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Category:Letter
MONTHYEARIR 05000369/20244042024-08-0101 August 2024 Cover Letter Security Baseline Inspection Report 05000369/2024404 and 05000370/2024404 IR 05000369/20253012024-07-29029 July 2024 Notification of Licensed Operator Initial Examination 05000369/2025301 and 05000370/2025301 IR 05000369/20240022024-07-24024 July 2024 Integrated Inspection Report 05000369/2024002 and 05000370/2024002 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000369/20244012024-07-0303 July 2024 – Security Baseline Inspection Report 05000369/2024401 and 05000370/2024401 ML24176A2802024-06-26026 June 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000369-2024404 and 05000370-2024404) IR 05000369/20240112024-06-0404 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000369/2024011 and 05000370/2024011 ML24149A1772024-05-28028 May 2024 NRC Response to Duke Energy 2025 FOF Schedule Change Request (Catawba and McGuire) IR 05000369/20240012024-05-0808 May 2024 Integrated Inspection Report 05000369-2024001 and 05000370-2024001 and 07200038-2024001 ML24110A0382024-04-30030 April 2024 – Correction to Issuance of Amendment Nos. 330 and 309, Regarding Implementation of Technical Specifications Task Force (TSTF) Traveler TSTF 505, Revision 2, “Provide Risk-Informed Extended Completion Times - Ritstf IR 05000369/20244032024-04-10010 April 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000369/2024403; and 05000370/2024403 ML24052A3062024-04-0808 April 2024 Issuance of Amendment Nos. 331 & 310, Regarding Adoption of Title 10 of Code of Federal Regulations Section 50.69, “Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24031A5402024-03-26026 March 2024 Issuance of Amendment Nos. 330 and 309 Regarding Implementation of TSTF 505,Rev. 2, “Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML24085A2402024-03-21021 March 2024 Requalification Program Inspection - McGuire Nuclear Station IR 05000369/20240102024-03-13013 March 2024 Comprehensive Engineering Team Inspection Report 05000369/2024010 and 05000370/2024010 IR 05000369/20230062024-02-28028 February 2024 Annual Assessment Letter for McGuire Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000369/2023006 and 05000370/2023006 ML24024A2182024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 ML24019A1392024-01-25025 January 2024 TSTF 505 and 50.69 Audit Summary ML24019A2002024-01-24024 January 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000369/20234022023-12-14014 December 2023 Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 ML23317A2272023-11-17017 November 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Transmittal of Dam Inspection Report - Non-Proprietary ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230032023-10-24024 October 2023 Integrated Inspection Report 05000369/2023003 and 05000370/2023003; and Inspection Report 07200038/2023001 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds IR 05000369/20233012023-09-20020 September 2023 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2023301 and 05000370/2023301 ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230052023-08-25025 August 2023 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 (Report 05000369/2023005 and 05000370/2023005) IR 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 IR 05000369/20234202023-07-24024 July 2023 Security Baseline Inspection Report 050003692023420 and 050003702023420 ML23206A0092023-07-24024 July 2023 William B. McGuire Nuclear Station Operator Licensing Written Examination Approval 05000369/2023301 and 05000370/2023301 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23159A2712023-06-20020 June 2023 William B. McGuire Nuclear Station, Unit 1 - Relief Request Impractical Reactor System Welds ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 ML23094A1832023-04-18018 April 2023 Audit Plan TSTF-505, Rev. 2, RITSTF Initiative 4B & 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors (EPIDs L-2023-LLA-0021 & L-2023-LLA-0022) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000369/20220062023-03-0101 March 2023 Annual Assessment Letter for McGuire Nuclear Station Units 1 and 2 (NRC Inspection Report 05000369/2022006 and 05000370 2022006) IR 05000369/20220042023-01-30030 January 2023 Mcguire Nuclear Station - Integrated Inspection Report 05000369/2022004 and 05000370/2022004 IR 05000369/20224202023-01-11011 January 2023 Security Baseline Inspection Report 05000369/2022420 and 05000370/2022420 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22347A1512022-12-13013 December 2022 William B. Mcguire Nuclear Station Notification of Licensed Operator Initial Examination 05000369/2023301 and 05000370/2023301 ML22340A6662022-12-0808 December 2022 Summary of November 30, 2022, Public Meeting with Duke Energy Carolinas, LLC for McGuire Nuclear Station, Units 1 & 2 Proposed LAR to Adopt TSTF-505, Rev. 2 and 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems ML22290A1012022-11-29029 November 2022 Issuance of Amendment Nos. 326 and 305, Regarding Changes to Technical Specification 3.4.3, Reactor Coolant System Pressure Temperature Limits ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations 2024-08-01
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML24110A0382024-04-30030 April 2024 – Correction to Issuance of Amendment Nos. 330 and 309, Regarding Implementation of Technical Specifications Task Force (TSTF) Traveler TSTF 505, Revision 2, “Provide Risk-Informed Extended Completion Times - Ritstf RA-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power2023-11-0202 November 2023 Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power RA-18-0090, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-02-17017 February 2023 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors RA-18-0190, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-02-16016 February 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022 Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-21-0320, License Amendment Request (LAR) to Revise the Applicability Term for Pressure and Temperature Limit Curves of Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits2021-12-20020 December 2021 License Amendment Request (LAR) to Revise the Applicability Term for Pressure and Temperature Limit Curves of Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits RA-21-0197, William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility2021-12-14014 December 2021 William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility RA-19-0043, Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2021-06-0909 June 2021 Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO 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 Description2019-07-0808 July 2019 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 Description RA-18-001, McGuire Nuclear Station, Units 1 and 2 - Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating.2018-07-10010 July 2018 McGuire Nuclear Station, Units 1 and 2 - Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating. RA-18-0015, Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating.2018-07-10010 July 2018 Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating. MNS-18-001, Application to Revise Technical Specifications to Adopt TSTF-234-A Revision 1, Add Action for More than One Dpri Inoperable2018-05-31031 May 2018 Application to Revise Technical Specifications to Adopt TSTF-234-A Revision 1, Add Action for More than One Dpri Inoperable ML18130A8072018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-18-000, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications MNS-18-017, Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs2018-02-26026 February 2018 Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs MNS-17-026, Submittal of License Amendment Request Proposing to Revise the Bases for Protection from Tornado-Generated Missiles2017-12-0808 December 2017 Submittal of License Amendment Request Proposing to Revise the Bases for Protection from Tornado-Generated Missiles RA-17-0005, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2017-11-0707 November 2017 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing MNS-17-031, License Amendment Request for Temporary Changes to Technical Specifications to Address an 'A' Train Nuclear Service Water System (Nsws) Non-Conforming Condition2017-09-14014 September 2017 License Amendment Request for Temporary Changes to Technical Specifications to Address an 'A' Train Nuclear Service Water System (Nsws) Non-Conforming Condition RA-17-0035, Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating.2017-07-20020 July 2017 Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating. RA-17-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2017-07-18018 July 2017 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules MNS-17-023, Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-05-25025 May 2017 Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML17122A1162017-05-0202 May 2017 Catawba and McGuire - License Amendment Request Proposing Changes to Technical Specification 3.8.1, AC Sources - Operating. RA-17-0003, Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers2017-01-11011 January 2017 Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers 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 Frequencies2016-12-19019 December 2016 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 Frequencies MNS-16-091, License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity.2016-12-0808 December 2016 License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity. ML16305A1412016-10-20020 October 2016 Document Transmittal Regarding Issue MNS FOL U-2, Rev. 3 RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process MNS-16-046, License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity2016-06-30030 June 2016 License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity MNS-16-039, Submittal Revising Attachment s of License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program2016-04-26026 April 2016 Submittal Revising Attachment s of License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program MNS-15-068, License Amendment Request to Technical Specification (TS) 3.6.13, Ice Condenser Doors.2016-03-24024 March 2016 License Amendment Request to Technical Specification (TS) 3.6.13, Ice Condenser Doors. MNS-16-015, License Amendment Request (LAR) for One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval2016-02-18018 February 2016 License Amendment Request (LAR) for One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval MNS-15-099, Submittal Regarding License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program2016-01-14014 January 2016 Submittal Regarding License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program MNS-16-002, Proposed Technical Specifications (TS) Amendment TS 3.7.10, Control Room Area Chilled Water System (Mns), and TS 3.7.11, Control Room Area Chilled Water System (CNS)2016-01-0707 January 2016 Proposed Technical Specifications (TS) Amendment TS 3.7.10, Control Room Area Chilled Water System (Mns), and TS 3.7.11, Control Room Area Chilled Water System (CNS) ML15258A0582015-09-0909 September 2015 Amendment 280 ML15258A0592015-09-0909 September 2015 Renewed Facility Operating License ML15258A0552015-09-0808 September 2015 Renewed Facility Operating License ML15258A0572015-09-0808 September 2015 Mcgurie Nuclear Station - MNS-TS-1.1 Amendment 280/260 Distribution MNS-15-069, Duke Energy Carolinas, LLC (Duke Energy), McGuire Nuclear Station, Unit 1 - License Amendment Request for One-Time Change to Technical Specification 3.5.2, Emergency Core Cooling Systems (ECCS) - Operating.2015-08-28028 August 2015 Duke Energy Carolinas, LLC (Duke Energy), McGuire Nuclear Station, Unit 1 - License Amendment Request for One-Time Change to Technical Specification 3.5.2, Emergency Core Cooling Systems (ECCS) - Operating. RA-15-0020, License Amendment Request and 10 CFR 50.12 Exemption Request for Use of Optimized Zirlo Fuel Rod Cladding2015-08-20020 August 2015 License Amendment Request and 10 CFR 50.12 Exemption Request for Use of Optimized Zirlo Fuel Rod Cladding RA-15-001, Catawba, McGuire, and Oconee - License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Foot2015-07-15015 July 2015 Catawba, McGuire, and Oconee - License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footn RA-15-0013, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 112015-07-15015 July 2015 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 11 MNS-15-025, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation2015-07-0909 July 2015 License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation MNS-15-026, License Amendment Request for Temporary Changes to Technical Specifications for Correction of an 'A' Train Nuclear Service Water System Degraded Condition - Drawing MCFD-2574-03.01, Rev. 11, Flow Diagram of Nuclear Service.2015-06-30030 June 2015 License Amendment Request for Temporary Changes to Technical Specifications for Correction of an 'A' Train Nuclear Service Water System Degraded Condition - Drawing MCFD-2574-03.01, Rev. 11, Flow Diagram of Nuclear Service. ML15191A0252015-06-30030 June 2015 License Amendment Request for Temporary Changes to Technical Specifications for Correction of an 'A' Train Nuclear Service Water System (Nsws) Degraded Condition ML15175A4482015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 6 of 6 ML15175A4472015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 5 of 6 ML15175A4452015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 4 of 6 2024-04-30
[Table view] Category:Technical Specifications
MONTHYEARML24052A3062024-04-0808 April 2024 Issuance of Amendment Nos. 331 & 310, Regarding Adoption of Title 10 of Code of Federal Regulations Section 50.69, “Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24031A5402024-03-26026 March 2024 Issuance of Amendment Nos. 330 and 309 Regarding Implementation of TSTF 505,Rev. 2, “Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 RA-21-0320, License Amendment Request (LAR) to Revise the Applicability Term for Pressure and Temperature Limit Curves of Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits2021-12-20020 December 2021 License Amendment Request (LAR) to Revise the Applicability Term for Pressure and Temperature Limit Curves of Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits ML18355A6102019-01-25025 January 2019 Issuance of Amendments to Revise the Licensing Basis for Protection from Tornado Generated Missiles ML18318A3582019-01-16016 January 2019 Issuance of Amendment Nos. 311 and 290 to Correct Non-Conservative Technical Specification 3.4.11, Pressurizer Power Operated Relief Valves Porvs) RA-17-0051, Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating2017-11-21021 November 2017 Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating ML17269A0552017-10-25025 October 2017 McGuire, Units 1 and 2 - Issuance of Amendments Adopting Technical Specification Task Force Traveler TSTF-283-A, Revision 3 (CAC NOS. MF9098 and MF9099) ML17248A4692017-08-29029 August 2017 Tech Spec and Tech Spec Bases TS-LOEP & TSB-LOES ML17237A0472017-08-17017 August 2017 Document Transmittal Form Regarding Technical Specification - List of Effected Pages (Rev. 111) RA-17-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2017-07-18018 July 2017 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) ML17087A2732017-03-22022 March 2017 Issue Tech Specification List of Affected Pages (Loep), Revision 108 ML17087A2722017-03-22022 March 2017 Renewed Facility Operating License - Amendment 293 ML16236A0532016-09-26026 September 2016 Issuance of Amendments Regarding One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval ML16243A3532016-08-17017 August 2016 Technical Specifications 5.5, Revision 1 - Amendment No. 276/256 ML16139A4612016-05-10010 May 2016 Technical Specification 3.3.1, Rev. 001, Amendments 283 and 262 ML16075A3012016-04-26026 April 2016 Issuance of Amendments Regarding the Revision of the Steam Generator Technical Specifications to Reflect the Adoption of TSTF-510(CAC Nos. MF6139,MF6140,MF6141,MF6142,MF6143,MF6144. ML16067A2292016-04-0808 April 2016 Issuance of Amendments Regarding Removal of Obsolete Technical Specification Requirements MNS-15-068, License Amendment Request to Technical Specification (TS) 3.6.13, Ice Condenser Doors.2016-03-24024 March 2016 License Amendment Request to Technical Specification (TS) 3.6.13, Ice Condenser Doors. ML15306A1412016-03-16016 March 2016 Issuance of License Amendment Regarding Nuclear Service Water System Allowed Outrage Time Extension ML16004A3522016-02-0303 February 2016 Issuance of Amendment Request to Revise Technical Specification for Residual Heat Removal System Air Handler Unit 1 ML15174A1732015-08-24024 August 2015 Issuance of Amendments Regarding Technical Specification Definition of Rated Thermal Power ML15133A4532015-06-11011 June 2015 McGuire Nuclear Station, Oconee Nuclear Station - Issuance of Amendments Regarding Changes to Cyber Security Plan Implementation Schedule Milestone 8 ML15063A2712015-04-14014 April 2015 Issuance of Amendments Technical Specification 3.1.3, Moderator Temperature Coefficient and TS 5.6.5, Core Operating Limits Report. ML15119A2182015-04-0707 April 2015 Technical Specification (TS) and Tech Spec Bases (Tsb) Manual ML15027A3662015-03-25025 March 2015 Issuance of Amendments DPC-NE-3001-P, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology MNS-15-013, Submits a License Amendment Request for the Renewed Facility Operating Licenses and Technical Specifications to Remove a Superseded TS Requirement2015-03-23023 March 2015 Submits a License Amendment Request for the Renewed Facility Operating Licenses and Technical Specifications to Remove a Superseded TS Requirement ML15002A3242015-02-12012 February 2015 McGuire Nuclear Station, and Oconee Nuclear Station - Issuance of Amendments Regarding Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Areas ML14231A6342014-09-10010 September 2014 Issuance of Amendments Regarding Technical Specification 3.8.4, DC Sources-Operating, ML14211A4032014-08-27027 August 2014 Issuance of Amendments Regarding Technical Specification 3.3.2 in Support of Compliance with NRC Order EA-12-049 ML14142A0112014-05-0505 May 2014 Technical Specification & Technical Specification Bases ML13316A0072013-10-31031 October 2013 Updated Technical Specifications Manual and Bases ML13277A3602013-09-24024 September 2013 Technical Specifications Bases ML13135A1332013-04-25025 April 2013 Annual Radioactive Effluent Release Report ML12340A4062012-11-27027 November 2012 Technical Specifications & Technical Specification Bases Updates. Includes Tsb Loes (Revision 114) & Tsb 3.6.15 (Entire Section) Rev 125 ML12240A1962012-09-29029 September 2012 Issuance of Amendments, Regarding Changes to Diesel Generator Starting Air Pressure Limits ML12229A1462012-08-0909 August 2012 License Amendment Request for One-Time Change to Technical Specification 3.8.4, DC Sources-Operating for Battery Replacement ML12082A2102012-03-0505 March 2012 License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML11341A1102011-12-0505 December 2011 License Amendment Request for Changes to Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation, Function 16(e) ML11318A1172011-11-0909 November 2011 License Amendment Request for Temporary Changes to Technical Specifications and Limited Duration Use of NUREG-0800, Section 3.5.1.3, Revision 3, to Allow Nuclear Service Water System (Nsws) 'A' Train Repair ML11131A1332011-09-12012 September 2011 License Amendment, Issuance of Amendments Regarding Technical Specification Changes to Allow Manual Operation of the Containment Spray System ML11140A0882011-05-12012 May 2011 Request for Exemption from Certain Requirements of 10 CFR 72.212(a)(2), 72.212(b)(2)(i), 72.212(b)(7) and 72.214 ML1106603442011-02-28028 February 2011 Technical Specification and Tec Spec Bases Updates ML1103200662011-01-24024 January 2011 Notice of Enforcement Discretion Request (Noed), Technical Specification (TS) Limiting Condition for Operation (LCO) 3.0.3 ML1032700962010-12-20020 December 2010 License Amendment, Issuance of Amendments Regarding Revision of Technical Specification (TS) 3.8.4 DC (Direct Current) Sources - Operating. ML1032706582010-11-18018 November 2010 Response to Request for Additional Information to Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements ML1022803352010-08-0404 August 2010 Technical Specification Updates ML1019504512010-08-0202 August 2010 Issuance of Amendments Regarding Replacement of Source Range and Intermediate Range Encore Detection Systems with Equivalent Neutron Monitoring Systems Using Fission Chamber Detectors (TAC ME1749 & ME1750) ML1021503242010-06-28028 June 2010 Technical Specifications and Technical Specifications Bases Updates 2024-04-08
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Duke GARY R. PETERSON PrPowere Vice President A Duke Energy Company McGuire Nuclear Station Duke Power MGOIVP/ 12700 Hagers Ferry Road Huntersville, NC 28078-9340 704 875 5333 704 875 4809 fax January 19, 2005 grpeters@duke-energy. corn U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk
SUBJECT:
Duke Energy Corporation McGuire Nuclear Station Units, 1 and 2 Docket Nos. 50-369, 50-370 License Amendment Request Applicable to Technical Specification 5.6.5.b, "Core Operating Limits Report (COLR)"
Pursuant to 10 CFR 50.90, Duke Energy Corporation (Duke) is requesting an amendment (LAR) to the McGuire Nuclear Station, Units 1 and 2, Technical Specifications (TS). This LAR adds an NRC-approved Topical Report, DPC-NE-1005P-A, "Duke Power Nuclear Design Methodology Using CASMO-4/SIMULATE-3 MOX," to the list of analytical methods used to determine core operating limits contained in TS 5.6.5.b, "Core Operating Limits Report (COLR)." Topical Report DPC-NE-1005P-A has been previously approved by the NRC.
The contents of this submittal package are as follows:
- An Affidavit is included within the cover letter.
- Attachment 1 provides a marked copy of the existing McGuire TS. The marked copy shows the proposed changes.
- Attachment 2 provides revised (clean) TS pages.
- Attachment 3 provides a Description of the Proposed Changes and Technical Justification.
- Pursuant to 10 CFR 50.92, Attachment 4 documents Duke's determination that this LAR contains No Significant Hazards Consideration.
www.duke-energy. corn
U. S. Nuclear Regulatory Commission January 19, 2005 Page 2
- Pursuant to 10 CFR 51.22(c)(10), Attachment 5 provides the basis for the categorical exclusion of this LAR from the requirement to perform an environmental assessment or environmental impact statement.
Duke is requesting NRC review and approval of this LAR by September 1, 2005, in order to support the McGuire Unit 1, Cycle 18 refueling. Duke has determined that the NRC's standard 30-day implementation grace period will be sufficient to implement this LAR. Please be aware that in a letter to the NRC dated September 28, 2004, Duke submitted an LAR that is applicable to McGuire TS 5.6.1 and 5.6.4, and in regard to the issuance of new TS pages, will require coordination with the current LAR contained herein.
Implementation of this LAR in the Facility Operating Licenses and TS will impact the McGuire Updated Final Safety Analysis Report (UFSAR). The necessary changes are discussed in and these will be submitted in accordance with 10 CFR 50.71(e). This submittal document contains no additional regulatory commitments.
Pursuant to 10 CFR 50.91, a copy of this LAR is being sent to the designated official of the State of North Carolina.
Inquiries on this matter should be directed to J. S. Warren at (704) 875-5171.
Very truly yours, G. R. Peterson
U. S. Nuclear Regulatory Commission January 19, 2005 Page 3 xc w/Attachments:
W. D. Travers, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 J. J. Shea (Addressee Only)
NRC Senior Project Manager (MNS)
U. S. Nuclear Regulatory Commission Mail Stop 0-7 D11 Washington, DC 20555-0001 J. B. Brady Senior Resident Inspector U. S. Nuclear Regulatory Commission McGuire Nuclear Site Beverly 0. Hall, Section Chief Radiation Protection Section 1645 Mail Service Center Raleigh, NC 27699-1645
U. S. Nuclear Regulatory Commission January 19, 2005 Page 4 G. R. Peterson, affirms that he is the person who subscribed his name to the foregoing statement, and that all the matters and facts set forth herein are true and correct to the best of his knowledge.
G. R. Peterson, Site Vice President Subscribed and sworn to me:
Date r(ada
/
A;4' /
, Notary Public My commission expires: AOigh 1-7,- 1 SEAL
Attachment 1 McGuire Units 1 and 2 Proposed Technical Specifications Changes (Mark-up)
5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- 4. DPC-NE-201I PA, 'Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," (DPC Proprietary).
- 5. DPC-NE-3001 PA, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," (DPC Proprietary).
- 6. DPC-NF-2010A, "Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design".
- 7. DPC-NE-3002A, -FSAR Chapter 15 System Transient Analysis Methodology".
- 8. DPC-NE-3000PA, "Thermal-Hydraulic Transient Analysis Methodology," (DPC Proprietary).
- 9. DPC-NE-1004A, "Nuclear Design Methodology Using CASMO-3/SIMULATE-3P".
- 10. DPC-NE-2004P-A, 'Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-Ol," (DPC Proprietary).
- 11. DPC-NE-2005P-A, "Thermal Hydraulic Statistical Core Design Methodology." (DPC Proprietary).
- 12. DPC-NE-2008P-A, "Fuel Mechanical Reload Analysis Methodology Using TACO3," (DPC Proprietary).
- 13. WCAP-1 0054-P-A, "Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code," (E Proprietary).
- 14. DPC-NE-2009-P-A, 'Westinghouse Fuel Transition Report," (DPC Proprietary).
- 15. WCAP-1 2945-P-A, Volume 1 and Volumes 2-5. "Code Qualification Document for Best-Estimate Loss of Coolant Analysis," (MLA Proprietary).
The COLR will contain the complete identification for each of the Technical Specifications referenced topical reports used to prepare the COLR (i.e., report number, title, revision number, report date or NRC SER date, and any supplements).
- 16. DPC-NE-1005P-A, "Duke Power Nuclear Design Methodology Using CASMO-4/SIMULATE-3 MOX," (DPC Proprietary).
(continued)
McGuire Units 1 and 2 5.64 Amendment Nos. / 4
Attachment 2 McGuire Units 1 and 2 Revised (Clean) Technical Specifications Pages Remove Insert 5.6-4 5.6-4 1
5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- 4. DPC-NE-201 1PA, "Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westinghouse Reactors," (DPC Proprietary).
- 5. DPC-NE-3001 PA, "Multidimensional Reactor Transients and Safety Analysis Physics Parameter Methodology," (DPC Proprietary).
- 6. DPC-NF-2010A, "Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Nuclear Physics Methodology for Reload Design ".
- 7. DPC-NE-3002A, "FSAR Chapter 15 System Transient Analysis Methodology".
- 8. DPC-NE-3000PA, "Thermal-Hydraulic Transient Analysis Methodology ," (DPC Proprietary).
- 9. DPC-NE-1004A, "Nuclear Design Methodology Using CASMO -
3/SIMULATE-3 P ".
- 10. DPC-NE-2004P-A, "Duke Power Company McGuire and Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01," (DPC Proprietary).
- 11. DPC-NE-2005P-A, "Thermal Hydraulic Statistical Core Design Methodology," (DPC Proprietary).
- 12. DPC-NE-2008P-A, "Fuel Mechanical Reload Analysis Methodology Using TACO3," (DPC Proprietary).
- 13. WCAP-10054-P-A, 'Westinghouse Small Break ECCS Evaluation Model using the NOTRUMP Code," c& Proprietary).
- 14. DPC-NE-2009-P-A,.'Westinghouse Fuel Transition Report," (DPC Proprietary).
- 15. WCAP-12945-P-A, Volume 1 and Volumes 2-5, " Code Qualification Document for Best-Estimate Loss of Coolant Analysis," (W. Proprietary).
- 16. DPC-NE-1005P-A, 'Duke Power Nuclear Design Methodology Using CASMO-4/SIMULATE-3 MOX," (DPC Proprietary).
The COLR will contain the complete identification for each of the Technical Specifications referenced topical reports used to prepare the COLR (i.e., report number, title, revision number, report date or NRC SER date, and any supplements).
(continued)
McGuire Units 1 and 2 5.6-4 Amendment Nos.
Attachment 3 Description of Proposed Changes and Technical Justification DESCRIPTION This license amendment request (LAR) proposes a change to the McGuire Nuclear Station, Units 1 and 2, Technical Specifications (TS) 5.6.5.b, "Core Operating Limits Report (COLR)." This TS contains a list of documents which comprise the analytical methods used to determine core operating limits. These documents are reviewed and approved by the NRC prior to inclusion in the TS. The change proposed in this LAR adds another document to TS 5.6.5.b as new item number 16. The new document is DPC-NE-1005P-A, "Duke Power Nuclear Design Methodology Using CASMO-4/SIMULATE-3 MOX," (DPC Proprietary).
TECHNICAL JUSTIFICATION Discussion Topical Report DPC-NE-1005P-A was approved by the NRC in a letter and safety evaluation report (SER) dated August 20, 2004 (Reference 1). This topical report addresses the use of the Studsvik Core Management System (Studsvik/CMS) code package to support reload design analyses for McGuire and Catawba Nuclear Stations. It is being included in McGuire TS 5.6.5.b consistent with the provisions of an NRC-approved Industry/Technical Specifications Task Force (TSTF) Standard Technical Specifications Traveler, TSTF-363, "Revise Topical Report References in ITS 5.6.5, COLR,"
and previously approved amendments for McGuire Units 1 and 2 (Reference 2), in that the new topical report is being added to the TS without listing the approval date or revision number. This detailed information is included in the complete citation for the topical reports that is contained in the plant's actual COLR documents. As mentioned above, this practice is consistent with TSTF-363 and the current, approved McGuire TS 5.6.5.b. Note that revisions to the COLR documents are routinely submitted to the NRC. Implementation of DPC-NE-1005P-A will be consistent with the provisions of the NRC's SER (Reference 1). Since the proposed change to TS 5.6.5.b consists only of adding a document that has been previously approved by 1
Attachment 3 Description of Proposed Changes and Technical Justification the NRC for use at McGuire, this LAR has been determined to be administrative in nature.
Implementation of this LAR in the Facility Operating Licenses and TS will impact the McGuire Updated Final Safety Analysis Report (UFSAR). Chapters 4, 14, and 15 of the UFSAR will be revised to include Topical Report DPC-1005P-A, as appropriate, in the lists of reference documents. The necessary changes will be submitted in accordance with 10 CFR 50.71(e), as stated in the cover letter of this LAR submittal package.
The addition of DPC-NE-1005P-A to Catawba TS 5.6.5.b has been previously addressed by a separate Duke LAR submittal (Reference 3).
Applicable Regulatory Criteria The NRC's Public Website provides the industry with a description of the agency's topical report program and describes the procedures for submitting topical reports for review and approval by the agency and subsequent publication by licensees. As stated in the website, the NRC's regulations related to topical reports are found in 10 CFR 170.11 and 10 CFR 2.390. This current submittal package consists of an LAR which Duke is submitting to the NRC pursuant to 10 CFR 50.90.
Conclusion Duke has evaluated the addition of Topical Report DPC-NE-1005P-A to TS 5.6.5.b and has determined this change to be solely administrative in nature, and thus, appropriate for implementation at McGuire.
REFERENCES
- 1. Letter, R. E. Martin, USNRC, to H. B. Barron, Duke Energy Corporation,
SUBJECT:
Final Safety Evaluation for Duke Topical Report, DPC-NE-1005P, "Nuclear Design Methodology Using CASMO-4/SIMULATE-3 MOX," Dated August 20, 2004.
2
Attachment 3 Description of Proposed Changes and Technical Justification
- 2. Letter, R. E. Martin, USNRC, to H. B. Barron, Duke Energy Corporation,
SUBJECT:
McGuire Nuclear Station, Units 1 and 2, RE: Issuance of Amendments (TAC Nos.
MB3702 and MB3703), Dated July 10, 2002.
- 3. Letter, M. S. Tuckman, Duke Energy Corporation, to Document Control Desk (USNRC);
SUBJECT:
Duke Energy Corporation, Catawba Nuclear Station, Units 1 & 2, Docket Nos. 50-413, 50-414; McGuire Nuclear Station, Units 1 & 2, Docket Nos. 50-369 and 50-370; Proposed Amendments to the Facility Operating License and Technical Specifications to Allow Insertion of Mixed Oxide Fuel Lead Assemblies and Request for Exemption from Certain Regulations in 10 CFR Part 50; Dated February 27, 2003.
3
Attachment 4 No Significant Hazards Consideration Determination Duke Energy Corporation (Duke) has made the determination that this license amendment request (LAR) involves No Significant Hazards Consideration through the application of the standards established by the NRC's regulations in 10 CFR 50.92. These three standards are discussed below.
- 1. Would implementation of the changes proposed in this LAR involve a significant increase in the probability or consequences of an accident previously evaluated?
No. This LAR makes an administrative change to Technical Specification (TS) 5.6.5.b, "Core Operating Limits Report (COLR).O This TS contains a listing of documents (analytical methods) that are used to determine core operating limits. These documents are separately and individually reviewed and approved by the NRC. The current LAR adds a new document, DPC-NE-1005P-A, "Duke Power Nuclear Design Methodology Using CASMO-4/SIMULATE-3 MOX," (DPC Proprietary), to the list in TS 5.6.5.b.
Topical Report DPC-NE-1005P-A has been previously reviewed by the NRC and determined to be appropriate for use at McGuire. The NRC's determination was documented in a safety evaluation report dated August 20, 2004.
Based on these considerations, it has been determined that the proposed administrative change has no impact on any accident probabilities or consequences.
- 2. Would implementation of the changes proposed in this LAR create the possibility of a new or different kind of accident from any accident previously evaluated?
No. This LAR is solely administrative in nature since it only adds an NRC-approved licensing basis document to the TS. No new accident causal mechanisms will be created as a result of the NRC approval of this LAR.
- 3. Would implementation of the changes proposed in this LAR Involve a significant reduction in a margin of safety?
No. This LAR is solely administrative in nature. The analytical methodologies used to generate the core operating limits are separately and individually reviewed and approved by the NRC, and are unchanged by this LAR.
The change contained in this LAR merely revises the McGuire TS in an administrative manner in order to 1
Attachment 4 No Significant Hazards Consideration Determination conform with a Duke licensing action that has been previously approved by the NRC. Therefore the change proposed in this amendment request has no impact on margin.
Conclusion Based upon the preceding discussion, Duke has concluded that this proposed amendment does not involve a significant hazards consideration.
2
- i Attachment 5 Environmental Assessment/Impact Statement The proposed license amendment request is administrative in nature and has been determined to meet the criteria given in 10 CFR 51.22(c)(10) for a categorical exclusion from the requirement for performing an environmental impact statement or environmental assessment.
1