Letter Sequence Approval |
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MONTHYEARML0730604052007-10-31031 October 2007 Tech Spec Pages for Amendment 237 Regarding Extension of Time Limit to Complete Emergency Core Cooling Systems Sump Modification Project stage: Other ML0727400622007-10-31031 October 2007 Issuance of License Amendment 237 Regarding Extension of Time Limit to Complete Emergency Core Cooling Systems Sump Modification Project stage: Approval 2007-10-31
[Table View] |
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Category:Letter
MONTHYEARIR 05000413/20230042024-02-0202 February 2024 Integrated Inspection Report 05000413-2023004 and 05000414-2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting 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 05000413/20230102023-10-11011 October 2023 NRC Inspection Report 05000413/2023010 and 05000414/2023010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000413/20230052023-08-25025 August 2023 Updated Inspection Plan for Catawba Nuclear Station Units 1 and 2 (Report 05000413/2023005 and 05000414/2023005) ML23233A1692023-08-17017 August 2023 EN 56683 - Curtiss Wright, Interim Notification Report for PotentialPurt2l IR 05000413/20230022023-07-25025 July 2023 Integrated Inspection Report 05000413/2023002 and 05000414/2023002 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 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 IR 05000413/20230012023-05-0505 May 2023 Integrated Inspection Report 05000413/2023001 and 05000414/2023001 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 05000413/20230112023-04-25025 April 2023 Focused Engineering Inspection Report 05000413/2023011 and 05000414/2023011 ML23107A2542023-04-14014 April 2023 301 Examination Report Letter and Report (Merged) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000413/20220062023-03-0101 March 2023 Annual Assessment Letter for Catawba Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000413/2022006 and 05000414/2022006) IR 05000413/20234012023-03-0101 March 2023 Security Baseline Inspection Report 05000413 2023401 and 05000414 2023401 IR 05000413/20233012023-02-17017 February 2023 Operator Licensing Examination Approval 05000413/2023301 and 05000414/2023301 IR 05000413/20220042023-01-31031 January 2023 Integrated Inspection Report 05000413/2022004 and 05000414/2022004 IR 05000413/20220112022-12-15015 December 2022 Biennial Problem Identification and Resolution Inspection Report 05000413/2022011 and 05000414/2022011 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 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 IR 05000413/20224032022-11-17017 November 2022 Cyber Security Inspection Report 05000413/2022403 and 05000414/2022403 (Public) ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22319A0942022-11-10010 November 2022 EN 56219 - Flowserve. 10 CFR Part 21 Report 38878-8 Solenoid Valve at Duke, Catawba Flowserve Evaluation 105 IR 05000414/20220032022-10-31031 October 2022 Integrated Inspection Report 05000414/2022003 and 05000414/2022003 IR 05000413/20224022022-10-28028 October 2022 Security Baseline Inspection Report 05000413 2022402 and 05000414 2022402 ML22297A2642022-10-25025 October 2022 Project Manager Assignment ML22276A2492022-10-25025 October 2022 Completion of License Renewal Commitment No. 10, Aging Management of Environmentally Assisted Fatigue ML22303A0052022-10-24024 October 2022 EN 56178 - Tioga Final. LTR-TP-22-29 2021 10CFR Part 21 Improper Notification of NRC 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 ML22231B1362022-09-0101 September 2022 Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi ML22303A0042022-08-31031 August 2022 Final Report Notification Pursuant to 10 CFR Part 21.21, Regarding Supply of 6 NPS Sch. 40 Seamless Stainless-Steel Pipe; Manufacturer: Maxim Tubes Company Pvt. Ltd.; Heat No: N200309AW01, SR No: 7; 9 Pcs; 180 Feet Total Procured as Unquali IR 05000413/20220052022-08-26026 August 2022 Updated Inspection Plan for Catawba Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000413/2022005 and 05000414/2022005 ML22217A0792022-08-0303 August 2022 301, Corporate Notification Letter (210-day Ltr) IR 05000413/20220022022-07-29029 July 2022 Integrated Inspection Report 05000413/2022002 and 05000414/2022002 IR 07200045/20220012022-07-26026 July 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200045/2022001 ML22215A2502022-07-25025 July 2022 EN 55960 - Update - Curtiss Wright IR 05000413/20220102022-07-21021 July 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000413/2022010 and 05000414/2022010 ML22195A2432022-07-19019 July 2022 Request for Withholding Information from Public Disclosure Regarding Reactor Vessel Closure Head Repair Alternative 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 ML22199A2552022-07-0606 July 2022 Ds Catawba 2022 RQ Inspection Notification Letter ML22222A0092022-07-0101 July 2022 EN 55974 - Flowserve, Part 21 Report Re Solenoid Coil Failure of Model 38878-8 Solenoid Valve at Catawba Nuclear Station for Use on FWIV Actuator ML22175A0342022-06-28028 June 2022 Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000413/2022403 and 05000414/2022403 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 ML22111A3572022-05-16016 May 2022 Letter Issuing Exemption to Catawba IR 05000414/20220012022-04-28028 April 2022 Integrated Inspection Report 05000413/ 2022001 and 05000414/2022001 2024-02-02
[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 ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22276A2492022-10-25025 October 2022 Completion of License Renewal Commitment No. 10, Aging Management of Environmentally Assisted Fatigue 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 ML20174A0452020-08-0404 August 2020 Issuance of Amendment No. 306 to Revise Technical Specification 3.4.3, RCS (Reactor Coolant System) Pressure and Temperature (P/T) Limits ML19296D1192020-01-31031 January 2020 Issuance of Amendment Nos. 305 and 301 to Revise Technical Specification 3.0, Surveillance Requirement (SR) Applicability ML19212A6552019-08-27027 August 2019 Issuance of Amendment Nos. 304 and 300 to Technical Specification 3.8.1, AC Sources - Operating ML19121A5512019-06-17017 June 2019 Issuance of Amendments Related to the Removal of Containment Valve Injection Water System Supply from Specified Containment Isolation Valves 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 ML18275A2782018-11-28028 November 2018 Issuance of Amendments Related to the Nuclear Service Water System New Condition for Single Pond Return Header Configuration ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application ML17296A2082018-01-0404 January 2018 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-197-A, Revision 2 (CAC Nos. MF8971 & MF8972, EPID L-2016-LLA-0026) ML17254A1442017-10-23023 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-352-A, Revision 1 (CAC Nos. MF8969 and MF8970; EPID L-2017-LLA-0031) ML17257A2972017-10-23023 October 2017 Issuance of Amendment Nos. 295 and 291, Adoption of TSTF-340-A, Revision 3, Allow 7-Day Completion Time for a Turbine-Driven AFW Pump Inoperable (CAC Nos. MF8979 and MF8980; EPID L-2017-LLA-0043) ML17261B2902017-10-23023 October 2017 Issuance of Amendment Nos. 296 and 292, Adopt TSTF-142-A, Revision 0, Increase the Completion Time When the Core Reactivity Balance Is Not within Limit (CAC Nos. MF8962 and MF8963); EPID L-2017-LLA-0024 ML17249A1352017-09-29029 September 2017 Issuance of Amendments Adopting Technical Specifications Task Force Travelers TSTF-349-A, Revision 1, TSTF-361-A, Revision 2, and TSTF-438-A, Revision 0 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) ML17172A4282017-07-26026 July 2017 Issuance of Amendments Adopting Technical Specification Task Force Traveler TSTF-315-A, Revision 0 ML17144A0342017-06-19019 June 2017 Correction Letter to Amendment Nos. 287 and 283 National Fire Protection Association Standard NFPA 805 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) ML16137A3082017-02-0808 February 2017 Issuance of Amendments Regarding National Fire Protection Association Standard NFPA 805 ML16229A1132016-09-12012 September 2016 Issuance of Amendments Regarding Extension of the Containment Integrated Leak Rate Test Intervals 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 ML16124A6942016-06-0202 June 2016 Issuance of Amendments Regarding Changes to Technical Specification 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 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) ML16081A3332016-04-29029 April 2016 Issuance of Amendments Regarding Measurement Uncertainty Recapture Power Uprate 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. ML16082A0382016-04-18018 April 2016 Issuance of License Amendment Regarding Emergency Action Level Scheme Change ML16067A2292016-04-0808 April 2016 Issuance of Amendments Regarding Removal of Obsolete Technical Specification Requirements ML15320A3332015-12-18018 December 2015 Issuance of Amendments Regarding Non-Conservative Technical Specifications Allowable Value 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. ML15027A3662015-03-25025 March 2015 Issuance of Amendments DPC-NE-3001-P, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology 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 ML14056A2172014-02-27027 February 2014 Issuance of Amendments Regarding Exigent License Amendment Request to Revise Technical Specification 3.3.4, Remote Shutdown System (TAC MF3473&74) ML13169A1392013-08-0909 August 2013 Issuance of Amendments Regarding Technical Specifications Changes for Nuclear Service Water System ML13168A0762013-07-16016 July 2013 Issuance of Amendments Regarding Changes to Technical Specification (TS) 3.6.14, Divider Barrier Integrity (TAC Nos. MF0620, MF0621, Mf 0626 and MF0627) ML12166A0222012-07-25025 July 2012 Issuance of Amendments Regarding Deletion of Superseded Technical Specification Requirements Following Implementation of the Emergency Core Cooling System Water Management Initiative 2023-08-29
[Table view] Category:Safety Evaluation
MONTHYEARML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 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 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 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22213A2532022-08-31031 August 2022 Authorization and Safety Evaluation for Alternative Request RA-21-0144 to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method 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 ML22007A3452022-01-11011 January 2022 Proposed Alternative to Use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885 ML21266A0112021-10-0505 October 2021 Staff Evaluation Related to Aging Management Program and Inspection Plan of Reactor Vessel Internals Per MRP-227, Revision 1-A ML21253A0822021-09-20020 September 2021 Proposed Alternative Request RA-21-0145 to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method 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 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 ML20174A0452020-08-0404 August 2020 Issuance of Amendment No. 306 to Revise Technical Specification 3.4.3, RCS (Reactor Coolant System) Pressure and Temperature (P/T) Limits ML19296D1192020-01-31031 January 2020 Issuance of Amendment Nos. 305 and 301 to Revise Technical Specification 3.0, Surveillance Requirement (SR) Applicability 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 ML19212A6552019-08-27027 August 2019 Issuance of Amendment Nos. 304 and 300 to Technical Specification 3.8.1, AC Sources - Operating ML19191A0612019-07-15015 July 2019 Review of the Steam Generator Tube Inservice Inspection Report for the Fall 2018 Refueling Outage 24 ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs ML19128A3262019-06-20020 June 2019 Alternative to Depth Sizing Qualification Examination of Welds ML19121A5512019-06-17017 June 2019 Issuance of Amendments Related to the Removal of Containment Valve Injection Water System Supply from Specified Containment Isolation Valves 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 ML18275A2782018-11-28028 November 2018 Issuance of Amendments Related to the Nuclear Service Water System New Condition for Single Pond Return Header Configuration ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application ML18016A1782018-01-24024 January 2018 Request for Relief No. 17-CN-001, Regarding Category B-J Pressure Retaining Welds for the Third 10-Year Inservice Testing Interval (CAC Nos. MF9807 and MF9808; EPID L-2017-LLA-0032) ML17296A2082018-01-0404 January 2018 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-197-A, Revision 2 (CAC Nos. MF8971 & MF8972, EPID L-2016-LLA-0026) ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML17261B2902017-10-23023 October 2017 Issuance of Amendment Nos. 296 and 292, Adopt TSTF-142-A, Revision 0, Increase the Completion Time When the Core Reactivity Balance Is Not within Limit (CAC Nos. MF8962 and MF8963); EPID L-2017-LLA-0024 ML17257A2972017-10-23023 October 2017 Issuance of Amendment Nos. 295 and 291, Adoption of TSTF-340-A, Revision 3, Allow 7-Day Completion Time for a Turbine-Driven AFW Pump Inoperable (CAC Nos. MF8979 and MF8980; EPID L-2017-LLA-0043) ML17254A1442017-10-23023 October 2017 Issuance of Amendments Adopting Technical Specifications Task Force Traveler TSTF-352-A, Revision 1 (CAC Nos. MF8969 and MF8970; EPID L-2017-LLA-0031) ML17249A1352017-09-29029 September 2017 Issuance of Amendments Adopting Technical Specifications Task Force Travelers TSTF-349-A, Revision 1, TSTF-361-A, Revision 2, and TSTF-438-A, Revision 0 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) ML17172A4282017-07-26026 July 2017 Issuance of Amendments Adopting Technical Specification Task Force Traveler TSTF-315-A, Revision 0 ML17165A4412017-07-21021 July 2017 Issuance of Amendments Adopting Technical Specification Task Force Traveler TSTF-269-A, Revision 2 (CAC Nos. MF8983 and MF8984). 08/10/2017 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) ML16137A3082017-02-0808 February 2017 Issuance of Amendments Regarding National Fire Protection Association Standard NFPA 805 ML16277A4042016-10-20020 October 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16208A2832016-08-0808 August 2016 Correction to Issuance of Amendments Regarding Use of Optimized Zirlo ML16159A3362016-07-19019 July 2016 Issuance of Amendments Regarding Request to Use an Alternate Fission Gas Gap Release Fraction (CAC Nos. MF6480 Through MF6486) ML16105A3262016-06-21021 June 2016 Issuance of Amendments Regarding Use of Optimized Zirlo ML16124A6942016-06-0202 June 2016 Issuance of Amendments Regarding Changes to Technical Specification 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 2023-09-25
[Table view] |
Text
October 31, 2007
Mr. J. R. Morris Site Vice President Catawba Nuclear Station Duke Power Company LLC 4800 Concord Road York, SC 29745
SUBJECT:
CATAWBA NUCLEAR STATION, UNIT 1 (CATAWBA UNIT 1), ISSUANCE OF AMENDMENT REGARDING EXTENSION OF TIME LIMIT TO COMPLETE EMERGENCY CORE COOLING SYSTEMS SUMP MODIFICATION (TAC NOS.
MD3443 AND MD3777)
Dear Mr. Morris:
The Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 237 to Renewed Facility O perating License NPF-35 for Catawba, Unit 1. The amendment consists of changes to the operating license in response to your application dated November 22, 2006.
The amendment revises the Catawba Unit 1 Facility Operating License (FOL) to add a license condition requiring a specific date by which the modifications to the Emergency Core Cooling Systems (ECCS) sump in response to 2004 Generic Letter (GL) 2004-02, APotential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors.
@ The changes add a license condition which requires that 1) Catawba Unit 1 will enter Mode 5 for the outage to install the sump strainer modification no later than May 19, 2008, and that 2) t he Unit 1 sump strainer modification will be completed prior to entry into Mode 4 after May 19, 2008.
By letter dated November 1, 2006, the licensee requested an extension to the December 31, 2007, completion deadline for modification associated with GL 2004-02. The NRC staff has reviewed the licensee
=s justification for the extension and determined that it is acceptable to extend the completion date for the passive strainer installation for Catawba Unit 1 until May 19, 2008.
A copy of the related Safety Ev aluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/ John Stang, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket No. 50-413
Enclosures:
- 1. Amendment No. 237 to NPF-35
- 2. Safety Evaluation
cc w/encls: See next page
A copy of the related Safety Ev aluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
/RA/ John Stang, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket No. 50-413
Enclosures:
- 1. Amendment No. 237 to NPF-35
- 2. Safety Evaluation
cc w/encls: See next page
DISTRIBUTION
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=Brien (hard copy) RidsNrrSscb(MScott) Package No.: ML073020190 Amendment No.: ML072740062 Tech Spec No.: ML073060405 *Memo transmitting SE dated OFFICE NRR/LPL3-1/PE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/SSIB/BC OGC NRR/LPL2-1/BC
NAME DWright JStang:nc MO=Brien MScott LSubin EMarinos DATE 10/15/07 10/15/07 10/15/07 12/28/06*
10/24/07 10/31/07 OFFICIAL RECORD COPY
Catawba Nuclear Station, Units 1 & 2 Page 1 of 2
cc:
Site Vice President Catawba Nulcear Station Duke Power Company, LLC 4800 Concord Road York, SC 29745
Associate General Counsel and Managing Attorney Duke Energy Carolinas, LLC 526 South Church Street - EC07H Charlotte, North Carolina 28202
Regulatory Compliance Duke Energy Corporation 4800 Concord Road York, South Carolina 29745
North Carolina Municipal Power Agency Number 1 1427 Meadowwood Boulevard P.O. Box 29513 Raleigh, North Carolina 27626
County Manager of York County York County Courthouse York, South Carolina 29745
Piedmont Municipal Power Agency 121 Village Drive Greer, South Carolina 29651
Assistant Attorney General North Carolina Department of Justice P.O. Box 629 Raleigh, North Carolina 27602
NCEM REP Program Manager 4713 Mail Service Center Raleigh, North Carolina 27699-4713
North Carolina Electric Membership Corp.
P.O. Box 27306 Raleigh, North Carolina 27611
Senior Resident Inspector U.S. Nuclear Regulatory Commission 4830 Concord Road York, South Carolina 29745
Assistant Director Division of Waste Management Bureau of Land and Waste Management Dept. of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201-1708
Manager Nuclear Regulatory Issues and Industry Affairs Duke Energy Corporation 526 South Church Street Mail Stop EC05P Charlotte, North Carolina 28202
Saluda River Electric P.O. Box 929 Laurens, South Carolina 29360
Vice President Customer Relations and Sales Westinghouse Electric Company 6000 Fairview Road 12th Floor Charlotte, North Carolina 28210
Owners Group (NCEMC)
Duke Energy Corporation 4800 Concord Road York, South Carolina 29745
Senior Counsel Duke Energy Carolinas, LLC 526 South Church Street - EC07H Charlotte, NC 28202
Catawba Nuclear Station, Units 1 & 2 Page 2 of 2
cc:
Division of Radiation Protection NC Dept. of Environment, Health, and Natural Resources 3825 Barrett Drive Raleigh, North Carolina 27609-7721
Group Vice President, Nuclear Generation and Chief Nuclear Officer P.O. Box 1006-EC07H Charlotte, NC 28201-1006
DUKE POWER COMPANY LLC
NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION
SALUDA RIVER ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-413
CATAWBA NUCLEAR STATION, UNIT 1
AMENDMENT TO RENEWED FACILITY OPERATING LICENSE
Amendment No. 237 Renewed License No. NPF-35
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility) Renewed Facility Operating License No. NPF-35 filed by the Duke Power Company LLC, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated November 22, 2006, 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, Renewed Facility Operating License No. NPF-52 is hereby amended as indicated in the attachment hereto.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/ Evangelos C. Marinos, Chief Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. NPF-35
Date of Issuance: October 31, 2007 ATTACHMENT TO LICENSE AMENDMENT NO. 237
RENEWED FACILITY OPERATING LICENSE NO. NPF-35
DOCKET NO. 50-413
Replace the following pages of the Renewed Facility Operati ng License and the Appendix B, Additional Conditions with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert License Pages License Pages
NPF-35 page 4 NPF-35 page 4
NPF-35 page 5 NPF-35 page 5
Appendix B page 2 Appendix B page 2
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 237 TO RENEWED FACILITY OPERATING LICENSE NPF-35 DUKE POWER COMPANY LLC CATAWBA NUCLEAR STATION, UNIT 1 DOCKET NO. 50-413
1.0 INTRODUCTION
By letter dated September 1, 2005 response (Agencywide Documents Access and Management System (ADAMS) Accession No. ML052500399) to Generic Letter (GL) 2004-02, APotential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors,@ Duke Power Company LLC, (the licnsee) committed to install a new approximately 2000 square foot surface area containment sump strainer in Catawba Nuclear Station, Unit 1 (Catawba Unit 1), during its fall 2006 refueling outage. Due to a delay in the completion of the final design of the sump strainer modification for Unit 1 and materials needed for prefabrication and mock-up work for the modification were significantly behind schedule, the licensee by letter dated November 1, 2006 (ADAMS ML063110609), requested an extension to delay the installation of the new containment sump strainer in Unit 1 until the refueling outage scheduled to begin May 19, 2008. In the November 1, 2006, letter, the licensee committed to submit for review and approval additional license conditions to require the above modifications to be completed prior to entry into Mode 4 after May 19, 2008. By application dated November 22, 2006 (ADAMS ML063420125), the licensee requested the additional
conditions be added to the Catawba Unit 1 Facility Operat ing License (FOL).
The proposed changes would revise the Catawba Unit 1 FOL to provide for an extension of the time limit to complete the required modification to the Emergency Core Cooling System (ECCS) sump per GL 2004-02, APotential Impact of Debris Blockage on Emergency Re-circulation Design Basis Accidents at Pressurized Water Reactors.
@ The changes would add a license condition which requires 1) Unit 1 to enter Mode 5 for the outage to install the sump strainer modification no later than May 19, 2008, and 2) the Unit 1 sump strainer modification to be completed prior to entry into Mode 4 after May 19, 2008.
2.0 REGULATORY EVALUATION
GL 2004-02, is part of the regulatory framework the NRC staff is using to address issues associated with Generic Safety Issue (GSI) 191, AAssessment of Debris Accumulation on PWR [Pressurized Water Reactor] Sump Performance,@ to improve evaluation of plant capability to meet Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.46(b)(5),
ALong-term cooling.
@ Section 50.46(b)(5) requires licensees to design their ECCS systems with capability for long-term cooling. After a successful system in itiation, the ECCS must be able to provide cooling to maintain the core temperature at an acceptably low value for a sufficient duration.
GSI-191 concerns the possibility that debris generated by a loss-of-c oolant accident (LOCA) could accumulate on the ECCS sump screen, resulting in a loss of net positive suction head margin. Debris passing through the screen may degrade downstream components such as pumps, valves, and heat exchangers or plug or restrict heat exchanger or fuel flow channels.
These phenomena may prevent the ECCS from meeting the criteria of Section 50.46 of Title10 of the Code of Federal Regulations , AAcceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors.
@ The GL requested all pressurized water reactor (PWR) licensees (1) to use an NRC-approved methodology to perform a mechanistic evaluation of the potential for post-accident debris blockage and operation with debris-laden fluids to impede or prevent the recirculation functions of ECCS and CSS following all postulated accidents for which these recirculation functions are required, and (2) to implement plant modifications or other corrective actions which the evaluation identifies as necessary to ensure system functionality by December 31, 2007.
SECY-16-0078, AStatus of Resolution of GSI-191, Assessment of [Effect of] Debris Accumulation on PWR Sump Performance," dated March 31, 2006, provides criteria for evaluating delay of hardware changes related to the resolution of GSI-191. It states:
Proposed extensions to permit changes at the next outage of opportunity after December 2007 may be acceptable if, based on the licensee
=s request, the NRC staff determines that:
$ the licensee has a plant-specific technical/experimental plan with milestones and schedule to address outstanding technical issues with enough margin to account for uncertainties and
$ the licensee identifies mitigative measures to be put in place prior to December 31, 2007, and adequately describes how these mitigative measures will minimize the risk of degraded ECCS and CSS functions during the extension period.
3.0 TECHNICAL EVALUATION
The licensee stated that there was a delay in the completion of the final design of the sump strainer modification for Catawba Unit 1 largely due to issues related to the final design of the
strainer trash racks. Further, materials for pre-fabrication and mock-up work for the modification were significantly behind schedule.
The licensee therefore proposed in its November 1, 2006, extension request letter, for the fall 2006 Catawba Unit 1 refueling outage, to only tear down and re-route interfering piping and hangers to support efficient strainer installation in the next outage, and to take precise
measurement in containment to facilitate inst allation mounting/support parts fabricat ion. Due to strainer component delivery delay, installation mock-up training has been severely limited.
The licensee stated that the vertical trash rack associated with the strainer vortex suppressor design may impact the ability of the strainer to perform its design function in that a significant pressure drop may occur across the integral trash rack. Further, the licensee believes that the current strainer design with integral trash rack does not meet all the existing detailed requirements outlined in Regulatory Guide 1.82, Rev. 0. Also, the large volume enclosed by the trash rack may cause difficulty in accessing several plant components normally used during outages. By letter dated March 29, 2007 (ADAMS Accession No. ML071020044) , the licensee submitted a license amendment request (LAR) which requested approval of the removal of the trash rack requirement.
The licensee stated that it may be able to reduce the estimated 100 REM ALARA strainer installation penalty through flushing and chemical cleaning processes if the project is implemented in the spring 2008 outage.
The licensee stated that it plans a number of modifications during the fall 2006 outage to address GSI-191 issues:
$ Replacement of NUKON fiberglass blankets from the bottom bowls of the Catawba Unit 1 steam generators with reflective metal insulation (RMI). This will involve removing 400 cubic feet of fibrous insulation (of which approximately 280 cubic feet are below the maximum flood level in containment). The only remaining fiberglass insulation below the
steam generator lateral support will be pads on the reacto r coolant loop pi ping (80 cubic feet per loop).
$ Replacement of Microtherm micro-porous fiber on the reactor vessel head flange with RMI.
$ Replacement of throttle valve orifice plates with smaller diameter plates to allow emergency core cooling system (ECCS) throttle valves to be opened wider than is currently allowed for flow balancing.
The licensee stated that there are a number of favorable site conditions for Catawba Unit 1:
$ Programmatic controls to control design basis accident (DBA) debris
$ Requirements for the identification and repair of qualified coatings, and evaluation, removal and repair of unqualified coatings that may be susceptible to detachment during a DBA.
$ Requirements for containment cleaning. These include extensive cleaning during outages using water spray, vacuuming and hand wiping, in general limited to lower containment that would be submerged during large-break LOCA conditions, with localized washdowns elsewhere as needed. Visual inspections are performed on the remaining areas of containment, and foreign materials are removed as necessary. Material accountability logs are maintained in Modes 1 through 4 for items carried into and out of containment.
$ Operator actions and training in response to Nuclear Regulatory Commission (NRC) Bulletin 2003-01, APotential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors,@ and recommendations made by the industry in WCAP-16204, AEvaluation of Potential ERG [Emergency Response Guideline] and EPG [Emergency Procedure Guideline] Changes to Address NRC Bulletin 2003-01 Recommendations
@: $ Initiation of refueling water storage tank makeup following transfer to recirculation from the containment emergency sump;
$ Earlier shutdown of a containment spray pump when no longer needed to mitigate an event;
$ Operator training on Bulletin 2003-01 ECCS sump clogging operating experience and procedural enhancement;
$ Development of an operator response procedure providing guidance on actions to be taken should both trains of ECCS and containment spray be affected by containment sump blockage;
$ An approved license amendment in response to GL 2004-02 allowing operators to manually start a containment air return fan early during certain small break LOCA events to mitigate the effects of debris accumulation in the containment sump.
$ Conservative assumptions relating to fibrous debris generation due to postulated pipe ruptures:
$ Pipe restraints exist at debris generation limiting break locations;
$ Double ended guillotine breaks for high energy line breaks which adversely affect lower containment are physically impossible due to pipe restraints;
$ Inspections and modifications of the reactor coolant system boundary:
$ Weld overlays on pressurizer nozzle connections during the fall 2006 outage;
$ A volumetric inspection of the reactor vessel head penetrations in the fall 2006 outage;
$ A 100 % bare metal visual inspection of the 58 bottom-mounted reactor coolant system instrumentation penetrations during the fall 2006 outage;
$ A 100% bare metal visual inspection of the 78 pressurizer heater penetrations during the fall 2006 outage; and
$ Walkdowns and American Society of Mechanical EngineersSection XI pressure test to ensure continued integrity of the reactor coolant system.
The licensee has performed a probab ilistic risk assessment (PRA) to specifically address the impact of extending the time for implementing the final sump strainer modification until the May 2008 refueling outage (a 140-day extension from the December 31, 2007. The licensee discussed the PRA methodology and various conservatisms in the PRA (e.g., no credit for the actual emergency coolant and containment spray pump net-positive suction head margin which would exist during a LOCA event). The licensee stated that the PRA demonstrated that the core damage frequency risk associated with extending the modification schedule by 140 days is less than or equal to 1E-6.
The NRC staff has reviewed the PRA results and finds that based on the above the licensee's actions will provide acc eptable strainer function with adequate margin for uncertainties for the 140-day extension time. Further, the NRC staff has concluded that the licensee has put mitigation measures in place to adequately reduce the risk for the requested short extension period. Therefore, the NRC staff finds it acceptable to extend the completion date for the corrective actions for the issues discussed in GL 2004-02 until the completion of the Catawba Unit 1 spring 2008 refueling outage, currently scheduled to begin on May 19, 2008. The new
license conditions assure that Catawba Unit 1 will shut down May 19, 2008, and will not restart until all modifications being made for GL 2004-02 have been completed.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the South 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 re spect 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 (72 FR 11386).
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) such activities will be conducted in compliance with the Commission's regul ations, 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: Leon Whitney
Date: October 31, 2007