ML22122A069

From kanterella
Jump to navigation Jump to search

Annual Radioactive Effluent Release Report for North Anna Power Station (January 01, 2021 to December 31, 2021)
ML22122A069
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 04/14/2022
From: Dunnavant J
Virginia Electric & Power Co (VEPCO)
To:
Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
22-110
Download: ML22122A069 (42)
v • d • e


Text

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION (JANUARY 01, 2021 TO DECEMBER 31, 2021) es W. Dunnavant Supervisor Radiological Analysis and Instrumentation Erin M. Salling Superintendent Health Physics Technical Services APPROVED BY : _...z....:.~

""~....::__:o.,=.===---

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 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 STATION JANUARY 01, 2021 TO DECEMBER 31, 2021 INDEX Section No. Subject EXECUTIVE SUMJ\1ARY .................................. . 4 2 PURPOSE AND SCOPE .................................... . 5 3 DISCUSSION ................................................. . 5-6 4 SUPPLEMENTAL INFORMATION ...................... . 6-7 Effluent Release Data ............................................. . 8 Annual and Quarterly Doses ..................................... . 9 Revisions to Offsite Dose Calculation Manual (ODCM) ....................................... . Major Changes to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems ................................................. . 11 Inoperability of Radioactive Liquid and Gaseous Effluent Monitoring Instrumentation ....................................... . 12 Unplanned Releases ............................................ . 13 Lower Limits of Detection (LLD) for Effluent Sample Analysis .......................... . 14-15 Results of Ground Water Protection Initiative Sample Analysis .................................... . 16-21 Carbon-14 Calculations ....................................... . 22 Miscellaneous Annual Effluent Release Report Log ....................... . 23

1.0 EXECUTIVE

SUMMARY

The Annual Radioactive Effluent Release Report describes the radioactive effluent control program conducted at the No11h Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) during the 2021 calendar year. This document summarizes the quantities ofradioactive 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 1 through December 31, 2021 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 2021.

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 voluntaiy communication criteria of the NE! Ground Water Protection Initiative. This will be discussed in Attachment 6.

10 CFR 50, Appendix I dose calculations were performed on the 2021 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 3.564E-01 mrem, which is 5.940% of the dose li1nit, and the critical organ dose due to liquid effluents was 3.587E-01 mrem, which is 1.794% of the dose limit.
b. The air dose due to noble gases was l .749E-05 mrad gamma, which is 8.745E-05% of the annual gamma dose limit, and 1.461E-05 mrad beta, which is 3.653E-05% of the annual beta dose limit.
c. The critical organ dose for 1-131, 1-133, H-3, and particulates with half-lives greater than 8 days including C-14 was 2.798E+0 mrem, which is 9.33% of the annual dose limit. The bases ofC- 14 calculations are des(:ribed in Attachment 9.
d. The critical organ dose for 1-131, 1-133, H-3, and particulates with half-lives greater than 8 days not including C-14 was 5.668E-03 mrem, which is l.889E-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 a revision to the Offsite Dose Calculation Manual.during this reporting period, Revision 30, effective on 08/23/21.

Based on the levels of radioactivity observed during this reporting period and the dose calculations performed, the operations of the North Anna Nuclear Power Station Units 1 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 Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants",

Revision 1, June 1974, with data summarized on a quarterly basis for Table 1 and 2 and on an annual basis on Table 3. The report submitted before May 1st 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 report.

3.0 DISCUSSION The basis for the calculation of percent of Technical Specification for the critical organ in Table IA of Attachment 1 is the ODCM, section 6.3.1, which requires that the dose rate for iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days be less than or equal to 1500 mrem/yrto the critical organ at or beyond the site boundary.

The critical organ is the child's bone ifC-14 is included and child's thyroid ifC-14 is not included both via the inhalation pathway.

The basis for the calculation of percent of Technical Specification for the total body and skin in Table IA of Attachment 1 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 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 umestricted 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.

Percent of Technical Specification calculations are based on the total gaseous or liquid effluents released for that respective quarter.

5

The annual and quarterly doses, as reported in Attachment 2, were calculated according to the methodology presented in the ODCM. The beta and gamma air doses due to noble gases released from the site were calculated at site boundary. 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, 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- I 31, iodine- I 33, 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. 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 determined 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 (NID) on Attachment 1 ofthis report. If an 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 performed 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 five (5) changes made from the land use census in 2021. The nearest meat animal location in the N sector changed from 4.03 miles to None. The nearest garden location in the E sector changed from 1.75 miles to 2.05 miles. The nearest resident location in the SSW sector changed from 1.27 miles to 1.11 miles. The nearest garden in the WSW sector changed from 1. 77 miles to 2.26 miles. Finally, the nearest meat animal location in the WNW sector changed from 4.98 miles to None.

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 of new locations for obtaining replacement samples. Milk samples were not collected in 2021 because the last of the operating dairies in the sampling area ceased operations atthe 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 6

surface water samples included as part of the Radiological Environmental Monitoring Program, North Anna obtained subsurface water samples from various locations on the site. 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.

7

ATTACHMENT 1 EFFLUENT RELEASE DATA (01/21 - 12/21)

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.1 of the ODCM liquid and gaseous data is summarized on a quarterly basis and solid waste is summarized on an annual basis.

8

ATTACHMENT 2 ANNUAL AND QUARTERLY DOSES (01/21 - 12/21)

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.

1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Total Body Dose (mrem} 1.825E-1 1.019E-1 5.161E-2 2.036E-2 3.564E-1 Critical Organ Dose (mrem} l.835E-1 1.027E-1 5.183E-2 2.063E-2 3.587E-1 1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Noble Gas Gamma Dose (mrad} 1.614E-5 3.969E-7 8.175E-7 1.314E-7 1.749E-5 Noble Gas Beta Dose (mrad} 1.173E-5 4.304E-7 2.393E-6 5.462E-8 1.461E-5 Critical Organ (Child bone)

Dose for 1-131, 1-133, H-3, Particulates with T1/2>8 days (including C-14} (mrem} 8.178E-2 7.611E-3 2.562E+0 1.466E-1 2.798E+0 Critical Organ (Child thyroid)

Dose for 1-131, 1-133, H-3, Particulates with T1/2>8 days

{excluding C-14} {mrem} 5.754E-4 2.051E-3 2.464E-3 5.775E-4 5.668E-3 9

ATTACHMENT 3 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL

{ODCM)

(01/21 - 12/21)

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 a revision to the ODCM during this reporting period. The latest revision, Revision 30, was effective on 08/23/2021.

Revision 30 was initiated to update Attachment 6, Vent-Vent tables to distinguish each radiation monitor and continuous sampler by making bullet items. Also, Note 3 was re-written for clarity, as requested by the station Operations Department.

10

ATTACHMENT 4 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS (01/21 - 12/21)

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 2021.

11

ATTACHMENT 5 INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION (01/21 - 12/21)

As required by the ODCM, Sections 6.2.2.b.2 and 6.3 .2.b.3, a list and explanation for extended inoperability of radioactive liquid and/or gaseous effluent monitoring instrumentation is provided in this attachment.

No liquid and/or gaseous effluent monitoring instrumentation was out of service for> 30 days during the reporting period.

12

I ATTACHMENT 6 UNPLANNED RELEASES (01/21 - 12/21)

As required by the ODCM, Section 6.7.2.a.3, a list of unplanned releases, from the site to unrestricted areas, of radioactive material in gaseous and liquid effluents occurring during the reporting period, is made in this attachment.

There were no unplanned releases during calendar year 2021 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 current 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.

13

ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/21 - 12/21)

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 l.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 14

ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/21 - 12/21)

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 l.S0E-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 15

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/21 - 12/21)

The Ground Water Protection Program was established to improve North Anna's management of and response to instances where the inadvertent release of radioactive 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 quarterly 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, if required 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 2021. All liquid results are reported 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.

16

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/21 - 12/21) 1st Quarter 2021 Sample Gamma -Emitting Alpha Sample Date H-311J 1-131 11 ) Sr-8919011! Fe-55 111 Ni-63111 Pu-24111!

Media Particulatesl1l TRU 11 l GWP-18 01/14/21 WATER 3800 N/A N/A NIA N/A NIA NIA N/A PZ-1 02/09121 Insufficient volume PZ-2 02/09/21 Insufficient volume PZ-3 02/09121 WATER <1103 N/A N/A N/A N/A N/A N/A N/A GWP-3 02/09121 WATER <1112 N/A N/A N/A N/A N/A N/A N/A GWP-4 02/09/21 WATER <1126 N/A N/A N/A N/A N/A N/A N/A GWP-5A 02/09/21 WATER <1109 N/A N/A N/A N/A N/A N/A N/A GWP-7 02/09/21 WATER <1123 N/A N/A N/A N/A N/A N/A N/A GWP-8 02/09/21 WATER <1138 N/A N/A N/A N/A N/A N/A N/A GWP-9 02/09/21 WATER <1126 N/A N/A N/A N/A N/A N/A N/A GWP-13 02/09/21 WATER <1113 N/A N/A N/A N/A N/A N/A N/A GWP-15R 02/23/21 WATER <1164 N/A N/A N/A N/A N/A N/A N/A GWP-17 02/23/21 WATER <1129 N/A N/A N/A N/A N/A N/A N/A GWP-18 02/23/21 WATER 2160 N/A N/A N/A N/A N/A N/A N/A GWP-19 02/24/21 WATER <1191 N/A N/A N/A N/A N/A N/A N/A GWP-20 02/24/21 WATER <1181 N/A N/A N/A N/A N/A N/A N/A GWP-6 02/24/21 WATER <1181 N/A N/A N/A N/A N/A N/A N/A GWP-18 03/09/21 WATER 2050 N/A N/A N/A N/A N/A N/A N/A Sub Surface Drains 02/17/21 WATER <1530 N/A N/A N/A N/A N/A N/A N/A U-1 Intake Storm Dr.ains 03/03/21 WATER <1640 N/A N/A N/A N/A N/A N/A N/A U-2 Intake Storm Drains 03/03/21 WATER <1640 N/A N/A N/A N/A N/A N/A N/A Disch Canal Storm Drains 03/03/21 WATER <1640 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump East 02/17/21 WATER <998 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 02/17/21 WATER <998 N/A N/A N/A N/A N/A N/A N/A U-2 Mat Sump Inside 02/23/21 WATER <1092 N/A N/A N/A N/A N/A N/A N/A U-2 Mat Sump Outside 02/17/21 WATER <998 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 02/17/21 WATER <998 N/A N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 02/17/21 WATER <998 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump East 03/24/21 WATER <1137 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 03/24/21 WATER <1143 N/A N/A N/A N/A N/A N/A N/A U-2 Mat Sump Inside 03/24/21 WATER <1134 N/A N/A N/A N/A N/A N/A N/A U-2 Mat Sump Outside 03/24/21 WATER <1128 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 03/24/21 WATER <1134 N/A N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 03/24/21 WATER <1146 N/A N/A N/A N/A N/A N/A N/A (1) pCi/L 17

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/21 - 12/21) 2 nd Quarter 2021 Sample Gamma -Emitting Alpha Sample Date H-3<1> 1-131<1> Sr-89/90<1> Fe-55< 1> Ni-6311> Pu-241< 1>

Media Particulates<1> TRU< 1>

GWP-18 04/07/21 WATER 3700 N/A N/A N/A N/A N/A N/A N/A PZ-1 05/02/21 Insufficient volume PZ-2 05/02/21 Insufficient volume PZ-3 05/02/21 WATER 1215 N/A N/A N/A N/A N/A N/A N/A GWP-4 05/02/21 WATER 979 N/A N/A N/A N/A N/A N/A N/A GWP-5A 05/02/21 WATER <846 N/A N/A N/A NIA N/A N/A N/A GWP-7 05/02/21 WATER <865 N/A N/A N/A N/A N/A N/A N/A GWP-8 05/02/21 WATER 892 N/A N/A N/A N/A N/A N/A N/A GWP-9 05/02/21 WATER <877 N/A N/A N/A N/A N/A N/A N/A GWP-13 05/02/21 WATER <851 N/A N/A N/A N/A N/A N/A N/A GWP-16 05/11/21 WATER <959 N/A N/A N/A N/A N/A N/A N/A GWP-19 05/10/21 WATER <949 N/A N/A N/A N/A N/A N/A N/A GWP-20 05/10/21 WATER <954 N/A N/A N/A N/A N/A N/A N/A GWP-21 05/10/21 WATER <977 N/A N/A N/A N/A N/A N/A N/A GWP-22 05/10/21 WATER <991 N/A N/A N/A N/A N/A N/A N/A GWP-23 05/10/21 Insufficient volume GWP-6 05/12/21 WATER <1095 N/A N/A N/A N/A N/A N/A N/A GWP-14 .05/12/21 WATER <924 N/A N/A N/A N/A N/A N/A N/A GWP-15R 05/12/21 WATER <914 N/A N/A N/A N/A N/A N/A N/A GWP-17 05/19/21 WATER 1129 N/A N/A N/A N/A N/A N/A N/A GWP-18 05/24/21 WATER 4558 N/A N/A N/A N/A N/A N/A N/A Sub Surface Drains 05/24/21 WATER <1687 N/A N/A N/A N/A N/A N/A N/A U-1 Intake Storm Drains 05/24/21 WATER <1700 N/A N/A N/A N/A N/A N/A N/A U-2 Intake Storm Drains 05/24/21 WATER <1820 N/A N/A N/A N/A N/A N/A N/A Disch Canal Storm Drains 05/24/21 WATER <1730 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump East 05/11/21 WATER 2717 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 05/11/21 WATER 3442 N/A N/A N/A N/A N/A N/A N/A U-2 Mat Sump Inside 05/11/21 WATER 1895 N/A N/A N/A N/A N/A N/A N/A U-2 Mat Sump Outside 05/11/21 WATER 2153 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 05/11/21 WATER 3436 N/A N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 05/11/21 WATER 2003 N/A N/A N/A N/A N/A N/A N/A GWP-3 06/02/21 WATER 4270 N/A N/A N/A N/A N/A N/A N/A GWP-18 06/17/21 WATER 3515 N/A N/A N/A N/A N/A N/A N/A BTW-1 06/24/21 WATER <1055 N/A N/A N/A N/A N/A N/A N/A BTW-2 06/24/21 WATER <1047 N/A N/A N/A N/A N/A N/A N/A BTW-4 06/23/21 WATER <1066 N/A N/A N/A N/A N/A N/A N/A TTW-2 06/23/21 WATER <1066 N/A N/A N/A N/A N/A N/A N/A TTW-3 06/24/21 WATER <1066 N/A N/A N/A N/A N/A N/A N/A 18

TTW-5 06/24/21 WATER <1092 N/A N/A N/A N/A N/A N/A N/A BTW-1 (2) 06/24/21 WATER <960 N/A N/A NIA N/A N/A N/A N/A BTW-2 (2) 06/24/21 WATER <960 N/A N/A N/A N/A N/A N/A N/A BTW-4 (2) 06/23/21 WATER <961 N/A N/A N/A N/A N/A N/A N/A TTW-2 (2) 06/23/21 WATER <960 N/A N/A N/A N/A N/A N/A N/A TTW-3 (2) 06/24/21 WATER <962 N/A N/A N/A N/A N/A N/A N/A TTW-5 (2) 06/24/21 WATER <961 N/A N/A N/A N/A N/A N/A N/A PZ-3 (2) 05/02/21 WATER 1030 N/A N/A N/A N/A N/A N/A N/A GWP-3 (2) 06/02/21 WATER 4230 N/A N/A N/A N/A N/A N/A N/A GWP-4 (2) 05/02/21 WATER 991 N/A N/A N/A N/A N/A N/A N/A GWP-5A (2) 05/02/21 WATER <969 N/A N/A N/A N/A N/A N/A N/A GWP-6 (2) 05/12/21 WATER <967 N/A N/A N/A N/A N/A N/A N/A GWP-7 (2) 05/02/21 WATER <968 N/A N/A N/A N/A N/A N/A N/A GWP-8 (2) 05/02/21 WATER <971 N/A N/A N/A N/A N/A N/A N/A GWP-9 (2) 05/02/21 WATER <967 N/A N/A N/A N/A N/A N/A N/A GWP-13 (2) 05/02/21 WATER <965 N/A N/A N/A N/A N/A N/A N/A GWP-14 (2) 05/12/21 WATER <966 N/A N/A N/A N/A N/A N/A N/A GWP-15R (2) 05/12/21 WATER <968 N/A N/A N/A N/A N/A N/A N/A GWP-16 (2) 05/11/21 WATER <968 N/A N/A N/A N/A N/A N/A N/A GWP-17 (2) 05/19/21 WATER 1000 N/A N/A N/A N/A N/A N/A N/A GWP-18 (2) 05/24/21 WATER 4700 N/A N/A N/A N/A N/A N/A N/A GWP-19 (2) 05/10/21 WATER <968 N/A N/A N/A N/A N/A N/A N/A GWP-20 (2) 05/10/21 WATER <968 N/A N/A N/A N/A N/A N/A N/A GWP-21 (2) 05/10/21 WATER <969 N/A N/A N/A N/A N/A N/A N/A GWP-22 (2) 05/10/21 WATER <966 N/A N/A N/A N/A N/A N/A N/A TTW-1 Well abandoned in place, pending decommissioning TTW-4 Well abandoned in place, pending decommissioning (1) pCi/L (2) Vendor Analysis 19

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/21 - 12/21) 3rd Quarter 2021 Sample Gamma -Emitting Sr- Alpha Sample Date H-311> 1-13111) Fe-55<1> Ni-63<1> Pu-24111>

Media Particulates<1> 89/90< 1> TRU<1>

GWP-18 07119121 WATER 2214 NIA NIA NIA NIA NIA NIA NIA GWP-3 07122121 WATER 2624 NIA NIA NIA NIA NIA NIA NIA PZ-3 08118121 WATER 1538 NIA NIA NIA NIA NIA NIA NIA GWP-4 08118121 WATER <965 NIA NIA NIA NIA NIA NIA NIA GWP-6 08118121 WATER <1125 NIA NIA NIA NIA NIA NIA NIA GWP-17 08118121 WATER 1658 NIA NIA NIA NIA NIA NIA NIA GWP-15R 08117121 WATER <960 NIA NIA NIA NIA NIA NIA NIA GWP-18 08117121 WATER 3206 NIA NIA NIA NIA NIA NIA NIA GWP-19 08117121 WATER <958 NIA NIA NIA NIA NIA NIA NIA GWP-20 08117121 WATER 1217 NIA NIA NIA NIA NIA NIA NIA GWP-18 09115121 WATER 4048 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 08118121 WATER <1590 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 09101121 WATER <1460 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 09101121 WATER <1460 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm <1460 09101121 WATER NIA NIA NIA NIA NIA NIA NIA Drains U-1 Mat Sump East 08124121 WATER <916 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 08124121 WATER <904 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 08119121 WATER <975 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 08124121 WATER <909 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 08119121 WATER <986 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 08119121 WATER <970 NIA NIA NIA NIA NIA NIA NIA (1) pCi/L 20

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/21 - 12/21) 4th Quarter 2021 Sample Gamma -Emitting Alpha Sample Date H-3<1> 1-131<1> Sr-89190< 1> Fe-55<1> Ni-63!1> Pu-241<1>

Media Particulates<1> TRU! 1l GWP-18 10120121 WATER 3925 NIA NIA NIA NIA NIA N/A NIA PZ-3 10/21121 WATER 1171 NIA NIA NIA NIA N/A N/A NIA GWP-3 10/21/21 WATER 2207 N/A NIA N/A N/A N/A N/A N/A GWP-4 10/21/21 WATER <1145 N/A NIA N/A N/A N/A N/A N/A GWP-6 10/25/21 WATER <1145 N/A N/A N/A N/A NIA NIA N/A GWP-15R 10/25/21 WATER <1145 N/A N/A N/A N/A NIA N/A N/A GWP-17 10/25/21 WATER 1438 N/A N/A N/A N/A N/A N/A N/A GWP-19 10/25/21 WATER <1145 NIA N/A N/A NIA N/A N/A N/A GWP-20 10125/21 WATER <1145 NIA N/A N/A NIA N/A N/A N/A GWP-18 11/16121 WATER 4138 N/A N/A N/A N/A N/A N/A N/A GWP-18 12/14121 WATER 3637 NIA N/A NIA NIA N/A N/A N/A Sub Surface Drains 12/2/21 WATER <1457 N/A N/A N/A N/A N/A N/A N/A U-1 Intake Storm Drains 12/2/21 WATER <1457 N/A N/A N/A N/A N/A N/A N/A U-2 Intake Storm Drains 12/2/21 WATER <1457 N/A N/A N/A N/A N/A N/A N/A Disch Canal Storm Drains 12/2/21 WATER <1457 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump East 10/25/21 WATER 1652 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 10/25/21 WATER 2281 N/A N/A N/A N/A N/A N/A N/A U-2 Mat Sump Inside 10/25/21 WATER 2166 N/A N/A N/A N/A N/A N/A N/A U-2 Mat Sump Outside 10/25/21 WATER 3514 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 10/25/21 WATER 1652 N/A N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 10/25/21 WATER 2568 N/A N/A N/A N/A N/A N/A N/A (1) pCi/L 21

ATTACHMENT 9 CARBON-14 CALCULATIONS (01/21 - 12/21)

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 Reporting 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 ofradionuclides 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 30.1 Ci ofC-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 28.0 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 quarter.

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 transformation from an organic to an inorganic chemical form 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 2.358E-0l mremfrom the inhalation pathway, or 1.57E-02% TS of the 1500 mrem/yr dose rate limit and 2.562E+0 mrem from the ingestion pathway or 8.54E+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.

22

Miscellaneous There was one entry on the 2021 Annual Effluent Release Report Log, to document the revision of the Offsite Dose Calculation Manual. The latest revision, Revision 30, was effective on 08/23/2021.

23

TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/21 - 12/21)

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

A. Fission and Activiation Gases:

1. Total Release Curies 1.1 0E-01 8.98E-03 1.80E+1
2. Average Release Rate For Period µCi/sec 1.41 E-02 1.14E-03
8. Iodines:
1. Total lodine-131 Release Curies 0.00E+00 0.00E+00 2.80E+1
2. Average Release Rate For Period µCi/sec 0.00E+00 0.00E+00 C. Particulate {T112 > 8 days): '
1. Total Particulate (T1I2 > 8 days) Release Curies 5.16E-06 0.00E+00 2.8.0E+1
2. Average Release Rate For Period µCi/sec 6.63E-07 0.00E+0O
3. Gross Alpha Radioactivity Release Curies 0.00E+00 0.00E+00 D. Tritium: -
1. Total Release Curies 1.55E+00 4.98E+00 3.10E+1
2. Average Release Rate For Period µCi/sec 1.99E-01 6.33E-01 E. Carbon-14
1. Total Release Curies 1.89E+00 1.68E-01
2. Average Release Rate For Period µCi/sec 2.43E-01 2.14E-02 F. Percentage Of Technical Specification Limits
1. Total Body Dose Rate  % 1.23E-05 2.92E-07
2. Skin Dose Rate  % 3.33E-06 8.24E-08
3. Critical Organ Dose Rate (with C-14)  % 1.35E-03 4.96E-04 Critical Organ Dose Rate (without C-14)  % 1.19E-04 4.34E-04

TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/21 - 12/21)

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

A. Fission and Activiation Gases:

1. Total Release Curies 5.71E-02 4.68E-04 1.80E+1
2. Average Release Rate For Period µCi/sec 7.18E-03 5.89E B. Iodines:
1. Total lodine-131 Release Curies 0.00E+00 0.00E+00 2.80E+1
2. Average Release Rate For Period µCi/sec 0.00E+00 0.00E+00 C. Particulate {T112 > 8 days):
1. Total Particulate (T112 > 8 days) Release Curies 8.97E-07 0.00E+00 2.80E+1
2. Average Release Rate For Period µCi/sec 1.13E-07 0.00E+00
3. Gross Alpha Radioactivity Release Curies 0.00E+00 0.00E+00 D. Tritium:
1. Total Release Curies 6.14E+00 2.20E+00 3.10E+1
2. Average Release Rate For Period µCi/sec 7.73E-01 2.77E-01 F. Carbon-14
1. Total Release Curies 2.15E+01 4.44E+00
2. Average Release Rate For Period µCi/sec 2.70E+00 5.59E-01 F. Percentage Of Technical Specification Limits
1. Total Body Dose Rate  % 5.42E-07 9.89E-08
2. Skin Dose Rate  % 2.12E-07 2.S0E-08
3. Critical Organ Dose Rate (with C-14)  % 5.99E-02 1.71 E-03 Critical Organ Dose Rate (without C-14)  % 5.12E-04 1.0SE-04

TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/21 - 12/21)

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 - 131 m Ci N/D N/D N/D N/D Xenon - 133 Ci N/D N/D 5.22E-02 8.16E-03 Xenon -133m Ci N/D N/D 1.22E-03 N/D Xenon - 135 Ci N/D N/D 9.75E-03 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 Other (Specify) N/D N/D N/D N/D Argon - 41 Ci 3.50E-02 N/D 4.05E-04 8.08E-04 Total For Period Ci 3.50E-02 N/D* 6.36E-02 8.97E-03 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 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 18 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/21 - 12/21)

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

Barium - Lanthanum - 140 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 Ag-110m 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 2.62E-01 1.21E-01 4.?0E-04 1.27E-03 CARBON-14 Ci 1.0BE+00 1.04E-01 5.93E-01 6.42E-02

TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/21 - 12/21)

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/0 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 5.67E-02 N/D Xenon -133m Ci N/D N/D N/D N/D Xenon - 135 Ci N/D N/D N/D 1.22E-04 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 Other (Specify) N/D N/D N/D N/D Argon -41 Ci N/D N/D N/D 3.46E-04 Total For Period Ci N/D N/D 5.67E-02 4.68E-04 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 7.77E-08 3.53E-07 Total For Period Ci 7.77E-08 3.53E-07 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-110m Ci 8.75E-09 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 (01/21 - 12/21}

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

Arsenic- 76 Ci 8.89E-07 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 Total for Period (T1/2 > 8 days) Ci 8.75E-09 N/D N/D N/D Total for Period (T1/2 < 8 days) Ci 8.89E-07 N/D N/D N/D Total For Period Ci 8.97E-07 N/D N/D N/D GROSS ALPHA: Ci N/D N/D N/D N/D TRITIUM: Ci 3.75E-01 1.16E+00 5.11 E-04 1.81 E-04 CARBON-14 Ci 2.55E-01 4.44E+00 0.00E+00 0.00E+00

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/21 - 12/21)

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 1.31 E-05 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 9.12E-03 1.11 E-05 Xenon - 133m Ci N/D N/D 2.32E-04 N/D Xenon - 135 Ci N/D N/D 1.68E-03 N/D Xenon -135m Ci N/D N/D 7.14E-06 N/D Xenon - 137 Ci N/D N/D N/D N/D Xenon - 138 Ci N/D N/D N/D N/D Other (Specify)

Argon - 41 Ci N/D N/D 8.56E-05 N/D Total For Period Ci N/D N/D 1.11 E-02 1.11 E-05 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 2.84E-06 N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt - 60 Ci 2.31 E-06 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

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/21 - 12/21)

Page 2 of 4 CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES 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-91 m (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 5.16E-06 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 4.15E+00 1.29E+00 6.99E-01 CARBON-14 Ci N/D N/D 2.14E-01 N/D

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/21 - 12/21)

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 1.76E-07 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 3.50E-04 N/D Xenon -133m Ci N/D N/D N/D N/D Xenon -135 Ci N/D N/D 2.14E-05 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 Other (Specify) Ci Argon - 41 Ci N/D N/D 2.47E-06 N/D Total For Period Ci N/D N/D 3.74E-04 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 N/D 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 (01/21 - 12/21)

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

Cesium -137 Ci N/D N/D N/D N/D Barium - Lanthanum - 140 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/O N/D Other (Specify)

Strontium-91 (T1/2 < 8 days) Ci N/D N/D N/D N/D Rubidium-88 (T1 /2 < 8 days) Ci N/D N/D N/D N/D Niobium-95 (T1/2 > 8 days) Ci N/D N/D N/D N/D Ag-11 Om (T1 /2 > 8 days) Ci N/D N/D N/D N/D Rhodium-105 (T1/2 < 8 days) Ci N/D N/D N/O N/D Ruthenium-105 (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 (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 9.23E-01 1.04E+00 4.84E+00 1.43E-05 CARBON-14 Ci 2.12E+01 N/D N/D N/D

TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT - SUMMATION OF ALL RELEASES FOR (01/21 - 12/21)

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

A. Fission and Activiation Products:

1. Total Release (not including tritium, noble gas, and gross alpha). Curies 5.06E-03 1.62E-03 2.00E+01
2. Average diluted concentration during the period.* µCi/ml- 1.83E-11* 2.38E-12
3. Percent of applicable limit (T.S.)  % 1.64E-05 3.59E-06 B. Tritium:
1. Total release activity. Curies 5.17E+02 2.89E+02 2.00E+01
2. Average diluted concentration during the perjod. µGi/ml 1.87E-06 4.24E-07
3. Percent of applicable limit (T.S.)  % 1.87E-02 4.24E-03 C. Dissolved and Entrained Gases:
1. Total release activity. Curies 0.00E+00 0.00E+00 2.00E+01
2. Average diluted concentration during the period. µCi/ml 0.00E+00 0.00E+00
3. Percent of applicable limit (T.S.)  % 0.00E+00 0.00E+00 D. Gross Alpha Radioactivity:
1. Total release activity. Curies 0.00E+00 0.00E+00 2.00E+01 E. Volume of waste released: (prior to dilution). Liters 8.70E+07 9.92E+07 3.00E+00 F. Total volume of dilution water used during the period. Liters 2.77E+11 6.81 E+11 3.00E+00

TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT- SUMMATION OF ALL RELEASES FOR {01/21 - 12/21)

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

A. Fission and Activiation Products:

1. Total Release (not including tritium, noble gas, and gross alpha). Curies 1.67E-03 1.84E-04 2.00E+01
2. Average diluted concentration during the period. µCi/ml 2.18E-12 3.01 E-13
3. Percent of applicable limit (T.S.)  % 3.93E-06 7.69E-07 B. Tritium:
1. Total release activity. Curies 1.46E+02 5.76E+01 2.00E+01
2. Average diluted concentration during the period. µCi/ml 1.90E-07 9.44E-08
3. Percent of aoolicable limit (T.S.)  % 1.90E-03 9.44E-04 C. Dissolved and Entrained Gases:
1. Total release activity. Curies 0.00E+00 0.00E+00 2.00E+01
2. Average diluted concentration during the period. µCi/ml 0.00E+00 0.00E+00
3. Percent of applicable limit (T.S.)  % 0.00E+00 0.00E+00 D. Gross Alpha Radioactivity:
1. Total release activity. Curies 0.00E+00 0.00E+00 2.00E+01 E. Volume of waste released: (prior to dilution). Liters . 1.01E+08 1.13E+08 3.00E+00 F. Total volume of dilution water used during the period. Liters 7.68E+11 6.1DE+11 3.00E+00

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/21 - 12/21)

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 1.25E-05 N/D NIA NIA Iron - 59 Ci NID NID NIA NIA Cobalt-58 Ci 1.22E-03 1.08E-03 NIA NIA Cobalt- 60 Ci 6.39E-04 4.35E-04 NIA NIA Strontium - 89 Ci NID NID NIA NIA Strontium - 90 Ci NID N/D NIA NIA Antimony-122 Ci NID N/D NIA NIA Tellurium-123m Ci 1.08E-04 6.66E-05 NIA NIA Chromium-51 Ci NID NID NIA NIA Iodine - 131 Ci NID NID NIA NIA Iodine - 133 Ci NID NID NIA

TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/21 - 12/21)

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 N/D N/D N/A N/A Xenon -133m Ci N/D N/D N/A NIA Xenon - 135 Ci N/D N/D N/A N/A Xenon -135m Ci N/D N/D N/A N/A Other (Specify) Ci N/D N/D N/A N/A Krypton-88 ( 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 N/A Total for Period Ci N/D N/D N/A N/A Tritium Ci 5.17E+02 2.89E+02 N/A N/A Gross Alpha Ci N/D N/D N/A N/A

TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/21 - 12/21)

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 N/D NID NIA NID Iron - 59 Ci NID NID NIA NID Cobalt-58 Ci 8.63E-04 3.70E-05 NIA NID Cobalt-60 Ci 7.20E-04 8.77E-05 NIA 8.90E-07 Strontium - 89 Ci NID NID NIA NID Strontium - 90 Ci NID NID NIA NID Niobium - 95 Ci NID NID NIA NID Zirconium - 95 Ci NID NID NIA NID Silver - 11 Om Ci NID NID NIA NID Iodine -131 Ci NID NID NIA NID Iodine - 133 Ci NID NID NIA NID Cesium -134 Ci NID NID NIA 1.31 E-06 Cesium -137 Ci 1.04E-05 NID NIA 1.25E-05 Tellurium-123m Ci 8.04E-05 NID NIA NID Cerium -141 Ci NID NID NIA NID Chromium-51 Ci NID NID NIA 1.82E-06 Nickel - 63 (T112 > 8 days) Ci NID NID NIA NID Ruthenium-105 (T112 < 8 days) Ci NID NID NIA N/D Antimony-125 (T112 > 8 days) Ci NID NID NIA 3.44E-05 Antimony-122 (T112 > 8 days) Ci NID NID NIA 1.89E-07 Tellurium-125m (T112 > 8 days) Ci N/D N/D NIA 7.97E-06 Total for Period Ci 1.67E-03 1.25E-04 NIA 5.92E-05

TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/21 - 12/21)

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

Xenon - 133 Ci NID NID NIA NID Xenon -133m Ci NID NID NIA NID Xenon -135 Ci NID NID NIA NID Xenon -135m Ci NID NID NIA NID Other (Specify)

Argon - 41 (T112 < 8 days) Ci NID NID NIA NID Krypton - 85 (T112 > 8 days) Ci NID NID NIA NID Total for Period Ci NID NID NIA NID Tritium Ci 1.46E+02 5.76E+01 NIA 4.79E-02 Gross Alpha Ci N/D NID NIA NID

TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-21 THROUGH 12-31-21 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, mJ 1.79E+01
  • 2.50E+01 evaporator bottoms, etc., Ci 9.37E+01 2.50E+01
b. Dry compressible waste, contaminated mJ 1.84E+02 ** 2.50E+01 equipment, etc., Ci 1.12E-01 2.50E+01
c. Irradiated components, control rods, mJ 0.OOE+00 *** 2.50E+01 etc., Ci O.0OE+00 2.50E+01
d. Other (describe)

Used oil/Blast media/Sewage/Gravel mJ 3.56E+OO **** 2.50E+01 Dessicant/Soil/Construction debris Ci 1.29E-01 2.50E+01 Animal Carcasses

2. Estimate of major nuclide composition Estimated Total (by type of waste) (%) (Ci) Percent Error (%)
a. Co-60 4.81E+01 4.56E+01 2.50E+01 Ni-63 1.78E+01 1.67E+01 2.50E+01 Fe-55 1.36E+01 1.27E+01 2.50E+01 Co-58 8.21E+00 7.68E+00 2.50E+01 Mn-54 4.87E+00 4.56E+00 2.50E+01 Zn-65 1.S0E+00 1.40E+00 2.50E+01 Sb-125 1.26E+00 1.18E+00 2.50E+01 Cs-137 1.24E+00 1.16E+00 2.50E+01 Be-7 1.11E+00 1.04E+00 2.50E+01 Ai:i-110m 3.70E-01 3.44E-01 2.50E+01 Co-57 1.B0E-01 1.72E-01 2.50E+01 Nb-95 1.B0E-01 1.66E-01 2.50E+01 C-14 1.70E-01 1.62E-01 2.50E+01
b. Co-60 5.29E+01 5.94E-02 2.50E+01 Nb-95 1.26E+01 1.42E-02 2.50E+01 Zr-95 7.19E+00 8.0BE-03 2.50E+01 Fe-55 6.17E+00 6.93E-03 2.50E+01 Co-58 5.61E+00 6.30E-03 2.50E+01 Cr-51 4.84E+00 5.44E-03 2.50E+01 Ni-63 .2.86E+00 3.22E-03 2.50E+01 Sb-125 2.71E+00 3.04E-03 2.50E+01 Mn-54 1.90E+00 2.14E-03 2.50E+01 Cs-137 1.60E+00 1.79E-03 2.50E+01 Te-125m 5.30E-01 5.91E-04 2.50E+01 Sn-113
  • 3.10E-01 3.51E-04 2.50E+01 Ai:i-110m 2.90E-01 3.29E-04 2.50E+01 H-3 2.20E-01 2.S0E-04 2.50E+01 C. NONE
d. C-14 9.64E+01 1.24E-01 2.50E+01 H-3 3.29E+00 4.24E-03 2.50E+01 Co-60 1.S0E-01 1.94E-04 2.50E+01 Cs-137
  • 9.00E-02 1.1 SE-04 2.50E+01 Ni-63 6.00E-02 8.35E-05 2.50E+01
Retrieved from "https://kanterella.com/w/index.php?title=ML22122A069&oldid=3440622"