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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
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August 12, 2016 NG-16-0153 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Duane Arnold Energy Center Docket No. 50-331 Facility Operating License No DPR-49 Response to Request for Information Supporting Flooding Hazards Reevaluation Report Audit
References:
(1) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)
Regarding Recommendation 2.1, Flooding, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident: Flood Hazard Reevaluation Report, dated March 10, 2014(ML14072A020)
(2) Nuclear Regulatory Commission Plan for the Audit of NextEra Energy Duane Arnold, LLC's Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1 - Flooding for Duane Arnold Energy Center, dated June 17, 2015(ML15160A715)
By letter dated March 10, 2014, NextEra Energy Duane Arnold, LLC (Duane Arnold) submitted a Flooding Hazards Reevaluation Report (FHRR) (Reference 1) in response to Title 10 of the Code of Federal Regulations 50.54(f) Request for Information, relating to Recommendation 2.1.
By letter dated June 17, 2015 (Reference 2), the NRC notified Duane Arnold of upcoming audit activities related to review of the FHRR submittal. During teleGonferences conducted during the audit, the NRC Staff requested clarifications related the Duane Arnold FHRR submittal.
Enclosure 1 provides the requested information.
This letter contains no new regulatory commitments. If you have any questions or require d~on, please contact Mike Davis at 319-851-7032.
T. A. Vehec Vice President, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC
. Enclosures cc: Regional Administrator, USNRC, Region Ill Resident Inspector, USNRC, Duane Arnold Energy Center Project Manager, USNRC, Duane Arnold Energy Center NextEra Energy Duane Arnold, LLC, 3277 DAEC Road, Palo, IA 52324
Enclosure 1 to NG-16-0153 NEXTERA ENERGY DUANE ARNOLD, LLC DUANE ARNOLD ENERGY CENTER RESPONSE TO REQUEST FOR INFORMATION SUPPORTING FLOODING HAZARDS REEVALUATION REPORT AUDIT 4 Pages Follow
Clarification Request Provide Local Intense Precipitation (LIP) maximum water surface elevations.
Response
During the audit discussions, NextEra provided flooding elevations associated with a LIP event.
- In the FHRR, only the flooding depths at the four critical door locations for the Turbine Building were given: The flood elevations (the ground elevation plus the depths) as a result of LIP-cau"sed flooding at the four critical doors are provided in Table 1.
Clarification Request In developing the probable maximum precipitation (PMP) used to estimate the probable maximum flood (PMF) at the Duane Arnold site, the analysis selected the complete drainage area of the Cedar River watershed at the point where the Cedar River joins the Iowa River. The*
- FHRR reported thatthe area of the watershed upstream of the Duane Arnold site is 6,250 mi 2 ,
and the total drainage area at the mouth of the Cedar River is 7,824 mi 2 . Because the area upstream of the Duane Arnold site is about 20 percent smaller than the total watershed area, there could be a significant increase in the PMP if the smaller area is used with depth-area-duration curves to estimate basin average precipitation.
Further, the requisite wind-wave calculations associated with the revised PMF elevation resulting from the use of the 6,250 mi 2 drainage basin area must be provided.
R~sponse
- The PMP is developed from envelopment curves (i.e., depth-area-duration relationships) specific to the DAEC location. Updates were made to the depth-area envelopment curves to be closer to actual data through further analytical refinements. These refined PMP envelopment values are provided in Table 2. The smaller drainage area (-6,250 mi 2 ) was evaluated with a refined PMP with calibrated/defined channel roughness and infiltration losses as presented in the DAEC FHRR.
In the FHRR analysis for a total drainage area of 7,824 mi 2 , the peak water surface elevation (WSEL) at DAEC was +763.5 ft-NAVD88. For the smaller drainage area evaluation described above, the peak WSEL increased by 1.3 ft to +764.8 ft-NAVD88.
Due to the increase-in peak PMF WSEL ~t DAEC, wind-wave activity was recomputed using the same methodology as detailed in the DAEC FHRR.
Wave runup was evaluated for the spectrum of waves that can potentially impact DAEC coincident with the PMF event. Wave action and calculations were performed based on methodologies and equations from the United States Army Corps of Engineers (USAGE)
. (USAGE, 1984; USAGE, 2008). The wind-generating wave mechanism considered the 2-year period wind speed along the critical fetch length, wind setup, wave setup and the potential for
- wave breaking, wave refraction, and wave shoaling were examined from topography and bathymetry near DAEG. Cross sections were cut using ArcGIS to show detailed topographic layouts of the ground surface across the fetch length to the DAEC power block. Other cases of
- wind and wave activity and associated wave runup were not examined, as they are less critical cases. Wave runup was calculated using parametric equations.
Page 1 of 4
The critical scenario for wave run up may occur from waves propagating from the east, west, south, southwest, southeast or northeast over the critical systems, structures, and components (SSCs) at the DAEC power block. These directions would have the most unobstructed route approaching the critical SSCs at DAEC during the PMF event and therefore were analyzed to determine the critical scenario for wave runup.
Fetch is defined as a distance over which the wind speed and direction are reasonably constant.
Fetches fall into two categories, open-water fetches, where wave growth is limited only by the *.
- incident meteorological conditions, and restricted fetches, where wave growth is)imited by .a confined geometry such as that of a lake, river, bay, or reservoir. DAEC is subject to a restricted
- fetch. The restricted fetch methodology applies the concept of wave development in off-wind directions and considers the shape of the basin.
The.results of the wind-wave activity recomputation are summarized in Table 3 for each cardinal and intercardinal side of the site. The bounding total wave activity (i.e., combined wind setup, wave setup and wave runup), which occurs on the south side of DAEC, was 2.6 ft in the DAEC FHRR. For* the revised PMF peak WSEL, the bounding total wave activity remains 2.6 ft above the peak PMF still water elevation. Figure 1 shows the controlling southerly fetch of 11 ,200 feet crosses groups of mature standing trees multiple times before it terminates at a stand of mature trees adjacent to an elevated highway. At this location, the peak PMF water surface is approximately 20 feet*above the ground surface elevation. Hence, the tops of larger vegetation would be expected to be at or above the peak PMF water level. However, it was conservatively assumed that a sustained wind would persist along that entire fetch uninhibited; in actuality, the clusters of mature trees and other vegetation within the fetch length would be expected to shorten the effective fetch length and attenuate wave growth/propagation. Smaller, attenuated waves would be expected to generate lower vertical wave runup heights at the site. Accordingly, the bounding total vertical water elevation is +767.4 ft-NAVD88 (767.8 ft-MSL) on the south side of DAEC. Other sides of the plant experience slightly lower total water elevations primarily because of shorter fetch lengths (Table 3). As noted in the current UFSAR Section 3.4, openings in safety-related buildings are protected from wave runup to an elevation of 770.5 ft-MSL on the northerly side, 773.7 ft-MSL on the southerly side and 769 ft-MSL on all other sides of safety-related buildings. There is available physical margin between the bounding total vertical elevations and the COB protection elevations.
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Table 1 - FHRR LIP Maximum Water Depths and Maximum Water Surface Elevations FL0-2D Cell Maximum Water Maximum Water Surface Door ID Elevation (ft-MSL) Depth (ft) Elevation (ft-MSL) 124 757 .5 0.5 758 .0 136 757.4 0.8 758 .2 137 757.4 0 .8 758 .2 154 757.4 0.6 758 .0 Table 2 - FHRR Site-Specific PMP Envelopment Values Licensee's D-A- D Values (from Excel files)
Duration (hours) 6 12 24 48 n 10 7.1 9.6 13.6 15.5 15.6 100 6.9 9.3 13.4 14.8 14.9 200 6.7 9.0 13.1 14.4 14.5 500 6.4 8.5 12.4 13.8 13.9 1000 6.1 8.1 11.7 13.2 13.3 2000 5.7 7.6 11.0 12.5 12.6 5000 5.2 6.9 9.9 11.5 11 .6 10000 4.5 6.1 8.7 10.5 10.6 20000 3.6 5.3 7.4 9.3 9.4 Table 3 - Wind Wave Results for Smaller Drainage Basin Area PMF Sibul Total Total Affected Wave Wave Wind Stillwater Fetch Wind Vertical Vertical Side of Setup Runup Direction Elevation (ft) Setup Height Height DAEC Site (ft) (ft)
(ft-NAVD88) (ft) (ft-NAVD88) (ft-MSL)
Northerly South +764.8 11,200 0.135 0.289 2.17 +767.4 +767.8 Northeasterly Southwest +764.8 10,000 0.122 0.276 2.06 +767.3 +767.7 Easterly West +764.8 1,600 0.031 0.117 0.85 +765.8 +766.2 Southwesterly Northeast +764.8 6,400 0.083 0.228 1.69 +766.8 +767.2 Westerly East +764.8 3,600 0.053 0.174 1.28 +766.3 +766.7 Northwesterly Southeast +764.8 3,600 0.053 0.174 1.28 +766.3 +766.7 1 1 1 1 1 Southeasterly Northwest +764.8 N/A N/A N/A N/A N/A N/A 1 Southerly North +764.8 N/A 2 N/A 2 N/A 2 N/A 2 N/A2 N/A 2 Note: Wind speed for all directions =40 mph.
1 The elevation increases above the PMF northwest of the site, therefore , it is unlikely that a critical wave run-up scenario would occur with the wind directed southeast.
2 There are no open ings to safety-related structures directly north of the power block, therefore ,
it is unlikely that a critical wave run-up scenario would occur when the wind is directed south.
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Legend PMF Inundated Area
- OTE: Manning's n polygon shapefile from the FHRR calculations containing mature tree gro vth.
Figure 1 - Dense Vegetation and Other Obstacle Locations Page 4 of 4