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Category:Letter type:L
MONTHYEARL-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023 Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023 Submittal of Fifth Ten Year Inservice Testing Program L-23-034, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-06-13013 June 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-135, Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-31031 May 2023 Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report L-23-131, Readiness for Resumption of NRC Supplemental Inspection2023-05-12012 May 2023 Readiness for Resumption of NRC Supplemental Inspection L-23-101, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 20222023-05-12012 May 2023 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station - 2022 L-23-092, Occupational Radiation Exposure Report for Year 20222023-04-27027 April 2023 Occupational Radiation Exposure Report for Year 2022 L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-23-037, and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2023-03-29029 March 2023 and Perry Nuclear Power Plant - Independent Spent Fuel Storage Installation Changes, Tests, and Experiments L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023 Annual Notification of Property Insurance Coverage L-23-059, Response to Apparent Violation in NRC Inspection Report 05000346/2022091; EA 23-0022023-03-0909 March 2023 Response to Apparent Violation in NRC Inspection Report 05000346/2022091; EA 23-002 L-22-212, CFR 50.55a Request RP-5 Regarding Inservice Pump Testing2023-03-0606 March 2023 CFR 50.55a Request RP-5 Regarding Inservice Pump Testing L-23-048, Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2023-03-0101 March 2023 Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023 Energy Harbor Nuclear Corp Retrospective Premium Guarantee L-22-253, Submittal of Pressure and Temperature Limits Report, Revision 52023-01-10010 January 2023 Submittal of Pressure and Temperature Limits Report, Revision 5 L-22-284, Request for Notice of Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink (UHS)2022-12-28028 December 2022 Request for Notice of Enforcement Discretion for Technical Specification 3.7.9, Ultimate Heat Sink (UHS) L-22-211, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2022-09-29029 September 2022 Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 42022-09-27027 September 2022 Submittal of Pressure and Temperature Limits Report. Revision 4 L-22-213, Occupational Radiation Exposure Report for Year 2021 - Correction2022-09-23023 September 2022 Occupational Radiation Exposure Report for Year 2021 - Correction L-22-129, Submittal of the Updated Final Safety Analysis Report, Revision 342022-09-20020 September 2022 Submittal of the Updated Final Safety Analysis Report, Revision 34 L-22-194, Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events2022-09-19019 September 2022 Submittal of Supplemental Information for the Reanalysis for Protection Against Low Temperature Reactor Coolant System Overpressure Events L-22-203, Submittal of Evacuation Time Estimates2022-09-12012 September 2022 Submittal of Evacuation Time Estimates L-22-050, Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual2022-08-0909 August 2022 Summary of Changes to the Energy Harbor Nuclear Corp. Quality Assurance Program Manual L-22-152, Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan2022-07-0505 July 2022 Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan L-22-068, Cycle 22 and Refueling Outage 22 Inservice Inspection Summary Report2022-06-30030 June 2022 Cycle 22 and Refueling Outage 22 Inservice Inspection Summary Report L-22-037, 2021 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2022-06-30030 June 2022 2021 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-22-149, Post Accident Monitoring Report2022-06-23023 June 2022 Post Accident Monitoring Report L-22-153, Readiness for NRC Supplemental Inspection Required for a White Finding2022-06-22022 June 2022 Readiness for NRC Supplemental Inspection Required for a White Finding L-22-098, Withdrawal of Proposed Inservice Inspection Alternative RR-A22022-06-22022 June 2022 Withdrawal of Proposed Inservice Inspection Alternative RR-A2 L-22-136, Steam Generator Tube Circumferential Crack Report - Spring 2022 Refueling Outage2022-06-0707 June 2022 Steam Generator Tube Circumferential Crack Report - Spring 2022 Refueling Outage L-22-102, Report of Facility Changes, Tests, and Experiments2022-05-16016 May 2022 Report of Facility Changes, Tests, and Experiments L-22-092, Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 20212022-05-16016 May 2022 Combined Annual Radiological Environmental Operating Report and Radiological Effluent Release Report for the Davis-Besse Nuclear Power Station - 2021 L-22-124, Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building2022-05-12012 May 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building L-22-047, Unit No.1 - Core Operating Limits Report, Cycle 23, Revision O and Revision 12022-05-10010 May 2022 Unit No.1 - Core Operating Limits Report, Cycle 23, Revision O and Revision 1 L-22-127, Readiness for NRC Supplemental Inspection Required for a Greater than Green Finding2022-05-0606 May 2022 Readiness for NRC Supplemental Inspection Required for a Greater than Green Finding L-22-089, Occupational Radiation Exposure Report for Year 20212022-04-12012 April 2022 Occupational Radiation Exposure Report for Year 2021 L-22-056, Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage2022-03-22022 March 2022 Energy Harbor Nuclear Corp., Annual Notification of Property Insurance Coverage L-22-059, Response to Request for Additional Information on Proposed Inservice Test Alternative RP-32022-03-21021 March 2022 Response to Request for Additional Information on Proposed Inservice Test Alternative RP-3 L-22-074, Response to Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-15015 March 2022 Response to Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations L-22-061, Ile Post Exam Letter L-22-0612022-02-24024 February 2022 Ile Post Exam Letter L-22-061 L-22-023, Retrospective Premium Guarantee2022-02-17017 February 2022 Retrospective Premium Guarantee L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A22022-01-27027 January 2022 Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 L-20-289, Emergency Plan Amendment Request2022-01-19019 January 2022 Emergency Plan Amendment Request L-21-290, Response to NRC Inspection Report 05000346/2021091, EA-21-1762021-12-21021 December 2021 Response to NRC Inspection Report 05000346/2021091, EA-21-176 2023-09-12
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-23-048, Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2023-03-0101 March 2023 Response to Request for Additional Information Regarding Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report ML22292A0232022-10-18018 October 2022 Framatome Inc., Document ANP-2718-007Q1NP, Revision 0, Response to Request for Additional Information on Appendix G Pressure-Temperature Limits for 52 EFPY for Davis-Besse Nuclear Power Station - First Energy Nuclear Operating Company L-22-229, Response to Request for Additional Information Regarding Request to Withhold Information in Framatome Inc. Document ANP-2718P-007 from Public Disclosure & Affidavit2022-10-13013 October 2022 Response to Request for Additional Information Regarding Request to Withhold Information in Framatome Inc. Document ANP-2718P-007 from Public Disclosure & Affidavit L-22-152, Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan2022-07-0505 July 2022 Response to Request for Additional Information Regarding a License Amendment Request That Revises the Davis-Besse Nuclear Power Station Emergency Plan L-22-124, Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building2022-05-12012 May 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise the Design Basis for the Shield Building L-22-059, Response to Request for Additional Information on Proposed Inservice Test Alternative RP-32022-03-21021 March 2022 Response to Request for Additional Information on Proposed Inservice Test Alternative RP-3 ML22081A1472022-03-11011 March 2022 R22 (March 2022) - Steam Generator Tube Inspection Discussion Points 11 March 2022 ML22049A0662022-02-10010 February 2022 Response to NRC Questions from 2/1/2022 Regulatory Conference on Failed Field Flash Selector Switch L-21-266, Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A22022-01-27027 January 2022 Response to Request for Additional Information on Proposed Inservice Inspection Alternative RR-A2 ML21130A2192021-05-10010 May 2021 Request for Additional Information Regarding Steam Generator Tube Inspection Reports (EPIDs L2020-LRO-0055, L-2020-LRO-0082, and L2020-LRO-0083) ML21088A3442021-03-29029 March 2021 Final Supplemental Response to Nuclear Regulatory Commission Generic Letter 2004-02 L-21-101, Final Supplemental Response to Nuclear Regulatory Commission Generic Letter 2004-022021-03-29029 March 2021 Final Supplemental Response to Nuclear Regulatory Commission Generic Letter 2004-02 L-21-030, Response to Request for Additional Information Regarding an Amendment to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications (EPID L-20202021-01-27027 January 2021 Response to Request for Additional Information Regarding an Amendment to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications (EPID L-2020 L-20-313, Response to Request for Additional Information Regarding Request for Exemption -Part 73 Force-on-Force2020-12-0707 December 2020 Response to Request for Additional Information Regarding Request for Exemption -Part 73 Force-on-Force L-20-183, Response to Request for Additional Information Regarding License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force2020-06-23023 June 2020 Response to Request for Additional Information Regarding License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force L-20-155, Response to Request for Additional Information Regarding Request for Exemptions to Certain Periodic Training Requirements for Security Personnel (Epids L-2020-LLE-0026 to -0040)2020-05-0606 May 2020 Response to Request for Additional Information Regarding Request for Exemptions to Certain Periodic Training Requirements for Security Personnel (Epids L-2020-LLE-0026 to -0040) L-20-041, Response to Request for Additional Information Regarding License Amendment Request to Extend Containment Leakage Test Interval2020-02-0303 February 2020 Response to Request for Additional Information Regarding License Amendment Request to Extend Containment Leakage Test Interval L-19-182, Response to RAI Regarding an Application for Order Consenting to Transfer of License2019-08-0202 August 2019 Response to RAI Regarding an Application for Order Consenting to Transfer of License L-19-178, Response to Request for Additional Information Regarding Request for Approval of Decommissioning Quality Assurance Program for the Davis-Besse Nuclear Power Station2019-07-16016 July 2019 Response to Request for Additional Information Regarding Request for Approval of Decommissioning Quality Assurance Program for the Davis-Besse Nuclear Power Station L-19-166, Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request for Proposed Post-Shutdown Emergency Plan2019-07-0808 July 2019 Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request for Proposed Post-Shutdown Emergency Plan L-19-160, Response to Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications2019-06-26026 June 2019 Response to Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications L-18-121, Response to Request for Supplemental Information Regarding Generic Letter 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.2018-05-25025 May 2018 Response to Request for Supplemental Information Regarding Generic Letter 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools. L-18-125, Response to Follow-up Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement IEPID-L-2017-l-LE-0019 (CAC Nos.000976/05000334/-L-2017-LLE-0019 MG0010, 000976/05000334/L-2017-LLE-0019 MG0011,000976/02018-05-0202 May 2018 Response to Follow-up Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement IEPID-L-2017-l-LE-0019 (CAC Nos.000976/05000334/-L-2017-LLE-0019 MG0010, 000976/05000334/L-2017-LLE-0019 MG0011,000976/0 L-18-085, Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052018-04-0202 April 2018 Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 L-18-061, Units. 1 & 2, Davis-Besse, and Perry, Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement2018-03-16016 March 2018 Units. 1 & 2, Davis-Besse, and Perry, Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement L-17-372, Response to Request for Additional Information Regarding Request to Use ASME Code Case N-513-4 (EPID 000976/05000334/L-2017-LLR-0088,000976/05000346/L-2017-LLR-0088, 000976/05000412/L-2017-LLR-0088, and 000976/05000440/L-2017-LLR-0088)2017-12-23023 December 2017 Response to Request for Additional Information Regarding Request to Use ASME Code Case N-513-4 (EPID 000976/05000334/L-2017-LLR-0088,000976/05000346/L-2017-LLR-0088, 000976/05000412/L-2017-LLR-0088, and 000976/05000440/L-2017-LLR-0088) L-17-253, Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052017-10-0909 October 2017 Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 L-17-233, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukishima Dai-ichi Accident2017-08-0202 August 2017 High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukishima Dai-ichi Accident L-17-189, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052017-06-16016 June 2017 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 ML17163A4122017-06-0808 June 2017 Areva, ANP-3542Q1NP, Revision 0, Response to NRC Request for Additional Information on Time-Limited Aging Analysis for the DB-1 Reactor Vessel Internals. L-17-158, Reply to Request for Additional Information Re License Renewal Commitment No. 422017-05-12012 May 2017 Reply to Request for Additional Information Re License Renewal Commitment No. 42 L-17-070, Reply to Request for Additional Information Related to License Renewal Commitment2017-02-22022 February 2017 Reply to Request for Additional Information Related to License Renewal Commitment L-16-371, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052017-01-17017 January 2017 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 L-16-345, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Cnfpa) Standard 8052016-12-16016 December 2016 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Cnfpa) Standard 805 L-16-323, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to CFR 50.54(f) Regarding Recommendation 2.1 of the Near Term Task Force Review of Insights from Fukushima Dai-inchi Accident2016-12-0909 December 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to CFR 50.54(f) Regarding Recommendation 2.1 of the Near Term Task Force Review of Insights from Fukushima Dai-inchi Accident L-16-291, Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2016-11-0101 November 2016 Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools L-16-279, Reply to Request for Additional Information Related to License Renewal Commitment 422016-09-26026 September 2016 Reply to Request for Additional Information Related to License Renewal Commitment 42 L-16-123, Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2016-09-23023 September 2016 Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events L-16-256, Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan2016-09-0606 September 2016 Response to Request for Additional Information Regarding a Request to Revise the Emergency Plan L-16-220, Response to Regulatory Issue Summary 2016-09, Preparation and Scheduling of Operator Licensing Examinations.2016-07-20020 July 2016 Response to Regulatory Issue Summary 2016-09, Preparation and Scheduling of Operator Licensing Examinations. L-16-085, Request for Additional Information Response Related to Modification of Technical Specification 5.3.1, Unit Staff Qualifications.2016-03-22022 March 2016 Request for Additional Information Response Related to Modification of Technical Specification 5.3.1, Unit Staff Qualifications. L-16-079, Supplemental Information for License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052016-03-0707 March 2016 Supplemental Information for License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 L-16-040, Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage and Frequency Surveillance Requirements2016-02-19019 February 2016 Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage and Frequency Surveillance Requirements ML15299A1432015-10-19019 October 2015 Additional Information for the Advisory Committee on Reactor Safeaquards Review of the License Renewal Application, Including Enclosure a, Bechtel Affidavit L-15-268, Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage and Frequency Surveillance Requirements2015-10-14014 October 2015 Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage and Frequency Surveillance Requirements ML15280A2872015-10-0606 October 2015 Additional Information for the Advisory Committee on Reactor Safeguards Review of License Renewal Application L-15-263, Response to Request for Additional Information Related to Security Plan Changes2015-08-17017 August 2015 Response to Request for Additional Information Related to Security Plan Changes L-15-197, Response to Request for Additional Information Regarding a Request to Amend Technical Specification 5.5.15. Containment Leakage Rate Testing Program2015-06-26026 June 2015 Response to Request for Additional Information Regarding a Request to Amend Technical Specification 5.5.15. Containment Leakage Rate Testing Program 2023-03-01
[Table view] |
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FENOC' 5501 North State Route 2 RrstEnergy Nuclear Operating Company Oak Harbor. Ohio 43449 Brian D. Boles 419-321-7676 Vice President, Fax: 419-321-7582 Nuclear February 22, 2017' L-17-070 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station, Unit No. 1 Docket No. 50-346, License Number NPF-3 Reply to Request for Additional Information Related to License Renewal Commitment No. 42 (CAC MF7626)
By letter dated April 21, 2016 (Agencywide Documents Access and Management, System (ADAMS) Accession No. ML16112A079), FirstEnergy Nuclear Operating Company (FENOC) submitted a Fatigue Monitoring Program evaluation for Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), to address License Renewal Commitment 42. By letter dated September26, 2016 (ADAMS Accession No.
ML16270A447), FENOC submitted a reply to a U.S. Nuclear Regulatory Commission (NRC) request for additional information regarding FENOC's April 21, 2016 letter.
By letter dated January 23, 2017 (ADAMS Accession No. ML16364A279), the NRC requested additional information to complete its review of FENOC's Fatigue Monitoring Program evaluation. Attachment 1 provides the FENOC reply to the NRC request for additional information. Attachment 2 provides a regulatory commitment to complete fatigue evaluations for nickel-based alloys (NBA) and low-alloy steel (LAS) components and submit the evaluations. These evaluations will be submitted on or before April 28, 2017.
If there are any questions or if additional information is required, please contact Mr. Patrick McCloskey, Manager- Regulatory Compliance, at (419) 321-7274.
Davis-Besse Nuclear Power Station, Unit No. 1 L-17-070 Page2 Attachments:
- 1. Reply to Request for Additional Information Related to Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), License Renewal Commitment 42
- 2. Regulatory Commitment List cc: NRC Region Ill Administrator NRC Resident Inspector NRC Project Manager Utility Radiological Safety Board
Attachment 1 L-17-070 Reply to Request for Additional"lnformation (RAI) Related to Davis-Besse Nuclear Power St~tion, Unit No. 1 (DBNPS),
License Renewal Commitment 42 Page 1 of 12 By letter dated January 23, 2017 (ADAMS Accession No. ML16364A279), the NRG requested additional information to complete its review of FirstEnergy Nuclear Operating Company's (FENOC's) Fatigue Monitoring Program evaluation. The requested information is provided below. The NRG staff request is shown in bold text, followed by the FENOC reply.
NRC STAFF RAI
Background
Section 2.C(11), "License Renewal Conditions," of Renewed Facility Operating License No. NPF-3 specifies that the Commitments in Appendix A of NUREG-2193, Supplement 1, "Safety Evaluation Report Related to the l..icense Renewal of Davis-Besse Nuclear Power Station," published April 2016 (ADAMS Accession No. ML16104A350), are part of the DBNPS Updated Final Safety Analysis Report.
License renewal Commitment No. 42 in Appendix A of NUREG 2193, Supplement 1, states the following:
Enhance the Fatigue Monitoring Program to:
- Evaluate additional plant-specific component locations in the reactor coolant pressure boundary that may be more limiting than those considered in NUREG/CR-62601* This evaluation will include identification of the most limiting fatigue location exposed to reactor coolant for.each material type (i.e., [carbon steel] CS, [low-alloy steel] LAS, [stainless steel] SS, and [nickel-based alloy] NBA) and that each bounding material/location will be evaluated for the effects of the reactor coolant environment on fatigue usage. Nickel-based alloy items will be evaluated using NUREG/CR-690!>2. Submit the evaluation to the NRC 1 year prior to the period of extended operation.
Enclosure B of the licensee's letter dated June 17, 2011 (ADAMS Accession No.
ML11172A389), provides AREVA Report No. 51-9157140-001. Table 3-9 of the AREVA Report contains the environmentally-assisted fatigue (EAF) values for the NUREG/CR-6260 locations. Table 3-8 of the AREVA Report contains a summary of 1 NUREG/CR-6260, "Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plant Components, dated February 1995, ADAMS Accession No. ML031480219.
2 NUREG/CR-6909 "Effect of LWR Coolant Environments on the Fatigue Life of Reactor Materials," dated February 2007.
L-17-070 Page 2 of 12 the reactor coolant system pressure boundary locations with environmentally-adjusted cumulative usage factor (CUFen) values that exceed the limit of 1.0.
In its April 21, 2016, letter, the licensee submitted the results of its evaluations associated with Commitment No. 42. The letter stated that locations were screened in accordance with the methodology of Electric Power Research Institute (EPRI) Technical Report 1024995, "Environmentally Assisted Fatigue Screening[:] Process and Technical Basis for Identifying EAF Limiting Locations," dated 2012. The letter also identified the most limiting locations for each of the four material types (i.e., CS, LAS, SS, and NBA). The CUFen values are provided for two of the four limiting locations. The CUFen values are not provided for the LAS and NBA locations. The LAS and NBA locations reference EPRI Technical Report 1024995.
By email dated August 26, 2016 (ADAMS Accession No. ML16242A008), the NRC staff requested additional information regarding the licensee's April 21, 2016, letter. The licensee responded to this request by letter dated September 26, 2016.
However, this response did not fully address the staff's request.
In the August 26, 2016, email, the NRC staff asked for the following information in Request (1 ):
Describe the plant-specific methodology and criteria used to rank locations and select the most limiting locations for EAF. Describe relevant factors for each step of the process, such as thermal zones, material types, transient complexity, temperature effects, and complexity of the systems (as applicable). Justify the use of different material types to bound locations. Justify that the process is appropriately conservative.
In addition, the NRC staff asked for the following information in Request (4):
State the locations being managed by the fatigue monitoring program to maintain the CUFen values below the limit of 1.0 through the period of extended operation. Provide the CUFen values for the locations being managed by the fatigue monitoring program.
The licensee's response to Request (1) did not justify the use of different material types to bound locations and did not justify that the process is appropriately conservative. In Table 1 of the licensee's September 26, 2016, letter, the licensee provided information regarding the screening of initial sentinel locations. The NBA and LAS locations in Table 3-9 of AREVA Report No. 51-9157140-001 are not bounded by the locations provided in Table 1 of the September 26, 2016, letter.
L-17-070 Page 3 of 12 The licensee's response to Request (4) states that Table 2 of the licensee's September 26, 2016, letter "lists the CUFen value for the components evaluated."
Table 2 appears to only include the non-NUREG/CR-6260 locations being tracked by the licensee's allowable operating transient cycle program to maintain the CUFen values below the limit of 1.0 through the period of extended operation.
Request The numbering is continued from the NRC staffs previous request for additional information issued by email dated August 26, 2016. - -
(5) a. Justify the use of different material types to bound locations.
- b. Justify the elimination of NBA and LAS locations with CUFen values that are more limiting than NBA and LAS locations considered in NUREG/CR-6260.
- c. Justify that the process is appropriately conservative if the allowable operating transient cycle program is tracking NBA and LAS locations that do not have the highest CUFen values and are not bounding for the respective material types.
- d. Provide the list of EAF locations being tracked by the fatigue monitoring program, if it is revised. *
(6) Provide both the NUREG/CR-6260 and non-NUREG/CR-6260 locations being managed by the fatigue monitoring program to maintain the CUFen values below the limit of 1.0 through the period of extended operation. Provide the CUFen value, American Society of Mechanical Engineers Code CUF value, material type, and environmental correction factor (Fen) for each EAF location being managed by the fatigue monitoring program.
(7) License renewal Commitment No. 23 states:
In association with the time-limited aging analysis for effects of environmentally assisted fatigue of the high-pressure injection (HPI) nozzle safe end including the associated Alloy 82/182 weld (weld that connects the safe end to the nozzle), replace the HPI nozzle safe end, including the associated Alloy 82/182 weld, for all four HPI nozzles prior to the period of extended operation. Apply the Fat_igue Monitoring Program to evaluate the environmental effects and manage cumulative fatigue damage for the replacement HPI nozzle safe ends and associated welds.
In its April 21, 2016, [letter,] the licensee stated that:
Due to higher than expected dose rates, the elbows immediately upstream of the HPI nozzles were not replaced as originally planned.
L-17-070 Page 4 of 12 The evaluation performed for Commitment 42 assumed these elbows would be replaced prior to entry into the period of extended operation, and therefore would have no appreciable fatigue life. The Fatigue Monitoring Program will be applied to these elbows as part of Commitment 23 to evaluate the environmental effects and manage cumulative fatigue damage for the elbows along with the replacement HPI nozzle safe ends and associated welds. This evaluation will be complete prior to October 22, 2016, as currently documented in NUREG-2193.
By letter dated November 18, 2016 (ADAMS Accession No. ML16327A066),
the licensee stated that it had completed those activities noted in license renewal commitments applicable to DBNPS, which are part of the DBNPS Updated Final Safety Analysis Report.
Confirm that the elbows immediately upstream of the HPI nozzles impacted by the completion of Commitment No. 23 are bounded by the limiting EAF locations that are being tracked. Confirm that the plant-specific methodology and criteria used to rank locations and select the most limiting locations for EAF was consistently applied to these locations.
FENOC REPLY TO RAI (5) a. Justify the use of different material types to bound locations.
- b. Justify tl:le elimination of NBA and LAS locations with CUFen values that
. are more limiting than NBA and LAS locations considered in NUREG/CR-6260.
- c. Justify that the process is appropriately conservative if the allowable operating transient cycle program is tracking NBA and LAS locations that do riot have the highest CUFen values and are not bounding for the respective material types.
- d. Provide the list of EAF locations being tracked by the fatigue monitoring program, if it is revised.
RESPONSE RAI (5) a - d In response to issues (5) a - c, in lieu of justifying the use of different materials to bound locations, FENOC will evaluate the limiting NBA and LAS for EAF for 60-year projected cycles. In addition, Davis-Besse plans to evaluate the remaining locations with EAF greater than 1.0 that were considered bounded by other locations. These locations were identified in FENOC Letter dated September 26, 2016 (ADAMS Accession No. ML16270A447), Table 1.
L-17-070 Page 5 of 12 See Attachment 2 to this letter for the regulatory commitment.
In response to issue (5) d, as discussed in FENOC Letter dated September 26, 2016 (ADAMS Accession No. ML16270A447), response to Question 4, all locations are being tracked by the Fatigue Monitoring Program. See Table 1 at the end of this section for the current list of EAF locations being managed by the Fatigue Monitoring Program.
(6) Provide both the NUREG/CR-6260 and non-NUREG/CR-6260 locations being managed by the fatigue monitoring program to maintain the CUFen values below the limit of 1.0 through the period of extended operation. Provide the CUFen value, American Society of Mechanical Engineers Code CUF value, material type, and environmental correction factor (Fen) for each EAF location being managed by the fatigue monitoring program.
RESPONSE RAI (6)
See Table 1 at the end of this section for the current list of Reactor Coolant System (RCS) pressure boundary components in contact with the RCS Environment being managed for EAF by the Fatigue Monitoring Program.
(7) License renewal Commitment No. 23 states:
In association with the time-limited aging analysis for effects of environmentally assisted fatigue of the high-pressure injection (HPI) nozzle safe end including the associated Alloy 82/182 weld (weld that connects the safe end to the nozzle}, replace the HPI nozzle safe end, including the associated Alloy 82/182 weld, for all four HPI nozzles prior
- to the period of extended operation. Apply the Fatigue Monitoring Program to evaluate the environmental effects and manage cumulative
- fatigue damage for the replacement HPI nozzle safe ends and associated welds.
In its April 21, 2016, [letter,] the licensee stated that:
Due to higher than expected dose rates, the elbows immediately upstream of the HPI nozzles were not replaced as originally planned.
The evaluation performed for Commitment 42 assumed these elbows would be replaced prior to entry into the period of extended operation, and therefore would have no appreciable fatigue life. The Fatigue Monitoring Program will be applied to these elbows as part of Commitment 23 to evaluate the environmental effects and manage cumulative fatigue damage for the elbows along with the replacement HPI nozzle safe ends and associated welds. This evaluation will be complete prior to October 22, 2016, as currently documented in NUREG-2193.
L-17-070 Page 6 of 12 By letter dated November 18, 2016 (ADAMS Accession No. ML16327A066),
the licensee stated that it had completed those activities noted in license renewal commitments applicable to DBNPS, which are part of the DBNPS Updated Final Safety Analysis Report.
Confirm that the elbows immediately upstream of the HPI nozzles impacted by the completion of Commitment No. 23 are bounded by the limiting EAF locations that are being tracked. Confirm that the plant-specific methodology and criteria used to rank locations and select the most limiting locations for EAF was consistently applied to these locations.
RESPONSE RAI (7)
An EAF evaluation was performed for the High Pressure Injection (HPI) Piping and elbowlet connection in accordance with NUREG/CR-5704, "Effects of LWR Coolan.t Environments on Fatigue Design Curves of Austenitic Stainless Steels."
The results of the evaluation are included in Table 1, below.
L-17-070 Page 7 of 12 Table 1: Reactor Coolant System (RCS) Components Managed by the Fatigue Monitoring Program Material Component Location CUF CUFadj Fen CUFen Notes Type RV Closure, Head LAS O.o3 2.45 0.07 RV Closure, Vessel LAS 0.02 2.45 0.05 CROM Housing, Adapter SS 0.014 15.35 0.21 CROM Housing, Body CROM Housing, Blind Flanges
. Ni-Cr-Fe SS 0.08 0.0024 4.78 15.35 0.38 0.04 CROM Housing, Motor Tube Flanges SS 0.00 15.35 0 Inlet Nozzle LAS 0.829 0.146 2.45 0.358 NUREGICR-6260 Location Outlet Nozzle LAS 0.768 0.335 2.45 0.821 NUREGICR-6260 Location Reactor Vessel Core Flood Nozzle to Safe End SS 0.064 15.34 0.982 Core Flood Nozzle LAS 0.504 2.45 0. 123 NUREGICR-6260 Location lncore Instrument Nozzles Ni-Cr-Fe 0.770 0.206 4. 16 0.857 NUREG/CR-6260 Location Segmented Skirt, Head to Skirt Structure cs 0.254 1.74 0.44 RV Shell, Nozzle Belt LAS 0.024 2.45 0.059 RV Shell, Lower Head LAS 0.024 2.45 0.059 NUREGICR-6260 Location Continuous Vent Nozzle, Reducer to Pipe Weld SS 0.001 15.35 0.02 Continuous Vent Nozzle, J-Groove Weld Ni-Cr-Fe 0.9 4.78 4.31 See Note 10 Reactor Coolant RC pump cover, cooling hole ligament SS 0.56 NIA NIA See Note 1 Pumps RC pump cover, bearing cavity SS 0.964 0.032 15.35 0.49
L-17-070 Page 8 of 12 Table 1: Reactor Coolant System (RCS) Components Managed by the Fatigue Monitoring Program, cont.
Material Component Location CUF CUFadj Fen CUFen Notes Type Spray Nozzle, Nozzle cs 0.01 1.74 0.02 Spray Nozzle, Safe End Ni-Cr-Fe 0.01 4.78 0.05 Spray Nozzle, Nozzle I Head Juncture cs 0.01 1.74 0.02 Spray Nozzle, Weld Overlay Ni-Cr-Fe 0.01 4.78 0.05 Surge Nozzle, Inside Radius cs 0.182 1.74 0.317 NUREG/CR-6260 Location Surge Nozzle, Safe End SS 0.108 0.0581 15.35 0.892 NUREG/CR-6260 Location Surge Nozzle, Piping to Safe End Weld SS 0.6 19 1.49 0.922 NUREG/CR-6260 Location Vessel Suooort Lugs, Support cs 0.01 1.74 0.02 Vessel Suooort Lugs, Shell cs 0.01 1.74 0.02 Heater Bundle Closure, Cover Plate LAS 0.05 2.45 0.123 Heater Bundle Closure, Diaphragm Plate SS 0.41 *
- 0.92 *See Note 3 Heater Bundle Closure, Seal Weld SS 0.66 *
- 0.75 *See Note 3 Pressuriz.er Shel~ Heater Belt Transition cs 0.13 1.74 0.23 3" Pressuriz.er Relief Nozzle, Nozzle cs Exempt See Note 4 3" Pressuriz.er Relief Nozzle, Safe End SS Exempt See Note 4 3" Pressuriz.er Relief Nozzle, Uooer Head cs Exempt See Note 4 Other Openings, Vent Nozzle Ni-Cr-Fe Exempt See Note 5 Other Openings, Level Sensing Nozzle (Upper) Ni-Cr-Fe Exempt See Note 5 Other Openings, Level Sensing Nozzle (Lower) Ni-Cr-Fe Exempt See Note 5 Other Openings, Level Sensing Nozzle (Lower) Opening Ni-Cr-Fe 0. 166 4.78 0.793 Other Openings, Thermowell Nozzle Ni-Cr-Fe Exempt See Note 5 Other Openings, Thennowell Nozzle Opening Ni-Cr-Fe 0.166 4.78 0.793 Other Openings, Sampling Nozzle Ni-Cr-Fe Exempt See Note 5 Other Openings, Sampling Nozzle Opening Ni-Cr-Fe 0.166 4.78 0.793 Other Openings, Manway cs Exempt See Note 5
L-17-070 Page 9 of 12 Table 1: Reactor Coolant System (RCS) Components Managed by the Fatigue Monitoring Program, cont.
Material Component Location CUF CUFadj Fen CUFen Notes Tvoe Primary Manwavs LAS 0.34 2.45 0.83 Primary Manway Diaphragm Seal Welds See Note 6 Primary Handhole Cover LAS 0.37 2.45 0.91 Primary Handhole Diaphragm Seal Weld See Note 6 Inlet Nozzle I Primary Head Juncture LAS 0.79 2.45 1.94 See Note 10 Primary Outlet Nozzles LAS 0.14 2.45 0.34 Outlet Nozzle I Primary Head Junctures LAS 0.25 2.45 0.61 Lower Primary Head away from Outlet Nozzles LAS 0.11 2.45 0.27 Steam Generators Upper Primary Head I Tubesheet Knuckle including Vent I LAS 0.28 2.45 0.69 (See Note 1) Level Sensing and Acoustic Sensor Lower Primary Head I Tubesheet Knuckle LAS 0.08 2.45 0.20 Perforated Tubesheets, Postulated Thin Ligament (Primary LAS 0.39 2.45 0.96 Side)
Lower Spherical I Flat Head Juncture LAS 0.33 2.45 0.81 Lower Flat Head LAS 0.10 2.45 0.25 Tubes Ni-Cr-Fe 0.36 4.78 1.72 See Note 10 Tube Seal Welds Ni-Cr-Fe 0.42 4.78 2.01 See Note 10 Tube Plug Seal Welds Ni-Cr-Fe 0.23 4.78 1.10 See Note 10
L-17-070 Page 10of12 Table 1: Reactor Coolant System (RCS) Components Managed by the Fatigue Monitoring Program, cont.
Material Component Location CUF CUFadj Fen CUFen Notes Type Hot Leg Piping cs 0.827 1.74 1.44 See Note 10 Uooer Cold Leg Piping cs 0.59 1.74 0. 10 Lower Cold Leg cs 0. 183 1.74 0.32 Pressurizer Surge Line, Hot Leg Surge Nozzle Inside Radius cs 0.445 1.74 0.774 NUREG/CR-6260 Location Pressurizer Surge Line, Piping Adjacent to Outboard End of Reactor Coolant SS 0.179 0.0385 9.05 0.348 NUREG/CR-6260 Location Hot Leg Surge Nozzle (End of Hot Leg Weld Overlay)
System (RCS)
Pressurizer Surge Line, Piping Elbows SS 0.6463 0.0833 11.13 0.927 NUREG/CR-6260 Location Piping Pressurizer Surge Line, Piping Straights SS 0.7658 0.0953 9.85 0.939 NUREG/CR-6260 Location Reactor Coolant Pump Discharge Nozzle SS 0.0007 15.35 0.01 Reactor Coolant Pump Suction Nozzle SS 0.0004 15.35 0.01 Spray Line Piping (Node 73) SS 0.486 9.013 4.38 See Note 10 Spray Line Piping (Node 81) SS 0.454 9.013 4.09 See Note 10 Decay Heat Nozzle cs 0.89 0.5269 1.74 0.92
L-17-070 Page 11 of 12 Table 1: Reactor Coolant System (RCS) Components Managed by the Fatigue Monitoring Program, cont.
Material Component Location CUF CUFadj Fen CUFen Notes Type HPl/MU Nozzle cs 0.226 0.271 1.74 0.472 NUREG/CR-6260 Location NUREG/CR-6260 Location HPl/MU Nozzle, Safe End including Weld SS 0.141 0.064
- See Note 8 Letdown Piping SS 0.604 0.04774 15.35 0.73 RC Drain Nozzles SS 0.132 0.1184
Core Flood Piping SS 0.582 0.23967 2.55 0.61 Piping Continuous Vent Line SS 0.0318 15.35 0.49 Core Flood Tank Discharge Check Valves SS 0.02839 15.35 0.44 Decay Heat Containment Isolation Valves SS 0.14594 0.01268 15.35 0.19 Decay Heat Bypass Containment Isolation Valves SS 0.02732 15.35 0.42 Low Pressure Injection Check Valves SS 0.14099 0.00935 15.35 0.14 Low Pressure Injection Containment Isolation Valves SS 0.18261 0.01294 15.35 0.20 Decay Heat Decay Heat Class l Piping SS 0.23303 2.55 0.595 NUREG/CR-6260 Location Piping
L-17-070 Page 12 of 12 Ta ble 1: Reacto r Coolant System (RCS) Components Managed by the Fatigue Monitoring Program, cont.
NOTES (1) Location not exposed to RCS environment, therefore not subject to EAF.
(2) Not a RCS Pressure Boundary Component.
(3) Detailed elastic and elastic-plastic analyses completed to determine adjusted usage factors. For the elastic portion of the fatigue usage, the maximum Fen factor of 15.35 is conservatively applied . For the elastic-plastic portion, a detailed Fen calculation is performed.
(4) These nozzles are shown acceptable by satisfying requirements of paragraphs N-415.1 and N-450 of ASME Section III - 1968 Edition with Summer 1968 Addenda.
(5) These nozzles are shown acceptable by satisfying the requirements of paragraph N-415.l of ASME Section III - 1968 Edition with Summer 1968 Addenda (6) Covers are sealed using gaskets and seal welds were not used, therefore fatigue calculations not required.
(7) Only primary RCS Pressure Boundary locations with CUF greater than 0.052 are evaluated for EAF.
(8) EAF CUF using integrated strain rate Fen factors.
(9) CUFen determined using NUREG/CR-6909 rules. The strain amplitude is less than the strain amplitude threshold of 0.10% in all cases, Fen does not need to be applied.
(10) These locations were considered bounded by other locations. See response to Question 5.
Attachment 2 L-17-070 Regulatory Commitment List Page 1 of 1 The followi ng list identifies those actions committed to by FirstEnergy Nuclear Operating Company (FENOC) for the Davis-Besse Nuclear Power Station , Unit No. 1 (Davis-Besse) in this document. Any other actions discussed in the submittal represent intended or planned actions by FENOC. They are described only as information and are not Regulatory Commitments. Please notify Mr. Patrick McCloskey, Manager - Regulatory Compliance, at (419) 321-7274 , of any questions regarding this document or associated Regulatory Commitments .
Regulatory Commitment Due Date
- 1. FENOC will evaluate the limiting nickel-based April 28, 2017 alloy (NBA) and low-alloy steel (LAS) components for environmentally-assisted fatigue (EAF) for 60-year projected cycles. In addition ,
Davis-Besse plans to evaluate the remaining locations with EAF greater than 1.0 that were considered bounded by other locations. These locations were identified in FENOC Letter dated September 26 , 2016 (ADAMS Accession No.
ML16270A447), Table 1. FENOC will submit the results of the evaluations to the Nuclear Regulatory Commission .