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MONTHYEARML14010A4612014-01-15015 January 2014 Acceptance of Requested Licensing Action License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants Project stage: Acceptance Review ML14293A7312014-10-21021 October 2014 Regulatory Audit in Support of the License Amendment Request to Implement a Risk-Informed, Performance-Based, Fire Protection Program Project stage: Other ML14308A0372014-11-20020 November 2014 Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program Project stage: RAI CNS-15-001, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, 75-Day Response to NRC Request for Additional...2015-01-13013 January 2015 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, 75-Day Response to NRC Request for Additional... Project stage: Request CNS-15-018, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, 120-Day Response to NRC RAI2015-02-27027 February 2015 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, 120-Day Response to NRC RAI Project stage: Response to RAI CNS-15-027, License Amendment Request (LAR) to Adopt National Fire Protection Association 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants2015-03-30030 March 2015 License Amendment Request (LAR) to Adopt National Fire Protection Association 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants Project stage: Request ML15099A5872015-04-14014 April 2015 Duke Energy Slides for April 14 Meeting on NFPA-805 for Catawba, McGuire and Robinson Project stage: Meeting ML15110A4532015-04-22022 April 2015 Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program Project stage: RAI ML15125A5212015-05-10010 May 2015 Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program Project stage: RAI ML15147A6762015-06-18018 June 2015 Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program Project stage: RAI ML15169A8752015-06-25025 June 2015 Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program Project stage: RAI ML15175A0712015-07-0202 July 2015 Request for Additional Information Regarding License Amendments Request to Implement a Risk-Informed, Performance-Based Fire Protection Program Project stage: RAI CNS-15-067, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Supplemental Response to NRC Request For..2015-07-15015 July 2015 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Supplemental Response to NRC Request For.. Project stage: Supplement CNS-15-070, Supplemental Response to NRC Request for License Amendment Request to Adopt National Fire Protection Association 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants2015-08-14014 August 2015 Supplemental Response to NRC Request for License Amendment Request to Adopt National Fire Protection Association 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants Project stage: Supplement CNS-15-101, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants2015-12-11011 December 2015 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants Project stage: Request CNS-16-002, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plan, LAR Supplement to Transmit Entire Attachment.2016-01-0707 January 2016 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plan, LAR Supplement to Transmit Entire Attachment. Project stage: Supplement CNS-16-014, License Amendment Request (LAR) to Adopt National Fire Protection (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, LAR Submittal to Correct a Legacy Submittal Discrepancy And.2016-03-23023 March 2016 License Amendment Request (LAR) to Adopt National Fire Protection (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, LAR Submittal to Correct a Legacy Submittal Discrepancy And. Project stage: Request CNS-16-030, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants - LAR Supplement to Address ...2016-06-15015 June 2016 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants - LAR Supplement to Address ... Project stage: Supplement CNS-16-051, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) an2016-08-0202 August 2016 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) and Project stage: Response to RAI CNS-16-064, License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 242016-09-0707 September 2016 License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 24 Project stage: Request CNS-17-004, Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants.2017-01-26026 January 2017 Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants. Project stage: Response to RAI 2015-06-18
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Category:Letter type:CNS
MONTHYEARCNS-18-008, License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing2018-07-19019 July 2018 License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing CNS-18-032, Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report2018-07-12012 July 2018 Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report CNS-18-031, Notice of Enforcement Discretion (NOED) Request2018-06-18018 June 2018 Notice of Enforcement Discretion (NOED) Request CNS-18-028, 2017 Annual Radiological Environmental Operating Report2018-05-14014 May 2018 2017 Annual Radiological Environmental Operating Report CNS-18-026, Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report2018-05-10010 May 2018 Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report CNS-18-023, (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System2018-05-0808 May 2018 (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System CNS-18-025, Submittal of 2017 Annual Radioactive Effluent Release Report2018-04-30030 April 2018 Submittal of 2017 Annual Radioactive Effluent Release Report CNS-18-022, Submittal of Emergency Plan Implementing Procedure2018-04-12012 April 2018 Submittal of Emergency Plan Implementing Procedure CNS-18-017, Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-22018-03-24024 March 2018 Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-2 CNS-18-015, Commitment Change Evaluation Report for 20172018-03-22022 March 2018 Commitment Change Evaluation Report for 2017 CNS-18-005, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-02-0808 February 2018 Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes CNS-18-006, Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days2018-01-23023 January 2018 Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days CNS-17-058, Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukus2017-12-28028 December 2017 Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushi CNS-17-061, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information2017-12-21021 December 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information CNS-17-056, Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-22017-11-0101 November 2017 Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-2 CNS-17-056, Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-22017-10-23023 October 2017 Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-2 CNS-17-053, Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement2017-10-12012 October 2017 Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement CNS-17-048, Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-1222017-09-29029 September 2017 Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-122 CNS-17-049, Submittal of Ufsar/Selected Licensee Commitment Changes Manual2017-09-28028 September 2017 Submittal of Ufsar/Selected Licensee Commitment Changes Manual CNS-17-051, Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask2017-09-28028 September 2017 Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask CNS-17-014, License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time2017-09-14014 September 2017 License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time CNS-17-050, ISFSI - Registration of Spent Fuel Storage Cask2017-09-12012 September 2017 ISFSI - Registration of Spent Fuel Storage Cask CNS-17-047, Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding2017-08-29029 August 2017 Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding CNS-17-041, ISFSI - Registration of Spent Fuel Storage Cask2017-08-15015 August 2017 ISFSI - Registration of Spent Fuel Storage Cask CNS-17-040, Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump2017-08-14014 August 2017 Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump CNS-17-039, Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump2017-07-27027 July 2017 Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump CNS-17-036, Mid-Cycle Power Uprate Ascension Startup Report2017-06-29029 June 2017 Mid-Cycle Power Uprate Ascension Startup Report CNS-17-033, Technical Specification Bases Changes2017-06-27027 June 2017 Technical Specification Bases Changes CNS-17-029, Flood Hazard Mitigating Strategies Assessment Report Submittal2017-06-20020 June 2017 Flood Hazard Mitigating Strategies Assessment Report Submittal CNS-17-030, Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core2017-06-20020 June 2017 Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core CNS-17-024, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations2017-05-25025 May 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations CNS-17-031, Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report2017-05-24024 May 2017 Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report CNS-17-027, Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report2017-05-10010 May 2017 Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report CNS-17-015, Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report2017-04-27027 April 2017 Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report CNS-17-021, Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days2017-04-20020 April 2017 Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days CNS-17-020, Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing2017-04-11011 April 2017 Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing CNS-17-008, Commitment Change Evaluation Report for 20162017-03-16016 March 2017 Commitment Change Evaluation Report for 2016 CNS-17-004, Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants.2017-01-26026 January 2017 Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants. CNS-17-002, End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report2017-01-0606 January 2017 End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report CNS-16-080, Submittal of Emergency Plan Implementing Procedure2016-12-20020 December 2016 Submittal of Emergency Plan Implementing Procedure CNS-16-077, Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-12-0808 December 2016 Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident CNS-16-066, Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task..2016-10-20020 October 2016 Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.. CNS-16-069, Submittal of Emergency Plan, Revision 16-22016-10-10010 October 2016 Submittal of Emergency Plan, Revision 16-2 CNS-16-068, Submittal of Emergency Plan Implementing Procedure Revisions2016-10-10010 October 2016 Submittal of Emergency Plan Implementing Procedure Revisions CNS-16-064, License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 242016-09-0707 September 2016 License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 24 CNS-16-061, Submittal of Design Basis Specification for the Plant Fire Protection Revision 252016-08-12012 August 2016 Submittal of Design Basis Specification for the Plant Fire Protection Revision 25 CNS-16-051, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) an2016-08-0202 August 2016 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) and CNS-16-049, ISFSI Registration of Spent Fuel Storage Cask2016-07-14014 July 2016 ISFSI Registration of Spent Fuel Storage Cask CNS-16-056, Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/00682016-07-13013 July 2016 Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/0068 CNS-16-050, Unit 2 - Ufsar/Selected Licensee Commitment Changes2016-07-12012 July 2016 Unit 2 - Ufsar/Selected Licensee Commitment Changes 2018-07-19
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23188A0732023-07-0707 July 2023 Acceptance of Requested Licensing Action License Amendment Application to Revise Control Room Cooling Technical Specifications RA-18-0007, License Amendment Application to Revise Control Room Cooling Technical Specifications2023-06-19019 June 2023 License Amendment Application to Revise Control Room Cooling Technical Specifications RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022 Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-21-0197, William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility2021-12-14014 December 2021 William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility RA-19-0043, Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2021-06-0909 June 2021 Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO RA-18-0156, Administrative License Amendment Request Proposing to Revise Technical Specification 3.0, Surveillance Requirement (SR) Applicability2019-09-0404 September 2019 Administrative License Amendment Request Proposing to Revise Technical Specification 3.0, Surveillance Requirement (SR) Applicability RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description2019-07-0808 July 2019 License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description RA-18-0036, License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits2019-07-0101 July 2019 License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits RA-18-0198, (Cns), Units 1 & 2 - Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System2018-10-29029 October 2018 (Cns), Units 1 & 2 - Supplement to License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System RA-18-0094, Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating2018-10-0808 October 2018 Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating CNS-18-008, License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing2018-07-19019 July 2018 License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing ML18130A8072018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-18-000, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-17-0005, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2017-11-0707 November 2017 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing CNS-17-014, License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time2017-09-14014 September 2017 License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time 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 RA-17-0035, Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating.2017-07-20020 July 2017 Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating. RA-17-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2017-07-18018 July 2017 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules ML17122A1162017-05-0202 May 2017 Catawba and McGuire - License Amendment Request Proposing Changes to Technical Specification 3.8.1, AC Sources - Operating. RA-16-0028, Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers2016-12-15015 December 2016 Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process CNS-16-030, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants - LAR Supplement to Address ...2016-06-15015 June 2016 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants - LAR Supplement to Address ... RA-16-0021, License Amendment Request Proposing an Updated Final Safety Analysis Report Revision to Reflect Electrical Power Systems Alignments for Shared Systems2016-05-26026 May 2016 License Amendment Request Proposing an Updated Final Safety Analysis Report Revision to Reflect Electrical Power Systems Alignments for Shared Systems CNS-16-014, License Amendment Request (LAR) to Adopt National Fire Protection (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, LAR Submittal to Correct a Legacy Submittal Discrepancy And.2016-03-23023 March 2016 License Amendment Request (LAR) to Adopt National Fire Protection (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, LAR Submittal to Correct a Legacy Submittal Discrepancy And. CNS-16-015, Technical Specification Bases Changes2016-02-18018 February 2016 Technical Specification Bases Changes CNS-16-001, License Amendment Request (LAR) to Revise Technical Specifications (TS) Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-01-18018 January 2016 License Amendment Request (LAR) to Revise Technical Specifications (TS) Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies CNS-15-101, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants2015-12-11011 December 2015 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants RA-15-0020, License Amendment Request and 10 CFR 50.12 Exemption Request for Use of Optimized Zirlo Fuel Rod Cladding2015-08-20020 August 2015 License Amendment Request and 10 CFR 50.12 Exemption Request for Use of Optimized Zirlo Fuel Rod Cladding RA-15-001, Catawba, McGuire, and Oconee - License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Foot2015-07-15015 July 2015 Catawba, McGuire, and Oconee - License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footn RA-15-0013, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 112015-07-15015 July 2015 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 11 ML15175A4482015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 6 of 6 ML15175A4422015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 3 of 6 ML15175A4472015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 5 of 6 RA-15-0006, Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 62015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 2 of 6 ML15175A4392015-06-24024 June 2015 Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-523, Rev. 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 1 of 6 ML15175A4452015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 4 of 6 CNS-15-058, Proposed Technical Specifications (TS) Amendments, TS 3.4.1, Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits2015-06-12012 June 2015 Proposed Technical Specifications (TS) Amendments, TS 3.4.1, Reactor Coolant System (RCS) Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ML15125A1352015-04-30030 April 2015 License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors, Dated November 2012 CNS-14-128, License Amendment Request for Changes to Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation and TS 3.3.5, Loss of Power Diesel Generator Start Instrumentation Resolution of Operable.2014-11-24024 November 2014 License Amendment Request for Changes to Technical Specification 3.3.2, Engineered Safety Feature Actuation System Instrumentation and TS 3.3.5, Loss of Power Diesel Generator Start Instrumentation Resolution of Operable. RA-14-0001, License Amendment Request to Reflect Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Area2014-07-21021 July 2014 License Amendment Request to Reflect Changes to Organization, Unit Staff Responsibility, Unit Staff Qualifications, Programs and Manuals, and High Radiation Area CNS-14-076, License Amendment Request (LAR) for Measurement Uncertainty Recapture (Mur) Power Uprate2014-06-23023 June 2014 License Amendment Request (LAR) for Measurement Uncertainty Recapture (Mur) Power Uprate CNS-14-026, Exigent License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.4, Remote Shutdown System.2014-02-17017 February 2014 Exigent License Amendment Request (LAR) to Revise Technical Specification (TS) 3.3.4, Remote Shutdown System. CNS-13-005, License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology2013-11-14014 November 2013 License Amendment Request for Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology ML13032A0332013-01-21021 January 2013 License Amendment Request for Technical Specification (TS) 3.6.14, Divider Barrier Integrity. ML1207600792012-06-25025 June 2012 Issuance of Amendment Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specifications ML12153A3282012-05-31031 May 2012 Proposed Technical Specifications Amendment TS 3.1.3, Moderator Temperature Coefficient (Mtc) TS 5.6.5, Core Operating Limits Report (COLR) License Amendment Request for Conditional Exemption of the End of Cycle (EOC) Mtc Measurement Method ML12038A1732012-02-0101 February 2012 Proposed Tech Specs Amendment TS 3.4.13, TS 5.5.9, TS 5.6.8, License Amendment Request to Revise TS for Permanent Alternate Repair Criteria 2023-07-07
[Table view] |
Text
Kelvin Henderson
,(~DUKE Vice President
~ ENERGY Catawba Nuclear Station Duke Energy CNOl VP I 4800 Concord Road York, SC 29745
. O: 803.701.4251 f: 803.701.3221
. I Th~ Attachment W pages to this l!i!tter contain security related information. Withhold from public disclosure in acc.ordance with 10 CFR 2,390. When the Attachment W pages are removed, this document is no lonQer security related.
CNS-16-014 March 23, 2016 10 CFR 50.90 U.S. Nuclear R~gulatory Commission (NRC)
Attention: Document Control DE)sk Washington, D.C. 20555
Subject:
Duke Energy Carolinas, LLC (Duke Energy)
Cat~wba Nuclear Station, Units 1 and 2
- Docket Numbers 50-413 and 50-414 Ucerise Am.engment ~eque.st (LAR) to Adopt NatJonal Fire Protection Association (~FPA) 805 Perfor1119_n~e.,Based Standard for Fire Protection for Lig~l~Water Reac;:tor Genera~irig Plants LAR SupplerJiemt to Correct a_ Legacy Submittal Discrepancy and to a
Revise Modification Commitment (TAC Nos. Mi=2936 and.MF2937)
References:
Lette~s frc;>m Duke Energy to the NRC, d~ted September 25, 2013 (ADAMS Accession Number ML 13276A5b3), January 13, 2015 (ADAMS Acce~s.ion Number ML15015A409), ~~muary 28, 4015 (ADAMS Acc~ssion Number ML1S029A697), Fepruary Tl, 2015 (APAM*s Acc~s~ion Nyfnber M1,.150(;35A 107), rvtarch 30, 2_015 (ADAMS Accession Number ML 15b91A339), April 28, 20f5 (ADAMS Accession Number ML 15119$\533), July 1'5, 2015 (ADAMS Accession Numl;>er l\;1L15198A636), August 14, 2015 (ADAMS Accessipn Number ML 15231)\010),* September 3, 2015 (AQAMS Accession Number ML 1531 OA123), becemb~r 11, 2015 (ADAMS Accessipn Number ML 15350A01*4}, and January 7, 2016 (ADAMS Accession Number ML16011A121) www.duke-energy.com
The Attachment W pages to this letter contain security related information. Withhold from public disclosure in accordance with 10CFR 2.390. When the Attachment W pages are removed, this document is no longer security related.
Document Control Desk Page 2 March 23, 2016 The reference letters comprise in their entirety Duke Energy's request for NRC review and approval for adoption of a new fire protection licensing basis which complies with the requirements in 10 CFR 50.48(a), 10 CFR 50.48(c), and the guidance in Regulatory Guide (RG) 1.205, "Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants", Revision 1, dated December 2009. The September 25, 2013 reference LAR was developed in accordance with the guidance contained in Nuclear Energy Institute (NEI) 04-02, "Guidance for Implementing a Risk-Informed, Performance-Based Fire Protection Program Under 10 CFR 50.48(c)", Revision 2.
The purpose of this LAR supplement is twofold:
- 1. Duke Energy is resolving a discrepancy that was recently discovered in the NFPA 805 Safe Shutdown Analysis. The NFPA 805 Nuclear Safety Capability Assessment was discovered to contain a legacy discrepancy that does not match the current Safe Shutdown Analysis. This led to an omission of a Variance From Deterministic Requirement (VFDR) from the September 25, 2013 reference LAR. This discovery was entered into the Catawba Corrective Action Program on February 22, 2016.
Since that time, Duke Energy has performed an extent-of-condition evaluation (no additional discrepancies were found) and has revised the affected NFPA 805 LAR document pages. These pages are contained herein and include: 1) a Compact Disc (CD) copy of entire Attachment C, "NFPA 805 Ch 4 Compliance (NEI 04-02 Table B-3)" (a CD copy is being provided as this entire attachment was affected by repagination and comprises 697 pages; the actual revised pages are 19, 24, 31, and 36); and 2) a paper copy of the revised pages of Attachment W, "Fire PRA Insights".
The revised Attachment C and Attachment W pages have the revisions designated by revision bars.
- 2. Duke Energy is revising a regulatory commitment associated with the mitigation of internal flooding concerns in the Auxiliary Feedwater (AFW) pump rooms. The revised commitment is shown on the revised page of LAR Attachment S, "Modifications and Implementation Items", which has the revision designated by revision bar. Also included is a re-transmittal of the entire final LAR Attachment S, which is designated as Revision 5 and has all revision bars removed. This
- constitutes the final clean copy of Attachment S for referencing in the Facility Operating Licenses. The revised Attachment W pages resulting from this revised commitment have the revisions designated by revision bars.
Duke Energy has determined that the revised Attachment W pages should be considered as Sensitive Unclassified Non-Safeguards Information (SUNSI) and has designated these pages as so. Duke Energy is requesting that the enclosed Attachment W pages be withheld from public disclosure in accordance with 10 CFR 2.390.
The Attachment W pages to this letter contain security related information. Withhold from public disclosure in accordance with 10 CFR 2.390. When the Attachment W pages are removed, this document is no longer security related.
Document Control Desk Page 3 March 23, 2016 The conclusions of the No Significant Hazards Consideration and the Environmental Consideration contained in the September 25, 2013 reference LAR are unaffected by this LAR supplement.
Except as indicated above, there are no regulatory commitments contained in this letter or its enclosure.
Pursuant to 10 CFR 50.91, a copy of this LAR supplement is being sent to the appropriate State of South Carolina official.
Inquiries on this matter should be directed to L.J. Rudy at (803) 701-3084.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on March 23, 2016.
Very truly yours,
~~
Vice President, Catawba Nuclear Station LJR/s Enclosure
The Attachment W pages to this letter contain security related information. Withhold from public disclosure in accordance with 10 CFR 2.390. When the Attachment W pages are removed, this document is no longer security related.
Document Control Desk Page 4 March 23, 2016 xc (with enclosure):
C. Haney Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 G.A. Hutto Ill Senior Resident Inspector (Catawba)
U.S. Nuclear Regulatory Commission Catawba Nuclear Station J.A. Whited (addressee only)
NRC Project Manager (Catawba)
U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8 B1A 11555 Rockville Pike Rockville, MD 20852-2738 S.E. Jenkins Manager Radioactive and Infectious Waste Management Division of Waste Management South Carolina Department of Health and Environmental Control 2600 Bull St.
Columbia, SC 29201
Enclosure NFPA 805 LAR Revised Pages and Compact Disc
Duke Energy Carolinas, LLC Catawba Nuclear Station Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition Transition Report Revision 5 March 2016
Duke Energy Carolinas, LLC Attachment S - Modifications and Implementation Items Table S-2a Plant Modifications Committed - Internal Events PRA In Comp Risk Informed Item Rank Unit Problem Statement Proposed Modification IEPRA Measure Characterization 01 High 1, 2 Auxiliary Shutdown Panels A Isolation of fire protection piping in y N This modification will provide and B are located in the CA the 560' and 577' elevation an internal flood risk reduction (Aux. Feed water) Pump room electrical penetration rooms. , to offset the Fire PRA risk and are theoretically increase post-transition.
susceptible to being rendered Completion Date:
non-functional by an internal December 31, 2017 flood from a pipe break at a higher elevation within the Auxiliary Building.
02 Deleted via Letter CNS-15-101.
03 High 1, 2 The 'current installation and Replace/upgrade turbine building y N This modification will provide maintenance program of the siding fasteners and in'stitute a an internal events high winds turbine building siding fasteners preventative maintenance program risk reduction to offset the Fire leave the siding susceptible to to periodically inspect the fasteners. PRA risk increase post-being affected by low speed transition.
(73-114 mph) straight line Completion Date:
winds thus increasing the PRA December 31, 2017 risk probability of a LOOP event.
I Rev5 Page S-3
Duke Energy Carolinas, LLC Attachment S - Modifications and Implementation Items S. Modifications and Implementation Items 11 Pages Attached Rev5 PageS-1
Duke Energy Carolinas, LLC Attachment S - Modifications and Implementation Items Tables S-1, Plant Modifications Completed, S-2a, Plant Modifications Committed - Internal Events PRA, and S-2b, Plant Modifications Committed - Fire PRA, provided below, include a description of the modifications along with the following information:
- Risk ranking of the modification,
- An indication if the modification is currently included in the Fire PRA,
- Compensatory Measure in place, and
- A risk-informed characterization of the modification and compensatory measure.
Table 5-1 Plant Modifications Completed In Comp Risk Informed Item Rank Unit Problem Statement Proposed Modification FPRA Measure Characterization NONE Revs Page S-2
Duke Energy Carolinas, LLC Attachment S - Modifications and Implementation Items Table S-2a Plant Modifications Committed - Internal Events PRA In Comp Risk Informed Item Rank Unit Problem Statement Proposed Modification IEPRA Measure Characterization 01 High 1, 2 Auxiliary Shutdown Panels A Isolation of fire protection piping in y N This modification will provide and B are located in the CA the 560' and 577' elevation an internal flood risk reduction (Aux. Feed water) Pump room electrical penetration rooms. to offset the Fire PRA risk and are theoretically increase post-transition.
susceptible to being rendered Completion Date:
non-functional by an internal December 31, 2017 flood from a pipe break at a higher elevation within the Auxiliary Building.
02 Deleted via Letter CNS-15-101.
03 High 1, 2 The current installation and Replace/upgrade turbine building y N This modification will provide maintenance program of the siding fasteners and institute a an internal events high winds turbine building siding fasteners preventative maintenance program risk reduction to offset the Fire leave the siding susceptible to to periodically inspect the fasteners. PRA risk increase post-being affected by low speed transition.
(73-114 mph) straight line Completion Date:
winds thus increasing the PRA December 31, 2017 risk probability of a LOOP event.
Revs Page S-3 .
Duke Energy Carolinas, LLC Attachment S - Modifications and Implementation Items Table S-2b.Plant Modifications Committed - Fire PRA In Comp Risk Informed Item Rank Unit Problem Statement Proposed Modification FPRA Measure Characterization 01 High 2 KSI Inverter Modification to Cable 2KSl-SKXP for N y This cable modification is relocate cable in fire area OETLPLSKXP will. be re-routed from required for NFPA 805.
- 9. SSF shutdown fire area 9 (Unit 2 Battery Room) to non-SSF Compensatory measures will shutdown fire area(s). be established when the NFPA 805 fire protection program Completion Date: becomes effective and remain December 31, 2017 in place until this modification is complete.
02 Med Unit 1 Breaker Coordination Remove the incoming breaker and y y This coordination modification issues identified forMGCs connect wiring directly to the MCC is required for NFPA 805.
1 EMXA, 1EMXB, 1 EMXC,, bus for the following MCCs: The current coordination study 1EMXD, 1EMXI, 1EMXJ, 1EMXA, 1EMXB, 1EMXC, 1EMXD, is valid for current licensing 1EMXK, and 1 EMXL. 1EMXI, 1EMXJ, 1EMXK, and basis.
1EMXL.
Compensatory measures will Completion Date: be established when the NFPA December31, 2017 805 fire protection program becomes effective and remain in place untilthis modification is complete.
03 Med 2 Unit 2 Breaker Coordination Remove the incoming breaker and y y This coordination modification issues identified for MCCs connect wiring directly to the MCC is required for NFPA 805.
2EMXA, 2EMXB, .2EMXC, bus for the following MCCs: The current coordination study 2EMXD, 2EMXI, 2EMXJ, 2EMXA, 2EMXB, 2EMXC, 2EMXD, is valid for curreht licensing 2EMXK, and 2EMXL. 2EMXI, 2EMXJ, 2EMXK, and basis.
Compensatory measures will Completion Date: be established when the NFPA December 31, 2017 805 fire protection program becomes effective and remain in place until this modification is complete.
Rev5 Page S-4
Duke Energy Carolinas, LLC Attachment S - Modifications and Implementation Items Table S-2b Plant Modifications Committed - Fire PRA In Comp Risk Informed Item Rank Unit Problem Statement Proposed Modification FPRA Measure Characterization 04 Med 1, 2 Breaker Coordination issues Install fuses on the load side of y y This coordination modification identified on load side of E_DE EDE and EDF breakers. Involves 4 is required for NFPA 805.
and EDF breakers. breakers on EDE and 3 on EDF. The current coordination study Mount new fuses in each panel. is valid for current licensing basis.
Completion Date:
December 31, 2017 Compensatory measures will be established when the NFPA 805 fire protection program becomes effective and remain in place until this modification is complete.
05 Med 1, 2 Spurious valve operation with Remove the fuse from the Motor y y This spurious operation Breaker Coordination issues Operator Heater circuit for 1CA modification is required for identified with 600 VAC MCCs. VA0050A and 2CAVA0050A. NFPA 805. The current deterministic analysis is valid Completion Date: for current licensing basis.
December 31, 2017 Compensatory measures will be established when the NFPA 805 fire protection program becomes effective and remain in place until this modification is complete.
06 Med 1, 2 Spurious valve operation with Route new cables for the normally y y This spurious operation Breaker Coordination issues energized circuits on 1WLLS5900 modification is required for identified with 600 VAC MCCs. and 2WLLS5900. NFPA 805. The current deterministic analysis is*valid Completion Date: for current licensing basis.
December 31, 2017 Compensatory measures will be established when the NFPA 805 fire protection program becomes effective and remain in place until this modification is complete.
Revs Page S-5
Duke Energy Carolinas, LLC Attachment S - Modifications and Implementation Items Table S-2b Plant Modifications Committed - Fire PRA In Comp Risk Informed Item Rank Unit Problem Statement
- Proposed Modification FPRA Measure Characterization 07 Med 1, 2 TDCAP ls susceptible to fire in Cable routes modified such that the y y This modification the ETA/ETB Switchgear TDCAP will remain available in the is required for NFPA 805.
Rooms. event of a fire in the ETA or ETB The modification will ensure Switchgear Room. that the TDCAP is available in addition to the already credited Completion. Date: opposite train motor driven CA December 31, 2017 pump for a fire in the ETA or ETB Switchgear Rooms.
Compensatory measures will be established when the NFPA 805 fire protection program becomes effective and remain in place until this. modification is complete.
Revs Page S-6
Duke Energy Carolinas, LLC Attachment S - Modifications and Implementation Items Table S-3, Items provided below are those items (procedure changes, process updates, and training to affected plant personnel) that will be completed prior to the implementation of new NFPA 805 fire protection program. This will occur within 180 days after issuance of the license amendment unless that date falls within a scheduled refueling outage. Then, implementation will occur within 60 days after startup from that scheduled refueling outage. Note Item 13 is associated with modifications in Table S-2b and will be completed 180 days after completion of the last risk related modification .
.Table S-3 Implementation Items Item Unit Description LAR Section I Source 1, 2 Perform the following recommendations from the Radiological Release 4.4.2 and Attachment E Evaluation:
- 1. Within each yard area fire strategy, identify radiologically
.controlled area boundaries within ~he strategy and any potential escape paths. This includes building sumps and storm drains, where applicable. For consistency, it is recommended that even hardened barriers are identified.
Examples of these would include: hatches, passage doors, and roll-up.doors.
- 2. Enhance the appropriate existing procedures or guidelines, or create a new procedure or guideline, to include more detail on the control measures usedto maintain radioactive release limits where monitoring cannot be accomplished.
Examples include:
- Water fog streams used for smoke scrubbing
- Controlling water runoff during fire suppression activities
- Covering drains and other similar containment measures
- 3. Enhance Fire Brigade Guidelines (Procedure RP-29) to instruct Radiation Protection personnel to respond to fires where there are radiological concerns inside and outside the Protected Area.
- 4. Enhance the appropriate existing procedures or guidelines, or create a new procedure or guideline, to include guidance for crossing RCA/Radioactive Control Zone boundaries including escape routes.
- 5. Create new fire strategies for yard areas that contain RCAs.
This includes the following:
Revs Page S-7
Duke Energy Carolinas, LLC Attachment S- Modifications and Implementation Items Table S-3 Implementation Items Item Unit Description LAR Section I Source
- Radiation Materials Control Building (Building 7767)
- Radioactive Materials Containers
- Tents Containing Radioactive :Material
- ISFSI Storage of non-ISFSI Radioactive Materials
- 6. Within each fire strategy, identify the Radiologically Controlled Area (RCA) or Radioactive Control Zone in the written text.
- 7. Fire Brigade training will be revised to ensure the new guidance proposed in Recommendations 2, 3 and 4 for radioactive release is covered during the established training interval.
- 8. Add a standard statement for smoke and water runoff to all radiologically controlled area fire strategies to prompt measures to avoid radioactive release.
- 9. Incorporate all fire fighting strategies into the electronic .
records management retrieval system (internally referred to as NEDL). This will provide consistency for current users and the ability to conduct effective reviews to ensure all radioactive release recommendations have been incorporated.
- 10. Add an appendix to the fire strategies for building sump drainage and site storm drains. This is NOT intended to be a detailed plan, but a site overview that identifies areas where runoff has the potential to route to a storm drain or an automatic sump that will pump without radiation monitoring.
- 11. Develop administrative guidance in collaboration with radiation protection to support ensuring that radioactive release(s) do not exceed limits in the event of a fire in areas where engineering controls will not contain the potential release. Attachment A contains a flow chart of the various considerations needed for administrative controls that can be directed via one or more plant procedures depending upon the performing group(s).
Revs Page S-8
Duke Energy Carolinas, LLC Attachment S - Modifications and Implementation Items Table S-3 Implementation Items Item Unit Description LAR Section I Source 2 1, 2 After the approval of the LAR, in accordance with 10 CFR 50.71(e) and 5.4 approved exemptions, the CNS UFSAR will be revised. The format and content will be consistent with NEI 04-02 FAQ 12-0062.
3 1,2 The Design Basis Specification for the Plant Fire Protection, which is the Attachment A, 3.2.2.4 primary fire protection program policy document, will be updated to include the statement that the NRC is the AHJ for fire protection changes requiring approval.
4 1,2 Appropriate fire protection program document(s) will be updated to Attachment A, 3.2.3(1) provide a requirement that if a plant elects to implement the methodologies in EPRI Report TR1006756, that the methodologies will be implemented in their entirety as they pertain to the fire protection systems or features being evaluated.
5 1,2 The monitoring program required by NFPA 805 Section 2.6 will be 4.6.2, Attachment A, 3.2.3(3) implemented after the LAR approval as part of the fire protection program transition to NFPA 805, in accordance with NFPA 805 FAQ 10-0059, and will include a process that reviews fire protection performance and trends in performance. Program specifics are provided in LAR Section 4.6.2.
6 1,2 Revise station procedures/directives to comply with NFPA 805 Section Attachment A, 3.3.1.2(1) 3.3.1.2(1 ).
7 1,2 Appropriate station documentation will be updated to include the Attachment A, 3.3.5.1 requirements for installation of cable above suspended ceilings.
8 1,2 The Fire Strategies will be reviewed and updated to include any changes Attachment A, 3.4.2.1 to equipment important to nuclear safety and other updates pertinent to the NFPA 805 Transition.
9 1,2 The Fire Protection Design Basis Document described in Section 2.7.1.2 4.7.1 of NFPA 805 and necessary supporting documentation described in Section 2.7.1.3 of NFPA 805 will be created as part of transition to 10 CFR 50.48(c) to ensure program implementation following receipt of the safety evaluation. Appropriate cross references will be established to supporting documents as required by Duke Energy processes.
Revs Page S-9
Duke Energy Carolinas, LLC Attachment S - Modifications and Implementation Items Table S-3 Implementation Items Item Unit Description LAR Section I Source 10 1, 2 Ensure the CNS configuration control process follows the requirements in 4.7.2 NFPA 805 and the guidance outlined in RG 1.174 which requires the use of qualified individuals, procedures that require calculations be subject to independent review and verification, record retention, peer review, and a corrective action program that ensures appropriate actions are taken when errors are discovered. The configuration control requirements should be implemented in accordance with FAQ 12-0061.
11 1, 2 Develop Engineering training guidelines to identify and document 4.7.3 required training and mentoring to ensure individuals are appropriately qualified per the requirements of NFPA 805 Section 2.7.3.4 to perform assigned work.
12 1, 2 Revise Shutdown Risk Management procedures to reflect the following 4.3 and Attachment D recommendations during higher risk evolutions from the calculation entitled, "NFPA 805 Transition Non-Power Fire Area Assessments (Pinch Points Analysis)":
- Include CNS specific HRPOS definition.
- Limit hot work in affected fire area during Higher Risk Plant Operating States (HRPOS's).
Prohibit hot work in affected fire areas during Higher Risk Plant Operating States (HRPOS's).
- Verify that the available fire detection systems located in the affected fire areas are functional. Post firewatch per SLCs in .
affected fire areas prior to entering Higher Risk Plant Operating States if system(s) are impaired.
- Verify that the available fire suppression systems located in the affected fire areas are functional. Post firewatch per SLCs in affected fire areas prior to entering Higher Risk Plant Operating States if system(s) are impaired.
- Limit transient combustible storage in affected fire areas during Higher Risk Plant Operating States (HRPOS's).
- Prohibit transient combustible storage in affected fire areas during Higher Risk Plant Operating States (HRPOS's).
- Provide a firewatch (continuous or periodic) in affected fire areas during Higher Risk Plant Operating States (HRPOS's).
Rev 5 Page S-10
Duke Energy Carolinas, LLC Attachment S - Modifications and Implementation Items Table S-3 Implementation Items Item Unit Description LAR Section I Source
- Activities in affected fire areas should be rescheduled to non-Higher Risk Plant Operating States (HRPOS's) periods.
13 1, 2 Following installation of the risk related modifications and the as-built 4.8.2 installation details, additional refinements surrounding the modification and any procedural implementation items (Table S~3 Items 12 and 16) will be incorporated into the Fire PRA model and Internal Events model, as required. In addition, a verification will be performed to confirm that the risk results are not appreciably changed. If the as-built change-in-risk estimates exceed the RG 1.174 acceptance guidelines, the responsible feature will be identified and evaluated. Actions taken to address such a case may be one or more of the following: 1) implementing additional modifications, 2) refining the analytical estimates, or 3) requesting that exceeding the guidelines be deemed acceptable in a new LAR.
14 1, 2 Develop formal training program for nonfire brigade personnel that Attachment A, 3.4.3(b) respond to a fire incident.
15 1, 2 4.7.3 Revise the QA Topical, as appropriate, to update the definition of QA 3 to match post NFPA 805 criteria. QA Topical currently defines QA 3 as:
"QA Condition 3 covers those systems, components, items, and services which are important to fire protection as defined in the Hazards Analysis for each station. The Hazards Analysis is in response to Appendix A of NRC Branch Technical Position APCSB 9.5-1."
16 1, 2 Implementation items resulting from the feasibility evaluation include: Attachment G
- Corrective Action to add equipment tags to the petcocks for the CA valves. These equipment numbers will be added to Fire Procedure, AP/O/A/5500/045.
- Corrective Action to revise steps to Fire Procedure, AP/O/A/5500/045 to add valve numbers (or descriptive nomenclature) as applicable to the individual steps for throttling the CA valves (valve to isolate air, bleed air).
- Corrective Action to revise steps to Fire Procedure, AP/O/A/5500/045 to include requiring operators to obtain a climbing harness prior to throttling the CA valves locally.
- Corrective Action to add steps to Fire Procedure Rev 5 Page S-11
Duke Energy Carolinas, LLC Attachment S - Modifications and Implementation Items Table S-3 Implementation Items Item Unit Description LAR Section I Source AP/O/A/5500/045 to trip the NC pumps locally (if unable to trip from the control room).
- Corrective Action to add performance of recovery action drills to Operator training.
17 1, 2 Update station documentation to indicate requirements for interior floor Attachment A, 3.3.3 finishes.
18 1, 2 Ensure procedures are provided for long-term alignments for makeup of 4.2.1.2 fuel oil, feedwater, and reactor coolant.
19 1, 2 Evaluate the transient combustible control procedure for additional RAI PRA-15b controls in the identified fire areas to account for a larger transient fire heat release rate.
Revs Page S-12