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Category:Letter
MONTHYEARIR 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 05000369/20240102023-10-13013 October 2023 Notification of McGuire Nuclear Station Comprehensive Engineering Team Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000369, 370/2024010 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 ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report 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 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 ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000369/20220032022-10-27027 October 2022 Integrated Inspection Report 05000369/2022003 and 05000370/2022003 IR 05000369/20220112022-09-29029 September 2022 Biennial Problem Identification and Resolution Inspection Report 05000369/2022011 and 05000370/2022011 ML22266A0782022-09-26026 September 2022 William B. Mcguire Nuclear Station, Unit 2 Pressurizer Power Operated Relief Valve Relief Request ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition IR 07200038/20220012022-09-12012 September 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200038/2022001 ML22230B6132022-09-0101 September 2022 Review of the Draft Environmental Assessment and Finding of No Significant Impact for Brunswick Steam Electric Plant and McGuire Nuclear Station Independent Spent Fuel Storage Installations Decommissioning Funding Plans IR 05000369/20220052022-08-29029 August 2022 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 NRC Inspection Report 05000369/2022005 and 05000370/2022005 IR 05000369/20220022022-07-26026 July 2022 Integrated Inspection Report 05000369/2022002 and 05000370/2022002 ML22215A2502022-07-25025 July 2022 EN 55960 - Update - Curtiss Wright ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22175A0162022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22111A3112022-05-16016 May 2022 Letter Issuing Exemption to McGuire IR 05000369/20224012022-05-12012 May 2022 Cyber Security Inspection Report 05000369/2022401 and 05000370/2022401 2024-01-31
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRA-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 ML15175A4422015-06-24024 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 3 of 6 2023-02-17
[Table view] Category:Technical Specification
MONTHYEARRA-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-18-0190, 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-22-0080, Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-0707 April 2022 Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System 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-21-0027, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-16016 September 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-20-0207, Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation2020-12-0303 December 2020 Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation 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-18-0232, Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS2019-02-0505 February 2019 Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS RA-18-0166, Supplement to Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs2018-09-13013 September 2018 Supplement to Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs ML18191A5452018-07-10010 July 2018 Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages RA-18-001, Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages2018-07-10010 July 2018 Attachment 2 - McGuire Technical Specification 3.8.1 Bases Marked Up Pages 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 RA-18-0001, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications 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-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 RA-17-0045, Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules.2017-10-12012 October 2017 Supplement: Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules. ML17237A0492017-08-17017 August 2017 Technical Specification Bases - List of Effected Sheets ML17237A0482017-08-17017 August 2017 Technical Specification Bases (Rev. 150) ML17237A0462017-08-17017 August 2017 Document Transmittal Form Regarding Technical Specification Changes - Amendment Nos. 296/275 ML17186A0682017-06-26026 June 2017 Tech Spec Bases - List of Affected Sections ML17186A0672017-06-26026 June 2017 Revision 151 to Tech Spec Bases - B 3.6.13 and B 3.6.14 ML17186A0662017-06-26026 June 2017 TS 3.6.13 Amendment 292/271 and TS 3.6.14 Amendment 294/273 ML17186A0692017-06-26026 June 2017 Issue Tech Spec - List of Affected Pages ML17136A2792017-05-0303 May 2017 Technical Specification Leep, Rev. 109 ML17136A2782017-05-0303 May 2017 Technical Specification Bases - Loes, Rev. 133 ML17136A3612017-05-0303 May 2017 Technical Specification Bases, Revision 149 ML17136A3602017-05-0303 May 2017 Technical Specification Amendment Nos. 285/264 ML17124A3682017-04-19019 April 2017 Tech Spec Bases List of Effected Pages ML17124A3712017-04-19019 April 2017 Bases B 3.5.1 - Accumulators ML17094A6722017-03-29029 March 2017 Issue Selected License Commitment Cslcl 16.7.14 Revision ML17094A6732017-03-29029 March 2017 Issue SLC List of Effected Pages ML17090A4522017-03-23023 March 2017 Revision to Technical Specification 3.3.2 - Amendment 293/272 ML17090A4512017-03-23023 March 2017 Revision to Technical Specification 3.8.1 - Amendment 293/272 ML17090A4352017-03-22022 March 2017 Technical Specification Bases ML17090A4502017-03-22022 March 2017 Revision to Technical Specification Bases - B 3.6.15 ML17094A6702017-03-15015 March 2017 Issue MNS-SLC-16.9.15. Snubbers 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 ML16305A1442016-10-20020 October 2016 Issue MNS Technical Specification 5.5 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 ML16265A5312016-08-30030 August 2016 Issue MNS Tech Spec Bases List of Effective Sections ML16265A5322016-08-30030 August 2016 Technical Specification Bases 3.6.14 Revisions, List of Revisions and Dates ML16250A0142016-08-29029 August 2016 Amendment 287 ML16243A3492016-08-23023 August 2016 Mccguire, Units 1 and 2, Revision 143 to Issue MNS Technical Specification Bases 3.3.1 ML16243A3482016-08-23023 August 2016 Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation. ML16243A3512016-08-23023 August 2016 Revision 105 to Technical Specifications List of Effective Pages ML16243A3502016-08-23023 August 2016 Revision 129 to Technical Specification Bases ML16243A3572016-08-18018 August 2016 Technical Specification Bases Revision 001, List of Revised Sections 2023-02-16
[Table view] Category:Amendment
MONTHYEARRA-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-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-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-22-0080, Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-0707 April 2022 Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System 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-21-0027, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-16016 September 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-20-0207, Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation2020-12-0303 December 2020 Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation 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-18-000, 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 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-18-0001, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications 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-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 ML16305A1442016-10-20020 October 2016 Issue MNS Technical Specification 5.5 ML16133A4462016-05-0202 May 2016 Technical Specification 3.7.7, Amendments 282 and 261 ML16133A4692016-05-0202 May 2016 Technical Specification 3.8.1, Amendments 282 and 261 ML16133A4662016-05-0202 May 2016 Technical Specification 3.7.7 - Rev. 140, Amendments 282/261 ML16133A4422016-04-28028 April 2016 Technical Specification 3.5.2, Amendments 282 and 261 ML16133A4432016-04-28028 April 2016 Technical Specification 3.6.6, Amendments 282 and 261 ML16133A4672016-04-28028 April 2016 Technical Specification 3.7.9, Amendments 282 and 261 ML16133A4452016-04-28028 April 2016 Technical Specification 3.7.6, Amendments 282 and 261 ML16133A4442016-04-28028 April 2016 Technical Specification 3.7.5, Amendments 282 and 261 ML16133A4682016-04-28028 April 2016 Technical Specification 3.7.11, Amendment 282/261 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. MNS-14-045, Responses to Request for Additional Information Related to License Amendment Request for One-Time Change to Technical Specification 3.8.4, DC Sources-Operating for Battery Replacement Dated October 28, 20132014-06-0303 June 2014 Responses to Request for Additional Information Related to License Amendment Request for One-Time Change to Technical Specification 3.8.4, DC Sources-Operating for Battery Replacement Dated October 28, 2013 ML13304B4452013-10-28028 October 2013 Revised License Amendment Request for One-Time Change to Technical Specification 3.8.4, DC Sources-Operating for Battery Replacement ML12340A0682012-11-0707 November 2012 Technical Specifications & Tech Spec Bases Updates ML12153A3282012-05-31031 May 2012 Proposed Technical Specifications Amendment TS 3.1.3, Moderator Temperature Coefficient (Mtc) TS 5.6.5, Core Operating Limits Report (COLR) License Amendment Request for Conditional Exemption of the End of Cycle (EOC) Mtc Measurement Method ML11311A1622011-10-31031 October 2011 Technical Specifications & Tech Spec Bases Updates ML1100500792010-12-28028 December 2010 Technical Specifications and Tech Spec Bases Manual Holders ML1026500392010-09-16016 September 2010 License Amendment Request to Revise Technical Specification 5.3, Unit Staff Qualifications ML1019002672010-06-29029 June 2010 License Amendment Request to Revise Reactor Trip System and Engineered Safety Feature Actuation System Technical Specifications ML0928600672009-09-30030 September 2009 Units 1 & 2 and Oconee, Units 1, 2, & 3 - License Amendment Request (LAR) Catawba and McGuire Containment Spray Nozzle and Oconee Reactor Building Spray and Cooling Systems Technical Specification Surveillance Requirement ML0913800922009-05-11011 May 2009 Technical Specification Update ML0911202002009-02-27027 February 2009 Duke Energy Carolinas, LLC - License Amendment Request for Adoption of TSTF-511, Rev. 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0829005322008-10-0202 October 2008 Units 1 and 2 - Amendment to Technical Specification 3.6.13, Ice Condenser Doors, Revised Surveillance Requirements ML0804305652008-02-13013 February 2008 Tech Spec Pages for Amendment 244 Regarding Extension of Appendix J, Type a Integrated Leakage Rate Test Interval ML0734804452007-12-11011 December 2007 Units 1 & 2 - Proposed Technical Specification (TS) Amendment to Relax Completion Times and Surveillance Intervals for the Reactor Trip System (RTS) Instrumentation TS 3.3.1, Engineered Safety Feature ML0726301322007-09-18018 September 2007 Corrected Technical Specification Pages Regarding Steam Generator Tube Integrity, TSTF-449, Rev 4 ML0723301182007-08-0909 August 2007 Response to Request for Additional Information Re Proposed Technical Specification (TS) Amendment TS 5.5.2 Containment Leak Rate Testing Program ML0706006602007-03-0101 March 2007 Technical Specification Pages Regarding Steam Generator Tube Integrity ML0706503552007-02-21021 February 2007 Proposed Technical Specification Amendment TS 5.5.2 Containment Leak Rate Testing Program ML0626901092006-09-25025 September 2006 Technical Specifications, Changes to the Updated Final Safety Analysis Report and Emergency Operating Procedures ML0520202062005-07-0707 July 2005 Units 1 & 2 - License Amendment Request Applicable to Technical Specification 3.9.1, Boron Concentration. ML0509701422005-04-0404 April 2005 Tech Spec Pages for Amendments 227, Eliminating Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process ML0509701552005-04-0404 April 2005 Tech Spec Pages for Amendments 209, Eliminating Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process ML0423804812004-08-18018 August 2004 License Amendment Request for Technical Specification 3.3.2, Engineered Safety Features Actuation System Instrumentation ML0409101232004-03-23023 March 2004 Duke Energy Corp License Amendment Request Applicable to Technical Specifications 5.5.7, Reactor Coolant Pump Flywheel Inspection Program, Using the Consolidated Line Item Improvement Process (CLIIP) ML0327604442003-09-29029 September 2003 Technical Specifications Pages, Amendments 217 & 199 ML0321304972003-06-25025 June 2003 Proposed Technical Specifications and Bases Amendment 2.0, Safety Limits; 3.3, Instrumentation; 3.4, Reactor Coolant System; 5.6, Reporting Requirements 2023-02-16
[Table view] |
Text
Duke Power
A Duke McGuire Nuclear Station 12700 Hagers Ferry Road Huntersville, NC 28078-9340 (704) 875-4000 (704) 875-5333 OFFICE D.M. Jamil (704) 875-4809 FAX Vice President, McGuire December 2, 2002 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555
Subject:
Duke Energy Corporation McGuire Nuclear Station, Units 1 and 2 Docket Numbers 50-369 and 50-370 Proposed Technical Specifications Amendment Administrative Controls 5.1.2, 5.2.2, 5.3.1, and 5.7.2 Responsibility, Unit Staff, Unit Staff Qualifications, and High Radiation Area Pursuant to 10CFR50.90, this letter submits a license amendment request (LAR) for the McGuire Nuclear Station Facility Operating Licenses and Technical Specifications (TS). This amendment applies to Administrative Controls 5.1.2, 5.2.2, 5.3.1, and 5.7.2 concerning Responsibility, Unit Staff, Unit Staff Qualifications, and controls of the High Radiation Area. The changes proposed by Duke Energy Corporation (Duke) in this amendment request will: 1) revise TS 5.1.2, 5.2.2, and 5.7.2 by accomplishing several administrative changes in order to reflect present McGuire operations shift responsibilities, and 2) modify TS 5.3.1 by deleting reference to the March 28, 1980 NRC letter to all licensees regarding the minimum qualifications of licensed Operators and Senior Reactor Operators. 10CFR55, "Operator's Licenses," specifies the minimum requirements for licensed Operators and Senior Reactor Operators.
The contents of this amendment package are as follows:
U.S. Nuclear Regulatory Commission Page 2 December 2, 2002 provides marked copies of the affected TS pages for McGuire showing the proposed changes. contains reprinted pages of the affected TS pages for McGuire. provides a description of the proposed changes and technical justification.
Pursuant to IOCFR50.92, Attachment 4 contains the results of the No Significant Hazards determination.
Pursuant to IOCFR51.22(c) (9), Attachment 5 provides the basis for the categorical exclusion from the performance of an Environmental Assessment/Impact Review.
The proposed amendment to TS 5.3.1 is similar to that submitted by the Catawba Nuclear Station on August 4, 1999, and approved by the NRC in the Safety Evaluation Report (SER) dated November 2, 1999.
Implementation of this amendment will not impact the McGuire Updated Final Safety Analysis Report (UFSAR).
Duke is requesting NRC approval of this License Amendment Request at its earliest convenience so that the identified Technical Specifications may be corrected.
In accordance with Duke administrative procedures and Quality Assurance Program Topical Report requirements, this proposed amendment has previously been reviewed and approved by the McGuire Plant Operations Review Committee and the Duke Corporate Nuclear Safety Review Board.
Pursuant to 10CFR50.91, a copy of this proposed amendment is being sent to the appropriate state official.
U.S. Nuclear Regulatory Commission Page 3 December 2, 2002 Inquiries on this matter should be directed to J. A.
Effinger at (704) 382-8688.
Very truly yours, D. M. Jamril
U.S. Nuclear Regulatory Commission Page 4 December 2, 2002 D. M. Jamil, being duly sworn, 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.
D. M. Jamil, Vice President Subscribed and sworn to me: Deeember c? c7,0 Date 2 , Notary Public D*lboraP S. PROrre My commission expires: Otýe-.b- 1 aoo4 I9,I SEAL
U.S. Nuclear Regulatory Commission Page 5 December 2, 2002 xc (w/attachments):
L. A. Reyes U. S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 R. E. Martin NRC Project Manager (MNS)
U. S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 20555-0001 S. M. Shaeffer Senior Resident Inspector (MNS)
U. S. Nuclear Regulatory Commission McGuire Nuclear Site B. 0. Hall, Section Chief Radiation Protection Section 1645 Mail Service Center Raleigh, NC 27699-1645
U.S. Nuclear Regulatory Commission Page 6 December 2, 2002 bxc w/attachments:
C. J. Thomas M. T. Cash K. L. Crane R. L. Gill McGuire Master File (MGO0DM)
ELL
ATTACHMENT 1 McGUIRE UNITS 1 AND 2 TECHNICAL SPECIFICATIONS MARKED COPY
Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The Station Manager shall be responsible for overall unit operation and shall ate ' w 'tin he su essio hi nsib~iliL ring his asoe 5.1.2 The s be responsb e control room command function. During any absence of the rom the control room while the unit is in MODE 1, 2,3, or 4, an individual (other than theq &I'&gfri) with an 1 '.,gp 7-
- ive -ac enior eactor Operator (SRO) license shall be designa d to assume the .
044.0 V jje-_
L ,A rcontrol room command function. During any absence of thet rhm the control room while the unit is in MODE 5 or 6, an individual with an active SRO license or Reactor Operator license shall be designated to assume the contr command function. R On occasion when there is a need for both the W9'tA ',Wf/and th@ SRO to be absent from the control room in MODE 1, 2, 3, or 4, the ý57-A shall be allowed to assume the control room command function and serve as the SRO in the c orovide r :
- a. the 3*i't*' fs vai a e to return to the control room within 10 minutes,
- b. the assumption of SRO duties by the is limited to periods not in excess of 15 minutes duration and a total time not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> dc jxr ny shift, and TA
- c. the Wg fbwA ~Jý j has a SRO license on the unit.
McGuire Units 1 and 2 5.1-1 Amendment Nos. P4zL.
Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)
- 2. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, nor more than 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period, all excluding shift turnover time;
- 3. A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shift turnover time;
- 4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.
Any deviation from the above guidelines shall be authorized in advance by the Station Manager or his designee, in accordance with approved administrative procedures, or by higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Station Manager or his designee to ensure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.
- f. The Operations Manager shall hold or have held an SRO license.
- g. The S p*'Ml*aefte Shift Technical Advisor (STA),shall provide advisory technical support to the eOJ,,i*.*v .JaLS-n the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. AV(flWWY,*f 3-r McGuire Units I and 2 5.2-3 Amendment Nos. B4tIV6-
Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI-N18.1-1971 for comparable positions, except the Radiation Protection Manager, who shall meet or exceed the qualifications of Regulato Guide 1.8, Set ember 197 p~osa Sn ed~g~ssfiee e ; 1 p air~
McGuire Units 1 and 2 5.3-1 Amendment Nos. 1tMG~
High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area 5.7.1 Pursuant to 10 CFR 20, paragraph 20.1601 (c), in lieu of the requirements of 10 CFR 20.1601, each high radiation area, as defined in 10 CFR 20, in which the intensity of radiation is > 100 mremlhr but < 1000 mrem/hr at-30 cm (12 in.) from the radiation source or from any surface which th~r.adiation penetrates, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures (e.g., Radiation Protection Technicians) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates
- 1000 mrem/hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
- a. A radiation rmonitoring device that continuously indicates the radiation dose rate in the area.
- b. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.
- c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Radiation Protection Manager in the RWP.
5.7.2 In addition to the requirements of Specification 5.7.1, areas with radiation levels
> 1000 mrem/hr at 30 cm (12 in.) from the radiation source or from any surface which the radiation penetrates shall be provided with locked or continuously o T-.,,- -5 guarded doors to prevent unauthorized entry and the keys shall be maintained
"----'--under the administrative control of thet ,e* on duty or radiation 14 -4 C, protection personnel. Doors shall remain locked except during periods of access by personnel under an approved RWP that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay times for individuals in those areas. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.
(continued)
McGuire Units I and 2 5.7-1 Amendment NosT
ATTACHMENT 2 McGUIRE UNITS 1 AND 2 TECHNICAL SPECIFICATIONS REPRINTED VERSION Remove Page Insert Page 5.1-1 5.1-1 5.2-3 5.2-3 5.3-1 5.3-1 5.7-1 5.7-1
Reportability 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The Station Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
5.1.2 The Control Room Senior Reactor Operator (CRSRO) shall be responsible for the control room command function. During any absence of the CRSRO from the control room while the unit is in MODE 1, 2, 3, or 4, an individual (other than the Shift Technical Advisor (STA) with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the CRSRO from the control room while the unit is in MODE 5 or 6, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.
On occasion when there is a need for both the CRSRO and the relief SRO to be absent from the control room in MODE 1, 2, 3, or 4, the STA shall be allowed to assume the control room command function and serve as the SRO in the control room provided that:
- a. the CRSRO or the relief SRO is available to return to the control room within 10 minutes,
- b. the assumption of SRO duties by the STA is limited to periods not in excess of 15 minutes duration and a total time not to exceed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during any shift, and
- c. the STA has a SRO license on the unit.
McGuire Units 1 and 2 5.1-1 Amendment Nos.
Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)
- 2. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, nor more than 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period, all excluding shift turnover time;
- 3. A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shift turnover time;
- 4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.
Any deviation from the above guidelines shall be authorized in advance by the Station Manager or his designee, in accordance with approved administrative procedures, or by higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Station Manager or his designee to ensure that excessive hours have not been assigned.
Routine deviation from the above guidelines is not authorized.
- f. The Operations Manager shall hold or have held an SRO license.
- g. The Shift Technical Advisor (STA) shall provide advisory technical support to the Control Room Senior Reactor Operator (CRSRO) in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit.
(continued)
McGuire Units 1 and 2 5.2-3 Amendment Nos.
Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI-N1 8.1-1971 for comparable positions, except the Radiation Protection Manager, who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
McGuire Units 1 and 2 5.3-1 Amendment Nos.
High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area 5.7.1 Pursuant to 10 CFR 20, paragraph 20.1601 (c), in lieu of the requirements of 10 CFR 20.1601, each high radiation area, as defined in 10 CFR 20, in which the intensity of radiation is > 100 mrem/hr but < 1000 mrem/hr at 30 cm (12 in.) from the radiation source or from any surface which the radiation penetrates, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures (e.g., Radiation Protection Technicians) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates
< 1000 mrem/hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
- a. A radiation monitoring device that continuously indicates the radiation dose rate in the area.
- b. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.
- c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Radiation Protection Manager in the RWP.
5.7.2 In addition to the requirements of Specification 5.7.1, areas with radiation levels
> 1000 mrem/hr at 30 cm (12 in.) from the radiation source or from any surface which the radiation penetrates shall be provided with locked or continuously guarded doors to prevent unauthorized entry and the keys shall be maintained under the administrative control of the Operations Shift Manager on duty or radiation protection personnel. Doors shall remain locked except during periods of access by personnel under an approved RWP that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay times for individuals in those areas. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.
(continued)
McGuire Units 1 and 2 5.7-1 Amendment Nos.
ATTACHMENT 3 DESCRIPTION OF PROPOSED CHANGES AND TECHNICAL JUSTIFICATION
DESCRIPTION OF PROPOSED CHANGES AND TECHNICAL JUSTIFICATON Proposed Change 1 Currently, Sections 5.1, "Responsibility," and 5.2, "Unit Staff," of the Administrative Controls section of the McGuire Technical Specifications (TS) refer to a Shift Supervisor (SS) position in paragraphs 5.1.2 and 5.2.2.
McGuire proposes to replace references to this position with the "Control Room Senior Reactor Operator (CRSRO)."
Additionally, paragraphs 5.1.2 and 5.2.2 of the Administrative Controls section of the McGuire TS refer to a Shift Work Manager position. McGuire proposes to replace references to this position with the "Shift Technical Advisor (STA)." The phrase "In addition, the Shift Work Manager shall meet the qualifications for STA specified by the Commission Policy Statement on Engineering Expertise on Shift" appearing in paragraph 5.2.2 (g) of the McGuire TS is deleted as unnecessary.
Paragraph 5.1.2 of the TS currently states that the Shift Work Manager shall be allowed to assume the control room command function and serve as the SRO in the control room on occasion when there is a need for both the Shift Supervisor and the SRO to be absent from the control room in MODE 1, 2, 3, or 4 provided, among other things, that the Shift Supervisor is available to return to the control room within 10 minutes. McGuire proposes to modify this paragraph by inserting the term "relief" immediately prior to the phrase SRO so as to make it clear that this person is temporarily relieving the Control Room SRO. McGuire also proposes to replace the Shift Supervisor position in paragraph 5.1.2(a) with the phrase "CRSRO or the relief SRO."
Section 5.7, "High Radiation Area," of the McGuire TS currently refers to a Shift Supervisor position in paragraph 5.7.2. McGuire proposes to replace the reference to this position with the "Operations Shift Supervisor (OSM) ."
The above listed changes are proposed so as to reflect current McGuire operations shift nomenclature and responsibilities.
Justification for the proposed changes is as follows:
The proposed changes are in alignment with the requirements of NUREG-1431, Revision 1, "Standard Technical Specifications, Westinghouse Plants."
The proposed changes do not adversely affect the minimum staffing levels required by the Technical Specifications.
McGuire will continue to meet the requirements of Technical Specification 5.2.2, "Unit Staff."
The proposed changes continue to ensure that no individual is assigned functions which will result in conflicting roles during design basis, fire, security, or other events.
Proposed Change 2 TS Administrative Controls, Section 5.3.1 "Unit Staff Qualifications" states, in part:
"The licensed Operators and Senior Reactor Operators shall also meet or exceed the minimum qualifications of the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees."
McGuire proposes to amend this requirement by deleting the above stated paragraph.
Justification for the proposed change is as follows:
By letter dated January 18, 2001, the NRC issued Regulatory Issue Summary (RIS) 2001-01, "Eligibility of Operator License Applicants." The NRC issued this RIS to familiarize addressees with the NRC's current guidelines for the qualification and training reactor operator (RO) and senior reactor operator (SRO) license applicants. As part of the RIS, the NRC staff encouraged all facility licensees to review their requirements and commitments related to RO and SRO education and experience and to update their documentation (e.g., UFSAR, TS, and training program descriptions) to enhance consistency and minimize confusion.
TS 5.3.1, which governs unit staff qualifications, is proposed to be modified to delete those references to additional requirements pertaining to licensed Operators and Senior Reactor Operators. These additional
requirements were included in the TS based on a March 28, 19801 NRC letter to all licensees. NUREG-1431, Revision 1, "Standard Technical Specification, Westinghouse Plants,"
formed the basis for the McGuire TS. NUREG-1431 recommends specifying minimum qualifications for members of the unit staff by use of an overall qualification statement. NUREG 1431 does not include reference to any supplemental qualification requirements for licensed Operators and Senior Reactor Operators.
Deletion of the reference to the stated requirements for licensed Operators and Senior Reactor Operators is acceptable because 10 CFR 55 specifies requirements pertaining to operator licenses. McGuire's operator licensing program meets all requirements of 10 CFR 55; therefore, it is not necessary to include additional requirements in the TS. This philosophy is identical to that employed in other sections of the Improved TS where requirements specified in regulations do not need to be duplicated in the TS. In addition, the NRC has previously reviewed and accepted McGuire's operator licensing program.
A similar change was approved for Duke Energy Corporation's Catawba Nuclear Station by letter dated November 2, 1999.2 1March 28, 1980, Harold R. Denton to All Power Reactor Applicants and Licensees, Qualifications of Reactor Operators.
2 November 2, 1999, Peter S. Tam to Mr. G. R. Peterson, Catawba Nuclear Station, Units 1 and 2, RE:
Issuance of Amendments (TAC NOS. MA6257, MA6258, MA6265 and MA6266).
ATTACHMENT 4 NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION
NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION As required by 10CFR50.91(a) (1), this analysis is provided to demonstrate that the proposed license amendment does not involve a significant hazard.
Conformance of the proposed amendment to the standards for a determination of no significant hazards, as defined in IOCFR50.92, is shown in the following:
- 1) Does the proposed license amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
No. Implementation of this amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.
Approval of this amendment will have no effect on accident probabilities or consequences since the changes are purely administrative in nature.
- 2) Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
No. Implementation of this amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated. No new accident causal mechanisms are created as a result of NRC approval of this amendment request. No physical changes are being made to the plant. Therefore, the introduction of any new accident scenarios does not exist. The amendment requires does not impact any plant systems that are accident initiators nor does it adversely impact any accident mitigating system. This amendment is purely administrative in nature.
- 3) Does the proposed change involve a significant reduction in margin of safety?
No. Implementation of this amendment will not involve a significant reduction in a margin of safety. Margin of safety is related to the confidence in the ability of the fission product barriers to perform their design functions during and following an accident situation. These barriers include the fuel cladding, the reactor coolant system, and the containment system. The performance of these fission product
barriers will not be impacted by implementation of this amendment. System and components are not affected and therefore are capable of performing as designed. This amendment is purely administrative nature, it will have no effect on any safety margins.
Conclusion Based on the preceding analysis, it is concluded that the proposed license amendment does not involve a Significant Hazards Consideration Finding as defined in IOCFR50.92.
ATTACHMENT 5 ENVIRONMENTAL ANALYSIS
ENVIRONMENTAL ANALYSIS The proposed amendment has been reviewed against the criteria of 10CFR51.22 for environmental considerations.
The proposed amendment does not involve a significant hazards consideration, increase the types and amounts of effluents that may be released offsite, or result in the increase of individual or cumulative occupational radiation exposures. Therefore, the proposed amendment meets the criteria provided by IOCFR51.22(c) (9) for categorical exclusion from the requirement for an Environmental Impact Statement.