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| {{#Wiki_filter:( ENERGY.Kelvin Henderson Vice President Catawba Nuclear Station Duke Energy CN01VP 1 4800 Concord Road York, SC 29745 o:803.701.4251 f: 803.701.3221 CNS-15-031 March 24, 2015 U.S. Nuclear Regulatory Commission Attention: | | {{#Wiki_filter:Kelvin Henderson |
| Document Control Desk Washington, DC 20555-0001 | | ( ENERGY. |
| | Vice President Catawba Nuclear Station Duke Energy CN01VP 1 4800 Concord Road York, SC 29745 o:803.701.4251 f: 803.701.3221 CNS-15-031 March 24, 2015 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 |
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| Duke Energy Carolinas, LLC (Duke)Catawba Nuclear Station, Units 1 and 2 Docket Nos.: 50-413 and 50-414 Commitment Change Evaluation Report for 2014 Attached is a summary of commitment change evaluations completed during the 2014 calendar year for Catawba Nuclear Station. These evaluations and subsequent commitment changes were made based on the guidance defined in NEI 99-04, Guidelines for Managing NRC Commitments, and have no adverse effect on compliance with NRC rules and regulations. | | Duke Energy Carolinas, LLC (Duke) |
| | Catawba Nuclear Station, Units 1 and 2 Docket Nos.: 50-413 and 50-414 Commitment Change Evaluation Report for 2014 Attached is a summary of commitment change evaluations completed during the 2014 calendar year for Catawba Nuclear Station. These evaluations and subsequent commitment changes were made based on the guidance defined in NEI 99-04, Guidelines for Managing NRC Commitments, and have no adverse effect on compliance with NRC rules and regulations. |
| Questions regarding this report should be directed to Cecil Fletcher, Regulatory Affairs Manager, at 803-701-3622. | | Questions regarding this report should be directed to Cecil Fletcher, Regulatory Affairs Manager, at 803-701-3622. |
| Sincerely, elvin Henderson Vice President, Catawba Nuclear Station Attachment F)www.duke-energy.com a U. S. Nuclear Regulatory Commission March 24, 2015 Page 2 xc: V. M. McCree, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 G. Edward Miller NRC Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8-G9A 11555 Rockville Pike Rockville, MD 20852-2738 G. A. Hutto Senior Resident Inspector CN01NC Catawba Nuclear Station Annual Commitment Change Summary Report for 2014 Docket Nos. 50-413 and 50-414 NRC Notification Number Source Document Original Commitment Modified Commitment Required Yes 2014-C-001 NRC Generic Letter Response (November 27,1997) and Commitment Change #2002-C-005 The intake and pit inspections will be performed on a three year frequency commencing from the last RN intake and Train B pump pit inspection conducted on 4/24/02.Defer the inspection of Nuclear Service Water (RN) Pump Pit A to no later than 11/20/2014. | | Sincerely, elvin Henderson Vice President, Catawba Nuclear Station Attachment F) www.duke-energy.com |
| This is a one-time deferral.The inspection of the A train RN Pump Pit is due 07/07/2014. | | |
| This inspection was scheduled for March of 2014 but could not be performed due to issues with providing adequate isolation of the pit. In order to minimize safety system unavailability, this inspection will be performed during scheduled valve maintenance which will require A train of RN to be removed from service.The most recent A train pit inspection was performed during refueling outage 1EOC17, October, 2010. No structural issues were identified with the condition of the pit and associated structures, as documented in the work order completion comments.The A and B train pits are operated in the same manner. Therefore, the condition of the B train pit is considered to be indicative of the condition of the A pit.The latest inspection of the B pit was performed in February, 2012. The results of that inspection concluded that no structural issues were present with respect to concrete, structural steel or the intake screens. As noted in the Corrective Action Program, the pit was in very good condition (C-12-1403). | | a U. S. Nuclear Regulatory Commission March 24, 2015 Page 2 xc: |
| This indicates the A pit is also in a similar Page 1 NRC Notification Number Source Document Original Commitment Modified Commitment Required condition. | | V. M. McCree, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 G. Edward Miller NRC Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8-G9A 11555 Rockville Pike Rockville, MD 20852-2738 G. A. Hutto Senior Resident Inspector CN01NC |
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| | Catawba Nuclear Station Annual Commitment Change Summary Report for 2014 Docket Nos. 50-413 and 50-414 NRC Notification Number Source Document Original Commitment Modified Commitment Required Yes 2014-C-001 NRC Generic Letter Response The intake and pit inspections will Defer the inspection of Nuclear Service (November 27,1997) and be performed on a three year Water (RN) Pump Pit A to no later than Commitment Change #2002-C- frequency commencing from the 11/20/2014. This is a one-time deferral. |
| | 005 last RN intake and Train B pump pit inspection conducted on 4/24/02. The inspection of the A train RN Pump Pit is due 07/07/2014. This inspection was scheduled for March of 2014 but could not be performed due to issues with providing adequate isolation of the pit. In order to minimize safety system unavailability, this inspection will be performed during scheduled valve maintenance which will require A train of RN to be removed from service. |
| | The most recent A train pit inspection was performed during refueling outage 1EOC17, October, 2010. No structural issues were identified with the condition of the pit and associated structures, as documented in the work order completion comments. |
| | The A and B train pits are operated in the same manner. Therefore, the condition of the B train pit is considered to be indicative of the condition of the A pit. |
| | The latest inspection of the B pit was performed in February, 2012. The results of that inspection concluded that no structural issues were present with respect to concrete, structural steel or the intake screens. As noted in the Corrective Action Program, the pit was in very good condition (C-12-1403). This indicates the A pit is also in a similar Page 1 |
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| | NRC Notification Number Source Document Original Commitment Modified Commitment Required condition. |
| Therefore, deferring the next committed A train pump pit inspection by four months (11/30/14) to minimize safety system unavailability will not result in any potential challenge of the A train of the RN system from being capable of meeting its design basis requirements. | | Therefore, deferring the next committed A train pump pit inspection by four months (11/30/14) to minimize safety system unavailability will not result in any potential challenge of the A train of the RN system from being capable of meeting its design basis requirements. |
| This deferral is only applicable to this single occurrence. | | This deferral is only applicable to this single occurrence. |
| Yes 2014-C-002 Letter from Thomas P. Harrall, Monitor the status of the TSTF Complete the evaluation of TSTF-523 and Duke Energy, to NRC, dated effort to provide revisions to submit a letter to the NRC providing a October 13, 2008, "Generic NUREG-1431 Technical schedule for submittal of a License Letter 2008-01, 9-Month Specifications and their associated Amendment Request by October 15, Response" Bases in regard to the periodic 2014.venting surveillance. | | Yes 2014-C-002 Letter from Thomas P. Harrall, Monitor the status of the TSTF Complete the evaluation of TSTF-523 and Duke Energy, to NRC, dated effort to provide revisions to submit a letter to the NRC providing a October 13, 2008, "Generic NUREG-1431 Technical schedule for submittal of a License Letter 2008-01, 9-Month Specifications and their associated Amendment Request by October 15, Response" Bases in regard to the periodic 2014. |
| Catawba will evaluate the resolution of TS issues Duke Energy's evaluation of TSTF-523 is with respect to the changes continuing. | | venting surveillance. Catawba will evaluate the resolution of TS issues Duke Energy's evaluation of TSTF-523 is with respect to the changes continuing. Additional time is needed to contained in the TSTF traveler, and complete the evaluation, and to prepare, submit a license amendment process, and submit an LAR. Therefore, request based on this evaluation Duke Energy is revising the commitments within 180 days following NRC to complete the evaluation and provide a approval of the TSTF. schedule for submittal of an LAR by October 15, 2014. Duke Energy believes that the actions completed in response to Generic Letter 2008-01 provide confidence that safety will be preserved during the extended evaluation period that the revised regulatory commitments afford. |
| Additional time is needed to contained in the TSTF traveler, and complete the evaluation, and to prepare, submit a license amendment process, and submit an LAR. Therefore, request based on this evaluation Duke Energy is revising the commitments within 180 days following NRC to complete the evaluation and provide a approval of the TSTF. schedule for submittal of an LAR by October 15, 2014. Duke Energy believes that the actions completed in response to Generic Letter 2008-01 provide confidence that safety will be preserved during the extended evaluation period that the revised regulatory commitments afford.Yes 2014-C-003 Letter from Bill Pitesa, Duke Implementation Milestone 8 of the Revise Implementation Milestone 8 Energy, to NRC dated April 15, Cyber Security Plan is to Complete completion date of June 30, 2015, to 2011, "License Amendment Operational and Management December 31, 2017.Request for Cyber Security controls as provided in NEI 08-09, Plan" Rev. 6, Appendix E, by June 30, The scope of the Critical Digital Asset 2015. (CDA) assessment activities was substantially underestimated by Duke Page 2 NRC Notification Number Source Document Original Commitment Modified Commitment Required Energy. The Milestone 8 completion date was established prior to any significant work being performed on program implementation; therefore, the scope of the assessment activities was not fully appreciated. | | Yes 2014-C-003 Letter from Bill Pitesa, Duke Implementation Milestone 8 of the Revise Implementation Milestone 8 Energy, to NRC dated April 15, Cyber Security Plan is to Complete completion date of June 30, 2015, to 2011, "License Amendment Operational and Management December 31, 2017. |
| The scope of the CDA assessment activities was also substantially underestimated by the industry in general, as evidenced by the need for additional industry guidance.Therefore, Duke Energy (DEC) is revising the commitment for Milestone 8 completion date of June 30, 2015, to December 31, 2017. Milestone 8 pertains to the date that complete operational and management controls, as provided in Nuclear Energy Institute 08-09, Revision 6, Appendix E, will be achieved. | | Request for Cyber Security controls as provided in NEI 08-09, Plan" Rev. 6, Appendix E, by June 30, The scope of the Critical Digital Asset 2015. (CDA) assessment activities was substantially underestimated by Duke Page 2 |
| Based on the status of the cyber security program, Duke Energy believes that safety will be preserved during the approval period that the revised regulatory commitments afford.Page 3}} | | |
| | NRC Notification Number Source Document Original Commitment Modified Commitment Required Energy. The Milestone 8 completion date was established prior to any significant work being performed on program implementation; therefore, the scope of the assessment activities was not fully appreciated. The scope of the CDA assessment activities was also substantially underestimated by the industry in general, as evidenced by the need for additional industry guidance. |
| | Therefore, Duke Energy (DEC) is revising the commitment for Milestone 8 completion date of June 30, 2015, to December 31, 2017. Milestone 8 pertains to the date that complete operational and management controls, as provided in Nuclear Energy Institute 08-09, Revision 6, Appendix E, will be achieved. Based on the status of the cyber security program, Duke Energy believes that safety will be preserved during the approval period that the revised regulatory commitments afford. |
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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:Report
MONTHYEARRA-22-0180, Supplement to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant2022-07-0707 July 2022 Supplement to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant RA-22-0115, Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle2022-04-21021 April 2022 Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle RA-21-0144, Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant2022-01-20020 January 2022 Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant RA-19-0245, of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology2021-10-25025 October 2021 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology RA-21-0145, Revision to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method2021-04-24024 April 2021 Revision to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method RA-21-0133, Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method2021-04-23023 April 2021 Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method ML20150A3322020-04-23023 April 2020 Revision of Slc'S 16-11-2, 16-11-7 and Loes RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 CNS-17-043, Report 16C4437-RPT-002, Revision 0, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for Catawba Nuclear Station.2017-07-0707 July 2017 Report 16C4437-RPT-002, Revision 0, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for Catawba Nuclear Station. CNS-17-036, Mid-Cycle Power Uprate Ascension Startup Report2017-06-29029 June 2017 Mid-Cycle Power Uprate Ascension Startup Report CNS-17-022, Summary of 10CFR 50.54(q) Evaluation2017-04-25025 April 2017 Summary of 10CFR 50.54(q) Evaluation ML15253A4102016-03-11011 March 2016 Enclosure 2 Screening Analysis Report 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 ML15238A7392015-08-24024 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask CNS-15-049, Submittal of 2013/2014 10 CFR 50.59 Summary Report of Changes, Tests, Experiments, and Evaluations2015-05-11011 May 2015 Submittal of 2013/2014 10 CFR 50.59 Summary Report of Changes, Tests, Experiments, and Evaluations ML15096A5132015-04-27027 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Revaluations Relating to Recommendation 2.1 of the NTTF Review ML15093A4212015-03-31031 March 2015 Submittal of CNEI-0400-281, Revision 0, Core Operating Limits Reports for Cycle 21 Reload Core, Calculation CNC-1553.05-00-0621 CNS-15-031, Commitment Change Evaluation Report for 20142015-03-24024 March 2015 Commitment Change Evaluation Report for 2014 CNS-14-129, Transmittal of Industry High Density Polyethylene (Hdpe) Test Results2014-12-0808 December 2014 Transmittal of Industry High Density Polyethylene (Hdpe) Test Results CNS-14-131, WCAP-17669-NP, Revision 0, Catawba Unit 1 Measurement Uncertainty Recapture (Mur) Power Uprate: Reactor Vessel Integrity and Neutron Fluence Evaluations2014-06-30030 June 2014 WCAP-17669-NP, Revision 0, Catawba Unit 1 Measurement Uncertainty Recapture (Mur) Power Uprate: Reactor Vessel Integrity and Neutron Fluence Evaluations ML14108A2012014-05-16016 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident CNS-14-045, Commitment Change Evaluation Report for 20132014-03-31031 March 2014 Commitment Change Evaluation Report for 2013 CNS-14-038, DUKCORP042-PR-001, Seismic Hazard & Screening Report in Response to the 50.54(f) Information Request Re Fukishima Near-Term Task Force Recommendation 2.1 Seismic2014-03-13013 March 2014 DUKCORP042-PR-001, Seismic Hazard & Screening Report in Response to the 50.54(f) Information Request Re Fukishima Near-Term Task Force Recommendation 2.1 Seismic ML14041A2952013-12-0202 December 2013 Document No. 1457690303-R-M-00005-0, Revision 0, NTTF 2.3 Seismic Peer Review Supplementary Report, Catawba Nuclear Station Unit 2. 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 ML13276A5052013-09-25025 September 2013 Transition Report, Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 2 of 2 ML13276A5042013-09-25025 September 2013 Transition Report, Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition. Part 1 of 2 ML14353A0282013-04-30030 April 2013 WCAP-16083-NP, Revision 1, Benchmark Testing of the Ferret Code for Least Squares Evaluation of Light Water Reactor Dosimetry ML13162A0702013-03-14014 March 2013 1457690303-R-M-00004-0, NTTF 2.3 Seismic Peer Review Supplementary Report ML13162A0722012-11-18018 November 2012 1457690303-R-M-00003-0, NTTF 2.3 Seismic Peer Review Report ML12167A0162012-06-21021 June 2012 Review of the 2011 Steam Generator Tube Inservice Inspection During Refueling Outage End of Cycle 19 ML12153A3292012-03-31031 March 2012 Attachment 6 - Duke Energy Methodology Report DPC-NE-1007, Revision 0, Conditional Exemption of the EOC Mtc Measurement Methodology (Non-proprietary) ML11327A1492011-11-22022 November 2011 Proposed Technical Specifications (TS) and Bases Amendment TS and Bases 3.7.8, Nuclear Service Water System (Nsws) ML11244A0552011-09-12012 September 2011 Review of the 2010 Steam Generator Tube Inspections During Refueling Outage 17 End of Cycle 17 ML11188A1082011-06-30030 June 2011 WCAP-17330-NP, Rev 1, H*: Resolution of NRC Technical Issue Regarding Tubesheet Bore Eccentricity (Model F/Model D5). (Non-Proprietary) NEI 99-04, Catawba, Units 1 & 2, Submittal of Commitment Change Evaluation Report for 20102011-03-30030 March 2011 Catawba, Units 1 & 2, Submittal of Commitment Change Evaluation Report for 2010 ML1109603572011-03-30030 March 2011 Submittal of Commitment Change Evaluation Report for 2010 ML16102A1592010-09-30030 September 2010 DPC-NE-3002-A Rev 4b, UFSAR Chapter 15 System Transient Analysis Methodology. ML1028504722010-09-29029 September 2010 CNEI-0400-203, Revision 0, Appendix a Power Distribution Monitoring Factors ML1023001682010-08-16016 August 2010 Units 1 & 2 - Supplement 2 to License Amendment Request for Duke Energy Cyber Security Plan ML1028504742010-08-0505 August 2010 CNEI-0400-203, Revision 0, Catawba, Unit 2 Cycle 18 Core Operating Limits Report ML1016700892010-06-10010 June 2010 Stations, Units 1 and 2 - Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model ML1019304172010-05-0606 May 2010 Tritium Database Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1011802492010-04-22022 April 2010 2009 10CFR50.59 Summary Report ML1017303842009-08-25025 August 2009 Westinghouse LTR-SGMP-09-109 NP-Attachment, Response to NRC Request for Additional Information on H*: RAI #4; Model F and Model D5 Generators. ML1017303912009-08-12012 August 2009 Westinghouse LTR-SGMP-09-100 NP-Attachment, Response to NRC Request for Additional Information on H*; Model F and Model D5 Steam Generators. ML1017303892009-05-31031 May 2009 WCAP-17072-NP, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model D5). ML16102A1582009-05-31031 May 2009 DPC-NE-3001-A, Rev 0a, Multidimensional Reactor Transients & Safety Analysis Physics Parameters Methodology. ML0904007952009-02-0404 February 2009 GSI-189 Action Plan, Feb. 09 Update, Publicly Available Version 2022-07-07
[Table view] Category:Miscellaneous
MONTHYEARRA-22-0115, Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle2022-04-21021 April 2022 Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 CNS-17-043, Report 16C4437-RPT-002, Revision 0, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for Catawba Nuclear Station.2017-07-0707 July 2017 Report 16C4437-RPT-002, Revision 0, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for Catawba Nuclear Station. CNS-17-022, Summary of 10CFR 50.54(q) Evaluation2017-04-25025 April 2017 Summary of 10CFR 50.54(q) Evaluation ML15253A4102016-03-11011 March 2016 Enclosure 2 Screening Analysis Report 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 ML15238A7392015-08-24024 August 2015 Submittal of 10 CFR 71.95 Report on the 8-120B Cask CNS-15-049, Submittal of 2013/2014 10 CFR 50.59 Summary Report of Changes, Tests, Experiments, and Evaluations2015-05-11011 May 2015 Submittal of 2013/2014 10 CFR 50.59 Summary Report of Changes, Tests, Experiments, and Evaluations ML15096A5132015-04-27027 April 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Revaluations Relating to Recommendation 2.1 of the NTTF Review ML15093A4212015-03-31031 March 2015 Submittal of CNEI-0400-281, Revision 0, Core Operating Limits Reports for Cycle 21 Reload Core, Calculation CNC-1553.05-00-0621 CNS-15-031, Commitment Change Evaluation Report for 20142015-03-24024 March 2015 Commitment Change Evaluation Report for 2014 CNS-14-131, WCAP-17669-NP, Revision 0, Catawba Unit 1 Measurement Uncertainty Recapture (Mur) Power Uprate: Reactor Vessel Integrity and Neutron Fluence Evaluations2014-06-30030 June 2014 WCAP-17669-NP, Revision 0, Catawba Unit 1 Measurement Uncertainty Recapture (Mur) Power Uprate: Reactor Vessel Integrity and Neutron Fluence Evaluations ML14108A2012014-05-16016 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident CNS-14-045, Commitment Change Evaluation Report for 20132014-03-31031 March 2014 Commitment Change Evaluation Report for 2013 ML12167A0162012-06-21021 June 2012 Review of the 2011 Steam Generator Tube Inservice Inspection During Refueling Outage End of Cycle 19 NEI 99-04, Catawba, Units 1 & 2, Submittal of Commitment Change Evaluation Report for 20102011-03-30030 March 2011 Catawba, Units 1 & 2, Submittal of Commitment Change Evaluation Report for 2010 ML1109603572011-03-30030 March 2011 Submittal of Commitment Change Evaluation Report for 2010 ML1023001682010-08-16016 August 2010 Units 1 & 2 - Supplement 2 to License Amendment Request for Duke Energy Cyber Security Plan ML1016700892010-06-10010 June 2010 Stations, Units 1 and 2 - Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model ML1019304172010-05-0606 May 2010 Tritium Database Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1011802492010-04-22022 April 2010 2009 10CFR50.59 Summary Report ML1017303842009-08-25025 August 2009 Westinghouse LTR-SGMP-09-109 NP-Attachment, Response to NRC Request for Additional Information on H*: RAI #4; Model F and Model D5 Generators. ML1017303912009-08-12012 August 2009 Westinghouse LTR-SGMP-09-100 NP-Attachment, Response to NRC Request for Additional Information on H*; Model F and Model D5 Steam Generators. ML1017303892009-05-31031 May 2009 WCAP-17072-NP, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model D5). ML0904005742009-02-0404 February 2009 Special Report, Revision 1 ML0821201412008-06-23023 June 2008 Operating Report for Cycle 17 Operation with Mixed Oxide (MOX) Fuel Lead Assemblies ML0812700912008-04-30030 April 2008 Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML0809303122008-03-26026 March 2008 Steam Generator Outage Summary 180-Day Report for End of Cycle 15 Refueling Outage ML0806505592008-02-29029 February 2008 Response to Request for Additional Information on GL-04-002 ML0731000852007-11-0101 November 2007 Transmittal of DPC-NE-2012-A, Dynamic Rod Worth Measurement Using Casmo/Simulate ML0708005462007-03-13013 March 2007 Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model ML0706504222007-02-27027 February 2007 Fitness-For-Duty Program Performance Data Reports for Period July 1, 2006 Through December 31, 2006 ML0704702722007-02-0808 February 2007 Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds ML0636100922006-12-19019 December 2006 Request for Relief Number 06-GO-001 Alloy 600 Pressurizer Weld Overlays - Submittal of Committed Information ML0636102172006-12-14014 December 2006 Request for Relief Number 06-GO-001, Alloy 600 Pressurizer Weld Overlays - Submittal of Committed Information ML0625501122006-08-31031 August 2006 Steam Generator Outage Summary 180-day Report for End of Cycle 14 Refueling Outage ML0624904272006-08-28028 August 2006 Fitness-For Duty Program Performance Data Reports for Period Covering January 1, 2006 Through June 30, 2006 ML0620602962006-07-18018 July 2006 Steam Generator Outage Summary Inservice Inspection Report for End of Cycle 14 Refueling Outage ML0606601682006-02-21021 February 2006 Fitness-For-Duty Program Performance Data Reports ML0524402932005-08-24024 August 2005 Fitness-For-Duty Program Performance Data Reports ML0517902102005-06-21021 June 2005 Report Pursuant to 10 CFR 50.46, Changes to or Errors in an ECCS Evaluation Model ML0509702852005-03-31031 March 2005 2004 10 CFR 50.59 Report ML0506100302005-02-18018 February 2005 Duke Energy Corporation, Fitness-For-Duty Program Performance Data Reports for Period Covering 07/01/2004 Through 12/31/2004 ML0424505372004-08-20020 August 2004 Letter Transmitting Fitness-For-Duty Program Performance Data Reports for Duke Energy Corp Oconee, McGuire and Catawba Nuclear Stations and the General Office ML0410501212004-04-0505 April 2004 CFR50.59 Report Containing a Brief Description of Changes, Tests, and Experiments, Including a Summary of the Safety Evaluation of Each Unit ML0324715282003-08-22022 August 2003 Fitness-for-Duty Program Performance Data Reports ML0312100492003-04-24024 April 2003 Duke Energy Topical Report Response to Request for Additional Information Letter Dated April 4, 2003 ML0306306812003-02-25025 February 2003 Fitness-for-Duty Program, Performance Data Reports ML0226600412002-09-12012 September 2002 Response to Request for Additional Information - Topical Report DPC-NE-1005P, Revision 0, Nuclear Design Methodology Using CASMO/4SIMULATE-3 MOX (Proprietary) 2022-04-21
[Table view] |
Text
Kelvin Henderson
( ENERGY.
Vice President Catawba Nuclear Station Duke Energy CN01VP 1 4800 Concord Road York, SC 29745 o:803.701.4251 f: 803.701.3221 CNS-15-031 March 24, 2015 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke)
Catawba Nuclear Station, Units 1 and 2 Docket Nos.: 50-413 and 50-414 Commitment Change Evaluation Report for 2014 Attached is a summary of commitment change evaluations completed during the 2014 calendar year for Catawba Nuclear Station. These evaluations and subsequent commitment changes were made based on the guidance defined in NEI 99-04, Guidelines for Managing NRC Commitments, and have no adverse effect on compliance with NRC rules and regulations.
Questions regarding this report should be directed to Cecil Fletcher, Regulatory Affairs Manager, at 803-701-3622.
Sincerely, elvin Henderson Vice President, Catawba Nuclear Station Attachment F) www.duke-energy.com
a U. S. Nuclear Regulatory Commission March 24, 2015 Page 2 xc:
V. M. McCree, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 G. Edward Miller NRC Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8-G9A 11555 Rockville Pike Rockville, MD 20852-2738 G. A. Hutto Senior Resident Inspector CN01NC
Catawba Nuclear Station Annual Commitment Change Summary Report for 2014 Docket Nos. 50-413 and 50-414 NRC Notification Number Source Document Original Commitment Modified Commitment Required Yes 2014-C-001 NRC Generic Letter Response The intake and pit inspections will Defer the inspection of Nuclear Service (November 27,1997) and be performed on a three year Water (RN) Pump Pit A to no later than Commitment Change #2002-C- frequency commencing from the 11/20/2014. This is a one-time deferral.
005 last RN intake and Train B pump pit inspection conducted on 4/24/02. The inspection of the A train RN Pump Pit is due 07/07/2014. This inspection was scheduled for March of 2014 but could not be performed due to issues with providing adequate isolation of the pit. In order to minimize safety system unavailability, this inspection will be performed during scheduled valve maintenance which will require A train of RN to be removed from service.
The most recent A train pit inspection was performed during refueling outage 1EOC17, October, 2010. No structural issues were identified with the condition of the pit and associated structures, as documented in the work order completion comments.
The A and B train pits are operated in the same manner. Therefore, the condition of the B train pit is considered to be indicative of the condition of the A pit.
The latest inspection of the B pit was performed in February, 2012. The results of that inspection concluded that no structural issues were present with respect to concrete, structural steel or the intake screens. As noted in the Corrective Action Program, the pit was in very good condition (C-12-1403). This indicates the A pit is also in a similar Page 1
NRC Notification Number Source Document Original Commitment Modified Commitment Required condition.
Therefore, deferring the next committed A train pump pit inspection by four months (11/30/14) to minimize safety system unavailability will not result in any potential challenge of the A train of the RN system from being capable of meeting its design basis requirements.
This deferral is only applicable to this single occurrence.
Yes 2014-C-002 Letter from Thomas P. Harrall, Monitor the status of the TSTF Complete the evaluation of TSTF-523 and Duke Energy, to NRC, dated effort to provide revisions to submit a letter to the NRC providing a October 13, 2008, "Generic NUREG-1431 Technical schedule for submittal of a License Letter 2008-01, 9-Month Specifications and their associated Amendment Request by October 15, Response" Bases in regard to the periodic 2014.
venting surveillance. Catawba will evaluate the resolution of TS issues Duke Energy's evaluation of TSTF-523 is with respect to the changes continuing. Additional time is needed to contained in the TSTF traveler, and complete the evaluation, and to prepare, submit a license amendment process, and submit an LAR. Therefore, request based on this evaluation Duke Energy is revising the commitments within 180 days following NRC to complete the evaluation and provide a approval of the TSTF. schedule for submittal of an LAR by October 15, 2014. Duke Energy believes that the actions completed in response to Generic Letter 2008-01 provide confidence that safety will be preserved during the extended evaluation period that the revised regulatory commitments afford.
Yes 2014-C-003 Letter from Bill Pitesa, Duke Implementation Milestone 8 of the Revise Implementation Milestone 8 Energy, to NRC dated April 15, Cyber Security Plan is to Complete completion date of June 30, 2015, to 2011, "License Amendment Operational and Management December 31, 2017.
Request for Cyber Security controls as provided in NEI 08-09, Plan" Rev. 6, Appendix E, by June 30, The scope of the Critical Digital Asset 2015. (CDA) assessment activities was substantially underestimated by Duke Page 2
NRC Notification Number Source Document Original Commitment Modified Commitment Required Energy. The Milestone 8 completion date was established prior to any significant work being performed on program implementation; therefore, the scope of the assessment activities was not fully appreciated. The scope of the CDA assessment activities was also substantially underestimated by the industry in general, as evidenced by the need for additional industry guidance.
Therefore, Duke Energy (DEC) is revising the commitment for Milestone 8 completion date of June 30, 2015, to December 31, 2017. Milestone 8 pertains to the date that complete operational and management controls, as provided in Nuclear Energy Institute 08-09, Revision 6, Appendix E, will be achieved. Based on the status of the cyber security program, Duke Energy believes that safety will be preserved during the approval period that the revised regulatory commitments afford.
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