1.0 0.2 +/- 1.1

< 2.0

-3.3 +/- 2.3

< 4.2

-0.9 +/- 1.4

< 2.2 10 Cs-137 0.7 +/- 0.7

< 1.1 0.3 +/- 1.4

< 2.4 1.9 +/- 2.4

< 3.8

-0.3 +/- 2.0

< 2.7 10 Ba-La-140

-3.1 +/- 0.7

< 2.9

-2.5 +/- 3.2

< 1.7

-1.6 +/- 2.4

< 2.5

-0.4 +/- 2.1

< 2.0 15 Other (Ru-103)

-1.3 +/- 0.5

< 2.0

-0.3 +/- 0.9

< 1.6

-2.5 +/- 2.2

< 2.7

-0.9 +/- 1.3

< 2.0 30 Lab Code ELW-1170 ELW-1563 ELW-1937 ELW-2340 Date Collected 05-09-23 06-13-23 07-12-23 08-08-23 Req. LLD Gross beta 1.1 +/- 0.5

< 0.9 1.1 +/- 0.5

< 0.9 0.7 +/- 0.5

< 0.9 0.9 +/- 0.5

< 0.9 4.0 1-131 0.10 +/- 0.12

< 0.21

-0.02 +/- 0.15

< 0.28

-0.02 +/- 0.13

< 0.23

-0.09 +/- 0.12

< 0.22 0.5 Be-7 9.0 +/- 4.9

< 23.4

-4.5 +/- 9.7

< 12.5

-12.1 +/- 24.3

< 28.3 10.3 +/- 32.6

< 62.4 Mn-54

-0.1 +/- 0.5

< 0.9 0.9 +/- 1.5

< 1.9 4.3 +/- 3.1

< 5.5 0.2 +/- 4.3

< 6.2 10 Fe-59 2.0 +/- 1.3

< 4.1 1.6 +/- 2.1

< 4.6

-1.2 +/- 6.6

< 8.4

-3.0 +/- 11.4

< 10.0 30 Co-58

-1.4 +/- 0.5

< 1.2 0.8 +/- 1.2

< 1.8 3.1 +/- 3.2

< 5.7 3.0 +/- 3.8

< 7.2 10 Co-60

-0.7 +/- 1.3

< 2.0 1.4 +/- 1.3

< 1.9 0.6 +/- 3.0

< 4.4 2.9 +/- 4.5

< 5.3 10 Zn-65 1.6 +/- 1.1

< 2.6 1.9 +/- 2.7

< 3.8 1.6 +/- 5.0

< 4.0

-13.8 +/- 10.7

< 5.6 30 Zr-Nb-95

-2.3 +/- 0.6

< 4.5

-1.3 +/- 1.3

< 2.0

-2.8 +/- 3.5

< 3.5 1.0 +/- 4.8

< 6.9 15 Cs-134 0.1 +/- 0.5

< 1.1 0.7 +/- 1.3

< 2.4

-0.7 +/- 2.9

< 5.2 3.2 +/- 4.8

< 7.7 10 Cs-137

-1.7+/-1.4

< 1.7

-0.7 +/- 1.4

< 1.4 1.2 +/- 3.6

< 6.1 0.8 +/- 5.2

< 7.6 10 Ba-La-140

-17.8 +/- 0.6 a< 25.5

-1.5 +/- 1.8

< 2.6 2.0 +/- 3.6

< 4.4 3.5 +/- 5.1

< 6.0 15 Other (Ru-103)

-1.2 +/- 0.6

< 2.8

-2.3 +/- 1.2

< 2.2 2.7 +/- 2.8

< 4.0

-3.4 +/- 4.7

< 5.4 30 Lab Code ELW-2678 ELW-3069 ELW-3445 ELW-3873 Date Collected 09-12-23 10-10-23 11-07-23 12-13-23 Req.LLD Gross beta 0.7 +/- 0.5

< 0.8 1.4 +/- 0.6

< 0.8 4.0 1-131

-0.10 +/- 0.20

< 0.41 0.10 +/- 0.22

< 0.40

-0.04 +/- 0.15

< 0.28

-0.16 +/- 0.14

< 0.27 0.5 Be-7

-14.1 +/- 19.0

< 21.6 3.0 +/- 35.2

< 56.8 3.0 +/- 10.7

< 22.8 0.3 +/- 12.3

< 22.8 Mn-54 1.8 +/- 2.6

< 5.1 0.3 +/- 5.5

< 9.5 1.0 +/- 1.5

< 2.1

-1.2 +/- 1.6

< 2.1 10 Fe-59

-1.5 +/- 4.5

< 3.2 3.5 +/- 9.7

< 8.2 0.0 +/- 2.6

< 4.5

-0.7 +/- 2.8

< 3.9 30 Co-58 0.7 +/- 2.2

< 3.8 1.5+/-3.9

< 6.0

-1.1 +/- 1.5

< 1.6 0.2 +/- 1.5

< 1.6 10 Co-60

-0.8 +/- 3.3

< 8.5 1.3 +/- 6.0

< 5.1 0.5 +/- 1.9

< 2.5

-0.6 +/- 1.3

< 1.1 10 Zn-65

-1.8 +/- 6.1

< 7.7

-9.0 +/- 11.8

< 7.0

-0.6 +/- 2.9

< 4.1

-0.5 +/- 3.0

< 5.4 30 Zr-Nb-95 0.2 +/- 2.6

< 4.1

-3.2 +/- 5.7

< 7.2

-1.8 +/- 1.9

< 2.3

-0.6 +/- 1.7

< 2.3 15 Cs-134

-1.5 +/- 2.5

< 4.8

-0.2 +/- 4.4

< 7.4

-1.8 +/- 1.4

< 2.5 0.6 +/- 1.6

< 2.7 10 Cs-137 1.2 +/- 2.6

< 6.8 0.3 +/- 5.7

< 8.2

-0.1 +/- 1.9

< 3.2 1.3 +/- 1.6

< 2.3 10 Ba-La-140 4.0 +/- 7.9

< 4.6

-3.9 +/- 5.9

< 5.2 0.1 +/- 1.4

< 1.9 1.3 +/- 1.4

< 2.4 15 Other (Ru-103) 2.0 +/- 2.6

< 5.4 0.9 +/- 3.8

< 6.0

-0.8 +/- 1.4

< 2.6 0.3 +/- 1.2

< 2.0 30 a MDA not met due to a delayed analysis.

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-40 ELW-332 ELW-520 ELW-864 Date Collected 01-10-23 02-15-23 03-08-23 04-12-23 Req.LLD Gross beta 1.8 +/-0.6

< 1.0 0.8 +/- 1.0

< 1.8 1.4 +/- 0.6

< 1.1 2.7 +/- 0.7

< 0.9 4.0 a

1-131

-0.05 +/-0.12

< 0.23

-0.19 +/- 0.16

< 0.30 0.04 +/- 0.20

< 0.36 1.21 +/- 0.11

< 0.11 0.5 Be-7 2.5 +/- 9.3

< 21.8 1.8 +/- 6.3

< 10.9

-1.2 +/- 11.2

< 18.4

-3.9 +/- 21.3

< 24.7 Mn-54

-0.3 +/- 1.5

< 2.1

-0.2 +/- 0.7

< 1.5

-0.4 +/- 1.4

< 2.8

-0.8 +/- 3.0

< 4.6 10 Fe-59 1.6 +/- 2.9

< 5.8 0.3 +/- 1.4

< 2.3

-0.8 +/- 2.8

< 2.1

-7.1 +/- 5.8

< 6.0 30 Co-58

-0.3 +/- 1.4

< 2.3

-0.3 +/- 0.7

< 1.1 1.5 +/- 1.4

< 2.0 2.7 +/- 2.7

< 4.2 10 Co-60

-0.3 +/- 1.7

< 1.2 0.4 +/- 1.5

< 2.7 0.3 +/- 1.7

< 1.2 2.9 +/- 2.8

< 3.7 10 Zn-65

-1.5 +/- 2.9

< 4.0

-1.9 +/- 1.6

< 2.2

-0.5 +/- 3.2

< 4.9

-1.7 +/- 6.7

< 7.8 30 Zr-Nb-95

-1.4 +/- 1.6

< 3.0

-1.6+/-0.8

< 1.7

-1.1 +/- 1.5

< 2.3 2.0 +/- 2.8

< 5.3 15 Cs-134 0.6 +/- 1.5

< 2.5 0.2 +/- 0.7

< 1.4 0.6 +/- 1.4

< 2.7

-2.1 +/- 2.7

< 5.2 10 Cs-137

-0.4 +/- 1.7

< 2.7

-1.3 +/- 1.5

< 2.3

-0.3 +/- 1.5

< 2.8 0.5 +/- 2.8

< 5.1 10 Ba-La-140 0.4 +/- 1.3

< 2.0 0.4 +/- 0.8

< 1.6 0.3 +/- 1.5

< 2.6

-1.8 +/- 2.8

< 2.4 15 Other (Ru-103) 0.2 +/- 1.1

< 2.6 0.3 +/- 0.7

< 1.4

-0.5 +/- 1.3

< 1.9 0.4 +/- 2.5

< 4.7 30 Lab Code ELW-1171 ELW-1564 ELW-1938 ELW-2341 Date Collected 05-09-23 06-13-23 07-12-23 08-08-23 Req.LLD Gross beta 1.4 +/- 0.6

< 0.9 1.1 +/- 0.6

< 0.9 0.7 +/- 0.5

< 0.9 0.9 +/- 0.5

< 0.8 4.0 1-131 0.06 +/- 0.12

< 0.21

-0.09 +/- 0.13

< 0.24 0.00 +/- 0.16

< 0.28

-0.01 +/- 0.10

< 0.19 0.5 Be-7 3.0 +/- 6.7

< 33.6

-4.7 +/- 20.8

< 30.8

-4.8 +/- 18.6

< 23.5

-2.8 +/- 19.1

< 23.3 Mn-54 0.2 +/- 0.9

< 2.2 0.6 +/- 2.7

< 3.3

-0.2 +/- 2.1

< 2.8 0.3 +/- 2.3

< 3.7 10 Fe-59 0.0 +/- 1.8

< 7.8

-0.4 +/- 5.1

< 11.3

-5.9 +/- 4.3

< 7.5

-4.0 +/- 4.6

< 4.6 30 Co-58

-1.1 +/- 0.8

< 2.0

-0.6 +/- 2.6

< 3.5

-2.8 +/- 2.1

< 2.6 1.6 +/- 2.2

< 4.0 10 Co-60 0.3 +/- 0.9

< 1.9

-2.2 +/- 3.0

< 2.9 1.6 +/- 1.9

< 2.5 0.4 +/- 1.2

< 7.8 10 Zn-65

-0.8 +/- 2.0

< 3.7 4.3 +/- 5.3

< 6.8 0.1 +/- 4.6

< 5.0

-6.7 +/- 5.2

< 2.6 30 Zr-Nb-95

-4.4 +/- 0.9

< 5.8

-1.8+/-2.8

< 4.9 1.3 +/- 2.1

< 3.1

-0.4 +/- 2.5

< 2.9 15 Cs-134

-0.1 +/- 0.8

< 1.7

-1.7 +/- 2.6

< 5.0 0.6 +/- 2.2

< 4.1

-0.8 +/- 1.9

< 4.4 10 Cs-137

-0.1 +/- 0.9

< 1.6 0.3 +/- 2.7

< 3.7

-0.4 +/- 2.3

< 2.7

-2.2 +/- 1.4

< 6.9 10 Ba-La-140

-68.9 +/- 3.1 b < 68.6

-3.9 +/- 3.0

< 8.0

-1.4 +/- 3.1

< 5.7 0.3 +/- 2.3

< 2.9 15 Other (Ru-103) 0.4 +/- 0.8

< 2.7 0.9 +/- 2.3

< 5.0

-0.2 +/- 2.0

< 3.7

-0.2 +/- 2.3

< 2.6 30 Lab Code ELW-2679 ELW-3070 ELW-3446 ELW-3874 Date Collected 09-12-23 10-10-23 11-07-23 12-13-23 Req. LLD Gross beta 0.5 +/- 0.5

< 0.9 0.3 +/- 0.5

< 0.9 1.5 +/- 0.6

< 0.9 1.3+/-0.6

< 0.9 4.0 1-131 0.12 +/-0.22

< 0.42 0.09 +/- 0.19

< 0.34 0.03 +/- 0.15

< 0.27

-0.04 +/-0.14

< 0.26 0.5 Be-7 19.4 +/- 31.5

< 29.7 1.6 +/- 22.5

< 27.6 10.9 +/- 9.9

< 21.0 9.8 +/- 10.2

< 14.1 Mn-54

-2.4 +/- 4.8

< 6.1 1.3 +/- 2.1

< 2.7

-0.8 +/- 1.3

< 1.4

-0.4 +/- 1.3

< 1.5 10 Fe-59

-0.4 +/- 8.1

< 8.2

-1.4 +/- 4.7

< 3.5 0.9 +/- 2.9

< 3.3

-0.3 +/- 2.2

< 3.1 30 Co-58 1.3 +/- 4.5

< 6.6

-0.6 +/- 2.6

< 1.9

-2.0 +/- 1.3

< 0.8

-1.5+/-1.7

< 1.6 10 Co-60 3.1 +/- 5.3

< 6.9 2.0 +/- 3.2

< 7.9 0.4 +/- 1.9

< 3.0

-1.5+/-1.7

< 2.5 10 Zn-65

-11.7 +/- 11.6

< 5.7

-4.7 +/- 4.5

< 2.9

-0.5 +/- 2.9

< 2.0

-2.6 +/- 3.0

< 2.1 30 Zr-Nb-95

-0.8 +/- 4.4

< 8.3 0.2+/-2.1

< 3.2

-2.6 +/- 1.6

< 1.9

-0.9 +/- 1.4

< 2.2 15 Cs-134 0.9 +/- 4.1

< 7.1

-0.4 +/- 2.5

< 4.6

-0.6 +/- 1.5

< 2.6 0.8 +/- 1.4

< 2.5 10 Cs-137 1.5 +/- 4.3

< 5.8 2.2 +/- 2.9

< 7.4

-0.7 +/- 1.6

< 2.2 0.2 +/- 1.7

< 2.7 10 Ba-La-140 0.8 +/- 4.7

< 5.6

-0.5 +/- 2.8

< 3.3

-1.0 +/- 1.8

< 2.8 0.5 +/- 1.6

< 3.0 15 Other (Ru-103)

-3.1 +/- 4.5

< 6.6

-0.7 +/- 2.7

< 4.1 0.7 +/- 1.1

< 2.5

-1.0 +/- 1.2

< 2.1 30 a Recount= 1.1 +/- 0.14 pCi/L, MDA < 0.17 pCi/L, Reanalysis 1.3 +/- 0.14 pCi/L, MDA < 0.15 pCi/L. For additional results see App. F b MDA not met due to a delayed analysis.

5-3

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

Gross Beta 1.2 +/- 0.5 1-131 0.02 +/- 0.22 Be-7

-0.7 +/- 9.5 Mn-54 0.3 +/- 1.2 Fe-59

-0.8 +/- 2.4 Co-58 Co-60 Zn-65 Zr-Nb-95 Mean +/- s.d.

0.0 +/- 1.3 0.3 +/- 1.2

-1.9 +/- 4.4

-0.9 +/- 1.4

.POINT BEACH Mean +/- s.d.

Cs-134

-0.3 +/- 1.7 Cs-137 0.2 +/- 1.0 Ba-La-140

-2.1 +/- 10.4 Ru-103

-0.4 +/- 1.3 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 Period 1st Qtr.

Lab Code ELW-557 H-3 181 +/- 89 Sr-89 0.07 +/- 0.45 Sr-90 0.21 +/- 0.27 Location Period 1st Qtr.

Lab Code ELW-558 H-3 187 +/- 89 Sr-89 0.39 +/-0.38 Sr-90

-0.13 +/- 0.22 Location Period 1st Qtr.

Lab Code ELW-559 H-3 121 +/- 86 Sr-89 0.21 +/- 0.46 Sr-90 0.05 +/-0.27 Tritium Annual Mean +/- s.d.

Sr-89 Annual Mean +/- s.d.

Sr-90 Annual Mean +/- s.d.

MDC

< 164

< 0.52

< 0.54

< 164

< 0.50

< 0.51

< 164

< 0.58

< 0.57 E-01 {Meteorological Tower}

2nd Qtr.

MDC 3rd Qtr.

ELW-1650 ELW-2783 141 +/- 82

< 157 5 +/- 77 0.04 +/- 0.74

< 0.95 0.28 +/- 0.79 0.12 +/-0.26

< 0.53 0.37 +/- 0.35 E-05 {Two Creeks Park}

2nd Qtr.

3rd Otr.

ELW-1651 ELW-2784 96 +/-80

< 157 35 +/- 79

-0.14 +/- 0.78

< 1.00

-0.41 +/- 0.76 0.18 +/- 0.27

< 0.55 0.38 +/- 0.37 E-06 {Coast Guard Station}

2nd Qtr.

ELW-1653 82 +/-79

-0.06 +/- 0.68 0.21 +/- 0.24 67 +/-83 0.05 +/- 0.28 0.15 +/- 0.17 3rd Qtr.

ELW-2785

< 157 19 +/- 78

< 0.82 0.21 +/- 0.73

< 0.46 0.23 +/- 0.35 6-1 MDC 4th Qtr.

MDC ELW-3925

< 163

-84 +/- 75

< 171

< 0.99

-0.09 +/-0.56

< 0.71

< 0.68 0.12 +/- 0.27

< 0.56 4th Qtr.

ELW-3926

< 163

-28 +/- 79

< 171

< 0.97

-0.38 +/-0.59

< 0.76

< 0.72 0.22 +/-0.29

< 0.57 4th Qtr.

ELW-3927

< 163 45 +/-83

< 171

< 0.87 0.47 +/- 0.54

< 0.85

< 0.71

-0.15 +/- 0.21

< 0.50

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

Location: E-13 Collection: Quarterly Units: pCi/g wet Collection Date Lab Code Type K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Other (Ru-103)

Collection Date Lab Code Type K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Other (Ru-103) 02-03-23 EF-399 Trout 2.31 +/- 0.36

-0.003 +/- 0.010 0.003 +/- 0.018

-0.013 +/- 0.010

-0.004 +/- 0.012

-0.015 +/- 0.024

-0.003 +/- 0.010 0.009 +/- 0.011

-0.036 +/- 0.008 04-25-23 EF-1507 Trout 2.84 +/- 0.29 0.001 +/- 0.008 0.002 +/- 0.010 0.005 +/- 0.010

-0.007 +/- 0.011

-0.006 +/- 0.015

-0.003 +/- 0.008 0.017 +/- 0.011 0.012 +/- 0.006 Sample Description and Concentration MDC MDC

< 0.017

< 0.070

< 0.023

< 0.017

< 0.020

< 0.017

< 0.019

< 0.030

< 0.010

< 0.066

< 0.018

< 0.010

< 0.019

< 0.011

< 0.021

< 0.032 02-18-23 EF-400 Burbot 2.33 +/- 0.30

-0.004 +/- 0.009

-0.015 +/- 0.016

-0.005 +/- 0.007

-0.005 +/- 0.008 0.008 +/- 0.018 0.003 +/- 0.008 0.030 +/- 0.017

-0.007 +/- 0.008 05-03-23 EF-1508 Burbot 2.72 +/- 0.36

-0.003 +/- 0.011 0.004 +/- 0.018

-0.020 +/- 0.010

-0.004 +/- 0.012 0.010 +/- 0.023

-0.021 +/- 0.011 0.011 +/- 0.012

-0.016 +/- 0.009 7-1

< 0.017

< 0.057

< 0.012

< 0.009

< 0.029

< 0.017

< 0.032

< 0.015

< 0.075

< 0.017

< 0.013

< 0.036

< 0.021

< 0.015

< 0.036 02-23-23 EF-401 Burbot 1.64 +/- 0.24 0.007 +/- 0.007 0.012 +/- 0.011 0.000 +/- 0.006 0.002 +/- 0.006 0.012 +/- 0.012

-0.005 +/- 0.006 0.013 +/- 0.008

-0.009 +/- 0.005 05-24-23 EF-1509 Burbot 2.62 +/- 0.33 0.003 +/- 0.007 0.018 +/- 0.018

-0.005 +/- 0.007 0.002 +/- 0.006

-0.002 +/- O.Q18 0.005 +/- 0.008 0.027 +/- 0.013 0.000 +/- 0.007 Req.

MDC LLD

< 0.016 0.13

< 0.046 0.26

< 0.017 0.13

< 0.013 0.13

< 0.023 0.26

< 0.011 0.13

< 0.014 0.15

< 0.017 0.5

< 0.010 0.13

< 0.047 0.26

< 0.012 0.13

< 0.009 0.13

< 0.024 0.26

< 0.010 0.13

< 0.042 0.15

< 0.019 0.5

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

Location: E-13 Collection: Quarterly Units: pCi/g wet Collection Date Lab Code Type K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Other ( Ru-1 03)

Collection Date Lab Code Type K-40 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Cs-134 Cs-137 Other ( Ru-103)

Sample Description and Concentration (pCi/g wet) 09-11-23 EF-2723 Rainbow Trout 3.20 +/- 0.41 0.000 +/- 0.009 0.005 +/- 0.017 0.003 +/- 0.009 0.009 +/- 0.010

-0.033 +/- 0.025

-0.010 +/- 0.010 0.023 +/- 0.012 0.001 +/- 0.010 08-17-23 EF-2727 Burbot 1.80 +/- 0.29

-0.006 +/- 0.007 0.003 +/- 0.017

-0.011 +/- 0.008 0.005 +/- 0.010

-0.020 +/- 0.021

-0.015 +/- 0.008 0.012 +/- 0.011 0.008 +/- 0.007 MDC MDC

< 0.016

< 0.046

< 0.024

< 0.032

< 0.034

< 0.018

< 0.028

< 0.029

< 0.013

< 0.034

< 0.012

< 0.030

< 0.029

< 0.016

< 0.026

< 0.038 07-03-23 EF-2725 Salmon 2.70 +/- 0.53 0.011 +/- 0.014

-0.046 +/- 0.029

-0.012 +/- 0.012

-0.008 +/- 0.014

-0.016 +/- 0.036

-0.025 +/- 0.015 0.013 +/- 0.018 0.058 +/- 0.012 10-14-23 EF-3736 Burbot 1.93 +/- 0.41

-0.013 +/- 0.016

-0.025 +/- 0.023

-0.003 +/- 0.011

-0.001 +/- 0.014 0.004 +/- 0.034

-0.003 +/- 0.012 0.010 +/- 0.015

-0.012 +/- 0.010 7-2

< 0.024

< 0.181

< 0.041

< 0.008

< 0.028

< 0.029

< 0.109

< 0.014

< 0.046

< 0.025

< 0.018

< 0.028

< 0.022

< 0.024

< 0.047 08-13-23 EF-2726 Lake Trout 2.49 +/- 0.20 0.000 +/- 0.004

-0.017 +/- 0.008 0.000 +/- 0.004

-0.001 +/- 0.005

-0.021 +/- 0.012

-0.009 +/- 0.004 0.012 +/- 0.005

-0.001 +/- 0.004 10-31-23 EF-3737 Burbot 2.88 +/- 0.49

-0.011 +/- 0.014

-0.009 +/- 0.027

-0.001 +/- 0.012

-0.004 +/- 0.016

-0.053 +/- 0.036

-0.015 +/- 0.014 0.016 +/- 0.016 0.018 +/- 0.011 Req.

MDC LLD

< 0.009 0.13

< 0.027 0.26

< 0.011 0.13

< 0.008 0.13

< 0.019 0.26

< 0.008 0.13

< 0.010 0.15

< 0.028 0.5

< 0.017 0.13

< 0.061 0.26

< 0.024 0.13

< 0.011 0.13

< 0.032 0.26

< 0.023 0.13

< 0.025 0.15

< 0.041 0.5

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

MDC Collection Date 10/17/2023 Lab Code ESS-3320 Location E-01 Be-7 0.032 +/- 0.054

< 0.149 K-40 5.386 +/- 0.406 Cs-134

-0.001 +/- 0.007

< 0.009 Cs-137 0.020 +/- 0.009

< 0.017 Tl-208 0.077 +/- 0.018 Pb-212 0.189 +/- 0.021 Bi-214 0.190 +/- 0.033 Ra-226 0.366 +/- 0.192 Ac-228 0.234 +/- 0.077 MDC 10/17/2023 ESS-3321 E-05 0.025 +/- 0.026

< 0.088 6.210 +/- 0.223 0.000 +/- 0.003

< 0.007 0.007 +/- 0.004

< 0.008 0.041 +/- 0.010 0.108 +/- 0.009 0.076 +/- 0.016 0.326 +/- 0.093 0.117 +/- 0.025 8-1 MDC 10/17/2023 ESS-3232 E-06 0.101 +/- 0.038 7.042 +/- 0.295

-0.003 +/- 0.005 0.020 +/- 0.009 0.093 +/- 0.012 0.262 +/- 0.014 0.318 +/- 0.027 0.394 +/- 0.150 0.343 +/- 0.046

< 0.082

< 0.007

< 0.010 Be-7 K-40 Cs-134 Cs-137 Tl-208 Pb-212 Bi-214 Ra-226 Ac-228 LLD 0.15 0.15 Annual Mean +/-s.d.

0.052 +/- 0.042 6.21 +/- 0.83 0.00 +/- 0.00 0.016 +/- 0.007 0.07 +/- 0.03 0.19 +/- 0.08 0.19 +/- 0.12 0.36 +/- 0.03 0.23 +/- 0.11

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

MDC MDC MDC Collection Date 9/28/2023 9/28/2023 9/28/2023 Req.

Lab Code ESQ-2921 ESQ-2922 ESQ-2923 LLD Location E-01 E-02 E-03 Be-7 0.457 +/- 0.26

< 0.30 0.099 +/- 0.11

< 0.18 0.121 +/- 0.04

< 0.09 K-40 20.60 +/- 0.84 17.48 +/- 0.81 17.88 +/- 0.32 Cs-134

-0.013 +/- 0.01

< 0.02

-0.006 +/- 0.01

< 0.02

-0.003 +/- 0.01

< 0.01 0.15 Cs-137 0.134 +/- 0.02

< 0.03 0.422 +/- 0.04

< 0.03 0.148 +/- 0.01

< 0.01 0.15 Tl-208 0.268 +/- 0.03 0.214 +/- 0.03 0.171 +/- 0.02 Pb-212 0.756 +/- 0.05 0.675 +/- 0.14 0.470 +/- 0.02 Bi-214 0.534 +/- 0.05 0.441 +/- 0.07 0.477 +/- 0.02 Ra-226 1.658 +/- 0.35 1.224 +/- 0.38 1.196 +/- 0.12 Ac-228 0.785 +/- 0.14 0.766 +/- 0.12 0.534 +/- 0.05 Collection Date 9/28/2023 9/28/2023 9/28/2023 Lab Code ESQ-2924 ESQ-2926 ESQ-2927 Location E-04 E-06 E-20 Be-7 0.034 +/- 0.08

< 0.16

-0.016 +/- 0.06

< 0.17

-0.003 +/- 0.11

< 0.28 K-40 15.54 +/- 0.71 11.79 +/- 0.57 16.16 +/- 0.77 Cs-134

-0.008 +/- 0.01

< 0.02

-0.001 +/- 0.01

< 0.02

-0.011 +/- 0.01

< 0.02 0.15 Cs-137 0.077 +/- 0.03

< 0.03 0.252 +/- 0.03

< 0.02 0.155 +/- 0.03

< 0.03 0.15 Tl-208 0.142 +/- 0.03 0.086 +/- 0.02 0.136 +/- 0.03 Pb-212 0.361 +/- 0.03 0.170+/-0.02 0.388 +/- 0.04 Bi-214 0.341 +/- 0.04 0.229 +/- 0.03 0.411 +/-0.05 Ra-226 1.307 +/- 0.26 0.389 +/- 0.22 1.176 +/- 0.33 Ac-228 0.443 +/- 0.08 0.247 +/- 0.06 0.437 +/- 0.08 Annual Mean +/- s.d.

Be-7 0.115 +/- 0.18 K-40 16.57 +/- 2.93 Cs-134

-0.007 +/- 0.00 0.15 Cs-137 0.20 +/- 0.12 0.15 Tl-208 0.17 +/- 0.06 Pb-212 0.47 +/- 0.22 Bi-214 0.41 +/- 0.11 Ra-226 1.16 +/- 0.42 Ac-228 0.54 +/- 0.21 9-1

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

Location Collection Date Lab Code Be-7 K-40 1-131 Cs-134 Cs-137 Other ( Co-60)

Location Collection Date Lab Code Be-7 K-40 1-131 Cs-134 Cs-137 Other (Co-60)

E-01 05-24-23 EG-1323 0.35 +/- 0.15 5.69 +/- 0.49 0.001 +/- 0.007

-0.003 +/- 0.009 0.001 +/- 0.010

-0.003 +/- 0.011 E-04 05-24-23 EG-1326 0.08 +/- 0.06 6.64 +/- 0.42 0.000 +/- 0.005

-0.002 +/- 0.006

-0.002 +/- 0.008

-0.001 +/- 0.009 MDC

< 0.016

< 0.017

< 0.013

< 0.014

< 0.018

< 0.017

< 0.017 E-02 05-24-23 EG-1324 0.17 +/- 0.10 6.24 +/- 0.38 0.000 +/- 0.004 0.001 +/- 0.006 0.002 +/- 0.006 0.000 +/- 0.006 E-06 05-24-23 EG-1327 0.12 +/- 0.06 4.18 +/- 0.27 0.002 +/- 0.003 0.001 +/- 0.004 0.024 +/- 0.010

-0.001 +/- 0.006 10-1 MDC

< 0.009

< 0.010

< 0.009

< 0.011

< 0.008

< 0.009

< 0.009 E-03 05-24-23 EG-1325 0.20 +/- 0.09 5.91 +/- 0.38

-0.005 +/- 0.004 0.000 +/- 0.006

-0.002 +/- 0.007 0.006 +/- 0.008 E-20 05-24-23 EG-1328 0.08 +/- 0.06 6.65 +/- 0.42 0.000 +/- 0.005

-0.002 +/- 0.006

-0.002 +/- 0.008

-0.001 +/- 0.009 MDC Req.LLD

< 0.007 0.060

< 0.012 0.060

< 0.011 0.080

< 0.012 0.060 Req.LLD

< 0.010 0.060

< 0.013 0.060

< 0.011 0.080

< 0.014 0.060

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

Location Collection Date Lab Code Be-7 K-40 1-131 Cs-134 Cs-137 Other (Co-60)

E-01 09-28-23 EG-2915 0.65 +/- 0.22 4.04 +/- 0.59

-0.009 +/- 0.014

-0.003 +/- 0.012 0.005 +/- 0.015

-0.009 +/- 0.016 E-04 09-28-23 EG-2918 1.69 +/- 0.32 5.97 +/- 0.61 0.018 +/- 0.011

-0.005 +/- 0.012 0.010 +/- 0.013 0.001 +/- 0.015 MDC

< 0.034

< 0.024

< 0.037

< 0.035

< 0.056

< 0.024

< 0.032

< 0.036 Be-7 Annual Mean +/- s.d.

K-40 Annual Mean +/- s.d.

1-131 Annual Mean+/- s.d.

Cs-134 Annual Mean +/- s.d.

Cs-137 Annual Mean +/- s.d.

Co-60 Annual Mean +/- s.d.

0.80 +/- 0.76 5.26 +/- 1.29

-0.002 +/- 0.009

-0.004 +/- 0.010 0.011 +/- 0.018 0.002 +/- 0.005 E-02 09-28-23 EG-2916 1.07 +/- 0.39 5.30 +/- 0.79

-0.011 +/- 0.014

-0.035 +/- 0.020 0.002 +/- 0.025 0.003 +/- 0.027 E-06 09-28-23 EG-2919 1.89 +/- 0.09 2.66 +/- 0.12 0.003 +/- 0.005 0.001 +/- 0.003 0.063 +/- 0.007 0.006 +/- 0.003 10-2 MDC

< 0.031

< 0.036

< 0.032

< 0.030

< 0.010

< 0.005

< 0.009

< 0.009 E-03 09-28-23 EG-2917 2.13 +/- 0.33 6.07 +/- 0.64

-0.015 +/- 0.012 0.003 +/- 0.015 0.011 +/- 0.015 0.008 +/- 0.014 E-20 09-28-23 EG-2920 1.15+/-0.22 3.72 +/- 0.44

-0.008 +/- 0.008

-0.007 +/- 0.008 0.015 +/- 0.010 0.009 +/- 0.009 MDC Req. LLD

< 0.029 0.060

< 0.020 0.060

< 0.032 0.080

< 0.037 0.060 Req.LLD

< 0.024 0.060

< 0.015 0.060

< 0.022 0.080

< 0.023 0.060

POINT BEACH NUCLEAR PLANT Table 11.

Ambient Gamma Radiation a LLD/7days: < 1 mR/TLD 1st. Quarter, 2023 Date Annealed:

12-06-22 Days in the field 88 Date Placed:

01-04-23 b

Days from Annealing Date Removed:

04-02-23 to Readout:

120 Date Read:

04-05-23 Days in mR/Stnd Qtr Location Field Total mR NetmR (91 days)

Net mR per 7 days Indicator E-1 88 15.6 +/- 1.0 9.9 +/- 1.0 10.2 +/- 1.0 0.78 +/- 0.08 E-2 88 20.9+/-1.2 15.2 +/- 1.2 15.7 +/- 1.2 1.21 +/- 0.09 E-3 88 20.4 +/- 1.3 14.7 +/- 1.3 15.2 +/- 1.3 1.17 +/- 0.10 E-4 88 16.4 +/- 0.9 10.7 +/- 0.9 11.0 +/- 0.9 0.85 +/- 0.07 E-5 88 17.4 +/- 0.3 11.6 +/- 0.3 12.0 +/- 0.3 0.92 +/- 0.02 E-6 88 18.0 +/- 0.7 12.3 +/- 0.7 12.7 +/-0.7 0.98 +/- 0.05 E-7 87 17.9 +/- 0.3 12.2 +/- 0.3 12.7 +/-0.4 0.98 +/- 0.03 E-8 88 15.5 +/- 0.7 9.8 +/- 0.7 10.1 +/- 0.7 0.78 +/- 0.06 E-9 87 17.1 +/- 0.2 11.4 +/- 0.3 11.9 +/- 0.3 0.92 +/- 0.02 E-12 88 13.5+/-0.4 7.7 +/- 0.5 8.0 +/- 0.5 0.62 +/- 0.04 E-14 87 19.2 +/- 0.7 13.5 +/-0.7 14.1 +/- 0.7 1.09 +/- 0.05 E-15 88 20.2 +/- 0.7 14.5 +/- 0.7 15.0 +/- 0.8 1.15 +/- 0.06 E-16B 87 18.8 +/- 0.7 13.0 +/- 0.7 13.6 +/- 0.7 1.05 +/- 0.06 E-17 87 16.9+/-0.4 11.2 +/- 0.5 11.7 +/- 0.5 0.90 +/- 0.04 E-18 87 18.5 +/-0.7 12.8 +/- 0.7 13.4 +/- 0.8 1.03 +/- 0.06 E-22 87 17.9 +/- 0.6 12.2 +/- 0.6 12.8 +/- 0.6 0.98 +/- 0.05 E-23 88 21.5 +/- 0.4 15.8 +/- 0.4 16.3 +/- 0.4 1.26 +/- 0.03 E-24 88 18.0 +/- 0.6 12.3 +/- 0.6 12.7 +/- 0.6 0.98 +/- 0.05 E-25 87 18.7+/-0.1 13.0 +/- 0.2 13.6 +/- 0.2 1.05 +/- 0.02 E-26B 87 16.9 +/- 0.4 11.2 +/- 0.4 11.7 +/-0.4 0.90 +/- 0.03 E-27 87 18.5 +/- 0.2 12.8 +/- 0.3 13.4 +/- 0.3 1.03 +/- 0.02 E-28 88 13.2 +/- 0.4 7.5 +/- 0.4 7.8 +/- 0.4 0.60 +/- 0.03 E-29 88 15.2 +/- 0.4 9.4 +/- 0.5 9.8 +/- 0.5 0.75 +/- 0.04 E-30 87 17.5 +/- 0.6 11.8 +/-0.7 12.3 +/- 0.7 0.95 +/- 0.05 E-31 88 19.0 +/- 0.4 13.3 +/- 0.4 13.7 +/-0.4 1.06 +/- 0.03 E-32 88 22.3 +/- 0.8 16.6 +/- 0.8 17.2 +/- 0.8 1.32 +/- 0.06 E-38 88 19.7 +/- 1.2 14.0 +/- 1.2 14.5 +/- 1.3 1.11 +/- 0.10 E-39 88 19.3 +/- 1.0 13.6 +/- 1.0 14.0 +/- 1.1 1.08 +/- 0.08 E-41 87 18.5 +/- 0.4 12.8 +/- 0.5 13.4 +/- 0.5 1.03 +/- 0.04 E-42 88 19.2 +/- 0.3 13.5 +/- 0.3 13.9 +/- 0.4 1.07 +/- 0.03 E-43 88 19.3 +/- 1.1 13.6 +/- 1.1 14.1 +/- 1.2 1.08 +/- 0.09 E-44 88 18.8 +/- 0.8 13.1 +/- 0.8 13.5 +/- 0.8 1.04 +/- 0.06 Control E-20 88 18.3 +/- 0.8 12.6 +/- 0.9 13.0 +/- 0.9 1.00 +/- 0.07 Mean+/-s.d.

18.1 +/- 2.0 12.4 +/- 2.0 12.9 +/- 2.1 0.99 +/- 0.16 In-Transit Exposure Date Annealed Date Read ITC-1 ITC-2 12-06-22 01-11-23 6.1 +/- 0.1 6.3 +/- 0.2 03-08-23 04-05-23 5.3 +/- 0.2 5.1 +/- 0.2 a 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.

b Some TLDs placed on 1/5, as indicated.

11-1

POINT BEACH NUCLEAR PLANT Table 11.

Ambient Gamma Radiation a LLD/7days: < 1 mR/TLD 2nd Quarter, 2023 Date Annealed:

03-08-23 Days in the field 94 Date Placed:

04-02-23 Days from Annealing Date Removed:

07-05-23 to Readout:

121 Date Read:

07-07-23 Days in mR/Stnd Qtr Location Field Total mR NetmR (91 days)

Net mR per 7 days Indicator E-1 94 18.2 +/- 0.2 13.0 +/- 0.5 12.6 +/- 0.5 0.97 +/- 0.04 E-2 94 24.7 +/- 1.4 19.6 +/- 1.5 19.0 +/- 1.4 1.46 +/- 0.11 E-3 94 22.8 +/- 1.9 17.6 +/- 1.9 17.1 +/- 1.9 1.31 +/-0.14 E-4 94 18.7 +/- 0.5 13.5 +/-0.7 13.1 +/-0.7 1.01 +/- 0.05 E-5 94 20.8 +/- 0.8 15.6 +/- 0.9 15.1 +/- 0.9 1.16 +/-0.07 E-6 94 18.1 +/- 0.6 12.9 +/- 0.7 12.5 +/- 0.7 0.96 +/- 0.06 E-7 94 18.0 +/- 0.2 12.8 +/- 0.5 12.4 +/- 0.5 0.95 +/- 0.04 E-8 94 18.0 +/- 0.8 12.9 +/- 1.0 12.5 +/- 0.9 0.96 +/- 0.07 E-9 94 19.7 +/- 0.3 14.5 +/- 0.6 14.1 +/- 0.6 1.08 +/- 0.04 E-12 94 15.4 +/- 0.9 10.2 +/- 1.0 9.9 +/- 1.0 0.76 +/- 0.08 E-14 94 19.8+/-1.9 14.6 +/- 1.9 14.1 +/- 1.9 1.09+/-0.14 E-15 94 20.0 +/- 0.8 14.8 +/- 1.0 14.4 +/- 0.9 1.10 +/-0.07 E-168 94 22.5 +/- 0.6 17.3 +/- 0.8 16.7 +/- 0.8 1.29 +/- 0.06 E-17 94 21.1 +/- 0.8 15.9 +/- 0.9 15.4 +/- 0.9 1.19 +/-0.07 E-18 94 22.6 +/- 1.6 17.5 +/- 1.7 16.9 +/- 1.6 1.30 +/- 0.12 E-22 94 21.8+/-0.5 16.6 +/- 0.7 16.1+/-0.7 1.24 +/- 0.05 E-23 94 24.1 +/- 0.6 19.0 +/- 0.8 18.3 +/- 0.8 1.41 +/- 0.06 E-24 94 21.1 +/-1.3 15.9 +/- 1.4 15.4 +/- 1.3 1.19+/-0.10 E-25 94 22.7 +/- 0.5 17.6 +/-0.7 17.0 +/-0.7 1.31 +/- 0.05 E-268 94 19.2 +/- 0.3 14.1 +/- 0.6 13.6 +/- 0.5 1.05 +/- 0.04 E-27 94 22.2 +/- 0.5 17.1 +/-0.7 16.5 +/- 0.7 1.27 +/- 0.05 E-28 94 13.7 +/- 0.2 8.5 +/- 0.6 8.2 +/- 0.5 0.63 +/- 0.04 E-29 94 16.1 +/- 0.8 10.9 +/- 0.9 10.6 +/- 0.9 0.81 +/- 0.07 E-30 94 19.2 +/- 0.6 14.1 +/- 0.7 13.6 +/- 0.7 1.05 +/- 0.06 E-31 94 22.9 +/- 1.4 17.7 +/- 1.5 17.1+/-1.4 1.32 +/- 0.11 E-32 94 23.1 +/- 0.5 17.9 +/- 0.7 17.3+/-0.7 1.33 +/- 0.05 E-38 94 21.1 +/- 0.6 15.9 +/- 0.8 15.4 +/-0.7 1.19 +/-0.06 E-39 94 21.8 +/- 0.6 16.7 +/- 0.8 16.1 +/-0.7 1.24 +/- 0.06 E-41 94 23.0 +/- 0.2 17.8 +/- 0.5 17.2 +/-0.5 1.33 +/- 0.04 E-42 94 22.7 +/- 0.6 17.6 +/-0.8 17.0 +/- 0.8 1.31 +/- 0.06 E-43 94 22.7 +/- 0.7 17.6 +/- 0.9 17.0 +/- 0.8 1.31 +/- 0.06 E-44 94 22.3 +/- 0.2 17.1 +/- 0.6 16.6 +/- 0.5 1.28 +/- 0.04 Control E-20 94 20.4 +/- 0.7 15.3 +/- 0.8 14.8 +/- 0.8 1.14 +/-0.06 Mean+/-s.d.

20.6 +/-2.6 15.5 +/- 2.6 15.0 +/- 2.5 1.15 +/-0.19 In-Transit Exposure Date Annealed Date Read

.ITC-1 ITC-2 03-08-23 04-05-23 5.3 +/- 0.2 5.1 +/- 0.2 06-12-23 07-07-23 5.0 +/- 0.3 5.2 +/- 0.3 a 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.

11-2

POINT BEACH NUCLEAR PLANT Table 11.

Ambient Gamma Radiation a LLD/7days: < 1mR/TLD 3rd Quarter, 2023 Date Annealed:

06-12-23 Days in the field 88 Date Placed:

07-05-23 Days from Annealing Date Removed:

10-01-23 to Readout:

115 Date Read:

10-05-23 Days in mR/Stnd Qtr Location Field Total mR NetmR (91 days)

Net mR per 7 days Indicator E-1 88 16.2 +/- 0.9 11.8 +/- 1.0 12.2 +/- 1.0 0.94 +/- 0.08 E-2 88 20.9 +/- 0.5 16.5 +/- 0.7 17.1 +/-0.7 1.31 +/- 0.05 E-3 88 21.7 +/- 1.0 17.3 +/- 1.1 17.9+/-1.2 1.38 +/- 0.09 E-4 88 17.4 +/- 0.7 13.0 +/- 0.8 13.4 +/-0.9 1.03 +/- 0.07 E-5 88 18.4 +/- 0.5 14.0 +/- 0.7 14.5 +/- 0.7 1.11 +/- 0.05 E-6 88 18.0 +/- 0.4 13.6 +/- 0.6 14.1 +/- 0.6 1.08 +/- 0.05 E-7 88 18.8 +/- 0.5 14.4 +/-0.7 14.9 +/-0.7 1.15 +/- 0.06 E-8 88 16.6 +/- 1.0 12.2 +/- 1.1 12.6+/-1.1 0.97 +/- 0.09 E-9 88 18.5 +/- 0.2 14.1 +/- 0.5 14.6 +/- 0.5 1.13 +/- 0.04 E-12 88 13.0+/-0.1 8.6 +/- 0.5 8.9 +/- 0.5 0.69 +/- 0.04 E-14 88 20.2 +/- 0.3 15.8+/-0.6 16.4 +/- 0.6 1.26 +/- 0.05 E-15 88 23.4 +/- 0.5 19.0 +/- 0.7 19.7 +/-0.7 1.51 +/- 0.05 E-16B 88 19.6 +/- 0.6 15.2 +/- 0.8 15.7 +/-0.8 1.21 +/- 0.06 E-17 88 17.6 +/- 0.5 13.2 +/- 0.7 13.7+/-0.7 1.05 +/- 0.05 E-18 88 20.8 +/- 0.7 16.4 +/- 0.8 17.0 +/- 0.9 1.31 +/- 0.07 E-22 88 19.7 +/- 0.6 15.3 +/- 0.8 15.8 +/- 0.8 1.22 +/- 0.06 E-23 88 23.4 +/- 0.5 19.0 +/- 0.7 19.6 +/- 0.7 1.51 +/- 0.05 E-24 88 18.7 +/- 0.6 14.3 +/- 0.7 14.8 +/- 0.8 1.14 +/-0.06 E-25 88 20.8 +/- 0.3 16.4 +/- 0.5 17.0 +/- 0.6 1.31 +/- 0.04 E-26B 88 18.6+/-0.4 14.2 +/- 0.6 14.7 +/-0.6 1.13 +/- 0.05 E-27 88 20.0 +/- 0.3 15.6 +/- 0.6 16.1 +/- 0.6 1.24 +/- 0.04 E-28 88 13.5 +/- 0.3 9.1 +/- 0.5 9.4 +/- 0.5 0.72 +/- 0.04 E-29 88 15.4+/-0.4 11.0 +/- 0.6 11.4 +/- 0.6 0.87 +/- 0.05 E-30 88 18.0 +/- 0.5 13.6 +/- 0.7 14.1 +/-0.7 1.08 +/- 0.05 E-31 88 21.1 +/- 0.6 16.7 +/- 0.8 17.3 +/- 0.8 1.33 +/- 0.06 E-32 88 25.0 +/- 0.2 20.6 +/- 0.5 21.3 +/- 0.5 1.64 +/- 0.04 E-38 88 21.6+/-1.4 17.2 +/- 1.5 17.8 +/- 1.6 1.37 +/-0.12 E-39 88 22.2 +/- 1.1 17.8 +/- 1.2 18.4+/-1.3 1.42 +/- 0.10 E-41 88 21.7 +/- 0.4 17.4 +/- 0.6 17.9 +/- 0.6 1.38 +/- 0.05 E-42 88 20.5 +/- 0.4 16.1 +/-0.6 16.6 +/- 0.6 1.28 +/- 0.05 E-43 88 23.0 +/- 0.8 18.7 +/- 0.9 19.3 +/- 1.0 1.48 +/- 0.08 E-44 88 20.8 +/- 0.7 16.4 +/- 0.8 16.9 +/- 0.9 1.30 +/- O.Q7 Control E-20 88 19.0 +/- 1.0 14.6 +/- 1.1 15.1 +/- 1.1 1.16 +/- 0.09 Mean+/-s.d.

19.5 +/- 2.7 15.1 +/-2.7 15.6 +/- 2.8 1.20 +/- 0.22 In-Transit Ex(;!osure Date Annealed Date Read ITC-1 ITC-2 06-12-23 07-07-23 5.0 +/- 0.3 5.2 +/- 0.3 09-12-23 10-05-23 3.8 +/- 0.1 3.6 +/- 0.2 a 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.

11-3

POINT BEACH NUCLEAR PLANT Table 11.

Ambient Gamma Radiation a LLD/7days: < 1mR/TLD 4th Quarter, 2023 Date Annealed:

09-12-23 Days in the field 95 Date Placed:

10-01-23 Days from Annealing Date Removed:

01-04-24 to Readout:

121 Date Read:

01-11-24 Days in mR/Stnd Qtr Location Field Total mR NetmR (91 days)

Net mR per 7 days Indicator E-1 95 19.1 +/- 0.2 15.0 +/- 0.4 14.4 +/- 0.4 1.11 +/- 0.03 E-2 95 25.7 +/- 1.1 21.6 +/- 1.1 20.7 +/- 1.1 1.59 +/- 0.08 E-3 95 23.0 +/- 1.5 19.0 +/- 1.5 18.2 +/- 1.5 1.40 +/- 0.11 E-4 95 18.9 +/- 0.5 14.8 +/- 0.6 14.2 +/- 0.6 1.09 +/- 0.05 E-5 95 22.0 +/- 0.7 17.9 +/- 0.8 17.2 +/- 0.7 1.32 +/- 0.06 E-6 95 18.0 +/- 0.4 13.9 +/- 0.5 13.3 +/- 0.5 1.02 +/- 0.04 E-7 95 18.6 +/- 0.5 14.6 +/- 0.7 13.9 +/- 0.6 1.07 +/- 0.05 E-8 95 19.1 +/- 0.7 15.1 +/-0.8 14.4 +/- 0.8 1.11 +/- 0.06 E-9 95 19.5 +/- 0.4 15.4 +/- 0.5 14.7 +/- 0.5 1.13 +/- 0.04 E-12 95 15.5 +/- 0.9 11.4 +/- 1.0 11.0 +/- 0.9 0.84 +/- O.D7 E-14 95 19.8 +/- 1.4 15.7+/-1.4 15.0+/-1.4 1.16 +/- 0.11 E-15 95 21.2 +/- 1.6 17.1 +/- 1.6 16.4 +/- 1.6 1.26 +/-0.12 E-168 95 22.5 +/- 0.6 18.4 +/- 0.7 17.7 +/- 0.7 1.36 +/- 0.05 E-17 95 19.4+/-0.7 15.3 +/- 0.8 14.7 +/- 0.8 1.13 +/- 0.06 E-18 95 22.3 +/- 0.8 18.2 +/- 0.9 17.4+/-0.8 1.34 +/- 0.06 E-22 95 21.9 +/- 0.8 17.9 +/- 0.8 17.1 +/- 0.8 1.32 +/- 0.06 E-23 95 24.6 +/- 0.3 20.6 +/- 0.5 19.7+/-0.5 1.52 +/- 0.04 E-24 95 19.9 +/- 1.0 15.8 +/- 1.1 15.2 +/- 1.0 1.17 +/- 0.08 E-25 95 21.5 +/- 0.6 17.4+/-0.7 16.7 +/-0.7 1.28 +/- 0.05 E-268 95 18.2 +/- 0.3 14.2 +/- 0.5 13.6 +/- 0.4 1.05 +/- 0.03 E-27 95 20.9 +/- 0.4 16.9 +/- 0.6 16.2 +/- 0.5 1.24 +/- 0.04 E-28 95 12.9 +/- 0.4 8.9 +/- 0.5 8.5 +/- 0.5 0.65 +/-0.04 E-29 95 14.8 +/- 0.3 10.7 +/- 0.5 10.2 +/- 0.5 0.79 +/- 0.03 E-30 95 18.7 +/- 0.6 14.6 +/-0.7 14.0 +/-0.7 1.08 +/- 0.05 E-31 95 22.5 +/- 1.2 18.5 +/- 1.2 17.7 +/- 1.2 1.36 +/- 0.09 E-32 95 21.8 +/- 0.6 17.7 +/- 0.7 17.0 +/- 0.7 1.31 +/- 0.05 E-38 95 20.1 +/- 0.5 16.1 +/-0.6 15.4 +/- 0.6 1.19 +/- 0.05 E-39 95 21.4 +/- 0.6 17.4 +/- 0.7 16.6 +/- 0.7 1.28 +/- 0.05 E-41 95 22.3 +/- 0.3 18.2 +/- 0.5 17.5 +/-0.5 1.34 +/- 0.04 E-42 95 22.3 +/- 0.9 18.3 +/- 1.0 17.5 +/- 1.0 1.35 +/- O.Q7 E-43 95 22.4 +/- 0.7 18.4 +/- 0.8 17.6 +/- 0.7 1.35 +/- 0.06 E-44 95 21.2 +/- 0.5 17.2+/-0.6 16.4 +/- 0.6 1.26 +/- 0.04 Control E-20 95 19.5 +/- 0.8 15.4 +/- 0.9 14.8 +/- 0.9 1.14 +/-0.07 Mean+/-s.d.

20.4 +/- 2.6 16.3 +/- 2.6 15.6 +/- 2.5 1.20+/-0.19 In-Transit EXQQfil!.r§ Date Annealed Date Read ITC-1 ITC-2 09-12-23 10-05-23 3.8 +/- 0.1 3.6 +/- 0.2 12-12-23 01-11-24 4.5 +/- 0.2 4.4 +/- 0.2 a 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.

Annual Indicator Mean+/-s.d.

Annual Control Mean+/-s.d.

Annual Indicator/Control Mean+/-s.d.

19.7 +/- 2.7 19.3 +/- 0.9 19.7 +/- 2.7 14.8 +/- 2.9 14.5 +/- 1.3 14.8 +/- 2.9 11-4 14.8 +/- 2.8 14.4 +/- 1.0 14.8 +/- 2.7 1.1 +/- 0.2 1.1+/-0.1 1.1 +/- 0.2

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 Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-18-23 EWW-105 80 +/- 84

< 160 01-18-23 EWW-106 218 +/- 91

< 160 02-15-23 EWW-343 113 +/- 79

< 154 02-15-23 EWW-344 327 +/- 91

< 154 03-22-23 EWW-603 156 +/- 88

< 164 03-22-23 EWW-604 306 +/- 95

< 164 04-19-23 EWW-955 227 +/- 88

< 161 04-19-23 EWW-956 235 +/- 88

< 161 05-17-23 EWW-1268 187 +/- 91

< 161 05-17-23 EWW-1269 214 +/- 92

< 161 06-21-23 EWW-1660 215 +/- 88

< 163 06-21-23 EWW-1661 288 +/- 92

< 163 07-19-23 EWW-2090 226 +/- 89

< 162 07-19-23 EWW-2091 226 +/- 89

< 162 08-22-23 EWW-2511 217 +/- 92

< 161 08-22-23 EWW-2512 207 +/- 92

< 161 09-21-23 EWW-2791 98 +/- 82

< 163 09-21-23 EWW-2792 82 +/- 81

< 163 10-17-23 NFa 10-17-23 NFa 11-14-23 EWW-3540 85 +/- 87

< 172 11-14-23 EWW-3541 187 +/- 93

< 172 12-20-23 EWW-3943 68 +/- 83

< 171 12-20-23 EWW-3944 169 +/- 89

< 171 Mean+/- s.d.

152 +/- 65 Mean+/- s.d.

224 +/- 68 Samele ID GW-03 GW-17 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-18-23 EWW-107 153 +/- 88

< 160 01-18-23 EWW-110 319 +/- 96

< 160 02-15-23 EWW-345 106 +/- 79

< 154 02-15-23 EWW-347 475 +/- 99

< 154 03-22-23 EWW-605 92 +/- 84

< 164 03-22-23 EWW-607 370 +/- 98

< 164 04-19-23 EWW-957 168 +/- 85

< 161 04-19-23 EWW-958 388 +/- 96

< 161 05-17-23 EWW-1271 199 +/- 91

< 161 05-17-23 EWW-1273 332 +/- 98

< 161 06-21-23 EWW-1662 153 +/- 85

< 163 06-21-23 EWW-1663 246 +/- 90

< 163 07-19-23 EWW-2092 148 +/- 85

< 162 07-19-23 EWW-2093 260 +/- 91

< 162 08-22-23 EWW-2513 89 +/- 85

< 161 08-22-23 EWW-2516 270 +/- 95

< 161 09-21-23 EWW-2793 114 +/- 83

< 163 09-21-23 EWW-2795 239 +/- 89

< 163 10-17-23 NFa 10-17-23 NFa 11-14-23 EWW-3542 43 +/- 85

< 172 11-14-23 EWW-3545 237 +/- 95

< 172 12-20-23 EWW-3945 143 +/- 87

< 171 12-20-23 EWW-3947 262 +/- 93

< 171 Mean+/- s.d.

128 +/- 44 Mean+/- s.d.

309 +/- 76 a "NF" = No flow.

Wells Samele ID GW-04 {EiC WelQ Collection Date Lab Code Tritium MDC 01-18-23 EWW-109 59 +/- 83

< 160 02-15-23 EWW-346 62 +/- 76

< 154 03-22-23 EWW-606 73 +/- 83

< 164 04-19-23 EWW-953 108 +/- 81

< 161 05-17-23 EWW-1272 88 +/- 85

< 161 06-21-23 EWW-1664 93 +/- 79

< 158 07-19-23 EWW-2098 62 +/- 80

< 162 08-22-23 EWW-2515 29 +/- 82

< 161 09-21-23 EWW-2794 66 +/- 80

< 163 10-17-23 EWW-3229

-44 +/- 76

< 169 11-14-23 EWW-3544

-39 +/- 80

< 172 12-20-23 EWW-3946 56 +/- 82

< 171 Mean+/- s.d.

51 +/-48 12-1

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

Units= Ci/L Beach Drains Samele ID S-1 S-3 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-05-23 ESW-34 415 +/- 95

< 157 01-05-23 ESW-35 178 +/- 83

< 157 02-07-23 ESW-243 358 +/- 98

< 159 02-07-23 a

ESW-245 1716 +/- 153

< 162 03-01-23 ESW-415 386 +/- 97

< 163 03-01-23 ESW-416 436 +/- 99

< 163 04-06-23 ESW-789 470 +/- 100

< 161 04-06-23 ESW-790 381 +/- 96

< 161 05-03-23 ESW-1093 435 +/- 100

< 162 05-03-23 ESW-1094 171 +/- 86

< 162 06-08-23 ESW-1482 443 +/- 98

< 157 06-08-23 ESW-1483 281 +/- 90

< 157 07-06-23 ESW-1797 288 +/- 90

< 158 07-06-23 ESW-1798 317 +/- 91

< 158 08-02-23 EWW-2302 381 +/- 97

< 159 08-02-23 ESW-2303 245 +/- 90

< 159 09-12-23 EWW-2680 287 +/- 92

< 163 09-12-23 ESW-2681 80 +/- 81

< 163 10-03-23 EWW-2995 369 +/- 97

< 167 10-03-23 ESW-2996 211 +/- 89

< 167 11-01-23 EWW-3402 322 +/- 96

< 171 11-01-23 ESW-3403 985 +/- 125

< 171 12-05-23 EWW-3773 331 +/- 98

< 171 12-05-23 EWW-3774 111 +/- 87

< 171 Mean+/- s.d.

374 +/- 60 Mean+/- s.d.

426 +/- 471 a Tritium> 1000 pCi/L. Water resampled on 2/9. Tritium result= 892 +/-

121 pCi/L, MDC< 159 pCi/LAdditional anall'.ses in ape. F.

Samele ID S-7 S-8 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-05-23 NFa 01-05-23 NFa 02-07-23 b

ESW-246 1407 +/- 139

< 159 02-07-23 NFa 03-01-23 ESW-417 281 +/- 92

< 163 03-01-23 NFa 04-06-23 NFa 04-06-23 NFa 05-03-23 NFa 05-03-23 NFa 06-08-23 NFa 06-08-23 NFa 07-06-23 NFa 07-06-23 NFa 08-02-23 NFa 08-02-23 NF 8

09-12-23 NF 8

10-03-23 NF 8

11-01-23 NFa 11-01-23 NF 8

12-05-23 NF 8

12-05-23 NFa Mean+/- s.d.

844 +/- 797 Mean+/- s.d.

b Tritium> 1000 eCi/L. *Additional analyses in a

. F.

Samele ID S-9 S-10 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-05-23 NFa 01-05-23 NF 8

02-07-23 NF 8

03-01-23 ESW-418 283 +/- 92

< 163 03-01-23 ESW-419 655 +/- 92

< 163 04-06-23 NF 8

04-06-23 NF 8

05-03-23 NF 8

06-08-23 NF 8

07-06-23 NF 8

08-02-23 NF 8

09-12-23 NF 8

10-03-23 NF 8

11-01-23 NF 8

11-01-23 ESW-3404 589 +/- 109 12-05-23 NF 8

12-05-23 NF 8

Mean+/- s.d.

Mean +/-s.d.

622 +/- 47 a "NF" = No flow.

12-2

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

Units= Ci/L Beach Drains (cont.)

Samele ID S-12 S-13 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-05-23 EWW-36 294 +/- 89

< 157 01-05-23 NF 8

02-07-23 EWW-247 287 +/- 94

< 159 02-07-23 NF 8

03-01-23 EWW-420 290 +/- 92

< 163 03-01-23 NF 8

04-06-23 EWW-791 276 +/- 91

< 161 04-06-23 NF 8

05-03-23 EWW-1095 500 +/- 103

< 162 05-03-23 NF 8

06-08-23 NF 8

07-06-23 NF 8

08-02-23 EWW-2304 338 +/- 95

< 159 08-02-23 NF 8

09-12-23 EWW-2683 237 +/- 90

< 163 09-12-23 NF 8

10-03-23 NF 8

11-01-23 EWW-3405 244 +/- 93

< 171 11-01-23 NF 8

12-05-23 EWW-3776 134 +/- 88

< 171 12-05-23 NF 8

Mean+/- s.d.

289 +/- 97 Mean+/- s.d.

Sample ID U2Fa ade Subsurface Drain Sump Collection Date Lab Code Tritium MDC 01-31-23 EW-225 1697 +/- 146

< 155 02-28-23 EW-342 1805 +/- 149

< 154 03-31-23 EW-894 1072 +/- 132

< 158 04-30-23 EW-1151 1384 +/- 138

< 162 05-31-23 EW-1481 1392 +/- 136

< 157 06-30-23 EW-2545 2339 +/- 169

< 161 07-31-23 EW-2342 1120 +/- 131

< 162 08-31-23 EW-2676 1004 +/- 123

< 163 09-30-23 EW-4057 1391 +/- 140

< 171 10-31-23 EW-4059 462 +/- 104

< 170 11-30-23 EW-4060 792 +/- 117

< 169 12-31-23 EW-4061 870 +/- 120

< 169 Mean+/- s.d.

1277 +/- 507 a "NF" = No flow.

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 01-05-23 01-05-23 01-05-23 01-05-23 Lab Code EW-34 MDC EW-35 MDC NFa MDC NFa MDC Be-7

-8.0 +/- 9.5

< 18.9

-3.5 +/- 11.3

< 21.1 Mn-54 0.8 +/- 1.5

< 2.0

-0.2 +/- 1.5

< 2.1 Fe-59 0.4 +/- 3.0

< 4.4 2.1 +/- 2.7

< 5.5 Co-58 0.7 +/- 1.4

< 2.7 1.5 +/- 1.4

< 2.3 Co-60 1.7 +/- 1.4

< 1.7 0.3 +/- 1.7

< 1.0 Zn-65 2.2 +/- 3.4

< 4.8 1.8 +/- 3.1

< 4.8 Zr-Nb-95

-0.8 +/- 1.4

< 2.2

-2.4 +/- 1.4

< 2.0 Cs-134

-0.4 +/- 1.3

< 2.4

-0.8 +/- 1.4

< 2.5 Cs-137 0.2 +/- 1.6

< 3.2 0.7 +/- 2.0

< 3.6 Ba-La-140

-0.9 +/- 1.8

< 2.5

-1.3 +/- 1.7

< 1.3 Location S-9 S-10 S-12 S-13 Collection Date 01-05-23 01-05-23 01-05-23 01-05-23 Lab Code NFa MDC NFa MDC EW-36 MDC NFa MDC Be-7

-14.2 +/- 14.2

< 22.4 Mn-54

-0.3 +/- 1.7

< 2.3 Fe-59 1.3 +/- 3.7

< 5.2 Co-58 1.3 +/- 3.0

< 2.5 Co-60

-1.6 +/- 3.3

< 6.2 Zn-65

-2.8 +/- 3.7

< 4.8 Zr-Nb-95 0.1 +/- 2.0

< 3.3 Cs-134

-0.5 +/- 1.6

< 3.3 Cs-137 1.0 +/- 3.2

< 5.3 Ba-La-140

-1.3 +/- 1.8

< 2.5 Location S-1 S-3 S-7 S-8 Collection Date 02-07-23 02-07-23 02-07-23 02-07-23 Lab Code EW-243 MDC EW-245 MDC EW-246 MDC NFa MDC Be-7 14.7 +/- 14.4

< 25.4

-1.5 +/- 9.0

< 17.5 4.1 +/- 15.4

< 28.7 Mn-54

-1.2 +/- 1.8

< 2.5

-1.3 +/- 1.3

< 1.3

-1.2+/-1.7

< 2.8 Fe-59 4.0 +/- 3.6

< 5.3

-1.2+/-3.1

< 3.7 1.9 +/- 2.7

< 3.5 Co-58

-0.1 +/- 1.7

< 1.6

-0.8 +/- 1.3

< 2.2 0.5 +/- 1.5

< 2.6 Co-60 0.3 +/- 1.9

< 1.8 0.1 +/- 1.7

< 2.3

-0.5 +/- 1.5

< 6.5 Zn-65

-3.7 +/- 4.1

< 3.3

-3.0 +/- 3.0

< 5.0

-2.9 +/- 3.8

< 4.8 Zr-Nb-95

-1.6 +/- 3.0

< 3.4

-1.4 +/- 2.3

< 1.9

-3.1 +/- 1.8

< 2.8 Cs-134

-0.4 +/- 1.7

< 3.2 0.0 +/- 1.3

< 2.2 0.2 +/- 1.5

< 2.9 Cs-137

-0.8 +/- 2.0

< 3.3 2.8 +/- 1.6

< 3.0 1.9+/-1.7

< 5.0 Ba-La-140

-0.5+/-2.1

< 3.0

-0.2 +/- 1.5

< 1.3 0.7 +/- 1.8

< 2.9 a "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 02-07-23 02-07-23 02-07-23 02-07-23 Lab Code NFa MDC NFa MDC EW-247 MDC NFa MDC Be-7

-7.1 +/- 2.3

< 22.1 Mn-54 0.3 +/- 2.6

< 4.3 Fe-59

-0.5 +/- 5.3

< 6.0 Co-58

-1.2+/-2.9

< 4.7 Co-60 2.4 +/- 2.9

< 4.9 Zn-65

-2.1 +/- 6.7

< 7.7 Zr-Nb-95

-2.2 +/- 3.0

< 3.7 Cs-134

-0.8 +/- 2.9

< 5.0 Cs-137

-1.0+/-3.3

< 4.2 Ba-La-140

-0.8 +/- 8.7

< 2.8 Location S-1 S-3 S-7 S-8 Collection Date 03-01-23 03-01-23 03-01-23 03-01-23 Lab Code EW-415 MDC EW-416 MDC EW-417 MDC NFa MDC Be-7 13.7 +/- 8.9

< 18.0 21.8 +/- 14.7

< 32.4 5.5 +/- 23.4

< 20.1 Mn-54

-0.9 +/- 1.4

< 1.7

-0.8 +/- 1.5

< 2.0 1.1 +/- 2.4

< 4.1 Fe-59

-2.0 +/- 2.5

< 3.9

-1.8 +/- 3.1

< 2.6

-2.8 +/- 5.4

< 3.6 Co-58 0.4 +/- 1.4

< 2.0 0.6 +/- 1.7

< 2.9 0.1 +/- 2.4

< 3.2 Co-60

-1.4 +/- 1.5

< 1.3

-2.0 +/- 0.6

< 6.3

-2.8 +/- 3.1

< 3.9 Zn-65 1.9 +/- 2.6

< 5.0

-2.5 +/- 3.6

< 4.8

-1.9 +/- 7.0

< 6.4 Zr-Nb-95

-2.4 +/- 1.5

< 2.8

-1.7 +/- 1.7

< 3.3

-1.1 +/- 2.8

< 4.7 Cs-134

-0.3 +/- 1.1

< 1.8 1.0 +/- 1.4

< 2.9

-3.4 +/- 2.7

< 4.9 Cs-137

-0.3+/-1.5

< 3.0 0.6 +/- 0.6

< 4.9

-1.4 +/- 3.1

< 4.4 Ba-La-140

-0.3 +/- 1.5

< 2.4

-2.1 +/- 1.4

< 1.8 1.7 +/- 3.3

< 4.8 Location S-9 S-10 S-12 S-13 Collection Date 03-01-23 03-01-23 03-01-23 03-01-23 Lab Code EW-418 MDC EW-419 MDC EW-420 MDC NFa MDC Be-7 15.2 +/- 15.2

< 30.5 14.6 +/- 8.7

< 18.4

-17.9 +/- 20.0

< 24.4 Mn-54 0.8 +/- 1.8

< 3.3

-1.0 +/- 1.2

< 1.6 2.4 +/- 2.6

< 4.7 Fe-59 2.4 +/- 3.8

< 6.6 1.8+/-2.3

< 3.9 7.3 +/- 5.4

< 4.0 Co-58 2.9 +/- 1.5

< 2.7 0.4 +/- 1.3

< 2.6

-6.0 +/- 2.6

< 4.7 Co-60 1.8 +/- 2.2

< 2.5 0.6 +/- 1.5

< 1.8 1.5 +/- 2.8

< 3.6 Zn-65

-1.1 +/- 4.0

< 5.6

-2.6 +/- 2.6

< 4.1

-4.4 +/- 6.7

< 6.9 Zr-Nb-95 0.8 +/- 2.1

< 3.6

-1.1 +/- 1.5

< 2.1 1.5 +/- 2.6

< 5.8 Cs-134 1.2 +/- 1.8

< 3.4 0.5 +/- 1.2

< 2.4

-0.6 +/- 2.7

< 4.4 Cs-137 0.7 +/- 2.1

< 4.6

-0.2 +/- 1.4

< 2.1 0.2 +/- 2.5

< 3.8 Ba-La-140

-1.0 +/- 2.1

< 2.9

-0.2 +/- 1.3

< 1.1 1.8 +/- 2.9

< 2.8 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 04-06-23 04-06-23 04-06-23 04-06-23 Lab Code EW-789 MDC EW-790 MDC NF 8

MDC NF 8

MDC Be-7 4.4 +/- 10.4

< 23.8

-0.7 +/- 1.0

< 25.9 Mn-54 0.3 +/- 1.5

< 2.2

-1.0 +/- 1.7

< 1.6 Fe-59 1.0 +/- 3.5

< 5.4

-2.0 +/- 3.2

< 4.4 Co-58

-0.3 +/- 1.7

< 1.4 0.7 +/- 1.8

< 1.9 Co-60 1.0 +/- 1.7

< 1.8

-1.4 +/- 1.8

< 2.0 Zn-65

-0.9 +/- 2.7

< 4.4 1.3 +/- 3.3

< 5.9 Zr-Nb-95 0.0 +/- 2.0

< 3.6

-3.4 +/- 1.8

< 2.6 Cs-134 0.2 +/- 1.6

< 3.0 1.5 +/- 1.3

< 2.6 Cs-137 1.3 +/- 1.7

< 3.0 1.6 +/- 1.7

< 2.4 Ba-La-140

-0.3 +/- 2.2

< 2.1 1.5 +/- 1.6

< 2.1 Location S-9 S-10 S-12 S-13 Collection Date 04-06-23 04-06-23 04-06-23 04-06-23 Lab Code NF 8

MDC NF 8

MDC EW-791 MDC NF 8

MDC Be-7

-8.1 +/- 16.6

< 23.5 Mn-54

-0.3 +/- 2.0

< 2.8 Fe-59 1.6 +/- 3.7

< 5.3 Co-58 0.6 +/- 1.7

< 3.1 Co-60 0.4 +/- 2.8

< 2.2 Zn-65

-4.8 +/- 4.6

< 3.5 Zr-Nb-95

-1.3 +/- 2.1

< 3.0 Cs-134

-0.8 +/- 2.0

< 4.1 Cs-137

-0.6 +/- 2.3

< 2.9 Ba-La-140

-2.8 +/- 2.0

< 3.6 Location S-1 S-3 S-7 S-8 Collection Date 05-03-23 05-03-23 05-03-23 05-03-23 Lab Code EW-1093 MDC EW-1094 MDC NF 8

MDC NF 8

MDC Be-7

-4.3 +/- 15.5

< 26.2 2.4 +/- 8.9

< 14.9 Mn-54

-1.9 +/- 2.0

< 2.4

-1.3 +/- 1.3

< 1.4 Fe-59

-1.0 +/- 3.9

< 6.6

-0.4 +/- 2.3

< 4.1 Co-58

-1.1 +/- 2.0

< 3.3 0.3+/-1.2

< 1.9 Co-60 1.7 +/- 2.3

< 2.1 0.1 +/- 1.6

< 1.9 Zn-65

-2.8 +/- 4.2

< 4.6

-3.5 +/- 2.7

< 4.6 Zr-Nb-95

-2.5 +/- 3.6

< 3.7

-1.1 +/- 1.3

< 2.0 Cs-134

-0.1 +/- 1.8

< 3.3

-0.7 +/- 1.3

< 2.3 Cs-137 1.1 +/- 2.2

< 3.3 0.5 +/- 1.5

< 2.6 Ba-La-140 2.0 +/- 2.1

< 4.4

-1.8 +/- 1.6

< 1.5 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 05-03-23 05-03-23 05-03-23 05-03-23 Lab Code NF 8

MDC NF 8

MDC EW-1095 MDC NF 8

MDC Be-7

-6.6 +/- 8.2

< 13.8 Mn-54

-0.3 +/- 1.4

< 2.0 Fe-59

-0.3 +/- 2.3

< 3.3 Co-58 0.2 +/- 1.3

< 2.2 Co-60 0.8 +/- 1.5

< 1.8 Zn-65 1.7 +/- 2.5

< 3.6 Zr-Nb-95

-1.0 +/- 1.3

< 2.1 Cs-134 0.2 +/- 1.2

< 2.2 Cs-137 1.0 +/- 1.5

< 2.5 Ba-La-140 0.9 +/- 1.4

< 3.2 Location S-1 S-3 S-7 S-8 Collection Date 06-08-23 06-08-23 06-08-23 06-08-23 Lab Code EW-1482 MDC EW-1483 MDC NF 0

MDC NF 0

MDC Be-7

-7.2 +/- 10.4

< 15.8

-4.1 +/- 9.8

< 13.8 Mn-54 0.3 +/- 1.4

< 2.9 1.5 +/- 1.2

< 2.9 Fe-59 0.8 +/- 2.7

< 5.5 2.1 +/- 2.4

< 3.7 Co-58

-0.1 +/- 1.4

< 2.7

-1.3+/-1.3

< 2.1 Co-60 0.3 +/- 1.4

< 2.5

-1.0 +/- 2.6

< 2.3 Zn-65

-4.1 +/- 3.1

< 2.2

-1.3 +/- 2.2

< 3.1 Zr-Nb-95 0.5 +/- 1.4

< 2.9

-0.3 +/- 1.3

< 2.4 Cs-134 0.3 +/- 1.2

< 2.3

-0.8 +/- 1.2

< 2.3 Cs-137

-0.3 +/- 1.4

< 2.7

-0.4 +/- 1.5

< 2.8 Ba-La-140

-0.9 +/- 1.7

< 3.4

-1.4 +/- 4.4

< 2.2 Location S-9 S-10 S-12 S-13 Collection Date 06-08-23 06-08-23 06-08-23 06-08-23 Lab Code NF 0

MDC NF 8

MDC 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 07-06-23 07-06-23 07-06-23 07-06-23 Lab Code EW-1797 MDC EW-1798 MDC NF 8

MDC NF 8

MDC Be-7 1.4 +/- 12.5

< 15.0

-0.8 +/- 1.3

< 15.5 Mn-54 0.9 +/- 1.4

< 1.6 1.2 +/- 1.4

< 1.7 Fe-59

-1.4 +/- 3.0

< 5.2 1.2 +/- 3.0

< 4.9 Co-58 0.5 +/- 1.3

< 1.6 0.3 +/- 1.4

< 1.7 Co-60

-1.1 +/- 1.5

< 1.9 0.2 +/- 1.5

< 1.9 Zn-65 0.4 +/- 3.0

< 3.8 2.0 +/- 2.8

< 4.1 Zr-Nb-95

-0.7 +/- 1.5

< 2.0 1.0 +/- 1.4

< 2.1 Cs-134 0.6 +/- 1.5

< 2.9 0.7+/-1.5

< 2.8 Cs-137

-0.2+/-1.6

< 2.0

-0.2+/-1.7

< 2.0 Ba-La-140

-0.9 +/- 1.8

< 2.2

-1.1 +/- 1.9

< 2.5 Location S-9 S-10 S-12 S-13 Collection Date 07-06-23 07-06-23 07-06-23 07-06-23 Lab Code NF 8

MDC NF 8

MDC MDC NF 8

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 08-02-23 MDC 08-02-23 MDC 08-02-23 MDC 08-02-23 MDC Lab Code EW-2302 EW-2303 NF 8

NF 8

Be-7 12.5 +/- 20.4

< 37.2 5.8 +/- 29.5

< 33.9 Mn-54

-1.6 +/- 2.2

< 3.8 4.9 +/- 3.6

< 5.2 Fe-59

-3.9 +/- 5.3

< 5.2 3.1 +/- 7.7

< 12.4 Co-58 0.8 +/- 2.3

< 2.6

-0.4 +/- 3.9

< 6.0 Co-60 0.8 +/- 2.7

< 3.6

-2.3 +/- 3.2

< 3.7 Zn-65 0.5 +/- 5.8

< 6.3

-6.1 +/- 8.4

< 5.5 Zr-Nb-95

-2.3 +/- 3.0

< 6.6

-0.3 +/- 4.5

< 8.1 Cs-134

-2.5 +/- 2.7

< 4.6

-0.5 +/- 3.2

< 6.0 Cs-137 0.3 +/- 3.0

< 4.2 0.9 +/- 3.6

< 7.0 Ba-La-140

-2.8 +/- 9.4

< 3.2

-12.6 +/- 5.0

< 6.3 a "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 08-02-23 08-02-23 08-02-23 08-02-23 Lab Code NF 8

MDC NFa MDC EW-230.4 MDC NF 8

MDC Be-7

-16.0 +/- 3.2

< 24.9 Mn-54

-6.1 +/- 4.2

< 5.2 Fe-59

-0.8 +/- 8.7

< 9.3 Co-58

-1.0+/-1.1

< 5.0 Co-60

-1.6 +/- 5.3

< 4.9 Zn-65

-2.5 +/- 10.1

< 15.4 Zr-Nb-95

-5.4 +/- 3.7

< 3.9 Cs-134 1.8 +/- 4.2

< 7.3 Cs-137

-1.6 +/- 4.5

< 4.7 Ba-La-140 3.0 +/- 3.6

< 3.8 Location S-1 S-3 S-7 S-8 Collection Date 09-12-23 09-12-23 09-12-23 09-12-23 Lab Code EW-2680 MDC EW-2681 MDC NF 8

MDC NF 8

MDC Be-7 19.7 +/- 22.7

< 38.3

-8.2 +/- 20.6

< 32.2 Mn-54

-1.5 +/- 2.6

< 2.6 0.2 +/- 2.2

< 3.3 Fe-59 1.6 +/- 6.3

< 5.1

-2.5 +/- 4.8

< 5.3 Co-58

-0.8 +/- 2.6

< 1.8

-0.4 +/- 2.2

< 2.3 Co-60 2.5 +/- 2.7

< 9.1

-1.0 +/- 2.7

< 8.2 Zn-65

-2.8 +/- 5.3

< 4.4

-2.5 +/- 5.3

< 7.3 Zr-Nb-95 0.2 +/- 2.8

< 4.8

-0.6 +/- 3.0

< 5.2 Cs-134

-0.3 +/- 2.6

< 4.8

-1.1 +/- 2.2

< 4.2 Cs-137 2.1 +/- 3.0

< 8.1 3.5 +/- 3.2

< 7.9 Ba-La-140

-2.9 +/- 2.5

< 3.9

-0.3 +/- 2.4

< 4.4 Location S-9 S-10 S-12 S-13 Collection Date 09-12-23 09-12-23 09-12-23 09-12-23 Lab Code NF 8

MDC NF 8

MDC EW-2683 MDC NF 8

MDC Be-7 10.2 +/- 27.8

< 33.1 Mn-54 0.8 +/- 3.4

< 6.6 Fe-59 8.3 +/- 6.5

< 9.2 Co-58

-2.0 +/- 3.3

< 5.2 Co-60

-3.5 +/- 3.7

< 4.1 Zn-65 6.6 +/- 9.1

< 7.5 Zr-Nb-95

-2.4 +/- 3.9

< 5.5 Cs-134

-1.9+/-3.4

< 6.3 Cs-137

-0.3 +/- 4.4

< 4.0 Ba-La-140 0.3 +/- 4.3

< 4.2 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 10-03-23 10-03-23 10-03-23 10-03-23 Lab Code EW-2995 MDC EW-2996 MDC NF 8

MDC NFa MDC Be-7

-10.3 +/- 19.1

< 26.8 33.0 +/- 28.6

< 41.8 Mn-54

-1.2 +/- 1.8

< 2.6

-0.6 +/- 4.7

< 6.3 Fe-59

-2.4 +/- 3.9

< 2.9 5.5 +/- 9.6

< 12.3 Co-58 0.6 +/- 2.0

< 1.7 2.1 +/- 4.6

< 6.5 Co-60 1.2 +/- 2.7

< 7.1

-6.4 +/- 4.6

< 4.7 Zn-65

-1.7 +/- 5.1

< 6.3 4.5 +/- 8.4

< 11.3 Zr-Nb-95

-2.5 +/- 2.3

< 2.8

-1.7 +/- 4.5

< 5.3 Cs-134

-0.3 +/- 2.2

< 3.9 0.1 +/- 4.1

< 7.6 Cs-137 4.0 +/- 2.5

< 6.0 2.4 +/- 4.2

< 5.9 Ba-La-140 0.6 +/- 2.1

< 2.8 1.9 +/- 4.2

< 3.4 Location S-9 S-10 S-12 S-13 Collection Date 10-03-23 10-03-23 10-03-23 10-03-23 Lab Code NFa MDC NFa MDC NF 8

MDC NF 8

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 11-01-23 11-01-23 11-01-23 11-01-23 Lab Code EW-3402 EW-3403 NFa NF 8

Be-7 9.5 +/- 27.1

< 28.0

-7.7 +/- 11.3

< 19.8 Mn-54 1.0 +/- 3.5

< 5.6

-0.2 +/- 1.6

< 2.7 Fe-59 9.0 +/- 7.2

< 10.5 0.3 +/- 3.2

< 5.5 Co-58 0.9 +/- 3.0

< 5.4 0.7 +/- 1.5

< 3.1 Co-60

-2.3 +/- 4.3

< 4.2 0.2 +/- 1.3

< 1.0 Zn-65 4.0 +/- 6.9

< 8.3

-1.3 +/- 2.4

< 2.9 Zr-Nb-95 1.3 +/- 3.4

< 5.4

-0.9 +/- 1.8

< 2.5 Cs-134 1.8 +/- 2.8

< 5.1

-0.6+/-1.7

< 2.7 Cs-137 0.1 +/- 3.6

< 5.4

-0.8 +/- 1.8

< 1.8 Ba-La-140

-4.8 +/- 4.3

< 3.0 1.1 +/- 1.6

< 3.1 a "NF"= No flow.

12-10

POINT BEACH NUCLEAR PLANT Beach Drains (cont.)

Units: = pCi\\L Gamma isotopic analysis S-9 S-10 S-13 Collection Date 11-01-23 11-01-23 11-01-23 11-01-23 Lab Code NFa MDC EW-3404 MDC EW-3405 MDC NF 8

MDC Be-7 1.4 +/- 13.4

< 23.7 2.2 +/- 23.2

< 29.3 Mn-54

-1.3 +/- 1.6

< 2.4 2.1 +/- 3.0

< 5.4 Fe-59

-2.3 +/- 3.1

< 3.4

-4.4 +/- 6.4

< 5.5 Co-58 1.0 +/- 1.6

< 2.4 1.1 +/- 2.8

< 4.3 Co-60 1.9 +/- 1.9

< 5.4 1.8 +/- 3.2

< 3.6 Zn-65

-0.8 +/- 3.7

< 5.9

-9.6 +/- 7.5

< 4.1 Zr-Nb-95

-2.1 +/- 1.5

< 1.8

-3.1 +/- 2.8

< 3.2 Cs-134 0.9 +/- 1.5

< 2.9

-4.8 +/- 3.2

< 5.5 Cs-137 1.2 +/- 1.9

< 4.6

-0.7 +/- 3.6

< 5.4 Ba-La-140

-3.8 +/- 2.0

< 2.3 2.7 +/- 2.6

< 2.2 Location S-1 S-3 S-7 S-8 Collection Date 12-05-23 12-05-23 12-05-23 12-05-23 Lab Code EW-3773 MDC EW-3774 MDC NF 8

MDC NFa MDC Be-7 2.7 +/- 12.9

< 18.4 3.8 +/- 11.8

< 24.9 Mn-54 0.8 +/- 1.5

< 1.9 0.9 +/- 1.7

< 2.5 Fe-59 2.1 +/- 2.8

< 5.1

-1.2 +/- 3.8

< 4.5 Co-58

-0.8 +/- 1.9

< 3.0 0.9+/-1.8

< 2.7 Co-60 0.4 +/- 2.1

< 1.4 1.3 +/- 2.2

< 3.3 Zn-65 0.7 +/- 2.9

< 2.7

-3.9 +/- 5.0

< 8.3 Zr-Nb-95

-1.1 +/- 2.1

< 2.6

-1.4 +/- 2.0

< 2.4 Cs-134

-0.2 +/- 1.7

< 3.2

-0.3 +/- 1.7

< 3.3 Cs-137 0.1 +/- 1.7

< 1.9 0.1 +/- 2.2

< 3.5 Ba-La-140

-0.8 +/- 1.9

< 2.0 1.4 +/- 2.1

< 2.6 Location S-9 S-10 S-12 S-13 Collection Date 12-05-23 12-05-23 12-05-23 12-05-23 Lab Code NF 8

MDC NFa MDC EW-3776 MDC NF 8

MDC Be-7

-8.0 +/- 14.5

< 27.2 Mn-54 0.8 +/- 2.0

< 2.8 Fe-59 2.5 +/- 4.1

< 5.2 Co-58 0.8 +/- 1.9

< 2.5 Co-60 0.6 +/- 1.7

< 2.6 Zn-65 1.7 +/- 4.0

< 4.5 Zr-Nb-95

-0.2 +/- 2.1

< 4.3 Cs-134 0.1 +/- 1.7

< 3.0 Cs-137

-1.1 +/- 2.3

< 2.6 Ba-La-140

-1.6 +/- 5.3

< 4.9 "NF" = No flow.

12-11

POINT BEACH NUCLEAR PLANT Table 12. Groundwater Tritium Monitoring Program

( Quarterly Collections)

Units= Ci/L Quarterly Wells Sample ID GW-05 (WH 6 Welll GW-06 (SBCC Well}

Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 01-18-23 EWW-111

-6 +/- 79

< 160 01-18-23 EWW-112 38 +/- 81

< 160 04-13-23 EWW-881 46 +/- 78

< 161 04-13-23 EWW-882

-34 +/- 72

< 161 07-19-23 EWW-2094 52 +/- 79 162 07-19-23 EWW-2096 55 +/- 79

< 162 10-10-23 EWW-3072

-51 +/- 75

< 170 10-10-23 EWW-3073 33 +/- 81

< 170 Mean+/- s.d.

10 +/- 49 Mean+/- s.d.

23 +/- 39 Sample ID GW-11 (MW-1}

GW-12 (MW-2 Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 02-08-23 EWW-272 93 +/- 84

< 159 02-08-23 EWW-273 11 +/- 79

< 159 04-27-23 EWW-1108 164 +/- 86

< 162 04-27-23 EWW-1109 75 +/- 81

< 162 07-19-23 EWW-2186 214 +/- 88

< 162 07-19-23 EWW-2187 5 +/- 76

< 162 12-07-23 EWW-3892 42 +/- 82

< 171 12-07-23 EWW-3893

-15 +/- 78

< 171 Mean+/- s.d.

128 +/- 76 Mean+/- s.d.

19 +/- 39 Sample ID GW-13 (MW-61 GW-14A (MW-05A}

Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 02-08-23 EWW-274 100 +/- 85

< 159 02-08-23 EWW-275 219 +/- 91

< 159 04-27-23 EWW-1110 118 +/- 83

< 162 04-27-23 EWW-1111 273 +/- 92

< 162 07-19-23 EWW-2188 74 +/- 80

< 162 07-19-23 EWW-2189 155 +/- 85

< 162 12-07-23 EWW-3894

-10 +/- 79

< 171 12-07-23 EWW-3895 106 +/- 85

< 171 Mean+/- s.d.

70 +/- 57 Mean+/- s.d.

188 +/- 73 Sample ID GW-15A (MW-41 GW-158 f MW-4}

Collection Collection Date Lab Code Tritium MDC Date Lab Code Tritium MDC 02-08-23 EWW-276 135 +/- 86

< 159 02-08-23 EWW-277 245 +/- 92

< 159 04-27-23 EWW-1112 193 +/- 87

< 162 04-27-23 EWW-1113 150 +/- 85

< 162 07-19-23 EWW-2190 200 +/- 88

< 162 07-19-23 EWW-2191 186 +/- 87

< 162 12-07-23 EWW-3896 66 +/- 83

< 171 12-07-23 EWW-3897 122 +/- 86

< 171 Mean+/- s.d.

148 +/- 63 Mean+/- s.d.

176 +/- 53 Sample ID GW-16A (MW-3}

Collection Date Lab Code Tritium MDC 02-08-23 EWW-278 245 +/- 92

< 159 04-27-23 EWW-1114 285 +/- 92

< 162 07-19-23 EWW-2192 314 +/- 94

< 162 12-07-23 EWW-3898 134 +/- 87

< 171 Mean+/- s.d.

245 +/- 79 12-12

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

Units= Ci/L Quarterly Wells (cont.)

_S_a_m.._pl_e_lD ______

G_W_-_1_8 (WH 7 _W_el......

l) __

Collection Date 01-18-23 04-13-23 07-19-23 10-10-23 Mean+/- s.d.

Sample ID Collection Date 02-28-23 05-02-23 07-25-23 10-02-23 Mean+/- s.d.

Sample ID Collection Date 05-18-23 Lab Code Tritium EWW-113 59 +/- 83 EWW-883 50 +/- 78 EWW-2097 124 +/- 83 EWW-3075

-25 +/- 77 52 +/- 61 GW-09 1Z-361A Lab Code Tritium EWW-482 288 +/- 92 EWW-1123 229 +/- 89 EWW-2343 261 +/- 95 EWW-3999 310 +/- 97 272 +/- 35 GW-10 2Z-361A Lab Code Tritium EWW-484 76 +/- 80 EWW-1125 91 +/- 82 EWW-2345 46 +/- 83 EWW-4001 88 +/- 85 75 +/- 21 GW-07 (North Bog)

Lab Code Tritium a EWW-1278 344 +/- 99 MDC

< 160

< 161

< 162

< 170 F a~ade Wells GW-09 1Z-361B MDC Collection Date Lab Code Tritium

< 163 02-28-23 EWW-483 221 +/- 89

< 162 05-02-23 EWW-1124 174 +/- 86

< 162 07-25-23 EWW-2344 230 +/- 93

< 173 10-02-23 EWW-4000 200 +/- 91 Mean+/- s.d.

206 +/- 25 GW-10 22-3618 MDC Collection Date Lab Code Tritium

< 163 02-28-23 EWW-485 138 +/- 84

< 162 05-02-23 EWW-1126 353 +/- 96

< 162 07-25-23 EWW-2346 286 +/- 96

< 173 10-02-23 EWW-4002 291 +/- 96 Mean+/- s.d.

267 +/- 91 (Annual Collections)

Units= Ci/L Bogs GW-08 EiC Bog Collection MDC Date Lab Code Tritium

< 161 05-18-23 0 EWW-1279 501 +/- 106 MDC

< 163

< 162

< 173 MDC

< 163

< 162

< 173 MDC

< 161 a Reanalysis= 245 +/- 101 pCi/L, MDC< 168 pCi/L.

6 Reanalysis = 493 +/- 112 pCi/L, MDC < 168 pCi/L.

12-13

POINT BEACH NUCLEAR PLANT Table 12. Groundwater Tritium Monitoring Program Units= Ci/L Manholes Sample ID MH Z-065A MH Z-0658 Collection Lab Code Tritium MDC Collection Lab Code Tritium MDC Date (pCi/L)

Date (pCi/L) 04-24-23 EW-1096 402 +/- 98

< 162 04-24-23 EW-1097 506 +/- 103

< 162 09-13-23 EW-3462 320 +/- 97

< 172 09-13-23 EW-3463 325 +/- 97

< 172 Mean+/- s.d.

361 +/- 58 Mean+/- s.d.

415 +/- 128 Sample ID MH Z-065C MH Z-065D Collection Lab Code Tritium MDC Collection Lab Code Tritium MDC Date (pCi/L)

Date (pCi/L)

Mean+/- s.d.

Sample ID MH Z-066A MH Z-0668 Collection Lab Code Tritium MDC Collection Lab Code Tritium MDC Date (pCi/L)

Date (pCi/L) 04-25-23 EW-1098 377 +/- 97

< 162 04-25-23 EW-1099 382 +/- 97

< 162 09-13-23 EW-3424 246 +/- 93

< 172 09-13-23 EW-3465 146 +/- 88

< 172 Mean+/- s.d.

312 +/- 93 Mean+/- s.d.

264 +/- 167 Sample ID MH Z-066C MH Z-066D Collection Lab Code Tritium MDC Collection Lab Code Tritium MDC Date (pCi/L)

Date (pCi/L) 04-25-23 EW-1100 453 +/- 101

< 162 04-25-23 EW-1101 358 +/- 96

< 162 09-13-23 EW-3466 310 +/- 96

< 172 09-13-23 EW-3467 206 +/- 91

< 172 Mean+/- s.d.

381 +/- 101 Mean+/- s.d.

282 +/- 107 Sample ID MH Z-067A MH Z-0678 Collection Lab Code Tritium MDC Collection Lab Code Tritium MDC Date (pCi/L)

Date (pCi/L) 04-24-23 EW-1103 334 +/- 95

< 162 04-25-23 EW-1104 448 +/- 101

< 162 09-13-23 EW-3468 225 +/- 92

< 172 09-13-23 EW-3469 237 +/- 93

< 172 Mean+/- s.d.

279 +/- 77 Mean+/- s.d.

342 +/- 149 12-14

Sample ID Collection Date 04-25-23 09-13-23 Mean+/- s.d.

Sample ID Collection Date 04-26-23 09-13-23 Mean+/- s.d.

Sample ID Collection Date Mean+/- s.d.

MH Z-067C Lab Code Tritium EW-1105 421 +/- 99 EW-3470 237 +/- 93 329 +/- 130 MH Z-068 Lab Code Tritium EW-1107 603 +/- 108 EW-3472 189 +/- 90 396 +/- 292 MH-4 Lab Code Tritium MH-7 Lab Code Tritium MH-16 Lab Code Tritium MH-5A Lab Code Tritium

.POINT BEACH NUCLEAR PLANT Manholes (cont.)

MDC (pCi/L)

< 162

< 172 MDC (pCi/L)

< 162

< 172 MDC (pCi/L)

MDC (pCi/L)

Collection Date 04-25-23 09-13-23 Mean+/- s.d.

Collection Date Mean+/- s.d.

12-15 MH Z-067D Lab Code Tritium EW-1106 256 +/- 91 EW-3471 108 +/- 86 182 +/- 105 MH-1 Lab Code Tritium MH-6 Lab Code Tritium MH-8 Lab Code Tritium MH-2 Lab Code Tritium MH-9 Lab Code Tritium MDC (pCi/L)

< 162

< 172 MDC (pCi/L)

MDC (pCi/L)

©) MICROBAC ~

700 Landwehr Road

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

fax (847) 564-4517 NOTE:

APPENDIX A INTERLABORATORY AND INTRALABORATORY COMPARISON PROGRAM RESULTS Appendix A is updated four times a year. The complete appendix is included in March, June, September and December monthly progress reports only.

October, 2022 through September, 2023

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.

Table A-2 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-3 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-4 lists results of the analyses on intralaboratory "blank" samples for the past twelve months. Data for previous years available upon request.

Table A-5 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-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.

Results in Table A-7 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

Analysis Gamma Emitters Strontium-89, Strontium-90 Potassium-40 Gross alpha Gross beta Tritium Radium-226, Radium-228 Plutonium lodine-129, lodine-131 Nickel-63, Technetium-99, Uranium-238 lron-55 Other Analyses Attachment A ACCEPTANCE CRITERIA FOR INTRALABORATORY "SPIKED" SAMPLES Ratio of lab result to known value.

0.8 to 1.2 0.8 to 1.2 0.8 to 1.2 0.5 to 1.5 0.8to1.2 0.8 to 1.2 0.7 to 1.3 0.8 to 1.2 0.8 to 1.2 0.7to1.3 0.8 to 1.2 0.8 to 1.2 A-2

TABLE A-1. lnterlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) 8 RAD study Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Acceptance Result Value Limits Acceptance RAD-132 Study ERDW-162 2/23/2023 Ba-133 33.0 +/- 3.5 30.5 24.2 - 34.6 Pass ERDW-162 2/23/2023 Cs-134 30.7 +/- 3.0 28.2 21.9-31.1 Pass ERDW-162 2/23/2023 Cs-137 191 +/- 7 190 171-211 Pass ERDW-162 2/23/2023 Co-60 110 +/- 4 110 99.0 - 123 Pass ERDW-162 2/23/2023 Zn-65 109 +/- 8 105 94.5 - 125 Pass ERDW-162 2/23/2023 Gr. Alpha 25.3 +/- 0.2 30.0 15.3 - 39.2 Pass ERDW-162 2/23/2023 G. Beta 15.0+/-0.1 16.5 9.25 - 24.8 Pass ERDW-162 2/23/2023 Ra-226 7.58 +/- 0.52 8.26 6.21 - 9.71 Pass ERDW-162 2/23/2023 Ra-228 7.44 +/- 1.53 7.17 4.51 - 9.20 Pass ERDW-162 2/23/2023 H-3 22,600 +/- 467 21,600 18,900 - 23,800 Pass RAD-134 Study ERDW-1956 7/10/2023 Ba-133 64.1 +/- 4.7 66.5 55.4 - 73.2 Pass ERDW-1956 7/10/2023 Cs-134 97.0 +/- 4.8 90.8 74.5 - 99.9 Pass ERDW-1956 7/10/2023 Cs-137 179 +/- 8 163 147 - 181 Pass ERDW-1956 7/10/2023 Co-60 26.6 +/- 2.9 20.7 17.5 -25.6 Fail b ERDW-1956 7/10/2023 Zn-65 318 +/- 12 290 261 - 339 Pass ERDW-50167 7/10/2023 Gr. Alpha 34.3 +/- 1.9 47.9 24.9 - 60.3 Pass ERDW-50167 7/10/2023 G. Beta 27.4 +/- 1.2 28.6 18.2 - 36.4 Pass ERDW-50171 7/10/2023 Ra-226 19.3 +/- 0.9 17.4 12.9 - 19.9 Pass ERDW-50171 7/10/2023 Ra-228 7.11 +/- 1.59 7.16 4.50 - 9.18 Pass ERDW-50173 7/10/2023 H-3 10,500 +/- 326 9,860 8,570 - 10,800 Pass ERDW-50169 7/10/2023 1-131 23.9 +/- 1.2 24.4 20.2 - 28.9 Pass a Results obtained by Microbac Laboratories Inc. - Northbrook as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resource Associates (ERA).

b The Cobalt-60 result did not meet ERA acceptance criteria. The sample was reanalyzed and passed for all analytes.

(Co-60 reanalysis result was 21.2 +/- 3.0 pCi/L). No cause for the earlier failure could be determined.

A-3

TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaS04: Dy Cards).

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

Environmental, Inc.

Group 1 2022-23-1 2/7/2023 Spike 1 134.0 134.5 0.00 2022-23-1 2/7/2023 Spike 2 134.0 131.1

-0.02 2022-23-1 2/7/2023 Spike 3 134.0 134.0 0.00 2022-23-1 2/7/2023 Spike 4 134.0 130.7

-0.02 2022-23-1 2/7/2023 Spike 5 134.0 131.5

-0.02 2022-23-1 2/7/2023 Spike 6 134.0 139.3 0.04 2022-23-1 2/7/2023 Spike 7 134.0 134.8 0.01 2022-23-1 2/7/2023 Spike 8 134.0 130.7

-0.02 2022-23-1 2/7/2023 Spike 9 134.0 133.1

-0.01 2022-23-1 2/7/2023 Spike 10 134.0 129.9

-0.03 2022-23-1 2/7/2023 Spike 11 134.0 125.6

-0.06 2022-23-1 2/7/2023 Spike 12 134.0 139.5 0.04 2022-23-1 2/7/2023 Spike 13 134.0 135.2 0.01 2022-23-1 2/7/2023 Spike 14 134.0 135.8 0.01 2022-23-1 2/7/2023 Spike 15 134.0 133.6 0.00 2022-23-1 2/7/2023 Spike 16 134.0 132.7

-0.01 2022-23-1 2/7/2023 Spike 17 134.0 125.1

-0.07 2022-23-1 2/7/2023 Spike 18 134.0 131.9

-0.02 2022-23-1 2/7/2023 Spike 19 134.0 125.3

-0.06 2022-23-1 2/7/2023 Spike 20 134.0 128.2

-0.04 Mean (Spike 1-20) 132.1

-0.01 Passd Standard Deviation (Spike 1-20) 4.1 0.03 Passd 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 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-4

TABLE A-2. Thermoluminescent Dosimetry, (TLD, CaS04: Dy Cards).

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

Environmental. Inc.

Group 2 2022-23-2 2/7/2023 Spike 21 70.0 71.7 0.02 2022-23-2 2/7/2023 Spike 22 70.0 72.1 0.03 2022-23-2 2/7/2023 Spike 23 70.0 66.2

-0.05 2022-23-2 2/7/2023 Spike 24 70.0 70.6 0.01 2022-23-2 2/7/2023 Spike 25 70.0 71.0 0.01 2022-23-2 2/7/2023 Spike 26 70.0 71.3 0.02 2022-23-2 2/7/2023 Spike 27 70.0 68.4

-0.02 2022-23-2 2/7/2023 Spike 28 70.0 70.2 0.00 2022-23-2 2/7/2023 Spike 29 70.0 72.1 0.03 2022-23-2 2/7/2023 Spike 30 70.0 71.2 0.02 2022-23-2 2/7/2023 Spike 31 70.0 67.5

-0.04 2022-23-2 2/7/2023 Spike 32 70.0 68.8

-0.02 2022-23-2 2/7/2023 Spike 33 70.0 72.2 0.03 2022-23-2 2/7/2023 Spike 34 70.0 69.6

-0.01 2022-23-2 2/7/2023 Spike 35 70.0 69.7 0.00 2022-23-2 2/7/2023 Spike 36 70.0 68.0

-0.03 2022-23-2 2/7/2023 Spike 37 70.0 72.2 0.03 2022-23-2 2/7/2023 Spike 38 70.0 70.6 0.01 2022-23-2 2/7/2023 Spike 39 70.0 70.4 0.01 2022-23-2 2/7/2023 Spike 40 70.0 66.5

-0.05 Mean (Spike 21-40) 70.0 0.00 Passd Standard Deviation (Spike 21-40) 1.9 0.03 Passd 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 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-5

TABLE A-3. lntralaboratory "Spiked" Samples Concentration a Lab Codeb Date Analysis Laboratory results Known Control Ratio 2s, n=1c Activity Limitsd Acceptance Lab/Known SPDW-40361 10/12/2022 Ra-226 10.0 +/- 0.3 12.3 8.6 - 16.0 Pass 0.81 SPDW-40344 11/3/2022 Ra-228 13.2 +/- 1.8 13.4 9.4 - 17.4 Pass 0.99 SPDW-40346 11/8/2022 Gr. Alpha 42.0 +/- 2.2 60.2 30.1 - 90.3 Pass 0.70 SPDW-40346 11/8/2022 Gr. Beta 16.6 +/- 1.0 17.7 14.2 - 21.2 Pass 0.94 SPDW-40352 11/17/2022 Sr-90 18.8 +/- 1.2 17.1 13.7 -20.5 Pass 1.10 SPDW-40355 11/18/2022 H-3 10,143 +/- 316 10,400 8,320 - 12,480 Pass 0.98 SPDW-40364 11/30/2022 Gr. Alpha 38.4 +/- 1.5 49.1 24.6 - 73.7 Pass 0.78 SPDW-40364 11/30/2022 Gr. Beta 30.9 +/- 1.2 31.5 25.2 - 37.8 Pass 0.98 LCS-W-110822 2/1/2022 Cs-137 222 +/- 10 206 165 - 247 Pass 1.08 LCS-W-110822 2/1/2022 Co-57 1,060 +/- 117 973 778 - 1,168 Pass 1.09 LCS-W-110822 2/1/2022 Co-60 250 +/- 8 251 201 - 301 Pass 1.00 LCS-W-110822 2/1/2022 Mn-54 537 +/- 18 511 409 - 613 Pass 1.05 LCS-W-110822 2/1/2022 Zn-65 673 +/- 35 708 566 - 850 Pass 0.95 SPDW-40372 11/21/2022 Ra-226 11.3 +/- 0.3 12.3 8.6 - 16.0 Pass 0.92 SPU-3883 12/1/2022 H-3 21,694 +/- 1,387 23,900 19,120 - 28,680 Pass 0.91 SPW-3950 12/1/2022 Ni-63 1,937 +/- 28 2,135 1,708 - 2,562 Pass 0.91 SPDW-40366 12/2/2022 H-3 22,466 +/- 464 23,900 19,120 - 28,680 Pass 0.94 SPW-3969 12/2/2022 Ni-63 2,123 +/-29 2,135 1,708 - 2,562 Pass 0.99 SPW-3881 12/5/2022 Tc-99 85.0 +/- 1.6 108 75 - 140 Pass 0.79 SPDW-40374 12/12/2022 H-3 22,554 +/- 463 23,900 19,120 - 28,680 Pass 0.94 SPDW-40382 12/12/2022 Ra-226 12.7 +/- 0.4 12.3 8.6 - 16.0 Pass 1.03 SPDW-40380 12/22/2022 H-3 22,200 +/- 462 23,900 19,120 - 28,680 Pass 0.93 SPDW-26 1/5/2023 Ra-228 11.8 +/- 1.9 13.4 9.4 - 17.4 Pass 0.88 SPDW-50002 1/11/2023 H-3 21,747 +/- 452 22,100 17,680 - 26,520 Pass 0.98 SPDW-50004 1/20/2023 H-3 21,861 +/- 458 22,100 17,680 - 26,520 Pass 0.99 SPDW-50006 1/5/2023 Ra-226 11.3 +/- 0.3 12.3 8.6 - 16.0 Pass 0.92 SPDW-50034 1/27/2023 Ra-226 12.6 +/- 0.4 12.3 8.6-16.0 Pass 1.02 LCS-S0-012723 8/1/2020 Cs-134 17.1+/-0.2 19.2 15.4 - 23.0 Pass 0.89 LCS-S0-012723 8/1/2020 Zn-65 13.8 +/- 1.7 14.1 11.3 - 16.9 Pass 0.98 LCS-S0-012723 8/1/2020 Co-60 26.4 +/- 0.2 27.0 21.6 - 32.4 Pass 0.98 LCS-S0-012723 8/1/2020 Co-57 30.7 +/- 0.1 30.9 24.7 - 37.1 Pass 0.99 LCS-S0-012723 8/1/2020 Mn-54 17.7 +/-0.8 16.5 13.2 -19.8 Pass 1.07 LCS-S0-012723 8/1/2020 K-40 18.4 +/- 0.7 16.8 13.4 - 20.2 Pass 1.10 SPDW-50010 1/31/2023 Ra-228 9.7 +/- 1.3 13.4 9.4 - 17.4 Pass 0.72 SPDW-50008 2/3/2023 H-3 21,961 +/- 459 22,100 17,680 - 26,520 Pass 0.99 SPDW-50016 2/10/2023 H-3 22,137 +/- 462 22,100 17,680 - 26,520 Pass 1.00 SPDW-50012 2/24/2023 Sr-90 18.6 +/- 1.2 17.1 13.7 - 20.5 Pass 1.09 SPDW-50032 2/16/2023 Ra-228 13.1 +/-1.9 13.4 9.4-17.4 Pass 0.98 SPDW-50018 2/16/2023 Gr. Alpha 19.1 +/-1.3 23.5 11.8 - 28.2 Pass 0.81 SPDW-50018 2/16/2023 Gr. Beta 133 +/- 2 141 112 - 169 Pass 0.94 SPDW-50021 2/17/2023 H-3 21,843 +/- 459 22,100 17,680 - 26,520 Pass 0.99 SPDW-50047 2/24/2023 Ra-226 12.8 +/- 0.4 12.3 8.6 - 16.0 Pass 1.04 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.

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

A-6

TABLE A-3. lntralaboratory "Spiked" Samples Concentration 8

Lab Codeb Date Analysis Laboratory results Known Control Ratio 2s, n=1c Activity Limitsd Acceptance Lab/Known SPDW-50049 3/17/2023 H-3 22,120 +/- 465 22,100 17,680 - 26,520 Pass 1.00 SPDW-50056 3/24/2023 H-3 21,911 +/-463 22,100 17,680 - 26,520 Pass 0.99 SPDW-50060 3/16/2023 Ra-226 12.9+/-0.4 12.3 8.6 - 16.0 Pass 1.05 SPDW-50097 4/13/2023 Ra-226 11.7 +/-0.5 12.3 8.6 - 16.0 Pass 0.95 SPDW-50068 4/14/2023 H-3 22,656 +/- 482 22,100 17,680 - 26,520 Pass 1.03 SPDW-50081 4/25/2023 H-3 21,594 +/- 461 22,100 17,680 - 26,520 Pass 0.98 SPDW-50131 5/3/2023 Ra-226 11.4+/-0.3 12.3 8.6 - 16.0 Pass 0.93 SPDW-50104 5/12/2023 H-3 21,513 462 22,100 17,680 - 26,520 Pass 0.97 SPDW-50117 5/26/2023 H-3 22,069 468 22,100 17,680 - 26,520 Pass 1.00 SPDW-50182 6/8/2023 Ra-226 10.4 +/- 0.3 12.3 8.6 - 16.0 Pass 0.85 SPDW-50137 6/12/2023 H-3 21,898 +/- 456 22,100 17,680 - 26,520 Pass 0.99 SPDW-50138 6/12/2023 H-3 21,898 +/-456 22,100 17,680 - 26,520 Pass 0.99 SPDW-50153 6/26/2023 H-3 21,672 +/- 456 22,100 17,680 - 26,520 Pass 0.98 SPDW-50153 6/26/2023 H-3 21,672 +/- 456 22,100 17,680 - 26,520 Pass 0.98 SPDW-50259 7/19/2023 Ra-226 10.5 +/- 0.3 12.3 8.6 - 16.0 Pass 0.85 SPDW-50219 8/15/2023 Sr-90 17.5 +/- 1.1 17.1 13.7 - 20.5 Pass 1.02 SPDW-50291 8/28/2023 Ra-226 11 +/- 0 12.3 8.6 - 16.0 Pass 0.89 SPDW-50249 8/22/2023 Gr. Alpha 16.7+/-1.4 23.5 11.8 - 28.2 Pass 0.71 SPDW-50249 8/22/2023 Gr. Beta 128 +/- 2 141 112 - 169 Pass 0.91 SPDW-50252 8/18/2023 H-3 21,628 +/- 459 22,100 17,680 - 26,520 Pass 0.98 SPDW-50257 8/25/2023 H-3 22,152 +/- 469 22,100 17,680 - 26,520 Pass 1.00 LCS-09/12/23 8/1/2020 Cs-134 17,533 +/- 346 19,170 15,336 - 23,004 Pass 0.91 LCS-09/12/23 8/1/2020 Co-60 27,480 +/- 347 26,055 20,844 - 31,266 Pass 1.05 LCS-09/12/23 8/1/2020 K-40 20,183 1268 18,468 14,774 - 22,162 Pass 1.09 SPDW-50270 9/6/2023 H-3 22,287 +/- 469 22,100 17,680 - 26,520 Pass 1.01 SPDW-50283 9/25/2023 H-3 21,062 +/- 444 22,100 17,680 - 26,520 Pass 0.95 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.

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

A-7

TABLE A-4. lntralaboratory "Blank" Samples Concentration a Lab Codeb Sample Date Analysisc Laboratory results (4.66cr)

Acceptance Type LLD Activity Criteria (4.66 a)

SPDW-40345 Water 11/8/2022 Gr. Alpha 0.53

-0.17+/-0.36 2

SPDW-40345 Water 11/8/2022 Gr. Beta 0.78

-0.05 +/- 0.54 4

SPDW-40350 Water 11/11/2022 H-3 166 96 +/- 84 200 SPDW-40352 Water 11/17/2022 Sr-89 0.66

-0.01 +/- 0.53 5

SPDW-40352 Water 11/17/2022 Sr-90 0.61 0.11 +/- 0.29 1

SPDW-40354 Water 11/18/2022 H-3 155 21 +/- 76 200 SPDW-40354 Water 11/18/2022 1-131 0.18

-0.11 +/- 0.09 1

SPW-3880 Water 12/1/2022 Tc-99 5.58 2.99 +/- 3.44 200 SPU-3882 Urine 12/1/2022 H-3 1157 599 +/- 642 2000 SPW-3949 Water 12/2/2022 Ni-63 16.3 9.0 +/- 10.0 200 SPW-3968 Water 12/2/2022 Ni-63 15.9 0.0 +/- 9.6 200 SPDW-40370 Water 12/7/2022 1-131 0.10

-0.04 +/- 0.06 SPDW-40381 Water 12/12/2022 Ra-226 0.06

-0.04 +/- 0.05 2

SPDW-40379 Water 12/22/2022 H-3 162 107 +/- 84 200 SPW-25 Water 1/5/2023 Ra-228 0.98 0.74 +/- 0.54 2

SPDW-50000 Water 1/6/2023 1-131 0.36

-0.10 +/- 0.16 1

SPDW-50001 Water 1/11/2023 H-3 157 13 +/- 74 200 SPDW-50003 Water 1/20/2023 H-3 161 98 +/- 85 200 SPDW-50005 Water 1/5/2023 Ra-226 0.02 0.00 +/- 0.03 2

SPDW-50033 Water 1/27/2023 Ra-226 0.03

-0.01 +/- 0.03 2

SPDW-50009 Water 1/31/2023 Ra-228 1.40 0.69 +/- 0.75 2

SPDW-50007 Water 2/3/2023 H-3 160 17 +/- 80 200 SPDW-50015 Water 2/10/2023 H-3 159 91 +/- 84 200 SPDW-50011 Water 2/9/2023 Sr-89 0.62 0.24 +/- 0.49 5

SPDW-50011 Water 2/9/2023 Sr-90 0.66

-0.02 +/- 0.30 SPDW-50018 Water 2/16/2023 Gr. Alpha 0.62 0.01 +/- 0.44 2

SPDW-50018 Water 2/16/2023 Gr. Beta 0.78

-0.10 +/- 0.54 4

SPDW-50020 Water 2/17/2023 H-3 154 122 +/- 80 200 SPDW-50031 Water 2/16/2023 Ra-228 0.82 0.42 +/- 0.43 2

SPDW-50046 Water 2/24/2023 Ra-226 0.03 0.05 +/- 0.04 2

SPDW-50044 Water 3/13/2023 1-131 0.15

-0.06 +/- 0.08 SPDW-50048 Water 3/17/2023 H-3 163 80 +/-80 200 SPDW-50055 Water 3/24/2023 H-3 169 63 +/- 82 200 SPDW-50059 Water 3/16/2023 Ra-226 0.04

-0.02 +/- 0.03 2

SPDW-50063 Water 3/28/2023 Ra-226 0.06

-0.01 +/- 0.05 2

SPDW-50067 Water 4/14/2023 H-3 173 92 +/- 87 200 SPDW-50069 Water 4/17/2023 1-131 0.11

-0.05 +/- 0.08 SPDW-50102 Water 5/15/2023 1-131 0.15

-0.01 +/- 0.08 SPDW-50103 Water 5/12/2023 H-3 161 67 +/- 80 200 SPDW-50116 Water 5/26/2023 H-3 161 122 +/- 87 200 a Liquid sample results are reported in pCi/Liter, air filters ( pCi/m3}, 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-8

TABLE A-4. lntralaboratory "Blank" Samples Concentration a Lab Codeb Sample Date Analysisc Laboratory results (4.66cr)

Acceptance Type LLD Activitl Criteria (4.66 cr)

SPDW-50137 Water 6/12/2023 H-3 157 125 +/- 80 200 SPDW-50154 Water 6/26/2023 H-3 157 105 +/- 80 200 SPDW-50181 Water 6/8/2023 Ra-226 0.04

-0.07 +/- 0.03 2

SPDW-50218 Water 8/15/2023 Sr-89 0.66

-0.07 +/- 0.48 5

SPDW-50218 Water 8/15/2023 Sr-90 0.55 0.02 +/- 0.26 1

SPDW-50248 Water 8/22/2024 Gr. Alpha 0.57

-0.03 +/- 0.40 2

SPDW-50248 Water 8/22/2024 Gr. Beta 0.70 0.28 +/- 0.50 4

SPDW-50256 Water 8/25/2023 H-3 161 75 +/- 84 200 SPDW-50258 Water 7/19/2023 Ra-226 0.06

-0.25 +/- 0.04 2

SPDW-50270 Water 9/6/2023 H-3 160 90 +/- 81 200 SPDW-50282 Water 9/25/2023 H-3 163 53 +/- 79 200 SPDW-50290 Water 8/28/2023 Ra-226 0.05 0.00 +/- 0.04 2

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).

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

d Activity reported is a net activity result.

A-9

TABLE A-5. lntralaboratory "Duplicate" Samples Concentrationa Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance AP-100321 A/B 10/3/2022 Gr. Beta 0.015 +/- 0.003 0.011 +/- 0.003 0.013 +/- 0.002 Pass S0-3140,3141 10/3/2022 Be-7 0.353 +/- 0.180 0.304 +/- 0.163 0.328 +/- 0.121 Pass S0-3140,3141 10/3/2022 K-40 11.2 +/- 0.6 11.0 +/- 0.6 11.1 +/- 0.4 Pass S0-3140,3141 10/3/2022 Cs-137 0.055 +/- 0.016 0.069 +/- 0.020 0.062 +/- 0.013 Pass S0-3140,3141 10/3/2022 Tl-208 0.132 +/- 0.022 0.114 +/- 0.024 0.123 +/- 0.016 Pass S0-3140,3141 10/3/2022 Bi-214 0.315 +/- 0.041 0.390 +/- 0.041 0.353 +/- 0.029 Pass S0-3140,3141 10/3/2022 Pb-212 0.344 +/- 0.029 0.357 +/- 0.029 0.351 +/- 0.020 Pass S0-3140,3141 10/3/2022 Pb-214 0.362 +/- 0.043 0.446 +/- 0.047 0.404 +/- 0.032 Pass S0-3140,3141 10/3/2022 Ra-226 0.602 +/- 0.250 0.768 +/- 0.248 0.685 +/- 0.176 Pass S0-3140,3141 10/3/2022 Ac-228 0.442 +/- 0.101 0.405 +/- 0.083 0.423 +/- 0.066 Pass S0-3140,3141 10/3/2022 Gr. Alpha 4.07 +/- 1.77 4.43 +/- 2.17 4.25 +/- 1.40 Pass S0-3140,3141 10/3/2022 Gr. Beta 15.6 +/- 1.6 17.0+/-1.5 16.3 +/- 1.1 Pass AP-101021A/B 10/10/2022 Gr. Beta 0.037 +/- 0.005 0.040 +/- 0.005 0.039 +/- 0.004 Pass S-3501,3502 10/18/2022 K-40 16.3 +/- 1.2 16.3 +/- 1.3 16.3 +/- 0.9 Pass AP-101821A/B 10/18/2022 Gr. Beta 0.026 +/- 0.003 0.027 +/- 0.003 0.026 +/- 0.002 Pass DW-40328,40329 10/25/2022 Ra-226 2.13 +/-0.18 2.17 +/- 0.28 2.15 +/-0.17 Pass AP-102621 A/B 10/26/2022 Gr. Beta 0.051 +/- 0.005 0.047 +/- 0.005 0.049 +/- 0.003 Pass SG-3557,3558 11/1/2022 Gr. Alpha 24.5 +/- 4.0 25.0 +/- 4.0 24.8 +/- 2.8 Pass SG-3557,3558 11/1/2022 Gr. Beta 26.7 +/- 2.2 29.3 +/- 2.3 28.0 +/- 1.6 Pass SG-3557,3558 11/1/2022 Pb-214 9.23 +/- 0.15 9.23 +/- 0.32 9.23 +/- 0.18 Pass SG-3557,3558 11/1/2022 Ac-228 7.35 +/- 0.31 8.26 +/- 0.63 7.81 +/- 0.35 Pass AP-110221A/B 11/2/2022 Gr. Beta 0.020 +/- 0.003 0.020 +/- 0.003 0.020 +/- 0.002 Pass DW-40341,40342 11/7/2022 Ra-226 1.18 +/- 0.15 0.89 +/- 0.14 1.04 +/- 0.10 Pass DW-40341,40342 11/7/2022 Ra-228 1.98 +/- 0.95 3.32 +/- 1.12 2.65 +/- 0.73 Pass AP-110921A/B 11/9/2022 Gr. Beta 0.025 +/- 0.003 0.025 +/- 0.003 0.025 +/- 0.002 Pass AP-111621A/B 11/16/2022 Gr. Beta 0.013 +/- 0.002 0.015 +/- 0.002 0.014 +/- 0.002 Pass AP-112321A/B 11/23/2022 Gr. Beta 0.034 +/- 0.004 0.031 +/- 0.004 0.032 +/- 0.003 Pass AP-113021A/B 11/30/2022 Gr. Beta 0.056 +/- 0.005 0.058 +/- 0.005 0.057 +/- 0.003 Pass SG-4016,4017 12/5/2022 Gr. Alpha 24.5 +/- 4.0 25.0 +/- 4.0 24.7 +/- 2.9 Pass SG-4016,4017 12/5/2022 Gr. Beta 26.7 +/- 2.2 29.3 +/- 2.3 28.0 +/- 1.6 Pass SG-4016,4017 12/5/2022 Pb-214 8.64 +/- 0.30 9.28 +/- 0.30 8.96 +/- 0.21 Pass SG-4016,4017 12/5/2022 Ac-228 10.8 +/- 0.8 10.0 +/- 0.8 10.4 +/- 0.6 Pass AP-120721A/B 12/7/2022 Gr. Beta 0.034 +/- 0.003 0.030 +/- 0.003 0.032 +/- 0.002 Pass DW-40375,40376 12/14/2022 Ra-228 5.05 +/- 0.96 7.15 +/- 1.09 6.10 +/-0.73 Pass DW-40375,40376 12/14/2022 Ra-226 3.33 +/- 0.27 4.28 +/- 0.29 3.81 +/- 0.20 Pass AP-121621A/B 12/16/2022 Gr. Beta 0.039 +/- 0.004 0.033 +/- 0.004 0.036 +/- 0.003 Pass AP-122721 A/B 12/27/2022 Gr. Beta 0.018 +/- 0.002 0.016 +/- 0.002 0.017 +/- 0.001 Pass W-21,22 12/27/2022 Ra-226 0.99 +/- 0.29 1.52 +/- 0.34 1.26 +/- 0.22 Pass AP-122821A/B 12/28/2022 Gr. Beta

0. 042 +/- 0. 003 0.039 +/- 0.003 0.041 +/-0.002 Pass A-10

TABLE A-5. lntralaboratory "Duplicate" Samples Concentration 8

Averaged Lab Codeb Date Analysis First Result Second Result Result Acceptance WW-65,66 1/10/2023 Gr. Beta 15.4 +/- 2.0 17.2+/-2.1 16.3 +/- 1.5 Pass WW-107,108 1/18/2023 H-3 153 +/- 88 132 +/- 87 143 +/- 62 Pass SG-187, 188 1/30/2023 Gr. Alpha 28.1 +/- 3.9 22.0 +/- 3.5 25.1 +/-2.6 Pass SG-187, 188 1/30/2023 Gr. Beta 22.3 +/- 1.8 22.2 +/- 1.8 22.3 +/- 1.3 Pass SG-187, 188 1/30/2023 Pb-214 4.08+/-0.16 3.38 +/- 0.09 3.73 +/- 0.09 Pass SG-187, 188 1/30/2023 Ac-228 3.88 +/- 0.28 3.98 +/- 0.14 3.93 +/- 0.16 Pass SWU-201,202 1/31/2023 H-3 171 +/- 89 234 +/- 92 203 +/- 64 Pass SW-243,244 2/7/2023 H-3 358 +/- 98 262 +/- 93 310 +/- 68 Pass PW-266,267 2/6/2023 Ra-226 0.61 +/-0.18 0.37 +/- 0.20 0.49 +/- 0.13 Pass DW-50028.50029 2/27/2023 Ra-226 0.68+/-0.13 0.76 +/-0.13 0.72 +/- 0.09 Pass DW-50028.50029 2/27/2023 Ra-228 2.26 +/- 0.65 1.20 +/- 0.65 1.73 +/- 0.46 Pass DW-50052,50053 2/27/2023 Ra-228 0.48 +/- 0.57 1.19 +/- 0.65 0.84 +/- 0.43 Pass DW-50035,50036 2/28/2023 Gr. Alpha 3.68 +/- 1.42 4.00 +/- 1.29 3.84 +/- 0.96 Pass DW-50035,50036 2/28/2023 Gr. Beta 2.50 +/- 0.64 1.99 +/- 0.64 2.25 +/- 0.45 Pass LW-518,519 3/8/2023 Gr. Beta 1.71 +/- 0.64 1.38 +/- 0.64 1.55 +/- 0.45 Pass SG-571,572 3/8/2023 Pb-214 7.80 +/- 0.46 8.20 +/- 0.35 8.00 +/- 0.29 Pass SG-571,572 3/8/2023 Ac-228 11.9 +/- 0.8 11.4 +/- 0.6 11.7 +/- 0.5 Pass SG-571.572 3/8/2023 Gr. Alpha 86.5 +/- 10.6 89.6+/-11.0 88.1 +/- 7.6 Pass DW-50052,50053 3/17/2023 Gr. Alpha 9.16+/-1.02 14.7 +/- 1.2 11.9 +/- 0.8 Pass DW-50052,50053 3/17/2023 Gr. Beta 6.03 +/- 0.71 7.58 +/- 0.75 6.81 +/- 0.52 Pass CF-700,701 3/22/2023 K-40 2.91 +/- 0.32 3.30 +/- 0.36 3.11 +/- 0.24 Pass SW-679,680 3/27/2023 H-3 14,480 +/- 389 14,487 +/- 389 14,484 +/- 275 Pass SG-974,975 4/4/2023 Gr. Alpha 12.0 +/-2.1 12.1 +/- 2.1 12.1 +/- 1.5 Pass DW-5007 4,50075 4/21/2023 Ra-226 1.63 +/- 0.22 1.56 +/- 0.28 1.60 +/- 0.18 Pass DW-5007 4,50075 4/21/2023 Ra-228 3.41 +/-0.98 2.14 +/- 0.80 2.78 +/- 0.63 Pass U-1038, 1039 4/20/2023 Gr. Beta 6.14+/-1.71 6.46 +/- 2.19 6.30 +/- 1.39 Pass WW-1101, 1102 4/25/2023 H-3 358 +/- 96 334 +/- 95 346 +/- 68 Pass DW-50092,50093 5/1/2023 Ra-226 1.00 +/- 0.22 1.46 +/- 0.19 1.23 +/- 0.15 Pass DW-50092,50093 5/1/2023 Ra-228 1.11 +/-0.73 1.57 +/- 0.82 1.34 +/- 0.55 Pass WW-1122, 1123 5/2/2023 H-3 307 +/- 93 229 +/- 89 268 +/- 64 Pass WW-1269,1270 5/17/2023 H-3 366 +/- 100 214 +/- 92 290 +/- 68 Pass DW-50110,50111 5/29/2023 Ra-226 6.27 +/- 0.40 4.77 +/- 0.26 5.52 +/- 0.24 Pass DW-50110,50111 5/29/2023 Ra-228 2.81 +/- 0.97 3.53 +/- 0.98 3.17 +/- 0.69 Pass SW-1356, 1357 5/30/2023 H-3 380 +/- 94 257 +/- 88 319 +/- 64 Pass WW-1398, 1399 5/24/2023 H-3 571 +/- 103 613+/-105 592 +/- 74 Pass SG-1377,1378 5/30/2023 Pb-214 1.07+/-0.14 1.19 +/- 0.15 1.13 +/- 0.10 Pass SG-1377,1378 5/30/2023 Ac-228 1.23 +/- 0.28 1.11 +/- 0.23 1.17 +/- 0.18 Pass A-11

TABLE A-5. lntralaboratory "Duplicate" Samples Concentration 8

Averaged Lab Codeb Date Analysis First Result Second Result Result DW-50124,50125 6/5/2023 Ra-226 0.25 +/- 0.08 0.24 +/- 0.09 0.25 +/- 0.06 DW-50126,50127 6/5/2023 Gr. Alpha 2.50 +/- 1.17 3.87 +/- 1.39 3.19 +/- 0.91 WW-1441,1442 6/6/2023 Gr. Beta 2.55 +/- 0.64 1.91 +/- 0.67 2.23 +/- 0.46 SW-1483,1484 6/8/2023 H-3 281 +/- 90 281 +/- 90 281 +/- 64 CF-1546,1547 6/12/2023 K-40 7.77 +/- 0.34 7.48 +/- 0.48 7.63 +/- 0.29 S-1567, 1568 6/14/2023 K-40 9.75 +/- 0.71 9.80 +/- 0.77 9.78 +/- 0.52 WW-1630,1631 6/6/2023 H-3 319 +/- 93 236 +/- 89 278 +/- 64 F-1945, 1946 6/26/2023 K-40 3.81 +/- 0.34 3.22 +/- 0.54 3.52 +/- 0.32 DW-50157,50158 6/26/2023 Gr. Beta 0.93 +/- 0.59 1.09 +/- 0.06 1.01 +/- 0.30 DW-50160,50161 7/5/2023 Ra-226 2.63 +/- 0.32 2.77 +/- 0.27 2.70 +/- 0.21 DW-50160,50161 7/5/2023 Ra-228 2.46 +/- 0.78 2.51 +/- 0.81 2.49 +/- 0.56 DW-50188,50189 7/21/2023 Ra-226 3.07 +/- 0.30 2.63 +/- 0.20 2.85+/-0.18 DW-50188,50189 7/21/2023 Ra-228 5.28 +/- 0.92 5.08 +/- 0.90 5.18+/-0.64 DW-50197,50198 7/24/2023 Gr. Alpha 5.82 +/- 1.50 5.78 +/- 1.30 5.80 +/- 0.99 DW-50200,50201 7/24/2023 Ra-226 2.51 +/- 0.24 4.07 +/- 0.29 3.29 +/- 0.19 DW-50200,50201 7/24/2023 Ra-228 7.04 +/- 1.13 6.55 +/- 1.09 6.80 +/- 0.79 SG-2199,2200 7/25/2023 Pb-214 1.18 +/- 0.22 1.03 +/-0.19 1.11 +/- 0.15 SG-2199,2200 7/25/2023 Ac-228 1.74 +/- 0.32 1.86 +/- 0.42 1.80 +/- 0.26 SG-2315,2316 8/3/2023 Gr. Alpha 59.5 +/- 6.7 48.2 +/- 6.1 53.9 +/- 4.5 SG-2315,2316 8/3/2023 Gr. Beta 39.8 +/- 2.9 34.4 +/- 2.6 37.1 +/- 1.9 DW-50200,50201 8/9/2023 Ra-228 1.88 +/- 0.71 1.29 +/- 0.70 1.59 +/- 0.50 DW-50262,50263 8/24/2023 Ra-228 2.62 +/- 0.87 1.46 +/- 0.52 2.04 +/- 0.51 DW-50262,50263 8/24/2023 Ra-228 2.62 +/- 0.87 2.8 +/- 0.67 2.71 +/- 0.55 DW-50262,50263 8/24/2023 Ra-228 2.62 +/- 0.87 1.73 +/- 0.67 2.18+/-0.55 DW-50268,50269 8/29/2023 Gr. Alpha 0.87 +/- 0.69 0.97 +/- 0.81 0.92 +/- 0.53 SG-2660,2661 9/4/2023 Gr. Alpha 68.5 +/- 7.1 51.0 +/- 6.3 59.8 +/- 4.7 SG-2660,2661 9/4/2023 Pb-214 13.7 +/- 0.5 14.2 +/- 0.5 14.0 +/- 0.4 SG-2660,2661 9/4/2023 Ac-228 14.4 +/- 0.8 14.3 +/- 0.9 14.4 +/- 0.6 W-2776,2777 9/18/2023 Gr. Alpha 1.86 +/- 1.73 0.99 +/- 1.64 1.43 +/- 1.19 W-2776,2777 9/18/2023 Ra-226 0.43 +/- 0.10 0.55 +/- 0.27 0.49 +/- 0.14 W-2776,2777 9/18/2023 Ra-228 1.71 +/- 1.07 3.33 +/- 1.12 2.52 +/- 0.77 DW-50296,50297 9/27/2023 Ra-226 0.51 +/- 0.09 0.54 +/- 0.20 0.53 +/- 0.11 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).

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

Acceptance Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass Pass 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), U (Urine), VE (Vegetation), W (Water), WW (Well Water).

A-12

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

Concentration a Reference Known Acceptance Lab Code b Date Analysis Laboratory result Activity Range c Acceptance MADW-2613 8/1/2022 Gross Alpha 1.39 +/-0.10 0.90 0.27 - 1.53 Pass MADW-2613 8/1/2022 Gross Beta 1.69 +/- 0.04 1.31 0.66 - 1.97 Pass MAS0-2737 8/1/2022 Cs-134 523 +/- 5 627 439 - 815 Pass MAS0-2737 8/1/2022 Cs-137 1.18+/-2.21 0

NA C Pass MAS0-2737 8/1/2022 Co-57 715 +/- 6 786 550 - 1022 Pass MAS0-2737 8/1/2022 Co-60

-0.04 +/- 1.07 0

NA C Pass MAS0-2737 8/1/2022 Mn-54 903 +/- 11 841 589 - 1093 Pass MAS0-2737 8/1/2022 Zn-65 1227 +/- 19 1140 798 - 1482 Pass MAS0-2737 8/1/2022 K-40 595 +/- 37 537 376 - 698 Pass MADW-2733 8/1/2022 Cs-134 13.6 +/- 0.3 17.1 12.0 - 22.2 Pass MADW-2733 8/1/2022 Cs-137 16.0 +/- 0.4 16.8 11.8-21.8 Pass MADW-2733 8/1/2022 Co-57 27.5 +/- 0.4 30.0 21.0 - 39.0 Pass MADW-2733 8/1/2022 Co-60 14.4 +/- 0.3 17.0 11.9 - 22.1 Pass MADW-2733 8/1/2022 Mn-54

-0.03 +/- 0.10 0

NA C Pass MADW-2733 8/1/2022 Zn-65 11.5+/-0.6 11.3 7.9 - 14.7 Pass MADW-2733 8/1/2022 K-40 3.88 +/- 1.51 0

NA C Pass MADW-2733 8/1/2022 Sr-90 6.79 +/- 0.32 7.73 5.41 -10.05 Pass MAAP-2735 8/1/2022 Cs-134

-0.001 +/- 0.029 0

NA C Pass MAAP-2735 8/1/2022 Cs-137 1.76 +/- 0.11 1.53 1.07-1.99 Pass MAAP-2735 8/1/2022 Co-57 3.50 +/- 0.07 3.32 2.32 - 4.32 Pass MAAP-2735 8/1/2022 Co-60 2.11 +/- 0.08 1.99 1.39 - 2.59 Pass MAAP-2735 8/1/2022 Mn-54 2.18+/-0.13 1.88 1.32 - 2.44 Pass MAAP-2735 8/1/2022 Zn-65 1.83 +/- 0.22 1.58 1.11 -2.05 Pass MAVE-2740 8/1/2022 Cs-134 0.01 +/- 0.06 0

NA C Pass MAVE-2740 8/1/2022 Cs-137 1.15+/-0.12 1.083

0. 758 - 1.408 Pass MAVE-2740 8/1/2022 Co-57

-0.003 +/- 0.035 0

NA C Pass MAVE-2740 8/1/2022 Co-60 4.71 +/- 0.14 4.62 3.23 - 6.01 Pass MAVE-2740 8/1/2022 Mn-54 2.67 +/- 0.19 2.43 1.70 -3.16 Pass MAVE-2740 8/1/2022 Zn-65 7.73 +/- 0.39 7.49 5.24 - 9.74 Pass MAAP-544 2/1/2023 Gross Alpha 1.23 +/- 0.10 0.97 0.29 - 1.65 Pass MAAP-544 2/1/2023 Gross Beta 1.67 +/- 0.06 1.49 0.75 - 2.24 Pass MADW-543 2/1/2023 Gross Alpha 0.843 +/- 0.074 1.19 0.36 - 2.02 Pass MADW-543 2/1/2023 Gross Beta 0.578 +/- 0.093 5.94 2.97 - 8.91 Fail ct A-13

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

Concentration a Reference Known Acceptance Lab Code b Date Analysis Laboratory result Activity Range c Acceptance MAS0-540 2/1/2023 Cs-134 2.33 +/- 2.77 0

NA C Pass MAS0-540 2/1/2023 Cs-137 1.22 +/- 2.41 0

NA C Pass MAS0-540 2/1/2023 Co-57 585 +/-4 698 489 - 907 Pass MAS0-540 2/1/2023 Co-60 727 +/- 8 795 557 - 1034 Pass MAS0-540 2/1/2023 Mn-54 1180 +/- 10 1230 861 - 1599 Pass MAS0-540 2/1/2023 Zn-65 846 +/- 11 990 693 - 1287 Pass MAS0-540 2/1/2023 K-40 526 +/- 23 574 402 - 746 Pass MADW-545 2/1/2023 Cs-134 9.17 +/- 0.17 9.6 6.7 - 12.5 Pass MADW-545 2/1/2023 Cs-137 9.38 +/- 0.29 8.7 6.1 - 11.3 Pass MADW-545 2/1/2023 Co-57

-0.01 +/- 0.08 0.0 NAC Pass MADW-545 2/1/2023 Co-60 7.47 +/-0.18 7.24 5.07 - 9.41 Pass MADW-545 2/1/2023 Mn-54 12.3 +/- 0.3 11.3 7.9 - 14.7 Pass MADW-545 2/1/2023 Zn-65 15.7 +/- 0.5 15.3 10.7-19.9 Pass MADW-545 2/1/2023 K-40 1.23 +/- 1.52 0

NAC Pass MADW-545 2/1/2023 Sr-90

-0.0035 +/- 0.0172 0

NAC Pass MAAP-538 2/1/2023 Cs-134 1.12 +/- 0.04 1.52 1.06 - 1.98 Pass MAAP-538 2/1/2023 Cs-137 0.56 +/- 0.07 0.630 0.441 - 0.819 Pass MAAP-538 2/1/2023 Co-57 0.62 +/- 0.30 0.661 0.463 - 0.859 Pass MAAP-538 2/1/2023 Co-60 0.89 +/- 0.07 1.05 0.74 - 1.37 Pass MAAP-538 2/1/2023 Mn-54 2.02 +/- 0.09 2.14 1.50 - 2.78 Pass MAAP-538 2/1/2023 Zn-65 2.13 +/- 0.14 2.25 1.58 - 2.93 Pass MAAP-538 2/1/2023 Sr-90 0.004 +/- 0.061 0

NA C Pass MAVE-545 2/1/2023 Cs-134 7.45 +/- 0.39 7.60 5.32 - 9.88 Pass MAVE-545 2/1/2023 Cs-137 0.010 +/- 0.084 0

NAC Pass MAVE-545 2/1/2023 Co-57 6.83 +/- 0.17 6.93 4.85 - 9.01 Pass MAVE-545 2/1/2023 Co-60 6.89+/-0.17 6.51 4.56 - 8.46 Pass MAVE-545 2/1/2023 Mn-54 9.08 +/- 0.28 8.03 5.62 - 10.44 Pass MAVE-545 2/1/2023 Zn-65 7.83 +/- 0.39 7.43 5.20 - 9.66 Pass a Results are reported in units of Bq/kg (soil), Bq/L (water) or Bq/total sample (filters, vegetation).

b Laboratory codes as follows: MAW (water), 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 an acceptance range.

ct A decimal point was misplaced in a unit conversion. If the conversion was was done properly the result: 5. 78 +/- 0.93 Bq/L woud have been within MAPEP's acceptance range.

A-14

TABLE A-7. lnterlaboratory Comparison Crosscheck Program, Environmental Resource Associates (ERA) 8 MRAD-38 Study Concentration a Lab Code b Date Analysis Laboratory ERA Acceptance Result Value c Limits d Acceptance ERAP-599 3/20/2023 Cs-134 139 153 99 - 188 Pass ERAP-599 3/20/2023 Cs-137 970 892 733 - 1170 Pass ERAP-599 3/20/2023 Co-60 474 467 397 - 593 Pass ERAP-599 3/20/2023 Mn-54

< 3.3

< 35.0 0.00 - 35.0 Pass ERAP-599 3/20/2023 Zn-65 1280 1110 910 -1700 Pass ERAP-599 3/20/2023 Sr-90 143 137 87 - 187 Pass ERAP-598 3/20/2023 Gross Alpha 72.7 76.8 40.1 -127 Pass ERAP-598 3/20/2023 Gross Beta 35.0 32.8 19.9 - 49.6 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).

c 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-15

APPENDIX B.

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

2.0. Single Measurements Each single measurement is reported as follows:

x +/- s where:

x = value of the measurement; s = 2cr counting uncertainty (corresponding to the 95% confidence level).

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

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

3.1 Individual results: For two analysis results; x1 +/- s1 and x2 +/- s2 Reported result:

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

3.2.

3.3.

Individual results:

< L1, < L2 Individual results:

x +/- s, < L Reported result: < L, where L = lower of L1 and L2 Reported result:

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

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

1 X =n Ix

- -0l. (x- ~ )2 s -

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

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

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

4.5 In rounding off, the following rules are followed:

4.5.1.

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

4.5.2.

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

B-1

.POINT BEACH NUCLEAR PLANT APPENDIX C Sampling Program and Locations

POINT BEACH NUCLEAR PLANT Locations Collection Type Analysis Sample Type No.

Codes (and Type)8 (and Frequencyt (and Frequencyt Airborne Filters 6

E-1-4, 8, 20 Weekly GB, GS, on QC for each location Airborne Iodine 6

E-1-4, 8, 20 Weekly 1-131 Ambient Radiation 22 E-1-9, 12, 14-18, 20, Quarterly Ambient Gamma (TLD's) 22-32, 34-36, 38,39 Lake Water 5

E-1, 5, 6, 33 Monthly GB, GS, 1-131 on MC H-3, Sr-89-90 on QC Well Water 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 1

E-13 2x I year GS (in edible portions) as available a Locations codes are defined in Table 2. Control Stations are indicated by (C). All other stations are indicators.

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

MC = monthly composite, QC = quarterly composite.

C-2

.POINT BEACH NUCLEAR PLANT APPENDIX D Graphs of Data Trends 0-1

POINT BEACH Air Particulates - Gross Beta Location E-1, monthly averages 2019-2023 0.050 -

0.040 0.030 C()

E -

0 0.020

0.

0.010 0.000 -t l i I I f I I I I I I I I I I I I I l I I I I I I I I I I I l f I l $ ! ! l l ! i l l ! I I f I I I l I l I I I I I g 2019 2020 2021 2022 2023 2024 Year Location E-2, monthly averages 2019-2023 0.050 C()

E

i 0.020 4--+---l+i~-~-._---~..;,r:._ ___ _:.~_..---~"--~--;-'--

0. 000 -..+-~-i-++-+++......+-+--+-+-+-+++-i-++-+-+-l--++-!--++-l--++-+-+-t--+-+++-l-++-i!-t-i--+-!-+-++-+--t-t-t-£ 2019 2020 2021 2022 2023 2024 Year D-2

POINT BEACH Air Particulates - Gross Beta Location E-3, monthly averages 2019-2023 0.050 0.040

(") 0.030 E

. 0.020

()

0.

0.010 0.000 2019 2020 2021 2022 2023 2024 Year Location E-4, monthly averages 2019-2023 0.050 0.040

(") 0.030 E

. 0.020

()

0.

0.010 0.000 2019 2020 2021 2022 2023 2024 Year D-3

POINT BEACH Air Particulates - Gross Beta Location E-8, monthly averages 2019-2023 0.050 0.040 CV) 0.030 E -u 0.020

a.

0.010 0.000 4-+-+

1-1-++i ~~.~~I I I I I I~ f I II I I I I I I I I I I!

2019 2020 2021 2022 2023 2024 Year Location E-20, monthly averages 2019-2023 0.050 0.040 +---------------------

("") 0.030 -1.;.....,.,,,.........----,.:..+----~'--',------,:..-+-,-----;---~>-+---~~

~

~ 0. 020 -l--\\--iliN~---"""----'~--"----"'.,.....'-----Jll<. ___ ;.,:__ __

-",,F ____ -\\-'-

0. 010 ----'--------------------

0, 000.-+-+-+-+-+-+-+-+--+-+++-+++--1 I I I I I I j I I I 1 l 1 I I l I l j I I 1 I l I I I I l ! ! I l 1 l 1 1 1 l I I I a 2019 2020 2021 2022 2023 2024 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 1Z-361A GW-091Z-361B GW-10 2Z-361A GW-10 2Z-361B Collection Date 02-28-23 02-28-23 02-28-23 02-28-23 Lab Code EWW-482 MDC EWW-483 MDC EWW-484 MDC EWW-485 MDC Be-7

-15.1 +/- 13.1

< 27.9 2.0 +/- 11.1

< 15.1

-8.8 +/- 19.7

< 34.6 3.0 +/- 16.8

< 28.6 Mn-54

-0.3 +/- 1.5

< 1.9

-0.4 +/- 1.4

< 1.6

-0.5 +/- 2.0

< 3.7 0.5 +/- 1.9

< 3.7 Fe-59

-6.0 +/- 3.0

< 5.3

-1.7 +/- 2.6

< 5.0 1.6 +/- 3.7

< 8.3 2.8 +/- 3.6

< 7.4 Co-58

-0.5 +/- 1.4

< 1.9 0.2 +/- 1.3

< 1.6

-0.8 +/- 2.0

< 3.6

-0.8 +/- 1.7

< 3.9 Co-60 0.6 +/- 1.6

< 2.1 0.5 +/- 1.4

< 1.7 0.4 +/- 2.5

< 4.5 1.0 +/- 2.0

< 4.0 Zn-65

-1.5 +/- 3.3

< 5.5

-2.6 +/- 2.5

< 3.0 2.8 +/- 3.3

< 4.1

-3.9 +/- 3.8

< 6.1 Zr-Nb-95

-3.5 +/- 1.6

< 2.3

-0.9 +/- 1.4

< 2.1

-3.5 +/- 2.7

< 5.6

-3.3 +/- 1.7

< 3.5 Cs-134

-0.5 +/- 1.6

< 3.0 0.6 +/- 1.4

< 2.5

-1.0 +/- 2.2

< 3.7

-1.9+/-1.7

< 3.5 Cs-137

-0.3 +/- 1.7

< 2.0 2.0 +/- 1.4

< 1.7 0.9 +/- 2.7

< 4.7 1.3 +/- 1.9

< 3.7 Ba-La-140 1.8 +/- 1.8

< 1.3 1.3 +/- 1.6

< 3.6

-4.3 +/- 2.5

< 6.3

-0.1 +/- 2.1

< 4.9 Location GW-09 1Z-361A GW-09 1Z-361 B GW-10 2Z-361A GW-10 2Z-361B Collection Date 05-02-23 05-02-23 05-02-23 05-02-23 Lab Code EWW-1122 MDC EWW-1124 MDC EWW-1125 MDC EWW-1126 MDC Be-7

-5.7 +/- 16.4

< 29.7

-10.0 +/- 13.3

< 17.3

-8.2 +/- 16.3

< 24.0

-1.8+/-7.3

< 14.4 Mn-54 1.2 +/- 1.9

< 3.8 0.8 +/- 1.6

< 2.1 1.0 +/- 1.9

< 3.2 0.4 +/- 0.9

< 1.5 Fe-59 0.1 +/- 3.5

< 6.2 1.3 +/- 3.1

< 5.7 2.8 +/- 3.4

< 8.5

-0.9 +/- 1.6

< 3.4 Co-58 1.9+/-1.7

< 3.4

-0.5 +/- 1.5

< 1.8

-0.1 +/- 1.6

< 2.6

-0.9 +/- 0.8

< 1.4 Co-60

-0.8 +/- 2.1

< 3.3 1.7 +/- 1.7

< 2.1 0.6 +/- 2.2

< 3.3 1.2 +/- 0.9

< 2.1 Zn-65 1.6 +/- 3.8

< 6.9 2.0 +/- 3.0

< 4.4 2.8 +/- 3.9

< 7.5

-0.4 +/- 1.7

< 2.6 Zr-Nb-95 0.6 +/- 1.8

< 2.9

-1.2 +/- 1.6

< 2.1

-3.0 +/- 1.8

< 2.5

-0.2 +/- 1.6

< 2.1 Cs-134

-0.6 +/- 1.8

< 3.6 0.1 +/- 1.7

< 3.0

-0.4 +/- 1.8

< 3.7

-0.5 +/- 0.9

< 1.6 Cs-137

-1.1+/-2.0

< 2.7 0.2 +/- 1.8

< 2.2

-0.2 +/- 2.0

< 3.2 1.2 +/- 1.1

< 1.9 Ba-La-140

-2.6 +/- 2.2

< 4.1

-4.0 +/- 2.1

< 2.7

-4.4 +/- 2.5

< 5.3

-0.1 +/- 1.0

< 2.0 GW-09 1Z-361A GW-09 1Z-361B GW-10 2Z-361A GW-10 2Z-361B Collection Date 07-25-23 07-25-23 07-25-23 07-25-23 Lab Code EWW-2343 MDC EWW-2344 MDC EWW-2345 MDC EWW-2346 MDC Be-7

-4.7 +/- 13.0

< 21.7 18.1 +/- 12.3

< 41.5 3.1 +/- 11.0

< 32.4 4.3 +/- 11.2 19.5 Mn-54

-0.3 +/- 1.5

< 1.8 0.1 +/- 1.6

< 3.2 0.2 +/- 1.2

< 2.6 0.7 +/- 1.3 1.6 Fe-59

-4.0 +/- 3.2

< 7.8

-3.1 +/- 3.3

< 7.7

-2.0 +/- 2.3

< 3.3 0.4 +/- 2.6 7.0 Co-58

-1.6 +/- 1.5

< 2.3 1.2 +/- 1.5

< 3.0

-0.2 +/- 1.1

< 2.8

-1.1 +/- 1.3 1.9 Co-60 2.5 +/- 1.6

< 2.1

-1.2 +/- 1.7

< 2.1 4.6 +/- 1.4

< 5.0

-0.6 +/- 1.6 1.9 Zn-65

-1.2+/-3.0

< 3.6

-4.7 +/- 3.6

< 5.8

-1.4 +/-2.5

< 4.4

-5.5 +/- 3.0 3.3 Zr-Nb-95

-2.6 +/- 1.6

< 3.3 0.2 +/- 1.6

< 4.1

-0.4 +/- 1.2

< 4.3

-0.8 +/- 2.3 3.3 Cs-134

-0.5 +/- 1.5

< 2.9

-1.2 +/- 1.5

< 2.8

-0.2 +/- 1.2

< 2.4

-1.0+/-1.5 2.8 Cs-137

-2.9 +/- 1.8

< 1.9

-1.0+/-1.7

< 2.4 4.1 +/- 1.4

< 4.0

-0.4 +/- 1.5 1.7 Ba-La-140

-8.9 +/- 2.1

< 10.2

-2.3 +/- 2.0

< 14.6

-3.8 +/- 1.4

< 13.0

-4.8 +/- 1.7 10.1 E-2

POINT BEACH NUCLEAR PLANT Location GW-09 12-361A GW-09 12-3618 GW-10 22-361A GW-10 22-3618 Collection Date 10-02-23 10-02-23 10-02-23 10-02-23 Lab Code EWW-3999 MDC EWW-4000 MDC EWW-4001 MDC EWW-4002 MDC Be-7

-21.5 +/- 10.5

< 43.2 6.4 +/- 7.3

< 44.5 8.2 +/- 8.8

< 62.3 13.8 +/-5.9

< 41.9 Mn-54 2.3 +/- 1.2

< 2.7 0.3 +/- 0.9

< 2.5

-0.3 +/- 1.1

< 2.9 0.1 +/- 0.7

< 1.9 Fe-59 1.5 +/- 2.3

< 20.0 2.7 +/- 1.5

< 15.4

-0.2 +/- 2.0

< 14.2 0.3 +/- 1.2

< 11.4 Co-58 1.0 +/- 1.2

< 6.4

-0.4 +/- 0.8

< 2.2

-1.4 +/- 1.1

< 4.6 1.1 +/- 0.7

< 3.0 Co-60 1.1 +/- 1.3

< 2.2 1.6 +/- 0.9

< 2.2 0.6 +/- 1.1

< 2.5 0.1 +/- 0.9

< 1.9 2n-65

-2.2 +/- 2.5

< 6.8 1.5 +/- 1.7

< 4.3

-1.2 +/-2.2

< 4.6 0.0 +/- 1.5

< 4.0 2r-Nb-95

-16.5 +/- 1.5

< 13.5

-4.5 +/- 1.0

< 12.9

-11.4 +/- 1.3

< 17.1

-5.6 +/- 0.8

< 10.9 Cs-134 0.4 +/- 1.4

< 3.2

-0.6 +/- 0.9

< 1.8

-1.4 +/- 1.1

< 2.2 0.0 +/- 0.8

< 1.4 Cs-137 0.0 +/- 1.5

< 2.5 1.4 +/- 1.0

< 2.0

-1.1 +/- 1.3

< 2.1 1.7+/-0.9

< 1.7 Ba-La-140

-320.1 +/- 1.5

< 314.1 a

8.1 +/- 1.0

< 333.0 a

-7.9+/-1.4

< 283.7 a -170.4 +/- 0.9

< 340.5 a LLD not reached due to late arrival and small sample size. Samples received on 1/4/24 E-3

POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: = pCi/L Gamma isotopic analysis Location GW-04 GW-18 U2FSSDS Collection Date 01-18-23 01-18-23 01-31-23 Lab Code EW-109 MDC EW-113 MDC EW-225 MDC Be-7 5.8 +/- 19.9

< 26.5 7.0 +/- 14.1

< 26.3

-3.7 +/- 7.7

< 14.1 Mn-54

-1.6 +/- 3.1

< 5.1 1.4 +/- 1.5

< 3.0 1.0 +/- 1.0

< 1.8 Fe-59

-6.8 +/- 6.6

< 4.1

-1.5 +/- 3.1

< 4.1

-0.7 +/- 1.7

< 3.4 Co-58

-2.5 +/- 2.6

< 4.4

-0.6 +/- 1.5

< 2.5

-0.9 +/- 0.9

< 1.6 Co-60

-1.9 +/- 3.2

< 4.5

-0.5 +/- 2.2

< 6.2 0.4 +/- 1.0

< 1.9 Zn-65 4.8 +/- 6.1

< 7.7

-2.5 +/- 3.9

< 6.6

-1.4 +/- 1.8

< 3.2 Zr-Nb-95

-3.3 +/- 2.9

< 2.9

-2.4 +/- 1.8

< 2.3

-1.9 +/- 1.0

< 2.5 Cs-134

-1.0 +/- 3.1

< 5.2 1.1 +/- 1.6

< 3.1

-0.3 +/- 1.0

< 1.6 Cs-137

-0.1 +/- 3.5

< 3.7

-1.1 +/- 2.3

< 5.6 0.4 +/- 1.1

< 1.9 Ba-La-140

-1.7 +/- 3.4

< 1.8

-0.8 +/- 1.7

< 2.1

-0.7 +/- 1.1

< 2.8 Location S-3 GW-04 GW-15A,8 Collection Date 02-09-23 02-15-23 02-10-23 Lab Code EW-268 MDC EW-346 MDC EW-279 MDC Be-7

-9.3 +/- 17.9

< 21.8 8.3 +/- 9.8

< 20.1

-5.1 +/- 7.5

< 18.4 Mn-54

-0.5+/-1.5

< 2.7 1.1 +/- 1.3

< 2.9 0.1 +/- 0.9

< 1.6 Fe-59 0.3 +/- 3.5

< 4.5 1.9 +/- 2.5

< 4.1

-1.2+/-1.6

< 2.9 Co-58

-0.6 +/- 2.0

< 3.0 1.1 +/- 1.3

< 2.5 0.4 +/- 0.9

< 1.4 Co-60

-0.3 +/- 1.0

< 1.4

-0.6 +/- 1.3

< 2.1 1.3 +/- 1.0

< 2.2 Zn-65

-1.2 +/- 3.4

< 2.2

-2.7 +/- 3.0

< 4.7

-0.6 +/- 1.9

< 3.8 Zr-Nb-95

-1.9 +/- 1.9

< 4.5 0.5 +/- 1.3

< 2.4

-2.2 +/- 1.1

< 2.5 Cs-134 0.8 +/- 1.8

< 3.5

-2.5 +/- 1.3

< 2.3

-0.4 +/- 0.9

< 1.7 Cs-137 0.0 +/- 1.0

< 2.0

-1.2 +/- 1.4

< 1.7 1.4 +/- 1.1

< 2.0 Ba-La-140

-1.0+/-1.7

< 1.9

-0.2 +/- 1.3

< 2.4

-1.0 +/- 1.1

< 2.7 Location U2FSSDS GW-04 U2FSSDS Collection Date 02-28-23 MDC 03-22-23 MDC 03-31-23 MDC Lab Code EW-342 EWW-606 EWW-894 Be-7

-1.9 +/- 12.8

< 23.9 3.8 +/- 15.6

< 29.1 4.5 +/- 12.3

< 19.3 Mn-54 2.1 +/- 1.5

< 2.2 0.2 +/- 1.8

< 3.1 1.0 +/- 1.6

< 2.0 Fe-59 3.3 +/- 2.7

< 7.8 0.7+/-1.1

< 3.3 2.5 +/- 2.7

< 6.6 Co-58

-1.3 +/- 1.5

< 2.6

-1.0 +/- 2.0

< 2.1

-1.2 +/- 1.4

< 1.9 Co-60 0.7 +/- 1.6

< 2.0 0.4 +/- 0.7

< 1.3

-0.4 +/- 1.8

< 2.2 Zn-65

-3.4 +/- 3.4

< 5.8

-2.0 +/- 5.0

< 8.3

-2.1 +/- 3.3

< 3.7 Zr-Nb-95

-3.0 +/- 1.6

< 3.9

-4.3 +/- 2.4

< 4.6 0.3 +/- 1.5

< 2.8 Cs-134 0.6 +/- 1.5

< 3.0

-2.4 +/- 1.9

< 4.0

-1.3 +/- 1.6

< 3.0 Cs-137

-0.1 +/- 1.8

< 2.2 1.3 +/- 0.6

< 1.3 1.1 +/- 1.8

< 2.2 Ba-La-140 0.4+/-1.8

< 13.9

-1.0 +/- 1.9

< 2.4

-8.1 +/- 2.1

< 6.1 E-4

POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: = pCi\\L Gamma isotopic analysis Location GW-18 GW-04 GW-15A,B Collection Date 04-13-23 04-19-23 04-27-23 Lab Code EW-883 MDC EW-953 MDC EW-1115 MDC Be-7

-1.3 +/- 23.9

< 41.3

-1.1 +/- 4.0

< 8.8

-12.0 +/- 15.4

< 28.2 Mn-54

-1.3 +/- 3.3

< 5.4 0.6 +/- 6.2

< 1.3 1.4 +/- 1.8

< 4.1 Fe-59

-1.0 +/- 7.7

< 10.5

-0.8 +/- 1.2

< 1.8

-1.9 +/- 3.4

< 8.2 Co-58

-0.2 +/- 3.6

< 5.3 0.4 +/- 0.6

< 1.2 0.7 +/- 1.7

< 3.4 Co-60

-1.8 +/- 4.1

< 4.3 0.5 +/- 0.7

< 1.1 0.6 +/- 2.0

< 2.5 Zn-65

-3.6 +/- 7.8

< 7.8 0.7+/-1.2

< 2.6

-2.1 +/- 3.9

< 6.1 Zr-Nb-95

-0.2 +/- 3.3

< 5.5

-0.2 +/- 0.6

< 1.1

-3.4 +/- 1.8

< 2.6 Cs-134 0.2 +/- 3.2

< 5.1

-0.1 +/-0.6

< 1.0

-0.6 +/- 1.7

< 3.6 Cs-137 0.2 +/- 3.9

< 3.5 0.6 +/- 0.6

< 1.3 1.3 +/- 2.0

< 4.0 Ba-La-140

-3.2 +/- 4.5

< 4.9 0.5 +/- 0.7

< 1.5

-1.2 +/-2.0

< 2.7 Location U2FSSDS GW-04 U2FSSDS Collection Date 04-30-23 05-17-23 05-31-23 Lab Code EW-1151 MDC EW-1272 MDC EW-1481 MDC Be-7

-11.5+/-12.7

< 17.5 5.8 +/- 7.3

< 18.7 16.2 +/- 18.0

< 38.6 Mn-54 0.9 +/- 1.5

< 2.1

-0.4 +/- 1.1

< 1.3 0.9 +/- 2.1

< 4.6 Fe-59

-2.6 +/- 2.8

< 5.4

-1.6 +/- 1.8

< 3.3

-1.0 +/- 3.8

< 9.4 Co-58

-0.6 +/- 1.4

< 1.6 0.4 +/- 1.0

< 1.3 0.7 +/- 1.7

< 3.5 Co-60

-0.7 +/- 1.5

< 1.7 1.1 +/- 1.4

< 1.7 0.7 +/- 2.2

< 4.6 Zn-65

-2.3 +/- 3.1

< 3.4

-1.4 +/- 2.3

< 2.5 2.7 +/- 4.2

< 8.3 Zr-Nb-95

-0.1 +/- 2.6

< 2.0 0.7 +/- 1.2

< 2.8

-0.8 +/- 1.9

< 3.7 Cs-134

-0.8 +/- 1.6

< 3.0

-1.0 +/- 1.1

< 2.1

-1.0 +/- 1.9

< 3.9 Cs-137 0.3+/-1.7

< 1.9 1.0 +/- 1.3

< 2.6

-0.7 +/- 2.2

< 3.8 Ba-La-140 2.7 +/- 1.7

< 3.4

-1.6 +/- 1.3

< 2.3 1.4 +/-2.3

< 8.3 Location GW-07 GW-04 U2FSSDS Collection Date 05-18-23 06-21-23 06-30-23 Lab Code EW-1278 MDC EW-1644 MDC EW-2545 l)

MDC Be-7

-6.2 +/- 16.3

< 31.0

-8.5 +/- 15.2

< 21.9

-1.7 +/- 13.1

< 33.2 Mn-54

-2.4 +/- 2.1

< 2.6

-2.8 +/- 3.7

< 2.8 1.2 +/- 1.5

< 2.0 Fe-59

-0.4 +/- 3.1

< 2.8

-0.5 +/- 3.9

< 8.0

-9.1 +/- 3.1

< 11.9 Co-58 1.2 +/- 2.2

< 4.6 1.8 +/- 1.7

< 2.7

-0.3 +/- 1.5

< 3.4 Co-60 0.7 +/- 2.2

< 3.9 1.4+/-2.0

< 2.5 1.0 +/- 1.6

< 2.1 Zn-65 0.2 +/- 4.7

< 4.3 0.3 +/- 3.5

< 4.5

-2.0 +/- 3.2

< 3.9 Zr-Nb-95

-3.2 +/- 2.2

< 3.1 0.3 +/- 1.8

< 3.1

-3.0 +/- 2.8

< 6.8 Cs-134

-0.7 +/- 1.9

< 3.7 0.0 +/- 1.9

< 3.9

-0.2 +/- 1.5

< 3.0 Cs-137 0.2 +/- 1.9

< 3.4

-0.9 +/- 2.1

< 2.2

-0.6 +/- 1.8

< 2.3 Ba-La-140

-3.7 +/- 2.5

< 5.8 3.8 +/- 4.0

< 4.8

-15.4 +/- 2.0

< 64.1 Unable to reach LLD due to late sample arrival.

E-5

POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: = pCi\\L Gamma isotopic analysis Location GW-18 GW-04 GW-15A,B Collection Date 07-19-23 07-19-23 07-19-23 Lab Code EW-2097 MDC EW-2098 MDC EW-2193 MDC Be-7 5.9 +/- 21.9

< 21.9

-13.7 +/- 29.8

< 51.8 26.7 +/- 12.3

< 21.2 Mn-54

-1.5 +/- 3.2

< 5.6

-0.2 +/- 3.5

< 5.5 1.0 +/- 1.5

< 1.9 Fe-59 1.4 +/- 5.7

< 9.9 5.2 +/- 6.1

< 8.1

-4.7 +/- 3.1

< 6.3 Co-58

-1.3 +/- 2.9

< 4.8

-2.3 +/- 4.8

< 8.5

-2.0 +/- 1.4

< 1.9 Co-60

-0.2 +/- 2.6

< 4.0 0.3 +/- 3.8

< 4.1 0.4 +/- 1.6

< 2.1 Zn-65

-5.8 +/- 7.0

< 5.0

-0.8 +/- 9.7

< 10.4 3.3 +/- 3.1

< 3.6 Zr-Nb-95 1.3+/-2.7

< 5.0

-3.5 +/- 4.6

< 9.6

-0.6 +/- 2.5

< 2.8 Cs-134

-1.9+/-2.8

< 4.6

-6.0 +/- 4.2

< 6.7

-1.5 +/- 1.6

< 2.9 Cs-137 1.3 +/- 2.7

< 5.0 0.9 +/- 4.2

< 4.5 0.4 +/- 1.7

< 2.1 Ba-La-140 1.0 +/- 3.4

< 5.8 3.6 +/- 4.4

< 4.5

-3.8 +/- 1.7

< 5.3 Location U2FSSDS GW-04 U2FSSDS Collection Date 07-31-23 08-22-23 08-31-23 Lab Code EW-2342 MDC EW-2515 MDC EW-2676 MDC Be-7

-2.2 +/- 23.9

< 51.2

-18.0 +/- 15.7

< 18.8 0.4 +/- 1.3

< 18.1 Mn-54 1.1 +/- 2.4

< 4.2 0.7 +/- 1.8

< 3.0 1.4 +/- 1.5

< 2.0 Fe-59 0.7 +/- 4.5

< 4.5

-3.2 +/- 4.0

< 2.7

-3.6 +/- 2.9

< 5.9 Co-58

-1.7 +/- 2.4

< 4.5

-0.1 +/- 1.7

< 2.2 1.4 +/- 1.4

< 2.0 Co-60 4.0 +/- 3.0

< 9.7 0.7 +/- 1.9

< 6.3

-0.3 +/- 1.8

< 2.0 Zn-65

-0.8 +/- 5.8

< 10.0

-1.2 +/- 4.0

< 4.4

-2.4 +/- 3.5

< 3.9 Zr-Nb-95

-0.8 +/- 2.6

< 7.3

-0.2 +/- 1.7

< 1.5

-1.9 +/- 1.6

< 2.5 Cs-134

-1.4 +/- 2.4

< 4.8

-0.3 +/- 1.5

< 3.3

-2.4 +/- 1.6

< 2.7 Cs-137 5.1 +/- 3.0

< 8.0 1.8 +/- 2.1

< 5.0 1.1 +/- 1.6

< 1.9 Ba-La-140

-7.0 +/- 2.8

< 10.8 1.5 +/- 2.2

< 3.1 0.0 +/- 1.8

< 3.9 Location GW-04 U2FSSDS GW-18 Collection Date 09-21-23 09-30-23 10-10-23 Lab Code EW-2794 MDC EW-4057 MDC EW-3075 MDC a

Be-7 14.3 +/- 38.1

< 51.0

-4.0 +/- 14.2

< 102.8

-16.4 +/- 17.7

< 21.7 Mn-54

-1.7 +/- 5.9

< 6.2

-1.7+/-1.5

< 2.7 0.3 +/- 1.7

< 2.9 Fe-59 3.7+/-11.7

< 8.9 6.4 +/- 2.9

< 27.0

-3.1 +/- 3.3

< 1.6 Co-58 0.9 +/- 4.5

< 5.1 2.0 +/- 1.4

< 6.7

-0.8 +/- 1.5

< 1.8 Co-60 1.8 +/- 3.9

< 5.0 2.8 +/- 1.7

< 5.8 3.8 +/- 2.7

< 6.5 Zn-65

-8.9 +/- 9.9

< 6.7

-7.3 +/- 3.6

< 7.0 1.7 +/- 4.1

< 4.4 Zr-Nb-95 1.4 +/- 5.0

< 5.9

-35.7 +/- 1.6

< 17.2

-0.2 +/- 2.1

< 3.3 Cs-134

-3.3 +/- 4.3

< 7.1

-3.7 +/- 1.6

< 3.3

-1.2 +/- 2.0

< 3.7 Cs-137

-0.8 +/- 5.8

< 5.3 3.5 +/- 1.8

< 5.1 4.1 +/- 2.4

< 5.6 Ba-La-140

-4.8 +/- 6.6

< 4.8

-199.4 +/- 1.7

< 1070.1

-1.7 +/- 2.3

< 2.4 a Unable to reach LLD due to small sample size and late arrival to the lab. Sample counted between 60K and 80K seconds.

E-6

POINT BEACH NUCLEAR PLANT Supplemental Analyses Units: = pCi\\L Gamma isotopic analysis Location GW-04 U2FSSDS GW-04 Collection Date 10-18-24 10-31-23 11-14-23 Lab Code EW-3229 MDC EW-4059 MDC EW-3544 MDC a

Be-7

-9.6 +/- 21.0

< 20.7 28.6 +/- 10.9

< 64.9 6.4 +/- 9.6

< 20.7 Mn-54 1.7 +/- 2.5

< 4.3 0.8 +/- 1.3

< 3.3 0.3 +/- 1.3

< 2.3 Fe-59 2.4 +/- 4.4

< 3.4 0.3 +/- 2.5

< 17.8 2.4 +/- 2.6

< 6.2 Co-58 0.5 +/- 2.0

< 1.9 0.7 +/- 1.4

< 4.7

-1.8 +/- 1.4

< 2.0 Co-60 1.8+/-2.3

< 7.3 0.3 +/- 1.4

< 2.8

-0.3 +/- 1.5

< 2.3 Zn-65

-5.3 +/- 6.1

< 4.6

-4.8 +/- 2.6

< 5.0 0.7 +/- 2.6

< 4.6 Zr-Nb-95

-1.6+/-2.3

< 2.0

-21.7 +/- 1.6

< 13.3

-0.1 +/- 1.5

< 2.8 Cs-134 0.9 +/- 2.1

< 4.3

-1.2 +/- 1.4

< 2.8

-1.0 +/- 1.2

< 2.2 Cs-137 4.6 +/- 2.8

< 7.0

-203.3 +/- 4.6

< 3.0 0.4 +/- 1.4

< 2.5 Ba-La-140 1.4 +/- 2.9

< 3.0 40.8 +/- 1.5

< 137.8

-0.2 +/- 3.8

< 6.8 Location U2FSSDS GW-15A,B GW-04 Collection Date 11-30-23 12-07-23 12-20-23 Lab Code EW-4060 MDC EW-3899 MDC EW-3946 MDC a

Be-7

-2.8 +/- 7.2

< 26.6 0.4 +/- 6.2

< 20.1

-3.0 +/- 6.8

< 9.4 Mn-54 0.6 +/- 0.9

< 1.8 0.2 +/- 0.8

< 1.6 0.3 +/- 1.0

< 1.5 Fe-59

-1.9 +/- 1.6

< 6.6 0.5 +/- 1.4

< 3.1

-1.3 +/- 2.1

< 2.9 Co-58

-0.5 +/- 0.8

< 1.4

-0.4 +/- 0.8

< 1.9 0.2 +/- 1.2

< 1.8 Co-60 0.7+/-1.0

< 2.1 0.3 +/- 0.8

< 1.8 2.1 +/- 1.2

< 2.2 Zn-65 0.4 +/- 1.8

< 3.3

-0.8 +/- 1.5

< 3.4

-1.4+/-2.4

< 3.2 Zr-Nb-95

-2.6 +/- 1.0

< 5.1

-3.5 +/- 0.9

< 2.4

-0.4 +/- 1.2

< 2.0 Cs-134 0.2 +/- 0.9

< 1.7

-0.4 +/- 0.8

< 1.5

-0.1 +/- 1.1

< 1.9 Cs-137 0.8 +/- 1.1

< 2.1 0.0 +/- 0.9

< 1.7 2.1 +/- 1.3

< 2.4 Ba-La-140 9.6 +/- 1.0

< 25.6

-3.2 +/- 0.9

< 4.7

-1.0 +/- 1.3

< 2.4 Location U2FSSDS Collection Date 12-31-23 Lab Code EW-4061 MDC Be-7 1.9 +/- 12.7

< 18.2 Mn-54 0.9 +/- 1.5

< 2.0 Fe-59 1.1 +/- 2.8

< 6.1 Co-58

-0.3 +/- 1.5

< 2.1 Co-60

-0.7 +/- 1.7

< 2.0 Zn-65 0.1 +/- 3.1

< 3.9 Zr-Nb-95

-2.1 +/- 1.5

< 3.8 Cs-134 1.4 +/- 1.6

< 2.8 Cs-137 0.1 +/- 1.6

< 1.7 Ba-La-140

-0.6 +/- 1.7

< 5.1 a Unable to reach LLD due to small sample size and late arrival to the lab. Sample counted between 60K and 80K seconds.

E-7

.POINT BEACH NUCLEAR PLANT APPENDIX F Special Analyses F-1

POINT BEACH NUCLEAR PLANT Additional Analyses Units pCi/L Location S-3 MDC S-7 MDC Collection Date 02-07-23 02-07-23 Lab Code EW-245 EW-246 Fe-55

-230.6 +/- 276. 7

< 476.6

-50.9 +/- 270.2

< 449.6 Ni-63

-7.70 +/- 44.5

< 73.5 4.20 +/- 41.4

< 68 Sr-89 0.20 +/- 0.4

< 0.50

-0.04 +/- 0.5

< 0.70 Sr-90

-0.05 +/- 0.2

< 0.50

-0.05 +/- 0.2

< 0.50 Tc-99 6.1 +/- 7.0

< 11.42

-3.1 +/- 3.4

< 5.70 Location E-006 MDC E-006 MDC Collection Date 04-12-23 04-20-23 Lab Code ELW-864 ELW-968 Fe-55 154.3 +/- 277. 7

< 443.9 Ni-63 1.22 +/- 45.2

< 74.4 Sr-89

-0.09 +/- 0.4

< 0.52 Sr-90 0.11 +/- 0.3

< 0.55 Tc-99 0.0 +/- 6.8

< 11.2 Location E-006 MDC Collection Date 04-20-23 Lab Code ELW-968 8

Gross beta 1.3 +/- 0.3

< 0.9 1-131

-0.01 +/- 0.22

< 0.49 Be-7 2.1 +/- 6.4

< 11.4 Mn-54

-0.5 +/- 0.8

< 1.9 Fe-59

-1.9 +/- 1.6

< 1.4 Co-58

-0.5 +/- 0.8

< 1.7 Co-60

-0.5 +/- 0.9

< 1.2 Zn-65

-0.7 +/- 1.7

< 3.2 Zr-Nb-95

-0.2 +/- 0.8

< 1.6 Cs-134

-0.2 +/- 0.8

< 1.5 Cs-137 0.1 +/- 0.9

< 1.5 Ba-La-140

-1.0 +/- 1.0

< 2.1 Other (Ru-103) 0.0 +/- 0.8

< 1.5 F-2

ATI Environmental, Inc.

r'\\.I Midwest Laboratory 700 Landwehr Road* N,c,rthbrcok, IL 60062-2310 phone (847} 564-0700

fs,c (847) 564-4517 Darren Peterson Radiation Protection Mgr.

Point Beach Nuclear Plant NextEraEnergy 6610 Nuclear Road Two Rivers, WI 54241 LABORATORY REPORT NO.:

8006-100-1506 SAMPLES RECEIVED:

04-04-23 PURCHASE ORDER NO.:

Below are the results of the readout of supplemental TLDs deployed during the first quarter, 2023.

Period:

Date Annealed:

Date Placed:

Date Removed:

Date Read:

Days in the Field:

Days from Annealing to Readout:

In-transit exposure:

Location SGSF-North SGSF-East SGSF-South SGSF-West ISFSI-North ISFSI-East ISFSI-South ISFSI-West Control Forrest G. Shaw Ill Quality Assurance Total mR 17.0 +/-0.6 16.4 +/-0.7 17.2 +/-0.4 16.9 +/-0.3 29.9 +/-0.9 44.8 +/- 1.5 38.1 +/- 1.3 88.2 +/-2.7 19.8 +/-0.8 NetmR 11.4 +/-0.7 10.8 +/-0.8 11.6 +/- 0;5 11.3 +/- 0.5 24.3 +/- 1.0 39.2 +/- 1.5 32.5 +/- 1.4 82.6 +/-2.7 14.3 +/-0.9 1st Quarter, 2023 12/06/22 01/04/23 04/02/23 04/05/23 NetmR Std Otr 11.8 +/-0.7 11.2 +/- 0.8 12.0 +/-0.5 11.7 +/-0.5 25.1 +/- 1.0 40.5 +/- 1.6 33.6 +/- 1.4 85.4 +/-2.8 14.7 +/- 0.9 APPROVED 88 120 5.59 +/-0.38 NetmR per7 days 0.91 +/-0.06 0.86 +/-0.06 0.92 +/-0.04 0.90 +/-0.04 1.93 +/- 0.08 3.12 +/- 0.12 2.58 +/-0.11 6.57 +/-0.22 1.13 +/- 0.07 Laboratory Manager

MICROBAC~

700 Landwehr Road

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

fax (847) 564-4517 Darren Peterson Radiation Protection Mgr.

Point Beach Nuclear Plant NextEraEnergy 661 O Nuclear Road Two Rivers, WI 54241 LABORATORY REPORT NO.:

SAMPLES RECEIVED:

PURCHASE ORDER NO.:

8006-100-1514 07-07-23 Below are the results of the readout of supplemental TLDs deployed during the second quarter, 2023.

Period:

Date Annealed:

Date Plaqed:

Date Removed:

Date Read:

Day~ in 1h.e Field:

Days f rorn Annealing to Readout:

In-transit exposure:

Location SGSF-North SGSF-East SGSF-South SGSF-West ISFSI-North ISFSI-East ISFSI-South ISFSI-West Control Total mR 17.8 +/-0.8 17.8 +/-0.3 17.3 +/-0.4 19.2 +/-0.5 34.6 +/- 1.8 50.5 +/-2.0 41.2 +/- 1.3 88.9 +/-5.3 23.3 +/- 1.1 E

~:,:zz_~ _ _ _

z...._21/23 Quality Assurance NetmR 12.9 +/-0.8 13,0 +/-0.5 12.5 +/-0.5 14.4 +/-0.6 29.8 +/- 1.8 45.7 +/-2.1 36.3 +/- 1.4 84.1 +/- 5.3 18.4 +/-1.1 Page 1 of 1 2nd Quarter, 2023 03/08/23 04/02/23 07/06/23 07/07/23 NetmR Std Qtr 12.4 +/- 0.8 12.4 +/- 0.4 11.9 +/- 0.5 13.8 +/-0.6 28.5 +/- 1.7 43.8 +/-2.0 34.8 +/- 1.3 80.5 +/-5.1 17.7+/-1.1 95 121 4.83 +/-0.34 NetmR per7 days 0.95.+/-0.06 0.96 +/- 0.03 0.92 +/-0.04 1.06 +/- 0.05 2.19 +/- 0.13 3.37 +/- 0.15 2.68 +/- 0.10 6.20 +/-0.39 1.36 +/-0.08 APPROVED -----1>..N,-~ 1/2.11/1-3 Ashok Banavali, Ph.D.

Laboratory Manager

MICROBAC 700 Landwehr Rqad

Northbroo1<1 IL 60062-2310 phone (847) 564-0700

fax (847) 564-4517 Darren Peterson Radiation Protection Mgr.

Point Beach Nuclear Plant NextEraEnergy 6610 Nuclear Road TwoAivers, WI 54241 LABORATORY REPORT NO.:

8006-100-1526 SAMPLES RECEIVED:

10-03-23 PURCHASE ORDER NO.:

Below are the results of the readout of supplemental TLDs deployed during the third q1,Jarter, 2023.

Period:

Date Annealed:

Date Placed:

Date Removed:

Date Read:

Days in the Field:

Days from Annealing to Readout:

In-transit exposure:

Location SGSF-North SGSF-East SGSF-South SGSF-West ISFSI-North ISFSI-East ISFSI-South ISFSI-West

-control Quality Assurance Specialist Total mR 16.8 +/- 0.6 16.0 +/- 0.7 16.6 ;1: 0.4 16.7 +/-0.4 29.0 +/- 0.8 46.2 +/-0.9 36.6 +/-.1.2 85.5 +/-2.6 19.8 +/- 0.8 NetmR 12.0 +/- 0.7 11.3 +/- 0.8 11.9 +/- 0.5 12.0 +/- 0.5 24.2 +/- 0.8 41.4 +/- 1.0 31.8 +/- 1.2 80.7 +/- 2.. 6 15.1 +/- 0.8 3rd Quarter, 2023 06/12/23 07/06/23 10/01/23 10/04/23 NetmR Std Qtr 12.6 +/- 0.7 11.8.+/- ().8 12.4 +/- 0.5 12.6 +/- 0.5 25.4 +/- 0.9 43.3 +/- 1.0 33.3 +/- 1.3 84.5 +/-2.8 15.8 +/-0.9 87 114 4.73 +/-0.33 NetmR per7 days 0.97 +/-0.05 0.91 +/- 0.06 0.96 +/- 0.04 0.97 +/- 0.04 1.95 +/- 0.0.7 3.33 +/- 0.08 2.56 +/- 0.10 6.50 +/-0.21 1.21 +/- 0.07 APPROVED~~~ Jf)/10/,:J Ashok Banavali, Ph.D.

Laboratory Director

fax (847) 564-4517 Rudi Prucha Senior Chemistry Analyst Point Beach Nuclear Plant NextEraEnergy 6610 Nuclear Road Two Rivers, WI 54241 LABORATORY REPORT NO.:

8006-100-1542 SAMPLES RECEIVED:

01-08-24 PURCHASE ORDER NO.:

Below are the results of the readout of supplemental TLDs deployed during the fourth quarter, 2023.

Period:

Date Annealed:

Date Placed:

Date Removed:

Date Read:

Days in the Field:

Days from Annealing to Readout:

In-transit exposure:

Location SGSF-North SGSF-East SGSF-South SGSF-West ISFSI-North ISFSI-East ISFSI-South ISFSI-West Control Quality Assurance Total mR 17.3 +/- 0.7 19.1 +/- 0.3 17.5 +/- 0.4 19.7 +/- 0.6 35.5 +/- 1.5 50.3 +/- 1.6 38.2 +/- 2.4 93.1 +/-3.8 23.3 +/- 1.0 NetmR 15.3 +/-0.7 17.0 +/- 0.4 15.4 +/- 0.4 17.6 +/- 0.6 33.4 +/- 1.5 48.2 +/- 1.6 36.1 +/-2.4 91.0 +/-3.8 21.2 +/- 1.0 4th Quarter, 2023 09/12/23 10/01/23 01/04/24 01/1 1/24 NetmR Std Otr 14.6 +/- 0.7 16.3 +/-0.4 14.8 +/- 0.4 16.8 +/- 0.6 32.0 +/- 1.4 46.2 +/- 1.5 34.6 +/-2.3 87.1 +/- 3.6 20.3 +/- 1.0 95 121 2.08 +/- 0.26 NetmR per 7 days 1.12 +/-0.05 1.25 +/- 0.03 1.14+/-0.03 1.30 +/- 0.05 2.46 +/- 0.11 3.55 +/- 0.12 2.66 +/-0.18 6.70 +/- 0.28 1.56 +/- 0.07 Ashok Banavali, Ph.D.

Laboratory Director

L-2024-067, Annual Monitoring Report

Contents

Text

Enclosure:

SUMMARY

1.0 INTRODUCTION

Reference:

8.0 INTRODUCTION

SUMMARY

1.0 INTRODUCTION

1.0 INTRODUCTION

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L-2024-067, Annual Monitoring Report

Text

Enclosure:

SUMMARY

1.0 INTRODUCTION

Reference:

8.0 INTRODUCTION

SUMMARY

1.0 INTRODUCTION

1.0 INTRODUCTION

Navigation menu

Search