Letter Sequence Approval |
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MONTHYEARML13304B4452013-10-28028 October 2013 Revised License Amendment Request for One-Time Change to Technical Specification 3.8.4, DC Sources-Operating for Battery Replacement Project stage: Request ML13351A3432013-12-19019 December 2013 Acceptance of Requested Licensing Action License Amendment Request for One-Time Change to Technical Specification 3.8.4, DC Sources-Operating for Battery Replacement Project stage: Acceptance Review ML14127A4622014-05-12012 May 2014 Request for Additional Information Regarding License Amendment Request to Modify Specification 3.8.4 Setpoint Project stage: RAI 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 Project stage: Response to RAI ML14178B2322014-07-14014 July 2014 Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.3.2 Setpoint Project stage: RAI ML14231A6342014-09-10010 September 2014 Issuance of Amendments Regarding Technical Specification 3.8.4, DC Sources-Operating, Project stage: Approval ML15202A6612015-07-27027 July 2015 Acceptance Review of License Amendment Request Temporary Changes to Technical Specifications for Correction of Nuclear Service Water System Degraded Condition Project stage: Acceptance Review ML15196A3862015-08-0404 August 2015 Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing and Order Imposing Procedures for Document Access To.. Project stage: Other MNS-15-062, Response to Request for Additional Information Regarding License Amendment Request (LAR) for Temporary Changes to Technical Specifications for Correction of an 'A' Train Nuclear Service Water System (Nsws) Degraded Condition2015-08-11011 August 2015 Response to Request for Additional Information Regarding License Amendment Request (LAR) for Temporary Changes to Technical Specifications for Correction of an 'A' Train Nuclear Service Water System (Nsws) Degraded Condition Project stage: Response to RAI ML15196A6162015-08-13013 August 2015 Duke Energy Carolinas, LLC, McGuire Nuclear Station, Units 1 and 2 - License Amendment Application; Opportunity to Comment, Request a Hearing, and Petition for Leave to Intervene; Order Project stage: Other ML15243A4082015-08-28028 August 2015 NRR E-mail Capture - Draft RAI for Nsws Temp AOT Extension Project stage: Draft RAI ML15252A2762015-09-14014 September 2015 Request for Additional Information Regarding License Amendment Request Nuclear Service Water System Allowed Outage Time Extension Project stage: RAI MNS-15-073, Response to NRC Letter Dated August 27, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension2015-09-24024 September 2015 Response to NRC Letter Dated August 27, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension Project stage: Request MNS-15-078, Response to NRC Letter Dated September 14, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension2015-10-0808 October 2015 Response to NRC Letter Dated September 14, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension Project stage: Request ML15289A5552015-10-26026 October 2015 Request for Additional Information Regarding License Amendment Request Nuclear Service Water System Allowed Outage Time Extension Project stage: RAI ML15343A0122015-12-0707 December 2015 Response to NRC Letter Dated 10/26/2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension. Project stage: Request MNS-16-005, Response to Request for Additional Information (RAI) During January 12, 2016, NRC Teleconference Pertaining to License Amendment Request for Nuclear Service Water System Allowed Outage Time Extension2016-02-10010 February 2016 Response to Request for Additional Information (RAI) During January 12, 2016, NRC Teleconference Pertaining to License Amendment Request for Nuclear Service Water System Allowed Outage Time Extension Project stage: Response to RAI 2015-12-07
[Table View] |
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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
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 10, 2014 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
~MENDMENTS REGARDING TECHNICAL SPECIFIC~TION 3.8.4, "DC fOURCES-OPERATING" (TAC NOS. MF2983 AND M,2984)
Dear Mr. Capps:
By letter dated October 28, 2013\ as supplemented by letter dated June 3, 2014, 2 Duke Energy Carolinas, LLC (Duke, the licensee), submitted a license amendment request to modify Technical Specification 3.8.4, "DC Sources-Operating." Specifically, the change provides a one-time extension to the completion time for Required Action A.2.2 to support replacement of the existing shared 125 VDC vital batteries.
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 274 to Renewed Facility Operating License NPF-9 and Amendment No. 254 to Renewed Facility Operating Licenses NPF-17 for the McGuire Nuclear Station, Units 1 and 2, respectively.
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.
1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML133048445.
2 ADAMS Accession No. ML14164A028.
S. Capps If you have any questions, please call me at 301-415-2481.
Sincerely, ~ .
G. (£;:.,, Pr~j,:c~nager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosures:
c
- 1. Amendment No. 274 to NPF-9
- 2. Amendment No. 254 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. 27 4 Renewed License No. NPF-9
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amend merit to the McGuire Nuclear Station, Unit 1 (the facility),
Renewed Facility Operating License No. NPF-9, filed by Duke Energy Carolinas, LLC (the licensee), dated October 28, 2013, as supplemented by letter dated June 3, 2014, 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 ali applicable requirements have been satisfied.
- 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. 274, 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. Implementation of the amendment shall include updating the UFSAR in accordance with 10 CFR 50.71 (e). This update shall include a statement that the license shall implement the twelve compensatory measures enumerated in Section 3.6 of the licensees October 28, 2013, license amendment request.
FOR THE NUCLEAR REGULATORY COMMISSION 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: September 10, 2014
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. 254 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 Duke Energy Carolinas, LLC (the licensee), dated October 28, 2013, as supplemented by letter dated June 3, 2014, 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. 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. 254, 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. Implementation of the amendment shall include updating the UFSAR in accordance with 10 CFR 50.71 (e). This update shall include a statement that the license shall implement the twelve compensatory measures enumerated in Section 3.6 of the licensees October 28, 2013, license amendment request.
FOR THE NUCLEAR REGULATORY COMMISSION.
-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 10, 2014
ATTACHMENT TO LICENSE AMENDMENT NO. 274 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND LICENSE AMENDMENT NO. 254 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' Licenses Licenses NPF-9, page 3 NPF-9, page 3 NPF-17, page 3 NPF-17, page 3 TSs TSs 3.8.4-1 3.8.4-1
(4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; *
(5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of McGuire Nuclear Station, Units 1 and 2, and; (6) Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at a reactor core full steady state power level of 3469 megawatts thermal (100%). *
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No)2'74are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on December 16,2002, describes certain future activities to be completed before the period of extended operation.
Duke shall complete these activities no later than June 12, 2021, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.
The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71 (e)(4), following issuance of this renewed operating license.
Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
Renewed License_No. NPF-9
(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 1o CFR Parts 30, 40 and 70, to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of McGuire Nuclear 'Station, Units 1 and 2; and, (6) Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.
C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level The licensee is authorized to operate the facility at a reactor core full steady state power level of 3469 megawatts thermal (1 00%).
(2) - Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No;,254are 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 A'nalysis Report required by 10 CFR 50.71 (e)(4), following issuance of this renewed operating license.
Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59, and otherwise complies with the requirements in that section. **
Renewed License No. NPF-17 Amendment No-254-
DC Sources - Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources- Operating LCO 3.8.4 The four channels of DC sources shall be OPERABLE.
APPLICABILITY: i MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel of DC A.1 Restore channel of DC 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> source inoperable. source to OPERABLE status.
OR A.2.1 Verify associated bus tie 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> breakers are closed between DC channels.
AND I : A.2.2 Restore channel of DC 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s*
source to OPERABLE status.
B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />
- The Completion' Time that one channel of DC source can be inoperable as specified by Required Action A.2.2 may be extended beyond the "72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />" for up to 14 days as part of the battery replacement project. This allowance may be used one-time for each of the four DC channels. Upon completion of the battery replacement project, this footnote is no longer applicable and will expire on December 31, 2016.
McGuire Units 1 and 2 3.8.4-1 Amendment No.
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 274 TO RENEWED FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT NO. 254 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 letter dated October 28, 2013, as supplemented by letter dated June 3, 2014, Duke Energy Carolinas, LLC (Duke, the licensee), submitted a license amendment request (LAR) to modify Technical Specification (TS) 3.8.4, "DC Sources-Operating." Specifically, the change would provide a one-time extension to the completion time for Required Action A.2.2 to support replacement of the existing shared 125 VDC vital batteries. The supplement clarified the application, did not expand the scope, and did not change the NRC staff's original proposed no
. significant hazards consideration determination as published in the Federal Register on January 21, 2014 (79 FR 3415).
2.0 REGULATORY EVALUATION
10 CFR 50.36(c)(2)(i) states, in part, that limiting conditions for operation (LCOs) 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. Typically, the remedial actions are to return the plant to compliance with the LCO in an appropriate time-frame.
NUREG-0800, Branch Technical Position (BTP) 8-8, "Onsite Emergency Diesel Generators (EDGs) and Offsite Power Sources Allowed Outage Time Extensions," provides guidance to the NRC staff in reviewing LARs proposing to extend the allowed outage time for onsite and offsite
- power sources beyond 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
3.0 TECHNICAL EVALUATION
3.1 Description of the Electrical Power System Each nuclear unit generates power at 24 Kilo-Volts (kV) and supplies power from the generator to two independent unit step-up transformers that increase the voltage from 24 kV to 230 kV. The power from Unit 1 and Unit 2 is then transmitted via four separate and independent overhead transmission lines to common 230 kV and 525 kV switching stations. The normal power supply to the auxiliary power transformers is the 24 kV unit generator and the preferred power supply is the 230 kV and 525 kV switching stations. Each unit is provided with two auxiliary power transformers which are sized to carry all of the auxiliaries of one operating nuc,Jear unit and the safety shutdown
- loads of the other nuclear unit. The 6900 Volt Normal Auxiliary Power System provides power to all of the large station auxiliary loads and the two redundant and independent 4160 Volt Essential Auxiliary Power Systems of each unit. Each of the 4160 Volt Essential Auxiliary Power Systems has a diesel-engine generator connected to it that will automatically start and supply power in the event that power supplied from the 6900 bus is not available. Together the two 4160 Essential Auxiliary Power Systems for each unit have sufficient independence, redundancy and testability to perform their safety functions assuming a single failure.
The On site DC Power Systems consist of one 250 VDC and two 125 VDC systems. The 125 VDC Vital Instrumentation and Control (I&C} Power System is provided to supply power to nuclear safety-related I&C loads requiring an uninterrupted power source to maintain safe reactor status.
The 125 VDC I&C power system consists of four independent and physically separate load channels with each serving both units. A load channel is comprised of a battery, charger connection box, battery charger, 125 VDC distribution center provided with undervoltage and ground detection equipment, and two 125 VDC power panelboards (one for each unit). Since the 125 VDC I&C power system is a safety-related system, each battery is separately housed in a ventilated room apart from its charger and distribution centers, and all related equipment is located in tt)e Auxiliary Building (Category 1 structure). Each vital battery bank consists of 60 GNB NCN-27 Flooded Lead Calcium (1945 Amp-Hr) battery cells, which were procured thro_ugh a third party qualifier, Nuclear Logistics, Inc. (NLI).
3.2 Proposed TS Change The 125 VDC vital batteries were last replaced in 1997 under a risk-informed one-time TS change.
All four battery channels are currently operable, but are nearing their 20 year nominal service life.
Battery replacement is currently scheduled for 2015 and 2016. Since battery replacement cannot be accomplished within the Completion Time (CT) currently allowed by TS 3.8.4 due to the number of activities, inspections, and tests, the licensee proposed a revision to the CT for Required Action A.2.2 of TS 3.8.4, "Restore channel of DC source to OPERABLE status," from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 14 days on a one-time temporary basis. A footnote would be added to the TS page stating: * ,
"The Completion Time that one channel of DC source can be inoperable as specified by Required Action A.2.2 may be extended beyond the "72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />" for up to a total of 14 days as part of the battery replacement project. This allowance may be used one-time for each of the four DC channels. Upon completion of the battery replacement project, this footnote is no longer applicable and will expire on December 31, 2016."
Battery replacement cannot be performed during a single unit refueling outage since the batteries are shared between the two units. Therefore the licensee's proposed LAR would allow replacement of the existing 125 VDC vital batteries while at power. During each vital battery replacement, the associated DC channel will remain energized by being cross-tied (bus tie with breakers) to another operable DC channel as allowed by TS 3.8.4 Condition A.2.1. The licensee also proposed a supplemental or an alternate power source consisting of a temporary battery as a backup DC power supply.
3.3 Compensatory Measures The licensee described the following compensatory measures that would be implemented to limit plant vulnerabilities during the battery replacement evolutions:
COMPENSATORY MEASURE 1a. During replacement of battery EVCA, the following systems and components will be protected and elective maintenance deferred:
- Unit 1 and 2 main step-up transformer yard
- Unit 1 and 2 6.9kV switchgear room .
- Component Cooling water trains (KC) 1B, 28
- Unit 1 and 2 Turbine driven CA pumps
- Diesei_Qowered Instrument Air _{VI) compressors G, H 2b. During replacement of battery EVCB, the following systems and components will be protected and elective maintenance deferred:
- Unit 1 and 2 main step-up transformer yard
- Unit 1 and 2 6.9kV switctigear room
- Motor driven CA pumps 1A, 2A
- . _Unit 1 and 2 Turbine driven CA pumps
- . Diesel powered VI compressors G, H 3c. During replacement of battery EVCC, the following systems and components will be protected and elective maintenance deferred:
- Unit 1 and 2 main step-up transformer yard
o Unit 1 and 2 6.9kV switchgear room
- Motor driven CA pumps 1B, 28
- Unit 1 and 2 Turbine driven CA pumps
- Diesel powered VI compressors G, H 4d. During replacement of battery EVCD, the following systems and components will be protected and elective maintenance deferred:
- Unit 1 and 2 main step-up transformer yard
- Unit 1 and 2 6.9kV switchgear room '*
- Motor driven CA pumps 1A, 2A
- Unit 1 and 2 Turbine driven CA pumps
- Diesel powered VI compressors G, H
- 2. A temporary battery located in the Service Building is available as a defense in depth measure. The temporary battery will be charged and has the necessary connections to tie-in to any of the four DC distribution centers, if necessary.
- 3. The ambient temperature and hydrogen concentration of the area containing the temporary battery will be monitored once per a 12-hour shift to ensure th~}'_ remain within battery specifications.
- 4. The ventilation in the area containing the temporary battery will be supplemented with fans to ensure good air flow and mixing across the temporar}'_ battery.
- 5. Appropriate training will be provided to Operational Sliift personnel, maintenance, and vendor technicians regarding the vital battery replacement evolution, emergency procedures, and temporary battery alignment. *
- 6. Alignment procedures for the temporary battery will be in place for Operations.
- 7. The manual connections to the temporary battery are designed to be accomplished by Operations within 60 minutes once it has been determined it can be done safely and this strategy is desired to support event recovery.
- 8. Pre-job briefings will be provided to Maintena~*ce and Vendor personnel
- each shift during the vital battery replacement evolutions.
- 9. The temporary battery will receive a full complement of TS surveillances tests including a Modified Performance Test prior to the first vital battery re_Qiacement.
- 10. All applicable TS surveillance tests will be performed on the temporary battery configuration during periods of battery bank re_Qiacement.
- 11. Prior to the start of each TS Completion Time extension and daily thereafter, McGuire will monitor the NationaiWeather Service for potential severe weather conditions. To the extent practical, severe weather conditions will be avoided.
- 12. Prior to the start of each TS Completion Time extension and daily thereafter, McGuire will contact the Transmission Control Center (TCC) regarding system grid stability. To the extent practical, system grid instability will be avoided.
3.4 NRC Staff Review The licensee stated that the 125 VDC vital batteries are currently operable but are nearing their 20 year nominal service life, with industry operating experience indicating that 15 to 18 years is a much closer approximation. The licensee's recent tests have indicated that three of the four*
batteries have capacity over 100% while the fourth battery has capacity of 99%. The licensee stated that the new vital batteries, which are scheduled for 2015 and 2016 installation, are essentially the same, having the same size and material and will meet the current licensing basis and perform the same safety functions as the existing batteries. Therefore, this NRC staff evaluation does not address the appropriateness of the replacement batteries. Instead, this evaluation considers the appropriateness of the one-time extension to the completion time for the required action to restore operability when one channel is inoperable. The licensee should use their existing 10 CFR 50.59 evaluation process to determine if the plant modification itself needs prior regulatory approval.
The battery replacement process will include the individual disconnection and removal of each of the old batteries cells, the individual installation of each of the new batteries cells and the installation of all the new intercell connectors, intertier jumpers and cables. After the installation of each of the batteries they will be charged, voltage and resistance measurements will be taken and tested in accordance with IEEE Standard 450. The licensee provided a timetable with all the required steps for the battery replacement process and a determination that the process will take a maximum of approximately 14 days. The NRC staff considers this a reasonable time-frame for the described evolution.
In considering the appropriateness of the one-time extension, the NRC staff considered how the compensatory measures proposed by the licensee address the following four categories:
- 1. Ensuring that a plant transient is unlikely when the channel is inoperable;
- 2. Ensuring that redundant, installed, equipment is available if a transient occurs when .the channel is inoperable;
- 3. Providing additional resources to supplant the inoperable equipment if a transient occurs when the channel is inoperable; and
- 4. Ensuring that the additional resources don't adversely affect the plant Compensatory measures 11 and 12 describe the licensee's actions to verify that conditions external to the plant do not carry an increased risk of transient. The NRC staff considers licensee's verification of weather and grid conditions to be appropriate for ensuring that a plant transient is unlikely during the battery replacement.
- Compensatory measures 1a, 1b, 1c, and 1d, describe the plant equipment that the licensee will consider "protected" and to which they will defer elective maintenance during the extended completion time. Tlie NRC staff considers that protection of the equipment described in each compensatory measure will reasonably ensure that redundant, installed, equipment is available to respond to a transient, if one occurs during the battery replacement.
Compensatory measures 2, 5, 6, 7, 8, 9, and 10 describe temporary equipment, activities, and procedures that the licensee will provide and implement during the extended completion time to supplant the inoperable battery. During the replacement of the vital batteries the licensee will have a temporary battery ready to be used in the event of the loss of the battery supporting the cross-tied channels. The temporary battery is identical to the new batteries and prior to the removal of the fourth battery it will be installed as one of the new vital batteries, while one of the old batteries will be set up as the temporary battery. The temporary battery will be connected to the DC side of a standby battery charger and it will remain electrically isolated from the Vital DC distribution centers. By letter dated May 12, 2014 (ADAMS Agencywide Documents Access and Management System Accession No. ML14127A462), the NRC staff requested additional*
information on the design and capability of the temporary battery charger. In its June 3, 2014, response, the licensee stated that the temporary charger is a commercial grade charger powered from a non-safety source and it's intended to maintain the temporary battery on a float charge.
The temporary charger will be isolated via a breaker or disconnect switch if the temporary battery is required. Per design the battery will be manually tied in and the operation can be accomplished within an hour. In its October 28, 2013, applic~tion, the licensee stated that all applicable TS surveillance tests will be pertormed on the temporary battery, prior to and during battery repiacement evolutions. The NRC staff considers the alternate means of providing DC power to the affected channel supportive of the one-time completion time extension for the battery replacement.
Compensatory measures 3 and 4 describe equipment, activities, and procedures that the licensee will provide and implement during the extended completion time to ensure that temporary equipment does not have an adverse impact on the plant.
The proposed temporary installation of the back-up battery/charger would introduce fire hazards in terms of potential hydrogen concentration and combustible loading increase in the affected areas. The licensee stated that an analysis of the temporary battery hydrogen production has validated that the existing ventilation in the affected area prevents hydrogen concentrations greater than 2%. In addition, ventilation in the area will be supplemented with fans to ensure good air flow and mixing across the temporary battery. The ambient terT)perature and hydrogen concentration in the area will also be monitored once per 12-hour shift to endure they remain within battery specifications.
The temporary equipment introduGes additional combustibles to the fire area (Room 700 of the Service Building). Any fire involving the temporary battery is not expected to impact the ,
- permanent batteries, because the temporary battery area is separated from the permanent battery rooms by 3-hour rated barriers. The licensee also indicated a fire in the temporary battery ar~a will not impact other plant areas since the temporary battery area is separated from other plant areas by 3-hour rated barriers, and existing hatch door and fire stops would prevent a fire from spreading into the Auxiliary Building. Whenever the hatch door is opened, a security guard will be stationed there to close the hatch if necessary. Fire detection instrumentation is also
provided in the area, which annunciate to the Main Control Room. Therefore, there is a low likelihood that the temporary equipment wi'll adversely affect the plant during the battery replac'ement.
The NRC staff notes that the temporary TS change also will not impact McGuire's transition to 10 CFR50.48(c), National Fire Protection Standard NFPA 805, which is currently under separate NRC review. This is because the temporary TS change can be carried forward during transition as a previously approved fire protection program element per NFPA 805, Chapter 2.
Based on the above, the NRC staff concludes that the licensee has provided adequate compensatory measures and maintained defense-in-depth such that the proposed one-time extension of the completion time for Required Action A.2.2 is consistent with 10 CFR 50.36 and the guidance provided in BTP 8~8.
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, which was published in the
- Federal Register on January 21, 2014 (79 FR 3415). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the 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 Contributors: T. Dinh S. Basturescu E. Miller Date: September 10, 2014
ML14231A634 *Via e-mail OFFICE N RRILPL2-1 /PM NRR/LPL2-1/LA NRRIDRA/AFPB/BC DSS/STSB/BC NAME GEMiller SFigueroa AKiein* REIIiot DATE 08/22/14 08/20/14 04/04/14 08/25/14 OGC OFFICE NRR/DE/EEEB/BC NRR/LPL2-1/BC NRR/LPL2-1/PM
/NLO w/coments NAME JZimmerman Jlindell RPascarelli GEMiller DATE 08/22/14 09/08/14 09/10/14 09/10/14