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Category:Letter type:NRC
MONTHYEARNRC-24-0064, Supplement to License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance2024-10-31031 October 2024 Supplement to License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance NRC-24-0058, Status of License Renewal Commitments2024-10-0303 October 2024 Status of License Renewal Commitments NRC-24-0057, Update to NRC 24-0041: Technical Specification (TS) 5.6.7 – Post Accident Monitoring Report2024-09-0303 September 2024 Update to NRC 24-0041: Technical Specification (TS) 5.6.7 – Post Accident Monitoring Report NRC-24-0053, Enrico Fermi Atomic Power Plant, Unit 1, Annual Report for Period Ending June 30, 20242024-08-30030 August 2024 Enrico Fermi Atomic Power Plant, Unit 1, Annual Report for Period Ending June 30, 2024 NRC-24-0050, Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval2024-08-12012 August 2024 Inservice Inspection-Nondestructive Examination (ISI-NDE) Program for the Fourth 10-Year Inspection Interval NRC-24-0048, Submittal of Inservice Inspection Summary Report2024-08-0606 August 2024 Submittal of Inservice Inspection Summary Report NRC-24-0046, Fenni 2 Power Plant - 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Final Response to Request for Additional Information for License Amendment Request Regarding Risk Informed Approach to Performance ECCS Strainer Performance2024-05-30030 May 2024 DTE Electric Company - Final Response to Request for Additional Information for License Amendment Request Regarding Risk Informed Approach to Performance ECCS Strainer Performance NRC-24-0017, 2023 Annual Radioactive Effluent Release Report and 2023 Radiological Environmental Operating Report2024-04-29029 April 2024 2023 Annual Radioactive Effluent Release Report and 2023 Radiological Environmental Operating Report NRC-24-0032, Transmittal of the Core Operating Limits Report for Cycle 232024-04-25025 April 2024 Transmittal of the Core Operating Limits Report for Cycle 23 NRC-24-0027, Partial Response to Request for Additional Information for License Amendment Request Regarding Risk Informed Approach to Performance ECCS Strainer Performance2024-04-24024 April 2024 Partial Response to Request for Additional Information for License Amendment Request Regarding Risk Informed Approach to Performance ECCS Strainer Performance NRC-24-0031, Retake Exam Outline Submittal Letter2024-04-22022 April 2024 Retake Exam Outline Submittal Letter NRC-24-0018, 2023 Annual Non-Radiological Environmental Operating Report2024-04-0909 April 2024 2023 Annual Non-Radiological Environmental Operating Report NRC-24-0015, Enrico Fermi Atomic Power Plant, Unit 1, Decommissioning Funding Status Report2024-03-31031 March 2024 Enrico Fermi Atomic Power Plant, Unit 1, Decommissioning Funding Status Report NRC-24-0001, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Rev. 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, TSTF-439, Rev. 2, Eliminate Second Completion2024-03-21021 March 2024 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Rev. 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, TSTF-439, Rev. 2, Eliminate Second Completion NRC-24-0019, Submittal of 2023 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report2024-03-14014 March 2024 Submittal of 2023 Safety Relief Valve Challenge Report, Main Steam Bypass Lines Report, and ECCS Cooling Performance Evaluation Model Changes or Errors Report NRC-24-0023, NRC-24-0023, Post Exam Package Submittal Letter to NRC2024-03-0707 March 2024 NRC-24-0023, Post Exam Package Submittal Letter to NRC NRC-24-0008, Levels and Sources of Property Insurance Coverage2024-02-15015 February 2024 Levels and Sources of Property Insurance Coverage NRC-24-0009, Request for NRC to Suspend Regulatory Audit of License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance for Fermi Unit 22024-02-0606 February 2024 Request for NRC to Suspend Regulatory Audit of License Amendment Request for a Risk Informed Approach to ECCS Strainer Performance for Fermi Unit 2 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-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-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-23-0075, Request for Exemption from Enhanced Weapons, Firearms Background Checks and Security Event Notification Implementation2023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks and Security Event Notification Implementation 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 2024-09-03
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Keith J. Poison Site vice President DTE Energy Company 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734.586.4849 Fax: 734.586.4172 Email: leith.polson@dteenergy.com DTE Energy-December 9, 2016 10 CFR 50.54(f)
NRC-16-0070 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
References:
- 1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43
- 2) NRC Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2012 (Accession No. ML12053A340)
- 3) DTE Electric Company (DTE) Letter to USNRC, "DTE Electric Submittal of Flooding Hazard Reevaluation Report in Response to March 12, 2012 Information Request Regarding Flood Protection Evaluations," dated March 8, 2013 (Accession No. ML13070A199)
- 4) DTE Electric Company (DTE) Letter to USNRC, Response to Request for Additional Information Regarding Fukushima Lessons Learned -
Flood Hazard Reevaluation Report, dated June 26, 2014 (Accession No. ML14178B358)
- 5) NRC Staff Requirements Memoranda to COMSECY-14-0037, "Integration of Mitigating Strategies for Beyond-Design-Basis External Events and the Reevaluation of Flooding Hazards," dated March 30, 2015 (Accession No. ML15089A236)
- 6) Nuclear Energy Institute (NEI), Report NEI 12-06 [Rev 2], "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide," dated December 2015 (Accession No. ML16005A625)
- 7) U.S. Nuclear Regulatory Commission, JLD-ISG-2012-01, Revision 1, "Compliance with Order EA 049, Order Modifving Licenses with
USNRC NRC-16-0070 Page 2 Regard to Requirements for Mitigating Strategies for Beyond-Design-Basis External Events," dated January 22, 2016 (Accession No. ML15357A163)
- 8) NRC Letter, "Fermi 2 - Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation," dated December 30, 2014 (Accession No. ML14351A438)
- 9) NRC Letter, "Supplemental Information Related to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Flooding Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 1, 2013 (Accession No. ML13044A561)
- 10) DTE Electric Company (DTE), "Compliance Letter and Final Integrated Plan in Response to the March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigating Strategies for Beyond-Design-Basis External Events (Order Number EA 049)," dated January 20, 2016 (Accession No. ML16022A118)
Subject:
Flooding Mitigating Strategies Assessment Report On March 12, 2012, the NRC issued Reference 2 to request information associated with Near-Term Task Force (NTTF) Recommendation 2.1 for Flooding. One of the Required Responses in Reference 2 directed licensees to submit a Flood Hazard Reevaluation Report (FHRR). For Fermi 2, the FHRR was submitted on March 8, 2013 (Reference 3). The reevaluated flood hazard was further developed in response to requests for additional information (Reference 4). Per Reference 9, the NRC considers the reevaluated flood hazard to be "beyond the current design/licensing basis of operating plants."
Concurrent to the flood hazard reevaluation, Fermi 2 developed and implemented mitigating strategies in accordance with NRC Order EA-12-049, "Requirements for Mitigation Strategies for Beyond-Design-Basis External Events." In Reference 5, the Commission affirmed that licensees need to address the reevaluated flooding hazards within their mitigating strategies for Beyond-Design-Basis External Events, including the reevaluated flood hazards. Guidance for performing mitigating strategies assessments (MSAs) is contained in Appendix G of Reference 6, endorsed by the NRC (with conditions) in Reference 7. For the purpose of the MSAs, the NRC has termed the reevaluated flood hazard, summarized in Reference 8, as the "Mitigating Strategies
USNRC NRC-16-0070 Page 3 Flood Hazard Information" (MSFHI). Reference 6, Appendix G, describes the MSA for flooding as containing the following elements:
" Section G.2 - Characterization of the MSFHI
" Section G.3 - Comparison of the MSFHI and FLEX DB Flood
" Section G.4.1 - Assessment of Current FLEX Strategies (if necessary)
" Section G.4.2 - Assessment for Modifying FLEX Strategies (if necessary)
" Section G.4.3 - Assessment of Alternative Mitigating Strategies (if necessary)
" Section G.4.4 - Assessment of Targeted Hazard Mitigating Strategies (if necessary)
The following provides the MSA results for Fermi 2. Only Sections G.2 and G.3 of Reference 6, Appendix G, were required for Fermi 2, in accordance with Reference 8.
Reference 6. Section G.2 - Characterization of the MSFHI Characterization of the MSFHI is detailed in Section 3 of Reference 8, the NRC's interim response to the flood hazard reevaluation submittal and amended submittal (References 3 and 4). A more detailed description of the MSFHI, along with the basis for inputs, assumptions, methodologies, and models, is provided in the following references:
- Local Intense Precipitation (LIP): See Section 3.1 of Reference 3, Enclosure 1.
- Flooding in Streams and Rivers: See Section 3.2 of Reference 3, Enclosure 1.
" Dam Breaches and Failures: See Section 3.4 of Reference 3, Enclosure 1.
- Storm Surge: See Section 3.3 of Reference 3, Enclosure 1.
- Seiche: See Section 3.3 of Reference 3, Enclosure 1.
- Tsunami: See Section 3.8 of Reference 3, Enclosure 1.
- Ice-Induced Flooding: See Section 3.6 of Reference 3, Enclosure 1.
- Channel Migration or Diversion: See Section 3.7 of Reference 3, Enclosure 1.
- Combined Effects (including wind-waves and runup effects): See Section 3.5 of Reference 3, Enclosure 1, and Reference 4.
" Other Associated Effects (i.e. hydrodynamic loading, including debris; effects caused by sediment deposition and erosion; concurrent site conditions; and groundwater ingress): See Sections 3.10 and 4 of Reference 3, Enclosure 1, and Reference 4.
- Flood Event Duration Parameters (i.e., warning time, period of site preparation, period of inundation, and period of recession): See Sections 3.10 and 4 of Reference 3, Enclosure 1, and Reference 4.
At Fermi 2, the seiche, tsunami, ice-induced flooding, channel migration or diversion, and NUREG/CR-7046, Appendix H combined-effect floods H.1 (floods caused by precipitation events, including hydrologic dam failure), H.2 (seismically-induced dam failure), and H.3 (floods along the shores of open and semi-enclosed bodies of water)
USNRC NRC-16-0070 Page 4 flood-causing mechanisms were either determined to be implausible or completely bounded by other mechanisms.
In Reference 8, the NRC concluded that the "the reevaluated hazard results for each reevaluated flood-causing mechanism are bounded by the current design-basis flood hazard" for Fermi 2.
Reference 6, Section G.3 - Basis for Mitigating Strategies Assessment (FLEX Design Basis Comparison)
For Fermi 2, the FLEX design basis (FLEX DB) flood, described in Reference 10, is equivalent to the plant's current design basis (CDB) flood. A complete comparison of the CDB and reevaluated flood hazards is provided in Section 4 of the Reference 3 . As described in References 3 and 4, and summarized below, the CDB and FLEX DB floods bound the reevaluated flood (i.e., MSFHI) for all applicable flood-causing mechanisms, including associated effects and flood event duration parameters.
The NRC further affirms in Reference 8 that "the reevaluated flood hazard mechanisms are bounded by the CDB" and "it is unnecessary for the licensee [Fermi 2] to perform an integrated assessment or focused evaluation."
Therefore, since the MSFHI is bounded by the FLEX DB (equivalent to the CDB), as affirmed by the NRC, Fermi 2 considers the requirement to address the reevaluated flooding hazards within its BDB mitigating strategies as being satisfied with no further action required.
This letter contains no new regulatory commitments and no revision to existing regulatory commitments.
Should you have any questions or require additional information, please contact Mr. Scott A. Maglio, Manager - Nuclear Licensing, at (734) 586-5076.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on December 9, 2016 Keith J. Polson Site Vice President
USNRC NRC-16-0070 Page 5 cc: Director, Office of Nuclear Reactor Regulation NRC Project Manager NRC Resident Office Reactor Projects Chief, Branch 5, Region III Regional Administrator, Region III Michigan Public Service Commission, Regulated Energy Division (kindschl@michigan.gov)