Text

Issuance of Amendments to Revise Restrictive Technical Specification Surveillance Requirement Frequencies
	ML23241A987
Person / Time
Site:	Oconee, Mcguire, Catawba, Harris, Robinson, McGuire
Issue date:	10/24/2023
From:	Shawn Williams; NRC/NRR/DORL/LPL2-2
To:	Gibby S; Duke Energy
References
	EPID L 2023-LLA-0015
	Download: ML23241A987 (53)
	v • d • e

October 24, 2023 Mr. Shawn Gibby Vice President Nuclear Engineering Duke Energy 526 South Church Street, EC-07H Charlotte, NC 28202

SUBJECT:

CATAWBA NUCLEAR STATION, UNIT NOS. 1 AND 2; SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1; MCGUIRE NUCLEAR STATION, UNIT NOS. 1 AND 2; OCONEE NUCLEAR STATION, UNIT NOS. 1, 2, AND 3; AND H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 - ISSUANCE OF AMENDMENTS TO REVISE RESTRICTIVE TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT FREQUENCIES (EPID L-2023-LLA-0015)

Dear Mr. Gibby:

The U.S. Nuclear Regulatory Commission (NRC, the Commission) has issued the following enclosed Amendment Nos. 318 and 314 to Renewed Facility Operating License Nos. NPF-35 and NPF-52 for the Catawba Nuclear Station, Unit Nos. 1 and 2, (Catawba) respectively; Amendment No. 200 to Renewed Facility Operating License No. NPF-63 for the Shearon Harris Nuclear Power Plant, Unit No. 1 (Harris); Amendment Nos. 329 and 308 to Renewed Facility Operating License Nos. NPF-9 and NPF-17 for the McGuire Nuclear Station, Unit Nos. 1 and 2, (McGuire) respectively; Amendment Nos. 429, 431, and 430 to Renewed Facility Operating License Nos. DPR-38, DPR-47, and DPR-55 for the Oconee Nuclear Station, Unit Nos. 1, 2, and 3, (Oconee) respectively; and Amendment No. 278 to Renewed Facility Operating License No. DPR-23 for the H. B. Robinson Steam Electric Plant, Unit No. 2 (Robinson).

The license amendments consist of changes to the technical specifications (TSs) in response to your application dated February 1, 2023, as supplemented by letter dated July 7, 2023. The amendments revise the surveillance requirement (SR) frequency for reactor coolant system pressure isolation valve operational leakage testing to reflect being in accordance with the inservice testing program, as governed by 10 CFR 50.55a. Specifically, this change would update TS SR 3.4.14.1 for Catawba, McGuire, Oconee, and Robinson and TS SR 4.4.6.2.2 for Harris. In addition, for Catawba and McGuire TS SR 3.3.1.8, Duke Energy removed restrictive surveillance frequency content that impedes the full application of the surveillance frequency control program to establish the frequency for performance of the channel operational test of select reactor trip system instrumentation.

A copy of the NRC staffs safety evaluation is also enclosed. The Notice of Issuance will be included in the Commissions monthly Federal Register notice.

If you have any questions, please contact me at (301) 415-1009 or by e-mail at Shawn.Williams@nrc.gov.

Sincerely,

/RA/

Shawn A. Williams, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.: 50-413, 50-414, 50-400, 50-369, 50-370, 50-269, 50-270, 50-287, and 50-261

Enclosures:

1. Amendment No. 318 to NPF-35 (Catawba 1)

2. Amendment No. 314 to NPF-52 (Catawba 2)

3. Amendment No. 200 to DPR-63 (Harris 1)

4. Amendment No. 329 to NPF-9 (McGuire 1)

5. Amendment No. 308 to NPF-17 (McGuire 2)

6. Amendment No. 429 to DPR-38 (Oconee 1)

7. Amendment No. 431 to DPR-47 (Oconee 2)

8. Amendment No. 430 to DPR-55 (Oconee 3)

9. Amendment No. 278 to DPR-23 (Robinson 2)

10. Safety Evaluation cc: Listserv

DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 318 Renewed License No. NPF-35

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment filed by Duke Energy Carolinas, LLC (the licensee), dated February 1, 2023, as supplemented on July 7, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-35 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 318, which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating Licenses and Technical Specifications Date of Issuance: October 24, 2023 David J.

Wrona Digitally signed by David J. Wrona Date: 2023.10.24 09:56:39 -04'00'

DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 314 Renewed License No. NPF-52

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment filed by the Duke Energy Carolinas, LLC (the licensee), dated February 1, 2023, as supplemented on July 7, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-52 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 314, which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC, shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating Licenses and Technical Specifications Date of Issuance: October 24, 2023 David J.

Wrona Digitally signed by David J. Wrona Date: 2023.10.24 09:57:08 -04'00'

ATTACHMENT TO DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT NO. 318 RENEWED FACILITY OPERATING LICENSE NO NPF-35 AND DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT NO. 314 RENEWED FACILITY OPERATING LICENSE NO. NPF-52 Replace the following pages of the Renewed Facility Operating Licenses with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert NPF-35, Page 4 NPF-35, Page 4 NPF-52, Page 4 NPF-52, Page 4 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 3.3.1-11 3.3.1-11 3.4.14-3 3.4.14-3 3.4.14-4 N/A Renewed License No. NPF-35 Amendment No. 318 (2)

TECHNICAL SPECIFICATION The Technical Specifications contained in Appendix A, as revised through Amendment No. 318, which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC shall operate the facility in accordance with the Technical Specifications.

(3)

Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation. Duke shall complete these activities no later than December 6, 2024, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4), following issuance of this renewed operating license. Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

(4)

Antitrust Conditions Duke Energy Carolinas, LLC shall comply with the antitrust conditions delineated in Appendix C to this renewed operating license.

(5)

Fire Protection Program Duke Energy Carolinas, LLC shall implement and maintain in effect all provisions of the approved fire protection program that complies with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment request dated September 25, 2013; as supplemented by letters dated January 13, 2015; January 28, 2015; February 27, 2015; March 30, 2015; April 28, 2015; July 15, 2015; August 14, 2015; September 3, 2015; December 11, 2015; January 7, 2016; March 23, 2016; June 15, 2016; August 2, 2016; September 7, 2016; and January 26, 2017, as approved in the SE dated February 8, 2017. Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.

Renewed License No. NPF-52 Amendment No. 314 (2)

TECHNICAL SPECIFICATION The Technical Specifications contained in Appendix A, as revised through Amendment No. 314, which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC shall operate the facility in accordance with the Technical Specifications.

(3)

Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation. Duke shall complete these activities no later than December 6, 2024, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4),

following issuance of this renewed operating license. Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

(4)

Antitrust Conditions Duke Energy Carolinas, LLC shall comply with the antitrust conditions delineated in Appendix C to this renewed operating license.

(5)

Fire Protection Program Duke Energy Carolinas, LLC shall implement and maintain in effect all provisions of the approved fire protection program that complies with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment request dated September 25, 2013, as supplemented by letters dated January 13, 2015; January 28, 2015; February 27, 2015; March 30, 2015; April 28, 2015; July 15, 2015; August 14, 2015; September 3, 2015; December 11, 2015; January 7, 2016; March 23, 2016; June 15, 2016; August 2, 2016; September 7, 2016; and, January 26, 2017, as approved in the SE dated February 8, 2017. Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c),

the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

Catawba Units 1 and 2 3.3.1-11 Amendment Nos. 318/314 SURVEILLANCE FREQUENCY SR 3.3.1.8

NOTE--------------------------------

This Surveillance shall include verification that interlocks P-6 (for the Intermediate Range channels) and P-10 (for the Power Range channels) are in their required state for existing unit conditions.

Perform COT.

NOTE-------

Only required when not performed within the Frequency specified in the Surveillance Frequency Control Program Prior to reactor startup AND Four hours after reducing power below P-10 for power and intermediate range instrumentation AND Four hours after reducing power below P-6 for source range instrumentation AND In accordance with the Surveillance Frequency Control Program (continued)

RCS PIV Leakage 3.4.14 Catawba Units 1 and 2 3.4.14-3 Amendment Nos. 318/314 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 -------------------------------NOTES---------------------------------

1.

Not required to be performed in MODES 3 and 4.

2.

Not required to be performed on the RCS PIVs located in the RHR flow path when in the shutdown cooling mode of operation.

3.

RCS PIVs actuated during the performance of this Surveillance are not required to be tested more than once if a repetitive testing loop cannot be avoided.

Verify leakage from each RCS PIV is equivalent to < 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm at an RCS pressure > 2215 psig and < 2255 psig.

In accordance with the INSERVICE TESTING PROGRAM

SR 3.4.14.2 Verify RHR system interlock prevents the valves from being opened with a simulated or actual RCS pressure signal > 425 psig.

In accordance with the Surveillance Frequency Control Program

DUKE ENERGY PROGRESS, LLC DOCKET NO. 50-400 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 200 Renewed License No. NPF-63

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Duke Energy Progress, LLC (the licensee),

dated February 1, 2023, as supplemented on July 7, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment 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; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-63 is hereby amended to read as follows:

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 200, are hereby incorporated into this license. Duke Energy Progress, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: October 24, 2023 David J.

Wrona Digitally signed by David J. Wrona Date: 2023.10.24 09:57:41 -04'00'

ATTACHMENT TO DUKE ENERGY PROGRESS, LLC DOCKET NO. 50-400 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 AMENDMENT NO. 200 RENEWED FACILITY OPERATING LICENSE NO. NPF-63 Replace the following page of the Renewed Facility Operating License with the revised page.

The revised page is identified by amendment number and contains a marginal line indicating the area of change.

Remove Insert NPF-63, Page 4 NPF-63, Page 4 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 3/4 4-24 3/4 4-24 3/4 4-25 3/4 4-25 Renewed License No. NPF-63 Amendment No. 200 C.

This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations 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 Duke Energy Progress, LLC, is authorized to operate the facility at reactor Core power levels not in excess of 2948 megawatts thermal (100 percent rated core power) in accordance with the conditions specified herein.

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 200, are hereby incorporated into this license. Duke Energy Progress, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

Antitrust Conditions Duke Energy Progress, LLC. shall comply with the antitrust conditions delineated in Appendix C to this license.

(4)

Initial Startup Test Program (Section 14)1 Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.

(5)

Steam Generator Tube Rupture (Section 15.6.3)

Prior to startup following the first refueling outage, Carolina Power & Light Company* shall submit for NRC review and receive approval if a steam generator tube rupture analysis, including the assumed operator actions, which demonstrates that the consequences of the design basis steam generator tube rupture event for the Shearon Harris Nuclear Power Plant are less than the acceptance criteria specified in the Standard Review Plan, NUREG-0800, at 15.6.3 Subparts II (1) and (2) for calculated doses from radiological releases. In preparing their analysis Carolina Power &

Light Company* will not assume that operators will complete corrective actions within the first thirty minutes after a steam generator tube rupture.

1The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

On April 29, 2013, the name of Carolina Power & Light Company (CP&L) was changed to Duke Energy Progress, Inc. On August 1, 2015, the name Duke Energy Progress, Inc. was changed to Duke Energy Progress, LLC.

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady-state operation. Not applicable to primary-to-secondary leakage.

- Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady-state operation.

SHEARON HARRIS - UNIT 1 3/4 4-24 Amendment No. 200 REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE SURVEILLANCE REQUIREMENTS 4.4.6.2.1 Reactor Coolant System operational leakages shall be demonstrated, at the frequency specified in the Surveillance Frequency Control Program, to be within each of the above limits by:

a.

Monitoring the containment Airborne Gaseous or Particulate Radioactivity Monitor; b.

Monitoring the containment sump inventory and Flow Monitoring System; c.

Measurement of the CONTROLLED LEAKAGE to the reactor coolant pump seals when the Reactor Coolant System pressure is 2235 +/- 20 psig with the modulating valve fully open. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4; d.

Performance of a Reactor Coolant System water inventory balance*; and e.

Monitoring the Reactor Head Flange Leakoff System.

4.4.6.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE by verifying leakage to be within its limit:

a.

In accordance with the INSERVICE TESTING PROGRAM.

b.

(DELETED) c.

(DELETED) d.

(DELETED)

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

4.4.6.2.3 Primary-to-secondary leakage shall be verified to be 150 gallons per day through any one steam generator at the frequency specified in the Surveillance Frequency Control Program**.

SHEARON HARRIS - UNIT 1 3/4 4-25 Amendment No. 200 TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES EBASCO VALVE NUMBER CP&L VALVE NUMBER TYPE FUNCTION MAXIMUM ALLOWABLE LEAKAGE 1-RH-V502-SB-1 1RH1 12" Gate RHR Pump Suction 5 gpm 1-RH-V503-SA-1 1RH2 12" Gate RHR Pump Suction 5 gpm 1-RH-V500-SB-1 1RH39 12" Gate RHR Pump Suction 5 gpm 1-RH-V501-SA-1 1RH40 12" Gate RHR Pump Suction 5 gpm 1-SI-V510-SA-1 1SI134 6" Check Low Head Injection (Hot Leg) 3 gpm 1-SI-V511-SB-1 1SI135 6" Check Low Head Injection (Hot Leg) 3 gpm 1-SI-V544-SA-1 1SI249 12" Check Accumulator Injection 5 gpm 1-SI-V547-SA-1 1SI250 12" Check Accumulator Injection 5 gpm 1-SI-V545-SB-1 1SI251 12" Check Accumulator Injection 5 gpm 1-SI-V548-SB-1 1SI252 12" Check Accumulator Injection 5 gpm 1-SI-V546-SA-1 1SI253 12" Check Accumulator Injection 5 gpm 1-SI-V549-SA-1 1SI254 12" Check Accumulator Injection 5 gpm 2-SI-V581-SA-1 1SI346 10" Check Low Head Injection 5 gpm 2-SI-V580-SB-1 1SI347 10" Check Low Head Injection 5 gpm 1-SI-V584-SA-1 1SI356 6" Check Low Head Injection 3 gpm 1-SI-V585-SB-1 1SI357 6" Check Low Head Injection 3 gpm 1-SI-V586-SA-1 1SI358 6" Check Low Head Injection 3 gpm 1-SI-V587-SA-1 1SI359 10" Gate Hot Leg Recirculation 5 gpm

DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-369 MCGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 329 Renewed License No. NPF-9

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Duke Energy Carolinas, LLC (the licensee),

dated February 1, 2023, as supplemented on July 7, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment 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; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-9 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 329, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating Licenses and Technical Specifications Date of Issuance: October 24, 2023 David J.

Wrona Digitally signed by David J. Wrona Date: 2023.10.24 09:58:10 -04'00'

DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-370 MCGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 308 Renewed License No. NPF-17

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Duke Energy Carolinas, LLC (the licensee), dated February 1, 2023, as supplemented on July 7, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations as set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-17 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 308, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating Licenses and Technical Specifications Date of Issuance: October 24, 2023 David J.

Wrona Digitally signed by David J. Wrona Date: 2023.10.24 09:58:32 -04'00'

ATTACHMENT TO DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-369 MCGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT NO. 329 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 AND DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-370 MCGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT NO. 308 RENEWED FACILITY OPERATING LICENSE NO. NPF-17 Replace the following pages of the Renewed Facility Operating Licenses with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert NPF-9, Page 3 NPF-9, Page 3 NPF-17, Page 3 NPF-17, Page 3 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 3.3.1-1 1 3.3.1-11 3.4.14-3 3.4.14-3 3.4.14-4 N/A

Renewed License No. NPF-9 Amendment No. 329 (4)

Pursuant to the Act and 10 CFR Parts 30, 40 and 70, 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 components; (5)

Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of McGuire Nuclear Station, Units 1 and 2, and; (6)

Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.

C.

This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations 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 The licensee is authorized to operate the facility at a reactor core full steady state power level of 3469 megawatts thermal (100%).

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 329, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3)

Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation.

Duke shall complete these activities no later than June 12, 2021, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4), following issuance of this renewed operating license.

Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

Renewed License No. NPF-17 Amendment No. 308 (4)

Pursuant to the Act and 10 CFR Parts 30, 40 and 70, 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 components; (5)

Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of McGuire Nuclear Station, Units 1 and 2, and; (6)

Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.

C.

This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations 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 The licensee is authorized to operate the facility at a reactor core full steady state power level of 3469 megawatts thermal (100%).

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 308, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3)

Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation.

Duke shall complete these activities no later than March 3, 2023, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4), following issuance of this renewed operating license.

Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

McGuire Units 1 and 2 3.3.1-11 Amendment Nos. 329/308 SURVEILLANCE FREQUENCY SR 3.3.1.8

NOTES----------------------------------

This Surveillance shall include verification that interlocks P-6 (for the Intermediate Range channels) and P-10 (for the Power Range channels) are in their required state for existing unit conditions.

Perform COT.

NOTE-------

Only required when not performed within the Frequency specified in the Surveillance Frequency Control Program Prior to reactor startup AND Four hours after reducing power below P-10 for power and intermediate range instrumentation AND Four hours after reducing power below P-6 for source range instrumentation AND In accordance with the Surveillance Frequency Control Program (continued)

RCS PIV Leakage 3.4.14 McGuire Units 1 and 2 3.4.14-3 Amendment Nos. 329/308 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 ------------------------------NOTE------------------------------------

1.

Not required to be performed in MODES 3 and 4.

2.

Not required to be performed on the RCS PIVs located in the RHR flow path when in the shutdown cooling mode of operation.

3.

RCS PIVs actuated during the performance of this Surveillance are not required to be tested more than once if a repetitive testing loop cannot be avoided.

Verify leakage from each RCS PIV is equivalent to < 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm at an RCS pressure > 2215 psig and < 2255 psig.

In accordance with the INSERVICE TESTING PROGRAM SR 3.4.14.2 Verify RHR system interlock prevents the valves from being opened with a simulated or actual RCS pressure signal > 425 psig.

In accordance with the Surveillance Frequency Control Program

DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 429 Renewed License No. DPR-38

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Duke Energy Carolinas, LLC (the licensee),

dated February 1, 2023, as supplemented on July 7, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations as set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Renewed Facility Operating License No. DPR-38 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 429 are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating Licenses and Technical Specifications Date of Issuance: October 24, 2023 David J.

Wrona Digitally signed by David J. Wrona Date: 2023.10.24 09:58:58 -04'00'

DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 431 Renewed License No. DPR-47

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Duke Energy Carolinas, LLC (the licensee),

dated February 1, 2023, as supplemented on July 7, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations as set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment 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; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Renewed Facility Operating License No. DPR-47 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 431 are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating Licenses and Technical Specifications Date of Issuance: October 24, 2023 David J.

Wrona Digitally signed by David J. Wrona Date: 2023.10.24 09:59:29 -04'00'

DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 430 Renewed License No. DPR-55

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Duke Energy Carolinas, LLC (the licensee),

dated February 1, 2023, as supplemented on July 7, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Renewed Facility Operating License No. DPR-55 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 430 are hereby incorporated into the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating Licenses and Technical Specifications Date of Issuance: October 24, 2023 David J.

Wrona Digitally signed by David J. Wrona Date: 2023.10.24 09:59:52 -04'00'

ATTACHMENT TO DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT NO. 429 RENEWED FACILITY OPERATING LICENSE NO. DPR-38 AND DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT NO. 431 RENEWED FACILITY OPERATING LICENSE NO. DPR-47 AND DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT NO. 430 RENEWED FACILITY OPERATING LICENSE NO. DPR-55 Replace the following pages of the Renewed Facility Operating Licenses with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert DPR-38, Page 3 DPR-38, Page 3 DPR-47, Page 3 DPR-47, Page 3 DPR-55, Page 3 DPR-55, Page 3 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 3.4-14-3 3.4.14-3 Renewed License No. DPR-38 Amendment No. 429 A.

Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2610 megawatts thermal.

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 429 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

C.

This license is subject to the following antitrust conditions:

Applicant makes the commitments contained herein, recognizing that bulk power supply arrangements between neighboring entities normally tend to serve the public interest. In addition, where there are net benefits to all participants, such arrangements also serve the best interests of each of the participants. Among the benefits of such transactions are increased electric system reliability, a reduction in the cost of electric power, and minimization of the environmental effects of the production and sale of electricity.

Any particular bulk power supply transaction may afford greater benefits to one participant than to another. The benefits realized by a small system may be proportionately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability of participating in the transaction. Accordingly, applicant will enter into proposed bulk power transactions of the types hereinafter described which, on balance, provide net benefits to applicant. There are net benefits in a transaction if applicant recovers the cost of the transaction (as defined in ¶1 (d) hereof) and there is no demonstrable net detriment to applicant arising from that transaction.

1.

As used herein:

(a)

Bulk Power means electric power and any attendant energy, supplied or made available at transmission or sub-transmission voltage by one electric system to another.

(b)

Neighboring Entity means a private or public corporation, a governmental agency or authority, a municipality, a cooperative, or a lawful association of any of the foregoing owning or operating, or proposing to own or operate, facilities for the generation and transmission of electricity which meets each of Renewed License No. DPR-47 Amendment No. 431 A.

Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2610 megawatts thermal.

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 431 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

C.

This license is subject to the following antitrust conditions:

Applicant makes the commitments contained herein, recognizing that bulk power supply arrangements between neighboring entities normally tend to serve the public interest. In addition, where there are net benefits to all participants, such arrangements also serve the best interests of each of the participants. Among the benefits of such transactions are increased electric system reliability, a reduction in the cost of electric power, and minimization of the environmental effects of the production and sale of electricity.

Any particular bulk power supply transaction may afford greater benefits to one participant than to another. The benefits realized by a small system may be proportionately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability of participating in the transaction. Accordingly, applicant will enter into proposed bulk power transactions of the types hereinafter described which, on balance, provide net benefits to applicant. There are net benefits in a transaction if applicant recovers the cost of the transaction (as defined in ¶1 (d) hereof) and there is no demonstrable net detriment to applicant arising from that transaction.

2.

As used herein:

(b)

"Bulk Power" means electric power and any attendant energy, supplied or made available at transmission or sub-transmission voltage by one electric system to another.

(c)

"Neighboring Entity" means a private or public corporation, a governmental agency or authority, a municipality, a cooperative, or a lawful association of any of the foregoing owning or operating, or proposing to own or operate, facilities for the generation and transmission of electricity which meets each of Renewed License No. DPR-55 Amendment No. 430 A.

Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2610 megawatts thermal.

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 430 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

C.

This license is subject to the following antitrust conditions:

Applicant makes the commitments contained herein, recognizing that bulk power supply arrangements between neighboring entities normally tend to serve the public interest. In addition, where there are net benefits to all participants, such arrangements also serve the best interests of each of the participants. Among the benefits of such transactions are increased electric system reliability, a reduction in the cost of electric power, and minimization of the environmental effects of the production and sale of electricity.

Any particular bulk power supply transaction may afford greater benefits to one participant than to another. The benefits realized by a small system may be proportionately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability of participating in the transaction. Accordingly, applicant will enter into proposed bulk power transactions of the types hereinafter described which, on balance, provide net benefits to applicant. There are net benefits in a transaction if applicant recovers the cost of the transaction (as defined in ¶1 (d) hereof) and there is no demonstrable net detriment to applicant arising from that transaction.

3.

As used herein:

(d)

"Bulk Power" means electric power and any attendant energy, supplied or made available at transmission or sub-transmission voltage by one electric system to another.

(e)

"Neighboring Entity" means a private or public corporation, a governmental agency or authority, a municipality, a cooperative, or a lawful association of any of the foregoing owning or operating, or proposing to own or operate, facilities for the generation and transmission of electricity which meets each of

RCS PIV Leakage 3.4.14 OCONEE UNITS 1, 2, & 3 3.4.14-3 Amendment Nos. 429, 431, 430 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1

NOTE--------------------------

Not required to be performed in MODES 3 and 4.

Verify leakage from each required RCS PIV is equivalent to 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm at an RCS pressure 2150 psia and 2190 psia.

In accordance with the INSERVICE TESTING PROGRAM

DUKE ENERGY PROGRESS, LLC DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE NO. DPR-23 Amendment No. 278 Renewed License No. DPR-23

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Duke Energy Progress, LLC (the licensee),

dated February 1, 2023, as supplemented on July 7, 2023, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment 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; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 3.B. of Renewed Facility Operating License No. DPR-23 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 278 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 120 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION David J. Wrona, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: October 24, 2023 David J.

Wrona Digitally signed by David J. Wrona Date: 2023.10.24 10:00:16 -04'00'

ATTACHMENT TO DUKE ENERGY PROGRESS, LLC DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT UNIT 2 AMENDMENT NO. 278 RENEWED FACILITY OPERATING LICENSE NO. DPR-23 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert DPR-23, Page 3 DPR-23, Page 3 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 3.4-39 3.4-39 3.4-40 3.4-40 Renewed Facility Operating License No. DPR-23 Amendment No. 278 D.

Pursuant to the Act and 10 CFR Parts 30, 40 and 70, 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 and equipment calibration or associated with radioactive apparatus or components; E.

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

3.

This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; 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:

A.

Maximum Power Level The licensee is authorized to operate the facility at a steady state reactor core power level not in excess of 2339 megawatts thermal.

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 278 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(1)

For Surveillance Requirements (SRs) that are new in Amendment 176 to Final Operating License DPR-23, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 176. For SRs that existed prior to Amendment 176, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 176.

RCS PIVs 3.4.14 HBRSEP Unit No. 2 3.4-39 Amendment No. 278 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1

NOTES---------------------------

1.

Not required to be performed in MODES 3 and 4.

2.

Not required to be performed on the RCS PIVs located in the RHR flow path when in the shutdown cooling mode of operation.

3.

RCS PIVs actuated during the performance of this Surveillance are not required to be tested more than once if a repetitive testing loop cannot be avoided.

Verify leakage from each RCS PIV is less than or equal to an equivalent of 5 gpm at an RCS pressure 2235 psig, and verify the margin between the results of the previous leak rate test and the 5 gpm limit has not been reduced by 50% for valves with leakage rates > 1.0 gpm.

In accordance with the INSERVICE TESTING PROGRAM SR 3.4.14.2 Verify RHR System interlock prevents the valves from being opened with a simulated or actual RCS pressure signal > 474 psig.

In accordance with the Surveillance Frequency Control Program

RCS PIVs 3.4.14 HBRSEP Unit No. 2 3.4-40 Amendment No. 278 Page 3.4-40 has been deleted by Amendment No. 278

0 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO DUKE ENERGY CAROLINAS, LLC AND DUKE ENERGY PROGRESS, LLC CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413, 50-414 AMENDMENT NOS. 318 AND 314 TO RENEWED FACILITY OPERATING LICENSE NOS. NPF-35 AND NPF-52 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO.1 DOCKET NO. 50-400 AMENDMENT NO. 200 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-63 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369, 50-370 AMENDMENT NOS. 329 AND 308 TO RENEWED FACILITY OPERATING LICENSE NOS. NPF-9 AND NPF-17 OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-269, 50-270, 50-287 AMENDMENT NOS. 429, 431, AND 430 TO RENEWED FACILITY OPERATING LICENSE NOS. DPR-38, DPR-47, AND DPR-55 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 AMENDMENT NO. 278 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-23

1.0 INTRODUCTION

By application dated February 1, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML23032A162), as supplemented by letter dated July 7, 2023 (ML23188A176), Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC (Duke Energy or the licensee), requested changes to the Catawba Nuclear Station, Units 1 and 2 (Catawba),

McGuire Nuclear Station, Units 1 and 2 (McGuire), Oconee Nuclear Station, Units 1, 2, and 3 (Oconee), H.B. Robinson Steam Electric Plant, Unit No. 2 (Robinson), and Shearon Harris Nuclear Power Plant, Unit 1 (Harris) Technical Specifications (TSs).

The proposed changes would revise the TS Surveillance Requirement (SR) frequency for the reactor coolant system (RCS) pressure isolation valve (PIV) operational leakage testing to reflect being in accordance with the Inservice Testing Program, as governed by 10 CFR 50.55a.

Specifically, this change will update TS SR 3.4.14.1 for Catawba, McGuire, Oconee, and Robinson and TS SR 4.4.6.2.2 for Harris. An additional revision is proposed to Catawba and McGuire TS SR 3.3.1.8 to remove restrictive surveillance frequency content that impedes the full application of the surveillance frequency control program (SFCP) to establish the frequency for performance of the channel operational test of select reactor trip system instrumentation.

2.0 REGULATORY EVALUATION

2.1 Regulatory Requirements and Guidance Documents In Title 10 of the Code of Federal Regulations (10 CFR) 50.36, Technical specifications, the U.S. Nuclear Regulatory Commission (NRC) established its regulatory requirements related to the content of TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) SRs; (4) design features; and (5) administrative controls.

Section 50.36(c)(3) of 10 CFR states, [s]urveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.

NUREG-1430, Revision 5.0, Standard Technical Specifications, Babcock and Wilcox, Volume 1, Specifications, and Volume 2, Bases (ML21272A363 and ML21272A370, respectively) and NUREG 1431, Revision 5.0, Standard Technical Specifications, Westinghouse Plants, Volume 1, Specifications, and Volume 2, Bases (ML21259A155 and ML21259A159, respectively), contain the improved Standard Technical Specifications (STS) for Babcock and Wilcox and Westinghouse plants, respectively. The improved STS were developed based on the criteria in the Final Policy Statement of Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132), which was subsequently codified by changes to 10 CFR 50.36 (60 FR 36953).

Section 50.55a, Codes and standards, in 10 CFR in 50.55a(f)(4), Inservice testing standards requirement for operating plants, states, in part, that throughout the service life of a boiling or pressurized water-cooled nuclear power facility, pumps and valves that are within the scope of the American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants (OM) Code, Division 1 must meet the inservice testing (IST) requirements (except design and access provisions) set forth in the ASME OM Code and addenda that become effective subsequent to editions and addenda specified in 10 CFR 50.55a(f)(2) and (3) and that are incorporated by reference in 10 CFR 50.55a(a)(1)(iv), to the extent practical within the limitations of design, geometry, and materials of construction of the components.

Section 50.55a(f)(5)(ii), IST program update: Conflicting IST Code requirements with technical specifications, states, in part, that if a revised inservice test program for a facility conflict, with the TS for the facility, the licensee must apply for an amendment of the TS to conform the TS to the revised program.

Section 50.55a(z), Alternatives to codes and standards requirements, states the following:

Alternatives to the requirements of [§§ 50.55a(b)-(h)] or portions thereof may be used when authorized by the Director, Office of Nuclear Reactor Regulation. A proposed alternative must be submitted and authorized prior to implementation.

The applicant or licensee must demonstrate that:

(1) Acceptable level of quality and safety. The proposed alternative would provide an acceptable level of quality and safety; or (2) Hardship without a compensating increase in quality and safety.

Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

3.0 TECHNICAL EVALUATION

3.1 Licensees Proposed Changes - TS SR 3.4.14.1 (TS SR 4.4.6.2.2 for Harris)

The licensee proposed to revise the frequencies for the SRs to reflect the removal of the requirement that the surveillance be performed prior to entering MODE 2 when the unit has been in MODE 5 for 7 days or more, if leakage testing has not been performed in the previous 9 months. In addition, for those licenses with a requirement to perform the surveillance within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of valve actuation due to automatic or manual action or flow through the valve, the licensee proposed to remove that content. Further, content related to performing the surveillance at a frequency in accordance with the SFCP is proposed to be removed or replaced to reflect reliance upon the frequency established by the IST program for each site.

The Catawba and McGuire SR 3.4.14.1 will be revised to reflect a frequency of:

Frequency In accordance with the INSERVICE TESTING PROGRAM, and in accordance with the Surveillance Frequency Control Program AND Prior to entering MODE 2 whenever the unit has been in MODE 5 for 7 days or more, if leakage testing has not been performed in the previous 9 months AND Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve The Oconee SR 3.4.14.1 will be revised to reflect a frequency of:

Frequency In accordance with the Surveillance Frequency Control Program INSERVICE TESTING PROGRAM AND Prior to entering MODE 2 whenever the unit has been in MODE 5 for 7 days, if leakage testing has not been performed in the previous 9 months The Robinson SR 3.4.14.1 will be revised to reflect a frequency of:

Frequency In accordance with the INSERVICE TESTING PROGRAM and in accordance with the Surveillance Frequency Control Program AND Prior to entering MODE 2 whenever the unit has been in MODE 5 for 7 days or more, if leakage testing has not been performed in the previous 9 months AND Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve The Harris SR 4.4.6.2.2 will be revised as follows:

Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE by verifying leakage to be within its limit:

a. At the frequency specified in the Surveillance Frequency Control Program, In accordance with the INSERVICE TESTING PROGRAM.

b. Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage testing has not been performed in the previous 9 months, [DELETED]

c. Prior to returning the valve to service following maintenance, repair, or replacement work on the valve, and [DELETED]

d. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve. [DELETED]

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4.

Additionally, the proposed deletion of SR 4.4.6.2.2.b and SR 4.4.6.2.2.d will be reflected administratively in Harris TS Table 3.4-1 with the removal of the following note:

Specifications 4.4.6.2.2.b. and d. do not apply to these valves Section 1.1, Definitions, in each TS for INSERVICE TESTING PROGRAM is defined as The INSERVICE TESTING PROGRAM is the licensee program that fulfills the requirements of 10 CFR 50.55a(f).

The current TS SR 3.4.14.1 for Catawba, McGuire, Oconee and Robinson and TS SR 4.4.6.2.2 for Harris contain certain testing requirements that are also required by the ASME OM Code and are implemented in each sites respective IST Program. Performance of leakage rate testing for PIVs is per the requirements of the IST Program, which is governed by 10 CFR 50.55a. In its current state, the respective site TS SR points to the IST Program or SFCP as the basis for the testing frequency, which is currently on a reload frequency. Despite the IST Program Frequency being based on the requirements of the ASME OM Code incorporated by reference into 10 CFR 50.55a, the site TS SR reflect a requirement to test after any cold shutdown for 7 days or more, effectively restricting the ability of the IST Program and the SFCP to govern the frequency of leakage testing. The proposed change to each sites TS SR Frequency would ensure ASME OM Code testing requirements for the RCS PIVs will be retained in the IST Program and duplicative testing requirements in the TS SR will be removed.

In a supplemental letter dated July 7, 2023, the licensee stated that all the PIVs currently required to be tested in accordance with each sites respective TS SR are included within their respective IST Program. The licensee indicated that the focus of this license amendment request (LAR) is to align the performance of the TS surveillance related to RCS PIV operational leakage with the frequency of the leakage testing required in accordance with the IST Program for each site, as based on the applicable edition and addenda of the ASME OM Code incorporated by reference in 10 CFR 50.55a. The licensee further indicated that, aside from the proposed change in testing frequency for the RCS PIVs, the current test method requirements of the TS surveillance remain unchanged, as no new leakage requirements are being added or removed. The licensee also indicated that the valves will continue to be required to meet the leakage limits provided within their respective TS SR.

The licensee describes the PIV testing regime as follows: Per ASME OM Code, Subsection ISTC, Inservice Testing of Valves in Water-Cooled Reactor Nuclear Power Plants, paragraph ISTC-3630 subparagraph (a), leakage rate testing for PIVs is required to be performed at least once every 2 years. The IST Programs for Catawba, Harris and Robinson reflect a frequency of testing the RCS PIVs within a 2-year period. The IST Program for Oconee reflects a frequency of testing the Core Flood RCS PIVs at a frequency of every cold shutdown and the low-pressure injection RCS PIVs at a frequency of once every two years. The IST Program for McGuire reflects a frequency of Per Tech Spec for testing the RCS PIVs. Upon issuance of the license amendment, the IST Program document will be revised to reflect the ISTC-3630 subparagraph (a) frequency of testing the RCS PIVs at least once every 2 years, as based on the ASME OM Code - 2004 Edition through 2006 Addenda reflected in the McGuire IST Program for the fourth 10-year interval (ML13078A009).

The licensee further describes, in part, that for each site except Oconee, the TS also includes a requirement to perform this surveillance within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valve. Although this specification provides a limit on allowable PIV leakage rate, its main purpose is to prevent overpressure failure of the low-pressure portions of connecting systems that would result from gross failure of the associated PIVs. The leakage limit is a measure indicating that the PIVs between the RCS and the connecting systems are degraded or degrading. As such, performing the valve leakage test in conjunction with the other valve tests specified in the ASME OM Code (e.g., exercise testing per ASME OM Code Subsection ISTC, paragraph ISTC-3520 and position indication verification per ASME OM Code Subsection ISTC, paragraph ISTC-3700) provides an acceptable method of determining valve integrity. In removing the frequency requiring performance of leakage testing within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation due to automatic or manual action or flow through the valves, the site will instead test at a frequency in accordance with the IST Program, which reinforces the established requirements of the OM Code that are endorsed by the NRC and incorporated by reference in 10 CFR 50.55a(a)(1)(iv).

For Harris only, there is a requirement that leakage be verified to be within its limit prior to returning the valve to service following maintenance, repair, or replacement work on the valve.

This is redundant to the requirement in ASME OM Code Subsection ISTC, paragraph ISTC-3310, that an inservice test be run when a valve or its control system has been replaced, repaired, or undergone maintenance that could affect the valves performance before it can be returned to service.

In Enforcement Guidance Memorandum (EGM) 12-001, Dispositioning Noncompliance with Administrative Controls Technical Specifications Programmatic Requirements that Extend Test Frequencies and Allow Performance of Missed Tests (ML11258A243), NRC staff determined that if a licensee finds that the requirements of TS conflict with the requirements of 10 CFR 50.55a, then the licensee must amend their TS to comply with 10 CFR 50.55a. The position related to conflicting requirements between TS and 10 CFR 50.55a is governed by 10 CFR 50.55a(f)(5)(ii), IST program update: Conflicting IST Code requirements with technical specifications, which requires, in part, that if a revised IST Program for a facility conflicts with the TS for the facility, the licensee must apply for an amendment of the TS to conform the TS to the revised program. The proposed change is therefore consistent with NRC staff positions and regulations with respect to conflicting requirements.

In updating the surveillance frequencies for verifying RCS PIV leakage to remove the restrictive and redundant requirements, the surveillance frequencies would instead be in accordance with the IST Program, which is required by regulation per both 10 CFR 50.54, Condition of licenses, and 10 CFR 50.55a(f). Specifically, paragraph (jj) of 10 CFR 50.54 states that structures, systems, and components (SSCs) subject to the codes and standards in 10 CFR 50.55a must be designed, fabricated, erected, constructed, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed.

Paragraph 10 CFR 50.55a(f)(4), lnservice testing standard requirement for operating plants Requirements, requires, in part, that IST of pumps and valves that are within the scope of the ASME OM Code must meet the requirements of the ASME OM Code incorporated by reference in the regulations. Exceptions are allowed where alternatives have been authorized by the NRC pursuant to paragraphs 10 CFR 50.55a(z)(1) and 10 CFR 50.55a(z)(2).

The licensee noted that the proposed change to each sites respective TS SR Frequency for RCS PIV leakage testing would not impact the TS PIV allowable leakage limits at each site (i.e.,

the parameter being measures). With the proposed change, testing of the RCS PIVs would still be performed in accordance with the IST Program in order to provide a means of assessing whether the PIVs between the RCS and the connecting systems are degraded or degrading.

The licensee stated that in aligning the frequency of the RCS PIV leakage verification SR with the IST Program, it allows for the potential to stay aligned with updates in regulations afforded by 10 CFR 50.55a(b). Paragraph (b)(6) of 10 CFR 50.55a allows for the application of the ASME Code Cases listed in Regulatory Guide 1.192, Operation and Maintenance Code Case Acceptability, ASME OM Code, without prior NRC approval subject to the conditions listed in 10 CFR 50.55a(b)(6), paragraphs (i) through (iii).

NRC Staffs Evaluation The NRC staff evaluated the information provided in the LAR. The NRC staff finds that the proposed changes to each sites TS SR Frequency would ensure ASME OM Code testing requirements for the RCS PIVs will be retained in the IST Program and duplicative testing requirements in the TS SR will be removed. Accordingly, the proposed TS SR Frequency change to INSERVICE TESTING PROGRAM, is consistent with the previously approved TSTF-545, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing (ML15294A555). In addition, the NRC staff has determined that the TS requirement to perform leakage testing within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation is directed to the same end as testing at a frequency in accordance with the IST Program, which meets the established requirements of the OM Code that are incorporated by reference in 10 CFR 50.55a(a)(1)(iv). Accordingly, the NRC staff finds that the requirement for leakage testing within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve actuation is unnecessary and may be deleted from the TS. For Harris only, the NRC staff finds that the licensee will still be required to meet the requirement in ASME OM Code Subsection ISTC, paragraph ISTC-3310, that an inservice test be run when a valve or its control system has been replaced, repaired, or undergone maintenance that could affect the valves performance before it can be returned to service and the deletion of the corresponding requirement from the TS is acceptable.

The NRC staff also finds that the proposed changes are consistent with NRC staff positions in EGM 12-001 and the requirements in the regulations with respect to conflicting requirements, specifically, 10 CFR 50.55a(f)(5)(ii), IST program update: Conflicting IST Code requirements with technical specifications.

In a letter dated July 7, 2023, the licensee stated that the current IST Programs for CNS, HNP RNP and ONS reflect testing frequency of all PIVs as required by the applicable ASME OM Code - 2004 Edition through 2006 Addenda for the Fourth 10-Year Interval. The IST Program for MNS reflects a frequency of Per TECH Spec for testing the RCS PIVS. Upon issuance of the license amendment, the IST Program document will be revised to reflect the ISTC-3630 subparagraph (a) frequency of testing the RCS PIVs at least once every 2 years, as based on the ASME OM Code - 2004 Edition through 2006 Addenda reflected in the IST Program for the Fourth 10-Year Interval (ML13078A009), which is equivalent to the current TS inspection frequency and therefore acceptable. Therefore, the NRC staff finds the licensees request acceptable, because the SR remains in compliance with the requirement specified in 10 CFR 50.36(c)(3).

3.2 Licensees Proposed Changes - TS SR 3.3.1.8 (McGuire and Catawba)

The note associated with the frequency of Catawba and McGuire SR 3.3.1.8 will be revised to reflect the removal of content related to the previous 184 days as follows:

Frequency

NOTE--------------------------------------------

Only required when not performed within the Frequency specified in the Surveillance Frequency Control Program or [the] previous 184 days The NRC issued license amendments to McGuire and Catawba allowing for the relocation of specific surveillance frequencies to the SFCP, which is a licensee-controlled program. In relocating these surveillance frequencies, changes could be made in accordance with NEI 04-10, Revision 1, Risk-Informed Technical Specifications Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies, April 2007 (ML071360456). The amendments (Amendment Nos. 263 and 259 for Catawba and Amendment Nos. 261 and 241 for McGuire) granted LARs based on NRC-approved TSTF-425, Revision 3, Relocation Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF)

Initiative 5b (ML090850642). In terms of which surveillance frequencies could be relocated to the SFCP, TSTF-425 established that all surveillance frequencies could be relocated except those that: (1) reference other approved programs for the specific interval; (2) are purely event-driven; (3) are event-driven but have a time component for performing the surveillance on a one-time basis once the event occurs; and (4) are related to specific conditions or conditions for the performance of a SR. TSTF-425 also established that the surveillance frequency associated with the performance of a channel operational test (COT) in NUREG-1431 ISTS SR 3.3.1.8 could be relocated to the SFCP.

While TSTF-425 relocated the 184-day surveillance frequency for performance of the COT from ISTS SR 3.3.1.8 to the SFCP, these amendments (Amendment Nos. 263 and 259 for Catawba and Amendment Nos. 261 and 241 for McGuire) inadvertently left the 184-day criterion in the corresponding note. As such, the note restricts the ability to use the SFCP to control the surveillance frequency in accordance with NEI 04-10, Revision 1, beyond the stated 184 days.

In its current state, a COT is required to be performed prior to any reactor startup that falls outside the 184 days from the previous performance of TS SR 3.3.1.8. The proposed change to McGuire and Catawba TS SR 3.3.1.8 would remove the extra content from the surveillance frequency note and allow the SFCP to establish the Frequency in accordance with the program requirements previously approved by the NRC.

NRC Staffs Evaluation The NRC staff evaluated the information provided in the LAR. The NRC staff finds that the proposed change to McGuire and Catawba TS SR 3.3.1.8 would remove the extra content from the surveillance frequency note and allow the SFCP to establish the frequency in accordance with the previously granted amendments adopting TSTF-425. Therefore, the NRC staff finds the licensees request acceptable, because the SR remains consistent with the requirement specified in 10 CFR 50.36(c)(3).

4.0 STATE CONSULTATION

In accordance with the Commissions regulations, State officials of North Carolina and South Carolina were notified of the proposed issuance of the amendments on August 30, 2023. On August 30, 2023, both State officials confirmed they had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes requirements with respect to installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and changes SRs. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, published in the Federal Register on March 21, 2023 (88 FR 17036), and there has been no public comment on such finding. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors: A. Russell, NRR G. Bedi, NRR Date:

October 24, 2023

ML23241A987 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-1/LA NRR/DSS/STSB/BC NAME SWilliams KGoldstein MJardaneh DATE 9/6/2023 08/31/2023 8/21/2023 OFFICE NRR/DEX/EMIB/BC NRR/DRA/APLB/BC NRR/DEX/EICB NAME SBailey JWhitman RStattel (ABC)

DATE 8/15/2023 9/1/2023 8/30/2023 OFFICE NRR/DSS/SCPB/BC NRR/DSS/SNSB/BC OGC - NLO NAME BWittick PSahd RWeisman DATE 9/6/2023 9/6/2023 9/29/2023 OFFICE NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME DWrona SWilliams DATE 10/24/2023 10/24/2023

v t e Letter Sequence Approval
EPID:L-2023-LLA-0015, TSTF-493, TSTF-425, TSTF-545 (Approved, Closed)
Initiation Request Acceptance Administration Questions 2 June 2023 20 June 2023 Answers 7 July 2023 Results Approval Other:
MONTHYEAR2023-02-27 [Table View]

ML23241A987

Text

SUBJECT:

Dear Mr. Gibby:

Enclosures:

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1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 STATE CONSULTATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 CONCLUSION

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