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Category:Letter type:NG
MONTHYEARNG-23-0010, Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-12-0606 December 2023 Supplement to Duane Arnold Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule NG-23-0009, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule NG-23-0006, Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-05-23023 May 2023 Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update NG-23-0004, 2022 Annual Radioactive Material Release Report2023-04-25025 April 2023 2022 Annual Radioactive Material Release Report NG-23-0003, 2022 Annual Exposure Report - Form 5s2023-04-21021 April 2023 2022 Annual Exposure Report - Form 5s NG-23-0002, 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report2023-03-27027 March 2023 10 CFR 50.59 Report, Commitment Changes, 10 CFR 72.48 Report, Quality Assurance Program Changes, Technical Specification Basis Changes, and Revision of the DAEC Defueled Safety Analysis Report NG-23-0001, 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report2023-03-27027 March 2023 2023 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-22-0055, Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan2022-05-20020 May 2022 Revision to Duane Arnold Energy Center (DAEC) ISFSI-Only Emergency Plan NG-22-0053, 2021 Annual Radiological Environmental Operating Report2022-05-0606 May 2022 2021 Annual Radiological Environmental Operating Report NG-22-0052, Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative2022-05-0404 May 2022 Regulatory Issue Summary 2000-11. NRC Emergency Telecommunications System, Statement of Intent to Implement the Proposed Voluntary Initiative NG-22-0050, Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 02022-04-26026 April 2022 Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 0 NG-22-0049, 2021 Annual Radioactive Material Release Report2022-04-26026 April 2022 2021 Annual Radioactive Material Release Report NG-22-0035, Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 02022-04-13013 April 2022 Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 0 NG-22-0047, Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool2022-04-11011 April 2022 Registration of Independent Spent Fuel Installation Storage Cask and Notification of Permanent Removal of All Spent Fuel Assemblies from the Spent Fuel Pool NG-22-0042, Registration of Independent Spent Fuel Installation Storage Casks2022-04-0808 April 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0041, and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report2022-03-31031 March 2022 and Independent Spent Fuel Storage Installation, 2022 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-22-0031, 2021 Annual Exposure Report - Form 5s2022-03-23023 March 2022 2021 Annual Exposure Report - Form 5s NG-22-0030, Registration of Independent Spent Fuel Installation Storage Casks2022-03-23023 March 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0025, Registration of Independent Spent Fuel Installation Storage Casks2022-03-0808 March 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0021, Registration of Independent Spent Fuel Installation Storage Casks2022-02-24024 February 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0014, Registration of Independent Spent Fuel Installation Storage Casks2022-02-10010 February 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0009, Registration of Independent Spent Fuel Installation Storage Casks2022-01-20020 January 2022 Registration of Independent Spent Fuel Installation Storage Casks NG-22-0001, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister2022-01-0606 January 2022 Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61BTH Type 2 Dry Shielded Canister NG-21-0038, Registration of Independent Spent Fuel Installation Storage Casks2021-12-22022 December 2021 Registration of Independent Spent Fuel Installation Storage Casks NG-21-0035, Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister2021-12-10010 December 2021 Supplement to Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister NG-21-0030, Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister2021-10-21021 October 2021 Exemption Request for Failed Fuel Can Weight in a Certificate of Compliance 1004 Renewed Amendment 17 61 Bth Type 2 Dry Shielded Canister NG-21-0028, Request for Approval of NextEra Energy Duane Arnold, Llc'S Decommissioning Quality Assurance Program Revision 02021-07-30030 July 2021 Request for Approval of NextEra Energy Duane Arnold, Llc'S Decommissioning Quality Assurance Program Revision 0 NG-21-0010, License Amendment Request (TSCR-192): Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme2021-06-28028 June 2021 License Amendment Request (TSCR-192): Independent Spent Fuel Storage Installation (ISFSI) Emergency Plan and Emergency Action Level Scheme NG-21-0026, CFR 72.48 Report of Changes. Tests. and Experiments2021-06-16016 June 2021 CFR 72.48 Report of Changes. Tests. and Experiments NG-21-0011, Submittal of 2020 Annual Radiological Environmental Operating Report2021-05-0404 May 2021 Submittal of 2020 Annual Radiological Environmental Operating Report NG-21-0009, Report of Facility Changes. Tests and Experiments. and Commitment Changes2021-04-27027 April 2021 Report of Facility Changes. Tests and Experiments. and Commitment Changes NG-21-0021, Supplement to License Amendment Request (TSCR-185): Application to Revise Operating License to Remove Cyber Security Plan Requirements2021-04-22022 April 2021 Supplement to License Amendment Request (TSCR-185): Application to Revise Operating License to Remove Cyber Security Plan Requirements NG-21-0006, 2021 Annual Decommissioning and Spent Fuel Management Funding Status Report2021-03-31031 March 2021 2021 Annual Decommissioning and Spent Fuel Management Funding Status Report NG-21-0005, NextEra Energy Duane Arnold, LLC - Transmittal of the DAEC Defueled Safety Analysis Report Revision 02021-03-29029 March 2021 NextEra Energy Duane Arnold, LLC - Transmittal of the DAEC Defueled Safety Analysis Report Revision 0 NG-20-0094, License Amendment Request (TSCR-189): Revision to Facility License and Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool2021-02-19019 February 2021 License Amendment Request (TSCR-189): Revision to Facility License and Technical Specifications to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pool NG-21-0004, Response to Request for Additional Information Related to Post Shutdown Decommissioning Activities Report2021-02-0505 February 2021 Response to Request for Additional Information Related to Post Shutdown Decommissioning Activities Report NG-20-0078, Update to Spent Fuel Management Plan Pursuant to 10 CFR 50.54(bb)2021-01-13013 January 2021 Update to Spent Fuel Management Plan Pursuant to 10 CFR 50.54(bb) NG-20-0101, Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to COVID-19 Pandemic2020-12-29029 December 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to COVID-19 Pandemic NG-20-0099, Response to Request for Additional Information Relating to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2020-12-0101 December 2020 Response to Request for Additional Information Relating to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme NG-20-0093, Supplement to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2020-10-29029 October 2020 Supplement to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme NG-20-0090, Certification of Permanent Removal of Fuel from the Reactor Vessel for Duane Arnold Energy Center2020-10-12012 October 2020 Certification of Permanent Removal of Fuel from the Reactor Vessel for Duane Arnold Energy Center NG-20-0083, Registration of Independent Spent Fuel Installation Storage Casks2020-10-12012 October 2020 Registration of Independent Spent Fuel Installation Storage Casks NG-20-0069, Response to Request for Additional Information Relating to Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E2020-10-0707 October 2020 Response to Request for Additional Information Relating to Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E NG-20-0082, Registration of Independent Spent Fuel Installation Storage Casks2020-09-28028 September 2020 Registration of Independent Spent Fuel Installation Storage Casks NG-20-0071, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Evaluated Exercise Requirements Due to COVID-19 Pandemic2020-09-22022 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Evaluated Exercise Requirements Due to COVID-19 Pandemic NG-20-0077, Registration of Independent Spent Fuel Installation Storage Casks2020-09-10010 September 2020 Registration of Independent Spent Fuel Installation Storage Casks NG-20-0073, Notice Regarding Proposed Amendment to Decommissioning Trust Agreements2020-09-0101 September 2020 Notice Regarding Proposed Amendment to Decommissioning Trust Agreements NG-20-0074, Certification of Permanent Cessation of Power Operations2020-08-27027 August 2020 Certification of Permanent Cessation of Power Operations NG-20-0067, Registration of Independent Spent Fuel Installation Storage Casks2020-08-12012 August 2020 Registration of Independent Spent Fuel Installation Storage Casks NG-20-0035, Request for Exemption from 10 CFR 50.54(w)(1)2020-07-16016 July 2020 Request for Exemption from 10 CFR 50.54(w)(1) 2023-05-23
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARNG-22-0050, Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 02022-04-26026 April 2022 Revised Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program, Revision 0 NG-22-0035, Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 02022-04-13013 April 2022 Response to Request for Additional Information Relating to Decommissioning Quality Assurance Program. Revision 0 NG-21-0004, Response to Request for Additional Information Related to Post Shutdown Decommissioning Activities Report2021-02-0505 February 2021 Response to Request for Additional Information Related to Post Shutdown Decommissioning Activities Report NG-20-0099, Response to Request for Additional Information Relating to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2020-12-0101 December 2020 Response to Request for Additional Information Relating to License Amendment Request (TSCR-187): Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme NG-20-0069, Response to Request for Additional Information Relating to Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E2020-10-0707 October 2020 Response to Request for Additional Information Relating to Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E NG-20-0050, Response to Request for Additional Information - NextEra Energy Duane Arnold, LLC Quality Assurance Topical Report (FPL-3)2020-06-26026 June 2020 Response to Request for Additional Information - NextEra Energy Duane Arnold, LLC Quality Assurance Topical Report (FPL-3) NG-20-0045, Response to Request for Additional Information (RAI) - Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1 )(Iv)2020-05-29029 May 2020 Response to Request for Additional Information (RAI) - Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1 )(Iv) NG-20-0042, Response to Request for Additional Information Regarding Exemption Request for Security Training Requirements Due to COVID-19 Pandemic2020-05-20020 May 2020 Response to Request for Additional Information Regarding Exemption Request for Security Training Requirements Due to COVID-19 Pandemic ML20016A2752020-01-13013 January 2020 Letter to NRC (1-13-20) FEMA Review of RAI Responses Pertaining to DAEC Emergency Plan to Address the Permanently Shutdown Condition NG-19-0124, Response to Request for Additional Information Relating to Proposed Changes to the Emergency Plan for Permanently Defueled Condition2019-10-28028 October 2019 Response to Request for Additional Information Relating to Proposed Changes to the Emergency Plan for Permanently Defueled Condition NG-19-0071, Response to Request for Additional Information Regarding Request for Approval of Certified Fuel Handler Training Program2019-05-30030 May 2019 Response to Request for Additional Information Regarding Request for Approval of Certified Fuel Handler Training Program NG-18-0121, Response to Second Round - Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - LAR TSCR-166, Adoption of EAL Scheme Pursuant to NEI 99-012018-10-18018 October 2018 Response to Second Round - Request for Additional Information (RAI) - Duane Arnold Energy Center (DAEC) - LAR TSCR-166, Adoption of EAL Scheme Pursuant to NEI 99-01 ML18212A2272018-07-26026 July 2018 Response to Request for Additional Information Regarding License Amendment Request (TSCR-166), Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. (Pa ML18212A2292018-07-26026 July 2018 Response to Request for Additional Information Regarding License Amendment Request (TSCR-166), Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. (Pa ML18212A2312018-07-26026 July 2018 Response to Request for Additional Information Regarding License Amendment Request (TSCR-166), Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. (Pa ML18212A2322018-07-26026 July 2018 Response to Request for Additional Information Regarding License Amendment Request (TSCR-166), Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. (Pa NG-18-0090, Response to Request for Additional Information Regarding License Amendment Request (TSCR-166), Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. (2018-07-26026 July 2018 Response to Request for Additional Information Regarding License Amendment Request (TSCR-166), Adoption of Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. (Pa NG-18-0068, Supplemental Response to Request for Additional Information, Fifth Lnservice Inspection Interval Program Plan, Relief Request RR-052018-06-0505 June 2018 Supplemental Response to Request for Additional Information, Fifth Lnservice Inspection Interval Program Plan, Relief Request RR-05 NG-18-0046, Response to Request for Additional Information, Fifth Inservice Inspection Interval Program Plan, Relief Request RR-052018-04-27027 April 2018 Response to Request for Additional Information, Fifth Inservice Inspection Interval Program Plan, Relief Request RR-05 L-2018-068, Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations2018-04-0303 April 2018 Florida Power and Light Co. - Response to Request for Additional Information Re Decommissioning Funding Plan Updates for Independent Spent Fuel Storage Installations NG-18-0024, Response to Request for Additional Information Regarding License Amendment Request (TSCR-170), Revision to Technical Specification 3.5.1, EGGS-Operating2018-03-0101 March 2018 Response to Request for Additional Information Regarding License Amendment Request (TSCR-170), Revision to Technical Specification 3.5.1, EGGS-Operating NG-18-0013, Response to Second Request for Additional Information, Fifth Inservice Inspection Lnterval Program Plan, Relief Request RR-032018-01-26026 January 2018 Response to Second Request for Additional Information, Fifth Inservice Inspection Lnterval Program Plan, Relief Request RR-03 NG-17-0241, Supplemental Response to Request for Additional Information, Fifth Inservice Inspection Interval Program Plan, Relief Request RR-032017-12-0707 December 2017 Supplemental Response to Request for Additional Information, Fifth Inservice Inspection Interval Program Plan, Relief Request RR-03 NG-17-0207, Response to Request for Additional Information Regarding License Amendment Request (TSCR-168), Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2017-11-0101 November 2017 Response to Request for Additional Information Regarding License Amendment Request (TSCR-168), Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. NG-17-0180, Response to Request for Additional Information, Fifth Lnservice Inspection Interval Program Plan, Relief Request RR-042017-09-12012 September 2017 Response to Request for Additional Information, Fifth Lnservice Inspection Interval Program Plan, Relief Request RR-04 NG-17-0177, Response to Request for Additional Information, Fifth Lnservice Inspection Interval Program Plan, Relief Request RR-012017-09-0505 September 2017 Response to Request for Additional Information, Fifth Lnservice Inspection Interval Program Plan, Relief Request RR-01 NG-17-0117, Revision to Request for Additional Information Relating to Revision to Staff Augmentation Times in the Duane Arnold Energy Center Emergency Plan2017-06-19019 June 2017 Revision to Request for Additional Information Relating to Revision to Staff Augmentation Times in the Duane Arnold Energy Center Emergency Plan NG-17-0077, Response to Request for Additional Information Relating to Revision to Staff Augmentation Times in the Duane Arnold Energy Center Emergency Plan2017-04-0707 April 2017 Response to Request for Additional Information Relating to Revision to Staff Augmentation Times in the Duane Arnold Energy Center Emergency Plan L-2016-188, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)2016-11-0303 November 2016 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools, Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) ML16267A4392016-09-23023 September 2016 Request for Information Letter 9/23/16 (LAS) NG-16-0180, Response to Request for Additional Information, License Amendment Request (TSCR-159) to Revise Technical Specifications Fuel Storage-Requirements - MF74862016-09-21021 September 2016 Response to Request for Additional Information, License Amendment Request (TSCR-159) to Revise Technical Specifications Fuel Storage-Requirements - MF7486 NG-16-0178, Response to Request for Additional Information Relating to Beyond Design Based External Event Staffing Study2016-09-15015 September 2016 Response to Request for Additional Information Relating to Beyond Design Based External Event Staffing Study NG-16-0153, Response to Request for Information Supporting Flooding Hazards Reevaluation Report Audit2016-08-12012 August 2016 Response to Request for Information Supporting Flooding Hazards Reevaluation Report Audit NG-16-0118, Supplemental Response to Request for Additional Information; License Amendment Request (TSCR-143) to Extend Containment Leakage Test Frequency2016-05-31031 May 2016 Supplemental Response to Request for Additional Information; License Amendment Request (TSCR-143) to Extend Containment Leakage Test Frequency NG-16-0076, Response to Request for Additional Information. License Amendment Request (TSCR-143) to Extend Containment Leakage Test Frequency2016-04-14014 April 2016 Response to Request for Additional Information. License Amendment Request (TSCR-143) to Extend Containment Leakage Test Frequency NG-16-0080, Response to Request for Additional Information, License Amendment Request (TSCR-153) to Reduce the Reactor Steam Dome Pressure Specified in the Reactor Core Safety Limits2016-04-12012 April 2016 Response to Request for Additional Information, License Amendment Request (TSCR-153) to Reduce the Reactor Steam Dome Pressure Specified in the Reactor Core Safety Limits NG-16-0055, Resubmittal of Affidavit Submitted with Response to Request for Additional Information, License Amendment Request (TSCR-144) to Revise and Relocate Pressure and Temperature Limit Curves to a Pressure and Temperature Limits Report - MF66172016-03-11011 March 2016 Resubmittal of Affidavit Submitted with Response to Request for Additional Information, License Amendment Request (TSCR-144) to Revise and Relocate Pressure and Temperature Limit Curves to a Pressure and Temperature Limits Report - MF6617 ML16055A1262016-02-19019 February 2016 Response to Request for Additional Information, License Amendment Request (TSCR-144) to Revise and Relocate Pressure and Temperature Limit Curves to a Pressure and Temperature Limits Report - MF6617 NG-16-0042, Duane Arnold - Response to Request for Additional Information, License Amendment Request (TSCR-144) to Revise and Relocate Pressure and Temperature Limit Curves to a Pressure and Temperature Limits Report - MF66172016-02-19019 February 2016 Duane Arnold - Response to Request for Additional Information, License Amendment Request (TSCR-144) to Revise and Relocate Pressure and Temperature Limit Curves to a Pressure and Temperature Limits Report - MF6617 NG-16-0029, Response to Request for Additional Information, License Amendment Request (TSCR-143) to Extend Containment Leakage Test Frequency2016-01-29029 January 2016 Response to Request for Additional Information, License Amendment Request (TSCR-143) to Extend Containment Leakage Test Frequency NG-15-0361, Six-Month Status Report and Phase 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions..2015-12-22022 December 2015 Six-Month Status Report and Phase 1 and 2 Overall Integrated Plan in Response to June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions.. NG-15-0342, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of: Insights from the Fukushima Dai-ichi Accident2015-12-15015 December 2015 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of: Insights from the Fukushima Dai-ichi Accident NG-15-0248, Submittal of 10 CFR 72.48 Report of Changes, Tests, and Experiments2015-07-16016 July 2015 Submittal of 10 CFR 72.48 Report of Changes, Tests, and Experiments 2022-04-26
[Table view] |
Text
NEx~era December 15, 2015 NG-1 5-0342 10 CFR 50.54(f)
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Duane Arnold Energy Center Docket No. 50-331 Renewed Op. License No. DPR-49 NextEra Energy Duane Arnold, LLC's 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 Fukushima Dai-ichi Accident
References:
- 1) NRC Letter, Request forIn formation Pursuantto Title 10 of the Code of FederalRegulations 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-ichiAccident, dated March 12, 2012 (ML12053A340)
- 2) NRC Letter, Electric Power Research Institute Report 3002000704, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima 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 Number ML13106A331
- 3) NRC Letter, Duane Arnold Energy Center-Screening and Prioritization Results regarding information pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f)
Related to Seismic Hazard Re-evaluations for Recommendation 2.1 of the Near-Term Task Force Reviews of Insights from the Fukushima Dai-ichi accident, dated August 21, 2014, ADAMS Accession Number ML14198A070
- 4) NextEra Energy Duane Arnold, LLC Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10OCFR50.54(f) regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, NG-14-0092, dated March 28, 2014, ADAMS Accession Number ML14092A331 AD/v NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Pal0, IA 52324
Document Control Desk NG-1 5-0342 Page 2 of 3
- 5) NEI Letter, Final Draft of Industry Seismic Evaluation Guidance (EPRI 1025287), dated November 27, 2012, ADAMS Accession Number ML12333A168 and ML12333A170
- 6) NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report 1025287, "Seismic Evaluation Guidance",
dated February 15, 2013, ADAMS Accession Number ML12319A074
- 7) NRC Letter, Screening and Prioritization Results regarding information pursuant to Title 10 of the Code of Federal Regulations 50.54(f) regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Reviews of Insights from the Fukushima Dai-ichi accident, dated May 9, 2014, ADAMS Accession Number ML1411I1A147
- 8) NEI Letter, Request for NRC Endorsement of High Frequency Program: Application Guidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396), dated July 30, 2015, ADAMS Accession Number ML15223A100
- 9) NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report 3002004396, "High Frequency Program:
Application Guidance for Functional Confirmation and Fragility",
dated September 17, 2015, ADAMS Accession Number MLI1521 8A569 On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a Request for Information per 10 CFR 50.54(f) (Reference 1) to all power reactor licensees. The required response section of Enclosure 1 indicated that licensees should provide a Seismic Hazard Evaluation and Screening Report within 1.5 years from the date of the letter for Central and Eastern United States (CEUS) nuclear power plants. By NRC letter dated May 7, 2013 (Reference 2), the date to submit the report was extended to March 31, 2014.
By letter dated August 21, 2014 (Reference 3), the NRC transmitted the results of the screening and prioritization review of the seismic hazards reevaluation submittal for the Duane Arnold Energy Center (Reference 4). In accordance with the screening, prioritization, and implementation details report (SPID) and Augmented Approach guidance (References 2, 5 and 6), the reevaluated seismic hazard is used to determine if additional seismic risk evaluations are warranted for a plant. Specifically, the reevaluated horizontal ground motion response spectrum (GMRS) at the control point elevation is compared to the existing safe shutdown earthquake (SSE) to determine if a plant is required to perform a high frequency confirmation.
As noted in the August 21, 2014 letter (Reference 3), the NRC concludes that consistent with the industry guidance, the Duane Arnold Energy Center should
Document Control Desk NG-1 5-0342 Page 3 of 3 be "screened-out" of performing the seismic risk evaluation, spent fuel pool evaluation, and expedited approach evaluation requested per the 50.54(f) letter (Reference 1). Duane Arnold Energy Center, however, is to perform a limited scope high frequency evaluation for those structures and components susceptible to high frequency accelerations because the re-evaluated ground motion response spectra (GMRS) exceeds the current safe shutdown earthquake above 10 Hz.
Within the May 9, 2014 letter (Reference 7), NRC acknowledged that these limited scope evaluations will require additional development of the assessment process. By Reference 8, the Nuclear Energy Institute (NEI) submitted an Electric Power Research Institute (EPRI) report entitled High Frequency Program:~Application Guidance for FunctionalConfirmation and Fragility Evaluation (EPRI 3002004396) for NRC review and endorsement. NRC endorsement was provided by Reference 9.
The High Frequency Confirmation for Duane Arnold Energy Center shows that the high-frequency spectral accelerations of the control point GMRS above 10Hz are within the limits identified in Section 3.1.1 of Reference 8 (less than or equal to 0.2g); therefore, no additional evaluation is necessary. The enclosure to this letter provides the SSE and GMRS information from Reference 4.
If you have any questions or require additional information, please contact Curt Bock at 319-851-7645.-...
This letter makes no new commitments or changes to existing commitments.
I declare under penalty of perjury that the foregoing isr true and correct.
Executed on December 15, 2015 f~ homas Vehec
-Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC
Enclosure:
GMRS and SSE Supporting Information cc: Regional Administrator, USNRC, Region III Resident Inspector, USNRC, Duane Arnold Energy Center Project Manager, USNRC, Duane Arnold Energy Center
Enclosure to NG-15-0342 GMRS and SSE Supportingi Information For the Duane Arnold Enerqy Center 2 pages follow
Enclosure to NG-15-0324 Page 1 of 2 Table 1: SSE and GMRS Data SSE GMRS Frequency (g) (g) 100.00 0.120 0.0881 90.00 0.120 0.0885 80.00 0.120 0.0895 70.00 0.120 0.0917 60.00 0.120 0.0978 50.00 0.120 0.1140 40.00 0.120 0.1370 35.00 0.120 0.1470 30.00 0.120 0.1590 25.00 0.140 0.1690 20.00 0.174 0.1740 15.00 0.200 0.1790 12.50 0.210 0.1760 10.00 0.224 0.1680 9.00 0.230 0.1600 8.00 0.234 0.1520 7.00 0.238 0.1440 6.00 0.256 0..1350 5.00 0.280 0.1210 4700 0.306 0.1030 3.50 0.318 0.0929 3.00 0.320 0.0806 2.50 0.318 0.0684 2.00 0.292 0.0666 1.50 0.180 0.0594 1.25 0.124 0.0581 1.00 0.128 0.0536 0.90 0.116 0.0514 0.80 0.100 0.0495 0.70 0.074 0.0476 0.60 0.070 0.0457 0.50 0.054 0.0435 0.40 0.0348 0.35 0.0304 0.30 0.0261 0.25 0.0217 0.20 0.0174 0.15 0.0130 0.125 0.0109 0.10 ____0.00869
Enclosure to NG-15-0342 Page 2 of 2 Figure 1: GMRS to SSE Comparison 0.350 - - - --- F--:-- ------ ,-----------.... ...---------- I t / *~~~SSE .. .. ..
' I ! L~~ - GMRS , !,
0.250 . ... _ ___ ___ __
Ii Ii
~ 1.00100.0
.. ..... 10.00.
Frequency (Hz.)
NEx~era December 15, 2015 NG-1 5-0342 10 CFR 50.54(f)
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Duane Arnold Energy Center Docket No. 50-331 Renewed Op. License No. DPR-49 NextEra Energy Duane Arnold, LLC's 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 Fukushima Dai-ichi Accident
References:
- 1) NRC Letter, Request forIn formation Pursuantto Title 10 of the Code of FederalRegulations 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-ichiAccident, dated March 12, 2012 (ML12053A340)
- 2) NRC Letter, Electric Power Research Institute Report 3002000704, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima 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 Number ML13106A331
- 3) NRC Letter, Duane Arnold Energy Center-Screening and Prioritization Results regarding information pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f)
Related to Seismic Hazard Re-evaluations for Recommendation 2.1 of the Near-Term Task Force Reviews of Insights from the Fukushima Dai-ichi accident, dated August 21, 2014, ADAMS Accession Number ML14198A070
- 4) NextEra Energy Duane Arnold, LLC Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10OCFR50.54(f) regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, NG-14-0092, dated March 28, 2014, ADAMS Accession Number ML14092A331 AD/v NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Pal0, IA 52324
Document Control Desk NG-1 5-0342 Page 2 of 3
- 5) NEI Letter, Final Draft of Industry Seismic Evaluation Guidance (EPRI 1025287), dated November 27, 2012, ADAMS Accession Number ML12333A168 and ML12333A170
- 6) NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report 1025287, "Seismic Evaluation Guidance",
dated February 15, 2013, ADAMS Accession Number ML12319A074
- 7) NRC Letter, Screening and Prioritization Results regarding information pursuant to Title 10 of the Code of Federal Regulations 50.54(f) regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Reviews of Insights from the Fukushima Dai-ichi accident, dated May 9, 2014, ADAMS Accession Number ML1411I1A147
- 8) NEI Letter, Request for NRC Endorsement of High Frequency Program: Application Guidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396), dated July 30, 2015, ADAMS Accession Number ML15223A100
- 9) NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report 3002004396, "High Frequency Program:
Application Guidance for Functional Confirmation and Fragility",
dated September 17, 2015, ADAMS Accession Number MLI1521 8A569 On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a Request for Information per 10 CFR 50.54(f) (Reference 1) to all power reactor licensees. The required response section of Enclosure 1 indicated that licensees should provide a Seismic Hazard Evaluation and Screening Report within 1.5 years from the date of the letter for Central and Eastern United States (CEUS) nuclear power plants. By NRC letter dated May 7, 2013 (Reference 2), the date to submit the report was extended to March 31, 2014.
By letter dated August 21, 2014 (Reference 3), the NRC transmitted the results of the screening and prioritization review of the seismic hazards reevaluation submittal for the Duane Arnold Energy Center (Reference 4). In accordance with the screening, prioritization, and implementation details report (SPID) and Augmented Approach guidance (References 2, 5 and 6), the reevaluated seismic hazard is used to determine if additional seismic risk evaluations are warranted for a plant. Specifically, the reevaluated horizontal ground motion response spectrum (GMRS) at the control point elevation is compared to the existing safe shutdown earthquake (SSE) to determine if a plant is required to perform a high frequency confirmation.
As noted in the August 21, 2014 letter (Reference 3), the NRC concludes that consistent with the industry guidance, the Duane Arnold Energy Center should
Document Control Desk NG-1 5-0342 Page 3 of 3 be "screened-out" of performing the seismic risk evaluation, spent fuel pool evaluation, and expedited approach evaluation requested per the 50.54(f) letter (Reference 1). Duane Arnold Energy Center, however, is to perform a limited scope high frequency evaluation for those structures and components susceptible to high frequency accelerations because the re-evaluated ground motion response spectra (GMRS) exceeds the current safe shutdown earthquake above 10 Hz.
Within the May 9, 2014 letter (Reference 7), NRC acknowledged that these limited scope evaluations will require additional development of the assessment process. By Reference 8, the Nuclear Energy Institute (NEI) submitted an Electric Power Research Institute (EPRI) report entitled High Frequency Program:~Application Guidance for FunctionalConfirmation and Fragility Evaluation (EPRI 3002004396) for NRC review and endorsement. NRC endorsement was provided by Reference 9.
The High Frequency Confirmation for Duane Arnold Energy Center shows that the high-frequency spectral accelerations of the control point GMRS above 10Hz are within the limits identified in Section 3.1.1 of Reference 8 (less than or equal to 0.2g); therefore, no additional evaluation is necessary. The enclosure to this letter provides the SSE and GMRS information from Reference 4.
If you have any questions or require additional information, please contact Curt Bock at 319-851-7645.-...
This letter makes no new commitments or changes to existing commitments.
I declare under penalty of perjury that the foregoing isr true and correct.
Executed on December 15, 2015 f~ homas Vehec
-Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC
Enclosure:
GMRS and SSE Supporting Information cc: Regional Administrator, USNRC, Region III Resident Inspector, USNRC, Duane Arnold Energy Center Project Manager, USNRC, Duane Arnold Energy Center
Enclosure to NG-15-0342 GMRS and SSE Supportingi Information For the Duane Arnold Enerqy Center 2 pages follow
Enclosure to NG-15-0324 Page 1 of 2 Table 1: SSE and GMRS Data SSE GMRS Frequency (g) (g) 100.00 0.120 0.0881 90.00 0.120 0.0885 80.00 0.120 0.0895 70.00 0.120 0.0917 60.00 0.120 0.0978 50.00 0.120 0.1140 40.00 0.120 0.1370 35.00 0.120 0.1470 30.00 0.120 0.1590 25.00 0.140 0.1690 20.00 0.174 0.1740 15.00 0.200 0.1790 12.50 0.210 0.1760 10.00 0.224 0.1680 9.00 0.230 0.1600 8.00 0.234 0.1520 7.00 0.238 0.1440 6.00 0.256 0..1350 5.00 0.280 0.1210 4700 0.306 0.1030 3.50 0.318 0.0929 3.00 0.320 0.0806 2.50 0.318 0.0684 2.00 0.292 0.0666 1.50 0.180 0.0594 1.25 0.124 0.0581 1.00 0.128 0.0536 0.90 0.116 0.0514 0.80 0.100 0.0495 0.70 0.074 0.0476 0.60 0.070 0.0457 0.50 0.054 0.0435 0.40 0.0348 0.35 0.0304 0.30 0.0261 0.25 0.0217 0.20 0.0174 0.15 0.0130 0.125 0.0109 0.10 ____0.00869
Enclosure to NG-15-0342 Page 2 of 2 Figure 1: GMRS to SSE Comparison 0.350 - - - --- F--:-- ------ ,-----------.... ...---------- I t / *~~~SSE .. .. ..
' I ! L~~ - GMRS , !,
0.250 . ... _ ___ ___ __
Ii Ii
~ 1.00100.0
.. ..... 10.00.
Frequency (Hz.)