ML21139A263

Independent Spent Fuel Storage Installation (ISFSI) - Annual Radioactive Effluent Release Report

ML21139A263
Person / Time
Site:	North Anna
Issue date:	04/26/2021
From:	Mladen F Virginia Electric & Power Co (VEPCO)
To:	Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
21-129
Download: ML21139A263 (129)

Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 26, 2021 United States. Nuclear Regulatory Commission Serial No.21-129 Attention: *Document Control Desk NAPS/DPM Washington, D. C. 20~55 Docket Nos. 50-338/339 72-16 72-56 License Nos. NPF-4/7 SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

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

ANNUAL RADIOACTIVE.EFFLUENT RELEASE REPORT Enclosed is the 2020 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 yours,

_//~

-z red Mladen---

Site Vice President

.Enclosure Commitments made irtthis letter: None cc: U. S. Nuclear Regulatory Commission (w/o Enclosure)

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• Region II

. Marquis One Tower *

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245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia, 30303-1257 * !VM 5 <; z?

• Director, Division of Spent Fuel Management (w/o Enclosure). ;J/c./<_

Office of Nuclear Material Safety and Safeguards

• U. S. Nuclear R~gulatory .Commission

vt-JS5 Washingtqn, D. G.20555

• NRC Senior Re~ident Inspector (w/o Enclosure)

North Anna Power Station

ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT NORTH ANNA POWER STATION (JANUARY 01, 2020 TO DECEMBER 31, 2020)

James W. Dunnavant Supervisor Radiological Analysis and Instrumentation REVIEWED BY:

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Health Physics Technical Services 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, 2020 TO DECEMBER 31, 2020 INDEX Section No. Subject Page 1 EXECUTIVE

SUMMARY

.................................. . 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) ....................................... . 10 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 North Anna Power Station and the Independent Spent Fuel Storage Installation (ISFSI) during the 2020 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 1 through December 31, 2020 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 2020.

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 2020 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 6.443E-01 mrem, which is 10.738% of the dose limit, and the critical organ dose due to liquid effluents was 6.509E-01 mrem, which is 3.255% of the dose limit.

b. The air dose due to noble gases was l.735E-04 mradgamma, which is 8.675E-04% of the annual gamma dose limit, and 9.913E-05 mrad beta, which is 2.478E-4% of the annual beta dose limit.

c. The critical organ dose for I-131, I-133, H-3, and particulates with half-lives greater than 8 days including C-14 was

2. 784E +O mrem, which is 9 .28% of the annual dose limit. The bases of C-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 8.183E-03 mrem, which is 2.728E-02% ofthe 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 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 ofRadioactive 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 and2 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.

Maj or 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 if C-14 is included and child's thyroid if C-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 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.

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 ofairbome 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. 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 of this report. Ifan analysis for an isotope was not performed, then the activity was reported as Not Applicable (NIA).

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 six (6) changes made from the land use census in 2020. The nearest garden location in the NNE sector changed from 1.66 miles to 3.25 miles. The nearest garden location in the ESE sector changed from 1.71 miles to 1.70 miles.

The nearest garden location in the SSE sector changed from 1.00 mile to 2.66 miles. The nearest garden in the S sector changed from 1.49 miles to 1.48 miles. The nearest garden in the SSW sector changed from 2.37 miles to 2.00 miles. Finally, the nearest garden location in the SW sector changed from 1.65 miles to 3.96 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 of new locations for obtaining replacement samples. Milk samples were not collected in 2020 because the last of the operating dairies in the sampling area ceased operations at the start ofcalendar year 2018. Vegetation samples were not collected from stations 14B, 15, 16, 23 and 26 from January through April 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- I 4.

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 (01/20 - 12/20)

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.

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ATTACHMENT 2 ANNUAL AND QUARTERLY DOSES (01/20 - 12/20)

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) 9.176E-2 3.105E-1 8.604E-2 1.561E-1 6.443E-1 Critical Organ Dose (mrem) 9.295E-2 3.124E-1 8.738E-2 1.581E-1 6.509E-1 1st 2nd 3rd 4th Annual Quarter Quarter Quarter Quarter Total Noble Gas Gamma Dose (mrad) 2.908E-6 1.411E-4 2.337E-5 6.00lE-6 1.734E-4 Noble Gas Beta Dose (mrad) 1.026E-6 5.732E-5 3.299E-5 7.792E-6 9.913E-5 Critical Organ (Child bone)

Dose for 1-131, 1-133, H-3, Particulates with T1/2>8 days (including C-14) (mrem) 8.215E-2 6.454E-3 2.546E+0 1.494E-1 2.784E+0 Critical Organ (Child thyroid)

Dose for 1-131, 1-133, H-3, Particulates with T1/2> 8 days (excluding C-14) (mrem) 1.449E-3 9.138E-4 2.463E-3 3.357E-3 8.183E-3 9

ATTACHMENT 3 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL

{ODCM)

{01/20 - 12/20)

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.

10

ATTACHMENT 4 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS (01120 - 12/20)

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 2020.

11

ATTACHMENT 5 INOPERABILITY OF RADIOACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION (01/20 - 12/20)

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.

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ATTACHMENT 6 UNPLANNED RELEASES (01/20 - 12/20)

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 2020 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. Elevated results indicated in Attachment 8 are from the on-going investigation/ mitigation for the voluntary communication made in 2010. The hydrological modeling indicates the horizontal groundwater movement around well

1. 6 is< 1 inch per day.

13

ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS (01/20 - 12/20)

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 14

ATTACHMENT 7 LOWER LIMITS OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS

{01/20 - 12/20)

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 l.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.S0E-8 6.00E-8 Iron - 59 5.00E-7 3.00E-8 7.00E-8 Cobalt- 60 5.00E-7 1.00E-8 5.S0E-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 15

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/20 - 12/20)

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 VP AP-2103N.

On the following pages is a summary of the samples and results of the ground water protection program taken for calendar year 2020. All liquid results are reported in pCi/L, while soil results for tritium are reported in pCi/g of soil, wet. An "NIA" indicates a sample analysis was not performed for that sample. An "NID" 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.

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ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/20 - 12/20) 1st Quarter 2020 Sample Gamma -Emitting Alpha Sample Date H-3 11 > 1-131<1> Sr-89/90<1> Fe-ssc1> Ni-63 11 > Pu-241<1>

Media Particulates<1> TRU<1>

PZ-3 01/14/20 WATER 1691 N/A N/A N/A N/A N/A N/A N/A PZ-3 02/03/20 WATER 1079 N/A N/A N/A N/A N/A N/A N/A PZ-3 03/18/20 WATER 2210 N/A N/A N/A N/A N/A N/A N/A GWP-3 01/14/20 WATER 2027 N/A N/A N/A N/A N/A N/A N/A GWP-3 02/03/20 WATER 1002 N/A N/A N/A N/A N/A N/A N/A GWP-3 03/18/20 WATER 2035 N/A N/A N/A N/A N/A N/A N/A GWP-4 01/15/20 WATER <943 N/A N/A N/A N/A N/A N/A N/A GWP-6 01/14/20 WATER 1537 N/A N/A N/A N/A N/A N/A N/A GWP-6 02/03/20 WATER <921 N/A N/A N/A N/A N/A N/A N/A GWP-6 03/18/20 WATER <841 N/A N/A N/A N/A N/A N/A N/A GWP-15R 01/15/20 WATER <918 N/A N/A N/A N/A N/A N/A N/A GWP-17 01/14/20 WATER 1852 N/A N/A N/A N/A N/A N/A N/A GWP-18 01/14/20 WATER 4088 N/A

• N/A N/A N/A N/A N/A N/A GWP18 02/14/20 WATER 4685 N/A N/A N/A N/A N/A N/A N/A GWP-18 03/18/20 WATER 4751 N/A N/A N/A N/A N/A N/A N/A GWP-19 01/14/20 WATER 1949 N/A N/A N/A N/A N/A N/A N/A GWP-20 01/15/20 WATER <916 N/A N/A N/A N/A N/A N/A N/A Sub Surface Drains 02/26/20 WATER <1411 N/A N/A N/A N/A N/A N/A N/A U-1 Intake Storm Drains 02/26/20 WATER <1402 N/A N/A N/A N/A N/A N/A N/A U-2 Intake Storm Drains 02/26/20 WATER <1407 N/A . N/A N/A N/A N/A N/A N/A Disch Canal Storm Drains 02/26/20 WATER <1407 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump East 02/27/20 WATER 1875 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 02/27/20 WATER 1421 N/A N/A N/A N/A N/A N/A N/A U-2 Mat Sump Inside 02/27/20 WATER 1493 N/A N/A N/A N/A N/A N/A N/A U-2 Mat Sump Outside 02/27/20 WATER 1007 N/A N/A N/A N/A N/A N/A NIA U-1 AB/FB GWMS 02/27/20 WATER 1688 N/A N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 02/27/20 WATER 1650 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 (01/20 - 12/20) 2 nd Quarter 2020 Sample Gamma -Emitting Alpha Sample Date H-3<1> 1-131 11 > Sr-89/90<1> Fe-5511> Ni-63 11 > TRUl1> Pu-241 11 >

Media Particulates<1>

PZ-3 04/15/20 WATER 1468 N/A N/A N/A N/A N/A N/A N/A PZ-3 05/20/20 WATER 2401 N/A N/A N/A N/A N/A N/A N/A PZ-3 06/03/20 WATER 1575 N/A N/A N/A N/A N/A N/A N/A PZ-3 (2) 06/03/20 WATER 1330 N/A N/A N/A N/A N/A N/A N/A GWP-3 04/15/20 WATER 1918 N/A N/A N/A N/A N/A N/A N/A GWP-3 05/20/20 WATER 993 N/A N/A N/A N/A N/A N/A N/A GWP-3 06/03/20 WATER 968 N/A N/A N/A N/A N/A N/A N/A GWP-3 (2) 06/03/20 WATER <909 N/A N/A N/A N/A N/A N/A N/A GWP-4 06/03/20 WATER 1721 N/A N/A N/A N/A N/A N/A N/A GWP-4 (2) 06/04/20 WATER 1630 N/A N/A N/A N/A N/A N/A N/A GWP-5A 06/05/20 WATER <1007 N/A N/A N/A N/A N/A N/A N/A GWP-5A (2) 06/05/20 WATER <906 N/A N/A N/A N/A N/A N/A N/A GWP-6 04/15/20 WATER <1001 N/A

• N/A N/A N/A N/A N/A N/A GWP-6 05/20/20 WATER 998 N/A N/A N/A N/A N/A N/A N/A GWP-6 06/05/20 WATER 1411 N/A N/A N/A N/A N/A N/A N/A GWP-6 (2) 06/05/20 WATER <908 N/A N/A N/A N/A N/A N/A N/A GWP-7 06/05/20 WATER <995 N/A N/A N/A N/A N/A N/A N/A GWP-7 (2) 06/05/20 WATER <906 N/A N/A N/A N/A N/A N/A N/A GWP-8 06/10/20 WATER <914 N/A N/A N/A N/A N/A N/A N/A GWP-8 (2) 06/10/20 WATER <907 N/A N/A N/A N/A N/A N/A N/A GWP-9 06/10/20 WATER <914 N/A N/A N/A N/A N/A N/A N/A GWP-9 (2) 06/10/20 WATER <906 N/A N/A N/A N/A N/A N/A N/A GWP-13 06/03/20 WATER <898 N/A N/A N/A N/A N/A N/A N/A GWP-13 (2) 06/03/20 WATER <907 N/A N/A N/A N/A N/A N/A N/A GWP-14 06/11/20 WATER <939 N/A N/A N/A N/A N/A N/A N/A GWP-14 (2) 06/11/20 WATER <911 N/A N/A N/A N/A N/A N/A N/A GWP-15R 06/18/20 WATER <868 N/A N/A N/A N/A N/A N/A N/A GWP-15R (2) 06/18/20 WATER <904 N/A N/A N/A N/A N/A N/A N/A GWP-16 06/18/20 WATER <863 N/A N/A N/A N/A N/A N/A N/A GWP-16 (2) 06/18/20 WATER <907 N/A N/A N/A N/A N/A N/A N/A GWP-17 06/17/20 WATER 1471 N/A N/A N/A N/A N/A N/A N/A GWP-17 (2) 06/17/20 WATER <906 N/A N/A N/A N/A N/A N/A N/A GWP-18 04/15/20 WATER 3076 N/A N/A N/A N/A N/A N/A N/A GWP-18 05/20/20 WATER 3251 N/A N/A N/A N/A N/A N/A N/A GWP-18 06/11/20 WATER 4425 N/A N/A N/A N/A N/A N/A N/A GWP-18 (2) 06/11/20 WATER 2320 N/A N/A N/A N/A N/A N/A N/A GWP-19 06/03/20 WATER 1005 N/A N/A N/A N/A N/A N/A N/A GWP-19 (2) 06/03/20 WATER 1160 N/A N/A N/A N/A N/A N/A N/A GWP-20 06/05/20 WATER <987 N/A N/A N/A N/A N/A N/A N/A GWP-20 (2) 06/05/20 WATER <907 N/A N/A N/A N/A N/A N/A N/A GWP-21 06/05/20 WATER <985 N/A N/A N/A N/A N/A N/A N/A GWP-21 (2) 06/05/20 WATER <906 N/A N/A N/A N/A N/A N/A N/A GWP-22 06/05/20 WATER <987 N/A N/A N/A N/A N/A N/A N/A 18

___J

GWP-22 (2) 06105120 WATER <744 NIA NIA NIA NIA NIA NIA NIA BTW-1 06124120 WATER <907 NIA NIA NIA NIA NIA NIA NIA BTW-1 (2) 06124120 WATER <720 NIA NIA NIA NIA NIA NIA NIA BTW-2 06124120 WATER <898 N/A NIA NIA NIA N/A N/A NIA BTW-2 (2) 06124120 WATER <736 NIA NIA N/A NIA NIA N/A NIA BTW-4 06124/20 WATER <914 NIA N/A NIA NIA N/A NIA NIA BTW-4 (2) 06124120 WATER <733 NIA N/A N/A N/A N/A NIA NIA TTW-2 06124120 WATER <903 N/A NIA NIA NIA NIA NIA N/A TTW-2 (2) 06/24120 WATER <747 N/A N/A NIA NIA NIA NIA NIA TTW-3 06124120 WATER <901 NIA NIA NIA NIA NIA NIA NIA TTW-3 (2) 06124120 WATER <741 NIA NIA N/A NIA NIA NIA NIA TTW-5 06124120 WATER <936 NIA NIA N/A N/A NIA NIA NIA TTW-5 (2) 06124120 WATER <734 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 05119120 WATER <1530 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 05120120 WATER <1506 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 05120120 WATER <1512 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 05120120 WATER <1496 NIA NIA N/A NIA NIA NIA NIA U-1 Mat Sump East 05120120 WATER 1327 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 051201200 WATER 1374 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 05120120 WATER 1805 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 05120120 WATER 1256 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 05120120 WATER 1407 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 05/20120 WATER 1963 NIA NIA NIA NIA NIA NIA NIA PZ-1 06103120 WATER 977 NIA NIA NIA NIA NIA NIA NIA PZ-1 (2) 06103120 WATER <725 NIA NIA NIA NIA NIA NIA NIA PZ-2 06103120 WATER <898 NIA NIA NIA NIA NIA NIA NIA PZ-2 (2) 06103120 WATER 743 N/A NIA N/A 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 19

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/20 - 12/20) 3 rd Quarter 2020 Sample Gamma -Emitting Sr- Alpha Sample Date H-3 111 1-131 111 Fe-55111 Ni-63111 Pu-241111 Media Particulates<1l 89190<1) TRU<1l PZ-3 0812012020 WATER 1370 NIA NIA NIA NIA NIA NIA NIA GWP-3 0812012020 WATER 1117 NIA NIA NIA NIA NIA NIA NIA GWP-4 0812012020 WATER 1042 NIA NIA NIA NIA NIA NIA NIA GWP-6 0812012020 WATER <908 NIA NIA NIA NIA NIA NIA NIA GWP-15R 0911012020 WATER <1013 NIA NIA NIA NIA NIA NIA NIA GWP-17 0911012020 WATER 1280 NIA NIA NIA NIA NIA NIA NIA GWP-18 0712912020 WATER 4397 NIA NIA NIA NIA NIA NIA NIA GWP-18 0812012020 WATER 3450 NIA NIA NIA NIA NIA NIA NIA GWP-18 0911012020 WATER 2436 NIA NIA NIA NIA NIA NIA NIA GWP-19 0812012020 WATER <910 NIA NIA NIA NIA NIA NIA NIA GWP-20 0812012020 WATER <924 NIA NIA NIA NIA NIA NIA NIA Sub Surface Drains 0812512020 WATER <1692 NIA NIA NIA NIA NIA NIA NIA U-1 Intake Storm Drains 0812012020 WATER <1557 NIA NIA NIA NIA NIA NIA NIA U-2 Intake Storm Drains 0812012020 WATER <1595 NIA NIA NIA NIA NIA NIA NIA Disch Canal Storm Drains 0812012020 WATER <1592 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 0811912020 WATER <964 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump East 0912412020 WATER <1047 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 0811912020 WATER <964 NIA NIA NIA NIA NIA NIA NIA U-1 Mat Sump South 0912412020 WATER <1050 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 0811912020 WATER <962 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Inside 0912412020 WATER 1697 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 0811912020 WATER 2005 NIA NIA NIA NIA NIA NIA NIA U-2 Mat Sump Outside 0912512020 WATER 2268 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 0811912020 WATER 1493 NIA NIA NIA NIA NIA NIA NIA U-1 ABIFB GWMS 0912412020 WATER <1047 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 0812112020 WATER 1715 NIA NIA NIA NIA NIA NIA NIA U-2 ABIFB GWMS 0912512020 WATER 2553 NIA NIA NIA NIA NIA NIA NIA (1) pCi/L 20

ATTACHMENT 8 RESULTS OF GROUND WATER PROTECTION INITIATIVE SAMPLE ANALYSIS (01/20 - 12/20) 4th Quarter 2020 (l)pCi/L Sample Gamma -Emitting Alpha Sample Date H-311> 1-13111) Sr-89/90<1> Fe-55 11 > Ni-63<1> Pu-241<1>

Media Particulatesl1> TRUl1>

PZ-3 11/06/2020 WATER <900 N/A N/A N/A N/A N/A N/A N/A GWP-3 11/06/2020 WATER 1083 N/A N/A N/A N/A N/A N/A N/A GWP-4 11/06/2020 WATER 1163 N/A N/A N/A N/A N/A N/A N/A GWP-6 12/03/2020 WATER 1496 N/A N/A N/A N/A N/A N/A N/A GWP-15R 12/03/2020 WATER <1015 N/A N/A N/A N/A N/A N/A N/A GWP-17 12/03/2020 WATER 1054 N/A N/A N/A N/A N/A N/A N/A GWP-18 10/27/2020 WATER 3965 N/A N/A N/A N/A N/A N/A N/A GWP-18 11/17/2020 WATER 2693 N/A N/A N/A N/A N/A N/A N/A GWP-18 12/12/2020 WATER 3945 N/A N/A N/A N/A N/A N/A N/A GWP-19 12/03/2020 WATER <1010 N/A N/A N/A N/A N/A N/A N/A GWP-20 12/03/2020 WATER <999 N/A N/A N/A N/A N/A N/A N/A Sub Surface Drains 11/17/2020 WATER <1685 N/A N/A N/A N/A N/A N/A N/A U-1 Intake Storm Drains 11/17/2020 WATER <1697 N/A N/A N/A N/A N/A N/A N/A U-2 Intake Storm Drains 11/17/2020 WATER <1639 N/A N/A N/A N/A N/A N/A N/A Disch Canal Storm Drains 11/17/2020 WATER <1702 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump East 10/28/2020 WATER <971 N/A N/A N/A N/A N/A N/A N/A U-1 Mat Sump South 10/28/2020 WATER <934 N/A N/A N/A N/A N/A N/A N/A U-2 Mat Sump Inside 10/28/2020 WATER <924 N/A N/A N/A N/A N/A N/A N/A U-2 Mat Sump Outside 10/28/2020 WATER 1257 N/A N/A N/A N/A N/A N/A N/A U-1 AB/FB GWMS 10/28/2020 WATER <934 N/A N/A N/A N/A N/A N/A N/A U-2 AB/FB GWMS 10/28/2020 WATER 2976 N/A N/A N/A N/A N/A N/A N/A 21

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

Carbon-14, 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 ofC-14 in the atmosphere. Due to the long half-life ofC-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 nuclearreactors, 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 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 30.1 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 27.8 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 2.35E-01 rnrem from the inhalation pathway, or 1. 57E-02 % TS of the 15 00 rnrem/yr dose rate limit and 2 .54E +0 rnrem from the ingestion pathway or 8 .47+00% TS of the 10CFR50, Appendix I, ALARA design objective of 15 rnrem/yrperunit. In both cases the critical organ was determined to be the child's bone.

22

Miscellaneous There were no entries on the 2020 Annual Effluent Release Report Log.

23

TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/20 - 12/20)

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

A. Fission and Activiation Gases:

1. Total Release Curies 8.22E-03 1.32E-01 1.80E+1

2. Average Release Rate For Period µCi/sec 1.05E-03 1.67E-02 B. Iodines:

1. Total lodine-131 Release Curies 0.00E+00 7.16E-09 2.80E+1

2. Average Release Rate For Period µCi/sec 0.00E+00 9.10E-10 C. Particulate (T112 > B days):

1. Total Particulate (T112 > 8 days) Release Curies 0.00E+00 4.98E-05 2.80E+1

2. Average Release Rate For Period uCi/sec 0.00E+00 6.34E-06

3. Gross Alpha Radioactivity Release Curies 0.00E+00 0.00E+00 D. Tritium:

1. Total Release Curies 5.87E+00 2.83E+00 3.10E+1

2. Average Release Rate For Period µCi/sec 7.47E-01 3.60E-01 E. Carbon-14

1. Total Release Curies 1.88E+00 1.68E-01

2. Average Release Rate For Period µCi/sec 2.39E-01 2.14E-02

"* i F. Percentage Of Technical S~ecification Limits

1. Total Body Dose Rate  % 2.22E-06 1.0BE-04

2. Skin Dose Rate  % 5.43E~g7 2.66E-05

3. Critical Organ Dose Rate (with C-14)  % 1.47E-03 2.42E-04 Critical Organ Dose Rate (without C-14)  % 2.60E-04 1.81E-04

TABLE 1A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF ALL GASEOUS EFFLUENT RELEASES FOR (01/20 - 12/20)

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

A. Fission and Activiation Gases:

1. Total Release Curies 1.64E-02 5.54E-02 1.80E+1

2. Average Release Rate For Period µCi/sec 2.06E-03 6.97E-03 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 {T1I2 > 8. dalr!s}:

1. Total Particulate (T1I2 > 8 days) Release Curies 5.S0E-06 0.00E+O0 2.80E+1

2. Average Release Rate For Period uCi/sec 6.92E-07 0.00E+00

3. Gross Alpha Radioactivity Release Curies 0.00E+00 0.00E+00 D. Tritium:

1. Total Release Curies 5.44E+00 8.32E+00 3.10E+1

2. Average Release Rate For Period µCi/sec 6.85E-01 1.05E+00 F. Carbon-14

1. Total Release Curies 2.14E+01 4.42E+00

2. Averaae Release Rate For Period uCi/sec 2.69E+00 5.56E-01 F. Percentage Of Technical Specification Limits

1. Total Body Dose Rate ,*.,% 2.24E-06 4.33E-06

2. Skin Dose Rate  % 6.38E-07 1.27E-06

3. Critical Organ Dose Rate (with*C-14)  % 5.96E-02* 2.30E-03 Critical Organ Dose Rate (without C-14)  % 4.30E-04 7.01E-04

TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR {01/20 - 12/20)

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/0 N/D Krypton - 87 Ci N/0 N/D N/0 NID Krypton - 88 Ci N/0 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 6.10E-02 Xenon -133m Ci N/D N/D N/D N/D Xenon - 135 Ci N/D N/D N/0 3.95E-04 Xenon -135m Ci N/D N/D N/0 N/D Xenon -137 Ci N/0 N/D N/D N/D Xenon -138 Ci N/D N/D N/D N/0 Other (Specify) N/D N/0 N/D N/0 Argon - 41 Ci 8.22E-03 3.86E-03 N/D N/0 Total For Period Ci 8.22E-03 3.86E-03 N/D 6.14E-02 Iodines:

lodine-130 Ci N/0 N/0 N/D N/0 Iodine - 131 Ci N/0 7.16E-09 N/0 N/0 Iodine- 132 Ci N/D N/D N/0 N/0 Iodine- 133 Ci N/D N/0 N/D N/D Iodine - 134 Ci N/D N/D N/D N/0 Iodine - 135 Ci N/D N/D N/D N/D Total For Period Ci N/D 7.16E-09 N/D N/0 Particulates:

Manganese - 54 Ci NID N/D N/D N/D Cobalt - 58 Ci N/D N/D N/D N/D Iron - 59 Ci N/D N/0 N/0 N/D Cobalt-60 Ci N/D N/0 N/0 N/D Zinc- 65 Ci NID

• Nto'*, N/D N/0 Strontium - 89 Ci N/0 N/D N/0 N/D Strontium - 90 Ci N/D N/D N/D N/0 Cesium -134 Ci N/D N/D N/D N/0 Cesium -136 Ci N/D N/0 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 (01/20 - 12/20)

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 3.39E+00 9.20E-01 1.0BE-04 .. 1.07E-04 CARBON-14 Ci 1.0BE+00 1.04E-01 5.90E-01 6.39E-0?

TABLE 1B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT MIXED MODE GASEOUS EFFLUENT RELEASES FOR (01/20 - 12/20)

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 5.47E-03 2.73E-02 Xenon -133m Ci N/D N/D N/D N/D Xenon - 135 Ci N/D N/D N/D 4.69E-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 Other (Specify) N/D N/D N/D N/D Argon - 41 Ci N/D 9.59E-03 3.30E-03 1.25E-03 Total For Period Ci N/D 9.59E-03 8.77E-03 2.86E-02 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 1.19E-07 N/D Total For Period Ci 1.19E-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-110m 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 (01/20 - 12/20)

Page 4 of 4 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH 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 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 6.45E-01 4.42E-01 1.02E-02 1.58E-03 CARBON-14 Ci 2.54E-01 4.42E+00 0.00E+00 0.00E+00

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/20 - 12/20)

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 1.15E-04 Krypton - 87 Ci N/D N/D N/D 6.99E-05 Krypton - 88 Ci N/D N/D N/D 1.50E-04 Xenon -131m Ci N/D N/D N/D N/D Xenon - 133 Ci N/D N/D N/D 1.37E-02 Xenon -133m Ci N/D N/D N/D 2.64E-04 Xenon - 135 Ci N/D N/D N/D 2.71 E-03 Xenon -135m Ci N/D N/D N/D 1.88E-04 Xenon -137 Ci N/0 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 N/D 4.92E-02 Total For Period Ci N/D N/D N/D 6.64E-02 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 (01/20 - 12/20)

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 4.98E-05 N/D N/D Rubidium-BB 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 4.98E-05 N/D N/D Total For Period Ci N/D 4.98E-05 N/O N/D GROSS ALPHA: Ci N/D N/D N/D N/0 TRITIUM: Ci 2.48E+00 1.19E+O0 2.66E-06 7.22E-01 CARBON-14 Ci N/D N/D 2.13E-01 N/D

TABLE 1C NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT GROUND LEVEL GASEOUS EFFLUENT RELEASES FOR (01/20 - 12/20)

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 2.74E-06 N/D Krypton - 87 Ci N/D N/D N/D N/D Krypton - 88 Ci N/D N/D 2.07E-06 N/D Xenon -131m Ci N/D N/D N/D N/D Xenon -133 Ci N/D N/D 7.03E-03 1.73E-02 Xenon -133m Ci N/D N/D 2.41E-05 N/D Xenon - 135 Ci N/D N/D 2.04E-04 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 3.52E-04 N/D Total For Period Ci N/D N/D 7.61 E-03 1.73E-02 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 1.10E-06 .*N/D N/D N/D Iron - 59 Ci N/D N/D N/D N/D Cobalt- 60 Ci 3.28E-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 (01/20 - 12/20)

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/D 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-110m (T1/2 > 8 days) Ci 1.12E-06 N/D N/D N/D Rhodium-105 (T1/2 < 8 days) Ci N/D N/D N/D 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 5.50E-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 2.98E+00 7.04E+00 1.81 E+00 8.37E-01 CARBON-14 Ci 2.11E+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 (01/20 - 12/20)

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

A. Fission and Activiation Products:

1. Total Release (not including tritium; noble gas, and gross alpha). Curies 4.14E-04 2.20E-03 2.00E+01

2. Average diluted concentration during the period. µCi/ml 1.12E-12 2.70E-12

3. Percent of applicable limit (T.S.)  % 3.17E-06 4.38E-06 B. Tritium:

1. Total release activitv. Curies 2.60E+02 8.80E+02 2.00E+01

2. Average diluted concentration during the period. µCi/ml 7.06E-07 1.0BE-06

3. Percent of applicable limit (T.S.)  % 7.06E-03 1.0BE-02 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 aoolicable limit (T.S.)  % 0.00E+00 0.00E+00 D. Gross Al~ha Radioactivitv:

I

1. Total release activity. Curies 0.00E+00 0.00E+00 2.00E+01

• * ,,.1.

E. Volume of waste released: (prior to dilution). Liters 1.25E+08 9.39E+07 3.00E+00 F. Total volume of dilution water used during the period. Liters 3.68E+11 8.16E+11 3.00E+00

TABLE 2A NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT - SUMMATION OF ALL RELEASES FOR (01/20 - 12/20)

Page 2 of2 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 Qross alpha). Curies 8.63E-04 1.77E-03 2.00E+01

2. Average diluted concentration during the period. µCi/ml 1.09E-12 2.63E-12

3. Percent of applicable limit (T.S.)  % 1.86E-06 3.29E-06 B. Tritium:

1. Total release activity. Curies 2.43E+02 4.42E+02 2.00E+01

2. Average diluted concentration during the period. µCi/ml 3.07E-07 6.57E-07

3. Percent of applicable limit (T.S.)  % 3.07E-03 6.57E-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 9.76E+07 8.52E+07 3.00E+00 F. Total volume of dilution water used during the period. Liters 7.92E+11 6.73E+11 3.00E+00

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/20 - 12/20)

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 NID NID NIA NIA Iron - 59 Ci NID NID NIA NIA Cobalt- 58 Ci 1.82E-04 1.53E-03 NIA NIA Cobalt- 60 Ci 1.36E-04 5.45E-04 NIA NIA Strontium - 89 Ci NID NID NIA NIA Strontium - 90 Ci N/D NID NIA NIA Antimony-122 Ci NID NID NIA NIA Tellurium-123m Ci NID NID NIA NIA Chromium-51 Ci N/D NID NIA NIA Iodine - 131 Ci NID NID NIA NIA Iodine - 133 Ci NID N/D NIA NIA Cesium -134 Ci NID NID NIA NIA Cesium - 137 Ci 6.09E-05 9.44E-05 NIA NIA Zirconium - 95 Ci N/D NID NIA NIA Cerium -141 Ci NID NID NIA NIA Silver-110m Ci NID 2.99E-05 Tellurium-125m Ci 6.?0E-06 N/D NIA NIA Niickel - 63 (T112 > 8 days) Ci NID NID NIA NIA Antimony-125 Ci 2.90E-05 NID NIA NIA Total for Period Ci 4.14E-04 2.20E-03 NIA NIA

. .~* l

• TABLE 28 NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/20 - 12/20)

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 2.60E+02 8.8GE+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 (01/20 - 12/20)

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/O N/O N/A N/A Iron - 59 Ci N/O N/O N/A N/A Cobalt-58 Ci 2.64E-04 3.76E-04 . N/A N/A Cobalt-60 Ci 1.59E-04 1.60E-04 N/A N/A Strontium - 89 Ci N/O N/O NIA NIA Strontium - 90 Ci NID N/0 NIA NIA Niobium - 95 Ci NID N/0 NIA NIA Zirconium - 95 Ci NID NID NIA NIA Silver - 110m Ci NID N/0 NIA NIA Iodine - 131 Ci NID NID NIA NIA Iodine -133 Ci NID NID NIA NIA Cesium -134 Ci NID NID NIA NIA Cesium-137 Ci 6.77E-05 1.03E-04 NIA NIA Tellurium-123m Ci NID 1.13E-05 NIA N/A Cerium -141 Ci NID NID NIA NIA Chromium-51 Ci NID NID NIA NIA Nickel - 63 (T112 > 8 days) Ci NID NID NIA NIA Ruthenium-105 (T112 < 8 days) Ci NID NID NIA NIA Antimony-125 (T112 > 8 days) Ci 3.02E-04 8.75E-04 NIA NIA Antimony-124 (T112 > 8 days) Ci NID 4.07E-05 NIA NIA Tellurium-125m (T112 > 8 days) Ci 6.97E-05 2.06E-04 NIA NIA Total for Period Ci 8.63E-04 1.77E-03 NIA NIA

• ,. *C

TABLE 2B NORTH ANNA POWER STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT LIQUID EFFLUENT RELEASES FOR (01/20 - 12/20)

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 NIA Xenon -133m Ci NID NID NIA NIA Xenon -135 Ci NID NID NIA NIA Xenon -135m Ci N/0 NID NIA NIA Other (Specify)

Argon - 41 (T112 < 8 days) Ci N/0 NID NIA NIA Krypton - 85 (T112 > 8 days) Ci NID NID NIA NIA Total for Period Ci NID NID NIA NIA Tritium Ci 2.43E+02 4.42E+02 NIA NIA Gross Alpha Ci N/0 NID NIA NIA

TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS FOR 01-01-20 THROUGH 12-31-20 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 1.61E+01

• 2.50E+01 evaporator bottoms, etc., Ci 1.71E+02 2.50E+01

b. Dry compressible waste, contaminated m3 1.64E+02 ** 2.50E+01 c.

equipment, etc.,

Irradiated components, control rods, Ci m3 1.35E+O0 O.00E+O0

... 2.50E+01 2.50E+01 etc., Ci O.00E+O0 2.50E+01

d. Other (describe)

Used oil/Blast media/Sewage/Gravel m3 0.00E+O() **** 2.50E+01 Dessicant/Soil/Construction debris Ci O.O0E+O0 2.50E+01 Animal Carcasses

2. Estimate of major nuclide composition Estimated Total (by type of waste) (%) (Ci) Percent Error (%)

a. Co-60 3.91E+01 6.71E+01 2.50E+01 Ni-63 2.33E+01 3.99E+01 2.50E+01 -,

Co-58 1.66E+01 2.85E+01 2.50E+01 ,,_

Fe-55 6.19E+00 1.06E+01 2.50E+01 Cs-137 4.17E+00 7.15E+00 .2.50E+01 Mn-54 3.61E+00 6.20E+00 2.50E+01 Cs-134 1.49E+00 2.56E+00 2.50E+01 Be-7 1.32E+00 2.26E+00 2.50E+01 Sb-125 7.69E-01 1.32E+00 2.50E+01 Zn-65 6.SSE-01 1.18E+00 2.50E+01 C-14 6.62E-01 1.14E+00 2.50E+01 A~-110m 5.77E-01 9.89E-01 2.50E+01

b. Co-60 4.62E+01 6.22E-01 2.50E+01 Co-58 1.76E+01 2.37E-01 2.50E+01 Cr-51 1.71E+01 2.30E-01 2.50E+01 Nb-95 4.28E+00 5.75E-02 2.50E+01 Fe-55 3.59E+00 4.83E-02 2.50E+01 Zr-95 2.31E+00 3.11E-02 2.50E+01 Ni-63 2.11E+00 2.84E-02 2.50E+01 Mn-54 1.76E+00 2.37E-02 2.50E+01 Sb-125 1.51E+00 2.03E-02 2.50E+01 Zn-65 6.62E-01 8.91E-03 2.50E+01 Fe-59 6.59E-01 8.87E-03 2.50E+01 Cs-137 5.02E-01 6.75E-03 2.50E+01

c. NONE

d. NONE

TABLE 3 NORTH ANNA POWER STATION RADIOACTIVE EFFLUENT RELEASE REPORT SUMMATION OF SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS 01~1~0THROUGH1~31~ 0 Page 2 of 2

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 7 Truck Oak Ridge, TN 1 Truck Clive, UT 1 Truck Andrews, TX B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A

• (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.

(2) shipment containing mechanical filters were shipped to a licensed waste processor for processing.

• • (4) shipments containing dry compactable waste were shipped to a licensed waste processor for processing (1) shipment containing dry compactable waste was shipped to a licensed waste facility for disposal.

• • • None

• • • • None

Station Administrative Procedure

Title:

Offsite Dose Calculation Manual (North Anna)

Process / Program Owner: Manager Radiological Protection and Chemistry (North Anna)

Procedure Number Revision Number Effective Date VPAP-2103N 29 On File Administrative Change Summary for Revision 29

• Removed the number "3" prior to site boundary when collecting "3" samples close to the site boundary from Attachment 9 (Page 2 of 5) Step,2.a. NAPS has only one site boundary,

• Updated logo and Company name on cover page Revision Summary Revision 28 Revision initiated to incorporate assignment from CR1081346:

• Attachment 10, Page 4 of 5:

• Removed milk sample location due to unavailability

• Added Foot Note b, stating no milk producing animals are available in NAPS monitoring locations following the Harris Dairy closure 01/01/2018. Future milk availability will be determined from the annual land use census data.

Approvals on File

DOMINION VPAP-2103N REVISION 29 .,i PAGE20F87

. TABLE OF CONTENTS Section Page 1.0 PURPOSE 5 2.0 SCOPE 5

3.0 REFERENCES

/COMMITMENT DOCUMENTS 6 4.0 DEFINITIONS 8 5.0 RESPONSIBILITIES . 11 6.0 INSTRUCTIONS 12 6.1 Sampling and Monitoring Criteria 12 6.2 Liquid Radioactive Waste Effluents 12 6.2.1 Liquid Effluent Concentration Limitations 12 6.2.2 Liquid Monitoring Instrumentation 13 6.2.3 Liquid Effluent Dose Limit 16 6.2.4 Liquid Radwaste Treatment 18 6.2.5 Liquid Sampling 19 6.3 Gaseous Radioactive Waste Effluents 19 6.3.1 Gaseous Effluent Dose Rate Limitation 19 6.3.2 Gaseous Monitoring Instrumentation 22 6.3.3 Noble Gas Effluent Air Dose Limit 25 6.3.4 I-131, 133, H-3 & Radionuclides In Particulate Form Effluent Dose Limit 27 6.3.5 Gaseous Radwaste Treatment 29 6.4 Radioactive Liquid and Gaseous Release Permits 31 6.4.1 Liquid Waste Batch Release Permits 31 6.4.2 Continuous Release Permit 31 6.4.3 Waste Gas Decay Tanlc (WGDT) Release Permit 32 6.4.4 Reactor Containment Release Permits 32 6.4.5 Miscellaneous Gaseous Release Permit 32

• noMINION .VPAP-2103N REVISION29 PAGE3 OF 87 TABLE OF CONTENTS (continued)

Section Page 6.4.6 Ra<:fioactive Liquid and ~aseo,u~.J.:le~e~~e_<;~ntr?ls 32 6.5 Total Dose Limit to Public From Uranium Fuel Cycle Sour~es 34 6.6 Radiological Environmental Monitoring 34 6.6.1 Monitoring Program 34 6.6.2 Land Use Census 36 6.6.3 Interlaboratory Comparison Program 37 6.7 Reporting Requirements 38 6.7.1 Annual Radiological Environmental Operatiri.g Report 38 6.7.2 Annual Radioactive Effluent Release Report 39 6.7.3 Annual Meteorological Data, c *., , 42

6. 7.4 Changes to the ODCM  ; *. ,, 42

6. 7 .5 Groundwater Protection Initiative [Reference 3.1.35] 43 7.0 RECORDS *r' ,

44

DOMINION VPAP-2103N REVISION 29 J PAGE40F87 TABLE OF CONTENTS (continued)

Section Page

.:,.**., 'i!j';,,ATTACHMENTS

• *1 * ' , Radioactive Liquid:EffluentMonitoring Instrumentation . 45 2 Radioactive Liquid Effluent Monitoring Instrumentation-Surveillance Requirements ,. ,; , .

• 47

• .3 Radioactive Liquid Waste :Sampling and Analysis Program 49

• 4 Radioactive Gaseous* WasteSimipling and Analysis Program 52 5 Gaseous Effluent Dose *Factors . '

• 56

.6 . Radioactive Gaseous Efflµ.~11t;Monitoring Instrumentation. 59

7. , Radioactive Gaseous EfflueiitMonitoring Instrumentation _.

Surveillance Requirements... ., 62 8 Critical Organ Dose Factors 65 9 ..Radiological Environmental Monitoring Program 67

10.

• Environmental Sampling Locations* 72 11 Detection Capabilities for Environmental Sample Analysis 77 12 Reporting Levels for Radioactivity Concentrations in Environmental Samples 79 13 . l\1eteorological, Liquid, and G-aseons Pathway Analysis 80

. DOMINION  : VPAP-2103N REVISlON29 PAGES OF87 1.0 PURPOSE The Offsite Dose Calculation Manual (ODCM) establishes requirements for the Radioactive Effluent and Radiological Environmental Monitoring Programs. Methodology and parameters are provided to calculate offsite doses resultiilg:,frotn:radidactive. gaseous*and liquid effluents, to calculate gaseous and liquid effluent monito.tjJ;lg, a.1.arwftrip setpoints, ;md to .conduct the Environmental Monitoring Program. Requirements :are 'established for the Annual Radiological Environmental Operating Report and:the, Annual Radioactive Effluent Release Report required by Station Technic~ Specjfi,catt9ns.:.G:alcul~J.io11 of offsite doses due to radioactive liquid and gaseous effluents are perforn;i~d to ~ssur~ that:

1.1*, * .- * ~ * -. , * ~

• Concentration of radioactive liquid effluents1tb 'the*: unrestricted area \¥ill be 'limited to ten times the effluent concentration values of 10 *eFR 20,'Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases and 2E-4* µCi/ml for dissolved or entrained noble gases.

• Exposure to the maximum exposed member-of the public in the unrestricted area from radioactive liquid effluents will not result in .doses greater than-the liquid dose limits of 10 CPR 50, Appendix l .. ., *

• Dose rate at and beyond the site boundary-from radioactive gaseous effluents will be limited to:

• • Noble gases - less than or equal to a doser'ate of 500 *mrem/yr to the total body and less than or equal to a dose rate of 3000 mrem/yr to the skin

.. 1131 , 1133, and H 3, and all radionuclides in particulate form with half-lives greater than 8 days - less than or equal to a dose rate of 1500 mrem/yr to any organ

• Exposure from radioactive gaseous effluents to the maximum exposed member of the public in the unrestricted area will not result in doses greater than the gaseous dose limits of 10 CPR 50, Appendix l, and

• Exposure to a real individual will not exceed 40 CPR 190 dose limits 2.0 SCOPE This procedure applies to the Radioactive Effluent and Environmental Monitoring Programs at North Anna Power Station.

• DOMINION VPAP-2103N REVISION 29 v PAGE6 OF87

3.0 REFERENCES

/COMMITMENT DOCUl\'IENTS 3.1 References 3.1~1 10 CFR' 20; St~dard~Joi- Prcitection i_.:n ~J:.'1.':: . ; ;;: . .

Against Radiation*

• . ~' * ,'I' *.::  :

• J.l.2 10 CFR: 50, Domestic_*L,icensing of Produetion and Utilization Facilities 3.1.3 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operatjons 3 .1.4 TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites 3 .1.5 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, Rev. 1, U.S. NRC, June 1974 3.1.6 Regulatory Guide 1.109, Calculation of Annual Doses tOMan Froin Routine Releases of Reactor Effluents fol," the Purppse of Evaluating Compliance With 10 CFR 50, Appendix I, Rev. i, *u~s'.}ffiC, October 1977

• - . -, 3.1.7 Regulatory GuideL111)v1eiliods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Rev. 1, U.S. NRC; July 1977 3.1.8 North Anna Technical Specifications

' 3.1.9 North Anna Technical Requirements Manual (TRM) 3.1.10 NUREG-a0324, XOQDOQ, 'Program for the Meteorological Evaluation of Routine Effluent Releases at Nucle~ Pow.er ~tations, U.S._ ;NRC, September 1977 3.1.11 NUREG/CR-1276, Users Jylanual for the LADTAP II Program, U.S. NRC, May, 1980 3.1.12 TID-4500, VCRL~50564, Rev. 1, Con~entration Factors of Chemical Elements in Edible Aquatic Organisms, October, 1972 3.1.13 WASH 1258, VoL2, July 1973, Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion "As Low As Pra~ticable" For Radioactive Material in Light Water-Cooled Nuclear Power Reactor Effluents 3.1.14 NUREG-0597, User's Guide to GASPAR Code, U.S. NRC, June, 1980

• 3.1.15 ._Radiological Assessment Branch Technical Position on Environmental Monitoring, November, 1979, Rev. 1 3.1.16 NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Stations, October, 1978 3.1.17 NUREG-0543, February 1980, Methods for Demonstrating LWR Compliance With the EPA Uranium Fuel Cycle Standard (40 CFR Part 190) 3.1.18 NUREG-0472, Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors, Proposed Rev. 3, March 1982

DOMINION VPAP-2103N REVISION29 PAGE 7 OF87 3.1.19 Environmental Measurements Laboratory,;: DOE HASL 300 Manual 3.1.20 NRC Generic Letter 89-01, Implementation of Programmatic Controls for Radiological Effluent Technical Specifications (lIBTS) .in the Administrative Controls Section of the Technical Specifications ~il'the R'.6locatimi of Procedural Details of

• RETS to the Offsite Dose Calculation Mariual;;or to 'the Process Control Program 3.1.21

• North Anna UFSAR 3.1.22 Nuclear Reactor Environmental Radiation Monitoring Quality Control Manual, IWL-0032-361 * , . : i * .-,:

3.1.23 *.North Anna Circulating Water System Modifications,

' ' ';'i .. >

. a. DC:.85-37-1 Unit 1

b. DC-85-38-2 Unit 2 3.1.24 Pl~t Issue (Deviation) N-1994~113?,

hnp:rop'er Place~ent of Emergency TLDs 3.1.25. ET N-05-0025, Justification for removingl-SW-RM-108 from service ~hen not in

,use 3.1.26 VPAP-2802, N otifi.cations and Re.pqrts ;:- *.

3.1.27 0-PT-75.21, 1-SW-RM-108 Flow VerifiGatio1;1 I

3.1.28 SAA001092, Non-SA SOER Effectiveness Review 93-1, Recommendation 3 3.1.29 NE107-07, Industry Ground Water Protection Initiative -:Final Guidance Document 3.1.30 CA086406, Land Use Census Resulti

• 3.1.31 Quality Assurance Audit Report Number 91-03, Observation 08N 3.1.32 Quality Assurance Audit Report Number 92-03, Observation 02N

' I ' . * ,,

3.1.33 Quality Assurance Audit Report Number 92-:03, Obsei:vation 04NS (Item 2) 3.1.34 Plant Issue (Deviation) N-,1997-0926,.Annual Radiological Effluent Release Report 3.1.35 Plant Issue (Licensing Commitment) N.:2006-4026-Rl5, Groundwater Monitoring Action Plan 3.1.36 SOER 93-1, Diagnosis and Mitigation of RCS Leakage including SGTR 3.1.37 CR558854/CA293145 - Environmental Monitoring TLD locations might not be aligned with the ODCM requirement 3.l.38 CR541897/CA300793,Revise section 2.3 in attachment 13 of the ODCM 3.2 Commitment Documents None

DOMINION VPAP-2103N REVISION 29 -.i PAGE8OF87 4.0 DEFINITIONS 4.1 Channel Calibration

. ' .: - ~

A channel calibration shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values ~f the parameter that the channel monitors. The channel calibration shall encompass all devices in the channel required for channel *operability. The channel calibration may be performed by means of any series of sequential, overlapping, ortotal*channel steps.

4.2 Channel Check A qualitative assessment, by observ~tion, of channel behavior during operation. This assessment includes, where pos~ibl~. comparison of the channel indication and status with other indications or status'cierived from independent instrumentation channels measuring the same parameter; 4.3 Channel Operational Test .

A Channel Operational Test (COT) shall be the injection of a simulated or actual signal into the chamiel as close to the sensor as *practicable to check OPERABILITY of all devices in the channel required for channel OPERABILITY. The COT shalliriclude adjustments, as necessary, of the required alarm;. interlock, and trip setpoints required for channel OPERABILITY such that setpoints.~e within the necessary range and accuracy. The COT may be performed by means of any series:of sequential, overlapping, or total channel steps.

4.4 Critical Organ That organ, which has been determined to be the maximum exposed organ based on an effluent pathway analysis, thereby ensuring the dose and dose rate limitations to any organ will not be exceeded.* Dose calculations to the critical organ will be evaluated in accordance with Technical Specifications 5 .5 .4 dose* rate limits specified for any organ to check that these limits have not been exceeded.

4.5 Dose Equivalent 1-131 That concentration ofl 131 (µCi/cc) that alone w~uld produce the same thyroid dose as the quantity and isotopic mixture ofl131 ,I 132, 1133 , 1134, and 1135 actually present. Thyroid dose conversion factors for this calculation are listed in Table III of TID-14844, Calculation of Distance Factors for Power and Test Reactor Sites. Thyroid dose conversion factors from NRC Regulatory Guide 1.109, Revision 1, may be used.

-DOMINION .*

• VPAP-2103N

'-v REVISION29 PAGE9 OF87 4.6 Frequency Notations NOTE: Frequencies are allowed a maximum extension of 25 percent.

. .-< ~. ',!I_~! , ~ _::.; :

NOTATION FREQUENCY D-Daily . J\t lf?~~tonce per 24.hours*

W-Weekly At 1{;.a"St once per 7 days M-Monthly At least once per 31 days Q - Quart~rly At least once per 92 days

-'. \ :*. ' .,-; -~ *' *- .; .

SA - Semi.,ann~ally _At lfa~t Cln.q~ per 184 days,

,'. *: *1*. . . . . * *.

R - Refueling At le~st .once per 18 months .

SIU - Start-up Prior to each reactor start:-up P - Prior to release Completed pi:ior to each release N,A. - Not applicable ~ot applicable DR- During the release At least once .during each release 4.7 Gaseous Radwaste Treatment System*

A system that reduces radioactive gaseous effluents by collecting primary coolant system

• offgases from the primary system and providing delay or holdup to reduce total radioactivity prior to release to the environment. The system comprises the waste gas decay tanks, regenerative heat exchanger, waste gas charcoal filters, process vent blowers, waste gas surge tanks, and waste gas diaphragm compressor.

4.8 . .General Nomenclature

• x, =- Chi: concentration at a point at a given instant (curies per cubic meter)

• • D =. Deposition: quantity of deposited radioactive material per unit area (curies per square meter)

Q = Source strength (instantaneous; grams, curies)

= Emission rate (continuous; grams per second_, curies per second)

= Emission rate (continuous line source; grams per second per meter) 4.9 Lower Limit of Detection (LLD)

The smallest concentration of radioactive material in a sample that will yield a net count (above system background) that can be detected with 95 percent probability with only five percent probability of falsely concluding that a blank observation represents a "real" signal.

• DOMINION VPAP-2103N REVISION 29 v PAGE 10OF87 4.10 Members of the Public Individuals who, by virtue oftheir:occupational status, have no formal association with the Station. This category includes non-employees of Dominion who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with Station

• . :_ * ' * : :**:, ~;. ':,.\,: t' .-', *:. . . .

functions. This category'does riot:iri~lude non-employees such as vending machine servicemen or postal workers who; as pari'~fllibi'~ formaljob*fu~ction, occasim~ally enter an area that is

• cohtrolled by Dominion' to pi-bt~8t hidi~iduals from e~posure to radiation and r~dloactive materials.

4.11 Operable - Operability . .

.A system; subsystem,*t:rain/cofupdhe~t, *or device is' operable or has ~perability when it is

. capa~le ~f p~rforring its' specitida furictions and all necessary, attendant instrmrientation,

.. c~~trols, normal and eniergeiicy Ji6ctrical,power sources, cooling or seal water, 'l~brication or

... , other.auxiliary equipm~nt thatare';bguh-ed for the system, subsyste~, trairi, component, or device to perform its fu:nctiorn(~e ruko capable of performing their related support functions.

4.12 Purge - Purging Controlled discharge of air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating' condition; so that replacement air or gas is required to purify the confinement 4.13 Rated Thennal Power Total reactor core heat transfer rate *to reactor coolant (i.e., North Anna_:_ 2940 MWt).

4.14 Site Boundary The line beyond which Dominion does not own, lease, or otherwise control the land.

4.15 Source Check

• A qualitative assessment of channel response when a channyl sensor is exposed to a radioactive source. This applies to installed radiation monitoring systems. For MGPI monitors, a source check is the verification of proper computer response to continuous operational checks on the detector and the electronics.*

4.16 Special Report A report to NRC to comply with Subsections 6.2, 6.3, or 6.5 of this procedure. Also refer to VPAP-2802, Notifications and Reports.

DOMINION *

• VPAP'"2103N REVISION29 PAGE 11 OF 87 4.17 Thermal Power Total reactor core.heat transfer rate to the reactor coolant!,

4.18 Unrestricted Area

_=_.:*)'*'

Any area at.or beyond the site boundary, acces~,!o~o/ill,P~.is neither limited nor controlled by Dominion fo~ purposes of protection of individu,als fi:o,m exposure to radiation and radioactive materials, or any area within the site boundary .

used, for residential

'*,. _, '_:.~-,: \..; ' . ' ._.,. i '  ; -. \

quarters or .for industrial, commercial, institutional and/or recreational purposes.

4.19 Ventilation Exhaust Treatment System A system that reduces gaseous radioiodine pr radioactive material in particulate form in i * . . . . . . . . '~  : ~ ' . * '  ;  ; . ~ ; ' . *

• effluents by '

passing ventilation or vent exhaust

.* ;_,'? :;

gas.es ), --.,'

through .

ch~coal adsorbers and High Efficiency Particulate Air (HEPA) fi~ters to rerr?,<;>Ve io4ines and particulates from a gaseous exhaust stream prior to release '

to the environment . . . .

(suc:h .a system is not considered to have any effect on noble gas effluents). Engineered Safety Featun~ (ESF) atmospheric cleanup systems

. ' .t: -.. : . ~ . ' ' . '

are not Ventilation Exhaust Treatment System components.

5.0 RESPONSIBILITIES

( ' '!*

5.1 Manager ~adiological Protection and Chemistry The Manager Radiological Protection and Chemistry is responsible for:

5 .1.1 Establishing and maintaining procedures for surveying, sampling, and monitoring radioactive effluents and ~e environment.

5 .1.2 Surveying, sampling, and analyzing plant effluents and environmental monitoring, and documenting these activities.

5.1.3 Analyzing plant effluent trends and recommending actions to correct adverse trends.

• 5.1.4 Preparing Effluent and Environmental Monitoring Program records.

5.2 Martager l'luclear Operatfons The Manager Nuclear Operations is responsible for requesting samples, analyses, and authorization to release effluents.

• * .DOMINION VPAP-2103N REVISION 29 .1 PAGE 12OF87 6.0 INSTRUCTIONS NOTE: Meteorological, liqu1d, ~d gaseous pathway analyses are presented in Meteorological, Liquid, and Gaseous Pathway Analysis (Attachment 13).

6.1 Sampling and Monitoring Critetja i_. **~ *

• 6.1.1 Surveys, sampling;~a'-~alyses shall use instn'.iments calibrated for the type and range of radiation monitored and the type of discharge monitored.

6.1.2 Installed monitoring systems shall be calibrated for the type and range of radiation or parameter monitored.' , .

6.1.3 A sufficient number, of;Sl.lfV~Y ;points shall be llSed or samples ,taken to adequately assess the status of the discharge monitored.

• 6.1.4 Samples shall be representative of the volume and type of discharge monitored.

6.1.5 Surveys, sampling, analyses,'and'monitoring records shall be accurately and legibly documented; arid suffici.~htly detailed that the meaning and'in'tent of the records are clear.

6.1.6 Surveys, analyses, and m.,onit~ringTecords shall be reviewed for trends, completeness, and accuracy.

6.2 Liquid Radioactive Waste Efflµeµts 6.2.1 Liquid Effluent Concentration Limitations

a. Liquid waste concentrations discharged from ~e Station shall not exceed the

• following limits: *

1. For radionuclides (other than dissolved or entrained noble gases), liquid effluent concentrations released to .unrestricted areas shall not exceed ten times the effluent concentration values specified in 10 CPR 20, Appendix B, Table 2, Column 2.

2. For dissolved or entrained noble gases, concentrations shall not exceed 2E-4 µCi/ml.

b. If the concentration of liquid effluent exceeds the limits in Step 6.2.1.a., promptly reduce concentrations to within limits.

.DOMINION VPAP-2103N REVISION29 PAGE 13 OF87

c. Daily concentrations of radioactive materials in liquid waste released to unrestricted areas shall meet the following:

. * , ** *; *. *. *i r?.: ,:1 :.~r. * ! ,

Volume of Waste Discharged+ Volume of Dilution Water~ 1 (l)

,:* ,,,;-' * **** - * µCi/ml.

Volume ofWast~.Di~_~h~~ged?<.

L ,

ACW-l

. . . i 1 where:

µCi/mli = the concentration of nuclide i iii the liquid effluent discharge

.- ACW-1 = ten times the effluent concentration value in unrestricted areas of nuclide i, expressed-a~_µCi/ml,from 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than noble gases, and 2E-4 µCi/ml for

_dissolved or entrained 'noble-.gases 6.2.2 Liquid Monitoring Instrumentation_

• • ' * ' * ' * 'I '

a. Radioactive. Liquid Effluent Mo~tori1:1,g Instrumentation ..

Radioactive liquid effluent monitoring instrumentation channels shown on Radioactive Liquid Effluent Monitoring Instrumentation (Attachment 1) shall be operable with their alarn'l/trip setpoints set to ensure that Step 6.2.1.a. limits are not exceeded.

1. Alarm/trip setpoints of these channels shall be determined and* adjusted in accordance with Step 6.2.2.d.,' Setpoint Calculation.

2. If a radioactive liquid efflueii't monitoring instrumentation channel alarm/trip setpoint is less conservative than required by Step 6.2.2.a., perform one of the following:

• Promptly suspend release ofradioactive liquid effluents monitored by the affected channel

• Declare the channel inoperable

• Change the setpoint to an acceptable, conservative value

• DOMINION VPAP-2103N REVISION 29 J PAGE 14OF87

b. Radioactive Liquid Effluent Monitoring Instrumentation Operability Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated 'op~fahi~ by performing a Channel Check, Source Check, Channel Calibration, and C.p.annel.Operational Test at the frequencies shown in Radioactive

• , , .: '

• I - ~; ,'. t" .. f ,. : ' :, .

Liquid Effluent Monitoring Instrumentation Surveillance Requirements (Attachment 2).

1. If the number of opefable channels is less than the minimum required by the tables in Radioactive Liquid Effluent Monitoring Instrumentation (Attachment

1) perform the action shown in those tables.

2. Attempt to return: the iiistruinents to operable status within 30 days. If u'.iisu~cessful and*tii~ channel is required to be in service, then explain in the next Annual Radioa~tive'_Effluent Release Report why the inoperability was not corrected in a titnely manner, C. Applicable Monitors Liquid effluent monitors for which .tlarm/trip setpoints shall be determined are:

Release Point Instrument Number Liquid Radwaste Effluent Line 1-LW-RM-111 Service Water System Effluent Line 1-SW-RM-108 Condenser Circulatmg Water Line l-SW-RM-130 2-SW-RM-230 Steam Generator High Capacity Blow- l-SS-RM-125 down Line 2-SS-RM-225

DOMINION * *., VPAP-2103N REVISION29 PAGE 15 OF87 d.- Setpoint Calculation

.* ' ' . . <. \~-Ji;,;* .>":":: .:, ' -

_NOTE: This methodology does not preclude use of IIlC>re .conservative setpoints.

. ., _.- *. ;-::c;~-~-:.:.r-':) t'-.*:*\: _t*(:- *.

1. Maximum setpoint values shall be _calci;ilated by:

- . , *:.::_:inc:!'<~*:_-...:; :-

(2) where:

S ~ the setpoint, in µCi/ml, 0£ th,_e rndioac.tivity monitor measuring the radioactivity concentration, in the effluent line prior to dilution C = the effl~ent concentraiionfurli°for the monitor used to implement

• 10 CFR 20 for the Station,' Iii** µCi/ml . * ..

FE = maximum design pathway- effluent flow rate Fn = dilution water flow rate calc;-qlated as:

.D =FE+

(218,000 gpm-- x number . -*, .. ..

of circ. pumps in service)

2. Each. of the condenser circulating water .' '.  ;

channels (e.g., SW-130, SW-230) monitors the effluent (service water, including component cooling service

'.  : ** ' -,

• J w~ter, circulating water, and liquid radwaste) in the circulating water discharge tunnel beyond the last point-of possible radioactive material addition. No dilution is assumed for this pathway. Therefore, Equation (2) becomes:

• s = c (3)

The setpoint for Station monitors used to implement 10 CFR 20 for the site becomes the effluent concentration limit.

3. In addition, for added conservatism, setpoints shall be calculated for the liquid radwaste effluent line LW-111 and the Service Water System effluent line SW-108.

DOMINION VPAP-2103N REVISION 29 ~

PAGE 16 OF 87

4. For the liquid radwaste effluent line, Equation (2) becomes:

s (4)

.*\;,: '*.

where:

. '*.,.. : *~

KLw = The fraction of the effluent concentration limit, used to implement 10 CFR 20 .for the site; attributable to the liquid radwaste effluent

. line pa,th~ay

..., . : . ~ .! . :: ",. .

5. For the Service .W.3:ter Systein effluent line, Equation (2) becomes:

s (5) where:

Ksw = The fraction of the effluent concentration limit, used to implement 10 CFR 20 for the Station, attributable to the service water effluent line pa~way .

6. The sum KLw + Ksw shall not be greater than 1.0.

6.2.3 Liquid Effluent Dose Limit*

a. Requirement At least once per 31 days, perform the dose calculations in Step 6.2.3.c. to ensure the dose or dose commitment to the maximum exposed member of the public from radioactive materials in liquid releases (from each reactor unit) to unrestricted areas is limited to:

1. During any calendar quarter:

• Less than or equal to L5 mrem to the total body

• Less than or equal to 5 mrem to the critical organ

2. During any calendar year:

• Less than or equal to 3 mrem to the total body

• Less than or equal to 10 mrem to the critical organ

DOMINION VPAP-2103N REVISION29 PAGE 17 OF 87

b. Action If the calculated dose from release of radioactive materials in liquid effluents exceeds any of the above limits, prepare and submit to the NRC, within 30 days, a special report in accordance with VPAP-2802, Notifications and Reports, that identifies causes for exceeding limits and defines corrective actions taken to reduce releases of radioactive materials in liquid effluents to ensure that subsequent releases will be in compliance with the above limits .

• ,: - I

c. *Dose Contribution Calculations ..

Dose contribution shall be calculated for all radionuclides identified in liquid effluents released to unrestricted areas'- based on:

(6)

Where:

Subscripts '

= i, refers to individual radionuclide D = the cumulative dose commitment to the total body or critical organ from the liquid effluents for the period*t, in mrem Bi = Dose Co:rnnntment Factors (mrem/Ci) for each age group of interest.

Values for Bi are provided :in code file for North Anna Power Station liquid pathway critical organ calculations Q. = .Total released activity*for. the considered period and the ith nuclide Q-1 =

• t x c.1 x. Waste. Flow (7)

Where:

t = the period for which Ci and F are averaged for all liquid releases, in hours Ci = the average concentration of radionuclide, i, in undiluted liquid effluent during the period, t, from any liquid releases, in µCi/ml

DOMINION VPAP-2103N REVISION 29 v PAGE 18 OF87

d. Quarterly. Composite Analyses For radionuclides*not determined in each batch or weekly composite, dose

• contributi,e>n ~9: ,co/:1'.,e,1,1;tJ:~onthly or cale:r:idar quarter c~mulative summation may be approximated by.~s:;;unring, an average monthly concentration based on previous

\ I

• I_ >,, ;', '.; ~ .* ' : *

• monthly or quartt?~lY:*.?C>,WP?~ite analyses. However, for reporting purposes, calculated dose contribution shall be based on the actual composite analyses.

: ; .~

6.2.4 Liquid Radwaste Treatment Historical data pertainitig to the volumes and radioactivity of liquid effluents released in connection with speGiflc station functions, su~h as maintenance or refueling

• *, *, . . *. -~). *. .' ; .', . . . '.

outages, shall be used in projections as appropriate.

a. Requirement

1. The Liquid Radwaste _Treatment System shall be used to reduce the radioactive materials in liquid waste prior to discharge when projected dose due to liquid effluent, from each re~ctor unit, fo unrestricted* areas would exceed 0.06 mrem to total body.or0.2miem to the critical organ in a 31-day period.

2. Doses d11e to liquid rele~ses shall be projected at least once per 31 days.

b. Action If radioactive liquid waste is discharged without treatment and in excess of the above limits prepare and submit to the NRC, within 30 days, a special report in accordance with VPAP-2802~ Notifications and Reports, that includes the following:*

1. An explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable* equipment or sub-system, and*the reason for the inoperability.

2. Actions taken to restore inoperable equipment to operable *status.

3. Summary description :of actions taken to prevent recurrence .

. c. Projected Total Body Dose Calculation

1. Determine DTB, the total body dose from liquid effluents in the previous 31-day period, per Equation (6).

DOMINION *. , VPAP-2103N REVISION29 PAGE 19 OF87

2. Estimate R 1, the ratio of the*estimatedvolume of liquid effluent releases in the present 31-day period to the volume;released in the previous 31-day period.

. 3. Estimate F 1, the ratio of the esti~a'.te'd liquid effluent radioactivity

• concentration in the present3i'~ciifp'eriddi>iiquid effluent concentration

'in the previous 31-day period (µCi/nil)'.***

4. Determine PDTB, the projected total body dose in a 31-day period.

(8) d; Projected Critical Organ Dose Calcitlatioii. *.

1. Determine D0 , the critical organ dose from liquid effluents in the previous 31-day period, per Equation (6). * * * *

• 2. .Estimate R 1 as in Step 6.2.4.c'.2.'

3. Estim~te F 1 as in Step 6.2.fc.3.

4. Determine PD 0 = projected critical organ .dose in a 31-day period.

(9) 62.5. Liquid Sampling Radioactive liquid wastes.shall be sampled and analyzed according to the sampling and analysis requirements in Radioactive Liqujd Waste Sampling and Analysis Program (Attachment 3).

6.3 *... Gaseous Radioactive Waste Effluents 6.3.1 Gaseous Effluent Dose Rate Limitation

a. Requirement Dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to:

1. The dose rate limit 'for n~ble gases shall be ~* 500 mrem/year to the total body and~ 3000 mrem/year to the skin. *

• DOMINION VPAP-2103N REVISION 29 J PAGE20OF87

2. The dose.rate<limit for 113 1,1133 , for tritium, and for.all radioactive materials in particulateJoi:'mfwith half-lives greater than 8 days shall be 5. 1500 mrem/year to the critical'organ: :,

b. Action

1. If dose rates ~x~~6dStep 6:3.1.a. limits, p~omptly decrease the release rate to within the above limits.

2. Dose rates a'ue to noble gases in gaseous effluents shall be determined, continuously, to be within Step 6.3.1.a. limits.

• * ., ' *, 1 1! ~'.; > ~- ' ' .  ;

3. Dose rat~s due to l 131 ,i133 , tritium, and all radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents shall be determined to be within the above limits by obtaining representative samples and performing analyses inaccordaiice with.the sampling and analysis program specified on Radioactive dasebus Waste Sampling and Analysis Program (Attachment 4).

DOMINION * *VPAP-2103N REVISION29 PAGE21 OF87

c. Calculations of Gaseous Effluent Dose ,Rates , ,:*

1. The dose rate limit for noble -gases* shall be.determined to be within the limit by limiting the release rate to the lesser_ of:'.* , : *, .

(10) 1 (11) where:

Subscripts = vv, refers to vent rel_e_ases from the building ventilation vent pv, refers to _they~:Q.~ releases fi:om the process vent; i, refers to indi;idu~ radioimclide The total body dose factor for ventilation vents or process vent release due to gamma emissions for each identified noble gas radionuclide i, in mrem/yr per Curie/sec. Factors are listed in Gaseous Effluent Dose Factors (Attachment 5)

The skin dose factor for ventilation vents or process vent release due to beta emissions for each identified noble gas radionuclide i, in mrem/yr per Curie/sec. Factors are listed in Gaseous Effluent Dose Factors (Attachment 5)

= The air dose factor for ventilation vents or process vent release due to gamma emissions for each identified noble gas radionuclide, i, in mrad/yr per Curie/sec. Factors are listed in Gaseous Effluent Dose Factors (Attachment 5)

= The release rate for ventilation vents or process vent of noble gas radionuclide i, in gaseous effluents in Curie/sec (per site) 1.1 The unit conversion factor that converts air dose to skin dose, in mrem/mrad

• . DOMINION VPAP-2103N REVISION 29 ~

PAGE22OF87

2. The dose rate limit for I 131 , I 133 , tritium, and for all radionuclides in particulate form withhalf:-lives greater than 8 days, shall be determined to be within the limit by restricting. the release. rate to:

L[PivvQiw't,Pi'pvQipvJ ~ 1500mrem/yrto the critical organ (12) 1

• where:-

-~: .* 1:hf c;riti,cal_ orfan dose factor for ventilation vents or process

• venffor 1131 , I 33 , H 3, and all radionuclides in particulate form

• **\Vlth half-lives greater*than 8 days, for the inhalation pathway,

., in imer,n/yr per Curie/sec .. Factors are listed in Gaseous Effluent Dose Factors (Attachment 5)

= The release rate for ventilation vents or process vent of I 131 ,

• I 133;H3, and all ra:dionuclides i, in particulate form with half-lives greater than 8 days, in gaseous effluents in Curie/sec (per site)

3. All gaseous releases, not through the process vent; are considered ground level and shall be fu.clud~d-k the deterrination of Qivv.

6.3.2 Gaseous Monitoring Instrumentation

a. Requirement

1. The radioactive gaseous effluent monitoring instrumentation channels shown in Radioactive Gaseous Effluent Monitoring Instrumentation (~ttachment 6) shall be operable with alarm/trip setpoints set to ensure that Step 6.3.1.a. noble gas limits are not exceeded. Alarm/trip setpoints of these channels shall be determined and adjusted in accordance with Step 6.3.2.d.

2. Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by Channel Checks, Source Checks, Channel Calibrations, and Channel Operational Tests at the frequencies shown in Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements (Attachment 7).

DOMINION VPAP-2103N f REVISION29 PAGE23 OF87

b. Action

1. If a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint is less conservative than r~quired by Step 6.3.2.a.l, promptly:

• Suspend the release of radioactive gaseous effluents monitored by the affected channel and declare the channel inoperabl~

or

• Change the setpoint so it is acceptably conservative

• 2. If the_ number of operable cha.rinds is less than the minimum required by tables in Radioactive Gaseous Effluent Monitoring Instrumentation (Attachment 6) take the action shown in those tables.

3. Return instruments to operable status within 30 days. If unsuccessful, explain in the next Annual Radioactive.Effluent Release Report why the inoperability was not corrected in a timely manner:'*'*

c. Applicable Monitors Radioactive gaseous effluent monitors for which alann/trip setpoints shall be determined are:

Release Point Instrument Number Process Vent l-GW-RM-178-1 Condenser Air Ejector 1-SV-RM-121 2-SV-RM-221 Ventilation Vent A * . l-VG-RM-179-1 Ventilation Vent B l-VG-RM-180-1

• :._ DOMINION VPAP-2103N REVISION 29 "

PAGE24OF87

. d. Setpoint Calculations :

1. Setpoint calculations for each monitor listed in Step 6.3.2.c. shall maintain this

. relationship::::,<:.;.:.-.-

(13) where:

D. . . . ~tep 6.3) .a. d9se limit,s _that implement 10 CFR 20 for the Station, mrem!yr" '* .

• • . . : .. , *.~ , .. r J ,: . * *

= ** The noble. gas site boundary dose rate from process vent gaseous

• effluent releases, mrem/yr ...

Dcae = The noble gas site boundary dose rate from condenser air ejector

, gaseous.*  :

effluent releases, mrem/yr

/ .

Dvv = The noble gas site boundary dose rate from summation of Ventilation Vent A plris B gaseous effluent releases, mrem/yr

• 2. Setpoint values shall be determined by:

(14) where:

m = Th~,release pathway, process vent (pv), ventilation vent (vv)

. condenser air ejector (cae)

Cm = The effluent concentration limit implementing Step 6.3.1.a.

for the Station, :µCi/ml Rm = The release rate limit for pathway rn determined from methodology in Step 6.3.1.c., using Xe133 as nuclide to be released, µCi/sec 2.12E-03 = CFM per ml/sec Fm = The maximum flow rate for pathway m, CFM

. DOMINION VPAP-2103N REVISION29 PAGE25OF87 NOTE: According to NUREG-0133, the radioactive effluent radiation monitor alann/trip setpoints should be based on the radioactive>noble gases. It is not practicable to apply instantaneous alann/trip setpoints to integrating monitors sensitive to radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases.

6.3.3 Noble Gas Effluent Air Dose Limit

a. Requirement

1. The air dose in unrestricted areas due to noble gases released in gaseous effluents from each unit at or bey~-~d the site boundary shall be limited to:

• During any calendar quarter: ~- 5 mrads for gamma radiation and ~ 10 mrads for beta radiation

• During any calendar year::-~ *10 rnrads for gamma radiation and ~ 20 mrads I ' ,

• for beta radiation

2. Cumulative dose contributions for noble gases for the current calendar quarter and current calendar year shall be determined in accordance with Step 6.3.3.c.

at least once per 31 days.

b. Action If the calculated air dose from radioactive noble gases in gaseous effluents exceeds any of the above limits, prepare and submit to the NRC, within 30 days, a special report in accordance with VP~-2802, Notifications and Reports, that identifies the causes for exceeding the limits and defines corrective actions that have been taken to reduce releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the limits in Step 6.3.3.a.

• DOMINION . VPAP-2103N REVISION29 PAGE26OF87

c. Noble Gas EffltientAir Dose.Calculation Gaseous releases, not through the process vent, are considered ground level and shall be included* in-the*determination of Q.vv-

. .  : \ . -::s ' .. ! J ; : ; {!' ' ( ~ '. *~-; . : : *: .

The air dose to areas at *or beyond the site boundary due to noble gases shall be by

. dete~~d the'.f~llo~kg:

I.\:..:

• For ga.mn;:i,a, radif!tio!1: ,

1 (15)

For beta radiation: ., .

• 3.17E-08L[NivvQivv + NipvQipvJ (16) 1

• Where::.

Subscripts = vv,'refers to vent releases from the building ventilation vents,

_including air ejectors .

. pv, r~fers to.the vent releases from the process vent

. i, refers to individual radionuclide .

= the air d9se for gamma radiation, in mrad

= the air dos~* for beta radiation, hi mrad

= the air dose factors for ventilation vents or process vent release due to gamma emissions for each identified noble gas

• radionuclide i, in mrad/yr per Curie/sec. Factors are listed in Gaseous Effluent Dose Factors (Attachment 5)

= the air dose factor for ventilation vents or process vent release due to beta emissions for each identified noble gas radionuclide i, in mrad/yr per Curie/sec. Factors are listed in Gaseous Effluent Dose Factors (Attachment 5)

= the release for ventilation vents or process vent of noble gas radionuclide i, in gaseous effluents for 31 days, quarter, or year as appropriate in Curies (per site) 3.17 E-08 = the inverse of the number of seconds in a year

DOMINION

• VPAP-2103N REVISION29 PAGE27 OF87 6.3.4 1-131, 133, H-3 & Radionuclidesln Particulate Form Effluent Dose Limit

a. Requirement ,;: ,')f--; *.-*:,, ;

1. Methods shall be implementedto ensui:"e,thafthe dose to any organ of a member of the public from I 131 , I 133 , tritium, and all radionuclides in particulate form

. * ' .  :* *--.' } .; :;_:.:,"-::'; **  ;:. ; .. ~ *.  !- : ..

with half-lives greater than 8 days, in,_gaseous effluents released from the site to

-~

\. .. ; - '

umestricted areas from each reactor unit shall be:

• During any calendar quarter:~ 7Sfurem to the critical organ

• During any calendar year: ~ 15 mrem to the critical organ

2. Cumulative dose contrib~tio~s to'. a ~eri:J.~er of the public from I 131 , I 133 ,

tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents released to umestricted areas for the current calendar quarter and current calendar year shall be determined at least once per 31 days in accordance with Step 6:3.4:c:

b. Action If the calculated dose from the release ofl 131 , r133 , tritium, and radionuclides in

_particulate form, with half-l_iyes: gr,eater than 8 days, in gaseous effluents exceeds any of the above liinits;*prepare'and submit to the NRC within 30 days, a special report µi accordance ~ith VPAP-2802, Notifications and Reports, that contains the:

1. Causes for exceeding limits ..

2. Corrective actions taken to reduce releases.

3. Proposed corrective, actions to be taken to assure that subsequent releases will

- be in compliance with limits stated in Step 6.3.4.a.

DOMINION VPAP-2103N REVISION29 PAGE280F87

c. Dose Calculations Gaseous releases, ;not through the process vent, are considered ground level and shall be included in :the ~etennination of (bvv- Historical data pertaining to the

-volumes and radioactive Qoncentrations of gaseous effluents released in connection to specific Station functions, such as containment purges, shall be used in the estimates as appropriate.

1. The dose to* the maximum exposed member of the public, attributable to gaseous efflue:p.ts ;at and beyond the site boundary, that contain I 131 , I 133 ,

tritium, and particulate""form radionuclides with half-lives greater than 8 days,

• *-shall be determined by: .

• Dr.= 3.1?~-08L[RMivvQivv + RMipvQipvJ (17) 1 Where:

Subscripts _, yv, refers to vent releases from the building ventilation vents;

-pv, refers to the vent r~leases fro*m the process vent Dr - the dose to the critical organ of the maximum exposed member of the public, in mrem RMivv, RMipv =the dose factor for ventilation vents or process vent release due to r131 , r 133 , tritium, and from all particulate-form radionuclides with half-lives greater than 8 days, in mrem/yr per Curie/sec. Factors are listed in Criti_cal Organ Dose Factors (Attachment 8)

= the release for ventilation vents or *process vent of I 131 , I 133 ,

tritium, and from all particulate-form radionuclides with half-lives greater than 8 days, in Curies J.17 E-08 = the inverse*of the number of seconds in a year

DOMINION VPAP..2103N REVISION29 PAGE29OF87 6.3.5 Gaseous Radwaste Treatment Historical data pertaining to the volume's and radioactive concentrations of gaseous effluents released in connection with* specific Station functions, such as containment purges, shall be used to calculate projected doses, as appropriate.

a. Requirement

1. The Gaseous Radwaste Treatme~t Sy.stem and the Ventilation Exhaust Treatment System shall be used to reduce radioactive material in gaseous waste before its discharge, when projected:gaseous effluent air doses due to gaseous effluent releases, from each unit to areas at and beyond the site boundary, would exceed 0.2 mrad for gamma radiation and OA mrad for beta radiation, averaged over 31 days.

2. The Ventilation Exhaust Treatin.erit System shall be used to reduce radioactive materials in gaseous waste before its discharge, when the projected doses due to gaseous effluent releases, from each unit to areas at and beyond the site boundary, would exceed 0.3 rieni'to the critical organ, averaged over 31 days.

3. Doses due to gaseous releases :from the site shall be projected at least once per 31 days, based on the calculations in Step 6.3.5.c.

b. Action If gaseous waste that exceeds the limits in Step 6.3.5.a. is discharged without treatment, prepare and submit to the NRC within 30 days, a special report in accordance with VPAP-2802, N~tifi<:;ations and Reports, that includes:

• 1.. An explanation why gaseous radwaste was being discharged without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability.

2. Actions taken to restore the inoperable equipment to operable status.

3. Summary description of actions taken to prevent recurrence.

c. Projected Gamma Dose

1. Determine Dg, the 31-day gamma air dose for the previous 31-day period, per Equation (15).

2. Estimate Rg, the ratio of the estimated volume of gaseous effluent in the current 31-day period to the volume released during the previous 31-day period.

, .* DOMINION VPAP-2103N REVISION 29 -

PAGE30OF87

3. Estimate Fg, the ratio of the estimated noble gas effluent activity in the current

31-day.peri.Qd,toJ

h~_no]Jle gas effluent activity, during*the previous 31-day period (µCi/ml).

4. Determine PDg, the :projected* 31-day gamma air dose.

,,,:-:",**: :~ :)>ng = Dg(Rg x F g) (18)

d. Projected Beta Dose

• 1. D~termirie Db, ililJl-day beta air dose in the previous 31 days, .

per Equation (16).

2 .. EstiIµ~te :t{g an,<i Fg;.,a~_in_Steps 6.3.5.c.2. and 6.3.5.~.3.

• 3. Determine PDb; the projected31-day beta air dose.

(19)

e. Projected Maximum Exposed Member of the Public Dose

1. Determine Dmax, -the3 l-day maximum exposed member of the public dose in the previous 31-day period, per Equation (14), where Dr= Dmax*

2. Estimate Fi, the ratio of the estimated activity from I 131 , I 133 , radioactive materials in particulate_ form with half-lives greater than 8 days, and tritium in the current 31-day p~riocl to fue activity of 1131 , ! 133 , r~di~active materials in particulate form with half-lives greater than 8 days, and tritium in the previous 31-day period (µCi/ml). *1.

3. Determine PDmax, the projected 31-day maximum exposed member of the public dose.

(20)

DOMINION . VPAP-2103N REVISION29 PAGE31 OF87 6.4 Radioactive Liquid and Gaseous Release.Permits;* ..

• RP shall maintain procedures for Liquid and GaseousiRelease Permits to ensure effluent dose limits are not exceeded when making releases. .; . .! ;

6.4.1 Liquid Waste Batch Release Permits'.*:, /;

• Operations shall obtain ~ authorization before initiating batch releases of radioactive liquids. Examples of batch releases include:

Batch Releases NOTE: If the clarifier is in service, releases,fro;m.Janks pro~essed through the clarifier are

• * * * * ' * * ~ * , I !. .' .

considered continuous releases. f,

• A Batch Release Permit is required for a:relea~e from any tanks/sumps which contain (or potentially contain) radioactive liquid: Tanks/sumps include:

• BRTT

• LLWDT

• HLWDT

• Turbine Building Sumps wh~n secondary c~9lant activity exceeds 1.0 E-5 µCi/ml

• CDT

'.. r

. 6.4.2 Continuous Release Permit Operations shall obtain RP authorizatfori. before initiating continuous releases of radioactive liquids.

Continuous Releases A Continuous Release Permit is required for:

• Clarifier, unless being bypassed

• Steam generator blowdown when ~larifier is bypassed

• Containment mat sumps and service water reservoir when clarifier is bypassed.

Sampling requirements and control and conditions for service water reservoir blowdown, when no radioactivity is detected, shall be specified on the permit.

• .*.*DOMINION

• VPAP-2103N REVISION29 PAGE320F87 6.4.3 Waste Gas Decay Tanlc{WGDT) Release Permit

• Operations shall obtain RP authorization before initiating WGDT releases.

6.4:4 Reactor ConfuimrierilRelease Permits Operations shall obtrurt:~uithoriiation from RP before initiating containment purges or containment hogging .. Refictor Containment

'*. i _-:: _;*. . . *.. .

Release Permits.. shall be valid from start of purge/hog until:

• Routine termination; ,.

,_ ._;

• .) : '

• Terminated for pausy-Iby R.P

• Receipt of Radiatior(~\1CJ~_(?ring Systelll (RMS) Containment Gas Monitor high alarm 6.4.5 Miscellaneous Gaseous .

Release .

Permit Operations shall obtain RP authorization before initiating releases of noble gases that may not be accounted for by routine sampling, or any planned release not being routed through the ProcessVent or Ventilation Vents (e.g., steam driven auxiliary feedwater pump testing if primary to secondary leakage exists).

• '.\ . '

6.4.6 Radioactive Liquid and Gaseous Release Controls

a. Operations shall notify RP of pending releases and request RP to initiate the appropriate release permit. Operations shall provide the necessary information to complete the required release permit.

b. A representative sample shall be obtained of the source to be released.

1. Operations*shallprovide RP with liquid samples and sample information (e.g.,

time of sample) for samples obtained outside the Primary Sample Room, except Clarifier Proportional Tank and Clarifier Grab Samples.

2. Chemistry shall provide RP with liquid samples and sample information for samples obtained from inside the Primary Sample Room.

3. RP shall obt:ilil gaseous samples.

c. RP shall perform required sample analyses.

DOMINION VPAP-2103N REVISION29 PAGE33 OF87

d. RP shall calculate and record the-following* information oh a release permit:

• Maximum authorized release rate * ':': " *

• Maximum authorized release rate in, pyi:cen!~ge _of limits specified by the ODCM

• Applicable conditions or controls pertaining to _the release

e. RP shall notify the Shift Supervis~i" 'ff ii" is <:dbten:nined that arelease may not be within the effluent dose limits.

f. Upon receipt of a release permit from RP/Operations shall:

1. Check that the correct source is' authorized for release:

2. Note maximum authorized release rate.

3. Note percent of Technical Specifications limits the release represents.

• ., ' ' j . .. *. ' . '

4. Note and ensure compliance *with ~y indicated controls or conditions applicable to the release.

g. When commencing release., Operations shall provide RP with required information.

As appropriate, required information shall include:

• Date and time release was started

• Starting tank/sump level

• Beginning pressure

• Release flow rate

• Dilution water flow rate

h. Upon terminating the release, Operations shall return the permit to RP and provide informa~io11. necessary for completion of permit. As appropriate, required information shall include:

~ Date and time release was stopped

• Tank/sump ending level

• Release flow rate just prior to termination

• Ending pressure

• Volume released

• DOMINION

• VPAP-2103N REVISION29 PAGE34OF87 6.5 TotalDose Limit to.Public:Fro:rµ Uranium Fuel Cycle Sources 6.5.1 Requirement*,:. :-*; ,-,~, :.

The annual (caleI1Cll9rY,e:p::) do~e qr dose commitment to areal individual due to relf?ases of ra9i9a~tiytry.,ap.d radiation from uranium fuel cycle sources shall not

, * * , .? *~ . l _; '~.'*/,*.' ! ." ** ' *'

exceed 25 mrem fo the total body or the critical org"1} (except the thyroid, which shall not exceed 75 mrem),-:

6.5.2 Action

a. If the calculated 'dose's* fr6m release of radioactive materials in liquid or gaseous effluents exceed tWitethe limits in Steps -6.2.3.a., 6.3.3.a., or 6.3.4.a., calculate (including direct radiation contribution from the units and from outside storage truµcs) wh~th~r limits-iA Stepe(,.5.1 have been exceeded.

' ' * * .* , ~ : :  ; *:* 1 : * * * *

b. If the limits in Step 65il :have been exceeded~*prepare and submit to the NRC

. within 30 days, a spec~aheport in accordance with VPAP-2802, Notifications and Reports, that defiµes the corrective action to be taken to reduce subsequent releases and to prevent recurrence, and includes a schedule for achieving conformance with the limits. Special reports, 1:1s defined in 10 CFR 20.2203(a)(4), shall include:

1. An analysis thatestimates the radiation exposure (dose) to a real individual

• from uranium fuel cycle-sources, including all effluent pathways and direct radiation, for.the calendar.year that includes the releases covered by the report.

2. A description: of the levels of radiation and. concentrations of radioactive material involved, and the cause or the exposure levels or concentrations.

3. If the estimated dose exceeds the limits in Step 6.5.1, and if the release condition that violates 40 CFR 190 has not already been corrected, the special

.report shall incl~de a.request for a variance inaccordance with the provisions of 40 CFR 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

6.6 Radiological Environmental Monitoring 6.6.1 Monitoring Prograni.

a. Requirement

1. The Radiological Environmental Monitoring Program shall be conducted as specified in Radiological Environmental Monitoring Program (Attachment 9).

DOMINION . VPAP~2103N REVISION29 PAGE35 OF87

2. Samples shall be collected from specific'locations specified in Environmental Sampling Locations (Attachment 10). [Reference 3.1.31]

• • 3. Samples shall be analyzed iil. accordance with: .

• Radiological Environmental Motiitbifug P;ogram (Attachment 9)

- ~ ~ ' " .

requirements

• Detection capabilities required by Detettion Capabilities for Environmental Sample Analysis (Attachment 11)

• Guidance of the Radiological Ass~ssment Branch Technical Position on

., Environmental Monitoring dated Novem)Jer, 1979, Revision No. 1

b. Action

1. If the Radiological Envirom11~ntal'Mblritorlng.Program is not being conducted as required in Step 6.6.1.a.~ reporfthe situation in accordance with VPAP-2802, Notifications and Reports, by preparing and submitting to the NRC, in the Annual Radiological Environmental Operating Report required by Technical Specifications 5 .6.2, a description of the reasons for not conducting the program as required, and the plan for precluding recurrence.

2. If, when averaged over any calendar quarter, radioactivity due to station effluents exceeds the reporting levels 'of Reporting Levels for Radioactivity Concentrations* in Environmental Samples (Attachment 12) prepare and submit to the NRC within 30 days,, a special report in accordance with VPAP-2802, Notifications and Reports, that:.

• Identifies the causes for exceeding the limits, and

• Defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose to a member of the public is less than the calendar year limits of Steps 6.2.3, 6.3.3, and 6.3.4 When more than one of the radionuclides listed in Reporting Levels for Radioactivity Concentrations in Environmental Samples (Attachment 12) are detected in the sampling medium, the report shall be submitted if:

concentration (1) + concentration (2) + ... ~ 1.0 (21) reporting level{l)

• reporting level (2)

.DOMINION VPAP-2103N REVISION 29

• PAGE36OF87 3;

• Whenradi.onuclides other than those listed in Reporting Levels for

• Radioactivity<i'.oncentrations in. Environmental Samples (Attachment 12) are detected and are. the result of plant effluents, the report shall be submitted if the potential annual'doseto a member of the public is equal to or greater than the calendaryearJimits 9f Steps 6.2.3, 6.3.3, and 6.3.4. The report is not required if the measured leveLof radioactivity was not the result of plant effluents; however, in such an event, report and describe the condition in the Annual Radiological Environmental Operating Report in accordance with VPAP-2802,

• *., *: ~ *. :r * ' ' *. , . * ' *

• Notifications and R~ports.

. - * . *. ~, . . , * :_-: l .' ; i.: : '. i '

• 4: If millc or, fresh leafyyegetable samples, are unavailable from one or more of the

... _sample locations. r,equfred by Environmental Sampling Locations (Attachment 10), identify. .

locations ,** .,, - .

for obtaining replacement samples and add them to the radiologic~! enviro~ental monitoring progr~ within 30 days. The specific locatioris.frolll which 'samples ~ere unavailable may then be deleted from the monitoring

. . program. '

Ide~tifythe' cause of the unavailability of samples and identify the new locations for obtaining r'eplacement samples in the next Annual Radiqactive EffluentRelease Report in accordance with VPAP-2802, Notifications and R~po_rts. Include in the report~ revised figure and table for the ODCM to reflect th~ new locations.

6.6.2 Land Use Census

a. Requirement .

A land use census shall be conducted and shall identify, within a distance of 8 km

' .. ~ ,: . .

(5 miles), the location meach of the 16 meteorological sectors of the following:

.* Nearest milk _animal

• Nearest residence.

• Nearest garden greater than 50 m 2 (500 ft2) that produces broad leaf vegetation

1. The land use census shall be conducted during the growing season, at least once per 12 months, using methods that will provide the best results (e.g., door-to-door survey, aerial survey, local agriculture authorities). Land use census results shall be included in the Annual Radiological Environmental Operating Report in accordance with VPAP-2802, Notifications and Reports.

DOMlNION VPAP-2103N REVISION29 PAGE37OF87

- 2. In lieu of the garden census, broad leaf vegetation sampling of at least three different kinds of vegetation may be* performed at the site boundary in each of two different direction sectors with,the-highestpredicted ground deposition (D/Qs). Specifications for broad leaf. vegetation sampling in Radiological Environmental Monitoring Program, (Attachment 9) shall be followed, including analysis of control samples; :

b. Action

1. If a land use census identifies locations that yield a calculated dose or dose commitment greater than the valu~s curr~ntly being calculated in 6.3.4.a.2, identify the new lcications in *the riext Annual Radioactive Effluent Release

• Report in accordance with VPA.P~2802, Notifications and Reports.

2. If a land use census identifies 16c~tions that yield a calculated dose or dose commitment (via the same 'exposure pathway) 25 percent greater than at a location from which samples* are currently being obtained, add the new locations to the Radiological, Env~~nmental Monitoring Program within 30 days. Sampling locations, excluding the. control station location, that have the lowest calculated dose or dose.commitments (via the same exposure pathway) may be deleted from the monitoring program. Identify new locations in the next Annual Radioactive Effluent Release Report and include in the report revised figures and tables reflecting the new locations in accordance with VPAP-2802, Notifications and Reports. [Reference 3.1.33]

6.6.3 Interlaboratory Comparison Program

a. Requirement Radioactive materials (which contain nu.elides produced at the Station), supplied as part of an Interlaboratory Comparison Program, shall be analyzed.

DOMINION VPAP-2103N REVISION29 PAGE38OF87

b. Action , r ,*

1.

• Analyses shalLbe performed at least semiannually as follows:

.~:.:*.'.-... *_.,-;~*: *' ! _'iC:~::*;, :_

Program , . . . Cross-Check of

- .*. . ;_*:( '*.** *.::r.:,. 1:)£***:i*:,y*; _.*: * * - *

• Milk . ..

--~ :**.:-: i _L.'.~ '._: :; *-,::.

1131 Gamma' Sr89 and Sr90

• Water; , .. : '* 11 :,,, Gross Beta Gamma I 131 H 3 (Tritium) Sr89

. and ~r90 (blind - any combinations of above

• * ' **i-~dionuclides)

• Air Filter* *., * *. : ; '.*: *Gros~ Beta, G~a, Sr90

, 2, If analyses_ are 11otpe.:rfurmed as required by Step 6.63.b., report in the Annual RadiologicalJ~nyironme.ntal Ope.rating Report in accordance with VPAP-2802, Notifications and Reports, the corrective actions taken to prevent recurrence.

I' . . .. , , '

c. Results Results shall be reported ' -.

jn the Annual Radiological Environmental Monitoring Report in accordaµce with VPAP-2802, Notifications and Reports.

. . ' -* .J ; ~ .  ! *. . ' '  :

6.7 . Reporting Req_uirements.

6. 7.1 . Annual Radiological, Environmentaj Operating Report Routine Radiological Environmental Operating Reports covering the operation of the units during the previous calendar year shall be submitted prior to May 1 of each year.

A single submittal may.be made :fot the Station.*Radiol~gical Environmental Operating Reports shall include:

a. Summaries, interpretations, and analysis of trends of rnsults of radiological

. environmental surveillance activities for the report period, including:

• A comparison (as _appropriate) with preoperational studies, operational controls, and pre~ious environmental surveillance reports

.

• An assessment of the 9bserved impacts of the plant operation on the environment

• Results of land use census per Step 6.6.2

DOMINION VPAP-2103N REVISION29 PAGE39OF87

b. Results of analysis of radiological environmental samples .and of environmental radiation measurements taken per,Step 6;6d,:Monitoring Program. Results shall be summarized and tabulated in the format of the table in the Radiological Assessment Branch Technical Position on Environmental Monitoring.

1. If some individual results are not available for inclusion with the report, the report shall be submitted, noting and explaining reasons for missing results.

2. Missing data shall be submitted in a supplementary report as soon as possible.

c. A summary description of the ra4iological environmental monitoring program.

d. At least two legible maps covering sampling locations, keyed to a table giving distances and directions from the 'centerline of one reactor. One map shall cover stations near the site boundary; a* seco:rid shall fociude more distant stations.

e. Results of Station participation in the futerlaboratory Comparison Program, per Step 6.6.3.

f. Discussion of deviations from the Station's environmental sampling schedule per

.Radiological Enviro~~ntal,Monitori~g Program (Attachment 9).

g. Discussion of analyses in which the lower limit of detection (LLD) required by Detection Capabilities for Environmental Sample Analysis (Attachment 11) was

• - not achievable.

h. Any sample results from any gr9undwater wells described in the environmental program, whether the results were required by the environmental program or not.

6.7.2 Annual Radioactive Effluent Release Report

a. Requirement - Station Radioactive Effluent Release Reports covering operation of the units during the previous 12 'months of ~peration shall be submitted before May 1 of each year. A single submittal may be made for the Station and should coinbine those sections that are common to both units. Radioactive Effluent Release Reports shall include:

1. A summary of quantities of radioactive liquid and gaseous effluents and solid waste released. Data shall be summarized on a quarterly basis following the format of Regulatory Guide 1.21, Appendix B, for liquid and gaseous effluents.

Data shall be summarized on an annual basis following the format of Regulatory Guide 1.21, Appendix B, for solid waste. [Reference 3.1.34]

• DOMJNION VPAP-2103N REVISION29 PAGE40OF87 2 . .An* assessment of :radiation doses to the maxirr~um exposed members of the public due to th~ radioactive liquid and gaseous effluents released from the Station during the previous calendar year. This. assessment shall be in . :, ~ .

accordance.with Step 6.7.2.b.

' "' ,. ' i ) (' f, s\j";* ~.~ \, ') ; :, . . ; . . .

3. A list and desGription of unplanned releases from the site to unrestricted areas, during the,reporting period,which meet the following criteria:

• Unplanned releases that exceeded the limits in Steps 6.2.1 and 6.3.1

.* Unplanned refoases'\vhich' require a Condition Report and involve the discharge of coriterits of the wrong Waste Gas Decay Tank or the wrong liquid radwaste release fahlc

• .Unplanned.releases

'  : . . "- ,, /

from.large leaks due to unexpected valve or pipe failures that result in a quantity of release such that a 10 CFR 50.72, Immediate Notification Requ:ireIUents for Operating Nuclear Power Reactoi;-s or 10 CFR 50.73., L.icensee Eyei+t.Report System, report is required

• Unplanned releases. as determined by Radiation Protection Supervision, which may or may not require a Condition Report ., 1

4. Major changes to radi.oactive liquid, gaseous, and solid waste treatment systems during the reporting period.

5. Changes to VPAP-2103N, Offsite Dose Calculation Manual (North Anna)

(See Step 6.7.4).

6. A listing of new locations for dose calculations or environmental monitoring identified by the land use census (See Step 6.6.2).

7. A summary of radioactive leaks or spills meeting the following criteria:

• An unintended spill or leak with the potential to reach groundwater, as defined in NEI 07-07, and

• The spill or leak must be greater than 100 gallons in volume or the volume cannot be quantified but is estimated to be greater than 100 gallons; or

• Any spill or leak, regardless of volume or activity deemed by the licensee to be reportable.

DOMINION VPAP-2103N REVISION29 PAGE41 OF87

8. Any groundwater sample results fromloeations not part of the Radiological Environmental Monitoring Progratrtf: " * *,, . *

b. Dose Assessment

1. Radiation dose to individuals drie :tc/iidioa~tive liquid and gaseous effluents from the Station during the previous calindar year shall either be calculated in accordance with this procedure or in accordance with Regulatory Guide 1.109.

Population doses shall not be included in*dose assessments.

2. The dose to the maximum exposed :JTiember of the public due to radioactive liquid and gaseou~ efflµents :(rointb,e. Station shall be incorporated with the dose assessment performed above._ If the,dose to th~ maximum exposed member of the public exceeds twice the limits of 6.2.3.a. l, 6.2.3.a.2, 6.3.3.a.1, or 6.3.4.a. l, the dose assessment shall incl~de tlie contribution from direct radiation.

NOTE: NUREG-0543 states: "There is reasonable* assurance that sites with up to four operating reactors that have releases within Appendix I design objective values are also in conformance with the EPA .

Uranium Fuel Cycle Standard, 40 CFR Part 190."

3. Meteorological conditions during the previous calendar year or historical annual average atmospheric dispersion conditions shall be used to determine gaseous pathway doses.

DOMINION VPAP-2103N REVISION29 PAGE42OF87 NOTE: The Annual. Radioactive Effluent Report for the North Anna ISFSI is included as part of the North Anna Station Annual Radioactive Effluent Release Report.

c. ISFSI Dose Assessment

• Radiation dose to individuals due to radioactive liquid and gaseous effluents during the previous calendar year shall either be calculated in accordance with this pro~edure.orii.J?. ac.cordci.nce with Regulatory Guide 1.109. Population doses shall-n9t be µicl1:1cdeq in. dose assessments ..

• '.The dose to t:p.e maximum exposed member of the public due to radioactive liquid

. and gaseoµs ~fflue_nts. from the Station shall be incorporated with the dose assessment performed:p,bove. If the dose to the maximum ~xposed member of the public exceeds twice the limits of 6.2.3.a.1, 6.2.3.a.2, 6.3.3.a.l, or 6.3.4.a.l, the dose assessment shall include the contribution from direct radiation .

• Meteorological conditions during the previous calendar year or historical annual average atrnospherit'. dispe~sfoh conditions shall be used to determine gaseous pathway doses.

6.7.3 Annual Meteorological Data

.a. Meteorological data col.lected during the previous year shall be in the form of joint frequency distrib~tiqns_of win,d speed, wind direction, and atmospheric stability.

b. Meteorological data shall be retained in a file on site and shall be made available to NRC upon request.

6.7.4 Changes to the ODCM Changes to the ODCM shall be:

a. Reviewed and. approved by Site Vice* President before implementation.

_b. Documented. Records ofreviews shall be retained as Station records.

Documentation shall include:

1. Sufficient information to support changes, together with appropriate analyses or

_evaluations justifying changes.

.DOMINION

• VPAP-2103N REVISION29 PAGE43 OF87

2. A determination that a change will ncit:adversely impact the accuracy or reliability of effluent doses or setpoint calculations, *and will maintain the level of radioactive effluent control required by:

• 10 CPR 20 Subpart D

• 40 CPR 190

.

• 10 CPR.50.36a

.

• 10 CPR 50,. Appendix I C *. a Submitted to NRC in the form of 'complete; legible copy of the entire ODCM as a part of, or concurrent with the Animal 'R:adioa:d:ive Effluent Release Report for the period of the report iri which any change was :made. Each change shall be identified

• by markings in the margin of the. affected pages,* clearly indicating the area of the page that was changed, and *shall indicate the* date (e.g., month/year) the change was implemented.

d; Submitted to NRC in accordance with VPAP-2802, Notifications and Reports.

6. 7.5 Groundwater J>rotection Initiative [Refer~nce 3.1.35]

a. Notifications and Reports

1. Informal communication shall be made to state/local/NRC officials by the end of the next business day for: *

• Ariy spill or leak meeting the'requirements of Step 6.7.2.a.7.

.

• Any groundwater sample ieshlt exceeding the reporting levels of Reporting Levels for Radioactivity*Concentrations in.Environmental Samples (Attachment 12).

2. A 30-day report shall be submitted to the NRC and a copy concurrently forwarded to state and local .officials for any groundwater Sampling result, whether on site or off site, exceeding the reporting levels of Reporting Levels for, Radioactivity Concentrations in Erivironmental Samples (Attachment 12)

'and having the potential to reach groundwater that is or could be used as a source of drinking water. A 30..:day report is*only required on the initial discovery of a contamin~ted groundwater plume. .

b. Any spill or leak for which an informal notification is made in accordance with Step 6.7.5.a. shall be summarized in the Annual Radioactive Effluent Report.

• . ,DO]y1]NION VPAP-2103N REVISION29 PAGE44OF87 C. Any groundwater ~sample ~esult frorri a groundwater source that is not part of the radiological environm~ntal monitoring program shall be included in the

• Annual Rallioactive Effluent Report.

d: Any groundw,3:.t~r .~~P,le result from any groundwater well described in the

. radlological environmental monitorinRprogram shall be included in the

, s* ~ * . . ., * * ~ -*

Annu,al Radiological Environmental Operatin& Report.

7.0 RECORDS 7.1 The following record(s) completed as a result of this procedure are required to be transmitted to Nuclear DocupientManag~IIiiht(DNM). The records have been identifi~d and 'retention requirements established for the Nuclear Records Retention Schedule (NRRS) per RM-AA-100, Record Creation, Transmittal and Retrieval.

Quality Assurance Records

• Records of changes to the ODCM in accordance with Step 6.7.4

• Records of meteorological dat~ hi. accordance with Step 6. 7.3

• Records of sampling and *analyses ( *

• Records of radioactive materials and other effluents released to the environment

• Records of preventive maintenance, surveillances, and calibrations 7.2 The following item(s) completed as a result of this procedure are NOT records and are NOT required to be transmitted to Nuclear Do~ument Management (DNM}.

None

DOMINION VPAP-2103N REVISION29 PAGE450F87 ATTACHMENT 1 (Page 1 of ~) ,

Radioactive Liquid Effluent M;o.ni~oling µisti;umentation Instrument 1VffiiimumUperable Acti*on

,' Channels

1. Liquid Radwaste Effluent (a) l-LW-RM-111, Liquid Radwaste Effluent Monitor 1 1

, (b) 1-LW-FT-104, Liquid Radwaste EffluentTotalFlo,w Measuring, .

'1 2 Device (c) l-LW-TK-20, Liquid Waste Effluent Sample V,esSel;,, : '. 1 1 (d) 1-LW-1130, Liquid Waste Effluent Proportional Samp1e\ia1ve 1 1 (e) 1-SW-RM-108, Service Water Effluent Monitor (Note, 1) (Note 2) 1 1 (f) 1-SW-RM-130, Unit 1 Circulating Water System Effluent Line 1 3 Monitor (g) 2-SW-RM-230, Unit 2 Circulating Water System Effluent Line 1 3 Monitor ,*

2. Steam Generator High Capacity Blowdown ,

(a) Steam Generator High Capacity Blowdown Radiation Monitor Unit 1 l-SS-RM-125 1 1 Unit 2 2-SS-RM-225 1 1 (b) Steam Generator High Capacity Blowdown Flash Tank Outlet Flo\\

Rate Unit 1 1-BD-FT-105 1 2 Unit 2 2-BD-FT-205 1 2 (c) Steam Generator High Capacity Blowdown Proportional Samplinf System Collection Tank Unit 1 1-BD-TK-4 1 1 Unit 2 2-BD-TK-4 1 1

DOMINION VPAP-'2103N REVISION29 PAGE46 OF87

: ATTACHMENT 1

':'. * (Page-2*of 2)

Radioactive Liquid:Effluent Monitoring.Instrumentation ACTION 1: If the number of operable channels is less than required, effluent releases via this

. pathway inay co~tµI~/if,f~t ieast once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are c~llected and

• analyzed for gross tadic>activity(beta and gamma) at an LLD of at least lxl0-7 µCi/g or an isotopic radioactivi~y at an LLD of at least 5x10-7 µCi/g.

ACTION 2: If the number: of operable channels-is less than required, effluent releases via this pathway may continue if the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases*. Design capatity' performance curves generated in situ may be used to estimate flow.

ACTION 3: If the number of operable chabnels is less than ~equired, make repairs as soon as possible. Effluent releases via this pathway may continue provided that, at least once

,  ;* ., r ** .' "-:' l 1 *! , . ' _ ' , , ~

per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples from the discharge canal are collected and analyzed for principal gamma emitters as defined in Radioactive Liquid Waste Sampling and Analysis Program (.Attachment 3): :

NOTE 1: The capability for obtaining grab samples at least every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> must exist. Grab samples shall commence if there is indication of radioactivity in the Service Water System or an indication from other radiation monitors in the Service Water System of an increase in radioactivity.

NOTE 2: To utilize l-SW-RM-108 as the effluent radiation monitor for the associated loop, 0-PT-75.21, (1-SW-RM-108 Flow Verification) must be performed prior to placing the loop in service. Effluent monitoring is not required when discharge flowpath is n6t in service.

DOMINION VPAP-2103N REVISION29 PAGE47 OF87 ATTAC1'ENT2

• (Page b:>f 2)

Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Channel Description . Channel Source Channel Channel

J t~hCck -- Check Calibration Operational Test

1. Liquid Radwaste Effluent (a) 1-LW-RM-111, Liquid Radwaste Effluent Monitor: .. D R - Q (NOTE 1)

(b) l-LW-F.T-104, _Liquid Radwaste Efflu,ent Total_ F,Iow D (NOTE )

Measunng Device

• 3 NIA R Q (c) l-LW-TK-20, Liquid Waste Effluent Sample Vessel _ D (NO'fp 4) NIA NIA - NIA (d) 1-LW-1130, Liquid Waste Effluent Prnportional Sample _D (NOTE ) NIA NIA NIA V~e . - __ . _ . , . . 4 (e) l-SW-RM-108, SW Effluent Monitor (NOTE 9) D M R Q (NOTE2)

(f) SW-RM-130, Unit 1 Circulating Water - System D M R Q (NOTE2) pffluent Line Monitor (g) 2-SW-RM-230, Unit 2 Circulating Water System M R Q (NOTE2)

Effluent Line Monitor

2. Steam Generator (SG) High Capacity Blowdown ,

(a) SG High Capacity Blowdown Radiation Monitor Unit 1 1-SS-RM-125 Q (NOTE6)

D (NOTE 7) D (NOTE 7) R Unit 2 2-SS-RM-225 R(NOTE5)

(b) SG High Capacity Blowdown Flash Tank Outlet Flow Rate Unit 1 l-BD-FI'-105 D (NOTES) NIA R NIA Unit 2 2-BD-FI'-205 (c) SG High Capacity Blowdown Proportional Samplin,!!

System Collection Tank Unit 1 l-BD-TK-4 D(NOTE4) NIA NIA NIA Unit 2 2-BD-TK-4

DOMINION VPAPc.2103N REVISION29 PAGE48OF87

'ATTACHMENT 2

', ,. (Page 2 of 2)

Radioactive Liquid EfflueneMonitoring* Instriiinentation Surveillance Requirements NOTE 1: The Channel Operational Test shall demonstrate:

a. Automatic isolation o{ thi~ .pathway and Control Room alarm annunciation occur if the instrument indicates measured.levels above alarm/trip setpoint.

b. Alarm arinuncia~o~;occurs if the instrument controls are not set in "operate" mode.

NOTE 2: - The Channel Operational Test sh.all demonstrate that Control Room alarm annunciation

• ,1, * * * * * * * * * * * .'

occurs if ~y ~f tlie f9ilowing conditions exists:

a. Instrument indicates measured levels above the alarm/trip setpoint.

b. Instrument controls not Set in*"operate" mode.

NOTE 3:- Channel Check shall consist of checking indication of flow during periods of release.

Channel Check shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases* are made.

• NOTE 4: Channel Check shall consist of checking that proportional flow exceeds 0.5 mls/gallon.

NOTE 5: Channel Operational Test shall d~monstrate that system i~olation occurs on a radiation monitor High-High Alarm.

NOTE 6: Channel Operational Test shall de,IIlonstrate:

a._ Trip signals are generated at-tb:erequired setpoints. Isolation is not required.

b. Local radiation monitor indicatj.on occurs if instrument controls are not set in Oper~te" mode or if the instrument indicates measured levels are above the alarm/trip setpoint.

NOTE 7: The radiation monitor automatically performs periodic source checks. The So~ce Check and Channel Check are satisfied as long as the green light is lit.

NOTE 8: This is confirmed by indicated effluent flow less than or equal to 190 gpm.

NOTE 9: To utilize 1-SW.,.RM-108 as the effluent radiation monitor for the associated loop, 0-PT-75.21, (l-SW-RM-108 Flow Verification) must be performed prior to placing the loop in service. Effluent monitoring is not required when discharge flowpath is not in service.

DOMINION - VPAP<?J03N REVISION29 PAGE490F87 ATTACHMEN:T 3 (Page 1 of 3)

Radioactive Liquid Waste Sampling; ?D,.(I Allalysis-~rogram ,

. Lower nmtot Liquid Release Sampling Minimum Analysis* . Type of Activity

• Detection (LLD)

Type Frequency . Frequep,cy1.... : . ,: , , . Analysis ..

(µCi/ml), (Note 1)

p. p, **l I ,._,;,.

. Prip.ciple. Gamma 5 X 10-7

. *Emitters (Note 3)

.. (Each Batch)' * . , . *. rBi *1*,

1 X 10-6

. (Each Batch) p 1J1sso1vee1 and 1 X 10-=>

Batch Releases .M., .. ; .. . Entrained Gases .

(OneBatch/M) (Note 8)

(Gamma Emitters)

(Notes 2 and 7) p M Composite iI3 1 X 10-S

,. . 'J  :

(Each Batch) (N()te 4) ,. Gross Alpha 1 X 10-7 p Q Composite Sr89 and sr9° Sx 10-8

,: ~  ; ..

(Each Batch) (Note 4) Fess 1 X 10-6 Principal Gamma 5 X 10-7 Emitters (Note 6)

Continuous W Composite*.- 1131 1 X 10-6

.. (Note 6) . (Not~ 6) 1J1ssolvee1 anel 1 X 10-.5 Continuous

• Entrained Gases Releases M Grab Sample (Note 8)

(Gamma Emitters)

(Note 5) Continuous M Composite H3 1 X 10-S (Note 6) (Note 6) . Gross Alpha 1 X 10-7 Continuous Q Composite Sr89 and sr9° 5 X 10-8

.. (Note 6) * (Note 6) Fess 1 X 10-6

DOMINION VPAP-2103N REVISION29 PAGE50OF87

. :.A'rTACl)MENT 3

.::: '. (Page 2 of 3)

Radioactiv;e iiqlJ.id ;waste.Sampling and Analysis Program

.'., NOTE .1: Fo!: a particular me.as:q~em~11~ 1system. (which may include radiochemical *separation): *

(9-1)

Where:

-LLD *\_ the "a pridri .(before the fact) Lower Limit of Detection as defined above (as micrbctiries'pet unit mass or volume) (See Subsection 4.8)

= the standard~~ti~ti~n of the background counting rate or of the counting a

. rate of blank sample as appropriate (as counts p~r minute, cpm)

E . = ~~ counting effj.ciency (as .counts per disintegrati~n)

.V = the sample size (in units of mass or volume) 2.22E+06 = the number ..,:

of.

disintegrations per minute (dpm) per microcurie Y = the fractional radiochemical-yield (when applicable)

• ,: ' I

• 1v = the radioactive. decay _constant for the particular radionuclide Lit = the elapsed time between the midpoint of sample collection and time of

. counting.

Typical values of E, V, Y arid ~t should b~ used in the calculation'.

The LLD .

is an "a priori'.' (l:>efore the fact) limit representing the capability 9f a measurement system and not a "posteriori" (after the fact) limit for a particular measure:i;nent.

NOTE 2: A batch release is the discharge of liquid wastes of a discrete volume. Before sampling for analyses, each batch shall be isolated, and then thoroughly mixed as the situation permits, to assure representative sampling.

DOMJNION VPAP-2103N REVISION29 PAGE51 OF87 ATTACHMENT 3

• (Page 3 of 3)

Radioactive Liquid Waste Samplfugi~nd:Analysis Program NOTE 3: The principal ganu:na emitters for which the~tLD specification applies exclusively' are the 137 141 following radionuclides: Mn54 , Fe59 , Co58 , Co60, Zn65 , Mo 99 , Cs 134, Cs , Ce , and Ce 144 . This list does not mean that only these nµcijdes are to be detected and reported.

Other peaks that are me:asurable and identifiabl~'. ~i levels exceeding the LLD, together with the above nuclides, shall also be identified and reported.

NOTE 4: A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged ,and fqr which, the method of sampling employed results in .8: specimen that is representative of the:ligll;iq~ releas~~-

NOTE 5: A continuous release is the discharge of liquid wastes of a non-discrete volume, e.g., from a volum~ of a system that has an input flow durit;tg the continuous release.

NOTE 6: To be representative of the quantities and concentrations of radioactive materials in liquid effluents; samples shall be collected continuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all .s~ples .taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent releases.

NOTE 7: . Whenever the secondary coolant activity ~xceeds 10~s µCi/ml, the turbine building sump pumps shall be placed in manual operation and samples shall be taken and analyzed prior to release. Secondary coolant activity samples shall be collected and analyzed on a weekly basis. These samples are analyzed for gross activity or gamma isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

NOTE 8: The gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135,.Xe-135m and Xe-138. This list does not mean that only these nuclides are to be detected and reported. Other peaks that are

.nieasurabie and identifiable, at levels exceiding the LLD, together with the above nuclides shall also be identified and reported. .

DOMJNION VPAP-2103N REVISION29 PAGE520F87

• .ATTACHMENT4

,;. (Page 1 of 4)

Radfoactive'Gaseous,Waste Sampling and Analysis Program Lower Lnmt or Gaseous Release Sampling Minimum Analysis Type of Activity Detection (LLD)

Type Frequency' * ' Frequency Analysis

... (µCi/ml), (Note 1)

'  :.. ' PnnClpal Uamma Prior to Release ' 1 X 10-4 A. Waste Gas Prior to Release Emitters (Note 2)

(Each Tank Storage Tank (Each Tank) H3 Grab Sample) 1 X 10-6 PnnClple Uamma 1 X 10-4 R Containment Prior to Release* .: Prior to Release Emitters (Note 2)

(Each.PURGE Purge (Each PURGE) H3 1 X 10-6 Grab Sample)

C. Ventilation Monthly . Principle Gamma

• • • , Monthly 1 X 10-4 (1) Process Vent (Grab Sample) Emitters (Note 2)

(2) VentVentA H3 1 X 10-6 (Notes 3 and 5) (Note 3)

(3) Vent Vent B Continuous Weekly 1131 1 X 10- 12 (Note 4 and 5) (Charcoal Sample) Iuj 1 X 10-lU Contmuous Weekly Pnnc1pa1 uamma 1 X 10-ll All Release (Note 4 and 5) Particulate Sample Emitter (Note 2)

Monthly Continuous * .*. Composite 1 X 10-ll Types as listed Gross Alpha (Note 4 and 5)

Particulate Sample (J_uarterly Continuous in A, B, and C Composite Sr89 and Sr90 1 X 10-ll (Note 4 and 5)

Particulate Contmuous Noble Uases Uross Noble Gas Monitor 1 X 10-6 (Note 4 and 5) Beta or Gamma Condenser Air Pnnc1p1e uamma 1 X 10-4 Weekly Weekly Ejector/Steam Emitters (Note 7)

Generator Grab Sample ' 3 Blowdown Vent/ H 1 X 10-6 (Note-6)

• BRTVent Containment Pnnc1p1e uamma Prior to Release Prior to each 1 X 10-4 Vacuum Steam Emitters (Note 2)

(Grab Sample) H3 1 X 10-6 Ejector (Hogger) Release (Note 8)

DOMINION VPAP..2103N REVISION29 PAGE53 OF87 ATTACHMENT 4

,(Page 2-;of 4)

Radioactive Gaseous Waste Sampliitg*and,Analysis Program NOTE 1: For a particular measurement system (which may include radiochemical separation):

LLD (11-1)

Where:

LLD = *the "a priori'.' (before t4e fict) 'tower Limit of D~tectiori as defined above

. . ' . .* ' : :, .* : . ,'* 1/ . !: . ' * . ' '* * * :'*

{as microcuries per unit mass or_ y9lume) (See Subsection 4.9)

. Sb = the standard deviation of the packgtoUIId counting rate or of the counting

.rate of a blank sample *as appropri_~te (as counts per Illlliute*, cpm)

E = the counting efficiency (as counts per ~sintegration)

V * = the sample size (in units of mass or volume) 2.22E+06 = the number of disintegrations per minute* (dpm) per microcurie Y = theJractional radiocheinical yield (when applicable)*

"A, = the radioactive decay constant for the particular radionuclide

.M = the elapsed time between the midpoint of sample collection and time of counting Typical values of E, V, Y and ~t should be used in the calculation.

The LLD isan "a priori" (before the fact) limit representing the capability of a measurement system and not as "posteriori" (after the fact) limit for a particular measurement.

NOTE 2: The principal gamma emitters for which the LLD. specification applies exclusively are the following radionuclides: Kr87 , Kr88 , Xe133 , Xe 133m, Xe135 , Xe135m, andXe138 for gaseous emissions and Mn54, Fe59 , Co58 , Co 60 , Zn65 , Mo99 , Cs 134, Cs 137, Ce 141 and Ce 144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks that are measurable and identifiable, at levels exceeding the LLD, together with the above nuclides, shall also be identified and reported.

• • DOMINION VPAP-2103N REVISION 29 ,

PAGE540F87

.,. ATTACHMENT4 (t *. {Page 3 of 4)

RadioactiveGaseous*W?ste Sampling and Analysis Program NOTE 3: .* .Sampling:and analysiifshalbilsobe*performed following shutdown, start-up, and whenever a thermal power chaI_1ge. exceeding: 15 percent of the rated thermal power occurs within any one-hour period, if:

a. Analysis shows that the dose equivalent I 131 concentration in the primary coolant is greater than 1.0 µCi/gm; and

b. The noble gas activity monitor shows that effluent activity has increased by more than a factor of 3.

NOTE 4: The ratio of the sample flow rate to the sampled stream flow rate shall be known for the period covered by each dose or dose rate calculation made in accordance with Steps 6.3.1, 6.3.3, and 6.3.4.

NOTE 5: Samples shall be changed at least once per seven days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least seven days following each shutdown, start-up or thermal power change exceeding 15 percent of rated thermal power in one hour and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement applies if:

a. Analysis shows that the dose equivalent 1131 concentration in the primary coolant is greater than 1.0 µCi/gm and;

b. Noble gas monitor shows that effluent activity has increased more than a factor of 3.

NOTE 6: Whenever the secondary coolant activity exceeds 10-5 µCi/ml, Condenser Air Ejector and Steam Generator Blowdown Vent samples shall be obtained and analyzed weekly.

Secondary coolant activity samples shall be collected and analyzed on a weekly basis.

These samples are analyzed for gross activity or gamma isotopic activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

NOTE 7: The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: K.r87 , K.r88 , Xe133 , Xe133m, Xe135 , Xe135m, and Xe138 for gaseous emissions. This list does not mean that only these nuclides are to be detected and reported.

Other peaks that are measurable and identifiable, at levels exceeding the LLD together with the above nuclides, shall also be identified and reported.

DOMINION '. . VPAP-2103N REVISION29 PAGE55 OF87 ATTACHMENT 4

• . (Page:4:of 4)

. Radioactive Gaseous Waste.-Sampliiigiand*AnalysisProgram NOTE 8:. If the secondary coolant activity level in any Steani:Generator supplying steam fo 'tlie, 0

• Hogger exceeds l.0E-5 µCi/ml, Steam GeneratoF.sarriples shall be obtained and analyzed prior to release.

DOMINION VPAP-2103N REVISION29 PAGE56OF87

• ATTACHMENT 5

• (Page 1 of 3)

• Gaseous *Effluent Dose Factors

• ' ,. {Gainma and Beta Dose Factors) x/Q = 9.3E-'06'sec/:iri3 at 1416 meters SE Direction

• Dose:Factors for Ventilation Vent

~vv *~*. Livv lvlivv Nivv Noble Gas Total Body. Skin GammaAir Beta Air Radionuclide mrem/yr ,. , mrem/yr mrad/yr inrad/yr

• curie/sec Curie/sec Curie/sec Curie/sec Kr.:.ssm 1:09E+04 * *t36E+04

... 1.14E+04 : 1.83E+04 Kr-85. 1.50E+02 l.25E+04 1.60E+02 1.81E+04

.Kr.:.s7 5.51E+04 . 9.05E+04 5.74E+04 9.58E+04

• l{r::.gg l.37E+05 - 2.20E+04 . 1.41E+05 2.72E+04 .

Kr,.89 l.54E+05 9.39E+04 ' 1.61E+05 9.86E+04 Xe-131m 8.51E+02 4.43E+03.

1.45E+03 1.03E+04 Xe-133m 2.33E+03 *- 9.24E+03 3.04E+03 1.38E+04 Xe-133 2.73E+03 2.85E+03 3.28E+03 9.77E+03 Xe-135m 2.90E+04 6.61E+03 3.12E+04 6.87E+03 Xe-135 1.68E+04 . 1.73E+04 .. 1.79E+04 2.29E+04 Xe-137 1.32E+04 1.13E+05 1.40E+04 l.18E+05 Xe-138 8.21E+04 3.84E+04 8.57E+04 4.42E+04 Ar-41 8.22E+04 2.50E+04 8.65E+04 3.05E+04

' DOMINION * *VPAP-'.2l03N REVISION29 PAGE57 OF87 ATTACHMENTS

• . (Page 2.of 3)

. Gaseous Effluent Dose.-F:attors (Gamma and Beta Dos.e:Ea.ctors) x!Q = 1.2E-:-06 sec/m3 at 1513..nietets S Direction

• Dose Factors for Process Vent Kipv . _Lipv r_;,. .*.*.*,Mipv

• Nipv Noble Gas Total Body Skin I Gamma Air. Beta Air Radionuclide mrem/~ *mrem/yr i .( . rnrad/yr mrad/yr Curie/sec Curie/sec *. ** 'Curie/sec* Curie/sec

'I{r-85m 1.40E+03 f.75E+03 *. -** ..

1.48E+03 2.36E+03 Kr-85 1.93E+0l 1.61E+03 2.06E+Ol 2.34E+03

• Kr-87 7.10E+03 1.17E+04

_,_ - 7.40E+03 1.24E+04 Kr-88 1.76E+04 2.84E+03 1.82E+04

• 3.52E+03 .

Kr-89 1.99E+04 . l.21E+04

• 2.088+04 1.27E+04 Xe-131m l.10E+02 5.71E+02 1.87E+02 1.33E+03 Xe-133m 3.01E+02

• L19E+03 3.92E+02 1.78E+03 Xe-133 3.53E+02

• 3.67E+02 . 4.24E+02 l.26E+03 Xe-135m 3.74E+03 8.53E+02 4.03E+03 8.87E+02 Xe-135 2.17E+03 2.23E+03 2.30E+03 . .. 2.95E+03 Xe-137 1.70E+03 1.46E+04 1.81E+03 1.52E+04 Xe~l38 1.06E+04 4.96E+03 l.11E+04 5.70E+03 Ar-41 1.06E+04 3.23E+03 . .' .

1.12E+04 3.94E+03

DOMINION VPAP-2103N REVISION29 PAGE58 OF87

,. **. ATTACHMENT 5

• (Page 3 of 3)

G-ase'ous*Effluent Dose Factors *

(Inhalation Pathway Dose Factors)

Ventilation Vent xJQ~-9:3E-06 sec/m3 at 1416 meters SE Direction Process V~nt x/Q b l.2E..,Q6 sec/m3 at 1513 meters S Direction Pivv l'ipv Radionuclide mrem/yr mrem/yr*

Curie/sec Curie/sec H-3 / 1.05E+04 1.35E+03 Cr-51 7.95E+02 1.02E+02 Mn-54 ND ND Fe-59 ND ND Co-58 ND ND Co-60 ND ND Zn-65 ND ND Rb-86 ND ND Sr-90 ND ND Y-91 ND ND I

Zr-95 ND ND Nb-95 ND ND Ru-103 ND ND ..

Ru-106 ND ND Ag-ll0m ND ND Te-127m 5.64E+04 7.28E+03:

• Te-129m 5.88E+04 7.59E+03 Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND Ba~140 ND ND Ce-141 ND ND Ce-144 ND ND I-131 1.51E+08 1.95E+07 I-133 3.58E+07 4.62E+06 ND - No data for dose factor according to Regulatory Guide 1.109, Revision 1

DOMINION VPAP-:2103N REVISION29 PAGE59OF87 ATTACHMENT 6 (Page 1- of 3)

Radioactive Gaseous EffluentMonitoririg Instrumentation INSTRUMENT ... - . ' ,.M,INJMUM OPERABLE ACTION

,_ C::HANNELS

1. PROCESSVENT SYSTEM ..

(a) Noble Gas Activity Monitor *.

1

• 1-GW-RM-178-1 . ...

2,4 (NOTE 3) ..

(b) Iodine Sampler ...

l-GW-RM-178-1 1

... . . 2,5 Pp)cess Vent Continuous HP Sampler (NOTE3).

(c) Particulate Sampler  ;

l-GW-RM-178-1 1 ..

2,5 Process Vent Continuous HP Sampler (NOTE3)

(d) Total Flow Monitor

• 1-GW-Ff-108 1 1 (e) Sampler Flow Rate Measuring Device -

MGPI Flow Rate Measuring Device 1 1

HP Sampler Rotameter (NOTE3)

2. CONDENSER AIR EJECTOR SYSTEM (a) Gross Activity .Monitor Unit 1 l~SV-RM-121 1 3 Unit2 2-SV-RM-221 (b)- ** Flow Rate Measuring Device

,

• Unit 1 1-SV-FI-lO0A 1-SV-FI-lOlA 1 (NOTE 1) 1 1-SV-FI-lO0B 1-SV-FI-lOlB tJnit2 2-SV-FI-200A .. . .

2-SV-FI-201A 1 (NOTE 2) 1 2-SV-FI-200B ..

2-SV-FI-201B

DOMINION VPAP-2103N REVISION29 PAGE60OF87

, ,*ATTACHMENT6

. . . , (Page 2 of 3)

Radioactive :Gaseous Effluent Monitoring Instrumentation INSTRUMENT, ,.,_ * .; . .i: MINIMUM OPERABLE ACTION

'., *::.;.* CHANNELS

.3. VENTILATION VENT A-_*:* .,

(a) Noble Gas Activity Monitor";"'

1 1-VG-RM-179-1 * '.'. ,:_:.:,. ., 2

'. - ,,,,., ,*,, i:*

(NOTE3)

(b) Iodine Sampler .. , ' : i *..*

l-VG-RM-179-1 1

2 Vent Vent A Continuous HP Sampler; (NOTE3)

' *,  : .,- .. i (c) Particulate Sampler. .

l-VG-RM-179-1 - ' 1 ' 2; Vent Vent A Continuous HP Sampler * (NOTE 3)

(d) Total Flow Monitor l-HV-Ff-1212A 1 1 (e) _Sampler Flow Rate Measuring. ~t:vice MGPI Flow Rate Measuring Device 1 HP Sampler Rotametei:- * * - 1 (NOTE3)

4. VENTILATION VENT B (a) Noble Gas Activity Monitor 1

l-VG-RM-180-1 2 (NOTE 3)

(b) Iodine Sampler l-VG-RM-180-1 1 2

Vent Vent B Continuous HP Sampler (NOTE 3)

(c) Particulate Sampler 1-VG-RM-180-1 1 2

Vent Vent B Continuous HP Sampler (NOTE3)

(d) Total Flow Monitor

. 1-HV-Ff-1212B 1 ' 1 (e) Sampler Flow Rate Measuring Device MGPI Flow Rate Measuring Device 1 1

HP Sampler Rotameter (NOTE 3)

• DOMINION VPAP-2103N REVISION29 PAGE61 OF87 ATTACHMENT 6

, (Page J of 3)

Radioactive Gaseous Effluent Monitoring Instrumentation ACTION 1: If the number of operable channels is less than required, effluent releases, via this path, may continue if the flow rate is estimated at least once per four hours.

ACTION 2: If the number of operable channels is less than required, effluent releases, via this path, may continue if grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for gross activity or gamma isotopic activity within2~ hours ..

ACTION 3: If the number of operable channels is less than required, effluent releases via this path may continue if grab samples are taken at least once per twelve (12) hours and these samples are analyzed for gross activity or gamma isotopic activity within eight (8) hours. This requirement is for effluent accountability and is distinct and separate from any requirement for primary-to-secondary leak rate determination. The need to determine the.primary-to-secondary leak rate, e.g., the performance of l/2-PT-46.3B, shall be.determined in accordance with the requirements of TRM TR 3.4.5. However, the same sample may be used to fulfiil both the requirements of this action and primary-to-secondary leak rate determination.

ACTION 4: If the number of operable channels is less than required, the contents of the Waste Gas Decay Tanks may be released to the environment.provided that prior to initiation of the release:

a. At least two independent samples of the tank's contents are analyzed, and:

b. At least two technically qualified members of the Station staff independently check the release rate calculations and discharge valve lineup.

ACTION 5: If the number of operable channels is less th.ail required, effluent releases from the Waste Gas Decay Tank may continue provided samples are continuously collected with auxiliary sampling equipment as required in Radioactive Gaseous Waste Sampling and Analysis Program (Attachment 4).

NOTE 1: A channel shall consist of:

a. The flow instrument installed in the ejector through which the discharge is routed; either Train A (1-SV-FI-lO0A, 101A), or Train B (1-SV-FI-lO0B, 101B) or both.

b. Flow instruments 101A and 101B provide low range measurement. Flow instruments 100A and 100B provide high range measurement.

NOTE 2: A channel shall consist of:

a. The flow instrument installed in the ejector through which the discharge is routed; either Train A (2-SV-FI-200A, 201A), or Train B (2-SV-FI-200B, 201B) or both.

b. Flow instruments 201A and 201B provide low range measurement. Flow instruments 200A and 200B provide high range measurement.

NOTE 3: A channel shall consist of a MGPI monitor; and a MGPI or HP particulate and iodine sampler, and its associated sampler flow rate measuring device or rotameter.

• DOMINION VPAP-2103N REVISION29 PAGE620F87

. *.ATTACHMENT 7

.< ,. (Page 1 of 3)

Radioactive Gaseous Ef{Ju,~pt.-M.Q,1;rltoring Instrumentation Surveillance Requirements

'~

CHANNEL DESCRIPTION

. ;: r*~ CHANNEL SOURCE CHANNEL Channel

-CHECK CHECK CALIBRATION Oper~tional Test

1. PROCESS VENT SYSTEM I

.. (a) Noble Gas Activity Monito:i;.

1-GW-RM-178-1 D M(NOTE5) R Q (NOTE 1)

(b) Iodine Sampler C 1-GW-RM-178-1 w NIA NIA NIA Process Vent Continuous HP Sampler '~-

D (NOTE3) NIA NIA NIA (c) Particulate Sampler 1-GW-RM-178-1 w NIA NIA NIA Process Vent Continuous HP Sampler D (NOTE3) NIA NIA NIA (d) Total Flow Monitor l-GW-Ff-108 -D NIA R Q (e) Sampler Flow Rate Measuring Device MGPI Flow Rate Measuring D (NOTE3) NIA R NIA Device HP Sampler Rotameter D (NOTE3) NIA Every 18 months NIA

2. CONDENSER AIR EJECTOR SYSTEM (a) Noble Gas Activity Monitor Unit 1 l-SV-RM-121 D M R Q,R(NOTE6)

Unit 2 2-SV-RM-221 (b) Flow Rate Measuring Device Unit 1 1-SV-Fl-lO0A l-SV-F1-101A 1-SV-Fl-lO0B J) NIA R NIA l-SV-F1-101B Unit2 2-SV-F1-200A 2-SV-F1-201A 2-SV-F1-200B D NIA R NIA 2-SV-F1-201B

DOMINION . VPAP-2103N REVISION29 PAGE63 OF87 ATTACHMENT 7

• (Page 'i bf 3)

Radioactive Gaseous Effluent Monitoring Instrnmentation 'Surveillance Requirements CHANN]j:(; , SOURCE * *

• CHANNEL Channel CHANNEL DESCRIPTION CHEC~ ' CHECI{ , . *CALIBRATION Operational Test

3. VENTILATION VENT A ., ,

(a) Noble Gas Activity Monitor 1-VG-RM-179-1 D R Q(NOTE2)

(b) Iodine Sampler l-VG-RM-179-1 w NIA NIA . NIA Vent Vent A Continuous HP Sampler D (NOTE3). NIA **NIA NIA (c) Particulate Sampler

.J_: i , __.

l-VG-RM~179-1 w NIA NIA Vent Vent A Continuous HP

.D (NOTE3).

Sampler. NIA NIA. NIA (d) Total Flow Monitor 1-HV-Ff-1212A NIA R Q (e) Sampler Flow Rate Measuring Device MGPI Flow Rate Measuring D (NOTE 3) NIA R NIA Device HP Sampler Rotameter D (NOTE 3) NIA Every 18 months NIA

4. VENTILATION VENT B (a) Noble Gas Activity Monitor 1-VG-RM-180-1 D. M (NOTE,5) R Q (NOTE 2)

(b)

• Iodine Sampler l-VG-RM-180-1 W NIA NIA NIA V,ent Vent B Continuous HP Sampler D (NOTE3) NIA NIA NIA (c), Particulate Sampler 1-VG-RM-180-1 w NIA NIA NIA Vent Vent B Continuous HP Sampler D (NOTE3) NIA, NIA NIA (d) Total Flow Monitor l-HV-Ff-1212B D NIA R Q (e) Sampler Flow Rate Measuring Device MGPI Flow Rate Measuring D (NOTE 3) NIA R NIA Device HP Sampler Rotameter D (NOTE 3) NIA R NIA

DOMINION VPAP-2103N REVISION29 PAGE64OF87

• .* ATTACI'ENT 7

• ./ l (Page 3 ,.of 3)

Radioactive Gaseous Effluent,Monitoringlnstrumentation Surveillance Requirements NOTE 1: The Channel Operati:onal1 Test *shall demonstrate:

. ' : . ****'"*T .'.'.\_;: " . . . .

a. Automatic actuation *of the valves in this pathway and Control Room alarm

' * * - * /-:: ( . : *, , \ . . * ' * ** *

~unciation occur, _if the instrument indii;;ates measured levels above the alarm/trip _setpoint. : : ; ... /; ; .

b.

• Alarm annunciation occurs if tli~* fustrument controls not set in "op~rate" mode.

NOTE 2: The <;hannel Operational Test shalldemonstrate: .

a. .Control Room .alarm annuncia,tion occurs if the instrument indicates measured

. levels are above the alarm/trip, setpoint.

. . b. -Alarm annunciation occurs i(the-instrument controls not set in "operate" mode.

NOTE 3: Channel Checks shall consist of checking indication of flow during periods of release.

Channel Checks shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made. Verification need only to be done to check operability of one train, either. MGPI or HP Sampler.

NO'IE 4: The C~annel Operati011al Test shall demonstrate that:

a. Control Room alarm annunciation occurs if the instrument indicates measured levels are above alarm/trip setpoint.

b. The Instrument mode selection:control automatically resets to "operate"*mode when

, released.

NOTE 5: Monitors l-GW-RM-178-I; i-VG-RM-179-1, and l-VG-RM-180-1 perform periodic source checks automatically.

NOTE 6:

• The quarterly, Q, Channel Operational Test shall demonstrate that Control' Room Alarm annuciation occurs if the instrument itidicates measured levels above the alarm/trip setpoint and alarm annunciation occurs if the instrument controls are not set in the "operate" mode.

• -The refueling, R, Channel Operational Test shall demonstrate:

a. Automatic actuation of the valves in this pathway and Control Room Alaqn annunciation occur if the instrument indicates above the alarm/trip setpoint.

b. Alarm annunciation occurs if the. instrument controls are not set in the "operate" mode.

DOMINION

• VPAP-2103N REVISION29 PAGE65 OF87 ATTACHMENTS (Page* 1,of 2)

Critical Organ Dose Factors* *

(Critical Pathway Dose*Factors)

Ventilation Vent X/Q = 3.3E-6 at 1593. p:ieters SSE Direction.

Process Vent X/Q = 9.5E-7 at 1593 ~eters *ssE Direction'

=

Ventilation Vent D/Q 1. 7E-8 at 1593 meters SSE Direction Process Vent D/Q = l.lE-8 at 1593 meters* SSE Direction KM*1VV,. KMipv Radionuclide *mrem/yr** .

ri:rrem/yr

. Curie/sec ,  : Curie/sec H-3 l.32E+4 3.81E+3

) .. J .

Mn-54 Nlf ND Fe-59 ND ND Cr-51 1.11E+3 *- 7.16E+2 Co-58 ND. ND Co-60 -ND ND Zn-65, .*ND, - - ND Rb-86 ND- -.

ND Sr-89 ND ND Sr-90 ND ND Y-91 ND ND Zr-95 ND ND Nb-95 ND ND Ru-103 ND ND Ru-106 ND ND Ag-llOm ND ND Te-127m 5.37E+6 3.48E+6 Te-129m. 4.61E:t6 2.98E+6

- I-131 8.08E+8 5.23:E;+8 I-133 l.38E+7 8.93E+6 Cs-134 ND ND Cs-136 ND ND Cs-137 ND ND Ba-140 ND ND Ce-141 ND ND

DOMINION VPAP-2103N REVISION29 PAGE660F87 1

• ',' -' ATTACHMENT 8

'.: ;'. ** {Page 2 of 2)

-: ;,*:!* *,Critfoal:Organ Dose Factors ivv ipv Radionuclide - mrem/yr mrem/yr

• Curie/sec Curie/sec.

Ce-144 ND ND ND - No data for dose factor according to Regulatory Guide 1.109, Revision 1

DOMINION .. *VPAP-2103N REVISION29 PAGE670F87 ATTACHMENT9 (Page Lof 5)

Radiological Environmental Monitoring Program requency o Analysis RADIATION (NOTE 3) 36 routine monitoring stations, either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, to be placed as follows:

1) An inner ring of stations, one in each environmental GAMMADOSE meteorological sector within the site boundary

2) An outer ring of stations, one in each environmental Quarterly Quarterly meteorological sector within 8 km range from the site

3) The balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations m appropnate emergency p an sectors. ese are not part o e envrronment rogram. Collect and report with environmental TLDs.

• DOMINION VPAP-2103N REVISION29 PAGE68 OF87

, : ATTACHMENT 9

' .* (Page 2 of 5)

Radiol~gical Environmental Monitoring Program requency o Analysis Samples from 5 locations:

a) 3 samples from close to the site boundary

• locations (in different

• Radioiodine Canister sectors) of the highest 1131 Analysis, weekly calcul.at~d :historical annual average ground Continuous Radioiodines and levelD/Q sampler, Particulates b) 1 sample from the operation with vicinity of a community sample collection Particulate Sampler having the highest . weekly Gross beta radioactivity calculated annual analysis following filter average ground level. change; (NOTE 4)

D/Q c) 1 sample froni a control .Gamma isotopic analy-location 15-40 km * * .sis of composite (by distant and in the least location) quarterly prevalent wind directio * (NOTE 5)

Samples from 3 locati<;ms:

Gamma isotopic analysis a) 1 sample upstream monthly; (NOTE 5) a) Surface b) 1 sample downstream Grab Monthly Composite for tritium c) 1 sample from cooling analysis quarterly lagoon amma 1sotop1c an tntmm Sample from 1 or 2 sources b) Ground Grab Quarterly analysis quarterly (NOTE only if likely to be affected 5) 1 sample from downstream Gamma isotopic analysis c) Sediment area with existing or Semi-Annually semi-annually (NOTE 5) potential recreational value

DOMINION .

• VPAP-2103N REVISlON29 PAGE69OF87 ATTACHMENT 9 (Page 3:of 5)

Radiological Environmental Mohltor~g*Program Expo.sure Pathway Number of Sample and,, ry;, -,;, :CQlle~ti,on Type and, Frequency of and/or Sample Sample Locati~n (NOTE2),i'; F~eque~cy 0

• -~' I** * * ' . .

• _Analysis

4. lNlih~TlUN a) Samples from milking . .

animals in 3 locations witl:mi _:-: * " ;

5 km that have the highest:  : * * :' * *

• potential. If there are none/*._** :' ;'. ' ; ' '

then 1 sample from milking t, animals in each of 3 areas* - , -~ * * .*. ,

. Monthly at all Gamma isotopic (NOTE 5) 1 a) Milk between 5 to 8 km where *

(NOTE 7) doses are calculated to-be.-. ' times _ ' and 1131 analysis.~onthly greater than 1 :ri:irem per yr. ' _. . '

(NOTE 6) * ..

I ,_, * ._,

b) ,1 *sample from milking ' :.

animals at a control location **. -

(15-30 km in the least -* *

prevalent wind direction).

a) 1 sample of commerciajl)'.' and recreationally important __ .

species (bass, sunfish, catfish) b) Fish and in vicinity of plant dis_ c_h~ge Gamma isotopic on edible Semiannually Invertebrates area ** portions b) 1 sample of same species in areas not influenced by plant*

discharge a) Samples of an edible broad leaf vegetation grown nearest

each of two different offsite locations of highest predicted historical annual average . , .Monthly if ground level D/Q if~lk: *; Gamma isotopic (NOTE 5) c) Food Products available, or sampling is not performed and 1131 analysis at harvest b) 1 sample of broad leaf .

vegetation grown 15-30kmin ...

the least prevalent wind direction if milk sampling is not performed

• odMINION VPAP-2103N REVISION29 PAGE70OF87

,ATTACHMENT 9

• / {Page 4 of 5)

RadiologicalEnviromnental Monitoring Program

• . 'NOTE l: *' The number; inedia;,:frequency/and location of samples may vary from site to site. This table presents an accepta:ble miiiimum program for a site at which each entry is applicable.

Local site characteristics must be**examined to determine if.pathways notcovered by this table may significantly contribute. to an individual's:dose and be included in the sampling program; NOTE 2: For each and every sanipie loditioii hi Environmental Sampling Locations (Attachment 10),

specific parameters. of distance arid direction sector from the centerline of the reactor, and additionaldescripti.on wlieiipdrtfuent, shall be provided in Attachmentlff 'Refer to

. Rac:liological Assessnient BrancfrT~dinical Positions and to NUREG-0133, Preparation of

Radiological Effluent'Techrucal Specifications for Nuclear Power Plant. Deviations are permitted from the required sampling schedule if specimens are unattainable due to hazardous conditions,

seasonal unavailability, malfunction of automatic sampling ,

equipment and other legitimate reasons. If specimens are unattainable due to sampling

. equipment malfunction, every effort shall be made to complete corrective action before the end of the next sampling*peri'od. All deviations from the sampling schedule shall be documented in the Annual RadioJogical Environmental Operating Report pursuantto ..

Step 6.7 .1. It is recogi;tlzed,th_at, ,~t times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location. or time. In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological envkonmentai monitori~g program. In lieu ofa Licensee Event Report and pursuant to Step 6. 7 .2, identify the cause* of the unavailability of samples for that pathway and identify the new locations for obtaining*replacement samples'in the next Annual Radioactive

• Effluent Release Report, and include revised figures and tables from the ODCM reflecting the new locations in the report:.:

'DOMINION .- VJ>AP.,2103N REVISION29 PAGE 71 OF87 ATTACHMENT 9 (Page 5 of 5)

Radiological EnvironmentalMonitorip.g1 Program NOTE 3:

• One or more instruments, such as a pressur:iz~d:ion;.chamber, for me~suring and recording dose rate continuously may be used in place bf; o:r*in,~ddition to, integrating dosimeters.

For the purposes of this table, a thermolumirtesce.nt:dosim~ter (TLD) is.considered to be

• one phosphor; two or more phosphors ma packet m.:e co:psidered_as two or more dosimeters.

Film badges shall not be used as dosimeters for measuring direct radiation; The 36 stations are not an absolute number. The numbe! of pir~ct.radiatioµ monitoring stations may be I

reduced according to geographical limitations, e.g., .at.~ ocean site, some sectors will be over water so that the number of dosimeter:s JJl~Y. ...be redt;iced. accordingly. .

The*.

frequency of

-.analysis

. . TLD systems will .d,epend_upon or readout for .., -*  :

the characteristics of the specific system used and should be selected.to optain.qptimum cl9se information with minimal fading.

NOTE,4: Airborne particulate sample filters shall be analyzed for gtoss beta radi_oactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

.or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate. samples is greater than ten times the yearly mean_ of control samples, gamma isotopic analysis-shall be performedonthe_individual samples.

NOTE 5: Gamma isotopic analysis is the identification and *quantification of gamma-emitting radionuclides that may be attributable to' effluents from the facility.

NOTE 6: The dose shall be calculated for the m~uin* organ and age group, using the methodology

• *. and parameters in *the ODCM.

NOTE 7: .If milk sampling cannot be performed, use item 4.c (Page 3 of 5, Radiological E:rwironmental Monitoring Program (Attachment 9)).

NOTE: Additionally, the following TLDs are placed in the indicated locations for Emergency Plan requirements. This is due to the fact that Emergency Plan and Environmental Plan grid centers are in different locations. These TLDs are collected quarterly in conjunction with Environmental Sector TLbs.

BP Sector TLD Designator Location A EPSAl/2 On fence, U-2 side, Intake Structure F EPSF3/4 On power pole on island (across from FPPH)

R EPSR5/6 On door of Substation "M" p EPSP 9/10 On/near Switchyard gate J EPSJ7/8 NW comer of the Generator Rewind Bldg.

DOMINION VPAP-2103N REVISION29 PAGE72OF87 ATTACHMENT 10

(, **(Page 1 of 5)

. , Environmental Sampling Locations

. Distance.and Direction From Unit No.1

,,sample ii station u1stance Direction L'.ollection Locati'on : .-" **

• Remarks

• • • Media I,;*

No. (Miles) Frequency Enviromnental NAPS Waste Treatment 01 0.20 NE . Quarterly & On-Site TLDs Plant, end of parking"lot B Annually Frederick's llall  :, (

02 5.30 SSW Quarterly&

Annually WSW Quarterly&

-Mineral VA'

• 03 7.10

' Annually WNW Quarterly&

Wares Crossroads 04 5.10 Annually

' Quarterly&

Route 752 05 4.20 NNE Annually Sturgeon's Creek Marina 05A ,, '2.04 N Quarterly&

Annually Levy, VA 06 4.70 ESE Quarterly&

' Annually Bumpass, VA .07 7.30 SSE. Quarterly&

Annually Quarterly& Site Boundary End of Route 685 21 1.00 WNW Annually Route 700 22 1.00 WSW Quarterly& Site Boundary

• , Annually "Aspen Hills" 23 SSE Quarterly& Site Boundary 0.93 Annually Quarterly&

Orange, VA 24 22.00 NW Control

Annually Bearing Cooling Tower . N-1/33 0.06 N Quarterly On-Site Sturgeon's Creek Marina N-2/34 2.04 N Quarterly Parking Lot "C" NNE~3/35 0.24 NNE Quarterly On-Site Good Hope Church NNE-4/36 3.77 NNE. Quarterly NAPS Waste Treatment NE

-5/37 0.20 NE Quarterly On-Site Plant, end of parking lot B Bogg's Drive

• NE-6/38 1.46 NE Quarterly Weather Tower Fence* ENE-7/39 0.36 ENE Quarterly On-Site Route 689 ENE-8/40 2.43 ENE Quarterly Near Training Facility £-9/41 0.30 E Quarterly On-Site

'Mormng Ulory Hlll b-lU/4:L L.~~ b l.,,luarterly 1s1and uuce lbSb-11/4:.i U.12 bSb l.,,luarterly Un-Site

. Koute f:JLL lbSb-12/44 4./U ESE (..!uarterly

DOMINION VPAP-2103N REVISION29 PAGE73 OF87 ATTAC1'ENT 10 (Page 2 :of 5)

Environmental Sampling, Locations Distance and Direction From**l:Jnif No. 1

sample :station - U1stance --Colleclfon

• Location No.

• Direction Remarks Media.*. (Miles) Frequency Environmental

• Biology Lab SE-13/45

• o:64* ,, SE Quarterly On-Site TLDs , . .,.

Route 701 SE-14/46 :5.88* .Quarterly (Dam Entrance)

~fr

Site

'"Aspen Hills" SSE-15/47 0.93 SSE . *. Quarterly Boundary Elk.Creek SSE-16/48 . 2.33 . '

SSE .Quarterly

• NAPS Access Road S-17/49-

• 0.36 s -Quarterly On-Site Elk Creek Church S-18/50 1.55 s Quarterly NAPS Access Road SSW-19/51 0.24* . . -SSW Quarterly On-Site Route 618 SSW-20/52 5.30* SSW Quarterly 500KVTower SW-21/53 0.60 SW Quarterly On-Site Route 700 SW-22/54 . 3.96 SW Quarterly At NAPS, on pole, SE of

' switchyard, entrance on WSW-23/55 0.38 WSW Quarterly On-Site

• . Rt. 700

Site Route 700 WSW-24/56. *. 1.00 WSW Quarterly Boundary

. South Gate of W-25/57 0.32 w Quarterly On-Site Switchyard Route 685 W-26/58 1.55 w Quarterly

.:Site End of Route 685 WNW-27/59 1.00. WNW Quarterly Boundary Route 685 WNW-28/60

• 1.40 WNW Quarterly Laydown Area North NW-29/61 0.52 NW Quarterly On-Site Gate Lake Anna Campgrounc NW-30/62 2.54 .. NW Quarterly

1. 1/#2 futake

• NNW-31/63

• 0.07 NNW

• Quarterly On-Site Route 208 NNW-32/64 2.21 NNW Quarterly Bumpass Post Office C-1/2 7.30 SSE Quarterly Orange, VA C-3/4 22.00 NW

• Quarterly Control Mineral, VA

• C-5/6 7.10* WSW Quarterly Louisa, VA C-7/8 11.54 WSW Quarterly Control

• These locations have been evaluated and are acceptable. (Reference 3.1.37)

DOMINION VPAP-2103N REVISION29 PAGE74OF87

• ,, ATTACHMENTlO (Page 3 of 5)

• 'Environmental Sampling Locations

• . Distarice:and Direction From UnitNo.1

. _* :sample *Location*:; ,, * * * *. .Matton IU1stance Direction Collection Remarks Media . :*_No. (Miles)

, Frequency Airborne

• NAPS Waste Treatment 01 0.20 NE Weekly On-Site Plant, end of park.mg lot B .

Particulate Biology Lab 01-A 0.64 SE Weekly On-Site and Frederick's Hall- '

. 02 5.30 SSW Weekly Radioiodine Mineral, VA *--03. 7.10 WSW Weekly Wares Crossroads* - 04 5.10 WNW Weekly

. Route 752 '. 05 4.20 NNE Weekly Sturgeon's Creek ;Marina . 05A 2.04 N Weekly Levy, VA  !

• . 06 4.70 - ESE Weekly Bumpass, VA - 07 i

7.30 SSE Weekly End of Route 685 .* 21 1.00 WNW Weekly Site Boundary Route 700 '. 22 1.00 WSW Weekly Site Boundary "Aspen Hills" 23 0.93 SSE. Weekly Site Boundary Orange, VA 24 22.00 NW Weekly Control

~urtace Water Waste Heat Treatment

[Reference Facility (Second Cooling 08 3.37 SSE Monthly 3.1.31] Lagoon)

North Anna River (upstream) Rt 669 Bridge 09A 12.9 WNW Monthly Control (Brook's Bridge)

North Anna River

• 11 5.80 SE Monthly (downstream) ......

Urounctwater 0lA 0.64 SE Quarterly (well water) Biology Lab Aquatic Waste Heat Treatment Semi-08

• 3.37 SSE Sediment Facility (Second Cooling Annually Lagoon)

North Anna River Semi-

• (upstream) Rt 669 Bridge 09A- 12.9 WNW Control Annually (Brook's Bridge)

North Anna River Senn- .

11 5.80 SE (downstream)

• Annually Shoreline Soil Lake Anna 08 3.37 SSE Semi-Annually Soil NAPS Waste Treatment 01 0.20 NE bnceper3 yrs On-Site Plant, end of parking lot B

DOMINION , VPAP-2103N REVISION29 PAGE 75 OF87 ATTACHMENT 10

. (Page 4 -of 5)

Envir()nmental SampUng:LQc~tions Distance and Direction F1;Qn:i-:DnitNo. l Sample Location :station u1sta~ce u1rect1on- _Lollecbon

• Remarks Media No. (Miles) Frequency Soil Fredericks Hall UL  :, ,ju  ; . ':S:SW .unce per j yrs (continued) Mineral, VA 03 7.10 **wsw** Once per 3 yrs Wares Crossroads 04 5.10 .. WNW. Orice per 3 yrs Route 752 05 4.20. -NNE ** *Once per 3 yrs Sturgeon's Creek 05A 2.04 N-*' .Once per 3 yrs Marina

_Levy,_VA. 06 4.70 ESE Once per 3 yrs Bumpass, VA 07 7'.30 SSE- Once per 3. yrs End of Route 685 21 1.00 WNW Once per 3 yrs Site Boundary Route 700 .22 1.00 WSW Once per 3 yrs Site Boundary "Aspen Hills" - 23 .0.93 .. SSE Once per 3 yrs Site Boundary Orange, VA 24 22.00 NW Once per 3 yrs Control Milkb TBD TBD Monthly Waste Heat Treatment Fish Facility (Second 08 3.37 SSE Semi-Annually Cooling Lagoon)

Lake Orange 25 16.50 NW. S_emi-Annually Control Food Products Stagecoach Road 14B varies NNE Monthly . '

(Edible if available, broadleaf Route 614 15 vanes SE or at harvest vegetationa)

Route 629/522 16 vanes NW Control Historic Ln 26 vanes s

Aspen Hills" Area 23 vanes SSE

a. If edible broadleaf vegetation is unavailable, -non-edible vegetation of similar leaf characteristics may be substituted.

b. Milk producing animals are no longer within NAPS momtonng locations following the Harris Dairy closure 01/01/2018. Annual Land use ce11sus data will be used to detennine future availability of milk samples.

• DOMINION VPAP-:2103N REVISION29 PAGE760F87 ATTACHMENTl0

* (Page 5.of 5)

.. , Environmental Sampling Locations NOTE: Additionally, thefollowingTI::Ds are placed in the indicated locations for Emergency Plan requirements. This-is due to the fact that Emergency Plan and Environmental Plan

- grid centers arei:µ different locations. These TLDs are collected quarterly in conjunction with Environmental Sector TLDs.

BP Sector TLD Designator Location A_ EPSAl/2 , Onfence, U-2 side, Intake Structure F EPSF3/4 ' On power pole on island (across from FPPH)

R EPSR5/6 . On door of Substation "M" p EPSP 9/10 On/:µear Switchyard gate 1 EPSJ 7/8- NW, comer of the Generator Rewind Bldg.

• NOTE: ISFSI well water samples are obtained as a Conditional Use Permit issued by the County of Louisa.

• DOMINION . VPAP-2103N REVISION29 PAGE 77 OF87 ATTACHMENT 11

• * (Page 1 of 2)

Detection Capabilities for Environmental Sample Analysis LOWER LIMIT OF DETECTION.(LLD)

.,, ; ,(

Airborne Food Fish*:  : *: ~

Sediment Analysis Water Particulate Milk Products (pCi/kg) ,. ' (pCi/kg)

(NOIB2) (pCi/1) or Gases (pCi/1) (pCi/kg)

(wet) (dry)

(pCifm3) (wet)

Gross beta 4 0.01 .'_;'I

. H-3

• 2,000 .'

Mn-54 15 130 . ' '

Fe-59 30 260* I.* .. ...

Co-58, 60 15 130 * ..

Zn-65 30 260 Zr-95 30 Nb-95 15 I-131 (NOIB3) 1 0.07 1 60 (NOTE4)

Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 (NOTE4)

La-140 15 15 (NOIB4)

NOTE 1: Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

NOTE 2: This list does not mean that only these nuclides are to be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

NOTE 3: LLD for the drinking water samples. Drinking water includes samples from Lake Anna and well samples analyzed as part of the REMP. The LLD for the non-drinking water samples is 10 pCi/1.

NOTE 4: No LLD for precipitation water due to short-half lives of these nuclides.

DOMINION VPAP:.2103N REVISION29 PAGE 78 OF87 ATTACHMENT 11

: ; (Page *2 of 2)

Detectim{Capa:bilities for Environmental Sample Analysis LOWER LIMIT OF DETECTION (LLD) (NOTE 3)

NOTE 1: For a particular measurementsystem(which may include radiochemical separation):

,

• 4.66 sh LLD . =.... . . . . .. . . (25-1)

E

• V

• 2.22E+06

• Y

• e.:...(11.At)

Where:

• . ;c: ,,,:

LLD = the "a ptj.qri" (before the fact) Lower Limit of Detection as defined

( ~ .

above (as microc;uries per unit mass or volume) (See Subsection 4.9) .

the standard :de;iation of the backgr~und counting rate ~r of the counting rate of a blank sample as appropriate (as counts' per minute, cpm)

E = the counting efficiency (as counts per disintegration)

V = the sample size (in units of mass or volume) **

• 2.22E+06 = the number of disintegrations per minute (dpm) per microcurie y = the fractional radiochemical yield (when applicable)

A, = the radioactive decay constant for the particular radionuclide At = the elapsed time between sample collection (or end of the sample collection period) and time of counting (for environmental samples, not plant effluent samples)

Typical values of E, V, Y and At should be used in the calculation.

The LLD is an "a priori" (before the fact) limit representing the capability of a measurement system and not a "posteriori" (after the fact) limit for a particular measurement.

DOMINION VPAP-2103N REVISION29 PAGE79OF87 ATTACHMENT 12 (Page 1 of 1)

Reporting Levels for Radioactivity. Concentrations in .Environmental Samples Airborne Water Fish Milk Food Products Analysis Particulate or (pCi/1) (pCi/kg, wet) (pCi/1) (pCi/kg, wet)

Gases (pCifm3)

(NOTE 1)

H-3 20,000 Mn-54 1,000 30,000 Fe-59 400 10,_000 Co-58 1,000 '30,'00b Co-60 300 10,000 Zn-65 300 ,20,000, Zr-Nb-95 400 I-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 NOTE 1: For drinking water samples

DOMINION VPAP-2103N REVISION 29

• PAGE80OF87 ATTACHMENT 13

* (J>age 1 of 8)

Meteorological, Liqµid,: and Gaseous Pathway Analysis

• 1.0 * , -l\'IETEOROLOGICAL-ANA.LY:SIS. .* -*

Ll* Purpose

• The purpose of the meteorologidif analysis was to determine the annual avetage X/Q and D/Q values at critical locations arburilfthe Station for ventilation vent (ground level) and process

vent (mixed mode) reld1.ses'. Tlfo annual average X/Q and D/Q.values were used to perform a dose pathway analysisto'deter.tiiliie*15bth the maximum exposed individual at site boundary and member of the public. The X/Q and D/Q values resulting in the maximum exposures were incorporated into the dose.__'factorsjl)

Oaseous Effluent Dqse Factors (At;tachment

5) and

_Critical Organ Dose Factors (Att11c}:nnent 8).

• *  :

• J ** '

• _ *** '

1.2 - Meteorological Data, Parameters, and Methodology

.*. Onsite meteorological d~ta for the period January 1, 1981, through December 3(1981, were used in calculations. These data included wind speed, wind direction, and differential

. :temperature.for the purpose of determining joint frequency distributions for those releases characterized as ground leyel (e.g._, ventilation vent), and those characterized as mixed mode (i.e., process vent). The portions.of release charactf?rized as ground level were based on t1T1s8.9ft-28.2ft ;md 28.2 f~,0t wind,~at~, ~d the portions characterized as mixed mode were based on t1T1s8.9ft-28.2ft and 15,8.9;-ft wind ~ata.

X/Q's and D/Q's were calculated usmg the NRC computer code XOQDOQ - Program for the Meteorological Evalu_ation of Routine Effluent Releases at Nuclear Power Stations,"

September, 1977. The code_js ~ased upon a straight line airflow model implementing the assumptions outlined in Section C (excluding C 1a and C 1b) of Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in

-Routine Releases from Light-Water-Cooled Reactors."

The open terrain a4justment factors -: .

were applie4 to the X/Q values as recommended in Regulatory Guide 1.1 ll. The site region is characterized by gently rolling terrain ~o open terrain correction factors were considered appropriate. The ground level ventilation vent release calculations included.a building wake correction based on a 1516 m 2 containment

, I *

• minimum cross-sectional area.

DOMINION *

• VPAP-2103N REVISION29 PAGE81 OF87 ATTACHMENT 13

• ' -(Page 2 of 8)

Meteorological, Liquid,. and Gaseous ,Pathway Analysis The effective release height used in mixed niode:i-el~ase* calcuiations was.based on a process vent release height of 157 .5 ft, and plume rise due to momentum for a vent diameter of3 in.

with plume exit velocity of 100 ft/sec. Ventilatiog v:~:nt,. and v~nt releases other than from the process ve1.1t, ai::e considered grounµ level as specifi,ed in,R~gul~tory Guide 1.111 for release points less than the height of adjacent solid ~tructur~s .. '.femrin elevations were obtained from

.North Anna Power Station Unit~ 1,and 2, Virgiaj!l ~leGtric;andPower.Company Final Safety Analysi,sReport Table llC.2-8.  : :.*, . - 1

'X/Q and D/Q values Were calculated for the 1foatest:sfr~ houndary; resident, Inilk cow, and vegetable garden by sector for process vent :fu:ci v~ritilatidn vent reieases at distances specified from North Anna Power Station Annual Env~opm~ntal Smyey Data for 1981.- .'X/Q values were

.also calculated for the nearest lake shoreline .by secto~ for. the process vent and ventilation vent

' * * * '*. '. ' I, ' '

releases.

According to the definition for shortterin irrNlJREG.:0133, "Preparation of Radiological EfflueiltTechriical Specifications fotNucleatPower Stations,"*bctober, 1978, some gaseous

• releases may fit this category, primarily waste gas decay tank releases and containinent purges.

However, these releases are considered fong term for dose calculations as past releases were both random in time of day and duration as 'evidenced by reviewing past release reports.

_ Therefore, th,e use of annual average concentrations is appropriate according to NUREG-0133.

• • The X,/Q and D/Q values calculated from 1981 meteorological data are comparable to the

• values presented in the North Anna Power Station UFSAR.

1.3 ..Results The X,/Q value that resulted in the maximum total body, skin and inhalation exposure for ventilation vent releases was 9.3E-06 secfm3 at a site boundary location 1416 meters SE sector. For pro,cess vent releas*es, the site boundary i!Q value was 1~2E-06 sec/m3 at a location 1513 meters S sector. The shoreline 'X/Q value th~t resulted.in the maximum inhalation exposure for ventilation vent releases was l.0E~04 sec/m3 at a location 274 meters NNE sector.

The shoreline X,/Q value for process vent was 2.7E-o'6 secfin3 at a location 274 meters NNE sector.

-:DOMINION

• VPAP-2103N REVISION 29

• PAGE82OF87

.1ATTACHMENT 13

.(Page 3

pf 8)

Meteorological;-Liquid,.and Gaseous Pathway Analysis

. **: Tp.e original pathway analysis ,-indicated that the maximum exposure from I 131 , I 133 , and from

• all radionuclides in particulate* fortn with half-lives greater than 8 days was through the

• grass-cows.milk pathway:' ThetD/Q value from ventilation vent releases resulting in the maximum exposure was 2AE..;09 per m2 at a location 3250 meters N sector. For process vent releases, the D/Qvalue wasJ. 1E~09 per m2 at aJocation 3250 meters N sector..For tritium, the

,XIQ value from ventilatiom vent.releases resulting. in the maximum exposure for. the milk pathway was 7 .2E-07 sec/m3, and .3.9E-07 sec/m3 for process vent releases at a location 3250 meters N sector.

Analysis using2007 release data:indicates that the most limiting critical organ is the child's

.-.thyroid. The location is 1593 meters* SSE sector. For process vent releases, the D/Q is l. lE-8.

For tritium releases, the X/Q values at this location are 9 .SE-7 for the process vent and 3.3E-6 for the ventilation vents.

2.0 LIQUID PATHWAYANALYSIS 2.1 Purpose* *

• The purpose of the liquid pathway analysis \vas to determine the maximum*exposed member of the public in unrestricteclareas as a result ofradioactive liquid effluent releases. The analysis includes a determination of most t~strictive liquid pathway, most restrictive age group, and critical organ. This analysis is'required for Subsection 6.2.

2.2 Data, Parameters, and Methodology Initially, radioactive liquid effluent release data for the years 1979, 1980, and 1981 were compiled from the North Anna Power Station semi-annual effluent release reports. The data for each year, along with appropriate site specific parameters and default selected parameters, were entered into the NRC computer code LADTAP as described in NUREG-0133.

• DOMINION -:, VPAP.::2103N REVISION29 PAGE830F87 ATTACHMENT 13

, i . (Page 4~of 8)

.Meteorological, Liquid, -and Gaseous :Pathway Analysis Re-concentration of effluents using the smalllake,corin~c.ted to larger water body model was selected with the appropriate parameters: determin~dfr6m Table 3.5\3.S;Design Data for Reservoir and Waste Heat Treatment Facility, frpin iVirgini_a Electric and Power Company, Applicant's ErivironmentalReport Supplement,:Notth*Anna:Power Station; Units 1 and 2, March 1.5, 1972: Dilution factors- for aquatic*foods;'. shoreline, and_ drinking water were set to

• one. Transit time calculations were based 0n:average flow-rates. All other parameters were defaults selected by the LADTAP compriter*code;.';, ,: * **.

Beginning in 1997, the activity by nuclide released in the previous year is entered into the North Anna Power Station liquid*pathwaicrifical organ calculations spreadsheet, which

.calculates the most limiting age group total body and critical organ;. This Process is repeated annually. * * *, *;_. *

• 2.3 Results Initially, the fish pathway resulted in the largest do:Se. The critical organ each yeat was the liver, and the adult and teenage age groups received the same organ dose. However, since the adult

. totaLbody dose was greater than. the teen tot;tl body dose for each year, the adult was selected

, *.. ', ' * . .* ' *. i . . ,. '

as ili,e most restrictive age group. Beg~g ip. 1~97, ~e most limiting age group for both total bo4y and. critical organ is calculated frolll tii~ ~pread.sheet or equivalent software for North Anna Power Station liquid pathway critical . -

organ calculations.

. ~ . .

• noMINION VPAP-2103N REVISION 29

• PAGE 840F87

,. :' ATTACHMENT 13

,;,> !*(Page 5 of 8)

• MeteorologieaI/Liquid, and .Gaseous Pathway Analysis

.* 3:0, ::* GASEOUS PATHWAY!ANA!LYSIS 3.1* Purpose

• .* A gaseous *effluent pathi~y ~filysi~i\1/~s *p~rformed to determine the locatio~ that would result

.in the maximum doses due 'tci* ~obie ga~es for us~ in demonstrating c~mpliance with Steps 6.3.1.~. and 6.3.id. The* aiialysis hlso included a determination of th{critical pathway,

.location of maximum ~xpo~~d 'iriefuber of the public, and the critical organ for the maximum dose due to 1131 , 1133 , tritium, and for all radionuclides in particulate form with half-lives

• .* gregiter than 8 days. for use,in demonstrating compliance witp requirements in Step 6.3 .4.a. l. In

• .* additiqn,: the analysis inclµded a det~rmination ofthe critical pathway, mazjm~ age group,

• ,and sector location of an expos~g individual through *the inhalation pathway from I 131 , I 133 ,

tritium, and particulates wit:li hajf-lives *greater Jhan 8 day~ to demonstrate compliance with

'. Step 6.3.1.a.

3.2 Data, Parameters, and Methodology Annual average X/Q values were calculated, as described in Section 1 of this attachment, for the nearest site boundary in each.cli,rectional*sector.and at other critical locations beyond the site boundary. The largest X/Q value was determined to be 9 .3E-06 sec/m3 at site boundary for ventilation vent releases at a location 1416 meters SE direction, and l .2E-06 sec/m3 at site a

boundary for process ventreleases~t locati~n 1513 *meters S *direction. The maximum doses to total body and skin, and air doses for gamma and beta radiation due to noble.gases, would be at these site boundary locations. The doses from both release points are summed in calculations to calculate total maximum dose.

Step 6.3. l .a.2 dose limits apply specifically to the in4alation pathway. Therefore, the locations and X/Q values determined Jar maximum noble gas doses can be used to determine the maximum dos~ from I 1~1, 1133 , tritium, ~dfor all radionuclides in ~articulate form with half.:-lives greater than 8 days:for the inhalation pathway.

DOMINION .. VPAP"'.2103N

• REVISION29 PAGE 85 OF87 ATTA.CHMENT 13

• (Page 6 of 8)

• . Meteorological, Liquid, and G;~~~ous;J>athway An~lysis The NRC computer code GASPAR, "Evalua,ti01;rof1Atmospheric Rele(j.ses," Revised 8/19/77, was run using 1979, 1980 and 1981 North Anna Power Station Gaseous Effluent Release Report data. Doses from I 131 , I 133 , tritium, and p.µti_culates. for the inhalation pathway were

. * *  : ' ,'1, .:** . * *

• calculated using the 9 .3E-06 sec/m3 site. boundary .X/Q. Except for the source term data and the XIQ value, computer code default parameters were used. Results for. each year indicated that

.the critical age group was the c];rild and the critic;;.al o,rgap. was the thyroid for the inhalation

' . , . ' . . ' .. . . * * ' .. : \ ' ' ' .. . -* ~ .i ' '. - .

pathway.

The gamma and beta dose factors Kivv, Livv,'Mivv, an:dNivv in Gaseous Effluent Dose Factors (Attachment 5) were obtained by petforining a units-conversion of the appropriate dose factors from Table B-1, Regulatory Guide 1.109, Rev: 1, to mrem/yr per Ci/m3 or mrad/yr per

• • Ci/m3, and multiplying by the ventilation vent site boundary X/Q value of 9 .3E-:-06 sec/m3. The same approach was used in calculating the gamma and beta dose factors Kipv, Lipv, Mipv, and Nipv in Gaseous Effluent Dose Factors (Attaclrrµent 5) using the process vent site boundary X/Q value of l .2E-06 sec/m3.

The inhalation pathway dose factors Pivv and Pipv in Gaseous Effluent Dose Factors (Attachment 5) were calculated using the following e.quation:

p. K'(BR) DFAi (x/Q) (mrem/yr per Curie/sec) (29-1) 1

.-**where:

K' = a constant of unit conversion,JE+ 12. pCi/Ci.

BR = the breathing rate of the child age group, 3700 m 3/yr, from Table E-5, Regulatory Guide 1.109, Rev .1 DFAi = the thyroid organ inhalation dose factor for child age group for the ith radionuclide, in mrem/pCi; from Table E-9, Regulatory Guide 1.109; Rev: 1 XIQ = the ventilation vent site boundary X/Q, 9.3E-06 sec/m3, or the process vent site boundary X/Q, l .2E-06 sec/m3, as appropriate

DOMINION VPAP-2103N REVISION 29

• PAGE86OF87

,: '* ,A'l'T:ACHMENT 13

,(I>age.7 of 8)

.MeteoroJogical, I~iqµid,,@d Gaseous Pathway Analysis Step 6.3.4.a., requires th~t*:tp.~ gQS~: to. the maximum exposed member- of the public from I 131 ,

1133 , tritium, and from all . *. q1dipnuc1,ide.~

• - *- ' ,- . . in particulate form with.half-lives great~r than 8 days

.be less. than or equal to the, sp'1c;ifj.eq.. limits_. Dose calculations were performed for an exposed

' ' , .* , .*' -.*.4 .* , ** ' *- . ' *

• member of the public within site boundary unrestricted areas, and to an exposed member of the

. -, public beyond site boun4acy flt:Joc;ations identified in the North.Anna Power Station Annual Environmental Survey Data for.1981. : ;

It was determin~d that ~e me~bef ~(the public within site boundary ~ould be using Lake Anna fo~ recreational: p¢.;pqse,s 8;, m~um of 223.2 h9urs per year. It is assumed that this

' ) __ - ...

member of the public would be located the entire 2232 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.49276e-4 months <br /> at the lake 'shoreline with the

• * * * ' *

• l * ,* * ',.  :  :, ** > -~ *, * * * * ; ,: * ,1 ~ * * '

• largest annual X/Q of 1.0E-94 at a location 274 meters NNE sector. The NRC computer code

- / ., -l . ,.

GASPAR was run to caltulate the inhalation dose to this individual. The GASPAR results were corrected for tlie 'fractional y~ar .th.ti nieinber of the' public would be using the lake .

. ,Using tµe NRC computer.code ~ASPA.R and annual average X/Q ~d D/Q values obtained as described in Section 1 of this attachment, the member of the public receiving .. the _ '.

_hrrgest dose beyond site boundary was determined to be located 1432 meters N sector. The critical pathway was vegetation, the maximum exposed age group was-the child; artd the critical organ was the thyroid.

Pathway analysis results indicate that existing pathways, including ground and inhalation, within five miles of North Anna Power Station, yield Ri dose factors less than those determined for the vegetation. [Reference 3.1:32] -

The RMivv and RMipv dose factors, except for tritium, in Critical Organ Dose*Factors (Attachment 8) were calculate4 by multiplring the appropriate D/Q value with the following equation:

(29-2) where:

K' = a constant of unit conversion, lE+ 12 pCi/Ci Yv = vegetable areal density in Kg/m2

DOMINION

• VPAP-2103N REVISION29 PAGE87OF87 ATTACHJ.ViENT 13 (Page 8 *of 8)

.Meteorological, Liquid, *and Gas~ohs'. Path-Way Analysis ucl,. --'

child leafy vegetable consumption 1rate;-26 Kg/yt:' -*

Des = child stored vegetable consumption 'rate; 5ZO'Kg/yi r = fraction of deposited activityretaine&on\.regetiiti'on, 1.0 for radioiodine; and 0.2 for particulates -., ,,. *: *( ,, *'f : -

DF'Lj_ - 'thyroid ingestion dose factor for the-ith-radionuclidefor the child, in mtem/pCi, from Table E-13, Regulatory Guide 1.109,.Rev,J* .* ,\: _:

Ai = decay constant for the ith radionuclide, m, sec- 1, from Kocher

• • : *, . : ~ : ;': .! * : - *; * . *** ~ ; - ** -

,Aw = decay constant for removal of activity of leaf and plant surfaces by weathering,

. 5.73E-07 sec~l (corresponding to a 14 ciayhaifilife) .. ' . . . :

tf = .._time between harvest of leafy vegetatioii* and ~ge.~tion~ 8.60E+4, fo seconds th. = -time between harvest of stored veget~tioii and µigestion, 5.f8E+6, ip. se~onds

, * ' . . ~* ;* ; ~ ' ' * *; * ~, * ! '. . '. , ' . I * '

fL = fraction of annual intake ofleafy vegetables grown locally, 1.0 (dimensionless) fg = fraction of annual intake of stored vegetables grown locally, 0.76 (dimensionless)

Parameters used in the above equation weriobtailied fromNUREG-0133 and Regulatory Guide 1.109, Revision 1 Since the concentration of tritium in vegetati<Jnjs_ based_ on the airborne concentr~tion rather than the deposition, the Critical Organ Dose Factors (Attachment 8)for tritium were calculated by multiplying the following equation by the appropriate X/Q:

(29-3) where:

K = a constant of unit conversion 1E+03 gm/kg H = absolute humidity of the atmosphere, 8.0, gm/m3 0.75 = the fraction of total feed that is-water ,

0.5 = the ratio of the specific activity of the feed grass to the atmospheric water Other parameters have been previously defined.