ML23118A265

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Submittal of 2022 Annual Radiological Effluent Release Report
ML23118A265
Person / Time
Site: Surry  Dominion icon.png
Issue date: 04/28/2023
From: Grady C
Virginia Electric & Power Co (VEPCO)
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
23-122
Download: ML23118A265 (1)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 28, 2023 United States Nuclear Regulatory Commission Serial No.23-122 Attention: Document Control Desk SPS: MMT RO Washington, DC 20555-0001 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 2022 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the Surry Power Station Annual Radioactive Effluent Release Report for January 1, 2022, through December 31, 2022. 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 2022 calendar year, as outlined in Regulatory Guide 1.21, Revision 1, June 1974.

If you have any further questions, please contact William Terry at 757-365-2010.

CewmQk-Sincerely, Cathy Grady 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

Serial No.23-122 SPS Annual Rad Effluent Report Docket Nos. 50-280, 50-281 ATTACHMENT 2022 Annual Radioactive Effluent Release Report Surry Power Station SURRY POWER STATION UNITS 1 AND 2 VIRGINIA ELECTRIC AND POWER COMPANY

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ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR SURRY POWER STATION January 1, 2022 through December 31, 2022 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 Attachment 1 Effluent Release Data Attachment 2 Annual and Quarterly Doses Attachment 3 Revisions to Offsite Dose Calculation Manual (ODCM)

Attachment 4 Major Changes to Radioactive Liquid, Gaseous and Solid Waste Treatment Systems Attachment 5 Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation Attachment 6 Unplanned Releases Attachment 7 Lower Limit of Detection (LLD) for Effluent Sample Analysis Attachment 8 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 2022 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 release and no unplanned gaseous effluent release as classified according to the criteria in the Offsite Dose Calculation Manual.

Based on the 2022 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 2.91E-04 mrem, which is 0.005 % of the 6 mrem dose limit. The critical organ dose due to liquid effluents was 3.02E-04 mrem to the GI-LLI, which is 0.002 % of the 20 mrem dose limit.
2. The air dose due to noble gases in gaseous effluents was 1.07E-05 mrad gamma, which is 0.00005 % of the 20 mrad gamma dose limit, and 6.01E-06 mrad beta, which is 0.00002 % 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 9.34E-02 mrem, which is 0.3 % 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.

There were no revisions made to VPAP-2103S, Offsite Dose Calculation Manual, 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 2022 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 2022.

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.

As required by the ODCM, Sections 6.2.2 and 6.3.2, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in Attachment 5 of this report. provides a summary of unplanned releases that occurred during the reporting period. 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 teen for the 1st, 2nd, 3rd quarters and a child for the 4th quarter.

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 teen at site boundary for the 1st, 2nd, and 3rd quarters and a child at site boundary for the 4th quarter. The critical organs for the 1st and 2nd quarters are the liver, thyroid, kidney, lung, and gastrointestinal-lower large intestine. The critical organ for the 3rd quarter is the lung and the critical organ for the 4th quarter is the bone. 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 gastrointestinal-lower large intestine as the critical organ. The total body dose was also determined for this individual.

No effluent radiation monitors were inoperable for greater than 30 days in 2022. 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 2022. This is reported in Attachment 6 as required by the ODCM, Section 6.7.2.

3

Discussion 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. All milk samples were collected and analyzed as required by the ODCM. 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

EFFLUENT RELEASE DATA January 1, 2022 through December 31, 2022 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

Attachment 1 TABLE 1A Page 1 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/22 TO 12/31/22 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 N/D N/D 1.80E+01
2. AVE RELEASE RATE FOR PERIOD µCi/sec N/A N/A 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 N/D 2.80E+01
2. AVE RELEASE RATE FOR PERIOD µCi/sec N/A N/A
3. GROSS ALPHA RADIOACTIVITY Ci N/D N/D D. TRITIUM
1. TOTAL RELEASE Ci 1.58E+01 8.68E+00 3.10E+01
2. AVE RELEASE RATE FOR PERIOD µCi/sec 2.04E+00 1.10E+00 E. CARBON-14
1. TOTAL RELEASE Ci N/D N/D
2. AVE RELEASE RATE FOR PERIOD µCi/sec N/A N/A PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE  % 3.11E-03 1.68E-03 TOTAL BODY DOSE RATE  % 0.00E-00 0.00E-00 SKIN DOSE RATE  % 0.00E-00 0.00E-00

Attachment 1 TABLE 1A Page 2 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/22 TO 12/31/22 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 6.04E-04 1.02E-01 1.80E+01
2. AVE RELEASE RATE FOR PERIOD µCi/sec 7.59E-05 1.28E-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 3.80E-06 1.03E-04 2.80E+01
2. AVE RELEASE RATE FOR PERIOD µCi/sec 4.78E-07 1.29E-05
3. GROSS ALPHA RADIOACTIVITY Ci N/D N/D D. TRITIUM
1. TOTAL RELEASE Ci 5.94E+00 1.13E+01 3.10E+01
2. AVE RELEASE RATE FOR PERIOD µCi/sec 7.47E-01 1.42E+00 E. CARBON-14
1. TOTAL RELEASE Ci 1.11E-01 1.87E+01
2. AVE RELEASE RATE FOR PERIOD µCi/sec 1.40E-02 2.35E+00 PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE  % 1.14E-03 5.72E-03 TOTAL BODY DOSE RATE  % 1.07E-09 7.99E-06 SKIN DOSE RATE  % 4.22E-10 2.03E-06

Attachment 1 TABLE 1B Page 3 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/22 TO 12/31/22 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/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 N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A 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 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 N/D 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 N/D TOTAL FOR PERIOD Ci N/A N/A N/A N/A

Attachment 1 TABLE 1B Page 4 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/22 TO 12/31/22 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 3.01E-02 6.04E-04 6.70E-02 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 N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A 3.01E-02 6.04E-04 6.70E-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 N/D 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 5.53E+00 1.11E-01 1.23E+01 TOTAL FOR PERIOD Ci N/A 5.53E+00 1.11E-01 1.23E+01

Attachment 1 TABLE 1C Page 5 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/22 TO 12/31/22 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 N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A 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 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 N/D 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 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 N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A N/A N/A

Attachment 1 TABLE 1C Page 6 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/22 TO 12/31/22 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 2.92E-03 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 N/D 1.86E-03 N/D N/D TOTAL FOR PERIOD Ci N/A 1.86E-03 N/A 2.92E-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 3.80E-06 1.03E-04 N/D 9.50E-09 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 3.41E-01 N/D 5.37E-01 TOTAL FOR PERIOD Ci 3.80E-06 3.41E-01 N/A 5.37E-01

Attachment 1 TABLE 2A Page 7 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/22 TO 12/31/22 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 1.62E-03 4.26E-04 2.00E+01
2. AVE DIL. CONC. DURING PERIOD µCi/mL 6.73E-13 1.81E-13
3. PERCENT OF APPLICABLE LIMIT  % 1.44E-06 1.18E-06 B. TRITIUM
1. TOTAL RELEASE Ci 1.27E+02 6.73E+01 2.00E+01
2. AVE DIL. CONC. DURING PERIOD µCi/mL 5.29E-08 2.86E-08
3. PERCENT OF APPLICABLE LIMIT  % 5.30E-04 2.86E-04 C. DISSOLVED AND ENTRAINED GASES
1. TOTAL RELEASE Ci N/D N/D 2.00E+01
2. AVE DIL. CONC. DURING PERIOD µCi/mL N/A N/A
3. PERCENT OF APPLICABLE LIMIT  % N/A N/A D. GROSS ALPHA RADIOACTIVITY
1. TOTAL RELEASE Ci N/D N/D 2.00E+01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS 5.24E+07 5.27E+07 3.00E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 2.41E+12 2.36E+12 3.00E+00

Attachment 1 TABLE 2A Page 8 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/22 TO 12/31/22 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 2.71E-04 1.12E-03 2.00E+01
2. AVE DIL. CONC. DURING PERIOD µCi/mL 8.71E-14 4.93E-13
3. PERCENT OF APPLICABLE LIMIT  % 6.69E-07 1.94E-06 B. TRITIUM
1. TOTAL RELEASE Ci 5.35E+02 6.33E+02 2.00E+01
2. AVE DIL. CONC. DURING PERIOD µCi/mL 1.72E-07 2.79E-07
3. PERCENT OF APPLICABLE LIMIT  % 1.72E-03 2.79E-03 C. DISSOLVED AND ENTRAINED GASES
1. TOTAL RELEASE Ci N/D 2.52E-04 2.00E+01
2. AVE DIL. CONC. DURING PERIOD µCi/mL N/A 1.11E-13
3. PERCENT OF APPLICABLE LIMIT  % N/A 5.55e-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 5.35E+07 5.48E+07 3.00E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 3.11E+12 2.27E+12 3.00E+00

Attachment 1 TABLE 2B Page 9 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/22 TO 12/31/22 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 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 2.53E-04 2.56E-04 1.99E-05 N/D I-131 Ci N/D N/D N/D N/D Co-58 Ci N/D N/D 2.24E-04 1.25E-04 Co-60 Ci N/D N/D 8.38E-05 4.49E-05 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 1.04E-03 N/D Nd-147 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci 2.53E-04 2.56E-04 1.37E-03 1.70E-04 Xe-133 Ci N/D N/D N/D N/D Xe-135 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A N/A N/A

Attachment 1 TABLE 2B Page 10 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/22 TO 12/31/22 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 1.97E-04 1.42E-04 N/D 2.27E-04 I-131 Ci N/D N/D N/D N/D Co-58 Ci N/D N/D 4.75E-05 5.65E-04 Co-60 Ci N/D N/D 2.61E-05 1.29E-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 9.09E-06 Sb-125 Ci N/D N/D N/D 1.62E-05 Nd-147 Ci N/D N/D N/D N/D Be-7 Ci N/D N/D N/D 3.14E-05 TOTAL FOR PERIOD Ci 1.97E-04 1.42E-04 7.36E-05 9.78E-04 Xe-133 Ci N/D N/D N/D 2.52E-04 Xe-135 Ci N/D N/D N/D N/D TOTAL FOR PERIOD Ci N/A N/A N/A 2.52E-04

Attachment 1 TABLE 3 Page 11 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD: 1/1/22 - 12/31/22 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 1.10E+01 Note 1 1.00E+01 bottoms, etc. Ci 5.62E+00 3.00E+01
b. Dry compressible waste, contaminated m3 6.53E+02 Note 2 1.00E+01 equip., etc. Ci 5.99E-01 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 (Waste oil) m3 0.00E+00 Note 3 1.00E+01 Ci 0.00E-00 3.00E+01
2. Estimate of major nuclide composition (by type of waste)
a. H-3  % 2.03E+00 Cr-51  % 1.09E+00 Fe-55  % 4.57E+00 Co-58  % 4.47E+01 Co-60  % 2.08E+01 Ni-63  % 1.98E+01 Sb-125  % 1.01E+00 Cs-137  % 3.36E+00
b. Mn-54  % 2.15E+00 Fe-55  % 4.44E+00 Co-58  % 3.93E+00 Co-60  % 6.99E+01 Ni-63  % 7.54E+00 Zr-95  % 2.62E+00 Nb-95  % 4.78E+00 Sb-125  % 1.44E+00 Pu-241  % 1.98E+00
c. N/A  % N/A
d. N/A  % N/A

Attachment 1 TABLE 3 Page 12 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD: 1/1/22 - 12/31/22 CONTINUED SURRY POWER STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 10 Truck EnergySolutions at Oak Ridge, TN (Bear Creek Operations) 14 Truck EnergySolutions at Oak Ridge, TN (Gallaher Rd Facility)

B. IRRADIATED FUEL SHIPMENT (Disposition)

Number of Shipments Mode of Transportation Destination 0

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 9.96E+00 m 3.

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 1.38E+01 m 3.

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 m 3.

Attachment 2 Page 1 of 1 ANNUAL AND QUARTERLY DOSES 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.

LIQUID Maximum Receptor - Adult 2022 Total Body GI-LLI Liver (mrem) (mrem) (mrem) 1st Quarter 2.70E-05 3.03E-05 2.76E-05 2nd Quarter 2.59E-05 2.59E-05 2.70E-05 3rd Quarter 8.48E-05 8.47E-05 8.52E-05 4th Quarter 1.54E-04 1.61E-04 1.55E-04 Annual 2.91E-04 3.02E-04 2.94E-04 GASEOUS - Air Dose 2022 Gamma Beta (mrad) (mrad) 1st Quarter 0.00E-00 0.00E-00 2nd Quarter 0.00E-00 0.00E-00 3rd Quarter 1.62E-09 4.82E-09 4th Quarter 1.07E-05 6.00E-06 Annual 1.07E-05 6.01E-06 GASEOUS - Organ Dose Annual Maximum by Quarter 2022 Maximum Teen/Lung Receptor / Organ (mrem) (mrem) 1st Quarter 0.00E-00 1.15E-02 Teen/Multi 2nd Quarter 0.00E-00 6.29E-03 Teen/Multi 3rd Quarter 5.01E-04 4.31E-03 Teen/Lung 4th Quarter 9.29E-02 9.29E-02 Child/Bone Annual 9.34E-02

Attachment 3 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.

Attachment 4 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 this reporting period.

Attachment 5 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 of the ODCM were inoperable greater than 30 days during this reporting period.

Attachment 6 Page 1 of 1 UNPLANNED RELEASES In accordance with the ODCM reporting requirements, there were no unplanned liquid or unplanned gaseous releases that occurred during the reporting period.

Attachment 7 Page 1 of 1 LOWER LIMIT OF DETECTION (LLD) FOR EFFLUENT SAMPLE ANALYSIS GASEOUS: Isotope Required LLD Typical LLD Kr-87 1.00E-04 2.32E 1.95E-05 Kr-88 1.00E-04 1.34E 2.05E-05 Xe-133 1.00E-04 1.13E 1.25E-05 Xe-133m 1.00E-04 4.73E 4.06E-05 Xe-135 1.00E-04 4.50E 5.41E-06 Xe-135m 1.00E-04 1.38E 9.41E-05 Xe-138 1.00E-04 2.66E 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 1.20E 1.34E-12 Sr-90 1.00E-11 1.64E 1.61E-13 Cs-134 1.00E-11 2.45E 2.65E-13 Cs-137 1.00E-11 1.88E 4.31E-13 Mn-54 1.00E-11 1.52E 7.15E-13 Fe-59 1.00E-11 9.33E 7.39E-13 Co-58 1.00E-11 1.74E 7.35E-13 Co-60 1.00E-11 2.69E 9.69E-13 Zn-65 1.00E-11 5.10E 1.31E-12 Mo-99 1.00E-11 4.06E 4.06E-12 Ce-141 1.00E-11 1.83E 3.82E-13 Ce-144 1.00E-11 6.99E 1.61E-12 Alpha 1.00E-11 1.66E 1.66E-14 Tritium 1.00E-06 5.13E 5.23E-08 LIQUID: Sr-89 5.00E-08 3.51E-08 - 4.22E-07 Sr-90 5.00E-08 9.22E-09 - 2.10E-08 Cs-134 5.00E-07 5.30E-09 - 1.49E-07 Cs-137 5.00E-07 2.16E-08 - 1.48E-07 I-131 1.00E-06 2.61E-08 - 6.11E-08 Co-58 5.00E-07 1.96E-08 - 6.94E-08 Co-60 5.00E-07 2.31E-09 - 8.02E-08 Fe-59 5.00E-07 1.13E-08 - 1.01E-07 Zn-65 5.00E-07 3.53E-08 - 1.81E-07 Mn-54 5.00E-07 2.69E-08 - 7.16E-08 Mo-99 5.00E-07 4.95E-07 - 4.95E-07 Ce-141 5.00E-07 3.27E-08 - 7.48E-08 Ce-144 5.00E-07 1.24E-07 - 3.47E-07 Fe-55 1.00E-06 3.40E-07 - 9.79E-07 Alpha 1.00E-07 2.51E-08 - 2.50E-08 Tritium 1.00E-05 1.27E-06 - 1.29E-06 Xe-133 1.00E-05 8.63E-08 - 2.10E-07 Xe-135 1.00E-05 3.33E-08 - 5.74E-08 Xe-133m 1.00E-05 2.99E-07 - 4.00E-07 Xe-135m 1.00E-05 1.35E-06 - 2.61E-06 Xe-138 1.00E-05 2.98E-06 - 7.88E-06 Kr-87 1.00E-05 1.23E-07 - 2.37E-07 Kr-88 1.00E-05 5.43E-08 - 2.20E-07

Attachment 8 Page 1 of 5 INDUSTRY GROUND WATER PROTECTION INITIATIVE The following is a summary of 2022 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 G-08 1/12/22 14900 NA NA NA NA NA P-44 1/12/22 1140 NA NA NA NA NA P-49 1/12/22 1160 NA NA NA NA NA P-52 1/20/22 <1380 ND NA NA NA NA P-44 1/24/22 2470 NA NA NA NA NA P-49 1/24/22 2000 NA NA NA NA NA G-08 2/3/22 12500 NA NA NA NA NA P-44 2/3/22 2090 NA NA NA NA NA P-49 2/3/22 1920 NA NA NA NA NA G-08 2/17/22 13600 NA NA NA NA NA P-44 2/17/22 1640 NA NA NA NA NA P-49 2/17/22 2120 NA NA NA NA NA P-29 2/28/22 <947 ND NA NA NA ND P-46 2/28/22 <949 ND NA NA NA ND P-48 2/28/22 <954 NA NA NA NA NA P-49 2/28/22 2750 ND <181.4 <4.05 <.948 ND P-52 2/28/22 <948 NA NA NA <.981 NA P-06 3/1/22 <945 ND <190.4 <3.96 <.909 ND P-07 3/1/22 <945 NA NA NA NA NA P-29 3/1/22 823 NA <44.39 <4.09 <.815 NA P-43 3/1/22 <946 ND NA NA NA NA P-44 3/1/22 2380 ND <108.7 <4.61 <.88 ND P-45 3/1/22 <942 ND <65.15 <4.46 <.856 ND P-46 3/1/22 287 NA NA NA NA NA P-47 3/1/22 <944 ND <83.03 <4.54 <.993 ND P-48 3/1/22 455 NA NA NA NA NA P-50 3/1/22 <946 ND NA NA NA NA P-52 3/1/22 704 NA NA NA NA NA G-08 3/2/22 12100 NA NA NA NA NA P-04 3/2/22 <945 NA NA NA NA NA P-05 3/2/22 3240 ND <114 <3.75 <.898 ND 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)

Attachment 8 Page 2 of 5 INDUSTRY GROUND WATER PROTECTION INITIATIVE 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 P-06 3/2/22 0 NA NA NA NA NA P-07 3/2/22 0 NA NA NA NA NA P-25 3/2/22 0 NA NA NA NA NA P-27 3/2/22 0 NA NA NA NA NA P-33 3/2/22 0 NA NA NA NA NA P-41 3/2/22 381 NA NA NA NA NA P-42 3/2/22 0 NA NA NA NA NA P-43 3/2/22 0 NA NA NA NA NA P-44 3/2/22 2490 NA NA NA NA NA P-45 3/2/22 406 NA NA NA NA NA P-47 3/2/22 372 NA NA NA NA NA P-49 3/2/22 2840 NA NA NA NA NA P-50 3/2/22 0 NA NA NA NA NA P-44 3/15/22 3210 NA NA NA NA NA P-49 3/15/22 2660 NA NA NA NA NA G-08 3/30/22 12700 NA NA NA NA NA P-44 3/30/22 8420 NA NA NA NA NA P-49 3/30/22 2280 NA NA NA NA NA P-44 4/7/22 2130 NA NA NA NA NA G-08 4/13/22 13400 NA NA NA NA NA P-49 4/13/22 3260 NA NA NA NA NA P-44 4/16/22 2900 NA NA NA NA NA P-51 4/18/22 13900 NA NA NA NA NA P-48 4/21/22 431 NA NA NA NA NA G-08 4/26/22 13800 NA NA NA NA NA P-49 4/26/22 3980 NA NA NA NA NA P-51 4/26/22 15400 NA NA NA NA NA G-08 5/16/22 13900 NA NA NA NA NA P-44 5/16/22 3140 NA NA NA NA NA P-51 5/16/22 8500 NA NA NA NA NA G-08 5/25/22 15100 NA NA NA NA NA P-44 5/25/22 2170 NA NA NA NA NA P-49 5/25/22 2730 NA NA NA NA NA NA = Analysis not required.

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

Attachment 8 Page 3 of 5 INDUSTRY GROUND WATER PROTECTION INITIATIVE 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 P-51 5/25/22 8050 NA NA NA NA NA P-29 5/31/22 1200 NA NA NA NA NA P-29 5/31/22 1200 NA NA NA NA NA P-29 5/31/22 1330 NA NA NA NA NA P-46 5/31/22 <970 NA NA NA NA NA P-46 5/31/22 <970 NA NA NA NA NA P-46 5/31/22 311 NA NA NA NA NA P-48 5/31/22 <970 NA NA NA NA NA P-48 5/31/22 50.7 NA NA NA NA NA P-48 5/31/22 <970 NA NA NA NA NA P-49 5/31/22 1570 NA NA NA NA NA P-49 5/31/22 1570 NA NA NA NA NA P-49 5/31/22 2030 NA NA NA NA NA P-50 5/31/22 <972 NA NA NA NA NA P-50 5/31/22 0 NA NA NA NA NA P-50 5/31/22 <972 NA NA NA NA NA P-51 5/31/22 6170 NA NA NA NA NA P-51 5/31/22 6590 NA NA NA NA NA P-51 5/31/22 6170 NA NA NA NA NA P-52 5/31/22 <971 NA NA NA NA NA P-52 5/31/22 <971 NA NA NA NA NA P-52 5/31/22 0 NA NA NA NA NA P-03 6/1/22 242 NA NA NA NA NA P-36 6/1/22 158 NA NA NA NA NA P-39 6/1/22 28.1 NA NA NA NA NA P-37 6/6/22 451 NA NA NA NA NA P-38 6/6/22 373 NA NA NA NA NA P-40 6/6/22 2770 NA NA NA NA NA P-23 6/7/22 972 NA NA NA NA NA P-34 6/7/22 381 NA NA NA NA NA G-08 6/8/22 10700 NA NA NA NA NA P-08 6/8/22 81.3 NA NA NA NA NA P-09 6/8/22 92.6 NA NA NA NA NA P-22 6/8/22 194 NA NA NA NA NA P-44 6/8/22 1990 NA NA NA NA NA P-49 6/8/22 5380 NA NA NA NA NA P-51 6/8/22 6630 NA NA NA NA NA P-20 6/9/22 435 NA NA NA NA NA P-24 6/9/22 473 NA NA NA NA NA NA = Analysis not required.

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

Attachment 8 Page 4 of 5 INDUSTRY GROUND WATER PROTECTION INITIATIVE 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 P-28 6/9/22 0 NA NA NA NA NA P-40 6/13/22 1.2 NA NA NA NA NA P-06 6/14/22 <731 ND NA NA NA NA P-05 6/15/22 2570 ND NA NA NA NA P-43 6/15/22 <720 ND NA NA NA NA P-44 6/15/22 1190 ND NA NA NA NA P-45 6/15/22 <713 ND NA NA NA NA P-47 6/15/22 1520 ND NA NA NA NA G-08 6/30/22 15900 NA NA NA NA NA P-44 6/30/22 2790 NA NA NA NA NA P-49 6/30/22 2110 NA NA NA NA NA P-51 6/30/22 7810 NA NA NA NA NA P-53 6/30/22 638 NA NA NA NA NA G-08 7/13/22 18800 NA NA NA NA NA P-44 7/13/22 1190 NA NA NA NA NA P-49 7/13/22 1440 NA NA NA NA NA P-51 7/13/22 5490 NA NA NA NA NA G-08 7/28/22 15700 NA NA NA NA NA P-44 7/28/22 1310 NA NA NA NA NA P-49 7/28/22 937 NA NA NA NA NA P-51 7/28/22 6100 NA NA NA NA NA G-08 8/18/22 14400 NA NA NA NA NA P-49 8/18/22 1720 NA NA NA NA NA P-51 8/18/22 3660 NA NA NA NA NA P-46 8/23/22 702 NA NA NA NA NA P-48 8/23/22 191 NA NA NA NA NA P-49 8/18/22 1720 NA NA NA NA NA P-51 8/18/22 3660 ND NA NA NA NA P-46 8/23/22 702 ND NA NA NA NA P-48 8/23/22 191 NA NA NA NA NA P-49 8/23/22 1050 ND NA NA NA NA P-51 8/23/22 4750 ND NA NA NA NA P-52 8/23/22 492 ND NA NA NA NA P-04 8/25/22 1070 ND NA NA NA NA P-05 8/25/22 4240 ND NA NA NA NA P-06 8/25/22 1760 ND NA NA NA NA P-43 8/26/22 877 ND NA NA NA NA P-07 8/30/22 663 ND NA NA NA NA NA = Analysis not required.

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

Attachment 8 Page 5 of 5 INDUSTRY GROUND WATER PROTECTION INITIATIVE 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 P-25 8/30/22 925 NA NA NA NA NA P-27 8/30/22 944 NA NA NA NA NA P-44 8/30/22 1550 ND NA NA NA NA P-45 8/30/22 812 ND NA NA NA NA P-47 8/30/22 2400 ND NA NA NA NA P-50 8/30/22 1090 ND NA NA NA NA P-29 9/1/22 9.25 NA NA NA NA NA P-33 9/1/22 807 NA NA NA NA NA P-41 9/1/22 132 NA NA NA NA NA P-42 9/1/22 9.25 NA NA NA NA NA G-08 9/12/22 14600 NA NA NA NA NA P-44 9/12/22 4310 NA NA NA NA NA P-49 9/12/22 6600 NA NA NA NA NA P-51 9/12/22 4090 NA NA NA NA NA G-08 10/10/22 13500 NA NA NA NA NA P-44 10/10/22 1810 NA NA NA NA NA P-49 10/10/22 1590 NA NA NA NA NA P-44 10/26/22 2450 NA NA NA NA NA P-49 10/30/22 2410 NA NA NA NA NA P-44 11/3/22 1540 ND NA NA NA NA P-47 11/3/22 1210 ND NA NA NA NA P-48 11/3/22 623 ND NA NA NA NA P-49 11/3/22 2430 ND NA NA NA NA P-51 11/3/22 5500 ND NA NA NA NA P-52 11/3/22 524 ND NA NA NA NA P-05 11/6/22 2860 NA NA NA NA NA P-06 11/6/22 409 NA NA NA NA NA P-43 11/6/22 398 NA NA NA NA NA P-45 11/6/22 952 ND NA NA NA NA P-49 11/17/22 2250 NA NA NA NA NA P-51 11/17/22 4190 NA NA NA NA NA P-49 11/30/22 2240 NA NA NA NA NA P-51 11/30/22 4360 NA NA NA NA NA P-51 12/20/22 3000 NA NA NA NA NA P-49 12/21/22 1720 NA NA NA NA NA NA = Analysis not required.

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

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