Letter Sequence Response to RAI |
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EPID:L-2020-LLR-0161, Submittal of Revised Relief Request RR-A39 for the Fourth Ten-Year Inservice Inspection Interval (Approved, Closed) |
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Similar Documents at Fermi |
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Category:Letter type:NRC
MONTHYEARNRC-24-0007, Report of Changes to Quality Assurance Program for Radioactive Material Packages2024-01-12012 January 2024 Report of Changes to Quality Assurance Program for Radioactive Material Packages NRC-24-0002, Clarification for Request for Additional Information Responses for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.122024-01-12012 January 2024 Clarification for Request for Additional Information Responses for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 NRC-23-0079, Transmittal of Revision 1 of the Core Operating Limits Report for Cycle 222023-12-14014 December 2023 Transmittal of Revision 1 of the Core Operating Limits Report for Cycle 22 NRC-23-0077, Submittal of Revision 50 to the Fermi 2 Radiological Emergency Response Preparedness Plan2023-12-0404 December 2023 Submittal of Revision 50 to the Fermi 2 Radiological Emergency Response Preparedness Plan NRC-23-0073, Guarantee of Payment of Deferred Premiums2023-11-29029 November 2023 Guarantee of Payment of Deferred Premiums NRC-23-0071, Response to Request for Additional Information (RAI) for Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating2023-10-13013 October 2023 Response to Request for Additional Information (RAI) for Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating NRC-23-0062, Response to Request for Additional Information for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.122023-10-12012 October 2023 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 NRC-23-0068, Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating2023-09-28028 September 2023 Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating NRC-23-0064, Additional Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-09-11011 September 2023 Additional Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0057, Independent Spent Fuel Storage Installation Cask Registration2023-08-31031 August 2023 Independent Spent Fuel Storage Installation Cask Registration NRC-23-0054, Enrico Fermi Atomic Power Plant, Unit 1, Annual Report for Period Ending June 30 20232023-08-31031 August 2023 Enrico Fermi Atomic Power Plant, Unit 1, Annual Report for Period Ending June 30 2023 NRC-23-0056, Inservice Testing (IST) Program for the Fourth 10-Year Inspection Interval2023-08-31031 August 2023 Inservice Testing (IST) Program for the Fourth 10-Year Inspection Interval NRC-23-0061, Clarification for NRC-23-0059, Response to Request for Additional Information for Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water..2023-08-30030 August 2023 Clarification for NRC-23-0059, Response to Request for Additional Information for Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water.. NRC-23-0059, Response to Request for Additional Information Exigent License Amendment Request for Technical Specification 3.7.2,Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-08-25025 August 2023 Response to Request for Additional Information Exigent License Amendment Request for Technical Specification 3.7.2,Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0060, Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-08-25025 August 2023 Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0053, Independent Spent Fuel Storage Installation Cask Registration2023-08-23023 August 2023 Independent Spent Fuel Storage Installation Cask Registration NRC-23-0050, Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-08-10010 August 2023 Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0048, Independent Spent Fuel Storage Installation Cask Registration2023-08-0101 August 2023 Independent Spent Fuel Storage Installation Cask Registration NRC-23-0049, Request for Enforcement Discretion for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-07-24024 July 2023 Request for Enforcement Discretion for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0043, Independent Spent Fuel Storage Installation, Cask Registration2023-06-27027 June 2023 Independent Spent Fuel Storage Installation, Cask Registration NRC-23-0020, License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance2023-06-13013 June 2023 License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance NRC-23-0039, Request for Enforcement Discretion for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-06-0606 June 2023 Request for Enforcement Discretion for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0030, Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval2023-06-0505 June 2023 Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval NRC-23-0029, Snubber Program for the Fourth 10-Year Testing Interval2023-06-0505 June 2023 Snubber Program for the Fourth 10-Year Testing Interval NRC-23-0037, 56542-EN 56542 - Fermi2023-05-26026 May 2023 56542-EN 56542 - Fermi NRC-23-0031, Response to NRC Request from Audit of License Amendment Request to Revise Technical Specification 3.8.1, AC Sources -Operating,' Emergency Diesel Generator Voltage and Frequency Surveillance Requirements2023-05-16016 May 2023 Response to NRC Request from Audit of License Amendment Request to Revise Technical Specification 3.8.1, AC Sources -Operating,' Emergency Diesel Generator Voltage and Frequency Surveillance Requirements NRC-23-0002, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.122023-05-0505 May 2023 License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 NRC-23-0010, License Amendment Request to Correct Non-Conservative Technical Specification 3.4.5, RCS Pressure Isolation Valve (PIV) Leakage2023-05-0505 May 2023 License Amendment Request to Correct Non-Conservative Technical Specification 3.4.5, RCS Pressure Isolation Valve (PIV) Leakage NRC-23-0017, Annual Radioactive Effluent Release Report and Radiological Environmental Operating Report2023-04-28028 April 2023 Annual Radioactive Effluent Release Report and Radiological Environmental Operating Report NRC-23-0025, Submittal of 2022 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2023-04-28028 April 2023 Submittal of 2022 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-23-0018, Annual Non-Radiological Environmental Operating Report2023-04-26026 April 2023 Annual Non-Radiological Environmental Operating Report NRC-23-0024, Levels and Sources of Property Insurance Coverage2023-04-0303 April 2023 Levels and Sources of Property Insurance Coverage NRC-23-0021, ISFSI, Decommissioning Funding Plan Update2023-03-30030 March 2023 ISFSI, Decommissioning Funding Plan Update NRC-23-0016, Decommissioning Funding Status Report2023-03-30030 March 2023 Decommissioning Funding Status Report NRC-23-0015, Decommissioning Funding Status Report for Fermi 12023-03-30030 March 2023 Decommissioning Funding Status Report for Fermi 1 NRC-23-0011, License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis2023-03-0707 March 2023 License Renewal Commitment 7c: Transmittal of Core Plate Hold-Down Bolt Analysis NRC-22-0026, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Emergency Diesel Generator Voltage and Frequency Surveillance Requirements2022-12-16016 December 2022 License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Emergency Diesel Generator Voltage and Frequency Surveillance Requirements NRC-22-0051, DTE Electric Company - Guarantee of Payment of Deferred Premiums2022-11-29029 November 2022 DTE Electric Company - Guarantee of Payment of Deferred Premiums NRC-22-0052, Replacement Files for Submittal of Revision 24 to the Fermi 2 Updated Final Safety Analysis Report (UFSAR) Through EIE on November 9, 20222022-11-17017 November 2022 Replacement Files for Submittal of Revision 24 to the Fermi 2 Updated Final Safety Analysis Report (UFSAR) Through EIE on November 9, 2022 NRC-22-0046, Submittal of Biennial Review of the Fermi 1 Safety Analysis Report2022-11-14014 November 2022 Submittal of Biennial Review of the Fermi 1 Safety Analysis Report NRC-22-0041, Evacuation Time Estimate Report2022-10-0505 October 2022 Evacuation Time Estimate Report NRC-22-0033, Enrico Fermi Atomic Power Plant, Unit 1 - Annual Report for Period Ending June 30, 20222022-08-29029 August 2022 Enrico Fermi Atomic Power Plant, Unit 1 - Annual Report for Period Ending June 30, 2022 NRC-22-0030, Inservice Inspection Summary Report2022-08-10010 August 2022 Inservice Inspection Summary Report NRC-22-0023, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2022-08-0404 August 2022 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements NRC-22-0022, Annual Non-Radiological Environmental Operating Report2022-04-29029 April 2022 Annual Non-Radiological Environmental Operating Report NRC-22-0021, Annual Radioactive Effluent Release Report and Radiological Environmental Operating Report2022-04-29029 April 2022 Annual Radioactive Effluent Release Report and Radiological Environmental Operating Report NRC-22-0020, Enrico Fermi Atomic Power Plant, Unit No. 1 & Fermi 2 Power Plant - 10 CFR 20.2206 Report of Individual Monitoring2022-04-28028 April 2022 Enrico Fermi Atomic Power Plant, Unit No. 1 & Fermi 2 Power Plant - 10 CFR 20.2206 Report of Individual Monitoring NRC-22-0003, Submittal of 2021 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2022-04-26026 April 2022 Submittal of 2021 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-22-0019, Submittal of the National Pollutant Discharge Elimination System Permit Application for Reissuance2022-04-0404 April 2022 Submittal of the National Pollutant Discharge Elimination System Permit Application for Reissuance NRC-22-0011, Enrico Fermi Atomic Power Plant, Unit No. 1 - Decommissioning Funding Status Report2022-03-31031 March 2022 Enrico Fermi Atomic Power Plant, Unit No. 1 - Decommissioning Funding Status Report 2024-01-12
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARNRC-24-0002, Clarification for Request for Additional Information Responses for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.122024-01-12012 January 2024 Clarification for Request for Additional Information Responses for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 NRC-23-0071, Response to Request for Additional Information (RAI) for Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating2023-10-13013 October 2023 Response to Request for Additional Information (RAI) for Exigent License Amendment Request for Revision of Technical Specification (TS) 3.8.1 AC Sources - Operating NRC-23-0062, Response to Request for Additional Information for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.122023-10-12012 October 2023 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 NRC-23-0061, Clarification for NRC-23-0059, Response to Request for Additional Information for Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water..2023-08-30030 August 2023 Clarification for NRC-23-0059, Response to Request for Additional Information for Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water.. NRC-23-0059, Response to Request for Additional Information Exigent License Amendment Request for Technical Specification 3.7.2,Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)2023-08-25025 August 2023 Response to Request for Additional Information Exigent License Amendment Request for Technical Specification 3.7.2,Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS) NRC-23-0031, Response to NRC Request from Audit of License Amendment Request to Revise Technical Specification 3.8.1, AC Sources -Operating,' Emergency Diesel Generator Voltage and Frequency Surveillance Requirements2023-05-16016 May 2023 Response to NRC Request from Audit of License Amendment Request to Revise Technical Specification 3.8.1, AC Sources -Operating,' Emergency Diesel Generator Voltage and Frequency Surveillance Requirements NRC-21-0045, Response to Request for Additional Information Regarding License Amendment Request to Revise the Fermi 2 Technical Specifications2021-08-17017 August 2021 Response to Request for Additional Information Regarding License Amendment Request to Revise the Fermi 2 Technical Specifications NRC-21-0032, Response to Request for Additional Information Regarding Revised Relief Request RR-A39 for the Fourth Ten-Year Inservice Inspection Interval2021-07-0101 July 2021 Response to Request for Additional Information Regarding Revised Relief Request RR-A39 for the Fourth Ten-Year Inservice Inspection Interval NRC-21-0007, Response to Request for Additional Information Regarding Revised Relief Request RR-A39 for the Fourth Ten-Year Inservice Inspection Interval2021-05-27027 May 2021 Response to Request for Additional Information Regarding Revised Relief Request RR-A39 for the Fourth Ten-Year Inservice Inspection Interval NRC-20-0077, Response to Request for Additional Information Regarding Exemption from the Annual Force on Force Training Requirements of 10 CFR 73, Appendix B, Section VI, Due to the COVID-19 Public Health Emergency2020-12-0303 December 2020 Response to Request for Additional Information Regarding Exemption from the Annual Force on Force Training Requirements of 10 CFR 73, Appendix B, Section VI, Due to the COVID-19 Public Health Emergency NRC-20-0057, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2020-09-11011 September 2020 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle NRC-20-0046, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Utilize Neutron Absorbing Inserts in Criticality Safety Analysis for Fermi 2 Spent Fuel Storage Racks2020-07-30030 July 2020 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Utilize Neutron Absorbing Inserts in Criticality Safety Analysis for Fermi 2 Spent Fuel Storage Racks NRC-19-0084, Response to Request for Additional Information Regarding Inservice Testing Program Relief Request VRR-006 for the Fourth 10-Year Interval2019-12-0606 December 2019 Response to Request for Additional Information Regarding Inservice Testing Program Relief Request VRR-006 for the Fourth 10-Year Interval NRC-19-0039, Response to NRC Request for Additional Information for License Amendment Request to Revise Technical Specification 3.3.5.3, Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation2019-06-18018 June 2019 Response to NRC Request for Additional Information for License Amendment Request to Revise Technical Specification 3.3.5.3, Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation NRC-19-0045, Response to Request for Additional Information Regarding Snubber Program Relief Request RR-S1 for the Fourth 10-Year Interval2019-06-12012 June 2019 Response to Request for Additional Information Regarding Snubber Program Relief Request RR-S1 for the Fourth 10-Year Interval NRC-19-0042, Responses to Requests for Additional Information Regarding Relief Requests for the Inservice Inspection Program Fourth Ten-year Interval2019-06-11011 June 2019 Responses to Requests for Additional Information Regarding Relief Requests for the Inservice Inspection Program Fourth Ten-year Interval NRC-18-0045, Response to NRC Requests for Additional Information for License Amendment Request to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-08-0707 August 2018 Response to NRC Requests for Additional Information for License Amendment Request to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control NRC-18-0040, Supplemental Information in Response to NRC Request for Additional Information for License Amendment Request to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-06-27027 June 2018 Supplemental Information in Response to NRC Request for Additional Information for License Amendment Request to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control NRC-18-0032, Response to NRC Request for Additional Information for License Amendment Request to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-05-17017 May 2018 Response to NRC Request for Additional Information for License Amendment Request to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control NRC-18-0019, Response to NRC Request for Additional Information for License Amendment Request to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2018-04-0404 April 2018 Response to NRC Request for Additional Information for License Amendment Request to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. NRC-18-0015, Response to Request for Additional Information (Set 1) Regarding License Amendment Request to Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Reactor Trip and Primary Containment Isolation System Group 1.2018-02-27027 February 2018 Response to Request for Additional Information (Set 1) Regarding License Amendment Request to Revise Technical Specifications to Eliminate Main Steam Line Radiation Monitor Reactor Trip and Primary Containment Isolation System Group 1. NRC-18-0014, Response to Request for Additional Information Regarding Relief Request No. RR-A37, Revision 1, for the Inservice Inspection Program Third 10-Year Interval2018-02-0606 February 2018 Response to Request for Additional Information Regarding Relief Request No. RR-A37, Revision 1, for the Inservice Inspection Program Third 10-Year Interval NRC-18-0001, DTE Energy Company - Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification Section 3.7.22018-01-0808 January 2018 DTE Energy Company - Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification Section 3.7.2 NRC-17-0036, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications for Emergency Core Cooling System Instrumentation and Reactor Core Isolation Cooling System Instrumentation2017-03-30030 March 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications for Emergency Core Cooling System Instrumentation and Reactor Core Isolation Cooling System Instrumentation NRC-16-0067, Spent Fuel Pool Evaluation Supplemental 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 Accident2016-12-0909 December 2016 Spent Fuel Pool Evaluation Supplemental 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 NRC-16-0049, Response to Request for Additional Information Regarding License Amendment Request to Revise Integrated Leak Rate Test - Type a and Type C Test Intervals2016-08-11011 August 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Integrated Leak Rate Test - Type a and Type C Test Intervals NRC-16-0042, Response to NRC Request for Additional Information Regarding Environmental Review of the License Renewal Application, Severe Accident Mitigation Alternatives Sensitivity Analysis2016-07-19019 July 2016 Response to NRC Request for Additional Information Regarding Environmental Review of the License Renewal Application, Severe Accident Mitigation Alternatives Sensitivity Analysis NRC-16-0038, Response to Request for Additional Information Regarding Revised Relief Request PRR-007 for the Inservice Testing Program Third 10-Year Interval2016-06-23023 June 2016 Response to Request for Additional Information Regarding Revised Relief Request PRR-007 for the Inservice Testing Program Third 10-Year Interval NRC-16-0021, Supplemental Response to NRC Request for Additional Information for the Review of the Fermi 2 License Renewal Application - Set 17 RAI 4.3.3-12016-03-10010 March 2016 Supplemental Response to NRC Request for Additional Information for the Review of the Fermi 2 License Renewal Application - Set 17 RAI 4.3.3-1 NRC-16-0003, Response to NRC Request for Additional Information for the Review of the License Renewal Application - Set 382016-02-0101 February 2016 Response to NRC Request for Additional Information for the Review of the License Renewal Application - Set 38 NRC-16-0004, Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) and Response to Request for Additional Information2016-01-20020 January 2016 Compliance with March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) and Response to Request for Additional Information NRC-15-0089, Response to NRC Request for Additional Information for the Review of License Renewal Application - Set 372015-09-24024 September 2015 Response to NRC Request for Additional Information for the Review of License Renewal Application - Set 37 NRC-15-0083, Supplemental Response to NRC Request for Additional Information for the Review of the License Renewal Application - Set 332015-08-20020 August 2015 Supplemental Response to NRC Request for Additional Information for the Review of the License Renewal Application - Set 33 NRC-15-0077, Response to Request for Additional Information (RAI) Regarding the License Amendment Request to Revise the Emergency Action Level (EAL) Scheme for the Emergency Plan2015-07-28028 July 2015 Response to Request for Additional Information (RAI) Regarding the License Amendment Request to Revise the Emergency Action Level (EAL) Scheme for the Emergency Plan NRC-15-0066, Response to NRC Request for Additional Information for the Review of the Fermi 2 License Renewal Application - Set 332015-07-0606 July 2015 Response to NRC Request for Additional Information for the Review of the Fermi 2 License Renewal Application - Set 33 2024-01-12
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Peter Dietrich Senior Vice President and Chief Nuclear Officer DTE Electric Company 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734.586.4153 Fax: 734.586.1431 Email: peter.dietrich@dteenergy.com 10 CFR 50.55a July 1, 2021 NRC-21-0032 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Fermi 2 Power Plant NRC Docket No. 50-341 NRC License No. NPF-43
Subject:
Response to Request for Additional Information Regarding Revised Relief Request RR-A39 for the Fourth Ten-Year Inservice Inspection Interval
References:
- 1) DTE Letter NRC-20-0054, Submittal of Revised Relief Request RR-A39 for the Fourth Ten-year Interval, dated December 30, 2020 (ML20365A043)
- 2) NRC E-mail Capture, Fermi 2 - Request for Additional Information for Revised Relief Request RR A-39 (EPID L-2020-LLR-0161), dated May 4, 2021 (ML21126A053)
- 3) DTE Letter NRC-21-0007, Response to Request for Additional Information Regarding Revised Relief Request RR-A39 for the Fourth Ten-year Interval, dated May 27, 2021 (ML21147A495)
- 4) Notice of Meeting between the NRC staff and the Electric Power Research Institute, dated April 20, 2021 (ML21111A087)
In Reference 1, DTE submitted a revision to NRC-approved relief request RR-A39 regarding the use of Boiling Water Reactor Vessel Internals Project guidelines in lieu of ASME Code requirements. In the Reference 2 email from Mr. Surinder Arora to Ms. Margaret Offerle dated May 4, 2021, the NRC sent DTE a Request for Additional Information (RAI) regarding the revised relief request. The response to the first question, RAI-1, was previously provided in Reference 3. The response to the second question, RAI-2, is enclosed. The response incorporates relevant information from the May 27, 2021 meeting identified in Reference 4.
No new commitments are being made in this submittal.
USNRC NRC-21-0032 Page 2 Should you have any questions or require additional information, please contact Mr. Ertman L.
Bennett III, Manager - Nuclear Licensing, at (734) 586-4273.
Sincerely, Peter Dietrich Senior Vice President and Chief Nuclear Officer
Enclosure:
- 1) Response to Request for Additional Information cc: NRC Project Manager NRC Resident Office Regional Administrator, Region III
Enclosure 1 to NRC-21-0032 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 Response to Request for Additional Information to NRC-21-0032 Page 1 Response to Request for Additional Information By letter dated December 30, 2020 (Agencywide Documents and Access Management System (ADAMS) Accession No. ML20365A043), DTE Electric Company (DTE or the licensee) submitted revised relief request RR-A39 for the Fourth Ten-Year Inservice Inspection Interval at the Enrico Fermi Nuclear Generating Station, Unit 2 (Fermi 2). DTE requested authorization to utilize BWRVIP Guidelines in lieu of the applicable Section XI requirements for Examination Categories B-N-1 and B-N-2. The revised submittal proposes the use of BWRVIP-25-R1-A, BWRVIP-41-R4-A, and BWRVIP-48-R1 in lieu of the previous revisions of these documents as approved in the original submittal per letter dated July 20, 2019.
Regulatory Basis Pursuant to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Paragraph 50.55a(z)(1), the licensee proposed to utilize BWRVIP Guidelines in lieu of the applicable Section XI requirements for Examination Categories B-N-1 and B-N-2. 10 CFR 50.55a(z)(1) requires the licensee to demonstrate that the proposed alternative provides an acceptable level of quality and safety.
The NRC staff needs to issue requests for additional information (RAIs) to complete its review of the licensee's proposed alternative.
Requests for Additional Information
RAI-2
Issue The NRC staff has become aware of a possible non-conservatism associated with the fracture toughness model published in BWRVIP-100, Rev. 1-A, Updated Assessment of the Fracture Toughness of Irradiated Stainless Steel for BWR Core Shrouds and incorporated into BWRVIP-235, BWR Vessel and Internals Project, Structural Analysis Software for BWR Internals, DLL Version 3.1. This issue has been communicated to applicable recipients through a 10 CFR Part 21, transfer of information notice, dated February 19, 2021 and updated on March 19, 2021. Furthermore, this information was communicated to the NRC on a letter dated March 22, 2021 (ADAMS Accession No. ML21084A164)
The NRC staff is aware that this possible non-conservatism exists in a fluence range of 5 x 1020 n/cm² to 3 x 1021 n/cm². More specifically, additional experimental data suggests the lower bound fracture toughness of 50 ksi-in is applicable at fluences of or greater than 5 x 1020 n/cm² as opposed to the defined threshold of 3 x 1021 n/cm².
The NRC staff has also become aware that this non-conservatism could potentially impact BWRVIP-76, Revision 1-A, BWRVIP-76, Revision 2, and BWRVIP Letter 2016-030. As a result, EPRI has determined that these documents cannot be used in their entirety as written.
to NRC-21-0032 Page 2 Furthermore, EPRI states that details on the specific impacts and recommended actions associated with BWRVIP-76, Revision 1-A, are included in Attachment 2. The NRC staff does not have access to the attachments provided in the Part 21 transfer of information notice.
The staff notes that BWRVIP-100, Rev. 1-A and BWRVIP-76-R1-A are included in the submittals table titled, BWRVIP Guidelines Used for Section XI Code Examinations (Part of this Request).
Request a) Provide detailed information on the applicability and intended use of BWRVIP-100, Rev. 1-A, as it applies to the applicable Section XI examinations that are being replaced by BWRVIP programs. Furthermore, the staff would like to know if the Part 21, transfer of information notices are applicable to Fermi 2. Within your response, provide the actions taken and/or planned to address the identified non-conservatism as applicable within the purview of this application.
b) Section 5 of the submittal includes a table titled, BWRVIP Guidelines Used for Section XI Code Examinations. Note (3) of the table references the applicability of BWRVIP-76, Revision 1-A. Provide information on how Fermi 2 is addressing EPRIs statement in regard to stopping the specified use of BWRVIP-76, Revision 1-A. Include which specific elements were impacted and which EPRI recommended actions are being taken (if applicable). If BWRVIP-76, Revision 1-A has been previously implemented, within your response, provide details on how this document was used within the purview of this application.
DTE RESPONSE The 10 CFR 21 communication from Electric Power Research Institute (EPRI) regarding the potential non-conservatism of BWRVIP-100 Rev. 1-A, captured in communication to the NRC in Reference 1.1 of this Enclosure, was received by DTE Electric Company (DTE) and promptly entered into the Fermi 2 Corrective Action Program (CAP) for review and evaluation. DTE also participated in the May 27, 2021 meeting between EPRI and the NRC, announced in Reference 1.2 of this Enclosure, to discuss the issue. Responses to the NRC requests are provided below based on the DTE CAP evaluation, including incorporation of feedback from the May 27, 2021 meeting.
a) As noted in BWRVIP-100 Rev. 1-A Section 1.5, Implementation Requirements, the only Needed guidance per NEI 03-08, Guideline for the Management for Materials Issues, within BWRVIP-100 Rev. 1-A is Section 4.1.4, which exclusively deals with the fracture toughness correlations forming the subject of the potential non-conservatism identified by EPRI. Therefore, DTE hereby withdraws the request to use BWRVIP-100 Rev. 1-A as part of the RR-A39 relief request submitted by DTE in Reference 1.3 of this Enclosure.
to NRC-21-0032 Page 3 EPRI is working to revise the fracture toughness correlations currently present in BWRVIP-100 Rev. 1-A. Once it has been revised by EPRI, DTE will implement the updated guidance approved for use by the BWRVIP Executive Committee in accordance with NEI 03-08. If use of the updated guidance was desired to be incorporated to a relief request, approval would be requested as needed in accordance with 10 CFR 50.55a. During the May 27, 2021 meeting, EPRI provided the NRC with a preliminary assessment of the fracture toughness correlations compared to the original guidance from BWRVIP-100 Rev. 1-A.
DTE has reviewed the 10 CFR 21 notice in Reference 1.1 for applicability and recommendations. Fermi 2 has no indications of intergranular stress corrosion cracking (IGSCC) associated with the core shroud. However, two shroud welds have to-date accrued, or will have accrued by end of plant life (52 EFPY), fluence greater than or equal to 5x1020 n/cm2 and therefore the 10 CFR 21 notice is applicable to those two welds.
DTE has reviewed current plant-specific analyses related to vessel internals, including inspection interval technical bases and proactively performed flaw evaluation handbooks.
Only those analyses specific to the two core shroud welds describe above were impacted by the 10 CFR 21 notice. DTE will revise the applicable analyses after the BWRVIP Executive Committee approves updated guidance related to the fracture toughness correlations originally present in BWRVIP-100 Rev. 1-A and/or BWRVIP-235. DTE has determined no additional examinations are required to address the 10 CFR 21 notice at this time. DTE may elect to perform supplementary examinations to develop further input for core shroud analysis revisions. The BWRVIP has initiated new tasks to address the 10 CFR 21 notice, as well as convened a Focus Group to provide for utility input (of which DTE is an active member for Fermi 2). Based on the conservatism inherent to the core shroud analyses and the fact that the Fermi 2 core shroud has no indications of IGSCC, DTE has reasonable assurance that the 10 CFR 21 notice does not reveal a substantial safety hazard such as a loss of a safety function to the extent that a major reduction in the degree of protection provided to the public health and safety exists, or would have existed, had the issue gone unnoticed or uncorrected.
b) Section 5 of the Reference 1.3 relief request provided a table showing which BWRVIP guidelines were included in the relief request. As described in the response to part (a) above, the request to use BWRVIP-100 Rev. 1-A has been withdrawn. The table also includes a note which relates BWRVIP-76-R1-A to BWRVIP-100 Rev. 1-A. Due to withdrawal of the request to use BWRVIP-100 Rev. 1-A, Note 3 of the Table BWRVIP Guidelines Used for Section XI Code Examinations is also withdrawn, as the fracture toughness values provided in BWRVIP-100 Rev. 1-A are found to be potentially non-conservative as identified in the 10 CFR 21 notice. As previously noted, DTE will implement the revised fracture toughness evaluation criteria after it has been reviewed and approved by the BWRVIP Executive Committee and issued to the BWRVIP utility members.
DTE has determined that the inspection criteria present in BWRVIP-76 Rev. 1-A remain more conservative when compared with the requirements of ASME Section XI (see Attachment 1 of the Reference 1.3 relief request), and plans to continue implementing those more conservative requirements (as modified by applicable EPRI recommendations) until the to NRC-21-0032 Page 4 BWRVIP provides an Executive Committee approved alternative to BWRVIP-76 Rev. 1-A.
For evaluation purposes, if revised fracture toughness criteria reviewed and approved by the BWRVIP Executive Committee are not available, but DTE emergent reevaluation is required to address Fermi 2 conditions associated with the core shroud, the preliminary assessment criteria provided by EPRI in the May 27, 2021 meeting will be utilized by DTE.
EPRI has provided preliminary instructions to allow for continued use of BWRVIP-235, if necessary. DTE has no plans at this time to utilize BWRVIP-235 prior to formal revision of the software to address the non-conservatism. EPRI has also provided preliminary recommendations related to revisions to the inspection interval and flaw evaluation guidance present in BWRVIP-76 Rev. 1-A. DTEs review concludes that flaw analysis revision is not an immediate requirement since the analysis was proactively produced and no IGSCC flaws are known to exist. DTEs review also concludes that the BWRVIP-76 Rev. 1-A recommended inspection interval revisions have not resulted in any missed examinations.
DTE plans to programmatically incorporate revised inspection and evaluation guidance after it is reviewed and approved by the BWRVIP Executive Committee.
BWRVIP-76 Rev. 1-A has previously been implemented at Fermi 2, with the previous examination having been performed during RF18 (2017). Five welds (including those two shroud welds with sufficient fluence for applicability to the 10 CFR 21 notice as described above) were examined via double-sided ultrasonic testing (UT). No relevant indications were identified. The examination requirements within BWRVIP-76 Rev. 1-A (EVT-1, UT) provide superior flaw characterization and detection than those present in ASME Section XI for Integrally Welded Core Support Structures (B-N-2), and as such BWRVIP-76 Rev. 1-A was originally included in this relief request as it provides a more stringent level of quality and safety. DTE will retain BWRVIP-76 Rev. 1-A as part of the relief request RR-A39.
References:
1.1) EPRI Letter 2021-030, Potential Non-Conservatism in EPRI Report, BWRVIP-100, Rev. 1-A, 3002008388 and Impacted BWRVIP Reports, dated March 22, 2021 (ML21084A164).
1.2) Notice of Meeting between the NRC staff and the Electric Power Research Institute, dated April 20, 2021 (ML21111A087).
1.3) DTE Letter NRC-20-0054, Submittal of Revised Relief Request RR-A39 for the Fourth Ten-year Interval, dated December 30, 2020 (ML20365A043).