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| {{#Wiki_filter:CNS-16-077 December 8, 2016 Attention: | | {{#Wiki_filter:TomSimr.il Vice :P,r.esident Catawba :l'iluclear:Statiom Duke Ener,gy CN01MP I 4800 Concord Road York, SC 29.745 |
| Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555-0001 Duke Energy Carolinas, LLC (Duke Energy) Catawba Nuclear Station (CNS), Units 1 and 2 Docket Nos. 50-413 and 50-414 Renewed License Nos. NPF-35 and NPF-52 TomSimr.il Vice :P,r.esident Catawba :l'iluclear:Statiom Duke Ener,gy CN01MP I 4800 Concord Road York, SC 29.745 .o.: 803.7c01.334.Q f: ,803.701.322j tom.simril@duke"enerogy.,com 10 CFR 50.54(f) | | .o.: 803.7c01.334.Q f: ,803.701.322j tom.simril@duke"enerogy.,com 10 CFR 50.54(f) |
| | CNS-16-077 December 8, 2016 Attention: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555-0001 Duke Energy Carolinas, LLC (Duke Energy) |
| | Catawba Nuclear Station (CNS), Units 1 and 2 Docket Nos. 50-413 and 50-414 Renewed License Nos. NPF-35 and NPF-52 |
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| ==Subject:== | | ==Subject:== |
| Catawba Nuclear Station Expedited Seismic Evaluation Process (ESEP) 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 | | Catawba Nuclear Station Expedited Seismic Evaluation Process (ESEP) 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 |
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| ==References:== | | ==References:== |
| : 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012 (ADAMS Accession No. ML12053A340) | | : 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012 (ADAMS Accession No. ML12053A340) |
| : 2. NEI Letter, Proposed Path Forward for NTTF Recommendation 2.1: Seismic Reevaluations, dated April 9, 2013 (ADAMS Accession No. ML13101A379) | | : 2. NEI Letter, Proposed Path Forward for NTTF Recommendation 2.1: Seismic Reevaluations, dated April 9, 2013 (ADAMS Accession No. ML13101A379) |
| : 3. NRC Letter, Electric Power Research Institute Final Draft Report XXXXXX, "Seismic Evaluation Guidance: | | : 3. NRC Letter, Electric Power Research Institute Final Draft Report XXXXXX, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Near-Term Task Force Recommendation 2.1: Seismic", as an Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013 (ADAMS Accession No. ML13106A331) |
| Augmented Approach for the Resolution of Near-Term Task Force Recommendation 2.1: Seismic", as an Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013 (ADAMS Accession No. ML13106A331) | | : 4. Electric Power Research Institute (EPRI) Final Report 3002000704, Seismic Evaluation Guidance, Augmented Approach for the Resolution of Fukushima Near Term Task Force Recommendation 2.1: Seismic, dated May 2013 |
| : 4. Electric Power Research Institute (EPRI) Final Report 3002000704, Seismic Evaluation Guidance, Augmented Approach for the Resolution of Fukushima Near Term Task Force Recommendation 2.1: Seismic, dated May 2013 5. Duke Energy Letter, Errata Letter for 1 O CFR 50.54(f) Submittal of Expedited Seismic Evaluation Process (ESEP) Report, Revision 2, dated November 5, 2015 (ADAMS Accession No. ML15317A013) | | : 5. Duke Energy Letter, Errata Letter for 10 CFR 50.54(f) Submittal of Expedited Seismic Evaluation Process (ESEP) Report, Revision 2, dated November 5, 2015 (ADAMS Accession No. ML15317A013) |
| United States Nuclear Regulatory Commission December 8, 2016 Page 2 On March 12, 2012, the Nuclear Regulatory Commission (NRG) issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 1 of Reference 1 requested each addressee located in the Central and Eastern United States (CEUS) to submit a Seismic Hazard Evaluation and Screening Report within 1.5 years from the date of Reference | | |
| : 1. The Nuclear Energy Institute (NEI) submitted Reference 2 requesting NRC agreement to delay submittal of the CEUS Seismic Hazard Evaluation and Screening, as well as endorsement of the guidance.
| | United States Nuclear Regulatory Commission December 8, 2016 Page 2 On March 12, 2012, the Nuclear Regulatory Commission (NRG) issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 1 of Reference 1 requested each addressee located in the Central and Eastern United States (CEUS) to submit a Seismic Hazard Evaluation and Screening Report within 1.5 years from the date of Reference 1. |
| The delay and industry guidance was endorsed by the NRC in a letter dated May 7, 2013 (Reference 3). In accordance with the NRG endorsed guidance of the final EPRI Seismic Evaluation Guidance Report 3002000704, dated May 2013 (Reference 4), the ESEP Report for Catawba was provided by a letter dated November 5, 2015 (Reference 5). Pursuant to Action #4 as listed in Table 8-1 of Section 8.4 of Reference 5, all required seismic walkdowns, evaluations, and modifications for Catawba Units 1 and 2 identified in the ESEP report have been completed. | | The Nuclear Energy Institute (NEI) submitted Reference 2 requesting NRC agreement to delay submittal of the CEUS Seismic Hazard Evaluation and Screening, as well as endorsement of the guidance. The delay and industry guidance was endorsed by the NRC in a letter dated May 7, 2013 (Reference 3). |
| No additional changes have been made to the enclosure in the Reference 5 letter. There are no regulatory commitments associated with this letter. Should you have any questions regarding this submittal, please contact Sherry Andrews at 803-701-3424. | | In accordance with the NRG endorsed guidance of the final EPRI Seismic Evaluation Guidance Report 3002000704, dated May 2013 (Reference 4), the ESEP Report for Catawba was provided by a letter dated November 5, 2015 (Reference 5). Pursuant to Action #4 as listed in Table 8-1 of Section 8.4 of Reference 5, all required seismic walkdowns, evaluations, and modifications for Catawba Units 1 and 2 identified in the ESEP report have been completed. No additional changes have been made to the enclosure in the Reference 5 letter. |
| I declare under penalty of perjury that the foregoing is true and correct. Executed on December 8, 2016. Sincerely, Tom Simril Site' Vice President, Catawba Nuclear Station United States Nuclear Regulatory Commission December 8, 2016 Page 3 xc: C. Haney, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 P.J. Bamford, Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mailstop 13 F15 11555 Rockville Pike Rockville, MD 20852-2738 Michael D. Orenak, Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mailstop 0-8G9A 11555 Rockville Pike Rockville, MD 20852-2738 J.D. Austin U.S. NRC Senior Resident Catawba Nuclear Station Justin Folkwein American Nuclear Insurers 95 Glastonbury Blvd., Suite 300 Glastonbury, CT 06033-4453}} | | There are no regulatory commitments associated with this letter. |
| | Should you have any questions regarding this submittal, please contact Sherry Andrews at 803-701-3424. |
| | I declare under penalty of perjury that the foregoing is true and correct. Executed on December 8, 2016. |
| | Sincerely, Tom Simril Site' Vice President, Catawba Nuclear Station |
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| | United States Nuclear Regulatory Commission December 8, 2016 Page 3 xc: |
| | C. Haney, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 P.J. Bamford, Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mailstop 13 F15 11555 Rockville Pike Rockville, MD 20852-2738 Michael D. Orenak, Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mailstop 0-8G9A 11555 Rockville Pike Rockville, MD 20852-2738 J.D. Austin U.S. NRC Senior Resident Catawba Nuclear Station Justin Folkwein American Nuclear Insurers 95 Glastonbury Blvd., Suite 300 Glastonbury, CT 06033-4453}} |
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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:Response to Request for Additional Information (RAI)
MONTHYEARRA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require RA-22-0195, Response to Request for Additional Information (RAI) for the Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue for the Safety Injection Nozzle2022-06-29029 June 2022 Response to Request for Additional Information (RAI) for the Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue for the Safety Injection Nozzle RA-22-0147, Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility2022-05-13013 May 2022 Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility RA-22-0102, Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology2022-04-0707 April 2022 Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology RA-22-0003, Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative2022-01-31031 January 2022 Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative RA-21-0321, Response to Request for Additional Information (RAI) Regarding Refuel 24 (C2R24) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report2021-12-14014 December 2021 Response to Request for Additional Information (RAI) Regarding Refuel 24 (C2R24) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report RA-21-0063, 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan2021-03-11011 March 2021 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan RA-21-0032, Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(42021-02-11011 February 2021 Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)( RA-21-0017, Response to Request for Additional Information Re License Amendment Request to Revise Tech Spec 3.8.1 to Reduce Emergency Diesel Generator Maximum Steady State Voltage2021-01-29029 January 2021 Response to Request for Additional Information Re License Amendment Request to Revise Tech Spec 3.8.1 to Reduce Emergency Diesel Generator Maximum Steady State Voltage RA-20-0104, Response to NRC Request for Additional Information - Catawba Nuclear Station-SG Report (RA-19-0391)-C2R232020-04-0606 April 2020 Response to NRC Request for Additional Information - Catawba Nuclear Station-SG Report (RA-19-0391)-C2R23 RA-20-0002, Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits2020-02-13013 February 2020 Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits RA-19-0280, Response to NRC RAI Clarifications Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.12019-07-10010 July 2019 Response to NRC RAI Clarifications Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 RA-19-0189, Supplement to Response for Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.12019-04-0808 April 2019 Supplement to Response for Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 RA-19-0004, Response to NRC for Additional Information (RAI) Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 for Catawba Nuclear Station, Units 1 and 22019-03-0707 March 2019 Response to NRC for Additional Information (RAI) Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 for Catawba Nuclear Station, Units 1 and 2 RA-19-0026, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)2019-02-11011 February 2019 Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001) RA-18-0162, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2018-12-0606 December 2018 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal RA-18-0097, (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 System2018-08-17017 August 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-18-023, (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 NRC-18-0016, Response to Request for Additional Information (Set 2) Regarding License Amendment Request to Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Reactor Trip and Primary Containment Isolation System Group 1..2018-02-21021 February 2018 Response to Request for Additional Information (Set 2) Regarding License Amendment Request to Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Reactor Trip and Primary Containment Isolation System Group 1.. 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-17-047, 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 RA-17-0039, Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001)2017-08-0909 August 2017 Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001) 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-17-0036, Supplement to the Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers2017-07-17017 July 2017 Supplement to the Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers RA-17-0029, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers2017-06-0808 June 2017 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers 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-17-004, 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-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.. RA-16-0035, Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation2016-10-0303 October 2016 Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation 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-16-051, 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 ML16204A0602016-07-20020 July 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant, Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident RA-16-0027, Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations2016-07-14014 July 2016 Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations CNS-16-043, Additional Information Regarding Flood Hazard Reevaluation Report, Response to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Forc2016-06-23023 June 2016 Additional Information Regarding Flood Hazard Reevaluation Report, Response to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force CNS-16-035, License Amendment Request to Revise Technical Specifications Permanent Extension of Type a and Type C Leak Rate Test Frequencies, Responses to NRC Requests for Additional Information CAC Nos. MF7265 and MF72662016-06-20020 June 2016 License Amendment Request to Revise Technical Specifications Permanent Extension of Type a and Type C Leak Rate Test Frequencies, Responses to NRC Requests for Additional Information CAC Nos. MF7265 and MF7266 CNS-16-022, Supplemental Information to the Final Notification of Full Compliance with Order EA-12-049,Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051, Et2016-03-31031 March 2016 Supplemental Information to the Final Notification of Full Compliance with Order EA-12-049,Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051, Et A MNS-16-023, Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request for Control Room Chilled Water System Technical Specifications2016-03-16016 March 2016 Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request for Control Room Chilled Water System Technical Specifications ML16102A1562016-03-11011 March 2016 Proposed Technical Specifications Amendments, TS 3.4.1, Reactor Coolant System Pressure, Temperature and Flow Departure from Nucleate Boiling Limits, Response to NRC Request for Additional Information ML16055A2272016-02-19019 February 2016 Response to Request for Additional Information and Emergency Action Level Technical Bases Document, Revision 1, Redline Version. Part 1 of 4 ML16055A2282016-02-19019 February 2016 Response to Request for Additional Information and Emergency Action Level Technical Bases Document, Revision 1, Redline Version. Part 2 of 4 CNS-16-010, Response to Request for Additional Information and Emergency Action Level Technical Bases Document, Revision 1, Clean Version. Part 4 of 42016-02-19019 February 2016 Response to Request for Additional Information and Emergency Action Level Technical Bases Document, Revision 1, Clean Version. Part 4 of 4 ML16055A2302016-02-19019 February 2016 Response to Request for Additional Information and Emergency Action Level Technical Bases Document, Revision 1, Redline Version. Part 3 of 4 RA-16-0006, Response to NRC Request for Additional Information (RAI) Regarding Application to Use Alternate Fission Gas Gap Release Fractions2016-02-0101 February 2016 Response to NRC Request for Additional Information (RAI) Regarding Application to Use Alternate Fission Gas Gap Release Fractions ML15324A0832015-11-16016 November 2015 License Amendment Request (LAR) for Measurement Uncertainty Recapture (Mur) Power Uprate, Response to NRC Requests for Additional Information (Rais) CNS-15-086, License Amendment Request (LAR) for Changes to Technical Specification (TS) 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation and TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start..2015-10-23023 October 2015 License Amendment Request (LAR) for Changes to Technical Specification (TS) 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation and TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start.. CNS-15-075, License Amendment Request (LAR) for Changes to Technical Specification (TS) 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation and TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start..2015-08-17017 August 2015 License Amendment Request (LAR) for Changes to Technical Specification (TS) 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation and TS 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start.. 2023-07-07
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TomSimr.il Vice :P,r.esident Catawba :l'iluclear:Statiom Duke Ener,gy CN01MP I 4800 Concord Road York, SC 29.745
.o.: 803.7c01.334.Q f: ,803.701.322j tom.simril@duke"enerogy.,com 10 CFR 50.54(f)
CNS-16-077 December 8, 2016 Attention: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555-0001 Duke Energy Carolinas, LLC (Duke Energy)
Catawba Nuclear Station (CNS), Units 1 and 2 Docket Nos. 50-413 and 50-414 Renewed License Nos. NPF-35 and NPF-52
Subject:
Catawba Nuclear Station Expedited Seismic Evaluation Process (ESEP) 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
References:
- 1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012 (ADAMS Accession No. ML12053A340)
- 2. NEI Letter, Proposed Path Forward for NTTF Recommendation 2.1: Seismic Reevaluations, dated April 9, 2013 (ADAMS Accession No. ML13101A379)
- 3. NRC Letter, Electric Power Research Institute Final Draft Report XXXXXX, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Near-Term Task Force Recommendation 2.1: Seismic", as an Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013 (ADAMS Accession No. ML13106A331)
- 4. Electric Power Research Institute (EPRI) Final Report 3002000704, Seismic Evaluation Guidance, Augmented Approach for the Resolution of Fukushima Near Term Task Force Recommendation 2.1: Seismic, dated May 2013
- 5. Duke Energy Letter, Errata Letter for 10 CFR 50.54(f) Submittal of Expedited Seismic Evaluation Process (ESEP) Report, Revision 2, dated November 5, 2015 (ADAMS Accession No. ML15317A013)
United States Nuclear Regulatory Commission December 8, 2016 Page 2 On March 12, 2012, the Nuclear Regulatory Commission (NRG) issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 1 of Reference 1 requested each addressee located in the Central and Eastern United States (CEUS) to submit a Seismic Hazard Evaluation and Screening Report within 1.5 years from the date of Reference 1.
The Nuclear Energy Institute (NEI) submitted Reference 2 requesting NRC agreement to delay submittal of the CEUS Seismic Hazard Evaluation and Screening, as well as endorsement of the guidance. The delay and industry guidance was endorsed by the NRC in a letter dated May 7, 2013 (Reference 3).
In accordance with the NRG endorsed guidance of the final EPRI Seismic Evaluation Guidance Report 3002000704, dated May 2013 (Reference 4), the ESEP Report for Catawba was provided by a letter dated November 5, 2015 (Reference 5). Pursuant to Action #4 as listed in Table 8-1 of Section 8.4 of Reference 5, all required seismic walkdowns, evaluations, and modifications for Catawba Units 1 and 2 identified in the ESEP report have been completed. No additional changes have been made to the enclosure in the Reference 5 letter.
There are no regulatory commitments associated with this letter.
Should you have any questions regarding this submittal, please contact Sherry Andrews at 803-701-3424.
I declare under penalty of perjury that the foregoing is true and correct. Executed on December 8, 2016.
Sincerely, Tom Simril Site' Vice President, Catawba Nuclear Station
United States Nuclear Regulatory Commission December 8, 2016 Page 3 xc:
C. Haney, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 P.J. Bamford, Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mailstop 13 F15 11555 Rockville Pike Rockville, MD 20852-2738 Michael D. Orenak, Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mailstop 0-8G9A 11555 Rockville Pike Rockville, MD 20852-2738 J.D. Austin U.S. NRC Senior Resident Catawba Nuclear Station Justin Folkwein American Nuclear Insurers 95 Glastonbury Blvd., Suite 300 Glastonbury, CT 06033-4453