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ML26062A21525 March 2026Issuance of Amendment Nos. 323, 319; 333, 312, Respectively, to Revise TSs to Allow Usage of a Full Spectrum Loss-Of-Coolant-Accident Methodology (EPID L-2025-LLA-0132) - Non-Proprietary
RA-25-0014, License Amendment Request to Adopt the Full Spectrum Loss of Coolant Accident Methodology and Axiom Fuel Cladding Topical Reports and Associated 10 CFR 50.46 Exemption Request for Use of Axiom Fuel Cladding18 August 2025License Amendment Request to Adopt the Full Spectrum Loss of Coolant Accident Methodology and Axiom Fuel Cladding Topical Reports and Associated 10 CFR 50.46 Exemption Request for Use of Axiom Fuel Cladding
ML25014A01416 January 2025Duke Energy January 16, 2025, Pre-Submittal Meeting Presentation Titled, Strategy for the Sequencing of Proposed License Amendment Requests to Facilitate the Utilization of Axiom Fuel Rod Cladding
ML24302A07028 October 2024Duke Energy Presubmittal Meeting on Adoption of Westinghouse Analysis PAD5/FSLOCA/AXIOM (EPID L-2024-LRM-0121) on October 28, 2024
ML20309A7348 October 20202 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems
ML20309A7448 October 20202 to Updated Final Safety Analysis Report, Chapter 18, Aging Management Programs and Activities
ML20309A7468 October 20202 to Updated Final Safety Analysis Report, Chapter 1, Appendix 1A, Tables
IR 05000369/202001231 July 2020NRC Post-Approval Site Inspection for License Renewal, Inspection Report 05000369/2020012 and 05000370/2020012
NL-20-0851, 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material22 July 202030-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material
RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description8 July 2019License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description
ML20093C98711 April 2019Updated Final Safety Analysis Report, Chapter 1, Tables
ML20093E62011 April 2019Updated Final Safety Analysis Report, Chapter 9
ML20095H52911 April 2019Updated Final Safety Analysis Report, Chapter 18
RA-19-0115, Transmittal of the Duke Energy Corporation Topic Report (Duke QAPD-001-A), Amendment 4418 February 2019Transmittal of the Duke Energy Corporation Topic Report (Duke QAPD-001-A), Amendment 44
IR 05000369/201800423 January 2019Nuclear Regulatory Commission Integrated Inspection Report - 05000369/2018004 and 05000370/2018004
RA-18-0004, Duke Energy Transmittal of Topical Report DUKE-QAPD-001-A, Amendment 4313 August 2018Duke Energy Transmittal of Topical Report DUKE-QAPD-001-A, Amendment 43
ML18009A84231 January 2018Issuance of Amendments to Extend the Containment Type a Leak Rate Test Frequency to 15 Years and Type C Leak Rate Test Frequency to 75 Months (CAC Nos. MF9020 and MF9021; EPID L-2016-LLA-0032)
RA-17-0025, Transmittal of the Duke Energy Corporation Topical Report (Duke-QAPD-001-A), Amendment 4222 May 2017Transmittal of the Duke Energy Corporation Topical Report (Duke-QAPD-001-A), Amendment 42
ML17034A36222 February 2017Mcguire Nuclear Station, Unit 1 - Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping Relief
MNS-16-092, License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies19 December 2016License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
MNS-16-077, Responding to Request for Additional Information Related to License Amendment Request to Implement a Risk-informed Performance-Based Fire Protection Program29 September 2016Responding to Request for Additional Information Related to License Amendment Request to Implement a Risk-informed Performance-Based Fire Protection Program
MNS-16-056, License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information30 June 2016License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information
MNS-16-053, Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping23 June 2016Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping
ML16127A5954 May 2016Rotork Controls Inc. Part 21 Notification Concerning V12 (Pt No. N69-921) and K5 (N69-838 & N69-926) Safety Related Micro Switches
MNS-16-015, License Amendment Request (LAR) for One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval18 February 2016License Amendment Request (LAR) for One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval
MNS-15-088, Relief Request Serial No. 15-MN-0029 November 2015Relief Request Serial No. 15-MN-002
MNS-14-095, Response to August 28, 2014, NRC Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program12 December 2014Response to August 28, 2014, NRC Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program
ML14085A06524 April 2014NRC Staff Review of the Documentation Provided by Duke Energy Carolinas, LLC, for McGuire Concerning Resolution of Generic LTR 2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressuriz
IR 05000369/201300523 January 2014IR 05000369-13-005, 05000370-13-005, 05000369-13-502 & 05000370-13-502; on 10/01/2013 - 12/31/2013; McGuire Nuclear Station; Routine Integrated Inspection Report
ML13073A04116 May 2013Issuance of Amendments Regarding Measurement Uncertainty Recapture Power Uprate
ML16230A12730 November 20129 to Updated Final Safety Analysis Report, Chapter 1, Appendix 1A, Tables
ML12199A0236 July 2012Response to Request for Additional Information Regarding License Amendment Related to Measurement Uncertainty Recapture Power Uprate
ML12200A0212 July 2012Final Responses to NRC Request for Additional Information (RAI) Related to Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents At.
ML12158A4816 June 2012Request for Additional Information Regarding License Amendment Related to Measurement Uncertainty Recapture Power Uprate
ML12082A2105 March 2012License Amendment Request for Measurement Uncertainty Recapture Power Uprate
ML11304A13526 October 2011Independent Spent Fuel Storage Installation, Quality Assurance Program Topical Report Amendment 39
ML11080042628 March 2011Relief 09-MN-002, Revision 1, for a Proposed Alternative to Delay the Update to the Code of Record for the Fourth 10-Year Inservice Inspection (ISI) Interval
ML10356059214 December 2010Relief Request Serial 09-MN-002, Revision 1, Response to Request for Additional Information
ML10287010030 September 2010Draft Responses to NRC Request for Additional Information Related to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents on Pressurized-Water..
ML10279016728 September 2010Response to Requests for Additional Information on Relief Request Serial 09-MN-002
ML10211029428 July 2010ISFSI, McGuire Units 1 & 2, Catawba Units 1 & 2, Quality Assurance Program Topical Report Alternate Amendment 37
IR 05000369/201000326 July 2010IR 05000369-10-003 and 05000370-10-003, on 04/01/10 - 06/30/10; McGuire Nuclear Station Maintenance Risk Assessment, Radiological Hazard Assessment and Exposure Controls
ML1012604453 May 2010Stations, Draft, Confirmatory Integrated Test Plan
ML10061038118 February 2010Duke Energy Carolinas, Topical Report Quality Assurance Program, Revision 37
ML1004809741 February 2010Relief Request Serial 09-MN-002 Response to Request for Additional Information
ML0927304607 October 2009Summary of Conference Call with Duke Regarding Responses to Generic Letter (GL) 2004-02. Meeting Handouts
ML0921706584 May 2009Submittal of Relief Request Serial No. 09-MN-002
ML08308035018 November 2008Request for Additional Information (RAI) Regarding Supplemental Responses to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized
ML08309004923 October 2008Duke Energy Carolinas Topical Report, Quality Assurance Program, Revision 36
ML08128048830 April 2008Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
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