ML24110A150

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Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report
ML24110A150
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 04/18/2024
From: Hilbert L
Virginia Electric & Power Co (VEPCO)
To:
Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk
References
24-033
Download: ML24110A150 (1)
v • d • e


Text

VIRGINIA ELECTRIC AND POWER COMPANY

RICHMOND, VIRGINIA 23261

April 18, 2024

United States Nuclear Regulatory Commission Serial No.: 24-033 Attention: Document Control Desk NAPS: CNC Washington, D. C. 20555 Docket Nos.: 50-338/339 72-16 72-56 License Nos.: NPF-4/7 SNM-2507

VIRGINIA ELECTRIC AND POWER COMPANY {DOMINION ENERGY VIRGINIA)

NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

Enclosed is the 2023 Annual Radioactive Effluent Release Report. This report is provided pursuant to North Anna Units 1 and 2 Technical Specification 5.6.3 [10 CFR 50.36a] and North Anna Independent Spent Fuel Storage Installation Technical Specification 5.5.2c [10 CFR 72.44(d)(3)].

If you have any questions or require additional information, please contact Mr. Marcus A. Hofmann at (540) 894-2100.

Very truly y.~u/)J_.

/4&1~

Lisa Hilbert Site Vice President

Enclosure

Commitments made in this letter: None Serial No.24-033 NAPS Annual Radioactive Effluent Release Report Page 2 of 2

cc: U. S. Nuclear Regulatory Commission (w/o Enclosure)

Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257

Director, Division of Spent Fuel Management (w/o Enclosure)

Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555

NRC Senior Resident Inspector (w/o Enclosure)

North Anna Power Station ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

NORTH ANNA POWER STATION

(JANUARY 01, 2023 TO DECEMBER 31, 2023)

PREPARED BY: ~£':'?' / ~ ;.,,Brya~c{ue

Supervisor Radiological Analysis and Instrumentation

REVIEWED BY, u),,:,L_ ~

Wilson ~

Superintendent Health Physics chnical

  • APPROVED BY:_~J:::'u-7:.:..J:-:::.......!.:::.......(~~===-

eorge R. Simmons Manager Radiological Protection and Chemistry FORWARD

This report is submitted in accordance with North Anna Unit 1 and 2 Technical Specification 5.6.3 (I0CFR50.36a) and North Anna Independent Spent Fuel Storage Installation (ISFSI) Technical Specification 5.5.2.c and 10CFR72.44(d)(3).

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

FOR THE

NORTH ANNA POWER ST A TION

JANUARY 01, 2023 TO DECEMBER 31, 2023

INDEX

Section No. Subject

EXECUTIVE

SUMMARY

................................... 4

2 PURPOSE AND SCOPE..................................... 5

3 DISCUSSION.................................................. 5-6

4 SUPPLEMENTAL INFORMATION....................... 6 Effluent Release Data.............................................. 7 Annual and Quarterly Doses...................................... 8 Revisions to Offsite Dose Calculation Manual (ODCM)........................................ 9 Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems.................................................. 10 Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation........................................ 11 Unplanned Releases............................................. 12 Lower Limits of Detection (LLD) for Effluent Sample Analysis........................... 13-14 Results of Ground Water Protection Initiative Sample Analysis..................................... 15-20

Carbon-14 Calculations........................................ 21

Miscellaneous Annual Effluent Release Report Log........................ 22 1.0 EXECUTIVE

SUMMARY

The Annual Radioactive Effluent Release Report describes the radioactive effluent control program conducted at the North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) during the 2023 calendar year. This document summarizes the quantities of radioactive liquid and gaseous effluents and solid waste released from the North Anna Power Station and ISFSI in accordance with Regulatory Guide 1.21 during the period of January I through December 31, 2023 and includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents.

There were no releases from the ISFSI during 2023.

There were no unplanned releases, meeting the reporting criteria of Section 6.7.2.a.3 of the Offsite Dose Calculation Manual during this reporting period. Also, there were no spills or leaks meeting the voluntary communication criteria of the NEI Ground Water Protection Initiative. This will be discussed in Attachment 6.

10 CFR 50, Appendix I dose calculations were performed on the 2023 effluent release data in accordance with the Offsite Dose Calculation Manual. The results of these pathway dose calculations indicate the following:

a. The total body dose due to liquid effluents was 5.662E-0l mrem, which is 9.437% of the dose limit, and the critical organ dose due to liquid effluents was 5.668E-0l mrem, which is 2.834% of the dose limit.
b. The air dose due to noble gases was 5.048E-06 mrad gamma, which is 2.525E-05% of the annual gamma dose limit, and 8.499E-06 mrad beta, which is 2.125E-05% of the annual beta dose limit.
c. The critical organ dose for I-131, I-133, H-3, and paiticulates with half-lives greater than 8 days including C-14 was l.060E+0 mrem, which is 3.53% of the annual dose limit. The bases ofC-14 calculations are described in Attachment 9.
d. The critical organ dose for I-131, I-133, H-3, and particulates with half-lives greater than 8 days not including C-14 was
3. l 76E-03 mrem, which is l.059E-02% of the annual dose limit.

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

There was no revision to the Offsite Dose Calculation Manual during this reporting period.

Based on the levels ofradioactivity observed during this reporting period and the dose calculations perfonned, the operations of the No1th Anna Nuclear Power Station Units I and 2 and ISFSI have resulted in negligible dose consequences to the maximum exposed member of the public in unrestricted areas.

4 2.0 PURPOSE AND SCOPE

The Radioactive Effluent Release Report includes, in Attachment 1, a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, "Measuring, Evaluating, and Repo1ting 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, with data summarized on a quarterly basis for Table I and 2 and on an annual basis on Table 3. The rep01t submitted before May !st of each year 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 the previous calendar year. The report also includes a list of unplanned releases during the reporting period in Attachment 6.

As required by Technical Specification, any changes to the Offsite Dose Calculation Manual (ODCM) for the time period covered by this report are included in Attachment 3.

Major changes to radioactive liquid, gaseous and solid waste treatment systems are reported in Attachment 4, as required by the ODCM, Section 6.7.2.a.4. Information to support the reason(s) for the change(s) and a summary of the 10 CFR 50.59 evaluation are included.

As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for the inoperability ofradioactive liquid and/or gaseous effluent monitoring instrumentation is provided in Attachment 5 of this rep01t.

3.0 DISCUSSION The basis for the calculation of percent of Technical Specification for the critical organ in Table I A of Attachment 1 is the ODCM, section 6.3. I, which requires that the dose rate for iodine-131, iodine-133, tritium, and all radionuclides in paiticulate form with half-lives greater than 8 days be less than or equal to 1500 mrem/yr to the critical organ at or beyond the site boundary.

The basis for the calculation of percent of Technical Specification for the total body and skin in Table I A of Attachment I is the ODCM, section 6.3.1, which requires that the dose rate for noble gases to areas at or beyond the 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 beta and gamma air doses due to noble gases released from the site were calculated at site boundaiy. The maximum exposed member of the public from the releases of airborne iodine-I 31, iodine-I 33, tritium and all radionuclides in pa1ticulate form with half-lives greater than 8 days, including carbon-14 is defined as a child, exposed through the vegetation pathway, with the critical organ being the bone. If carbon-14 is excluded from these calculations, the maximum exposed member of the public from the releases of airborne iodine-131, iodine-133, tritium and all radionuclides in particulate form with half-lives greater than 8 days is defined as a child, exposed through the vegetation pathway, with the critical organ being the thyroid gland.

5 The basis for the calculation of the percent of Technical Specification in Table 2A in Attachment 1 is the ODCM, section 6.2.1, which states that the concentrations of radioactive material released in liquid effluents to unrestricted areas shall be limited to 10 times the concentrations specified in 10 CFR 20, 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 2.0E-4 uCi/ml.

The maximum exposed member of the public for calculation of total body dose from radioactive materials in liquid effluents released to unrestricted areas is defined as a child. The critical organ dose calculation was detetmined to be the child liver. The age group is exposed via the drinking water and fish ingestion pathways.

As shown in Attachment 6, there were no unplanned releases meeting the requirements of6.7.2.a.3 of the ODCM.

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 volume 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 that radioisotope was reported as Not Detectable (N/D) on Attachment I of this report. Ifan analysis for an isotope was not performed, then the activity was reported as Not Applicable (N/A).

4.0 SUPPLEMENTAL INFORMATION

As required by the ODCM, section 6.6.2, evaluation of the Land Use Census is perfonned to identify if new location(s) need be added for the radiological environmental monitoring program pursuant to the ODCM. There were no new sampling locations added. There were two (2) garden location changes during the reporting period. The nearest garden location in the SW sector changed from 3.96 miles to 2.16 miles. The nearest garden location in the WNW sector changed from 2.67 miles to 2.05 miles.

Section 6.6.1.b.4 of the ODCM requires identification of the cause(s) for the unavailability of milk or leafy vegetation samples, and the identification ofnew locations for obtaining replacement samples. Milk samples were not collected in 2023 because the last of the operating dairies in the sampling area ceased operations at the start of calendar year 2018. Vegetation samples were not collected from stations 14B, 15, 16, 23 and 26 from January through March and November through December due to seasonal unavailability. All other vegetation samples were obtained.

Attachment 8 contains the results of samples associated with ground water protection sampling undertaken at North Anna to voluntarily comply with the Nuclear Energy Institute, NEI, Ground Water Protection Initiative. In addition to the well, river, and surface water samples included as part of the Radiological Environmental Monitoring Program, North Anna obtained subsurface water samples from various locations on the site.

Attachment 9 contains an explanation of the bases for the carbon-14 calculations performed to assess doses due to carbon-14.

Doses and %TS for gaseous releases are displayed with C-14 included and without for comparison of the values.

6 ATTACHMENT 1 EFFLUENT RELEASE DATA

{01/23 - 12/23)

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, except that in accordance with Step 6.7.2.a. l of the ODCM liquid and gaseous data is summarized on a quarterly basis and solid waste is summarized on an annual basis.

7 ATTACHMENT 2 ANNUAL AND OUARTERL Y DOSES (01/23 - 12/23)

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 will be made as required by ODCM Section 6.7.2.

Liquid Effluent Doses

1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Total Body Dose (mrem) 1.761E-2 2.610E-2 3.589E-1 1.636E-1 5.662E-l Critical Organ Dose (mrem) 1.785E-2 2.619E-2 3.592E-1 1.636E-l 5.668E-1

Gaseous Effluent Doses

1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Noble Gas Gamma Dose (mrad) 3.820E-11 0.00E0 4.647E-6 4.012E-7 5.048E-6 Noble Gas Beta Dose (mrad) 1.136E-10 0.00E0 8.032E-6 4.668E-7 8.499E-6 Critical Organ (Child bone)

Dose for 1-131, 1-133, H-3, Particulates with T1/2 > 8 days (including C-14) (mrem) 4.781E-5 5.299E-4 9.974E-1 6.191E-2 1.060E0

Critical Organ (Child thyroid)

Dose for 1-131, 1-133, H-3, Particulates with T1/2 > 8 days (excluding C-14) (mrem) 3.940E-5 5.299E-4 1.981E-3 6.260E-4 3.176E-3

8 ATTACHMENT 3

REVISIONS TO OFFSITE DOSE CALCULATION MANUAL

(ODCM)

(01/23 - 12/23)

As required by Technical Specification 5.5.1.c, revisions to the ODCM, effective for the time period covered by this report, are summarized in this attachment.

There was no revision to the ODCM during this reporting period.

9 ATTACHMENT 4 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS (01/23 - 12/23)

As required by the ODCM, Section 6.7.2.a.4, major changes to radioactive liquid, gaseous and solid waste treatment systems for the time period covered by this report are synopsized in this attachment. Supporting information as to the reason(s) for the change(s) and a summary of the 10 CFR 50.59 evaluations are included, as applicable.

There were no major changes to the radioactive liquid, gaseous, and solid waste treatment systems for 2023.

10 ATTACHMENT 5 INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS

EFFLUENT MONITORING INSTRUMENTATION

(01/23 - 12/23)

As required by the ODCM, Sections 6.2.2.b.2 and 6.3.2.b.3, a list and explanation for extended inoperability ofradioactive liquid and/or gaseous effluent monitoring instrumentation is provided in this attachment.

l-SS-RM-125, Ul HCBD effluent radiation monitor, was out of service for more than 30 consecutive days during the rep01ting period. The monitor was initially declared non-functional on 12/31/22 @22: 16 when a l-SS-RM-125 "trouble alann "was received in the Control Room. l-SS-RM-125 indications were nonnal and grab sampling showed that High Capacity Blowdown liquid effluent remained non radioactive.

On O 1/04/23, while troubleshooting and calibrating I-SS-RM-125, it was found that the reference and Cs-137 peaks were out of specification. The Cs-137 peak was found to be at 701 KeV with an acceptable range of 656 KeV to 668 KeV. The reference peak was found to be at 898 KeV with an acceptable range of 800 Ke V to 850 KeV. Detector high voltage was adjusted and all readings were brought within specification. l-SS-RM-125 remained non functional pending further investigation and observation.

On 02/02/23 it was discovered, during l-SS-RM-125 calibration, that the reference peak was again out of specification. The reference peak was found to be at 875 KeV with an acceptable range of800 KeV to 850 KeV. The radiation monitor manufacturer, Mirion, was contacted for assistance in detennining a possible cause of the monitor's continued drifting condition. During discussions with Mirion, a representative advised that peak drifting could be caused by inadequate perfonnance of the radiation monitors "MA" electronic board.

Subsequently, the "MA" electronic board was replaced. Following "MA" electronic board replacement and detector adjustments, the detector calibration was completed on 02/02/23." MA" board induced electronic drifting was a condition with which the organization was not familiar which made the associated time necessary to diagnose and conect the issue longer than would be normally expected.

Following the "MA" electronic board replacement on 02/02/23 the l-SS-RM-125, U-1 High Capacity Blowdown Effluent Monitor perfonnance was evaluated and trended over a period of time. During this period of evaluation and trending, no other issues were noted with the radiation monitors perfonnance and no instances of electronic drifting were identified.

The U-1 High Capacity Blowdown Effluent Monitor, 1-SS-RM-125, was returned to functional status on 02/20/23.

11 ATTACHMENT 6

UNPLANNED RELEASES

(01/23 - 12/23)

As required by the ODCM, Section 6.7.2.a.3, a list of unplanned releases, from the site to unrestricted areas, ofradioactive material in

gaseous and liquid effluents occurring during the reporting period, is made in this attachment.

There were no unplanned releases during calendar year 2023 meeting the criteria of Section 6. 7.2.a.3 of the ODCM from the site to

unrestricted areas. Also, there were no spills or leaks that required voluntary communication under the criteria of the NEI Ground

Water Protection Initiative, NEI 07-07. The current groundwater monitoring network provides adequate assurance that radiological

contamination of groundwater will be detected in a timely manner. (i.e., prior to migration offsite). Both the historic and current

tritium levels do not pose a risk to human health and the environment. The cmTent tritium levels are well below the drinking

water standard of20,000 pCi/L. Furthermore, the impacted groundwater is controlled and discharged via a monitored discharge.

12 ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/23 - 12/23)

Gaseous Effluents:

Required L.L.D. Typical L.L.D.

Radioisotope µCi/mL µCi/mL

Krypton - 87 1.00E-4 2.50E-8 7.50E-8

Krypton - 88 1.00E-4 4.00E-8 2.50E-7

Xenon -133 1.00E-4 2.00E-8 1.00E-7

Xenon - 133m 1.00E-4 1.00E-7 4.00E-7

Xenon - 135 1.00E-4 1.00E-8 5.00E-8

Xenon -135m 1.00E-4 5.00E-8 2.00E-7

Xenon - 138 1.00E-4 9.00E-8 4.00E-7

Iodine - 131 1.00E-12 3.00E-14 1.00E-13

Iodine - 133 1.00E-10 1.00E-14 7.00E-13

Manganese - 54 1.00E-11 2.00E-14 6.00E-14

Cobalt - 58 1.00E-11 2.00E-14 6.00E-14

Iron - 59 1.00E-11 6.00E-14 1.00E-13

Cobalt - 60 1.00E-11 3.00E-14 1.00E-13

Zinc - 65 1.00E-11 6.00E-14 2.00E-13

Strontium - 89 1.00E-11 3.00E-14 8.00E-12

Strontium - 90 1.00E-11 3.00E-15 9.00E-12

Molybdenum - 99 1.00E-11 2.00E-14 1.00E-13

Cesium - 134 1.00E-11 2.00E-14 8.00E-14

Cesium - 137 1.00E-11 3.00E-14 8.00E-14

Cerium - 141 1.00E-11 3.00E-14 1.00E-13

Cerium - 144 1.00E-11 1.50E-13 4.00E-13

Gross Alpha 1.00E-11 7.00E-15 2.00E-14

Tritium 1.00E-6 4.00E-09 9.00E-09

13 ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS

{01/23 - 12/23)

Liguid Effluents:

Required L.L.D. Typical L.L.D.

Radioisotope µCi/mL µCi/mL

Krypton - 87 1.00E-5 3.00E-8 1.00E-7

Krypton - 88 1.00E-5 5.00E-8 5.00E-7

Xenon -133 1.00E-5 3.00E-8 1.00E-7

Xenon -133m 1.00E-5 9.00E-8 3.00E-7

Xenon -135 1.00E-5 1.00E-8 5.00E-8

Xenon-135m 1.00E-5 3.00E-8 2.00E-7

Xenon -138 1.00E-5 1.00E-7 1.00E-6

Iodine -131 1.00E-6 1.00E-8 5.00E-8

Manganese - 54 5.00E-7 1.00E-8 5.00E-8

Iron - 55 1.00E-6 3.00E-7 8.00E-7

Cobalt-58 5.00E-7 1.50E-8 6.00E-8

Iron - 59 5.00E-7 3.00E-8 7.00E-8

Cobalt-60 5.00E-7 1.00E-8 5.50E-8

Zinc - 65 5.00E-7 3.00E-8 6.00E-8

Strontium - 89 5.00E-8 1.00E-8 4.00E-8

Strontium - 90 5.00E-8 5.00E-9 9.00E-9

Molybdenum - 99 5.00E-7 2.00E-8 6.00E-8

Cesium - 134 5.00E-7 1.50E-8 5.00E-8

Cesium -137 5.00E-7 1.50E-8 6.00E-8

Cerium -141 5.00E-7 3.00E-8 9.00E-8

Cerium -144 5.00E-7 1.00E-7 5.00E-7

Gross Alpha 1.00E-7 2.00E-8 7.00E-8

Tritium 1.00E-5 2.00E-6 5.00E-6

14 ATTACHMENT 8

RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/23 - 12/23)

The Ground Water Protection Program was established to improve North Anna's management of and response to instances where the inadvertent release ofradioactive substances may result in low but detectible levels of plant-related materials in subsurface soils and water.

It complies with the requirements ofNEI 07-07, INDUSTRY GROUND WATER PROTECTION INITIATIVE - FINAL GUIDANCE DOCUMENT. The industry initiative is intended to improve public trust and confidence in the nuclear industry through sampling and analysis of ground water and timely and effective communication with stakeholders, including the public and local, state, and federal officials.

Samples are obtained from monitoring wells installed both inside and outside the restricted area on a quaiterly basis and analyzed onsite.

Annually, during the second quarter, these samples are analyzed by an Independent Lab. Samples are also obtained from sumps and yard drains on a quarterly basis and analyzed onsite. Samples may be obtained more frequently than normal, ifrequired and may be analyzed on-site or by an Independent Lab. The required Lower Limits of Detection, LLDs, and reporting limits for the ground water detection program are those associated with the radiological environmental program as listed in Attachments 11 and 12 to VPAP-2103N.

On the following pages is a summary of the samples and results of the ground water protection program taken for calendar year 2023. All liquid results are rep01ted in pCi/L, while soil results for tritium are reported in pCi/g of soil, wet. An "N/ A" indicates a sample analysis was not performed for that sample. A"< value" indicates an analysis was performed but the result was less than the Minimum Detectable Activity, MDA, and the required LLD. If a result is greater than the MDA, but less than the LLD the result is listed. Some of these results may be false positives, due to the analysis software or interferences from naturally occurring radioactivity. In these cases, instead of the value, an explanatory footnote is provided.

15 ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/23 - 12/23)

1st Quarter 2023 Sample Date Sample H-3t1l Gamma -Emitting 1-131{1) Sr-89/90t1l TRUt 1l 1l Fe-55l1l Ni-63l1l Alpha Pu-241t 1l Media Particulatesl GWP-18 01127123 WATER 4650 NIA NIA NIA NIA NIA NIA NIA GWP-18 02108123 WATER 4717 NIA NIA NIA NIA NIA NIA NIA GWP-18 03116123 WATER 7107 NIA NIA NIA NIA NIA NIA NIA PZ-3 01127123 WATER 1542 NIA NIA NIA NIA NIA NIA NIA GWP-3 02109123 WATER <724 NIA NIA NIA NIA NIA NIA NIA GWP-4 02109123 WATER <740 NIA NIA NIA NIA NIA NIA NIA GWP-15R 02111123 WATER <745 NIA NIA NIA NIA NIA NIA NIA GWP-17 02111123 WATER 1496 NIA NIA NIA NIA NIA NIA NIA GWP-19 02109123 WATER 1463 NIA NIA NIA NIA NIA NIA NIA GWP-20 02110123 WATER 709 NIA NIA NIA NIA NIA NIA NIA GWP-6 02109123 WATER <682 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 02110123 WATER <1350 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 02111123 WATER <1270 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 02111123 WATER <1350 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 02111123 WATER <1260 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 01131123 WATER 2645 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 01131123 WATER 1471 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 01131123 WATER 3333 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 01131123 WATER 3479 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 01131123 WATER 1422 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 01131123 WATER 2436 NIA NIA NIA NIA NIA NIA NIA

(1) pCi/L

16 ATTACHMENT 8 RES UL TS OF GROUNDWATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01 /23 - 12/23)

2 nd Quarter 2023

Sample Date Sample H-3!1l Gamma -Emitting 1-131(1) Sr-89190!Media Particulates!1l TRU!1l 1! Fe-SS!1l Ni-63!1l Alpha Pu-241!1l

GWP-18 04106123 WATER 8117 NIA NIA NIA NIA NIA NIA NIA GWP-18 04112123 WATER 8837 NIA NIA NIA NIA NIA NIA NIA GWP-18 04119123 WATER 8526 NIA NIA NIA NIA NIA NIA NIA GWP-18 04126123 WATER 8532 NIA NIA NIA NIA NIA NIA NIA GWP-18 05102123 WATER 6195 NIA NIA NIA NIA NIA NIA NIA GWP-18 05109123 WATER 6851 NIA NIA NIA NIA NIA NIA NIA GWP-18 05116123 WATER 6353 NIA NIA NIA NIA NIA NIA NIA GWP-18 05123123 WATER 5303 NIA NIA NIA NIA NIA NIA NIA GWP-18 05131123 WATER 5907 NIA NIA NIA NIA NIA NIA NIA GWP-18 06107123 WATER 6191 NIA NIA NIA NIA NIA NIA NIA GWP-18 06114123 WATER 6053 NIA NIA NIA NIA NIA NIA NIA GWP-18 06120123 WATER 3608 NIA NIA NIA NIA NIA NIA NIA GWP-18 06128123 WATER 4001 NIA NIA NIA NIA NIA NIA NIA PZ-1 06114123 Insufficient volume PZ-2 06114123 Insufficient volume PZ-3 05109123 WATER <1153 NIA NIA NIA NIA NIA NIA NIA GWP-3 06115123 WATER <1152 NIA NIA NIA NIA NIA NIA NIA GWP-4 06115123 WATER <1152 NIA NIA NIA NIA NIA NIA NIA GWP-5A 06115123 WATER <1152 NIA NIA NIA NIA NIA NIA NIA GWP-6 06115123 WATER <1152 NIA NIA NIA NIA NIA NIA NIA GWP-7 06115123 WATER <1063 NIA NIA NIA NIA NIA NIA NIA GWP-8 06129123 WATER <1063 NIA NIA NIA NIA NIA NIA NIA GWP-9 06128123 WATER <1063 NIA NIA NIA NIA NIA NIA NIA GWP-13 06115123 WATER <1063 NIA NIA NIA NIA NIA NIA NIA GWP-16 06128123 WATER <1063 NIA NIA NIA NIA NIA NIA NIA GWP-19 06115123 WATER <1152 NIA NIA NIA NIA NIA NIA NIA GWP-20 06115123 WATER <1063 NIA NIA NIA NIA NIA NIA NIA GWP-21 06115123 WATER <1152 NIA NIA NIA NIA NIA NIA NIA GWP-22 06128123 WATER 2473 NIA NIA NIA NIA NIA NIA NIA GWP-23 06115123 Insufficient volume GWP-14 06129123 WATER <1063 NIA NIA NIA NIA NIA NIA NIA GWP-15R 06128123 WATER <1063 NIA NIA NIA NIA NIA NIA NIA GWP-17 06128123 WATER <1135 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 05125123 WATER <1260 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 05131123 WATER <1576 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 05131123 WATER <1576 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 05131123 WATER <1576 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 05109123 WATER 1155 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 05109123 WATER <1153 NIA NIA NIA NIA NIA NIA NIA 17 U-2 Mat Sump Inside 05109123 WATER 1439 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 05109123 WATER 1885 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 05109123 WATER 1601 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 05109123 WATER 1974 NIA NIA NIA NIA NIA NIA NIA BTW-1 06129123 WATER <1063 NIA NIA NIA NIA NIA NIA NIA BTW-2 06129123 WATER <1063 NIA NIA NIA NIA NIA NIA NIA BTW-4 06129123 WATER <1063 NIA NIA NIA NIA NIA NIA NIA TTW-2 06129123 WATER <1063 NIA NIA NIA NIA NIA NIA NIA TTW-3 06129123 WATER <1085 NIA NIA NIA NIA NIA NIA NIA TTW-5 06129123 WATER <1085 NIA NIA NIA NIA NIA NIA NIA BTW-1 (2) 06129123 WATER <870 NIA NIA NIA NIA NIA NIA NIA BTW-2 (2) 06129123 WATER <876 NIA NIA NIA NIA NIA NIA NIA BTW-4 (2) 06129123 WATER <871 NIA NIA NIA NIA NIA NIA NIA TTW-2 (2) 06129123 WATER <873 NIA NIA NIA NIA NIA NIA NIA TTW-3 (2) 06129123 WATER <888 NIA NIA NIA NIA NIA NIA NIA TTW-5 (2) 06129123 WATER <901 NIA NIA NIA NIA NIA NIA NIA PZ-3 (2) 05109123 WATER <888 NIA NIA NIA NIA NIA NIA NIA GWP-3 (2) 06115123 WATER 1460 NIA NIA NIA NIA NIA NIA NIA GWP-4 (2) 06115123 WATER 1090 NIA NIA NIA NIA NIA NIA NIA GWP-5A (2) 06115123 WATER <884 NIA NIA NIA NIA NIA NIA NIA GWP-6 (2) 06115123 WATER <890 NIA NIA NIA NIA NIA NIA NIA GWP-7 (2) 06115123 WATER <891 NIA NIA NIA NIA NIA NIA NIA GWP-8 (2) 06129123 WATER <882 NIA NIA NIA NIA NIA NIA NIA GWP-9 (2) 06128123 WATER <869 NIA NIA NIA NIA NIA NIA NIA GWP-13 (2) 06115123 WATER <874 NIA NIA NIA NIA NIA NIA NIA GWP-14 (2) 06129123 WATER <875 NIA NIA NIA NIA NIA NIA NIA GWP-15R (2) 06128123 WATER <883 NIA NIA NIA NIA NIA NIA NIA GWP-16 (2) 06128123 WATER <867 NIA NIA NIA NIA NIA NIA NIA GWP-17 (2) 06128123 WATER <873 NIA NIA NIA NIA NIA NIA NIA GWP-18 (2) 06128123 WATER 4500 NIA NIA NIA NIA NIA NIA NIA GWP-19 (2) 06115123 WATER 883 NIA NIA NIA NIA NIA NIA NIA GWP-20 (2) 06115123 WATER <884 NIA NIA NIA NIA NIA NIA NIA GWP-21 (2) 06115123 WATER <876 NIA NIA NIA NIA NIA NIA NIA GWP-22 (2) 06128123 WATER 1430 NIA NIA NIA NIA NIA NIA NIA TTW-1 Well abandoned in place, pending decommissioning TTW-4 Well abandoned in place, pending decommissioning

(1) pCi/L (2) Vendor Analysis

18 ATTACHMENT 8 RES UL TS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/23 - 12/23)

3rd Quarter 2023

Sample Date Sample H-Jt1i Gamma -Emitting 1-131(1) Sr-Fe-sst1l Ni-63!11 Alpha Pu-241 111 Media Particulates 111 89/90 111 TRLJl1l

GWP-18 07105123 WATER 4642 NIA NIA NIA NIA NIA NIA NIA GWP-18 07112123 WATER 3130 NIA NIA NIA NIA NIA NIA NIA GWP-18 07126123 WATER 4845 NIA NIA NIA NIA NIA NIA NIA GWP-18 08109123 WATER 4096 NIA NIA NIA NIA NIA NIA NIA GWP-18 09106123 WATER 3784 NIA NIA NIA NIA NIA NIA NIA GWP-18 08123123 WATER 4661 NIA NIA NIA NIA NIA NIA NIA GWP-18 09119123 WATER 2064 NIA NIA NIA NIA NIA NIA NIA PZ-3 08109123 WATER <1135 NIA NIA NIA NIA NIA NIA NIA PZ-3 09106123 WATER <1238 NIA NIA NIA NIA NIA NIA NIA GWP-3 09106123 WATER <1238 NIA NIA NIA NIA NIA NIA NIA GWP-4 09106123 WATER <1238 NIA NIA NIA NIA NIA NIA NIA GWP-6 09106123 WATER <1238 NIA NIA NIA NIA NIA NIA NIA GWP-15R 09106123 WATER <1238 NIA NIA NIA NIA NIA NIA NIA GWP-17 09106123 WATER <1238 NIA NIA NIA NIA NIA NIA NIA GWP-19 09107123 WATER <1238 NIA NIA NIA NIA NIA NIA NIA GWP-20 09107123 WATER <1238 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 09106123 WATER <1570 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 09105123 WATER <1380 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 09105123 WATER <1590 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm 09105123 WATER <1440 NIA NIA NIA NIA NIA NIA Drains NIA U-1 Mat Sump East 09106123 WATER 1356 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 09119123 WATER <1354 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 09106123 WATER 1186 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 09119123 WATER <1129 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 09106123 WATER 1623 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 09119123 WATER 2343 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 08110123 WATER <1135 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 09119123 WATER 3835 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 08110123 WATER <1135 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 09119123 WATER <1129 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 09106123 WATER <1129 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 09119123 WATER 4555 NIA NIA NIA NIA NIA NIA NIA

(1) pCi/L

19 ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/23 - 12/23)

4th Quarter 2023 Sample Date Sample H-3(1l Gamma -Emitting 1-131(1) Sr-89/90(1l Fe-55(1l Ni-63(Media Particulates( 1l TRU( 1l 1l Alpha Pu-241( 1l

GWP-18 10104/23 WATER 3657 NIA NIA NIA NIA NIA NIA NIA GWP-18 10118123 WATER 4428 NIA NIA NIA NIA NIA NIA NIA GWP-18 11128123 WATER 4089 NIA NIA NIA NIA NIA NIA NIA GWP-18 12121123 WATER 4139 NIA NIA NIA NIA NIA NIA NIA PZ-3 11122123 WATER <1156 NIA NIA NIA NIA NIA NIA NIA GWP-3 12123123 WATER <1247 NIA NIA NIA NIA NIA NIA NIA GWP-4 12123123 WATER <1247 NIA NIA NIA NIA NIA NIA NIA GWP-6 12123123 WATER <1247 NIA NIA NIA NIA NIA NIA NIA GWP-15R 12122123 WATER <1247 NIA NIA NIA NIA NIA NIA NIA GWP-17 12122123 WATER <1247 NIA NIA NIA NIA NIA NIA NIA GWP-19 12123123 WATER <1247 NIA NIA NIA NIA NIA NIA NIA GWP-20 12123/23 WATER <1247 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 11130123 WATER <1140 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 11130123 WATER <1400 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 11130123 WATER <1420 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 11130123 WATER <1737 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 11112123 WATER 1941 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 11112123 WATER 2767 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 11112123 WATER 2309 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 11112123 WATER 2225 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 11112123 WATER 3686 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 11/12123 WATER 3136 NIA NIA NIA NIA NIA NIA NIA

(1) pCi/L

20 ATTACHMENT 9 CARBON-14 CALCULATIONS (01/23 - 12/23)

Carbon-I 4, C-14, is a naturally occurring isotope of carbon produced by cosmic ray interactions in the atmosphere. Nuclear weapons testing in the 1950s and 1960s significantly increased the amount of C-14 in the atmosphere. Due to the long half-life of C-14, 5730 years, a significant portion of the C-14 from this testing is still present in the environment. C-14 is also produced in commercial nuclear reactors, but the amounts produced are much less than those produced naturally or from weapons testing.

In Regulatory Guide 1.21, Revision 2, "Measuring, Evaluating, and Repo1ting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste", the NRC has recommended that U.S. nuclear power plants evaluate whether C-14 is a "principal radionuclide", and if so, report the amount of C-14 released. At North Anna, improvements over the years in fuel performance have resulted in a decrease in the amount and distribution of radionuclides released to the environment in gaseous effluents. As a result, C-14 has become a "principal radionuclide" for the gaseous effluent pathway at North Anna, as defined in Regulatory Guide 1.21, Revision 2. Because the dose contribution of C-14 to liquid radioactive waste is a small fraction of the dose compared to other nuclides, evaluation of C-14 in liquid effluents is not required by Regulatory Guide 1.21, Revision 2.

The quantity of gaseous C-14 released to the environment can be estimated by use of a C-14 source term scaling factor based on power generation. North Anna utilized methodology in EPRI Report, Estimation of C-14 in Nuclear Power Gaseous Effluents. Based on this document, at full capacity, North Anna would generate and release about 31.8 Ci of C-14 per year. Since the units did not operate at full power for 100% of the year, this value was corrected for the capacity factor of each unit yielding an estimated 29.1 Ci ofC-14 produced and released. North Anna assumed that the fractional release of gaseous C-14 in any quarter and pathway could be approximated by the fraction of noble gasses released via that pathway in that quaiter.

Most C-14 species initially produced in a Pressurized Water Reactor are organic, e.g., methane. C-14 releases in PWRs occur primarily as a mix of organic carbon and carbon dioxide released from the waste gas system. C-14 in the primary coolant is essentially all organic with a large fraction as a gaseous species. Any time the RCS liquid or gas is exposed to an oxidizing environment, a slow transfonnation from an organic to an inorganic chemical fo1m can occur. Various studies documenting measured C-14 releases from PWRs suggest a range of 70% to 95% organic. North Anna used a value of70% organic and 30% CO2 in its calculations.

Public dose estimates from airborne C-14 were performed using dose models in NUREG-0133 and Regulatory Guide 1.109. The estimated C-14 dose impact on the maximum organ dose from airborne effluents released at North Anna is estimated to be 4.998E-2 mrem from the inhalation pathway, or 3.332E-03% TS of the 1500 mrem/yr dose rate limit and l.007E+00 mrem from the ingestion pathway or 3.356E+00% TS of the 10CFR50, Appendix I, ALARA design objective of 15 mrem/yr per unit. In both cases the critical organ was determined to be the child's bone.

21 Miscellaneous There was one entry on the 2023 Annual Effluent Release Report Log. Item 23-01 was entered to document that l-SS-RM-125, U-1 HCBD Effluent Radiation Monitor was out of service for greater than 30 consecutive days.

22 TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR {01/23 - 12/23)

Page 1 of 2

1 ST 2ND ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (%)

A. Fission and Activiation Gases:

1. Total Release Curies 3.67E-07 N/D 1.80E+1
2. Average Release Rate For Period µCi/sec 4.72E-08 N/D

B. Iodines:

1. Total lodine-131 Release Curies N/D N/D 2.80E+1
2. Average Release Rate For Period ~1Ci/sec N/D N/D

C. Particulate (T112 > 8 days):

1. Total Particulate (T1I2 > 8 days) Release Curies N/D N/D 2.80E+1
2. Average Release Rate For Period ~1Ci/sec N/D N/D
3. Gross Alpha Radioactivity Release Curies N/D N/D

D. Tritium:

1. Total Release Curies 3.26E-01 1.94E+00 3.10E+1
2. Average Release Rate For Period µCi/sec 4.20E-02 2.46E-01

E. Carbon-14

1. Total Release Curies 6.97E-05 0.00E+00
2. Average Release Rate For Period µCi/sec 8.96E-06 0.00E+00

F. Percentage Of Technical Specification Limits

1. Total Body Dose Rate % 2.57E-11 0.00E+00
2. Skin Dose Rate % 1.02E-11 0.00E+00
3. Critical Organ Dose Rate (with C-14) % 3.98E-06 9.91E-05 Critical Organ Dose Rate (without C-14) % 3.78E-06 9.91 E-05 TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/23 - 12/23)

Page 2 of 2

3RD 4TH ESTIMATED TOTAL UNITS QUARTER QUARTER PERCENT ERROR (%)

A. Fission and Activiation Gases:

1. Total Release Curies 1.43E-01 9.65E-03 1.80E+1
2. Average Release Rate For Period ~tCi/sec 1.80E-02 1.21 E-03

B. Iodines:

1. Total lodine-131 Release Curies N/D N/D 2.80E+1
2. Average Release Rate For Period µCi/sec N/D N/D

C. Particulate (T112 > 8 days):

1. Total Particulate (T112 > 8 days) Release Curies N/D N/D 2.80E+1
2. AveraQe Release Rate For Period µCi/sec N/D N/D
3. Gross Alpha Radioactivity Release Curies N/D N/D

D. Tritium:

1. Total Release Curies 5.26E+00 1.52E+00 3.10E+1
2. Average Release Rate For Period µCi/sec 6.62E-01 1.91E-01

F. Carbon-14

1. Total Release Curies 2.72E+01 1.83E+00
2. Average Release Rate For Period ~tCi/sec 3.42E+00 2.30E-01

F. Percentage Of Technical Specification Limits

1. Total Body Dose Rate % 3.28E-06 2.91E-07
2. Skin Dose Rate % 1.0?E-06 8.35E-08
3. Critical Organ Dose Rate (with C-14) % 1.29E-02 8.14E-04 Critical Organ Dose Rate (without C-14) % 4.05E-04 1.31E-04 TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/23 - 12/23)

Page 1 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases:

Krypton - 85 Ci N/D N/D N/D N/D Krypton - 85m Ci N/D N/D N/D N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon - 131m Ci N/D N/D N/D N/D Xenon - 133 Ci N/D N/D N/D N/D Xenon -133m Ci N/D N/D N/D N/D Xenon -135 Ci N/D N/D N/D N/D Xenon - 135m Ci N/D N/D N/D N/D Xenon - 137 Ci N/D N/D N/D N/D Xenon -138 Ci N/D N/D N/D N/D Argon - 41 Ci N/D N/D N/D N/D

Total For Period Ci N/D N/D N/D N/D

Iodines:

Iodine - 130 Ci N/D N/D N/D N/D Iodine - 131 Ci N/D N/D N/D N/D Iodine - 132 Ci N/D N/D N/D N/D Iodine - 133 Ci N/D N/D N/D N/D Iodine - 134 Ci N/D N/D N/D N/D Iodine - 135 Ci N/D N/D N/D N/D Bromine - 82 Ci N/D 2.42E-08 N/D Total For Period Ci N/D 2.42E-08 N/D N/D

Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt - 60 Ci N/D N/D N/D N/D Zinc - 65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Cesium - 134 Ci N/D N/D N/D N/D Cesium - 136 Ci N/D N/D N/D N/D Cesium -137 Ci N/D N/D N/D N/D TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/23 - 12/23)

Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.)

Arsenic -76 Ci N/D N/D N/D N/D Cerium - 141 Ci N/D N/D N/D N/D Cerium -144 Ci N/D N/D N/D N/D Silver -11 Om Ci N/D N/D N/D N/D

Total for Period (T1/2 > 8 days) Ci N/D N/D N/D N/D Total for Period (T1/2 < 8 days) Ci N/D N/D N/D N/D

Total For Period Ci N/D N/D N/D N/D

GROSS ALPHA: Ci N/D N/D N/D N/D

TRITIUM: Ci 3.26E-01 9.44E-01 6.19E-05 2.68E-05

CARBON-14 Ci N/D N/D N/D N/D TABLE 18 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/23 - 12/23)

Page 3 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases:

Krypton - 85 Ci N/D N/D N/D N/D Krypton - 85m Ci N/D N/D N/D N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon - 131m Ci N/D N/D N/D N/D Xenon - 133 Ci N/D N/D 1.27E-01 8.82E-03 Xenon -133m Ci N/D N/D 3.09E-03 N/D Xenon - 135 Ci N/D N/D 9.31E-04 3.08E-06 Xenon -135m Ci N/D N/D N/D N/D Xenon - 137 Ci N/D N/D N/D N/D Xenon - 138 Ci N/D N/D N/D N/D Argon - 41 Ci 5.44E-03 N/D 4.14E-04 7.76E-04 Total For Period Ci 5.44E-03 N/D 1.32E-01 9.60E-03

Iodines:

Iodine - 130 Ci N/D N/D N/D N/D lodine-131 Ci N/D N/D N/D N/D Iodine - 132 Ci N/D N/D N/D N/D Iodine - 133 Ci N/D N/D N/D N/D Iodine - 134 Ci N/D N/D N/D N/D Iodine - 135 Ci N/D N/D N/D N/D Bromine-82 Ci 2.12E-07 N/D N/D N/D

Total For Period Ci 2.12E-07 N/D N/D N/D

Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt-58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt-60 Ci N/D N/D N/D N/D Zinc - 65 Ci N/D N/D N/D N/D Strontium - 85 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D N/D Silver-11 Om Ci N/D N/D N/D N/D Cesium -134 Ci N/D N/D N/D N/D Cesium -137 Ci N/D N/D N/D N/D TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/23 - 12/23)

Page 4 of 4 -

CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.)

Arsenic - 76 Ci N/0 N/0 N/0 N/0 Cerium - 141 Ci N/0 N/0 N/0 N/0 Cerium -144 Ci N/0 N/0 N/0 N/0

Total for Period (T1/2 > 8 days) Ci N/0 N/0 N/0 N/0 Total for Period (T1/2 < 8 days) Ci N/0 N/0 N/0 N/0

Total For Period Ci N/0 N/0 N/0 N/0

GROSS ALPHA: Ci N/0 N/0 N/0 N/0

TRITIUM: Ci 7.56E-01 4.22E-02 4.67E-04 3.22E-04

CARBON-14 Ci 1.03E+OO N/0 2.51E+01 1.82E+OO TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/23 - 12/23)

Page 1 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases:

Krypton - 85 Ci N/D N/D N/D N/D Krypton - 85m Ci N/D N/D N/D N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D N/D N/D Xenon -131m Ci N/D N/D N/D N/D Xenon - 133 Ci N/D N/D 3.67E-07 N/D Xenon - 133m Ci N/D N/D N/D N/D Xenon - 135 Ci N/D N/D N/D N/D Xenon -135m Ci N/D N/D N/D N/D Xenon - 137 Ci N/D N/D N/D N/D Xenon - 138 Ci N/D N/D N/D N/D Argon - 41 Ci N/D N/D N/D N/D Total For Period Ci N/D N/D 3.67E-07 N/D

Iodines:

Iodine - 130 Ci N/D N/D N/D N/D Iodine - 131 Ci N/D N/D N/D N/D Iodine - 132 Ci N/D N/D N/D N/D Iodine - 133 Ci N/D N/D N/D N/D Iodine - 134 Ci N/D N/D N/D N/D Iodine - 135 Ci N/D N/D N/D N/D

Total For Period Ci N/D N/D N/D N/D

Particulates:

Manganese - 54 Ci N/D N/D N/D N/D Cobalt - 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt-60 Ci N/D N/D N/D N/D Zinc-65 Ci N/D N/D N/D N/D Strontium - 89 Ci N/D N/D N/D N/D Strontium - 90 Ci N/D N/D N/D NID Cesium - 134 Ci N/D N/D N/D N/D TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/23 - 12/23)

Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDE$ RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.)

Cesium -137 Ci N/D N/D N/D N/D Arsenic-76 ( T1/2 < 8 days) Ci N/D N/D N/D N/D Rubidium-88 Ci N/D N/D N/D N/D Cerium -144 Ci N/D N/D N/D N/D Niobium-95 Ci N/D N/D N/D N/D Zirconium-95 Ci N/D N/D N/D N/D Tellurium-131m (T1/2 < 8 days) Ci N/D N/D N/D N/D Yttrium-91m (T1/2 < 8 days) Ci N/D N/D N/D N/D Chromium-51 Ci N/D N/D N/D N/D Total for Period (T1/2 > 8 days) Ci N/D N/D N/D N/D Total for Period (T1/2 < 8 days) Ci N/D N/D N/D N/D

Total For Period Ci N/D N/D N/D N/D

GROSS ALPHA: Ci N/D N/D N/D N/D

TRITIUM: Ci N/D 9.92E-01 4.40E-06 3.72E-05

CARBON-14 Ci N/D N/D 6.97E-05 N/D TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/23 - 12/23)

Page 3 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDE$ RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Gases:

Krypton - 85 Ci N/D N/D N/D N/D Krypton - 85m Ci N/D N/D N/0 N/D Krypton - 87 Ci N/D N/0 N/0 N/0 Krypton - 88 Ci N/D N/0 N/0 N/0 Xenon - 131m Ci N/0 N/D N/D N/D Xenon - 133 Ci N/0 N/D 5.38E-03 3.88E-05 Xenon -133m Ci N/0 N/0 1.08E-04 1.04E-06 Xenon - 135 Ci N/D N/0 3.40E-04 6.32E-06 Xenon -135m Ci N/0 N/D N/0 N/D Xenon-137 Ci N/0 N/0 N/0 N/0 Xenon - 138 Ci N/D N/0 N/0 N/0 Argon -41 Ci N/0 N/0 N/0 N/D Total For Period Ci N/0 N/D 5.83E-03 4.62E-05

Iodines:

Iodine - 130 Ci N/0 N/D N/0 N/D Iodine -131 Ci N/0 N/D N/0 N/0 Iodine - 132 Ci N/0 N/0 N/0 N/0 Iodine - 133 Ci N/D N/0 N/D N/D Iodine - 134 Ci N/D N/D N/0 N/0 Iodine - 135 Ci N/0 N/0 N/0 N/0

Total For Period Ci N/D N/D N/D N/0

Particulates:

Manganese - 54 Ci N/0 N/0 N/D N/0 Cobalt - 58 Ci N/D N/0 N/D N/0 Iron - 59 Ci N/D N/D N/0 N/0 Cobalt-60 Ci N/0 N/0 N/0 N/0 Zinc-65 Ci N/D N/0 N/D N/D Strontium - 89 Ci N/0 N/D N/0 N/0 Strontium - 90 Ci N/0 N/0 N/0 N/D Cesium - 134 Ci N/D N/D N/0 N/D TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/23 - 12/23)

Page 4 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDE$ RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Particulates: (cont.)

Cesium -137 Ci N/D N/D N/D N/D Niobium-95 (T1/2 > 8 days) Ci N/D N/D N/D N/D Silver-110m (T1/2 > 8 days) Ci N/D N/D N/D N/D Arsenic -76 ( T1/2 < 8 days) Ci 8.96E-05

Total for Period (T1/2 > 8 days) Ci N/D N/D N/D N/D Total for Period (T1/2 < 8 days) Ci 8.96E-05 N/D N/D N/D

Total For Period Ci 8.96E-05 N/D N/D N/D

GROSS ALPHA: Ci N/D N/D N/D N/D

TRITIUM: Ci 2.21E+00 8.18E-01 2.30E+00 6.62E-01

CARBON-14 Ci N/D N/D 1.11 E+00 8.78E-03 TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT_- SUMMl\\TION OF ALL BELEASES FOR (01/23 - 12/23)

Page 1 of 2 1 ST 2ND ESTIMATED TOT AL UNITS QUARTER QUARTER PERCENT ERROR (%)

A. Fission and Activiation Products:

1. Total Release (not including tritium, noble gas, and gross alpha). Curies 6.03E-04 6.22E-04 2.00E+01
2. Average diluted concentration during the period. ~tCi/ml 1.76E-12 7.51E-13
3. Percent of applicable limit (T.S.) % 3.06E-06 1.50E-06

B. Tritium:

1. Total release activity. Curies 4.98E+01 7.39E+01 2.00E+01
2. Average diluted concentration during the period. ~tCi/ml 1.46E-07 8.93E-08
3. Percent of applicable limit (T.S.) % 1.46E-03 8.93E-04

C. Dissolved and Entrained Gases:

1. Total release activity. Curies N/D N/D 2.00E+01
2. Average diluted concentration during the period. ~tCi/ml N/D N/D
3. Percent of applicable limit (T.S.) % N/D N/D

D. Gross Alpha Radioactivity:

1. Total release activity. Curies N/D N/D 2.00E+01

E. Volume of waste released: (prior to dilution). Liters 8.61 E+07 6.98E+07 3.00E+00

F. Total volume of dilution water used during the period. Liters 3.42E+11 8.28E+11 3.00E+00 TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT-SUMMATION OF ALL RELEASES FOR (01/23 - 12/23)

Page 2 of 2 3 RD 4 TH ESTIMATED TOT AL UNITS QUARTER QUARTER PERCENT ERROR (%)

A. Fission and Activiation Products:

1. Total Release (not including tritium, noble gas, and gross alpha). Curies 6.86E-04 5.64E-03 2.00E+01
2. Average diluted concentration during the period. ~tCi/ml 9.15E-13 8.42E-12
3. Percent of applicable limit (T.S.) % 2.39E-06 1.01E-05

B. Tritium:

1. Total release activity. Curies 1.02E+03 4.64E+02 2.00E+01
2. Average diluted concentration during the period. ~tCi/ml 1.36E-06 6.92E-07
3. Percent of applicable limit (T.S.) % 1.36E-02 6.92E-03

C. Dissolved and Entrained Gases:

1. Total release activity. Curies N/D N/D 2.00E+01
2. Average diluted concentration during the period. ~tCi/ml N/D N/D
3. Percent of applicable limit (T.S.) % N/D N/D

D. Gross Alpha Radioactivity:

1. Total release activity. Curies N/D N/D 2.00E+01

E. Volume of waste released: (prior to dilution). Liters 7.77E+07 8.71 E+07 3.00E+00

F. Total volume of dilution water used during the period. Liters 7.49E+11 6.70E+11 3.00E+00 TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUl;NT REl..EASES FOR (01/23 - 12/23)

Page 1 of 4 -

CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Products:

Manganese - 54 Ci N/D N/D N/D N/A Iron - 59 Ci N/D N/D N/D N/A Cobalt-58 Ci 2.31 E-04 2.37E-04 N/D N/A Cobalt-60 Ci 2.10E-04 3.14E-04 4.35E-06 N/A Strontium - 89 Ci N/D N/O N/0 N/A Strontium - 90 Ci N/O N/O N/D N/A Tellurium-123m Ci 6.66E-05 7.73E-06 N/O N/A Tellurium-132 Ci N/D N/O N/D N/A Chromium-51 Ci N/O N/O 1.71E-06 N/A Iodine - 131 Ci N/D N/D N/D N/A Iodine - 133 Ci N/D N/O N/O N/A Cesium -134 Ci N/D N/O N/D N/A Cesium - 137 Ci 6.96E-06 4.78E-06 5.32E-06 N/A Zirconium - 95 Ci N/O N/0 N/O N/A Cerium -141 Ci N/D N/D N/D N/A Silver-11 Om Ci N/D N/D 2.12E-07 N/A Tellurium-125m Ci 6.64E-06 1.08E-05 7.85E-06 N/A Nickel - 63 (T1/2 > 8 days) Ci N/D N/D N/O N/A Antimony-125 Ci 2.87E-05 4.68E-05 3.41E-05 N/A Total for Period Ci 5.50E-04 6.22E-04 5.35E-05 N/A TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/23 - 12/23)

Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Dissolved & Entrained Noble Gases:

Xenon -133 Ci NID NID NID NIA Xenon -133m Ci NID NID NID NIA Xenon -135 Ci NID NID NID NIA Xenon -135m Ci NID NID NID NIA Other (Specify) Ci NID NID NID NIA Krypton-88 ( T112 < 8 days) Ci NID NID NID NIA Krypton-85 (T112 > 8 days) Ci NID NID NID NIA

Total for Period Ci NID NID NID NIA

Tritium Ci 4.97E+01 7.39E+01 8.93E-02 NIA

Gross Alpha Ci NID NID NID NIA TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID ~EFFLUENT RELEASES FOR (01/23 - 12/23)

Page 3 of 4 -

CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Fission & Activation Products:

Manganese - 54 Ci NID NID NIA NIA Iron - 59 Ci NID NID NIA NIA Cobalt-58 Ci 2.08E-04 3.55E-03 NIA NIA Cobalt-60 Ci 4.64E-04 1.41 E-03 NIA NIA Strontium - 89 Ci NID NID NIA NIA Strontium - 90 Ci NID NID NIA NIA Niobium - 95 Ci NID NID NIA NIA Zirconium - 95 Ci NID NID NIA NIA Silver - 11 Om Ci NID NID NIA NIA Iodine - 131 Ci NID NID NIA NIA Iodine - 133 Ci NID NID NIA NIA Cesium -134 Ci NID N/D NIA NIA Cesium - 137 Ci 1.43E-05 NID NIA NIA Tellurium-123m Ci N/D N/D NIA N/A Cerium - 141 Ci NID NID NIA NIA Chromium-51 Ci N/D NID NIA NIA Nickel - 63 (T112 > 8 days) Ci N/D NID NIA NIA Ruthenium-105 (T112 < 8 days) Ci NID NID NIA NIA Antimony-125 (T112 > 8 days) Ci NID 5.37E-04 NIA NIA Antimony-124 (T112 > 8 days) Ci NID 1.01 E-05 NIA NIA Tellurium-125m (T112 > 8 days) Ci N/D 1.24E-04 NIA NIA

Total for Period Ci 6.86E-04 5.64E-03 NIA NIA TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/23 - 12/23)

Page 4 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDE$ RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Dissolved & Entrained Noble Gases:

Xenon - 133 Ci N/D N/D N/A N/A Xenon -133m Ci N/D N/D N/A N/A Xenon -135 Ci N/D N/D N/A N/A Xenon - 135m Ci N/D N/D N/A N/A Other (Specify)

Argon - 41 (T1/2 < 8 days) Ci N/D N/D N/A N/A Krypton - 85 (T1/2 > 8 days) Ci N/D N/D N/A NIA

Total for Period Ci N/D N/D N/A N/A

Tritium Ci 1.02E+03 4.64E+02 N/A N/A

Gross Alpha Ci N/D N/D N/A N/A TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-23 THROUGH 12-31-23 Page 1 of 2 A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 12-Month Estimated Total

1. Type of Waste Unit Period Percent Error (%)
a. Spent resins, sludges, filters sludge, m3 1.70E+01
  • 2.50E+01 evaporator bottoms, etc., Ci 1.16E+02 2.50E+01
b. Dry compressible waste, contaminated m3 2.16E+02 ** 2.50E+01 equipment, etc., Ci 2.61E+00 2.50E+01 C. Irradiated components, control rods, m3 0.00E+00 *** 2.50E+01 etc., Ci 0.OOE+O0 2.50E+01
d. Other (describe)

Waste Oil/Blast media/Sewage/Gravel m3 2.31E+00 **** 2.50E+01 Dessicant/Soil/Construction debris Ci 2.76E-06 2.50E+01 Animal Carcasses

2. Estimate of major nuclide composition Estimated Total (by type of waste) (%) (Ci) Percent Error (%)
a. Co-60 5.04E+01 5.84E+01 2.50E+01 Ni-63 2.58E+01 2.99E+01 2.50E+01 Fe-55 1.21 E+01 1.40E+01 2.50E+01 Mn-54 2.88E+00 3.34E+00 2.50E+01 Co-58 2.60E+00 3.02E+00 2.50E+01 Sb-125 1.69E+00 1.96E+00 2.50E+01 Cs-137 1.59E+00 1.84E+00 2.50E+01 Zn-65 5.98E-01 6.93E-01 2.50E+01 Ae1-110m 4.03E-01 4.67E-01 2.50E+01 H-3 3.1 0E-01 3.59E-01 2.50E+01 Nb-95 2.69E-01 3.12E-01 2.50E+01 C-14 2.57E-01 2.98E-01 2.50E+01 Ni-59 1.99E-01 2.31 E-01 2.50E+01
b. Co-60 4.94E+01 1.29E+00 2.50E+01 Nb-95 1.50E+01 3.91E-01 2.50E+01 Zr-95 8.35E+00 2.18E-01 2.50E+01 Fe-55 5.78E+00 1.51 E-01 2.50E+01 Cr-51 5.42E+00 1.41 E-01 2.50E+01 Co-58 4.82E+00 1.26E-01 2.50E+01 Ni-63 3.00E+00 7.81E-02 2.50E+01 Cs-137 2.73E+00 7.12E-02 2.50E+01 Sb-125 1.92E+00 5.01 E-02 2.50E+01 Mn-54 1.39E+00 3.62E-02 2.50E+01 Ae1-110m 8.88E-01 2.31 E-02 2.50E+01 Sb-124 5.04E-01 1.31E-02 2.50E+01 Sn-113 2.69E-01 7.01 E-03 2.50E+01 H-3 1.64E-01 4.27E-03 2.50E+01
c. NONE
d. Cs-137 6.34E+01 1.75E+00 2.50E+01 Co-60 2.20E+01 6.08E-01 2.50E+01 Be-7 1.40E+01 3.86E-01 2.50E+01 Sb-125 2.64E-01 7.28E-03 2.50E+01 Fe-55 1.82E-01 5.02E-03 2.50E+01 Ni-63 4.89E-02 1.35E-03 2.50E+01 C-14 2.44E-03 6.74E-08 2.50E+01 TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS 01~1~3THROUGH12~1~3 Page 2 of 2
3. Solid Waste Disposition

Number of Shipments Mode of Transportation Destination

8 Truck Oak Ridge, TN 1 Truck Andrews, TX 2 Truck Clive, UT Note: Some of the 11 solid waste shipments contained multiple waste types and are therefore listed in more than one category below.

8. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination

0 N/A NIA

  • (3) shipments containing resins were shipped to a licensed waste processor for final dewatering and disposal (1) shipment containing resins was shipped to a licensed waste facility for disposal.

(1) shipment containing mechanical filters was shipped to a licensed waste processor for processing.

(1) shipment containing mechanical filters was shipped to a licensed waste facility for disposal.

    • (5) shipments containing dry compactible waste were shipped to a licensed waste processor for processing.

(1) shipment containing low activity calibration standards was shipped to a licensed waste facility for disposal.

      • None
        • (1) shipment containing waste oil was shipped to a licensed waste processor for processing.

(1) shipment containing dry sludge was shipped to a licensed waste processor for processing.

(1) shipment containing dry vegetation was shipped to a licensed waste processor for processing.

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