ML24215A264

Subsequent Renewed License

ML24215A264
Person / Time
Site:	North Anna
Issue date:	08/28/2024
From:	Andrea Veil NRC/NRR/DNRL/NLRP
To:	Carr E Dominion Innsbrook Technical Center
Shared Package
ML24215A220	List: ML24215A262 ML24215A263 ML24215A264 ML24215A265 ML24215A266
References
Download: ML24215A264 (10)

Text

NORTH ANNA - UNIT 2 Subsequent Renewed License No. NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 SUBSEQUENT RENEWED FACILITY OPERATING LICENSE Subsequent Renewed License No. NPF-7

1.

The Nuclear Regulatory Commission (the Commission having previously made the findings set forth in Renewed License NPF-7 issued on March 20, 2003, has now found that:

A.

The application to subsequently renew License No. NPF-7 filed by Virginia Electric and Power Company (VEPCO or the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations as set forth in 10 CFR Chapter I and all required notifications to other agencies or bodies have been duly made; B.

Actions have been identified and have been or will be taken with respect to (1) managing the effects of aging during the subsequent period of extended operation on the functionality of structures and components that have been identified to require review under 10 CFR 54.21(a)(1), and (2) time-limited aging analyses that have been identified to require review under 10 CFR 54.21(c), such that there is reasonable assurance that the activities authorized by this subsequent renewed license will continue to be conducted in accordance with the current licensing basis, as defined in 10 CFR 54.3, for North Anna Power Station, Unit No. 2, and that any changes made to the plant's current licensing basis in order to comply with 10 CFR 54.29(a) are in accord with the Act and the Commission's regulations; C.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; D.

There is reasonable assurance: (i) that the activities authorized by this subsequent renewed operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; NORTH ANNA UNIT 2 Subsequent Renewed License No. NPF-7 E.

VEPCO is technically and financially qualified to engage in the activities authorized by this subsequent renewed operating license in accordance with the rules and regulations of the Commissions regulations set forth in 10 CFR Chapter I; F.

VEPCO and the Old Dominion Electric Cooperative (ODEC) have satisfied the applicable provisions of 10 CFR Part 140, of the Commission's regulations; G.

The issuance of this subsequent renewed operating license will not be inimical to the common defense and security or to the health and safety of the public; H.

After weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Subsequent Renewed Facility Operating License No. NPF-7, subject to the conditions for protection of the environment set forth herein, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; I.

The receipt, possession, and use of source, byproduct, and special nuclear material as authorized by this subsequent renewed license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40, and 70; and J.

ODEC is a partial financial owner of the facility and will not operate the facility.

2.

On the basis of the foregoing findings regarding this facility, Renewed Facility Operating License No. NPF-7, issued on March 20, 2003, is superseded by Subsequent Renewed Facility Operating License No. NPF-7, which is hereby issued to VEPCO and ODEC to read as follows:

A.

This subsequent renewed license applies to the North Anna Power Station, Unit No. 2, a pressurized water reactor and associated equipment (the facility), owned by VEPCO and ODEC. The facility is located near Mineral, in Louisa County, Virginia, and is described in VEPCOs Updated Final Safety Analysis Report and the Environmental Report as supplemented and amended.

B.

Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:

(1)

Pursuant to Section 103 of the Act and 10 CFR Part 50, VEPCO and ODEC to possess and VEPCO to use and operate the facility at the designated location in Louisa County, Virginia, in accordance with the procedures and limitations set forth in this subsequent renewed license; (2)

Pursuant to the Act and 10 CFR Part 70, VEPCO to receive, possess, and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in VEPCOs Updated Final Safety Analysis Report; NORTH ANNA - UNIT 2 Subsequent Renewed License No. NPF-7 (3)

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material, without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or component; and (5)

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, VEPCO to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C.

This subsequent renewed license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations as set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level VEPCO is authorized to operate the facility at steady state reactor core power levels not in excess of 2940 megawatts (thermal).

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 280 are hereby incorporated in the subsequent renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3)

Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the condition or within the operational restrictions indicated.

The removal of these conditions shall be made by an amendment to the subsequent renewed license, supported by a favorable evaluation by the Commission:

a. If VEPCO plans to remove or to make significant changes in the normal operation of equipment that controls the amount of radioactivity in effluents from the North Anna Power Station, the NORTH ANNA - UNIT 2 Subsequent Renewed License No. NPF-7 NRC shall be notified in writing regardless of whether the change affects the amount of radioactivity in the effluents.

VEPCO shall report any violations of this requirement within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegram, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate, no later than the first working day following the violation, with a written follow-up report within 14 days.

b. The licensee shall implement a procedure that will prohibit entry into an extended Emergency Diesel Generator Outage Time (14 days),

for scheduled maintenance purposes, if severe weather conditions are expected, as described in the licensee's application dated June 25, 1998, and evaluated in the staffs Safety Evaluation dated August 26, 1998.

c. The licensee is authorized to relocate certain Technical Specification requirements previously included in Appendix A to licensee-controlled documents, as described in Table R, Relocated Specifications and Removed Details, attached to the NRC staffs Safety Evaluation enclosed with Amendment No. 212.

These requirements shall be relocated to the appropriate documents no later than September 2, 2002.

d. The schedule for performing surveillance requirements (SRs) that are new or revised in Amendment No. 212 shall be as follows:

For SRs that are new in this amendment, the first performance is due at the end of the first surveillance interval that begins on the date of implementation of this amendment.

For SRs that existed prior to this amendment whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of this amendment.

For SRs that existed prior to this amendment that have modified acceptance criteria, the first performance subject to the modified acceptance criteria is due at the end of the first surveillance interval that began on the date the surveillance was last performed prior to the implementation of this amendment.

For SRs that existed prior to this amendment whose intervals of performance are being extended, the first extended surveillance NORTH ANNA UNIT 2 Subsequent Renewed License No. NPF-7 interval begins upon completion of the last surveillance performed prior to implementation of this amendment.

This license condition is effective as of its date of issuance.

e. VEPCO may operate one lead test assembly containing advanced zirconium-based alloys for one cycle, to a lead rod burn-up not exceeding 75,000 MWD/MTU, as described in the licensee's submittal dated February 11, 2002.

f. Upon implementation of Amendment No. 232. adopting TSTF-448, Revision 3, the determination of Main Control Room/Emergency Switchgear Room (MCR/ESGR) envelope unfiltered air inleakage as required by TS SR 3.7.10.4 in accordance with TS 5.5.16.c(i),

the assessment of MCR/ESGR envelope habitability as required by Specification 5.5.16.c(ii), and the measurement of MCR/ESGR envelope pressure as required by Specification 5.5.16.d, shall be considered met. Following implementation:

(i) The first performance of SR 3.7.10.4 in accordance with Specification 5.5.16.c(i), shall be within the specified frequency of 6 years plus the 18-month allowance of SR 3.0.2, as measured from September 21, 2003, the date of the most recent successful tracer gas test, as stated in the March 30, 2004 letter response to Generic Letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.

(ii) The first performance of the periodic assessment of MCR/ESGR envelope habitability, Specification 5.5.16.c(ii),

shall be within 3 years, plus the 9-month allowance of SR 3.0.2, as measured from September 21, 2003, the date of the most recent successful tracer gas test, as stated in the March 31, 2004 letter response to Generic Letter 2003-01, or within the next 9 months if the time period since the most recent successful tracer gas test is greater than 3 years.

(iii) The first performance of the periodic measurement of MCR/ESGR envelope pressure, Specification 5.5.16.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from February 27, 2007, the date of the most recent successful pressure measurement test, or within 138 days if not performed previously.

NORTH ANNA - UNIT 2 Subsequent Renewed License No. NPF-7 (4)

The licensee is authorized to receive from the Surry Nuclear Power Station, Unit Nos. 1 and 2, possess, and store irradiated Surry Power Station fuel assemblies containing special nuclear material, enriched to not more than 4.1 percent by weight U-235, subject to the following conditions:

a. Surry Power Station fuel assemblies may not be placed in North Anna Power Station, Unit Nos. 1 and 2, reactors.

b. Irradiated fuel shipped to North Anna Power Station shall have been removed from the Surry Power Station reactors no less than 730 days prior to shipment.

c. No more than 500 Surry Power Station irradiated fuel assemblies shall be received for storage at the North Anna Power Station, Unit Nos. 1 and 2, spent fuel pool.

(5)

Environmental Protection Plan The Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 178, is hereby incorporated in the subsequent renewed license. The licensee shall operate the facility in accordance with the Environmental Protection Plan.

D. Fire Protection VEPCO shall implement and maintain in effect all provisions of the approved fire protection program as described in the licensee's Updated Final Safety Analysis Report for the facility and as approved in the SER dated February 1979 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

E. Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Millstone, North Anna and Surry Power Stations' Security Plan, Training, and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program" with revisions submitted through May 15, 2006.

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved Kewaunee, Millstone, North Anna, and Surry Power Stations Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The CSP was approved by NORTH ANNA - UNIT 2 Subsequent Renewed License No. NPF-7 License Amendment No. 245, as supplemented by a change approved by License Amendment No. 258.

F.

Updated Final Safety Analysis Report (1)

The licensees Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on July 25, October 1, November 4, and December 2, 2002, describes certain future inspection activities to be completed before the period of extended operation. The licensee shall complete these activities no later than August 21, 2020, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

(2)

The UFSAR supplement as revised on July 25, October 1, November 4, and December 2, 2002, shall be included in the next scheduled update to the UFSAR required by 10 CFR 50.71(e)(4), following the issuance of the renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

G. Mitigation Strategy Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:

(1) Fire fighting response strategy with the following elements:

a. Pre-defined coordinated fire response strategy and guidance

b. Assessment of mutual aid fire fighting assets

c. Designated staging areas for equipment and materials

d. Command and control

e. Training of response personnel (2) Operations to mitigate fuel damage considering the following:

a. Protection and use of personnel assets

b. Communications

c. Minimizing fire spread

d. Procedures for implementing integrated fire response strategy

e. Identification of readily-available pre-staged equipment

f. Training on integrated fire response strategy

g. Spent fuel pool mitigation measures NORTH ANNA - UNIT 2 Subsequent Renewed License No. NPF-7 (3) Actions to minimize release to include consideration of:

a. Water spray scrubbing

b. Dose to onsite responders H.

COMMITMENT SCHEDULED COMPLETION DATE

1. Dominion will perform the final acceptance of the North Anna 2 uncertainty analysis to ensure the results are bounded by the statements contained in this LAR (Attachment 5 Section I.1.D.4.1 ).

Prior to operating above 2893 MWt (98.4% RTP).

2. Technical Requirements Manual (TRM) will be revised to include UFM administrative controls (Attachment 1 Section 3.0).

Prior to operating above 2893 MWt (98.4% RTP).

3. Procedures and documents for the new UFM (Attachment 5 Section I.1.D.1.1, I.1.H, and Vll.2.A).

Prior to operating above 2893 MWt (98.4% RTP).

4. Appropriate personnel will receive training on the UFM and affected procedures (Attachment 5 Sections I.1.D.1.1, Vll.2.A, and Vll.2.D).

Prior to operating above 2893 MWt (98.4% RTP).

5. Simulator changes and validation will be completed (Attachment 5 Section Vll.2.C).

Prior to operating above 2893 MWt (98.4% RTP).

6. Revise existing plant operating procedures related to temporary operation above full steady-state licensed power levels (Attachment 5 Section Vll.4).

Prior to operating above 2893 MWt (98.4% RTP).

7. Replace Steam Generator secondary manway bolts or change cumulative fatigue usage analysis to support using existing bolts for the licensed period for each unit (Attachment 5 Section IV.1.A.vi.2 and IV.1.B.ii).

Prior to exceeding 45 years of in-service use for each secondary manway bolt.

NORTH ANNA - UNIT 2 Subsequent Renewed License No. NPF-7 H.

(continued)

COMMITMENT SCHEDULED COMPLETION DATE

8. The impact of radiation effects on the EQ Program qualification requirements will be determined (Attachment 5 Section V.1.C).

Prior to operating above 2893 MWt (98.4% RTP).

9. The FAC Checkworks SFA models will be updated to reflect the MUR power uprate conditions (Attachment 5 Section IV.1.E.iii).

Prior to operating above 2893 MWt (98.4% RTP).

10. Dominion will determine the EQ-service life of the excore detectors.

(Attachment 5 Section II.2).

Prior to operating above 2893 MWt (98.4% RTP).

11. Verify bounding calibration test data and confirm that actual field performance meets the uncertainty bounds established for the instruments Prior to operating above 2893 MWt (98.4% RTP).

12. Confirm that the variation in the flow normalization factors over a 48-hour period is negligible and that the normalized venturi flows are an acceptable surrogate for the Ultrasonic Flow Meter flows during the 48-hour completion time Prior to any such use above 2893 MWt (98.4% RTP).

I.

Subsequent License Renewal License Conditions (1)

The information in the Updated Final Safety Analysis Report supplement submitted as required by 10 CFR 54.21(d), and revised during the application review process, and the licensees commitments listed in Appendix A of the Safety Evaluation Report Related to the Subsequent License Renewal of North Anna Power Station, Units 1 and 2, dated January 2022, are collectively the Subsequent License Renewal Updated Final Safety Analysis Report Supplement. This Supplement is henceforth part of the UFSAR which will be updated in accordance with 10 CFR 50.71(e).

As such, the licensee may make changes to the programs, activities, and commitments described in the Subsequent License Renewal Updated Final Safety Analysis Report Supplement, provided the licensee evaluates such changes pursuant to 10 CFR 50.59, Changes, Tests and Experiments, and otherwise complies with the requirements in that section.

(2)

This Subsequent License Renewal Updated Final Safety Analysis NORTH ANNA - UNIT 2 Subsequent Renewed License No. NPF-7 Report Supplement, as defined in subsequent renewed license condition [1] above, describes programs to be implemented and activities to be completed before the subsequent period of extended operation, which is the period following the August 21, 2040, expiration of the initial renewed license.

a.

The licensee shall implement those new programs and enhancements to existing programs no later than the date 6 months before the subsequent period of extended operation.

b.

The licensee shall complete those activities by the date 6 months prior to the subsequent period of extended operation or by the end of the last refueling outage before the subsequent period of extended operation, whichever occurs later.

c.

The licensee shall notify the NRC in writing within 30 days after having accomplished item (a) above and include the status of those activities that have been or remain to be completed in item 2(b) above.

d.

The programs and commitments described in the Subsequent License Renewal Updated Final Safety Analysis Report Supplement shall continue in effect during the subsequent period of extended operation, to the extent set forth therein, unless modified in accordance with the process set forth in 10 CFR 50.59.

J.

This subsequent renewed license is effective as of the date of issuance and shall expire at midnight on August 21, 2060.

FOR THE NUCLEAR REGULA TORY COMMISSION R/A Andrea D. Veil, Director Office of Nuclear Reactor Regulation Attachments:

1.

Appendix A, Technical Specifications

2.

Appendix B, Environmental Protection Plan Date of Issuance: August 28, 2024