ML21120A325

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Submittal of Annual Radioactive Effluent Release Report
ML21120A325
Person / Time
Site: Surry  Dominion icon.png
Issue date: 04/30/2021
From: Henderson J
Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
21-150
Download: ML21120A325 (34)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 30, 2021 United States Nuclear Regulatory Commission Serial No.21-150 Attention: Document Control Desk S&L/JWD 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 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the Surry Power Station Annual Radioactive Effluent Release Report for January 1, 2020, through December 31, 2020. The report, submitted pursuant to Surry Power Station Technical Specification 6.6.8.3, includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released during the 2020 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.

J. enderson 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.21-150 SPS Annual Rad Effluent Report Docket Nos. 50-280, 50-281 ATTACHMENT 2020 Annual Radioactive Effluent Release Report Surry Power Station SURRY POWER STATION UNITS 1 AND 2 VIRGINIA ELECTRIC AND POWER COMPANY

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION January 1, 2020 through December 31 , 2020 Prepared By: _

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J. R. Hopkins

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Manager Radiological Protection and Chemistry

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE SURRY POWER STATION January 1, 2020 through December 31, 2020 Index Section No. Subject Page 1 Executive Summary 1 2 Purpose and Scope 2 3 Discussion 3 4 Supplemental Information 4 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 2020 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 was one unplanned liquid effluent release and no unplanned gaseous effluent release as classified according to the criteria in the Offsite Dose Calculation Manual.

The unplanned liquid effluent release is described in Attachment 6.

Based on the 2020 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 1.77E-04 mrem, which is 2.95E-03%

of the 6 mrem dose limit. The critical organ dose due to liquid effluents was 2.33E-04 mrem to the GI-LLI, which is 1.17E-03% of the 20 mrem dose limit.

2. The air dose due to noble gases in gaseous effluents was 9.84E-05 mrad gamma, which is 4.92E-04% of the 20 mrad gamma dose limit, and 3.68E-05 mrad beta, which is 9.20E-05% 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 1.05E-01 mrem, which is 3.50E-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.

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.

Based on the radioactivity measured and the dose calculations performed during this reporting period, the operation of Surry Power Station has resulted in negligible radiation dose consequences to the maximum exposed member of the public in unrestricted areas.

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 2020.

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. In 2020, one radiation monitor was inoperable and not returned to operable status within 30 days. provides a summary of unplanned releases that occurred during the reporting period. In 2020, one unplanned liquid release occurred and is summarized in Attachment 6. 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. One informal communication was made in 2020 in accordance with the Industry Ground Water Protection Initiative to State, Local, and NRC officials. The event details are summarized in Attachment 8.

2

Discussion The basis for the calculation of the percent of technical specification for the critical organ in Table 1A of Attachment 1 is the ODCM, Section 6.3.1, which requires that the 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 to the critical organ at or beyond the site boundary. The critical receptor was modeled as a child for the 1st, 2nd and 3rd quarters and the teen was the critical receptor 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 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.

One liquid effluent radiation monitor was inoperable for greater than 30 days in 2020 and is summarized in Attachment 5 as required by the ODCM, Section 6.2.2 and 6.3.2. No gaseous effluent radiation monitors were inoperable for greater than 30 days in 2020.

There was one unplanned liquid release and no unplanned gaseous releases in 2020. The unplanned liquid release is summarized 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. In 2020, a control location was unavailable for two consecutive months. The details are summarized below.

  • Milk from the Beachy Farm control location was seasonally unavailable during the months of January and February of 2020. During these two months the dairy farmer experienced a reduction in milking animals, the animals diet was reduced, and the birth and nursing of a new calve resulted in limited milk being available for human consumption. Milk collection from Beachy Farm resumed in March 2020. During this period, 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

Attachment 1 EFFLUENT RELEASE DATA January 1, 2020 through December 31, 2020 This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, Appendix B.

Attachment 1 TABLE 1A Page 1 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/20 TO 12/31/20 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 1.64E-02 1.63E-01 1.80E+01
2. AVE RELEASE RATE FOR PERIOD µCi/sec 2.09E-03 2.07E-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 6.23E-05 1.40E-05 2.80E+01
2. AVE RELEASE RATE FOR PERIOD µCi/sec 7.92E-06 1.78E-06
3. GROSS ALPHA RADIOACTIVITY Ci N/D N/D D. TRITIUM
1. TOTAL RELEASE Ci 1.39E+01 1.61E+01 3.10E+01
2. AVE RELEASE RATE FOR PERIOD µCi/sec 1.76E+00 2.04E+00 E. CARBON-14
1. TOTAL RELEASE Ci 1.73E+00 1.71E+01
2. AVE RELEASE RATE FOR PERIOD µCi/sec 2.20E-01 2.18E+00 PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE  % 9.49E-03 3.25E-03 TOTAL BODY DOSE RATE  % 6.37E-05 2.95E-07 SKIN DOSE RATE  % 1.56E-05 1.16E-07

Attachment 1 TABLE 1A Page 2 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/20 TO 12/31/20 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 2.75E-03 N/D 1.80E+01
2. AVE RELEASE RATE FOR PERIOD µCi/sec 3.46E-04 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 4.33E+00 8.46E+00 3.10E+01
2. AVE RELEASE RATE FOR PERIOD µCi/sec 5.45E-01 1.06E+00 E. CARBON-14
1. TOTAL RELEASE Ci 2.89E-01 N/D
2. AVE RELEASE RATE FOR PERIOD µCi/sec 3.64E-02 N/A PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE  % 1.57E-03 1.63E-03 TOTAL BODY DOSE RATE  % 1.10E-05 N/A SKIN DOSE RATE  % 2.69E-06 N/A

Attachment 1 TABLE 1B Page 3 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/20 TO 12/31/20 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 1.63E-01 Xe-135 Ci N/D N/D N/D 1.98E-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 1.63E-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 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 1.71E+01 TOTAL FOR PERIOD Ci N/A N/A N/A 1.71E+01

Attachment 1 TABLE 1B Page 4 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/20 TO 12/31/20 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 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 1C Page 5 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/20 TO 12/31/20 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 1.30E-05 N/D 8.80E-04 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 3.50E-04 N/D 1.52E-02 N/D TOTAL FOR PERIOD Ci 3.63E-04 N/A 1.61E-02 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 1.67E-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 5.81E-05 1.40E-05 N/D N/D Co-60 Ci 4.17E-06 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 3.82E-02 N/D 1.69E+00 N/D TOTAL FOR PERIOD Ci 3.83E-02 1.40E-05 1.69E+00 N/A

Attachment 1 TABLE 1C Page 6 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/20 TO 12/31/20 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 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 1.90E-04 N/D 2.56E-03 N/D TOTAL FOR PERIOD Ci 1.90E-04 N/A 2.56E-03 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 2.00E-02 N/D 2.69E-01 N/D TOTAL FOR PERIOD Ci 2.00E-02 N/A 2.69E-01 N/A

Attachment 1 TABLE 2A Page 7 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/20 TO 12/31/20 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 4.66E-03 4.24E-03 2.00E+01
2. AVE DIL. CONC. DURING PERIOD µCi/mL 7.36E-12 7.22E-12
3. PERCENT OF APPLICABLE LIMIT  % 7.76E-06 1.09E-05 B. TRITIUM
1. TOTAL RELEASE Ci 2.90E+02 4.78E+02 2.00E+01
2. AVE DIL. CONC. DURING PERIOD µCi/mL 4.58E-07 8.14E-07
3. PERCENT OF APPLICABLE LIMIT  % 4.59E-03 8.14E-03 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 5.32E+07 5.38E+07 3.00E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 6.33E+11 5.87E+11 3.00E+00

Attachment 1 TABLE 2A Page 8 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/20 TO 12/31/20 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 1.15E-03 1.13E-03 2.00E+01
2. AVE DIL. CONC. DURING PERIOD µCi/mL 1.46E-12 1.63E-12
3. PERCENT OF APPLICABLE LIMIT  % 5.37E-06 5.95E-06 B. TRITIUM
1. TOTAL RELEASE Ci 4.92E+01 2.14E+01 2.00E+01
2. AVE DIL. CONC. DURING PERIOD µCi/mL 6.23E-08 3.09E-08
3. PERCENT OF APPLICABLE LIMIT  % 2.17E-03 1.10E-02 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 5.32E+07 5.34E+07 3.00E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 7.90E+11 6.92E+11 3.00E+00

Attachment 1 TABLE 2B Page 9 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/20 TO 12/31/20 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 1.51E-04 1.43E-04 1.05E-04 1.49E-04 I-131 Ci N/D N/D N/D N/D Co-58 Ci N/D N/D 7.19E-04 1.60E-03 Co-60 Ci N/D N/D 2.56E-04 6.36E-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 1.08E-05 N/D Sb-125 Ci N/D N/D 3.41E-03 1.71E-03 Nd-147 Ci 5.02E-06 N/D N/D N/D TOTAL FOR PERIOD Ci 1.56E-04 1.43E-04 4.50E-03 4.10E-03 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 1.17E-04

Attachment 1 TABLE 2B Page 10 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/20 TO 12/31/20 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 5.13E-06 Cs-134 Ci N/D N/D N/D 8.27E-07 Cs-137 Ci 2.07E-04 1.64E-04 8.70E-05 1.18E-04 I-131 Ci N/D N/D N/D N/D Co-58 Ci N/D N/D 3.78E-04 2.69E-04 Co-60 Ci N/D N/D 2.24E-04 3.25E-04 Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci N/D N/D N/D 5.66E-07 Mn-54 Ci N/D N/D N/D 2.75E-06 Cr-51 Ci N/D N/D N/D N/D Zr-95 Ci N/D N/D N/D 1.22E-06 Nb-95 Ci N/D N/D N/D 2.23E-06 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 2.51E-04 N/D Sb-125 Ci N/D N/D N/D 2.35E-04 Co-57 Ci N/D N/D N/D 1.34E-06 Nb-97 Ci N/D N/D N/D 1.07E-06 TOTAL FOR PERIOD Ci 2.07E-04 1.64E-04 9.39E-04 9.62E-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 3 Page 11 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD: 1/1/20 - 12/31/20 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 2.18E+01 Note 1 1.00E+01 bottoms, etc. Ci 1.70E+02 3.00E+01
b. Dry compressible waste, contaminated m3 2.36E+02 Note 2 1.00E+01 equip., etc. Ci 9.26E-01 3.00E+01
c. Irradiated components, control m3 0.00E+00 rods, etc. Ci 0.00E+00
d. Other (Waste oil) m3 3.96E+00 Note 3 1.00E+01 Ci 4.57E-03 3.00E+01
2. Estimate of major nuclide composition (by type of waste)
a. Mn-54  % 2.90E+00 Fe-55  % 2.88E+01 Co-58  % 2.03E+00 Co-60  % 5.13E+01 Ni-63  % 1.64E+00 Zn-65  % 1.31E+00 Sb-125  % 9.68E+00
b. Mn-54  % 3.41E+00 Fe-55  % 5.45E+00 Co-60  % 7.25E+01 Ni-63  % 1.16E+01 Nb-95  % 1.01E+00 Sb-125  % 1.42E+00 Pu-241  % 2.05E+00
c. n/a  % n/a
d. H-3  % 9.87E+01 Cs-137  % 1.26E+00

Attachment 1 TABLE 3 Page 12 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD: 1/1/20 - 12/31/20 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 12 Truck Oak Ridge, TN (EnergySolutions )

1 Truck Clive, UT (EnergySolutions )

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 7.58E+00 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 1.04E+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.

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 2020 Total Body GI-LLI Liver (mrem) (mrem) (mrem) 1st Quarter 5.73E-05 7.04E-05 5.72E-05 2nd Quarter 1.03E-04 1.32E-04 1.02E-04 3rd Quarter 9.94E-06 1.49E-05 1.02E-05 4th Quarter 6.53E-06 1.59E-05 6.90E-06 Annual 1.77E-04 2.33E-04 1.76E-04 GASEOUS - Air Dose 2020 Gamma Beta (mrad) (mrad) 1st Quarter 8.34E-05 3.03E-05 2nd Quarter 4.40E-07 1.30E-06 3rd Quarter 1.46E-05 5.15E-06 4th Quarter 0.00E+00 0.00E+00 Annual 9.84E-05 3.68E-05 GASEOUS - Organ Dose Annual Maximum by Quarter 2020 Maximum Child/Bone Receptor /

(mrem) (mrem) Organ 1st Quarter 2.40E-02 3.55E-02 Child/Bone 2nd Quarter 7.74E-02 7.74E-02 Child/Bone 3rd Quarter 4.02E-03 5.92E-03 Child/Bone 4th Quarter 0.00E+00 6.14E-03 Teen/Lung Annual 1.05E-01

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 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 for 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 the ODCM Attachments 1 and 5, which were determined to be inoperable, were not returned to operable status within 30 days. One radiation monitor, 1-SW-RM-107D, was not returned to operable status within 30 days and is detailed below.

1-SW-RM-107D was declared non-functional on 1/25/2020 at 04:10 due to lower than expected radiation monitor readings and was returned to service on 3/5/2020 at 14:38 following maintenance to clean the pin sockets on the radiation monitor cable connector.

During this period (1/25/2020 - 3/5/2020), 1-CC-E-1D, the CCHX for radiation monitor 1-SW-RM-107D, was removed from service on 1/27/2020 at 03:00 to clean tubes and to perform weld and coating repairs and was returned to service on 2/8/2020 at 04:51.

Attachment 6 Page 1 of 1 UNPLANNED RELEASES There was one unplanned liquid release and no unplanned gaseous release during this reporting period.

A summary of the liquid release is described below.

While investigating a lowering trend in Unit 2 RWST level, the North Yard Operator reported standing water adjacent to 2-CD-E-2B. The ground around the piping below 2-CS-36 appeared wet. No active leak could be seen from the piping and components and the source could not be immediately identified due to installed insulation. HP-3010.023 - Unplanned Liquid Release was initiated. The total volume discharged was estimated to be 336 gallons. The calculated total % Tech Spec for this release is 2.53e-05. The State and Local officials and NRC were notified of this event.

Liquid Release Permit (L-20201207-284-B) was generated to account for the activity released.

Total activity released is 5.76E-02 Ci with a maximum receptor dose of 5.11E-06 mRem.

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 2.43E 1.78E-05 Kr-88 1.00E-04 1.11E 1.82E-05 Xe-133 1.00E-04 1.10E 1.24E-05 Xe-133m 1.00E-04 3.93E 4.06E-05 Xe-135 1.00E-04 5.50E 5.38E-06 Xe-135m 1.00E-04 6.18E 4.59E-05 Xe-138 1.00E-04 1.65E 9.90E-05 I-131 1.00E-12 4.06E 4.06E-13 I-133 1.00E-10 4.06E-11 4.06E-11 Sr-89 1.00E-11 1.38E 3.73E-12 Sr-90 1.00E-11 2.03E 4.76E-13 Cs-134 1.00E-11 8.39E 7.83E-13 Cs-137 1.00E-11 6.75E 8.48E-13 Mn-54 1.00E-11 2.06E 8.21E-13 Fe-59 1.00E-11 1.97E 2.01E-12 Co-58 1.00E-11 1.65E 9.65E-13 Co-60 1.00E-11 3.12E 1.16E-12 Zn-65 1.00E-11 2.12E 2.14E-12 Mo-99 1.00E-11 4.06E 4.06E-12 Ce-141 1.00E-11 1.62E 6.87E-13 Ce-144 1.00E-11 7.08E 3.06E-12 Alpha 1.00E-11 1.68E 2.08E-14 Tritium 1.00E-06 5.75E 1.07E-07 LIQUID: Sr-89 5.00E-08 2.88E 4.86E-08 Sr-90 5.00E-08 5.58E 1.86E-08 Cs-134 5.00E-07 8.80E 6.48E-08 Cs-137 5.00E-07 7.54E 1.05E-07 I-131 1.00E-06 2.65E 9.98E-08 Co-58 5.00E-07 3.33E 7.47E-08 Co-60 5.00E-07 5.92E 7.72E-08 Fe-59 5.00E-07 1.75E 1.69E-07 Zn-65 5.00E-07 1.10E 2.03E-07 Mn-54 5.00E-07 4.34E 1.01E-07 Mo-99 5.00E-07 1.66E 4.95E-07 Ce-141 5.00E-07 3.63E 8.39E-08 Ce-144 5.00E-07 2.08E 4.33E-07 Fe-55 1.00E-06 1.33E 7.91E-07 Alpha 1.00E-07 2.62E 3.23E-08 Tritium 1.00E-05 1.42E 2.64E-06 Xe-133 1.00E-05 9.08E 2.33E-07 Xe-135 1.00E-05 2.85E 5.30E-08 Xe-133m 1.00E-05 2.25E 3.77E-07 Xe-135m 1.00E-05 6.88E 2.68E-06 Xe-138 1.00E-05 2.05E 7.63E-06 Kr-87 1.00E-05 1.02E 2.29E-07 Kr-88 1.00E-05 8.06E 1.62E-07

Attachment 8 Page 1 of 6 INDUSTRY GROUND WATER PROTECTION INITIATIVE In 2020, one leak to ground occurred resulting in voluntary communications to Local, State, and NRC officials, in accordance with Section 6.7.5 of the ODCM. This event is summarized below.

At 2214, on 12/12/20, Surry Power Station personnel identified leakage from the Unit 2 RWST Cooling System to the ground. Leakage was estimated to be greater than 100 gallons (336 gallons est.) with a tritium concentration determined to be 4.5E-07 pCi/L, requiring report in accordance with the industry voluntary groundwater protection program. This event is documented in NRC Form 361 - Reactor Plant Event Notification Worksheet (EN#55035). This event is also documented in Attachment 6.

Attachment 8 Page 2 of 6 INDUSTRY GROUND WATER PROTECTION INITIATIVE The following is a summary of 2020 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-44 1/6/20 3,350 NA NA NA NA NA 1-PL-Piez-51 1/6/20 3,320 NA NA NA NA NA G-06 1/6/20 27,100 NA NA NA NA NA G-08 1/6/20 1,920 NA NA NA NA NA G-06 1/15/20 26,700 NA NA NA NA NA 1-PL-Piez-49 1/16/20 4,320 NA NA NA NA NA 1-PL-Piez-44 1/23/20 3,210 NA NA NA NA NA 1-PL-Piez-49 1/23/20 2,950 NA NA NA NA NA 1-PL-Piez-51 1/23/20 3,050 NA NA NA NA NA G-06 1/23/20 23,000 NA NA NA NA NA G-08 1/23/20 3,140 NA NA NA NA NA G-06 1/30/20 32,500 NA NA NA NA NA 1-PL-Piez-44 2/3/20 3,590 NA NA NA NA NA 1-PL-Piez-49 2/3/20 2,700 NA NA NA NA NA 1-PL-Piez-51 2/3/20 7,900 NA NA NA NA NA G-06 2/3/20 34,400 NA NA NA NA NA G-08 2/3/20 2,420 NA NA NA NA NA G-06 2/21/20 29,400 NA NA NA NA NA G-08 2/21/20 3,240 NA NA NA NA NA 1-PL-Piez-44 2/24/20 8,660 NA NA NA NA NA 1-PL-Piez-49 2/24/20 3,320 NA NA NA NA NA 1-PL-Piez-44 2/26/20 3,060 NA NA NA NA NA 1-PL-Piez-44 2/26/20 3,060 NA NA NA NA NA 1-PL-Piez-49 2/26/20 1,900 NA NA NA NA NA 1-PL-Piez-51 2/26/20 3,330 NA NA NA NA NA G-06 2/26/20 15,800 NA NA NA NA NA G-08 2/26/20 2,020 NA NA NA NA NA 1-PL-Piez-44 3/13/20 3,030 NA NA NA NA NA 1-PL-Piez-51 3/13/20 3,090 NA NA NA NA NA G-08 3/13/20 1,650 NA NA NA NA NA 1-PL-Piez-29 3/26/20 1,410 ND ND ND ND ND 1-PL-Piez-49 3/26/20 1,310 ND ND ND ND ND 1-PL-Piez-52 3/26/20 ND 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)

ND = not detected NA = analysis not required

Attachment 8 Page 3 of 6 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 1-PL-Piez-51 3/26/20 2,030 ND ND ND ND ND 1-PL-Piez-46 3/26/20 ND ND ND ND ND ND 1-PL-Piez-50 3/30/20 ND ND NA NA NA NA 1-PL-Piez-48 3/30/20 ND ND NA NA NA NA 1-PL-Piez-47 3/30/20 ND ND ND ND ND ND 1-PL-Piez-44 3/30/20 1,480 ND ND ND ND ND 1-PL-Piez-07 3/30/20 ND ND NA NA NA NA 1-PL-Piez-45 3/30/20 ND ND ND ND ND ND 1-PL-Piez-04 3/30/20 ND ND NA NA NA NA 1-PL-Piez-05 3/30/20 3,530 ND ND ND ND ND 1-PL-Piez-06 3/30/20 ND ND ND ND ND ND 1-PL-Piez-43 3/30/20 ND ND NA NA NA NA 1-PL-Piez-05 4/1/20 5,000 NA NA NA NA NA 1-PL-Piez-06 4/1/20 863 NA NA NA NA NA 1-PL-Piez-43 4/1/20 621 NA NA NA NA NA 1-PL-Piez-45 4/1/20 1,120 NA NA NA NA NA 1-PL-Piez-47 4/1/20 1,760 NA NA NA NA NA 1-PL-Piez-41 4/1/20 1,960 NA NA NA NA NA 1-PL-Piez-05 4/7/20 3,530 NA NA NA NA NA 1-PL-Piez-29 4/7/20 1,410 NA NA NA NA NA 1-PL-Piez-44 4/7/20 1,480 NA NA NA NA NA 1-PL-Piez-49 4/7/20 1,310 NA NA NA NA NA 1-PL-Piez-51 4/7/20 2,030 NA NA NA NA NA 1-PL-Piez-44 4/15/20 2,350 NA NA NA NA NA 1-PL-Piez-49 4/15/20 2,030 NA NA NA NA NA 1-PL-Piez-51 4/15/20 3,040 NA NA NA NA NA G-08 4/15/20 1,800 NA NA NA NA NA G-06 4/22/20 16,300 NA NA NA NA NA 1-PL-Piez-44 4/28/20 4,060 NA NA NA NA NA 1-PL-Piez-49 4/28/20 1,790 NA NA NA NA NA 1-PL-Piez-44 4/29/20 4,060 NA NA NA NA NA 1-PL-Piez-49 4/29/20 1,790 NA NA NA NA NA 1-PL-Piez-44 5/11/20 1,260 NA NA NA NA NA 1-PL-Piez-49 5/11/20 1,890 NA NA NA NA NA 1-PL-Piez-44 5/26/20 7,450 NA NA NA NA NA 1-PL-Piez-49 5/26/20 3,410 NA NA NA NA NA G-08 5/26/20 1,580 NA NA NA NA NA 1-PL-Piez-44 6/8/20 3,570 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 6 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 1-PL-Piez-44 6/8/20 3,570 NA NA NA NA NA 1-PL-Piez-49 6/8/20 2,590 NA NA NA NA NA G-08 6/8/20 1,960 NA NA NA NA NA 1-PL-Piez-44 7/1/20 3,080 NA NA NA NA NA 1-PL-Piez-49 7/2/20 5,250 NA NA NA NA NA G-06 7/14/19 16,500 NA NA NA NA NA 1-PL-Piez-48 7/15/19 1,620 NA NA NA NA NA 1-PL-Piez-49 7/15/19 2,340 NA NA NA NA NA 1-PL-Piez-49 7/16/20 1,140 NA NA NA NA NA 1-PL-Piez-29 7/16/20 ND ND NA NA NA NA 1-PL-Piez-46 7/16/20 ND ND NA NA NA NA 1-PL-Piez-49 7/16/20 1,140 ND NA NA NA NA 1-PL-Piez-48 7/16/20 ND ND NA NA NA NA 1-PL-Piez-52 7/16/20 ND ND NA NA NA NA 1-PL-Piez-50 7/16/20 ND ND NA NA NA NA 1-PL-Piez-28 7/16/20 ND ND NA NA NA NA 1-PL-Piez-47 7/16/20 1,110 ND NA NA NA NA 1-PL-Piez-45 7/16/20 ND ND NA NA NA NA 1-PL-Piez-44 7/16/20 14,900 ND NA NA NA NA 1-PL-Piez-05 7/16/20 3,250 ND NA NA NA NA 1-PL-Piez-06 7/16/20 ND ND NA NA NA NA 1-PL-Piez-43 7/16/20 ND ND NA NA NA NA 1-PL-Piez-44 7/16/20 14,900 NA NA NA NA NA 1-PL-Piez-47 7/16/20 1,110 NA NA NA NA NA 1-PL-Piez-44 7/23/20 23,800 NA NA NA NA NA G-08 7/27/20 2,590 NA NA NA NA NA G-08 8/11/20 2,810 NA NA NA NA NA 1-PL-Piez-44 8/11/20 7,450 NA NA NA NA NA 1-PL-Piez-43 8/13/20 3,210 NA NA NA NA NA G-08 8/25/20 2,090 NA NA NA NA NA 1-PL-Piez-44 8/25/20 3,470 NA NA NA NA NA 1-PL-Piez-49 9/1/20 2,670 NA NA NA NA NA G-08 9/10/20 1,370 NA NA NA NA NA 1-PL-Piez-44 9/10/20 2,810 NA NA NA NA NA 1-PL-Piez-49 9/10/20 2,420 NA NA NA NA NA 1-PL-Piez-29 9/21/20 1,080 NA NA NA NA NA 1-PL-Piez-49 9/21/20 4,940 NA NA NA NA NA 1-PL-Piez-06 9/22/20 1,590 NA NA NA NA NA 1-PL-Piez-44 9/22/20 9,520 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 5 of 6 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 1-PL-Piez-44 8/11/20 7,450 NA NA NA NA NA 1-PL-Piez-43 8/13/20 3,210 NA NA NA NA NA G-08 8/25/20 2,090 NA NA NA NA NA 1-PL-Piez-44 8/25/20 3,470 NA NA NA NA NA 1-PL-Piez-49 9/1/20 2,670 NA NA NA NA NA G-08 9/10/20 1,370 NA NA NA NA NA 1-PL-Piez-44 9/10/20 2,810 NA NA NA NA NA 1-PL-Piez-49 9/10/20 2,420 NA NA NA NA NA 1-PL-Piez-29 9/21/20 1,080 NA NA NA NA NA 1-PL-Piez-49 9/21/20 4,940 NA NA NA NA NA 1-PL-Piez-06 9/22/20 1,590 NA NA NA NA NA 1-PL-Piez-44 9/22/20 9,520 NA NA NA NA NA 1-PL-Piez-47 9/22/20 1,590 NA NA NA NA NA 1-PL-Piez-06 9/22/20 1,170 NA NA NA NA NA 1-PL-Piez-44 9/22/20 8,260 NA NA NA NA NA 1-PL-Piez-47 9/22/20 1,050 NA NA NA NA NA 1-PL-Piez-49 9/22/20 1,170 ND NA NA NA NA 1-PL-Piez-44 9/22/20 8,260 ND NA NA NA NA 1-PL-Piez-47 9/22/20 1,050 ND NA NA NA NA 1-PL-Piez-51 9/22/20 ND ND NA NA NA NA G-8 9/22/20 1,050 ND NA NA NA NA G-08 9/23/20 2,260 NA NA NA NA NA 1-PL-Piez-05 9/28/20 2,860 NA NA NA NA NA 1-PL-Piez-49 10/12/20 3,000 NA NA NA NA NA 1-PL-Piez-44 10/12/20 3,070 NA NA NA NA NA 1-PL-Piez-51 10/13/20 2,250 NA NA NA NA NA 1-PL-Piez-51 10/14/20 ND NA NA NA NA NA 1-PL-Piez-44 10/21/20 6,410 NA NA NA NA NA 1-PL-Piez-49 10/21/20 2,890 NA NA NA NA NA 1-PL-Piez-51 10/21/20 2,540 NA NA NA NA NA 1-PL-Piez-29 11/9/20 1,030 ND NA NA NA NA 1-PL-Piez-49 11/9/20 1,720 ND NA NA NA NA 1-PL-Piez-44 11/12/20 3,840 NA NA NA NA NA 1-PL-Piez-49 11/12/20 2,610 NA NA NA NA NA 1-PL-Piez-44 11/19/20 2,090 ND NA NA NA NA 1-PL-Piez-05 11/23/20 3,380 ND NA NA NA NA 1-PL-Piez-44 11/24/20 2,140 NA NA NA NA NA 1-PL-Piez-49 11/24/20 2,470 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 6 of 6 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 G-08 11/25/20 2,540 NA NA NA NA NA G-08 12/8/20 3,210 NA NA NA NA NA 1-PL-Piez-49 12/8/20 2,450 NA NA NA NA NA 1-PL-Piez-51 12/8/20 2,540 NA NA NA NA NA 1-PL-Piez-51 12/8/20 1,790 ND NA NA NA NA G-09 12/15/20 2,370 NA NA NA NA NA 1-PL-Piez-48 12/15/20 2,360 NA NA NA NA NA G-08 12/23/20 4,360 NA NA NA NA NA 1-PL-Piez-44 12/23/20 3,470 NA NA NA NA NA 1-PL-Piez-49 12/23/20 9,630 NA NA NA NA NA 1-PL-Piez-51 12/23/20 3,760 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)

ND = not detected

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