ML25251A213
| ML25251A213 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire  (NPF-035, NPF-052, NPF-009, NPF-017) |
| Issue date: | 11/13/2025 |
| From: | John Klos Plant Licensing Branch II |
| To: | Gibby S Duke Energy Carolinas |
| References | |
| EPID L-2025-LLA-0046, WCAP-17642-NP-A, Rev 1 | |
| Download: ML25251A213 (1) | |
Text
November 13, 2025 Shawn Gibby Vice President Nuclear Engineering Duke Energy 525 S. Tyron St.
Charlotte, NC 28202
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2, AND MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS TO REVISE REACTOR CORE SAFETY LIMIT TO REFLECT TOPICAL REPORT WCAP-17642-NP-A, REVISION 1 (EPID L-2025-LLA-0046)
Dear Shawn Gibby:
The U.S. Nuclear Regulatory Commission has issued the following enclosed Amendment Nos. 322 and 318 to Renewed Facility Operating License Nos. NPF-35 and NPF-52 for the Catawba Nuclear Station (Catawba), Units 1 and 2, respectively, and the following enclosed Amendment Nos. 332 and 311 to Renewed Facility Operating License Nos. NPF-9 and NPF17 for the McGuire Nuclear Station (McGuire), Units 1 and 2, respectively. The amendments are in response to your application dated March 11, 2025.
The amendments revise Technical Specification (TSs) 2.1.1.2, Reactor Core SLs [Safety Limits], to reflect the peak centerline melt temperature specified in Topical Report WCAP-17642-NP-A, Revision 1, Westinghouse Performance Analysis and Design Model (PAD5).
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions Federal Register notice.
S. Gibby If you have any questions, please contact me at (301) 415-0610 or via email at John.Klos@nrc.gov.
Sincerely,
/RA/
John Klos, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.
50-413, 50-414 50-369, 50-370
Enclosures:
- 1. Amendment No. 322 to NPF-35
- 2. Amendment No. 318 to NPF-52
- 3. Amendment No. 332 to NPF-9
- 4. Amendment No. 311 to NPF-17
- 5. Safety Evaluation cc: Listserv DUKE ENERGY CAROLINAS, LLC NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 322 Renewed License No. NPF-35 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Renewed Facility Operating License No. NPF-35 filed by the Duke Energy Carolinas, LLC (licensee), dated March 11, 2025, 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 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 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. 322, 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 its date of issuance and shall be implemented prior to the Unit 1 Cycle 30 reload campaign, currently scheduled for Spring 2026.
FOR THE NUCLEAR REGULATORY COMMISSION Michael Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. NPF-35 and Technical Specifications Date of Issuance: November 13, 2025 MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2025.11.13 07:10:25 -05'00' DUKE ENERGY CAROLINAS, LLC NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 318 Renewed License No. NPF-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Renewed Facility Operating License No. NPF-52 filed by the Duke Energy Carolinas, LLC (licensee), dated March 11, 2025, 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 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 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. 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 its date of issuance and shall be implemented prior to the Unit 1 Cycle 30 reload campaign, currently scheduled for Spring 2026.
FOR THE NUCLEAR REGULATORY COMMISSION Michael Markley, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. NPF-52 and the Technical Specifications Date of Issuance: November 13, 2025 MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2025.11.13 07:11:03 -05'00' DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-369 MCGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 332 Renewed License No. NPF-9 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Renewed Facility Operating License No. NPF-9 filed by the Duke Energy Carolinas, LLC (licensee), dated March 11, 2025, 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 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 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. 332, 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 its date of issuance and shall be implemented prior to the Unit 1 Cycle 32 reload campaign, currently scheduled for Fall 2026.
FOR THE NUCLEAR REGULATORY COMMISSION Michael Markley, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. NPF-9 and Technical Specifications Date of Issuance: November 13, 2025 MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2025.11.13 07:11:40 -05'00' DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-414 MCGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 311 Renewed License No. NPF-17 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Renewed Facility Operating License No. NPF-17 filed by the Duke Energy Carolinas, LLC (licensee), dated March 11, 2025, 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 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 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. 311, 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 its date of issuance and shall be implemented prior to the Unit 1 Cycle 32 reload campaign, currently scheduled for Fall 2026.
FOR THE NUCLEAR REGULATORY COMMISSION Michael Markley, Chief Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. NPF-17 and the Technical Specifications Date of Issuance: November 13, 2025 MICHAEL MARKLEY Digitally signed by MICHAEL MARKLEY Date: 2025.11.13 07:12:18 -05'00'
ATTACHMENT AMENDMENT NO. 322 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-35 AMENDMENT NO. 318 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-52 CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 Renewed Facility Operating License Nos. NPF-35 and 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 Appendix A to Renewed Facility Operating License Nos. NPF-35 and NPF-52 Replace the following pages of the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert TS 2.0-1 TS 2.0-1
Renewed License No. NPF-35 Amendment No. 322 (2)
TECHNICAL SPECIFICATIONS The Technical Specifications contained in Appendix A, as revised through Amendment No. 322, 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. 318 (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)
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.
Catawba Units 1 and 2 2.0-1 Amendment Nos. 322/318 SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR for four loop operation; and the following SLs shall not be exceeded:
2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained
> 1.14 for the WRB-2M CHF correlation.
2.1.1.2 The peak fuel centerline temperature shall be maintained < 5080 degrees F, decreasing 9 degrees F for every 10,000 MWd/mtU of fuel burnup.
2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained < 2735 psig.
2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2 If SL 2.1.2 is violated:
2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.
ATTACHMENT AMENDMENT NO. 332 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-9 AMENDMENT NO. 311 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-17 MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370 Renewed Facility Operating License Nos. NPF-9 and 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 Appendix A to Renewed Facility Operating License Nos. NPF-9 and NPF-17 Replace the following pages of the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert TS 2.0-1 TS 2.0-1
Renewed License No. NPF-9 Amendment No. 332 (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. 332, 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. 311 (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. 311, 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.
McGuire Units 1 and 2 2.0-1 Amendment Nos. 332/311 SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR for four loop operation; and the following SLs shall not be exceeded:
2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained
>1.14 for the WRB-2M CHF correlation.
2.1.1.2 The peak fuel centerline temperature shall be maintained <5080 degrees F, decreasing 9 degrees F for every 10,000 MWd/mtU of fuel burnup.
2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained < 2735 psig.
2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2 If SL 2.1.2 is violated:
2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO CATAWBA NUCLEAR STATION, UNITS 1 AND 2 AMENDMENT NO. 322 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-35 AMENDMENT NO. 318 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-52 AND MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 AMENDMENT NO. 332 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-9 AMENDMENT NO. 311 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-17 DUKE ENERGY CAROLINAS, LLC DOCKET NOS. 50-369, 50-370, 50-413 AND 50-414
1.0 INTRODUCTION
By application dated March 11, 2025, Agencywide Documents Access and Management System (ADAMS) Accession No. ML25070A183, Duke Energy Carolinas, LLC (Duke Energy or the licensee) requested changes to the Technical Specifications (TSs) for Catawba Nuclear Station (Catawba), Units 1 and 2, and McGuire Nuclear Station (McGuire), Units 1 and 2.
The proposed amendment would revise the TS Reactor Core SLs [Safety Limits] 2.1.1.2 peak fuel centerline temperature to reflect the fuel centerline melt temperature specified in Topical Report (TR) WCAP-17642-NP-A, Revision 1, Westinghouse Performance Analysis and Design Model (PAD5), November 2017, (ML17338A396, non-proprietary version).
2.0 REGULATORY EVALUATION
2.1 Plant Type The nuclear steam supply systems (NSSS) at the Catawba units are identical and are similar to that at the McGuire units. Each Catawba and McGuire unit consists of a Westinghouse designed pressurized water reactor with four closed reactor coolant loops connected in parallel to the reactor vessel. Each loop contains a reactor coolant pump, a steam generator, loop piping, and instrumentation. The NSSS also contains an electrically heated pressurizer and certain auxiliary systems. The containment of each unit is an ice condenser type consisting of a free-standing cylindrical steel structure enclosed by a separate reinforced concrete reactor building with an annulus between the two structures. The ice condenser mitigates the high post-accident pressures in the containment by absorbing the energy of the released reactor coolant, thereby reducing the driving potential for escape of fission products from the containment.
2.2
System Description
The proposed amendments are related to the Catawba and McGuire nuclear fuel. Reactor core SL 2.1.1.2 protects against overheating of the nuclear fuel and fuel cladding, which would lead to the fuel centerline temperature rising above the fuel melting point. The consequences of fuel and cladding overheating include fuel clad perforation, which leads to nuclear fission product release to the reactor coolant. Clad perforation can occur when the fuel centerline temperature reaches the melting point for the fuel and the fuel pellet expands. Reactor core SL 2.1.1.2 is dependent on burnup and is applicable when the reactor is critical in MODES 1 and 2.
2.3 Licensees Proposed Changes In its submittal dated March 11, 2025 (ML25070A183), the licensee proposed to revise the TS reactor core SL 2.1.1.2 peak fuel centerline temperature to reflect the fuel centerline melt temperature specified in TR WCAP-17642-NP-A, Revision 1 (ML17338A396). The changed TS SL is indicated in BOLD font as provided below.
Current TS SL 2.1.1.2 states:
The peak fuel centerline temperature shall be maintained < 5080 degrees F, decreasing 58 degrees F for every 10,000 MWd/mtU of fuel burnup.
Revised TS SL 2.1.1.2 would state:
The peak fuel centerline temperature shall be maintained < 5080 degrees F, decreasing 9 degrees F for every 10,000 MWd/mtU of fuel burnup.
2.4 Regulatory Requirements The statutes and regulations that are applicable to the proposed TS SL 2.1.1.2 change include Section 182a, License Applications, of the Atomic Energy Act, which requires applicants for nuclear power plant operating licenses to include TSs as part of the license to enable the Commission to find that the utilization of special nuclear material will be in accord with the common defense and security and will provide adequate protection to the health and safety of the public Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, Technical Specification, which requires that TSs include items in the following categories:
(1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; (5) administrative controls; (6) decommissioning; (7) initial notification; and (8) written reports. Specifically, 10 CFR 50.36(c)(1) defines safety limits for nuclear reactors as the limits upon important process variables that are found to be necessary to reasonably protect the integrity of certain physical barriers that guard against the uncontrolled release of radioactivity.
10 CFR, Section 50.36(c)(1)(i)(A), states in part, Safety limits for nuclear reactors are limits upon important process variables that are found to be necessary to reasonably protect the integrity of certain physical barriers that guard against the uncontrolled release of radioactivity. If any safety limit is exceeded, the reactor must be shut down.
Section 50.36(b) requires that the Technical Specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto.
Regulations in 10 CFR 50.90, Application for amendment of license, construction permit, or early site permit, specifies an application must be filed with the Commission, as specified in §§ 50.4 or 52.3 of this chapter, as applicable, fully describing the changes desired, and following as far as applicable, the form prescribed for original applications.
Appendix A to 10 CFR Part 50, General Design Criteria for Nuclear Power Plants [GDC], Criterion 10, Reactor design, which requires that the reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.
3.0 TECHNICAL EVALUATION
The scope of the Nuclear Regulatory Commission (NRC) staff review is limited to the proposed change related to the SL for peak fuel centerline temperature.
3.1 Evaluation of the Proposed TS Change The proposed SL reflects the limit in NRC-approved TR WCAP-17642-P-A, Revision 1 (ML17338A396) which in Section 6.1.5, Melting Point, states the updated melting point correlations for the above fuels. In these correlations, it is noted that the burnup dependent fuel centerline melt temperature is based on the inherent fuel properties only.
In the safety evaluation (SE) for TR WCAP-17642-NP-A (Section A of ADAMS Accession No. ML17338A396) Section 3.7.12, Pellet Overheating Melting, it is stated that the burnup dependence of the fuel melting limit is acceptable for UO2, UO2-Gd2O3, and up to the certain specified limits for UO2-Er2O3.
The proposed 9oF decrease in the fuel centerline melt temperature for every 10,000 MWd/mtU of fuel burnup is based on the PAD5 graph in Figure 59, PAD5 and FRAPCON fuel melting temperature for UO2 and for UO2-(10wt%) Gd2O3, of the SE for WCAP-17642-NP-A (ML1733A396, Section A). The NRC staff determines the proposed change acceptable because the burnup dependence of the fuel meting temperature is based on an assessment of fuel properties data only.
3.2 Consideration of WCAP-17642-NP-A Limitations and Conditions The licensee addressed limitations and conditions (L&Cs) (a) and (b) described in Section 4.1, Limitations and Conditions, of the NRC staff SE on WCAP-17642-NP-A (ML1733A396, Section A). These L&Cs are the only the ones applicable to the proposed changes in this license amendment request (LAR).
L&C (a) in the SE on WCAP-17642-NP-A states, in part, that:
The NRC staff limits the applicability of the PAD5 code and methodology for cladding, fuel types and reactor for the ranges that are listed.
The NRC staff confirmed that Catawba and McGuire use Westinghouse fuel and cladding that meets the constraints identified in L&C (a). In the LAR, Section 3.1, Limits of Applicability, the licensee stated:
The Westinghouse cladding and fuel utilized by CNS [Catawba] and MNS
[McGuire] meet the constraints identified in Limitation and Condition (a).
Furthermore, Duke Energy will apply PAD5 within the limits specified in Section 4.1 of the SE for WCAP-17642-P-A for cladding, fuel, and reactor parameters to be used at CNS and MNS. Since these PAD5 inputs depend on the reload design, these parameters are validated on a cycle-specific basis.
L&C (b) in the SE on WCAP-17642-NP-A (ML1733A396, Section A) states:
The application of PAD5 should at no time exceed the fuel melting temperature as calculated by PAD5 due to the lack of properties for molten fuel in PAD5 and other properties such as thermal conductivity and FGR [fission gas release].
In the LAR, Section 3.1, the licensee also stated:
The peak fuel centerline temperature for CNS [Catawba] and MNS [McGuire] will be limited per this license amendment request. The requested amendment revises the peak fuel centerline temperature SL for CNS and MNS to ensure that fuel melt is precluded during conditions for normal operation and anticipated operational occurrences, consistent with GDC 10.
The NRC staff determined that the licensees statement is acceptable because the LAR specifically proposes to change the peak fuel centerline temperature SL to ensure that fuel melt is precluded during conditions for normal operation and anticipated operational occurrences, consistent with the requirements of GDC 10. The NRC staff also notes that the LAR only proposed implementing the empirically derived TS SL and therefore, this SE does not approve the use of PAD5 to calculate any associated parameters. The L&C (b) require that, should WCAP-17642-P-A be implemented in future, the Catawba and McGuire specific analyses are not to be used to predict fuel conditions beyond the melting point.
L&C (c) associated with the use of TR WCAP-17642-NP-A is not applicable because it is not related to the contents of this LAR.
L&C (d), which restricts Westinghouse from implementing the model and methods improvement process, is not applicable because the LAR does not request any such approval or implementation.
L&C (e) requires Westinghouse to include the SE and all requests for additional information responses in the final accepted version (-A) of TR WCAP-17642-NP-A and is therefore not applicable to this LAR.
3.3 TS SL 2.1.1.2 Change Evaluation In the LAR, the licensee requests to change Catawba and McGuire TS SL 2.1.1.2 to reflect the peak fuel centerline melt temperature found in WCAP-17642-NP-A (ML1733A396). TS SL 2.1.1.2 limits the peak fuel centerline temperature. For normal operation and anticipated operational occurrences, the reactor protection system is designed to ensure that the peak fuel centerline temperature does not exceed the fuel melt temperature criterion. The intent of this criterion is to avoid gross fuel melting.
The NRC staff determined that the peak fuel centerline temperature is not dependent on the PAD5 methodology. The staff evaluated the peak fuel centerline temperature and determined that it is applicable to Catawba and McGuire.
The proposed SL was empirically derived and covers the lower bound of the fuel property data, which is conservative because the lower bound assures that the SL does not underestimate the applicable data. Additionally, as documented in the NRC staffs SE on WCAP-17642-NP-A (ML1733A396, Section A), the NRC staff compared the fuel centerline melting temperatures in the TR WCAP-17642-NP-A (ML1733A396) to the fuel centerline melting temperature in the NRCs confirmatory calculation code, FRAPCON (now known as FAST). The WCAP-17642-NP-A fuel centerline melting temperature is less than that in FRAPCON, which is conservative.
The NRC staff determined that its analysis and technical justification for the fuel centerline melting temperature in the SE on WCAP-17642-NP-A (ML1733A396, Section A) is applicable to Catawba and McGuire because the properties of the fuel design in use at Catawba and McGuire are consistent with the fuel property data used to generate the fuel centerline melting temperature. Therefore, the NRC staff determined that the proposed SL is conservative for Catawba and McGuire.
As stated by the licensee in its LAR, Section 2.4, Description of the Proposed Change,:
The current licensing basis safety analyses use the existing SL 2.1.1.2 for fuel melt as an acceptance criterion as required by the current methodology. Thus, CNS [Catawba] and MNS [McGuire] will continue to meet the existing SL when using their respective current licensing basis safety analyses, even with the implementation of the proposed SL. Since the existing SL for peak fuel centerline temperature is more restrictive than the proposed limit, the current licensing basis safety analyses will continue to meet the proposed SL following implementation of this license amendment request.
In the licensees Final Safety Analysis Reports (FSAR), Section 4.2.4.1 Cladding, item no. 11, Linear Heat Rate to Melt, for Catawba (ML24296A048, Revision 24) and Section 4.2.1.3.1.1, Cladding, item no. 11, Linear Heat Rate to Melt, for McGuire (ML25083A313, Revision 25),
the licensee discusses the basis for the existing SL. These sections state that a calculated fuel centerline temperature of 4,700 °F has been selected as an overpower limit to ensure no fuel melting. This conservative limit assures that the applicable safety analyses demonstrate that the proposed TS SL is not exceeded. The licensee stated in the LARs Section 2.4 that the FSAR Sections referenced above will be revised in accordance with 10 CFR 50.59 to address the updated fuel melt safety limit and its technical basis. Based on the above, including the LAR information that supports the use of the empirically derived and less restrictive temperature, the NRC staff concludes that the proposed increase in the peak fuel centerline temperature TS SL would continue to meet 10 CFR 50.36(b) requirement in that the TSs would be derived from licensee safety analyses, as amended.
The licensees proposed TS change meets the requirements of GDC 10 and Section 182a of the Atomic Energy Act, because (1) the peak fuel centerline temperature is based on a conservative evaluation of test data that is applicable to the fuel design used at CNS and MNS, and (2) the proposed limit will ensure that fuel melt is precluded during conditions of normal operations and under anticipated operational occurrences. Therefore, the NRC staff concludes that the proposed TS change would continue to meet 10 CFR 50.36(c)(1)(i)(A). The NRC finds that there is reasonable assurance that the revised TS SL would maintain an important variable that is necessary to reasonably protect the integrity of a physical barrier that guards against the uncontrolled release of radioactivity and is therefore acceptable.
3.4 Technical and Regulatory Conclusions The NRC staff concludes that the fuel centerline melting temperature in the SE on WCAP-17642-NP-A (ML1733A396, Section A) is applicable to Catawba and McGuire because the properties of the fuel design in use at CNS and MNS are consistent with the fuel property data used to generate the fuel centerline melting temperature. Therefore, the NRC staff determines that the proposed SL is conservative for CNS and MNS.
The proposed TS change would meet the requirements of GDC 10 because (1) the peak fuel centerline temperature is based on a conservative evaluation of test data that is applicable to the fuel design used at Catawba and McGuire, and (2) the proposed limit will ensure that fuel melt is precluded during conditions of normal operations and under anticipated operational occurrences.
The proposed TS change would also meets 10 CFR 50.36(c)(1)(i)(A) because the revised TS limits an important variable that is necessary to reasonably protect the integrity of a physical barrier that guards against the uncontrolled release of radioactivity. Therefore, the NRC staff concludes that the proposed change is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the South Carolina and North Carolina State officials were notified of the proposed issuance of the amendment on September 8, 2025. The State of South Carolina officials had no comments on September 8, 2025 and the State of North Carolina had no comment on September 8, 2025.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change the requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve 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 amendments involve no significant hazards consideration published in the Federal Register on May 14, 2025 (90 FR 20513), and there has been no public comment on such finding. Accordingly, the amendments meet 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 amendments.
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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: R. Fu, NRR A. Sallman, NRR A. Russell, NRR Date: November 13, 2025
- via eConcurrence NRR-058 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA*
NRR/DSS/STSB/BC NRR/DSS/SNSB/BC NAME JKlos KZeleznock SMehta NDifrancesco DATE 9/8/2025 9/30/2025 8/11/2025 8/11/2025 OFFICE NRR/DSS/SFNB/BC NRR/DORL/LPL2-1/BC*
NRR/DORL/LPL2-1/PM*
NAME SKrepel MMarkley JKlos DATE 8/11/2025 11/13/2025 11/13/2025