ML22118A346

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Annual Radioactive Effluent Release Report
ML22118A346
Person / Time
Site: Surry  Dominion icon.png
Issue date: 04/28/2022
From: Henderson J
Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
22-123
Download: ML22118A346 (34)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 APR 2 8 2022 United States Nuclear Regulatory Commission Serial No.22-123 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 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the Surry Power Station Annual Radioactive Effluent Release Report for January 1, 2021, through December 31, 2021. 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 2021 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.

Sincerely, J. Henderson 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.22-123 SPS Annual Rad Effluent Report Docket Nos. 50-280, 50-281 ATTACHMENT 2021 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 FOR SURRY POWER STATION January 1, 2021 through December 31, 2021 Index Section No. Subject Page Executive Summary 1 2 Purpose and Scope 2 3 Discussion 3 4 Supplemental Infonnation 4 5 Effluent Release Data 5 Attachment 1 Effluent Release Data Attachment 2 Annual and Qua1terly 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 lnoperability 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 Indust1y Ground Water Protection Initiative

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION January J, 202 J through December 3 J, 2021 Prepared By:

I 12:.: uJ. ~ 0 7 J. W. Abbott, Jr.

Health Physicist J. R. Hopkins Superintendent Health Physics Technical Services Approved By:

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Terry Manager Radiological Protection and Chemistry

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 I 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 Rep011 describes the radiological effluent control prngram conducted at Surry Power Station during the 2021 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 Rep011ing 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 repo11 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 2021 effluent release data, 10CFR50 Appendix I dose calculations were performed in accordance with the Offsite Dose Calculation Manual. The dose calculations are as follows:

l. The total body dose due to liquid effluents was 3.91 E-04 mrem, which is 6.52E-03%

of the 6 mrem dose limit. The critical organ dose due to liquid effluents was 4.66E-04 mrem to the GI-LLI, which is 2.33E-03% of the 20 mrem dose limit.

2. The air dose due to noble gases in gaseous effluents was 3.82E-05 mrad gamma, which is 1.91 E-04% of the 20 mrad gamma dose limit, and I .79E-05 mrad beta, which is 4.48E-05% of the 40 mrad beta dose limit.
3. The critical organ dose from gaseous effluents due to 1-131, 1-133, H-3, and particulates with half-lives greater than 8 days is 9.13E-02 mrem, which is 3.04E-0l % of the 30 mrem dose limit.

There were no major changes to the radioactive liquid, gaseous or solid waste treatment systems during this repo11ing 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.

Purpose and Scope Attachment I 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 qua1terly 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 2021.

As required by Technical Specification 6.8.B, changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this repmt 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 repmt shall include information to suppmt the reason for the change and a summary of the 10CFRS0.59 evaluation. In lieu of rep01ting major changes in this repo1t, major changes to the radioactive waste treatment systems may be submitted as pait 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 repott. 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 repo1ting protocol. Sample analyses from ground water wells that are not pa1t of the Radiological Environmental Monitoring Program are also provided in Attachment 8.

2

Discussion The basis for the calculation of the percent of technical specification for the critical organ in Table I A of Attachment 1 is the ODCM, Section 6.3.1, which requires that the dose rate for iodine- I 31, iodine-I 33, 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 1si, 2nd , 3rd , and 4th quarters.

The basis for the calculation of the percent of technical specification for the total body and skin in Table I A 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 repoited 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- I 31, iodine-I 33, tritium and all radionuclides in particulate form with half-lives greater than 8 days, was modeled as a child at 0.33 miles for the 1st quarter and a child at 2.0 I miles for the 2nd

  • 3rd , and 4 th quaiters. The bone was selected as the critical organ via the ingestion pathway for 2021. 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 dete1mined for this individual.

No effluent radiation monitors were inoperable for greater than 30 days in 2021. This is repo1ted in as required by the ODCM, Section 6.2.2 and 6.3.2.

There were no unplanned liquid release and no unplanned gaseous releases in 2021. 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 repo1ted as Not Detected (N/D) on Attachment 1 of this repo1t.

When all isotopes listed on Attachment 1 for a paiticular 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.

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 repo1ting period identified no change in sample locations for the Radiological Environmental Monitoring Program.

4

EFFLUENT RELEASE DATA January 1, 2021 through December 31, 2021 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 I TABLE IA Page I of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/21 TO 12/31/21 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND %EST. ERROR QUARTER QUARTER A. FISSION & ACTIVATION GASES

1. TOT AL RELEASE Ci 6.46E-03 8.0 I E-02 l.80E+01
2. AVE RELEASE RATE FOR PERIOD µCi/sec 8.3 IE-04 l.02E-02 B. IODINE
1. TOTAL 1-131 Ci N/D 2.82E-09 2.80E+0l
2. A VE RELEASE RA TE FOR PERIOD ~tCi/sec NIA 3.59E-10 C. PARTICULATE I. HALF-LIFE >8 DAYS Ci l .04E-05 l.15E-05 2.80E+0l
2. A VE RELEASE RA TE FOR PERIOD ~tCi/sec I.34E-06 1.46E-06
3. GROSS ALPHA RADIOACTIVITY Ci N/D N/D D. TRITIUM I. TOT AL RELEASE Ci 7.30E+00 l.29E+0I 3.I0E+0l
2. AVE RELEASE RATE FOR PERIOD ~tCi/sec 9.39E-01 l.63E+00 E. CARBON-14 I. TOT AL RELEASE Ci 5.70E-01 7.06E+00
2. AVE RELEASE RATE FOR PERIOD µCi/sec 7.33E-02 8.98E-0l PERCENTAGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE  % 3.16E-03 2.86E-03 TOTAL BODY DOSE RATE  % 2.64E-05 2.39E-06 SKIN DOSE RATE  % 6.44E-06 6.93E-07

Attachment l TABLE lA Page 2 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/21 TO 12/31/21 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH  % EST. ERROR QUARTER QUARTER A. FISSION & ACT!V ATION GASES I. TOT AL RELEASE Ci 4.67E-02 6.92E-02 l.80E+0l

2. A VE RELEASE RATE FOR PERIOD ~tCi/sec 5.88E-03 8.70E-03 B. IODINE I. TOTAL 1-131 Ci N/D NID 2.80E+0l
2. A VE RELEASE RA TE FOR PERIOD µCi/sec NIA NIA C. PARTICULATE
1. HALF-LIFE >8 DAYS Ci l.96E-06 8.69E-07 2.80E+0I
2. A VE RELEASE RA TE FOR PERIOD µCi/sec 2.47E-07  ! .09E-07
3. GROSS ALPHA RADIOACTIVITY Ci N/D N/D D. TRITIUM I. TOT AL RELEASE Ci 6.52E+00 2.00E+0l 3.I0E-t-01
2. A VE RELEASE RA TE FOR PERIOD ~tCi/sec 8.21 E-0 I 2.52E+00 E. CARBON-14 I. TOT AL RELEASE Ci 4.12E+00 6.I0E+00
2. A VE RELEASE RATE FOR PERIOD µCi/sec 5.lSE-01 7.67E-0l PERCENT AGE OF T.S. LIMITS CRITICAL ORGAN DOSE RATE  % I .28E-03 3.98E-03 TOT AL BODY DOSE RA TE  % 8.29E-08 3.11 E-07 SKIN DOSE RA TE  % 3.26E-08 l.22E-07

Attachment 1 TABLE 1B Page 3 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/21 TO 12/31/21 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER I. 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 7.S0E-02 Xe-135 Ci N/D NID NID I .S0E-04 Xe-135m Ci N/D N/D N/D N/D Xe-138 Ci NID NID N/D N/D Xe-13 lm Ci N/D NID N/D NID Xe-133m Ci N/D N/D NID NID Ar-41 Ci NID N/D N/D NID TOTAL FOR PERIOD Ci NIA NIA NIA 7.52E-02

2. IODINES

[-131 Ci NID 2.82E-09 NID NID 1-133 Ci NID NID NID NID 1-135 Ci N/D N/D NID N/D TOTAL FOR PERIOD Ci NIA 2.82E-09 NIA NIA

3. PARTICULATES Sr-89 Ci NID NID NID N/D Sr-90 Ci NID N/D N/D NID Cs-134 Ci NID N/D N/D NID Cs-137 Ci NID N/D N/D N/D Ba-140 Ci NID N/D N/D N/D La-140 Ci NID N/D N/D NID Co-58 Ci N/D N/D NID N/D Co-60 Ci N/D NID N/D N/D Mn-54 Ci N/D NID NID NID Fe-59 Ci NID N/D N/D NID Zn-65 Ci NID NID N/D N/D Mo-99 Ci NID N/D NID N/D Ce-141 Ci N/D NID N/D N/D Ce-144 Ci NID N/D NID N/D C-14 Ci N/D N/D NID 6.63E+00 TOTAL FOR PERIOD Ci NIA NIA NIA 6.63E+00

Attachment 1 TABLE 1B Page 4 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/21 TO 12/31/21 GASEOUS EFFLUENTS-MIXED MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER I. 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 4.67E-02 6.75E-02 Xe-135 Ci N/D N/D N/D 2.67E-04 Xe-135m Ci N/D N/D N/D N/D Xe-138 Ci N/D N/D N/D N/D Xe-13lm Ci N/D N/D N/D N/D Xe-l33m Ci N/D N/D N/D N/D Ar-41 Ci N/D N/D N/D N/D TOT AL FOR PERIOD Ci NIA NIA 4.67E-02 6.77E-02

2. IODINES J. I 31 Ci N/D N/D N/D N/D 1-133 Ci N/D N/D N/D N/D 1-135 Ci N/D N/D N/D N/D TOT AL FOR PERIOD Ci NIA NIA NIA NIA
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 NID 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 8.48E-09 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 4.12E+00 5.97E-"-00 TOTAL FOR PERIOD Ci 8.48E-09 NIA 4.l2E+00 5.97E+00

Attachment I TABLE IC Page 5 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/21 TO 12/31/21 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 NID N/D N/D Kr-87 Ci N/D N/D N/D N/D Kr-88 Ci N/D NID N/D N/D Xe-133 Ci N/D NID N/D 4.49E-03 Xe-135 Ci N/D N/D N/D NID Xe-135m Ci N/D NID N/D NID Xe-138 Ci N/D N/D N/D N/D Xe-!31m Ci NID NID N/D NID Xe-133m Ci N/D N/D NID NID Ar-41 Ci 6.84E-04 4.07E-04 5.78E-03 N/D TOTAL FOR PERIOD Ci 6.84E-04 4.07E-04 5.78E-03 4.49E-03
2. IODINES 1-131 Ci N/D N/D N/D N/D 1-133 Ci N/D N/D N/D N/D 1-135 Ci N/D N/D N/D N/D TOT AL FOR PERIOD Ci NIA NIA NIA NIA
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 NID N/D N/D Cs-137 Ci N/D N/D N/D N/D Ba-140 Ci N/D N/D N/D NID La-140 Ci NID N/D N/D N/D Co-58 Ci N/D l.15E-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 NID NID N/D Mo-99 Ci NID N/D N/D N/D Ce-141 Ci NID N/D N/D N/D Ce-144 Ci N/D N/D N/D N/D Nb-95 Ci 6.63E-06 N/D N/D N/D Zr-95 Ci 3.78E-06 N/D N/D N/D C-14 Ci 6.03E-02 3.59E-02 5.lOE-01 3.96E-01 TOT AL FOR PERIOD Ci 6.03E-02 3.59E-02 5. l0E-01 3.96E-0I

Attachment 1 TABLElC Page 6 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/21 TO 12/31/21 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER I. FISSION & ACTIVATION GASES Kr-85 Ci NID NID N/D NID Kr-85m Ci NID NID N/D N/D Kr-87 Ci N/D N/D N/D N/D Kr-88 Ci N/D N/D N/D NID Xe-133 Ci N/D NID N/D I .42E-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 NID Xe-13lm Ci N/D N/D N/D N/D Xe-133m Ci N/D N/D N/D N/D Ar-41 Ci NID N/D N/D N/D TOTAL FOR PERIOD Ci NIA NIA NIA l.42E-03

2. IODINES 1-131 Ci NID NID NID N/D 1-133 Ci NID NID N/D N/D 1-135 Ci NID N/D N/D N/D TOT AL FOR PERIOD Ci NIA NIA NIA NIA
3. PARTICULATES Sr-89 Ci N/D NID NID NID Sr-90 Ci N/D N/D NID NID Cs-134 Ci N/D N/D N/D NID Cs-137 Ci N/D NID NID N/D Ba-140 Ci N/D N/D NID N/D La-140 Ci N/D N/D NID N/D Co-58 Ci l .96E-06 8.69E-07 N/D NID Co-60 Ci N/D N/D N/D N/D Mn-54 Ci NID N/D N/D NID Fe-59 Ci N/D N/D N/D N/D Zn-65 Ci NID NID NID NID Mo-99 Ci NID N/D N/D N/D Ce-141 Ci N/D NID N/D NID Ce-144 Ci N/D N/D N/D NID C-14 Ci N/D N/D NID l.25E-0 I TOT AL FOR PERIOD Ci l.96E-06 8.69E-07 NIA 1.25E-0 I

Attachment I TABLE2A Page 7 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/21 TO 12131/21 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. TOT AL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) Ci 7.07E-04 3.82E-03 2.00Ei-01
2. A VE DIL. CONC. DURING PERIOD ~tCilmL 2.78E-13 J.77E-12
3. PERCENT OF APPLICABLE LIMIT  % 9.36E-07 2.59E-06 B. TRITIUM I. TOTAL RELEASE Ci 3.29E+02 8.25E+02 2.00E+0l
2. A VE DIL. CONC. DURING PERIOD µCilmL l .29E-07 3.81 E-07
3. PERCENT OF APPLICABLE LIMIT  % l .29E-03 3.81E-03 C. DISSOLVED AND ENTRAINED GASES I. TOT AL RELEASE Ci NID NID 2.00E+0l
2. A VE DIL. CONC. DURING PERIOD µCilmL NIA NIA
3. PERCENT OF APPLICABLE LIMIT  % NIA NIA D. GROSS ALPHA RADIOACTIVITY I. TOT AL RELEASE Ci NID NID 2.00E+0l E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS 5.29E+07 5.39E+07 3.00E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 2.54E+l2 2.l 7E+ 12 3.00E+00

Attachment 1 TABLE2A Page 8 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/21 TO 12131/21 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH  % EST. ERROR QUARTER QUARTER A. FISSION AND ACTIVATION PRODUCTS I. TOT AL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) Ci 5.44E-03 2.87E-03 2.00E+0l

2. A VE OIL. CONC. DURING PERIOD ~1Ci/mL I. 72E-l 2 IJ0E-12
3. PERCENT OF APPLICABLE LIMIT  % 2.2 IE-06 l .69E-06 B. TRITIUM I. TOT AL RELEASE Ci l.95E+02 4.2IE+02 2.00E+0 I
2. A VE OIL. CONC. DURING PERIOD µCilmL 6.16E-08 1.91 E-07
3. PERCENT OF APPLICABLE LIMIT  % 5.40E-04 3.43E-03 C. DISSOL YEO AND ENTRAINED GASES I. TOT AL RELEASE Ci NID N/D 2.00E+0l
2. A VE OIL. CONC. DURING PERIOD ~1Ci/mL NIA NIA
3. PERCENT OF APPLICABLE LIMIT  % NIA NIA D. GROSS ALPHA RADIOACTIVITY I. TOT AL RELEASE Ci NID NID 2.00E+0I E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS 5.41E+07 5.46E+07 3.00E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 3.17E+I2 2.21E+l2 3.00E+00

Attachment 1 TABLE2B Page 9 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 111121 TO 12/31/21 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER Sr-89 Ci NID NID NID NID Sr-90 Ci NID NID NID NID Fe-55 Ci NID NID NID NID Cs-134 Ci NID NID NID NID Cs-137 Ci l.13E-04 l.28E-04 6.65E-05 4.63E-05 1-13 I Ci NID NID NID NID Co-58 Ci NID NID 3.24E-05 l .39E-03 Co-60 Ci NID NID I .36E-04 7.80E-04 Fe-59 Ci NID NID NID NID Zn-65 Ci NID NID NID NID Mn-54 Ci NID NID NID NID Cr-51 Ci NID NID NID 4.8 IE-05 Zr-95 Ci NID NID NID NID Nb-95 Ci NID NID NID NID Mo-99 Ci NID NID NID NID Tc-99m Ci NID NID NID NID Ba-140 Ci NID NID NID NID La-140 Ci NID NID NID NID Ce-141 Ci NID NID NID NID Ce-144 Ci NID NID NID NID Sb-124 Ci NID NID NID 9.ISE-05 Sb-125 Ci NID NID 3.60E-04 l.34E-03 Nd-147 Ci NID NID NID NID TOT AL FOR PERIOD Ci l. l 3E-04 l.28E-04 5.95E-04 3.70E-03 Xe-133 Ci NID NID NID NID Xe-135 Ci NID NID NID NID TOT AL FOR PERIOD Ci NIA NIA NIA NIA

Attachment I TABLE2B Page lO of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD: 1/1/21 TO 12/31/21 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-I 37 Ci 2.02E-04 2.36E-04 5.75E-05 1.S0E-05 1-131 Ci N/D N/D NID N/D Co-58 Ci N/D N/D 2.S0E-03 6.65E-04 Co-60 Ci N/D N/D 7.57E-04 7.96E-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 3.20E-05 N/D Cr-51 Ci N/D N/D 6.69E-05 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-I 40 Ci N/D NID 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 2.00E-05 N/D Sb-125 Ci N/D N/D 1.8 I E-03 I.86E-03 Nd-147 Ci N/D N/D N/D 5.87E-06 Nb-97 Ci N/D N/D N/D N/D TOT AL FOR PERIOD Ci 2.02E-04 2.36E-04 5.24E-03 2.63E-03 Xe-133 Ci N/D N/D N/D N/D Xe-135 Ci N/D N/D N/D N/D TOT AL FOR PERIOD Ci NIA NIA NIA NIA

Attachment 1 TABLE 3 Page 11 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD: 1/1/21 - 12131/21 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 l.03E+0l Note I l.00E+0l bottoms, etc. Ci 3.01E+02 3.00E+0l
b. Dry compressible waste, contaminated m3 4.21E+02 Note 2 l.00E+0l equip., etc. Ci 2.BE-01 3.00E+0l
c. Irradiated components, control mJ 0.00E+00 l.00E+0I rods, etc. Ci 0.00E+00 3.00E+0I
d. Other (Waste oil) nl 3.57E+00 Note 3 l.00E+0l Ci 3.84E-03 3.00E+0l
2. Estimate of major nuclide composition (by type of waste)
a. Fe-55  % 7.44E+00 Co-58  % 9.12E+00 Co-60  % 3.31E+0l Ni-63  % 2.55E+0l Sn-113  % l.64E+00 Sb-125  % 1.92E+0l Cs-137  % 1.32E+00
b. Mn-54  % 4.17E+00 Fe-55  % 4.83E+00 Co-58  % 4.39E+00 Co-60  % 6.70E+0I Ni-63  % 7.29E+00 Zr-95  % 3.02E+00 Nb-95  % 5.26E+00 Sb-125  % I.43E+00 Pu-241  % 1.38E+00
c. NIA  % NIA
d. H-3  % 9.87E+0l Cs-137  % l.31E+00

Attachment I TABLE3 Page 12 of 12 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD: 1/1/21

  • 12/31/21 CONTINUED SURRY POWER STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)
3. Solid Waste Disposition Number of Shipments Destination 11 Truck Oak Ridge, TN (EnergySolutions) 3 Truck Erwin, TN (ResinSolutions)

B. IRRADIATED FUEL SHIPMENT (Disposition)

Number of Shipments Mode of Transportation Destination 0

NOTE I: 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 3.15E+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 repo11ing period is 3.91 E+0l 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 I of 1 ANNUAL AND OUARTERL Y 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 2021 Total Body GI-LU Liver (mrem) (mrem) (mrem) 1st Quarter 6.42E-05 6.66E-05 6.45E-05 2nd Quarter 1.93E-04 2.26E-04 1.91 E-04 3rd Quarter 3.59E-05 6.53E-05 3.46E-05 4th Quarter 9.78E-05 1.09E-04 9.80E-05 Annual 3.91E-04 4.66E-04 3.88E-04 GASEOUS - Air Dose 2021 Gamma Beta (rnrad) (mrad) 1st Quarter 3.43E-05 I .2 lE-05 2nd Quarter 3.27E-06 4.06E-06 3rd Quarter 1.26E-07 3.73E-07 4th Quarter 4.71E-07 1.39E-06 Annual 3.82E-05 1.79E-05 GASEOUS - Organ Dose Annual Maximum by Quaiter 2021 Maximum Child/Bone Receptor I Organ (mrern) (mrem) 1st Quarter 7.93E-03 1. 17E-02 Child/Bone 2nd Quarter 3.60E-02 3.60E-02 Child/Bone 3rd Quarter 1.86E-02 1.86E-02 Child/Bone 4th Quarter 2.87E-02 2.87E-02 Child/Bone Annual 9.13E-02

Attachment 3 Page I 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 reprnt, are included with this attachment. There were no revisions to the ODCM implemented during this reporting period.

Attachment 4 Page I of I 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 I INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION The Annual Radioactive Effluent Release Report shall explain why monitoring instrumentation required by Attachments l 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 Attachments l and 5 of the ODCM were inoperable greater than 30 days during this repo11ing period.

Attachment 6 Page I of I UNPLANNED RELEASES In accordance with the ODCM reporting requirements, no unplanned liquid or unplanned gaseous releases occurred during the repo1ting period.

Attachment 7 Page I ofl LOWER LIMIT OF DETECTION (LLD) FOR EFFLUENT SAMPLE ANALYSIS GASEOUS: Isotope Reguired LLD Typical LLD Kr-87 1.00E-04 2. l0E 1.78E-05 Kr-88 J.00E-04 1.11 E 1.88E-05 Xe-133 l.00E-04 9.74£ 4.06E-05 Xe-133m l .00E-04 3.93E 4.06E-05 Xe-135 l .00E-04 5.50£ 5.76E-06 Xe-135rn l .00E-04 8.98£ 9.41E-05 Xe-138 l .00E-04 l.81E 9.90£-05 I- I 31 1.00E-12 4.06E 4.06E-13 1-133 1.00E-10 4.06E-l l 4.06E- 11 Sr-89 l .00E-11 1.20£ 3.51E-12 Sr-90 1.00E-11 1.91 E 4.86£-13 Cs-134 1.00E-11 I.24E-l 3 - 7.83£-13 Cs- 137 1.00E-11 l.85E- l 3 - 8.48E-13 Mn-54 l.00E-11 1.55£ 8.21£-13 Fe-59 l .00E-11 4.42£ 2.01 E-12 Co-58 l .00E-11 l.70E 9.65E-13 Co-60 1.00E-11 2.92£ 1.16E-12 Zn-65 1.00E-11 5.54E-I 4 - 2.14E-12 Mo-99 1.00E-11 4.06E 4.06E-l 2 Ce-141 l.00E-11 1.66E 6.87E- I 3 Ce-144 1.00E-1 I 5.96E-l 3 - 3.06E-12 Alpha l .00E-11 l.66E 2.08£-14 Tritium l .00E-06 5.23£ 1.07£-07 LIQUID: Sr-89 5.00E-08 4.39E-09 - 6.82E-07 Sr-90 5.00E-08 6.91E-10 - 2.05E-08 Cs-134 5.00E-07 2.1 0E-08 - 6.39E-08 Cs-137 5.00E-07 2.70E-08 - 1.l0E-07 1-131 l .00E-06 2.65E-08 - 5.32E-08 Co-58 5.00E-07 2.0IE-08 - 7.24E-08 Co-60 5.00E-07 5.51 E-09 - 8.llE-08 Fe-59 5.00E-07 8.05E-09 - 9.80E-08 Zn-65 5.00E-07 I .06E-08 - l .66E-07 Mn-54 5.00E-07 2.28£-08 - 7.99E-08 Mo-99 5.00E-07 4.95E-07 - 4.95E-07 Ce-141 5.00E-07 3.48E-08 - 6.75E-08 Ce-144 5.00E-07 1.59E-07 - 3.47E-07 Fe-55 l .00E-06 4.07E-08 - 9.91 E-07 Alpha l.00E-07 2.S0E-08 - 3.23£-08 Tritium I .00E-05 1.29£-06 - 2.64E-06 Xe-133 l .00E-05 6.67E-08 - 2.72£-07 Xe-135 l.00E-05 2.50E-08 - 4.88E-08 Xe-133m I .00E-05 2.22E-07 - 3.77E-07 Xe-135m 1.00E-05 1.26£-06 - 2.68£-06 Xe-138 l .00E-05 6.40E-07 - 7.63E-06 Kr-87 l .00E-05 7.81E-08 - 2.21 E-07 Kr-88 1.00E-05 8.06E-08 - 1.97E-07

Attachment 8 Page I of 6 INDUSTRY GROUND WATER PROTECTION INITIATIVE The following is a summary of 2021 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 1/12/21 855 NA NA NA NA NA 1-PL-Piez-44 1/12/21 25100 NA NA NA NA NA I-PL-Piez-49 1/12/21 25300 NA NA NA NA NA I-PL-Piez-51 1/12/21 1940 NA NA NA NA NA 1-PL-Piez-50 1/14/21 25.1 NA NA NA NA NA G-08 1/19/21 606 NA NA NA NA NA I -PL-Piez-44 1/19/21 16700 NA NA NA NA NA I-PL-Piez-48 1/19/21 198 NA NA NA NA NA l-PL-Piez-49 l/19/21 26500 NA NA NA NA NA 1-PL-Piez-51 1/19/21 2170 NA NA NA NA NA G-08 2/8/21 2850 NA NA NA NA NA 1-PL-Piez-49 2/8/21 1740 NA NA NA NA NA 1-PL-Piez-51 2/8/21 2710 NA NA NA NA NA l-PL-Piez-48 2/9/21 <691 NA NA NA NA NA 1-PL-Piez-50 2/9/21 <691 NA NA NA NA NA l-PL-Piez-48 2110/21 <681 NA NA NA NA NA 1-PL-Piez-48 2/10/21 102 NA NA NA NA NA 1-PL-Piez-50 2/10/21 <681 NA NA NA NA NA G-08 2/22/21 9530 NA NA NA NA NA 1-PL-Piez-44 2/22/21 5700 NA NA NA NA NA 1-PL-Piez-49 2/22/21 5180 NA NA NA NA NA 1-PL-Piez-51 2/22/21 2380 NA NA NA NA NA 1-PL-Piez-29 2/24/21 <954 ND <61.25 <4.17 <.807 NA 1-PL-Piez-46 2/24/21 <951 ND <78.24 <3.82 <.824 NA 1-PL-Piez-52 2/24/21 <953 NA NA NA NA NA 1-PL-Piez-04 2/25/21 <949 NA NA NA NA NA 1-PL-Piez-05 2/25/21 3120 NA <44.39 <4.09 <.815 NA I-PL-Piez-06 2/25/21 <950 ND <176.8 <3.85 <.778 NA 1-PL-Piez-07 2/25/21 <953 NA NA NA NA NA 1-PL-Piez-43 2/25/21 <950 NA NA NA NA NA 1-PL-Piez-45 2/25/21 <951 ND <118.7 <4.59 <.895 NA 1-PL-Piez-47 2/25/21 1300 ND <48.91 <4.78 <.832 NA 1-PL-Piez-49 3/3/21 1700 NA <146.2 <3.72 <.870 NA NA Analysis not required.

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

Attachment 8 Page 2 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 l-PL-Piez-51 3/3/21 1360 ND <127.7 <4.14 <.947 NA 1-PL-Piez-51 3/4/21 3250 NA NA NA NA NA G-08 3/10/21 3230 NA NA NA NA NA G-08 3/22/21 2600 NA NA NA NA NA 1-PL-Piez-44 3/22/21 1380 ND <40.65 <4.72 <.975 NA l-PL-Piez-48 3/22/21 I 05 NA NA NA NA NA l-PL-Piez-49 3/22/21 2070 NA NA NA NA NA l-PL-Piez-50 3/22/21 0 NA NA NA NA NA l-PL-Piez-51 3/22/21 2140 NA NA NA NA NA G-08 3/24/21 2600 NA NA NA NA NA G-08 3/30/21 2550 NA NA NA NA NA l-PL-Piez-44 3/30/21 1460 NA NA NA NA NA l-PL-Piez-48 3/30/21 86.1 NA NA NA NA NA l -PL-Piez-49 3/30/21 1650 NA NA NA NA NA l-PL-Piez-50 3/30/21 0 NA NA NA NA NA 1-PL-Piez-51 3/30/21 1980 NA NA NA NA NA G-08 4/13/21 3030 NA NA NA NA NA 1-PL-Piez-44 4/13/21 3150 NA NA NA NA NA 1-PL-Piez-51 4/13/21 1980 NA NA NA NA NA l-PL-Piez-49 4/15/21 1950 NA NA NA NA NA G-08 4/25/21 3170 NA NA NA NA NA l-PL-Piez-44 4/25/21 2550 NA NA NA NA NA l-PL-Piez-49 4/25/21 1310 NA NA NA NA NA 1-PL-Piez-51 4/25/2 I 1320 NA NA NA NA NA G-08 5/10/21 4460 NA NA NA NA NA l-PL-Piez-49 5/10/2 I 1460 ND NA NA NA NA l-PL-Piez-51 5/10/21 2200 ND NA NA NA NA 1-PL-Piez-44 5/14/21 1930 ND NA NA NA NA 1-PL-Piez-44 5/20/21 2480 ND NA NA NA NA l-PL-Piez-47 5/21/21 621 ND NA NA NA NA G-08 5/23/21 3920 ND NA NA NA NA l-PL-Piez-44 5/23/21 1340 NA NA NA NA NA l-PL-Piez-49 5/23/21 856 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 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 l-PL-Piez-51 5/23/21 2240 NA NA NA NA NA l-PL-Piez-50 5/31/21 <786 NA NA NA NA NA 1-PL-Piez-06 6/1 /2 l <790 NA NA NA NA NA l-PL-Piez-08 6/1/21 703 NA NA NA NA NA l-PL-Piez-09 6/1/21 159 NA NA NA NA NA l-PL-Piez-20 6/1/21 466 NA NA NA NA NA l-PL-Piez-22 6/1/21 658 NA NA NA NA NA I-PL-Piez-24 6/1/21 575 NA NA NA NA NA l-PL-Piez-28 6/1/21 388 NA NA NA NA NA 1-PL-Piez-43 6/1/21 <770 NA NA NA NA NA l-PL-Piez-44 6/1/21 1560 NA NA NA NA NA l-PL-Piez-45 6/1/21 <787 NA NA NA NA NA l-PL-Piez-47 6/1/21 1110 NA NA NA NA NA l-PL-Piez-50 6/1/21 757 NA NA NA NA NA 1-PL-Piez-34 6/7/21 505 NA NA NA NA NA l-PL-Piez-36 6/7/21 33.4 NA NA NA NA NA l-PL-Piez-37 6/7/21 577 NA NA NA NA NA l-PL-Piez-38 6/7/21 237 NA NA NA NA NA l -PL-Piez-39 6/7/21 429 NA NA NA NA NA l-PL-Piez-40 6/7/21 309 NA NA NA NA NA l-PL-Piez-53 617/21 0 NA NA NA NA NA I-PL-Piez-03 6/8/21 251 NA NA NA NA NA 1-PL-Piez-05 6/8/21 2590 NA NA NA NA NA 1-PL-Piez-23 6/8/21 442 NA NA NA NA NA I-PL-Piez-48 6/8/21 336 NA NA NA NA NA I-PL-Piez-29 6/9/21 <772 NA NA NA NA NA 1-PL-Piez-46 6/9/21 <761 NA NA NA NA NA l-PL-Piez-48 6/9/21 <768 ND NA NA NA NA 1-PL-Piez-51 6/9/21 1410 ND NA NA NA NA l -PL-Piez-52 6/9/21 <913 ND NA NA NA NA G-08 6/17/21 18400 ND NA NA NA NA G-08 6/18/21 17300 ND NA NA NA NA G-08 6/21/21 3330 ND NA NA NA NA l-PL-Piez-49 6/21/21 2640 ND NA NA NA NA G-08 7/6/21 2910 ND NA NA NA NA I -PL-Piez-44 7/6/21 2850 NA NA NA NA NA l-PL-Piez-51 7/6/21 2460 NA NA NA NA NA l-PL-Piez-49 7/13/21 1850 NA NA NA NA NA G-08 7/19/21 3920 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 l -PL-Piez-51 7/19/21 2140 NA NA NA NA NA I -PL-Pi ez-44 7/21 /2 l 2490 NA NA NA NA NA l-PL-Piez-49 7/21 /2 l 2040 NA NA NA NA NA l-PL-Piez-44 7/31/21 2230 NA NA NA NA NA I-PL-Piez-51 7/31/21 2690 NA NA NA NA NA G-08 8/2/21 3820 NA NA NA NA NA l-PL-Piez-44 8/2/21 3610 NA NA NA NA NA l-PL-Piez-4 7 8/2/21 1910 NA NA NA NA NA l-PL-Piez-51 8/2/21 2470 NA NA NA NA NA l-PL-Piez-48 8/4/21 282 NA NA NA NA NA 1-PL-Piez-44 8/16/21 2000 NA NA NA NA NA l-PL-Piez-51 8/16/21 5780 NA NA NA NA NA G-08 8/17/21 4120 NA NA NA NA NA l-PL-Piez-51 8/17/21 6840 NA NA NA NA NA l-PL-Piez-07 8/19/21 645 NA NA NA NA NA l-PL-Piez-49 8/19/21 7240 NA NA NA NA NA G-08 8/24/21 5680 ND ND ND ND NA l-PL-Piez-29 8/24/21 852 ND ND ND ND NA 1-PL-Piez-44 8/24/21 2090 ND ND ND ND NA I-PL-Piez-46 8/24/21 425 ND ND ND ND NA l -PL-Piez-4 7 8/24/21 544 ND ND ND ND NA 1-PL-Piez-49 8/24/21 1630 ND ND ND ND NA l-PL-Piez-51 8/24/21 7380 ND ND ND ND NA G-08 8/31/21 6560 NA NA NA NA NA l-PL-Piez-44 8/31/21 2170 NA NA NA NA NA 1-PL-Piez-51 8/31/21 15700 NA NA NA NA NA 1-PL-PiezA9 9/1/21 714 NA NA NA NA NA l-PL-Piez-51 9/1/21 11300 NA NA NA NA NA 1-PL-Piez-49 9/13/21 2430 ND ND ND ND NA I-PL-Piez-51 9/13/21 19500 NA NA NA NA NA G-08 9/14/21 6660 NA NA NA NA NA 1-PL-Piez-44 9/14/21 1970 NA NA NA NA NA 1-PL-Piez-48 9/15/21 <704 NA NA NA NA NA 1-PL-Piez-48 9/15/21 233 NA NA NA NA NA 1-PL-Piez-25 9/20/21 220 NA NA NA NA NA l-PL-Piez-29 9/20/21 1140 ND NA NA NA NA 1-PL-Piez-46 9/20/21 <705 ND NA NA NA NA 1-PL-Piez-49 9/20/21 2280 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 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-50 9/20/21 <723 ND NA NA NA NA 1-PL-Piez-51 9/20/21 16600 ND NA NA NA NA 1-PL-Piez-52 9/20/21 <710 ND NA NA NA NA I-PL-Piez-04 9/27/21 <739 ND NA NA NA NA 1-PL-Piez-05 9/27/21 2330 NA NA NA NA NA 1-PL-Piez-06 9/27/21 <748 NA NA NA NA NA l-PL-Piez-43 9/27/21 <730 NA NA NA NA NA 1-PL-Piez-44 9/27/21 1900 NA NA NA NA NA 1-PL-Piez-45 9/27/21 <732 ND NA NA NA NA l-PL-Piez-07 9/28/21 <726 ND NA NA NA NA 1-PL-Piez-07 9/28/21 483 ND NA NA NA NA l-PL-Piez-33 9/28/21 12.2 ND NA NA NA NA 1-PL-Piez-41 9/28/21 368 ND NA NA NA NA 1-PL-Piez-42 9/28/21 833 ND NA NA NA NA l-PL-Piez-47 9/28/21 <692 NA NA NA NA NA l-PL-Piez-50 9/29/21 888 ND NA NA NA NA I-PL-Piez-51 9/29/21 18000 ND NA NA NA NA l-PL-Piez-52 9/29/21 578 ND NA NA NA NA G-08 10/14/21 16000 NA NA NA NA NA 1-PL-Piez-44 10/14/2 I 1970 ND NA NA NA NA l-PL-Piez-49 l 0/14/21 1350 ND NA NA NA NA l-PL-Piez-51 10/14/21 14900 NA NA NA NA NA G-08 10/15/21 10900 NA NA NA NA NA G-08 10/25/21 13700 NA NA NA NA NA 1-PL-Piez-49 10/25/21 2140 NA NA NA NA NA l-PL-Piez-51 10/25/21 16000 NA NA NA NA NA 1-PL-Piez-44 10/26/21 1950 NA NA NA NA NA G-08 11/7/21 15200 NA NA NA NA NA l-PL-Piez-44 11/7/21 2040 ND NA NA NA NA 1-PL-Piez-51 11/7/21 15900 ND NA NA NA NA l-PL-Piez-49 l I /8/21 1490 NA NA NA NA NA l-PL-Piez-29 11/9/21 761 NA NA NA NA NA l-PL-Piez-46 11/9/21 <685 ND NA NA NA NA l-PL-Piez-49 11/9/21 1130 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 1-PL-Piez-51 11/9/21 14800 NA NA NA NA NA 1-PL-Piez-05 11/11/21 2730 NA NA NA NA NA I -PL-Piez-06 11111/21 <691 NA NA NA NA NA l-PL-Piez-43 11/11/21 <666 ND NA NA NA NA 1-PL-Piez-44 11/11/21 1070 NA NA NA NA NA l-PL-Piez-45 l l /11/21 <690 ND NA NA NA NA 1-PL-Piez-47 11/11/21 780 NA NA NA NA NA G-08 11/22/21 17400 NA NA NA NA NA l-PL-Piez-44 11/22/21 2150 NA NA NA NA NA 1-PL-Piez-49 11/22/21 4530 ND NA NA NA NA l-PL-Piez-51 11/22/21 21300 ND NA NA NA NA l-PL-Piez-47 12/2/21 1820 ND NA NA NA NA l-PL-Piez-48 12/2/21 <924 NA NA NA NA NA l-PL-Piez-50 12/2/21 <923 NA NA NA NA NA G-08 12/6/21 15900 NA NA NA NA NA l-PL-Piez-44 12/6/21 2150 NA NA NA NA NA l-PL-Piez-49 12/6/21 1800 ND NA NA NA NA G-08 12/20/21 19300 NA NA NA NA NA 1-PL-Piez-44 12/20/21 1650 NA NA NA NA NA l-PL-Piez-49 12/20/21 1230 ND 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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