ML25119A063

Annual Radioactive Effluent Release Report

ML25119A063
Person / Time
Site:	Surry
Issue date:	04/29/2025
From:	Terry W Virginia Electric & Power Co (VEPCO)
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
25-129
Download: ML25119A063 (1)

Text

VIRGINIA ELECT R I C AND POWER COMPANY RICHMOND, VIRGINIA 23261 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 2024 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Serial No.

SPS/MMT Docket Nos.

License Nos.25-129 RO 50-280 50-281 DPR-32 DPR-37 Enclosed is the Surry Power Station Annual Radioactive Effluent Release Report for January 1, 2024, through December 31, 2024. The report submitted pursuant to Surry Power Station Technical Specification 6.6.B.3, includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released during the 2024 calendar year, as outlined in Regulatory Guide 1.21, Revision 1, June 1974.

If you have any further questions, please contact Selma Spratley at 757-365-2551.

Sincerely, William Terry (Acting)

Director Nuclear Safety & Licensing Surry Power Station Attachment Commitments made in this letter: None cc:

U. S. Nuclear Regulatory Commission Region II Marquis One Tower ATTN: Division of Reactor Safety - Radiation Safety Branch 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector Surry Power Station April 29, 2025

ATTACHMENT Serial No.25-129 SPS Annual Rad Effluent Report Docket Nos. 50-280, 50-281 2024 Annual Radioactive Effluent Release Report Surry Power Station SURRY POWER STATION UNITS 1 AND 2 VIRGINIA ELECTRIC AND POWER COMPANY

2024 Annual Radioactive Effluent Release Report Surry Power Station

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR SURRY POWER STATION January 1, 2024 through December 31, 2024 Index Section No.

Subject Page 1

Executive Summary 1

2 Purpose and Scope 2

3 Discussion 3

4 Supplemental Information 4

5 Effluent Release Data 5 Effluent Release Data Annual and Quarterly Doses Revisions to Offsite Dose Calculation Manual (ODCM) Major Changes to Radioactive Liquid, Gaseous and Solid Waste Treatment Systems Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation Unplanned Releases Lower Limit of Detection (LLD) for Effluent Sample Analysis Industry Ground Water Protection Initiative

FORWARD This report is submitted as required by Appendix A to Operating License Nos. DPR-32 and DPR-37, Technical Specifications for Surry Power Station, Units 1 and 2, Virginia Electric and Power Company, Docket Nos. 50-280, 50-281, Section 6.6.B.3.

EXECUTIVE

SUMMARY

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT The Annual Radioactive Effluent Release Report describes the radiological effluent control program conducted at Surry Power Station during the 2024 calendar year. This document summarizes the quantities of radioactive liquid and gaseous effluents and solid waste released from Surry Power Station in accordance with Regulatory Guide 1.21, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants", Revision 1, June 1974. The report also includes an assessment of radiation doses to the maximum exposed member of the public due to the radioactive liquid and gaseous effluents.

During this reporting period, there were no unplanned liquid effluent releases and no unplanned gaseous effluent releases as classified according to the criteria in the Offsite Dose Calculation Manual.

Based on the 2024 effluent release data, 10CFR50 Appendix I dose calculations were performed in accordance with the Offsite Dose Calculation Manual. The dose calculations are as follows:

1. The total body dose due to liquid effluents was 5.62E-04 mrem, which is 9.37E-03% of the 6 mrem dose limit. The critical organ dose due to liquid effluents was 5.99E-04 mrem to the GI-LLI, which is 3.00E-03% of the 20 mrem dose limit.

2. The air dose due to noble gases in gaseous effluents was 2.49E-04 mrad gamma, which is 1.25E-03% of the 20 mrad gamma dose limit, and 9.14E-05 mrad beta, which is 2.29E-04% of the 40 mrad beta dose limit.

3. The critical organ dose from gaseous effluents due to I-131, I-133, H-3, and particulates with half-lives greater than 8 days is 9.77E-02 mrem to the bone, which is 3.26E-01% of the 30 mrem dose limit.

There were no major changes to the radioactive liquid, gaseous or solid waste treatment systems during this reporting period.

No changes were made the Offsite Dose Calculation Manual (ODCM), VPAP-2103S, during this reporting period.

In accordance with the Nuclear Energy Institute (NEI)

Industry Ground Water Protection Initiative, analysis results of ground water monitoring locations not included in the Radiological Environmental Monitoring Program (REMP), will be included in this report.

Ground water monitoring well sample results are provided in Attachment 8.

The operation of Surry Power Station in 2024 resulted in a negligible radiation dose consequence to the maximum exposed member of the public in unrestricted areas. This is based on measured radioactivity and dose calculations performed.

1

Purpose and Scope includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, with data summarized on a quarterly or annual basis following the format of Tables 1, 2 and 3 of Appendix B, thereof. Attachment 2 of this report includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during 2024.

As required by Technical Specification 6.8.B, changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this report are included in Attachment 3. Major changes to the radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, Section 6.7.2. If changes are made to these systems, the report shall include information to support the reason for the change and a summary of the 10CFR50.59 evaluation. In lieu of reporting major changes in this report, major changes to the radioactive waste treatment systems may be submitted as part of the annual FSAR update. identifies and explains why specific radioactive liquid and gaseous effluent monitoring instrumentation, as required by the ODCM in Attachments 1 and 5, was determined to be inoperable and not returned to operable status within 30 days. provides a list and description of unplanned releases from the site to unrestricted areas, during the reporting period, that meet the criteria listed in Step 6.7.3 of the ODCM. provides the typical lower limit of detection (LLD) capabilities of the radioactive effluent analysis instrumentation.

As required by the ODCM, Section 6.7.5, a summary is provided in Attachment 8 of on-site radioactive leaks or spills and ground water sample analyses that were communicated in accordance with the Industry Ground Water Protection Initiative reporting protocol.

Sample analyses from ground water wells that are not part of the Radiological Environmental Monitoring Program are also provided in Attachment 8.

2

Discussion The basis for the gaseous critical organ percent technical specification calculation, as documented on Attachment 1, Table 1A, is the ODCM. The requirements of Section 6.3.1 of the ODCM, are site boundary critical organ dose rate for iodine-131, iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days shall be less than or equal to 1500 mrem/yr. The maximum critical receptor was the child for the 1st and 2nd quarters and the teen for the 3rd and 4th quarters.

The basis for the calculation of the percent of technical specification for the total body and skin in Table 1A of Attachment 1 is the ODCM, Section 6.3.1, which requires that the dose rate for noble gases to areas at or beyond site boundary shall be less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin.

The basis for the calculation of the percent of technical specification in Table 2A of Attachment 1 is the ODCM, Section 6.2.1, which states that the concentration of radioactive material released in liquid effluents to unrestricted areas shall not exceed ten times the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.00E-04 microcuries/mL.

Percent of technical specification calculations are based on the total gaseous or liquid effluents released for the respective quarter.

The annual and quarterly doses, as reported in Attachment 2, were calculated according to the methodology presented in the ODCM. The beta and gamma air doses due to noble gases released from the site were calculated at the site boundary. The maximum exposed member of the public from the release of airborne iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days, was modeled as a child at 2.01 miles with the critical organ being the bone via the ingestion pathway. The maximum exposed member of the public from radioactive materials in liquid effluents in unrestricted areas was modeled as an adult, exposed by either the invertebrate or fish pathway, with the critical organ typically being the gastrointestinal-lower large intestine. The total body dose was also determined for this individual.

No effluent radiation monitors were inoperable for greater than 30 days in 2024. This is reported in Attachment 5 as required by the ODCM, Section 6.2.2 and 6.3.2.

There were no unplanned liquid releases and no unplanned gaseous releases in 2024. This is reported in Attachment 6 as required by the ODCM, Section 6.7.2.

3

The typical lower limit of detection (LLD) capabilities of the radioactive effluent analysis instrumentation are presented in Attachment 7. These LLD values are based upon conservative conditions (i.e., minimum sample volumes and maximum delay time prior to analysis). Actual LLD values may be lower. If a radioisotope was not detected when effluent samples were analyzed, then the activity of the radioisotope was reported as Not Detected (N/D) on Attachment 1 of this report. When all isotopes listed on Attachment 1 for a particular quarter and release mode are less than the lower limit of detection, then the totals for this period will be designated as Not Applicable (N/A).

Supplemental Information Section 6.6.1 of the ODCM requires the identification of the cause(s) for the unavailability of milk, or if required, leafy vegetation samples, and the identification for obtaining replacement samples. Milk samples were available for collection during this reporting period. Therefore, leafy vegetation sampling was not required.

As required by the ODCM, Section 6.6.2, evaluation of the Land Use Census is made to determine if new sample location(s) must be added to the Radiological Environmental Monitoring Program.

Evaluation of the Land Use Census conducted for this reporting period identified no change in sample locations for the Radiological Environmental Monitoring Program.

4 Discussion

EFFLUENT RELEASE DATA January 1, 2024 through December 31, 2024 provides a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, Appendix B.

5

TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/24 TO 12/31/24 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND

% EST. ERROR QUARTER QUARTER A. FISSION & ACTIVATION GASES

1. TOTAL RELEASE Ci 4.39E-02 3.48E-01 1.80E+01

2. AVE RELEASE RATE FOR PERIOD

µCi/sec 5.58E-03 4.43E-02 B. IODINE

1. TOTAL I-131 Ci N/D N/D 2.80E+01

2. AVE RELEASE RATE FOR PERIOD

µCi/sec N/A N/A C. PARTICULATE

1. HALF-LIFE >8 DAYS Ci N/D 6.07E-05 2.80E+01

2. AVE RELEASE RATE FOR PERIOD

µCi/sec N/A 7.72E-06

3. GROSS ALPHA RADIOACTIVITY Ci N/D N/D D. TRITIUM

1. TOTAL RELEASE Ci 5.59E+00 8.45E+00 3.10E+01

2. AVE RELEASE RATE FOR PERIOD

µCi/sec 7.11E-01 1.08E+00 E. CARBON-14

1. TOTAL RELEASE Ci 1.81E+00 1.44E+01

2. AVE RELEASE RATE FOR PERIOD

µCi/sec 2.30E-01 1.83E+00 PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE

95E-03 1.79E-03 TOTAL BODY DOSE RATE

E-0

4.62E-06 SKIN DOSE RATE

E-0

1.23E-06 Page 1 of 12

TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/24 TO 12/31/24 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH

% EST. ERROR QUARTER QUARTER A. FISSION & ACTIVATION GASES

1. TOTAL RELEASE Ci 1.09E-03 3.08E-02 1.80E+01

2. AVE RELEASE RATE FOR PERIOD

µCi/sec 1.37E-04 3.88E-03 B. IODINE

1. TOTAL I-131 Ci N/D N/D 2.80E+01

2. AVE RELEASE RATE FOR PERIOD

µCi/sec N/A N/A C. PARTICULATE

1. HALF-LIFE >8 DAYS Ci 9.06E-07 9.87E-06 2.80E+01

2. AVE RELEASE RATE FOR PERIOD

µCi/sec 1.14E-07 1.24E-06

3. GROSS ALPHA RADIOACTIVITY Ci N/D N/D D. TRITIUM

1. TOTAL RELEASE Ci 4.48E-02 1.27E+00 3.10E+01

2. AVE RELEASE RATE FOR PERIOD

µCi/sec 5.64E-03 1.60E-01 E. CARBON-14

1. TOTAL RELEASE Ci 1.79E+00 1.42E+01

2. AVE RELEASE RATE FOR PERIOD

µCi/sec 2.26E-01 1.79E+00 PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE 3.77E-04 2.81E-03 TOTAL BODY DOSE RATE 4.36E-06 3.28E-06 SKIN DOSE RATE 1.06E-06 8.41E-07 Page 2 of 12

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/24 TO 12/31/24 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER

1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D N/D N/D Kr-85m Ci N/D N/D N/D N/D Kr-87 Ci N/D N/D N/D N/D Kr-88 Ci N/D N/D N/D N/D Xe-133 Ci N/D N/D N/A 3.38E-01 Xe-135 Ci N/D N/D N/D 3.89E-03 Xe-135m Ci N/D N/D N/D N/D Xe-138 Ci N/D N/D N/D N/D Xe-131m Ci N/D N/D N/D N/D Xe-133m Ci N/D N/D N/D 5.64E-03 Ar-41 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A N/A 3.47E-01

2. IODINES I-131 Ci N/D N/D N/D N/D I-133 Ci N/D N/D N/D N/D I-135 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A N/A N/A

3. PARTICULATES Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci N/D 3.69E-08 N/D N/D Ba-140 Ci N/D N/D N/D N/D La-140 Ci N/D N/D N/D N/D Co-58 Ci N/D 7.38E-08 N/D N/D Co-60 Ci N/D N/D N/D N/D Mn-54 Ci N/D N/D N/D N/D Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci N/D N/D N/D N/D Ce-144 Ci N/D N/D N/D N/D C-14 Ci N/D N/D N/D 1.43E+01 TOTAL FOR PERIOD Ci N/A 1.11E-07 N/A 1.43E+01 Page 3 of 12

TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/24 TO 12/31/24 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER

1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D N/D N/D Kr-85m Ci N/D N/D N/D N/D Kr-87 Ci N/D N/D N/D N/D Kr-88 Ci N/D N/D N/D N/D Xe-133 Ci N/D N/D N/D 2.82E-02 Xe-135 Ci N/D N/D N/D 4.49E-04 Xe-135m Ci N/D N/D N/D N/D Xe-138 Ci N/D N/D N/D N/D Xe-131m Ci N/D N/D N/D N/D Xe-133m Ci N/D N/D N/D N/D Ar-41 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A N/A 2.86E-02

2. IODINES I-131 Ci N/D N/D N/D N/D I-133 Ci N/D N/D N/D N/D I-135 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A N/A N/A

3. PARTICULATES Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci N/D N/D N/D N/D Ba-140 Ci N/D N/D N/D N/D La-140 Ci N/D N/D N/D N/D Co-58 Ci 4.08E-10 N/D N/D N/D Co-60 Ci N/D N/D N/D N/D Mn-54 Ci N/D N/D N/D N/D Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci N/D N/D N/D N/D Ce-144 Ci N/D N/D N/D N/D C-14 Ci N/D N/D N/D 1.18E+00 TOTAL FOR PERIOD Ci 4.08E-10 N/A N/A 1.18E+00 Page 4 of 12

TABLE 1C EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/24 TO 12/31/24 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER

1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D N/D N/D Kr-85m Ci N/D N/D N/D N/D Kr-87 Ci N/D N/D N/D N/D Kr-88 Ci N/D N/D N/D N/D Xe-133 Ci N/D N/D N/D N/D Xe-135 Ci N/D N/D N/D N/D Xe-135m Ci N/D N/D N/D N/D Xe-138 Ci N/D N/D N/D N/D Xe-131m Ci N/D N/D N/D N/D Xe-133m Ci N/D N/D N/D N/D Ar-41 Ci 4.39E-02 9.75E-04 N/D N/D TOTAL FOR PERIOD Ci 4.39E-02 9.75E-04 N/A N/A

2. IODINES I-131 Ci N/D N/D N/D N/D I-133 Ci N/D N/D N/D N/D I-135 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A N/A N/A

3. PARTICULATES Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci N/D 1.64E-05 N/D N/D Ba-140 Ci N/D N/D N/D N/D La-140 Ci N/D N/D N/D N/D Co-58 Ci N/D 4.42E-05 N/D N/D Co-60 Ci N/D N/D N/D N/D Mn-54 Ci N/D N/D N/D N/D Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci N/D N/D N/D N/D Ce-144 Ci N/D N/D N/D N/D Nb-95 Ci N/D N/D N/D N/D Zr-95 Ci N/D N/D N/D N/D C-14 Ci 1.81E+00 4.02E-02 N/D N/D TOTAL FOR PERIOD Ci 1.81E+00 4.03E-02 N/A N/A Page 5 of 12

TABLE 1C EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/24 TO 12/31/24 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER

1. FISSION & ACTIVATION GASES Kr-85 Ci N/D N/D N/D N/D Kr-85m Ci N/D N/D N/D N/D Kr-87 Ci N/D N/D N/D N/D Kr-88 Ci N/D N/D N/D N/D Xe-133 Ci N/D N/D N/D 1.37E-03 Xe-135 Ci N/D N/D N/D 7.01E-05 Xe-135m Ci N/D N/D N/D N/D Xe-138 Ci N/D N/D N/D N/D Xe-131m Ci N/D N/D N/D N/D Xe-133m Ci N/D N/D N/D N/D Ar-41 Ci 1.09E-03 7.43E-04 N/D N/D TOTAL FOR PERIOD Ci 1.09E-03 7.43E-04 N/A 1.44E-03

2. IODINES I-131 Ci N/D N/D N/D N/D I-133 Ci N/D N/D N/D N/D I-135 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A N/A N/A

3. PARTICULATES Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci N/D N/D N/D N/D Ba-140 Ci N/D N/D N/D N/D La-140 Ci N/D N/D N/D N/D Co-58 Ci 9.05E-07 9.87E-06 N/D N/D Co-60 Ci N/D N/D N/D N/D Mn-54 Ci N/D N/D N/D N/D Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Ce-141 Ci N/D N/D N/D N/D Ce-144 Ci N/D N/D N/D N/D C-14 Ci 4.48E-02 3.07E-02 N/D 5.95E-02 TOTAL FOR PERIOD Ci 4.48E-02 3.07E-02 N/A 5.95E-02 Page 6 of 12

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/24 TO 12/31/24 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND

% EST. ERROR QUARTER QUARTER A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)

Ci 7.83E-04 2.51E-03 2.00E+01

2. AVE DIL. CONC. DURING PERIOD

µCi/mL 3.28E-13 1.40E-12

3. PERCENT OF APPLICABLE LIMIT 8.87E-07 2.53E-06 B. TRITIUM

1. TOTAL RELEASE Ci 3.75E+02 8.38E+02 2.00E+01

2. AVE DIL. CONC. DURING PERIOD

µCi/mL 1.57E-07 4.65E-07

3. PERCENT OF APPLICABLE LIMIT 1.57E-03 4.65E-03 C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE Ci N/D 2.38E-04 2.00E+01

2. AVE DIL. CONC. DURING PERIOD

µCi/mL N/A 1.32E-13

3. PERCENT OF APPLICABLE LIMIT N/A 6.62E-08 D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE Ci N/D N/D 2.00E+01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION)

LITERS 5.32E+07 5.43E+07 3.00E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 2.39E+12 1.80E+12 3.00E+00 Page 7 of 12

TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/24 TO 12/31/24 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH

% EST. ERROR QUARTER QUARTER A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)

Ci 1.27E-03 1.44E-03 2.00E+01

2. AVE DIL. CONC. DURING PERIOD

µCi/mL 4.16E-13 6.41E-13

3. PERCENT OF APPLICABLE LIMIT 1.04E-06 2.73E-06 B. TRITIUM

1. TOTAL RELEASE Ci 5.68E+01 4.63E+02 2.00E+01

2. AVE DIL. CONC. DURING PERIOD

µCi/mL 1.86E-08 2.06E-07

3. PERCENT OF APPLICABLE LIMIT 1.86E-04 2.06E-03 C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE Ci N/D 3.84E-06 2.00E+01

2. AVE DIL. CONC. DURING PERIOD

µCi/mL N/A 1.71E-15

3. PERCENT OF APPLICABLE LIMIT N/A 8.53E-10 D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE Ci N/D N/D 2.00E+01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION)

LITERS 5.38E+07 5.43E+07 3.00E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 3.06E+12 2.25E+12 3.00E+00 Page 8 of 12

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/24 TO 12/31/24 LIQUID EFFLUENTS SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Fe-55 Ci N/D N/D N/D N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci 1.17E-04 1.62E-04 3.88E-05 7.55E-05 I-131 Ci N/D N/D N/D N/D Co-58 Ci N/D N/D 1.24E-04 7.59E-04 Co-60 Ci N/D N/D 1.10E-04 4.36E-04 Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mn-54 Ci N/D N/D N/D N/D Cr-51 Ci N/D N/D N/D N/D Zr-95 Ci N/D N/D N/D N/D Nb-95 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Tc-99m Ci N/D N/D N/D N/D Ba-140 Ci N/D N/D N/D N/D La-140 Ci N/D N/D N/D N/D Ce-141 Ci N/D N/D N/D N/D Ce-144 Ci N/D N/D N/D N/D Sb-124 Ci N/D N/D N/D N/D Sb-125 Ci N/D N/D 3.94E-04 1.08E-03 Nd-147 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci 1.17E-04 1.62E-04 6.66E-04 2.35E-03 Xe-133 Ci N/D 2.38E-04 N/D N/D Xe-135 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A 2.38E-04 N/A N/A CONTINUOUS MODE BATCH MODE Page 9 of 12

TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/24 TO 12/31/24 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER Sr-89 Ci N/D N/D N/D N/D Sr-90 Ci N/D N/D N/D N/D Fe-55 Ci N/D N/D N/D N/D Cs-134 Ci N/D N/D N/D N/D Cs-137 Ci 1.60E-04 1.65E-04 8.33E-05 1.91E-04 I-131 Ci N/D N/D N/D N/D Co-58 Ci N/D N/D 2.30E-04 3.22E-04 Co-60 Ci N/D N/D 1.26E-04 1.01E-04 Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D N/D Mn-54 Ci N/D N/D N/D N/D Cr-51 Ci N/D N/D N/D N/D Zr-95 Ci N/D N/D N/D N/D Nb-95 Ci N/D N/D N/D N/D Mo-99 Ci N/D N/D N/D N/D Tc-99m Ci N/D N/D N/D N/D Ba-140 Ci N/D N/D N/D N/D La-140 Ci N/D N/D N/D N/D Ce-141 Ci N/D N/D N/D N/D Ce-144 Ci N/D N/D N/D N/D Sb-124 Ci N/D N/D N/D N/D Sb-125 Ci N/D N/D 6.75E-04 6.54E-04 Ci N/D 9.36E-06 N/D N/D Ci N/D N/D 7.32E-7 N/D Ci 1.60E-04 1.74E-04 1.11E-03 1.27E-03 Ci N/D N/D N/D 3.84E-06 Ci N/D N/D N/D N/D Nd-147 Co-57 TOTAL FOR PERIOD Xe-133 Xe-135 TOTAL FOR PERIOD Ci N/A N/A N/A 3.84E-06 Page 10 of 12 Page 11 of 12 TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT=

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS=

PERIOD: 1/1/24 - 12/31/24 SURRY POWER STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

1. Type of waste 12 month Est. Total Period Error, %

a. Spent resins, filter sludges, evaporator m3 1.14E+01 1.00E+01 bottoms, etc.

Ci 2.232E+02 3.00E+01

b. Dry compressible waste, contaminated m3 4.90E+02 1.00E+01 equip., etc.

Ci 1.77E+00 3.00E+01

c. Irradiated components, control m3 0.00E+00 1.00E+01 rods, etc.

Ci 0.00E+00 3.00E+01

d. Other m3 4.56E+00 1.00E+01 Ci 1.28E-03 3.00E+01 1.16E+00 3.46E+01 1.36E+00 3.04E+01 1.67E+01 2.10E+00 6.61E+00 4.91E+01 3.67E+00 6.18E+00 1.49E+00 7.40E+00 N/A

2. Estimate of major nuclide composition (by type of waste)

a. Fe-55 Co-58 Co-60 Ni-63 Cs-137

b. Cr-51 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Zr-95 Nb-95 Sb-125 Cs-137 Pu-241

c. N/A

d. H-3 1.08E+01 9.96E+01 3.20E+00 3.93E+00 2.46E+00 Note 1 Note 2 Note 3 Page 12 of 12 TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT=

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS=

PERIOD: 1/1/24 - 12/31/24 SURRY POWER STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

3. Solid Waste Disposition Mode of Transportation Truck Number of Shipments 16 1

3 Truck Destination EnergySolutions at Oak Ridge, TN (Bear Creek Operations)

EnergySolutions at Memphis, TN (Memphis Facility)

Erwin ResinSolutions, LLC B. IRRADIATED FUEL SHIPMENT (Disposition)

Mode of Transportation Destination Number of Shipments 0

Truck NOTE 1: Some of this waste was shipped to licensed waste processors for processing and/or volume reduction. Therefore, this volume is not representative of the actual volume buried. The total volume buried for this reporting period is 1.10E+01 m3.

NOTE 2: Some DAW was shipped to licensed waste processors for processing and/or volume reduction. Therefore, this volume is not representative of the actual volume buried. The total volume buried for this reporting period is 1.40E+02 m3.

NOTE 3: This waste was shipped to a licensed waste processor for processing and/or volume reduction. Therefore, this volume is not representative of the actual volume buried. The total volume buried for this reporting period is 0.00E+00 m3.

Page 1 of 1 ANNUAL AND QUARTERLY DOSES Total Body GI-LLI Liver (mrem)

(mrem)

(mrem) 1st Quarter 9.21E-05 9.57E-05 9.24E-05 2nd Quarter 3.01E-04 3.26E-04 3.01E-04 3rd Quarter 1.28E-05 1.64E-05 1.31E-05 4th Quarter 1.55E-04 1.61E-04 1.56E-04 Annual 5.62E-04 5.99E-04 5.63E-04 Gamma Beta (mrad)

(mrad) 1st Quarter 2.33E-04 8.22E-05 2nd Quarter 6.16E-06 4.66E-06 3rd Quarter 5.77E-06 2.04E-06 4th Quarter 4.38E-06 2.55E-06 Annual 2.49E-04 9.14E-05 Annual Maximum Child / Bone (mrem)

(mrem) 1st Quarter 2.52E-02 3.71E-02 2nd Quarter 6.53E-02 6.53E-02 3rd Quarter 6.24E-04 1.42E-03 4th Quarter 6.59E-03 1.06E-02 Annual 9.77E-02 Teen / Lung Teen / Lung Child / Bone Child / Bone Receptor / Organ Maximum by Quarter GASEOUS - Organ Dose 2024 2024 GASEOUS - Air Dose 2024 LIQUID Maximum Receptor - Adult An assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of this report, along with an annual total of each effluent pathway is made pursuant to the ODCM, Section 6.7.2, requirement.

Page 1 of 1 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM)

As required by Technical Specification 6.8.B, revisions to the ODCM, effective for the time period covered by this report, are included with this attachment. There were no revisions to the ODCM implemented during this reporting period.

Page 1 of 1 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS There were no major changes to the radioactive liquid, gaseous or solid waste treatment systems during the reporting period.

Page 1 of 1 INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION The Annual Radioactive Effluent Release Report shall explain why monitoring instrumentation required by Attachments 1 and 5 of the ODCM were determined to be inoperable and were not returned to operable status within 30 days.

No radiation monitors referenced on Attachment 1 and Attachment 5 of the ODCM were inoperable greater than 30 days during the reporting period.

Page 1 of 1 In accordance with the ODCM reporting requirements, no unplanned liquid releases or unplanned gaseous releases occurred during the reporting period.

UNPLANNED RELEASES Page 1 of 1 GASEOUS:

Isotope Required LLD Kr-87 1.00E-04 2.13E 1.95E-05 Kr-88 1.00E-04 8.81E 1.88E-05 Xe-133 1.00E-04 9.63E 4.06E-05 Xe-133m 1.00E-04 3.81E 4.06E-05 Xe-135 1.00E-04 4.51E 5.76E-06 Xe-135m 1.00E-04 1.38E 9.41E-05 Xe-138 1.00E-04 2.59E 9.90E-05 I-131 1.00E-12 4.06E 4.06E-13 I-133 1.00E-10 4.06E 4.06E-11 Sr-89 1.00E-11 1.04E 1.81E-12 Sr-90 1.00E-11 1.55E 4.71E-13 Cs-134 1.00E-11 2.45E 7.83E-13 Cs-137 1.00E-11 1.47E 8.48E-13 Mn-54 1.00E-11 3.89E 8.21E-13 Fe-59 1.00E-11 9.33E 2.01E-12 Co-58 1.00E-11 1.97E 9.65E-13 Co-60 1.00E-11 2.70E 1.16E-12 Zn-65 1.00E-11 3.89E 2.14E-12 Mo-99 1.00E-11 4.06E 4.06E-12 Ce-141 1.00E-11 1.83E 6.87E-13 Ce-144 1.00E-11 6.99E 3.06E-12 Alpha 1.00E-11 1.67E 1.67E-14 Tritium 1.00E-06 5.03E 5.77E-08 LIQUID:

Sr-89 5.00E-08 4.11E 4.12E-07 Sr-90 5.00E-08 6.81E 2.62E-08 Cs-134 5.00E-07 2.45E 3.46E-13 Cs-137 5.00E-07 1.47E 5.77E-13 I-131 1.00E-06 4.06E 4.06E-11 Co-58 5.00E-07 1.97E 5.06E-13 Co-60 5.00E-07 2.70E 7.54E-13 Fe-59 5.00E-07 9.33E 7.82E-13 Zn-65 5.00E-07 3.89E 1.18E-12 Mn-54 5.00E-07 3.89E 4.27E-13 Mo-99 5.00E-07 4.06E 4.06E-12 Ce-141 5.00E-07 1.83E 4.91E-13 Ce-144 5.00E-07 6.99E 1.88E-12 Fe-55 1.00E-06 1.83E 8.43E-07 Alpha 1.00E-07 2.43E 2.46E-08 Tritium 1.00E-05 1.24E 1.43E-06 Xe-133 1.00E-05 9.63E 1.48E-05 Xe-135 1.00E-05 4.51E 6.93E-06 Xe-133m 1.00E-05 3.81E 4.06E-05 Xe-135m 1.00E-05 1.38E 9.41E-05 Xe-138 1.00E-05 2.59E 9.90E-05 Kr-87 1.00E-05 2.13E 1.95E-05 Kr-88 1.00E-05 8.81E 2.05E-05 Typical LLD LOWER LIMIT OF DETECTION (LLD) FOR EFFLUENT SAMPLE ANALYSIS Page 1 of 4 The following is a summary of 2024 sample analyses of ground water monitoring wells that are not a part of the Radiological Environmental Monitoring Program (REMP).

Well Sample Tritium Gamma Fe-55 Ni-63 Sr-90 TRU Designation Date pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter 1-PL-Piez-47 1/4/24 11600 NA NA NA NA NA 1-PL-Piez-47 1/10/24 11600 NA NA NA NA NA 1-PL-Piez-49 1/10/24 1950 NA NA NA NA NA 1-PL-Piez-51 1/10/24 7180 NA NA NA NA NA 1-PL-Piez-44 1/11/24 2410 NA NA NA NA NA 1-PL-Piez-47 1/18/24 11100 NA NA NA NA NA 1-PL-Piez-05 1/24/24 2250 NA NA NA NA NA 1-PL-Piez-29 1/24/24 7450 NA NA NA NA NA 1-PL-Piez-44 1/24/24 780 NA NA NA NA NA 1-PL-Piez-47 1/24/24 10400 NA NA NA NA NA 1-PL-Piez-49 1/24/24 1020 NA NA NA NA NA 1-PL-Piez-51 1/24/24 6430 NA NA NA NA NA 1-PL-Piez-44 2/8/24 2220 NA NA NA NA NA 1-PL-Piez-47 2/8/24 10000 NA NA NA NA NA 1-PL-Piez-49 2/8/24 812 NA NA NA NA NA 1-PL-Piez-51 2/8/24 6810 NA NA NA NA NA 1-PL-Piez-47 2/22/24 10600 NA NA NA NA NA 1-PL-Piez-49 2/22/24 1340 NA NA NA NA NA 1-PL-Piez-51 2/22/24 6550 NA NA NA NA NA 1-PL-Piez-04 2/27/24 185 ND NA NA NA NA 1-PL-Piez-05 2/27/25 3190 ND

<38.03

<4.96

<.985 ND 1-PL-Piez-06 2/29/24

<1250 ND

<39.80

<4.43

<.924 ND 1-PL-Piez-43 2/29/24

<1240 ND NA NA NA NA 1-PL-Piez-50 2/29/24

<1250 ND NA NA NA NA 1-PL-Piez-25 2/29/24

<1240 NA NA NA NA NA 1-PL-Piez-07 3/4/24

<1240 ND NA NA NA NA 1-PL-Piez-27 3/4/24

<1250 NA NA NA NA NA 1-PL-Piez-45 3/4/24

<1240 ND

<51.20

<4.16

<.955 ND 1-PL-Piez-49 3/7/24 1760 NA NA NA NA NA 1-PL-Piez-51 3/7/24 6090 NA NA NA NA NA 1-PL-Piez-47 4/4/24 6080 ND

<10.30

<4.57

<.836 ND 1-PL-Piez-29 4/5/24 7560 ND

<71.20

<4.88

<.788 ND 1-PL-Piez-47 4/5/24 5500 NA NA NA NA NA NA = analysis not required.

ND = No non-natural gamma emitting nuclides detected when analyzed to REMP LLDs.

TRU = Transuranics (Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240 and Pu-241)

INDUSTRY GROUND WATER PROTECTION INITIATIVE Page 2 of 4 Well Sample Tritium Gamma Fe-55 Ni-63 Sr-90 TRU Designation Date pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter 1-PL-Piez-44 4/10/24 1940 ND

<67.30

<4.30

<.884 ND 1-PL-Piez-49 4/10/24 1780 NA NA NA NA NA 1-PL-Piez-52 4/10/24

<1240 ND NA NA NA NA 1-PL-Piez-44 4/10/24 1940 NA NA NA NA NA 1-PL-Piez-49 4/10/24 2550 ND

<76.70

<4.82

<.829 ND 1-PL-Piez-46 4/11/24

<1240 ND

<64.80

<4.40

<.744 ND 1-PL-Piez-48 4/14/24

<1240 ND NA NA NA NA 1-PL-Piez-29 5/19/24 8720 NA NA NA NA NA 1-PL-Piez-47 5/19/24 5800 NA NA NA NA NA 1-PL-Piez-05 6/11/24 1860 ND NA NA NA NA 1-PL-Piez-06 6/11/24 0

ND NA NA NA NA 1-PL-Piez-43 6/11/24 344 ND NA NA NA NA 1-PL-Piez-44 6/11/24 1960 ND NA NA NA NA 1-PL-Piez-45 6/11/24 270 ND NA NA NA NA 1-PL-Piez-47 6/11/24 5720 ND NA NA NA NA 1-PL-Piez-50 6/11/24 81.7 ND NA NA NA NA 1-PL-Piez-33 6/13/24 0

NA NA NA NA NA 1-PL-Piez-41 6/13/24 0

NA NA NA NA NA 1-PL-Piez-42 6/13/24 0

NA NA NA NA NA 1-PL-Piez-29 6/14/24 4620 ND NA NA NA NA 1-PL-Piez-46 6/14/24 0

ND NA NA NA NA 1-PL-Piez-48 6/14/24 0

ND NA NA NA NA 1-PL-Piez-49 6/14/24 772 ND NA NA NA NA 1-PL-Piez-51 6/14/24 6000 ND NA NA NA NA 1-PL-Piez-52 6/14/24 1320 ND NA NA NA NA 1-PL-Piez-44 7/9/24 781 NA NA NA NA NA 1-PL-Piez-49 7/9/24 1070 NA NA NA NA NA 1-PL-Piez-51 7/9/24 5200 NA NA NA NA NA 1-PL-Piez-29 7/10/24 6330 NA NA NA NA NA 1-PL-Piez-44 7/25/24 1650 NA NA NA NA NA 1-PL-Piez-49 7/25/24 1530 NA NA NA NA NA 1-PL-Piez-51 7/25/24 4340 NA NA NA NA NA 1-PL-Piez-44 8/13/24 1490 NA NA NA NA NA NA = analysis not required.

ND = No non-natural gamma emitting nuclides detected when analyzed to REMP LLDs.

TRU = Transuranics (Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240 and Pu-241)

INDUSTRY GROUND WATER PROTECTION INITIATIVE Page 3 of 4 Well Sample Tritium Gamma Fe-55 Ni-63 Sr-90 TRU Designation Date pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter 1-PL-Piez-49 8/13/24 2090 NA NA NA NA NA 1-PL-Piez-51 8/13/24 4090 NA NA NA NA NA 1-PL-Piez-49 8/28/24 2760 NA NA NA NA NA 1-PL-Piez-51 8/28/24 4770 NA NA NA NA NA 1-PL-Piez-44 8/29/24 1160 NA NA NA NA NA 1-PL-Piez-44 9/11/24 1770 NA NA NA NA NA 1-PL-Piez-49 9/11/24 1430 NA NA NA NA NA 1-PL-Piez-51 9/11/24 4310 NA NA NA NA NA 1-PL-Piez-04 9/30/24 0

ND NA NA NA NA 1-PL-Piez-05 9/30/24 2380 ND NA NA NA NA 1-PL-Piez-06 9/30/24 374 ND NA NA NA NA 1-PL-Piez-07 9/30/24 398 ND NA NA NA NA 1-PL-Piez-43 9/30/24 337 ND NA NA NA NA 1-PL-Piez-45 9/30/24 856 ND NA NA NA NA 1-PL-Piez-44 10/1/24 1380 ND NA NA NA NA 1-PL-Piez-50 10/1/24 155 NA NA NA NA NA 1-PL-Piez-29 10/2/24 4330 ND NA NA NA NA 1-PL-Piez-46 10/2/24 1050 ND NA NA NA NA 1-PL-Piez-47 10/2/24 5940 ND NA NA NA NA 1-PL-Piez-48 10/2/24 159 ND NA NA NA NA 1-PL-Piez-49 10/2/24 6040 ND NA NA NA NA 1-PL-Piez-51 10/2/24 4580 ND NA NA NA NA 1-PL-Piez-52 10/2/24 406 ND NA NA NA NA 1-PL-Piez-25 10/3/24 0

NA NA NA NA NA 1-PL-Piez-34 10/3/24 0

NA NA NA NA NA 1-PL-Piez-36 10/3/24 565 NA NA NA NA NA 1-PL-Piez-37 10/3/24 476 NA NA NA NA NA 1-PL-Piez-39 10/3/24 0

NA NA NA NA NA 1-PL-Piez-38 10/8/24 0

NA NA NA NA NA 1-PL-Piez-53 10/8/24 0

NA NA NA NA NA 1-PL-Piez-49 10/15/24 1660 NA NA NA NA NA 1-PL-Piez-51 10/15/24 3030 NA NA NA NA NA G-08 11/12/24 8980 NA NA NA NA NA 1-PL-Piez-44 11/12/24 1630 NA NA NA NA NA 1-PL-Piez-51 11/12/24 4130 NA NA NA NA NA G-08 11/26/24 9480 NA NA NA NA NA 1-PL-Piez-44 11/26/24 2120 NA NA NA NA NA 1-PL-Piez-49 11/26/24 1800 NA NA NA NA NA 1-PL-Piez-51 11/26/24 2890 NA NA NA NA NA NA = analysis not required.

ND = No non-natural gamma emitting nuclides detected when analyzed to REMP LLDs.

TRU = Transuranics (Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240 and Pu-241)

INDUSTRY GROUND WATER PROTECTION INITIATIVE Page 4 of 4 Well Sample Tritium Gamma Fe-55 Ni-63 Sr-90 TRU Designation Date pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter pCi/Liter 1-PL-Piez-33 12/10/24 0

NA NA NA NA NA 1-PL-Piez-40 12/10/24 0

NA NA NA NA NA 1-PL-Piez-41 12/10/24 0

NA NA NA NA NA 1-PL-Piez-42 12/10/24 0

NA NA NA NA NA 1-PL-Piez-05 12/12/24 2730 ND NA NA NA NA 1-PL-Piez-06 12/12/24 340 ND NA NA NA NA 1-PL-Piez-43 12/12/24 57.9 ND NA NA NA NA 1-PL-Piez-45 12/12/24 539 ND NA NA NA NA G-08 12/14/24 8330 NA NA NA NA NA 1-PL-Piez-44 12/17/24 1410 NA NA NA NA NA 1-PL-Piez-49 12/17/24 3120 NA NA NA NA NA 1-PL-Piez-51 12/17/24 3640 NA NA NA NA NA 1-PL-Piez-08 12/18/24 0

NA NA NA NA NA 1-PL-Piez-24 12/18/24 0

NA NA NA NA NA 1-PL-Piez-44 12/18/24 2580 ND NA NA NA NA 1-PL-Piez-47 12/18/24 489 ND NA NA NA NA 1-PL-Piez-50 12/18/24 3780 NA NA NA NA NA 1-PL-Piez-09 12/19/24 906 NA NA NA NA NA 1-PL-Piez-22 12/19/24 290 NA NA NA NA NA 1-PL-Piez-28 12/19/24 347 NA NA NA NA NA 1-PL-Piez-29 12/23/24 4060 ND NA NA NA NA 1-PL-Piez-46 12/23/24 805 ND NA NA NA NA 1-PL-Piez-48 12/23/24 1190 ND NA NA NA NA 1-PL-Piez-49 12/23/24 2810 ND NA NA NA NA 1-PL-Piez-51 12/23/24 4450 ND NA NA NA NA 1-PL-Piez-52 12/23/24 568 ND NA NA NA NA NA = analysis not required.

ND = No non-natural gamma emitting nuclides detected when analyzed to REMP LLDs.

TRU = Transuranics (Am-241, Cm-242, Cm-243/244, Pu-238, Pu-239/240 and Pu-241)

INDUSTRY GROUND WATER PROTECTION INITIATIVE