Letter Sequence Approval |
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MONTHYEARML11277A0222011-09-26026 September 2011 Amendment to Technical Specification 3.8.3, Diesel Fuel Oil and Starting Air. Project stage: Request ML12074A1832012-03-15015 March 2012 Request for Additional Information Regarding Licensing Amendment Related to Changes to Related Specifications Diesel Fuel Oil and Starting Air Project stage: RAI ML12128A0302012-04-16016 April 2012 Amendment to Technical Specification 3.8.3, Diesel Fuel Oil and Starting Air, Response to Request for Additional Information Project stage: Response to RAI ML12240A1962012-09-29029 September 2012 Issuance of Amendments, Regarding Changes to Diesel Generator Starting Air Pressure Limits Project stage: Approval 2012-03-15
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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-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility 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 ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition 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 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 ML22010A2812022-03-0404 March 2022 Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161 ML21224A1012021-10-0707 October 2021 Issuance of Amendments to Revise the Technical Specification for Engineered Safety Feature Actuation System Instrumentation ML21155A2132021-08-26026 August 2021 Plant ML21131A0262021-06-23023 June 2021 Issuance of Amendments to Change Technical Specification 3.8.1, to Reduce Emergency Diesel Generator Maximum Voltage ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML19184A5852019-08-0808 August 2019 Issuance of Amendment Nos. 316 and 295 to Correct Editorial Error in Technical Specification 3.0 and Remove Expired Footnotes from TS 3.5.2, 3.6.6, 3.7.5, 3.7.6, 3.7.7, 3.7.9, 3.7.11, 3.8.1, and 3.8.4 ML19126A0302019-06-28028 June 2019 Issuance of Amendments to Technical Specification 3.8.1, AC Sources-Operating ML19050A2972019-04-18018 April 2019 McGuire Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, H B. Robinson Steam Electric Plant, Unit 2 - Issuance of Amendments Regarding Removal 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) ML18277A3222018-11-19019 November 2018 Issuance of Amendments 310 and 289 to Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application ML18009A8422018-01-31031 January 2018 Issuance of Amendments to Extend the Containment Type a Leak Rate Test Frequency to 15 Years and Type C Leak Rate Test Frequency to 75 Months (CAC Nos. MF9020 and MF9021; EPID L-2016-LLA-0032) ML17297A9172018-01-0505 January 2018 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-197-A, Revision 2 (CAC Nos. MF9110 and MF9111; EPID L-2017-LLA-0161) ML17271A0342017-10-31031 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-349-A, Revision 1, TSTF-361-A, Revision 2, and TSTF-438-A, Revision 0 (CAC Nos. MF9101 - MF9107) ML17277A3132017-10-31031 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-340-A, Revision 3 (CAC Nos. MF9117 and MF9118; EPID L-2017-LLA-0169) ML17269A1982017-10-31031 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-352-A, Revision 1 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) ML17261B2182017-10-25025 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-315-A Revision 0 (CAC Nos. MF9112 and MF9113; EPID L-2017-LLA-0171) ML17244A1022017-09-25025 September 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF 285-A, Revision 1 ML17240A3542017-09-18018 September 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-269-A, Revision 2 ML17188A3872017-08-21021 August 2017 Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660) ML17055A6472017-05-0808 May 2017 Brunswick, Catawba, McGuire, Shearon Harris, and H. B. Robinson - Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF8422, MF8423, MF8424, MF8425, MF8426, MF8427, MF8428, and MF8429) 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) ML17060A4812017-03-27027 March 2017 Issuance of Amendments Regarding Change to Technical Specification 3.6.14, & Divider Barrier Integrity; ML17087A2722017-03-22022 March 2017 Renewed Facility Operating License - Amendment 293 ML17003A0192017-03-0808 March 2017 Issuance of Amendments Regarding Change to Technical Specifications (Ts), Removal of Superseded TS Requirements ML16355A3082017-02-24024 February 2017 Issuance of Amendments Regarding Change to Technical Specification (TS) 3.6.13, Ice Condenser Doors ML16077A1352016-12-0606 December 2016 Issuance of Amendments Regarding National Fire Protection Association Standard NFPA 805 ML16305A0942016-10-20020 October 2016 Renewed Facility Operating License ML16236A0532016-09-26026 September 2016 Issuance of Amendments Regarding One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval ML16159A3362016-07-19019 July 2016 Issuance of Amendments Regarding Request to Use an Alternate Fission Gas Gap Release Fraction (CAC Nos. MF6480 Through MF6486) ML16174A0722016-06-27027 June 2016 Correction to License Pages Issuance of Amendments Regarding Adoption of TSTF-523 (Cac Nos. MF6413 Through MF6422) ML16105A3262016-06-21021 June 2016 Issuance of Amendments Regarding Use of Optimized Zirlo ML16109A0842016-06-21021 June 2016 Issuance of Amendments Regarding Revision of Technical Specification 3.3.1, Reactor Trip System Instrumentation ML16083A2082016-05-24024 May 2016 Issuance of License Amendments Regarding Emergency Action Level Scheme Change ML16139A4582016-05-10010 May 2016 Facility Operating License NPF-9 Amendment No. 283 MNS-16-020, License Amendment Request Removal of Superseded Technical Specification Requirements2016-05-0505 May 2016 License Amendment Request Removal of Superseded Technical Specification Requirements ML16132A2472016-05-0303 May 2016 Facility Operating License No. NPF-9, Amendment No. 282 ML16133A4412016-05-0202 May 2016 Facility Operating License NPF-17, Amendment 261 ML16133A4402016-05-0202 May 2016 Renewed Facility Operating License NPF-009, Amendment 281 ML16085A1132016-04-29029 April 2016 1 & 2; Shearon Harris Nuclear Power Plant 1; Catawba Nuclear Station 1 & 2; Mcguire Nuclear Station 1 & 2; and Oconee Nuclear Station 1, 2, & 3: Issuance of Amendments Regarding Adoption of TSTF-523 (CAC Nos. MF6413-MF6422) 2023-08-29
[Table view] Category:Safety Evaluation
MONTHYEARML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds 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 ML23159A2712023-06-20020 June 2023 William B. McGuire Nuclear Station, Unit 1 - Relief Request Impractical Reactor System Welds 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 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility 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 ML22266A0782022-09-26026 September 2022 William B. Mcguire Nuclear Station, Unit 2 Pressurizer Power Operated Relief Valve Relief Request ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition 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 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 ML22010A2812022-03-0404 March 2022 Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161 ML21306A1592021-11-16016 November 2021 Request to Use Provisions of Later Edition and Addenda of the ASME Code, Section XI (EPID; L-2021-LLR-0048) ML21155A2132021-08-26026 August 2021 Plant ML21131A0262021-06-23023 June 2021 Issuance of Amendments to Change Technical Specification 3.8.1, to Reduce Emergency Diesel Generator Maximum Voltage ML21113A0132021-05-0606 May 2021 Request for Use of a Later Edition of ASME Boiler and Pressure Vessel Code, Section XI for Repair and Replacement Activities ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20300A2062020-11-0909 November 2020 Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20230A2052020-08-21021 August 2020 Relief Request RA-20-0031, Delay to Update the Code of Record for Inservice Inspection ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML19254A6202019-09-17017 September 2019 Duke Energy Fleet (Brunswick, Catawba, Robinson, McGuire, Oconee, and Shearon Harris) - Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19217A3242019-08-14014 August 2019 Relief Request MC-SRV-NC-03, Alternate Testing for Pressurizer Power Operated Relief Valve Block Valve 2NC-35B ML19184A5852019-08-0808 August 2019 Issuance of Amendment Nos. 316 and 295 to Correct Editorial Error in Technical Specification 3.0 and Remove Expired Footnotes from TS 3.5.2, 3.6.6, 3.7.5, 3.7.6, 3.7.7, 3.7.9, 3.7.11, 3.8.1, and 3.8.4 ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs ML19126A0302019-06-28028 June 2019 Issuance of Amendments to Technical Specification 3.8.1, AC Sources-Operating ML19128A3262019-06-20020 June 2019 Alternative to Depth Sizing Qualification Examination of Welds ML19050A2972019-04-18018 April 2019 McGuire Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, H B. Robinson Steam Electric Plant, Unit 2 - Issuance of Amendments Regarding Removal ML19091A1942019-04-17017 April 2019 Safety Evaluation Input for License Amendment Request to Revise the Technical Specifications 3.8.1, AC Sources - Operating. 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) ML18277A3222018-11-19019 November 2018 Issuance of Amendments 310 and 289 to Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application ML18009A8422018-01-31031 January 2018 Issuance of Amendments to Extend the Containment Type a Leak Rate Test Frequency to 15 Years and Type C Leak Rate Test Frequency to 75 Months (CAC Nos. MF9020 and MF9021; EPID L-2016-LLA-0032) ML17297A9172018-01-0505 January 2018 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-197-A, Revision 2 (CAC Nos. MF9110 and MF9111; EPID L-2017-LLA-0161) ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML17277A3132017-10-31031 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-340-A, Revision 3 (CAC Nos. MF9117 and MF9118; EPID L-2017-LLA-0169) ML17269A1982017-10-31031 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-352-A, Revision 1 ML17271A0342017-10-31031 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-349-A, Revision 1, TSTF-361-A, Revision 2, and TSTF-438-A, Revision 0 (CAC Nos. MF9101 - MF9107) ML17261B2182017-10-25025 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-315-A Revision 0 (CAC Nos. MF9112 and MF9113; EPID L-2017-LLA-0171) 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) ML17244A1022017-09-25025 September 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF 285-A, Revision 1 ML17240A3542017-09-18018 September 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-269-A, Revision 2 ML17188A3872017-08-21021 August 2017 Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660) ML17055A6472017-05-0808 May 2017 Brunswick, Catawba, McGuire, Shearon Harris, and H. B. Robinson - Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF8422, MF8423, MF8424, MF8425, MF8426, MF8427, MF8428, and MF8429) 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) ML17060A4812017-03-27027 March 2017 Issuance of Amendments Regarding Change to Technical Specification 3.6.14, & Divider Barrier Integrity; ML17003A0192017-03-0808 March 2017 Issuance of Amendments Regarding Change to Technical Specifications (Ts), Removal of Superseded TS Requirements 2023-09-25
[Table view] Category:Technical Specifications
MONTHYEARML23195A0782023-08-29029 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 ML1010600442010-05-0505 May 2010 Issuance of Amendments Regarding Revision of Technical Specification (TS) 3.8.1, AC Sources - Operating (TAC Nos. ME0231 and ME0232) ML1012500442010-04-26026 April 2010 Amendment to Technical Specification 3.8.1, AC Sources-Operating. 2023-08-29
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 September 29, 2012 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING CHANGES TO DIESEL GENERATOR STARTING AIR PRESSURE LIMITS (TAC NOS. ME7275 AND ME7276)
Dear Mr. Capps:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 267 to Renewed Facility Operating License NPF*9 and Amendment No. 247 to Renewed Facility Operating License NPF-17 for the McGuire Nuclear Station, Units 1 and 2. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated September 26, 2011, as supplemented by letter dated April 16, 2012.
The amendments revise the TSs to incorporate aspects of NUREG-1431, "Standard Technical Specifications - Westinghouse [Electric Company] Plants," [Standard Technical Specification]
STS 3.8.3, "Diesel Fuel Oil, Lube Oil, and Starting Air," Condition E, regarding Diesel Generator starting air receiver pressure limits.
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
S. Capps -2 If you have any questions, please call me at 301-415-1119.
Sincerely, Jon Thompson, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosures:
- 1. Amendment No. 267 to NPF-9
- 2. Amendment No. 247 to NPF-17
- 3. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-369 MCGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 267 Renewed License No. NPF-9
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility),
Renewed Facility Operating License No. NPF-9, filed by the Duke Energy Carolinas, LLC (licensee), dated September 26,2011, as supplemented April 16, 2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
-2
- 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-9 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 267, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
3, This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/ )
/Yl.~~ ,.
i/ * / I C~..-tYtA.-,LA./t Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-9 and the Technical Specifications Date of Issuance: 28, 2012
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-370 MCGUIRE NUCLEAR STATION. UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 247 Renewed License No. NPF-17
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility),
Renewed Facility Operating License No. NPF-17, filed by the Duke Energy Carolinas, LLC (the licensee), dated September 26, 2011, as supplemented April 16, 2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
-2
- 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-17 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 26.*7 ,are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/"7.-1, ~.) // .
/{ri?~-Ll~
Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to License No. NPF-17 and the Technical Specifications Date of Issuance: September 28, 2012
ATTACHMENT TO LICENSE AMENDMENT NO. 267 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND LICENSE AMENDMENT NO. 247 RENEWED FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Renewed Facility Operating Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove License Pages License Pages NPF-9, page 3 NPF-9, page 3 NPF-17, page 3 NPF-17, page 3 TS Pages TS Pages 3.8.3-2 3.8.3-2
-3 (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of McGuire Nuclear Station, Units 1 and 2, and; (6) Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at a reactor core full steady state power level of 3411 megawatts thermal (100%).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 267 are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical SpeCifications.
(3) Updated Flnsl Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation.
Duke shall complete these activities no later than June 12, 2021, and shall notify the NRC In writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement as revised on December 16,2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following issuance of this renewed operating license.
Until that update is complete, Duke may make changes to the programs described In such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth In 10 CFR 50.59 and otherwise complies with the reqUirements in that section.
Renewed License No. NPF-9 Amendment No. 267
-3 (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use In amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of McGuire Nuclear Station, Units 1 and 2; and, (6) Pursuant to the Act and 10 CFR Part 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and Is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at a reactor core full steady state power level of 3411 megawatts thermal (100%).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 247 are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on December 16, 2002, describes certain future activities to be completed before the period of extended operation.
Duke shall complete these activities no later than March 3, 2023, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement as revised on December 16,2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4), following issuance of this renewed operating license.
Until that update is complete, Duke may make changes to the programs described In such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59, and otherwise complies with the requirements in that section.
Renewed Licen~~
Amendment No. <+
0/0. NPF-17
Diesel Fuel Oil and Starting Air 3.8.3 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. -----NOTE------- D.1 Restore starting air receiver 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> A single starting air pressure to ~ 210 psig.
receiver may be isolated without entering Condition D.
One or more DGs with starting air receiver i pressure < 210 psig and
~ 125 psig.
E. Required Action and E.1 Declare associated DG Immediately associated Completion inoperable.
Time not met.
OR One or more DGs diesel fuel oil or starting air subsystem not within limits for reasons other than Condition A, B, C, orD.
McGuire Units 1 and 2 3.8.3-2 Amendment Nos. 267 and 247
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 267 TO RENEWED FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT NO. 247 TO RENEWED FACILITY OPERATING LICENSE NPF-17 DUKE ENERGY CAROLINAS, LLC MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370
1.0 INTRODUCTION
By application dated September 26, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11277A022), as supplemented by letter dated April 16, 2012.
(ADAMS Accession No. ML12128A030) Duke Energy Carolinas, LLC (Duke, the licensee),
requested changes to the Technical Specifications (TSs) for the McGuire Nuclear Station, Units 1 and 2 (McGuire 1 and 2). The supplement dated April 16, 2012, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published the Federal Register on May 29,2012 (77 FR 31659).
The license amendment request (LAR) would revise the TSs to incorporate aspects of NUREG-1431, "Standard Technical Specifications - Westinghouse [Electric Company] Plants,"
[Standard Technical Specification] STS 3.8.3, "Diesel Fuel Oil, Lube Oil, and Starting Air,"
Condition E. LCO 3.8.3, Condition E, of NUREG-1431 describes the required actions when the Diesel Generator (DG) starting air receiver pressure is less than the minimum required pressure.
Specifically, the amendments would revise McGuire 1 and 2 TS 3.8.3, Condition 0, regarding the DG starting air receiver pressure limits by inserting a new Note, revising Required Action 0.1, and deleting Required Action 0.2.
2.0 REGULATORY EVALUATION
Section 3.1 of the McGuire 1 and 2 Updated Final Safety Analysis Report (UFSAR) discusses the design criteria for the facility structures, systems and components important to safety and how these criteria meet the General Design Criteria (GDC) described in Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants." As required by 10 CFR, Part 50, Appendix A, Criterion 17, "Electric power systems,"
- 2 (GDC 17) an onsite electric power system" ... shall be provided to permit functioning of structures, systems and components important to safety .... The onsite electric power supplies, including the batteries, and the onsite electric distribution system, shall have sufficient independence, redundancy, and testability to perform their safety functions assuming a single failure ... "
The regulation at 10 CFR 50.36(c)(2)(i) describes TS limiting conditions for operation (LCOs) as follows: Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met.
3.0 TECHNICAL EVALUATION
The UFSAR provides a description of the DG Starting Air (VG) system and states that:
The Diesel Generator Starting Air System (DGSAS) for each diesel unit consists of two air compressors, two 100 cubic feet starting air tanks, two aftercoolers, and two air dryers.
Each air compressor is designed to deliver 40 standard cubic feet per minute at 250 psig.
The air compressor discharges through an isolation valve to the aftercoolers, driers, and starting air tanks.
The LAR revises the McGuire 1 and 2 TS 3.8.3, "Diesel Fuel Oil and Starting Air," to prevent a condition in which the starting air system could be operated outside the conditions allowed by TS.
Currently, Condition D of TS 3.8.3 is entered when "One or more DGs with 1 of 2 starting air receiver pressures < [less than] 210 psig." Condition D currently specifies two required actions, D.1 and D.2. D.1 requires that the licensee "Initiate action to isolate the degraded starting air receiver." D.2 requires the licensee to "Restore both starting air receiver pressures 2!
[greater than or equal to] 210 psig."
The new TS 3.8.3, Condition D, Note would be state "A single starting air receiver may be isolated without entering Condition D." Condition D is revised to state "One or more Diesel Generators with 1 of 2 starting air receiver pressure less than 210 psig and greater than or equal to 125 psig."
Revised Required Action D.1 would state "Restore starting air receiver pressure to greater than or equal to 210 psig." Required Action D.2 is no longer applicable and is deleted.
The proposed TS change involves the four onsite DGs at McGuire 1 and 2. The VG system provides a start capability for the DG engines by using compressed air to roll the engines until they start. The licensee stated that a cross tie connection exists between the VG sub-trains upstream of the VG receiver tanks. The licensee states that there are sufficient piping connections to allow for alternate means to charge the air receivers from the compressed air bottles. In a requestfor additional information (RAI) dated March 15,2012 (ADAMS Accession No. ML12074A183), the NRC staff asked, among other RAI questions, for the licensee to provide a revised figure 9-143 that clearly identifies the cross connection that allows the VG system to meet the operability requirements of the DG system. The licensee provided the information requested in the RAI by letter dated April 16, 2012. This revised figure 9-143 shows a cross tie capability upstream of the air receiver tanks with valves 119/120 for McGuire 1 and valves 121/122 for McGuire 2.
-3 The licensee states that for the McGuire 1 and 2 DG engines, upon receiving a diesel start signal, all four starting air solenoid valves open. These valves remain open until the engine reaches 40%
rated speed, or until 20 seconds passes and a timer secures the starting sequence. In its RAI dated March 15, 2012, the NRC staff also asked the licensee to provide the test results showing where the air pressure is maintained in both air headers of the diesels when one air receiver is isolated. The licensee's letter dated April 16, 2012, shows that through empirical data and testing of the diesels, sufficient air pressure is maintained and five starts can be achieved without recharging the single air receiver. In the USFAR, Section 9.5.6.1 also outlines the ability of VG system to start the DGs five times consecutively with one of the two starting air receivers isolated.
In the LAR, the licensee states that in the case of manually isolating a degraded air receiver and upon receiving a diesel start signal, part of the starting air is lost to pressurizing the degraded receiver. With either starting air receiver having a pressure less than 210 psig and greater than 125 psig, Condition D applies until the degraded receiver is isolated. The licensee states that an alarm response procedure ensures this period is minimized and actions are taken to isolate the degraded receiver. With the degraded starting air receiver isolated and the remaining receiver pressure greater than or equal to 210 psig, the capacity for a minimum of five consecutive DG engine starts without recharging the air receiver exists and the DG can be considered OPERABLE while the repairs necessary to restore the degraded receiver are completed.
Based its review of the diesel starting air system configuration and the empirical and test data provided by the licensee in the LAR and the associated supplement, the NRC staff finds that the proposed changes are acceptable. The NRC staff has also determined that the proposed changes do not impact the reliability of the DGs for safe shutdown of the plant and, therefore, the licensee would continue to meet the requirements of GDC 17. The NRC staff's determination is further supported by its findings that the proposed changes are consistent with NUREG-1431 and will enable the licensee to avoid unnecessary entry into an Action Statement when one of the two air receiver tanks is removed from service.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the North Carolina State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (77 FR 31659).
Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
-4
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: O. Hopkins, NRR Date: September 28,2012
S. Capps - 2 If you have any questions. please call me at 301-415-1119.
Sincerely.
IRA!
Jon Thompson, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosures:
- 1. Amendment No. 267 to NPF-9
- 2. Amendment No. 247 to NPF-17
- 3. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
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- No su bstantla OFFICE NRR/LPL2-1/PM NRRlLPL2-1/LA DSS/SBPB/BC DElEEEB/BC DE/EICB/BC II NAME JThompson SFigueroa GCaslo' JAndersen JThorp' i[
DATE 08/29112 08/29112 09111112 09106/12 09/06112 i
iOFFICE DEIEPTBIBC DIRSISTSB/BC OGC NLO NRRlLPL2-1IBC NRRlLPL2-1/PM ilNAME AMcMurtray' RElliolt BMizuno RPascarelli RMartin for JThompson IloATE 09/06112 09110112 09/18112 09/28/12 09128112 I OFFICIAL RECORD COPY