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Category:Letter type:L
MONTHYEARL-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule L-24-032, Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report2024-07-15015 July 2024 Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report L-24-063, License Amendment Request to Remove the Table of Contents from the Technical Specifications2024-07-0808 July 2024 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-19019 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-214, Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2024-06-0505 June 2024 Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements L-24-019, Unit No.1 - Report of Facility Changes, Tests, and Experiments2024-05-22022 May 2024 Unit No.1 - Report of Facility Changes, Tests, and Experiments L-24-072, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 20232024-05-15015 May 2024 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023 L-24-111, Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-05-15015 May 2024 Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations L-24-031, Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage2024-05-14014 May 2024 Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage L-24-069, Occupational Radiation Exposure Report for Year 20232024-04-30030 April 2024 Occupational Radiation Exposure Report for Year 2023 L-24-018, Submittal of Core Operating Limits Report, Cycle 24, Revision 02024-04-16016 April 2024 Submittal of Core Operating Limits Report, Cycle 24, Revision 0 L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee L-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-22-194, 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-22-098, Withdrawal of Proposed Inservice Inspection Alternative RR-A22022-06-22022 June 2022 Withdrawal of Proposed Inservice Inspection Alternative RR-A2 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-22-136, Steam Generator Tube Circumferential Crack Report - Spring 2022 Refueling Outage2022-06-0707 June 2022 Steam Generator Tube Circumferential Crack Report - Spring 2022 Refueling Outage 2024-08-27
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule 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 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) 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 ML21088A3442021-03-29029 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 2024-08-15
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FENOC- Davis-8esseNuclear Pawer Station 5501N. StateRautaZ FirctErreryy NuclearOpnting hmpany Qak Harboc Ohio 43449 December9, 2016 L-16-323 10cFR50.54(D ATTN: DocumentControlDesk U.S,NuclearRegulatory Commission 11555Rockville Pike Rockville,MD 2ABS?
SUBJECT:
Davis-Besse NuclearPowerStation DocketNo.50-346,LicenseNo. NpF-3 ear-I=e[q Iisk Force(NTTH Reviewof tnsiontstrq (CACNos.MF3728and MF523g)
On March12,2A12,the NuclearRegulatory Commission (NRC)issueda Requestfor lformation per 10 CFR 50,54(0(Reference1) to all powerreactorlicensees.
Enclosure1, ltem (9) of the 50.54(f)letterrequestedaddresseesto providelimited sgoPespentfuel pool(SFP)evaluations.By letterdatedOc'tober 27,2015 (Refepnce2), the NRCtransmittedfinalseismicinfonnationrequesttables,which identified thatFirstEnergy NuclearOperatingGompany{FENOC)is to conducta limited scopeSFPevaluationfor Davis-BesseNuclearPowerStation(DBNPS).By Reference3, NuclearEnergyInstitute(NEl)submittedan ElectricPowerResearch fnstitute(EPRf)reportentitled,SerbmicEvaluationGuidanceSpenf Fuel PaolIntegrity Evaluation(EPRI3002007148) (Reference4), for NRCreviewand endo6ement.ltnC endorsement was provided by ReferenceS.
EPRI3002007148 providescriteriafor evaluatingthe seismicadequacyof a SFPto the reevaluated groundmotionresponsespectrum(GMRS)hazardlevels. Thisreport suppfementsthe guidancein the SeismicEvatuationGuidance,Screening,Prioritization and lmplementatianDefals (SPID)for the Resolutionof FukushimaNear-TermTask Force Recammendation 2.1: Ser.smic(Reference8) reportfor plantswherethe GMRS peakspectralacceleration is lessthanor equalto 0.8g. Section3.3of EPRl 3002007148lists the parametersto be verifiedto confirmthatthe resultsof the report are applicable to DBNPS,andthatthe DBNPSSFP is seismically adequatein accordance withNTTF2.1 Seismicevaluation criteria.
Davis-Besse NuclearPowerStation L-16-323 Page2 The attachmentto this letterprovidesthe datafor DBNPSthat confirmsapplicabilityof the EPRI3002007148 criteria,confirmsthatthe SFP is seismically adequate,and providesthe requestedinformationin responseto ltem (9) of the 50.54(f)letter associated with NTTFRecommendation 2.1 Seismicevaluation criteria.
Thereare no new regulatory commitments containedin this letterandno revisionsto existingregulatory commitments.lf thereare any questionsor if additionalinfonnation is Pquired,pleasecontactMr.ThomasA. LenE,-Manager - FleetLicensing, at 330-315S810.
I declareunderpenaltyof perjurythatthe foregoingis trueandcorrect.Executedon Decemberq , 2016.
Perfornance lmprovement Attachment Site-SpecificSpentFuelPoofCriteriafor Davis-BesseNuclearPowerStation
References:
- 1. NRC Lefter,Requestfor Information Pursuantto Title10 of the Codeof Federal Regulations 50.54(f)RegardingRecommendations 2.1, 2.3,and 9.3,of the Near-TermTaskForceReviewof Insightsfromthe FukushimaDalichiAccident,dated March12,2A12,Agencywide Documents Accessand Management System (ADAMS)AccessionNumberML12053A940.
- 2. NRCLetter,FinalDetermination of LicenseeSeismicProbabilistic Risk Assessments Underthe Requestfor Information Pursuantto Title10 of the Code of FederalRegulations 50.54(0RegardingRecommendation 2.1 "seisrnic"of the Near-TermTask ForceReviewof Insightsfromthe Fukushima Dai-ichiAccident, datedOctober27,2015,ADAMSAccessionNumberMLl5194A015.
- 3. NEI Letter,Requestfor Endorsement of Seismic Evaluation Guidance:SpenfFuel PoolIntegrityEvaluation(EPRI 3002007148), datedFebruary23,2A16,ADAMS AccessionNumberMLIO05SA01 7.
- 4. EPRf Report3002007148,SelsmicEvaluatianGuidanceSpanfFuetPool Integrity Evaluation,February2016,ADAMSAccessionNumberML16055A021.
Davis-Besse NuclearPowerStation L-16-323 Page3
- 5. NRCLetter,Endorsement of ElectricPowerResearchInstituteReport 3002007148, "SeismicEvaluationGuidance:SpentFuelPoolIntegrity Evaluation,"datedMarch17, 2016,ADAMSAccession NumberML15350A158.
6 . FENOCLetter,FirstEnergy NuclearOperating Company (FENOC)SeismicHazard andScreening Report(CEUSSites),Response to NRCRequestfor Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1of the Near-Term TaskForce(NTTF)Reviewof Insightsfromthe Fukushima Dai-ichiAccident, datedMarch31,2014,ADAMSAccessionNumberML14092A203.
7 . NRCLetter,Davis-Besse NuclearPowerStation,Unit1 - StaffAssessment of lnformation ProvidedPursuantto Title10 of the Codeof FederalRegulations Part 50, Section50.54(0,SeismicHazardReevaluations for Recommendation 2.1 of the Near-Term TaskForceReviewof Insightsfromthe Fukushima Dai-ichi Accident(TACNo.MF3728), datedAugust25,2015,ADAMSAccessionNumber M115230A289.
8 . EPRIReport1025287,SeismicEvaluationGuidance,Screening,Prioritization and lmplementationDetailsISPID]for the Resolution of FukushimaNear-TermTask ForceRecommendation 2.1: Seismic,November2012,ADAMSAccession NumberM112333A170.
9 . FENOCLetter,FirstEnergy NuclearOperating Company(FENOC)Expedited SeismicEvaluation Process(ESEP)Reports,Response to NRCRequestfor Information Pursuantto 10 CFR50.54(f)Regarding Recommendation 2.1of the Near-Term TaskForce(NTTF)Reviewof Insightsfromthe Fukushima Dai-ichi Accident,datedDecember 19,2014,ADAMS Accession Number ML14353A059.
1 0 . NRCLetter,Davis-Besse NuclearPowerStation,Unit1 - StaffReviewof Interim EvafuationAssociated withReevaluated SeismicHazardlmplementing Near-Term TaskForceRecommendation2.l (TACNo.MF5238), datedOctober19,2015, ADAMSAccessionNumberML15273A237.
cc: Director, Officeof NuclearReactorRegulation (NRR)
NRCRegionlll Administrator NRCResidentInspector NRRProjectManager UtilityRadiological SafetyBoard
ATTACHMENT FirstEnergy NuclearOperating Company NuclearPowerStation Davis-Besse DocketNo.50-346 LicenseNo.NPF-3 Nuclear SpentFuelPoolCriteriafor Davis-Besse Site-Specific PowerStation
Attachment L-16-323 Page1 of 3 The 50.54(f)letter(Reference 1) requested that,in conjunction withthe response to NTTF Recommendation 2.1,a seismicevaluation be madeof the SFP. Morespecifically, plants wereaskedto consider"allseismically inducedfailuresthatcan lead to draining of the SFP."Suchan evaluation wouldbe neededfor anyplantin whichthegroundmotion responsespectrum(GMRS)exceedsthe safeshutdownearthquake (SSE)in the 1 to 10 Hz frequencyrange.Thestaffconfirmed throughReferences 2 and7 thatthe GMRS exceedsthe SSEandconcluded thata SFPevaluation is meritedfor the FirstEnergy NuclearOperating Company(FENOC,the licensee) Davis-Besse NuclearPowerStation (DBNPS).By letterdatedMarch17,2016(Reference 5),the staffdetermined thatEPRI 3002007148 was an acceptable approach for performing SFPevaluations for plants wherethe peakspectralacceleration is lessthanor equalto 0.89.
Thetablebelowliststhe criteriafromSection3.3of EPRI3002007148 alongwithdatafor DBNPSthatconfirmsapplicability of the EPRI3002007148 criteriaandconfirmsthatthe SFPis seismically adequateandcan retainadequatewaterinventory for 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />sin accordance withNTTF2.1 Seismicevaluation criteria.
SFPCriteriafrom EPRl3O02007t48 Sitepecific Data,,,
Site Parameters GMRSpeak 1 . Thesite-specific TheGMRSpeakspectralacceleration in NTTF2.1 spectralacceleration at any SeismicHazardandScreeningReportDavis-Besse frequencyshouldbe lessthanor NuclearPowerStationOttawaCounty,Ohio(Reference equalto 0.89. 6), as acceptedby the NRCin Davis-Besse NuclearPower Station,Unit1 StaffAssessment of Information Provided Pursuantto Title10 of the Codeof FederalRegulations Part50,Section50.54(f), SeismicHazardReevaluations for Recommendation 2.1 of the Near-Term TaskForce Reviewof InsightsFromthe Fukushima Dai-ichi Accident (TACNo. MF3728)(Referen ce 7), hasbeensuperseded by the FirstEnergy NuclearOperating Company(FENOC)
Expedited SeismicEvaluation Process(ESEP)Reports, Response to NRCRequestfor Information Pursuant to 10 CFR50.54(0Regarding Recommendation2.l of the Near-Term TaskForce(NTTF)Reviewof Insightsfromthe Fukushima Dai-ichi Accident(Reference 9), as accepted by the NRCin letterDavis-Besse NuclearPowerStation, Unit1 - StaffReviewof InterimEvaluation Associated with Reevaluated SeismicHazardlmplementing Near-Term TaskForceRecommendation 2.1 (Reference 10),is 0.549, whichis 0.89;therefore, this criterion is met.
StructuralParameters
- 2. Thestructure housingthe SFP TheSFPis housedin theauxiliary building, whichis shouldbe designed usingan SSE seismically designed to the siteSSEwitha PGAof 0.159 witha peak ground acceleration perUSARSection3.2.1.TheDBNPSPGAis greaterthan (PGA)of at least0.19. 0.1g;therefore, thiscriterionis met.
Attachment L-16-323 Page2 of 3 SFPGriteriafrom EPRI3002007148 Sitepecific Data
- 3. Thestructural loadpathto the SFP TheSFPis housedin Auxiliary Building, Area8, whichis shouldconsistof somecombination constructed of steelframing,reinforced concrete(RC) of reinforced concreteshearwall walls,roofsandfloors[Ref.Drawings C-202andC-230].
elements,reinforced concreteframe Theexteriorwallsof the SFPare5 ft. 6 in.thickRCwalls.
elements, post-tensioned concrete TheSFPflooris a 5 ft. thickRCslab. Thestructural load elementsand/orstructural steel pathfromthe SFPto the foundationconsistsof 5 ft 6 in.
frameelements. thickRCwallsat the boundary of the poolandalsoby several2 ft. to 3 ft. thickintermediate bearingwallsof 13ft. 6 in. height.Thefoundation is a 3 ft. thickRC mat slabthatbearson bedrock.Therefore, thiscriterionis met for DBNPS.
- 4. TheSFPstructure shouldbe TheSFPstructure is includedin the DBNPSStructures included in theCivillnspection Monitoring Programin accordance with10 CFR50.65, Programperformed in accordance whichmonitors the performance or condition of structures, withMaintenance Rule. systems, or components (SSCs)in a mannersufficient to providereasonable assurance that these SSCs are capableof fulfilling theirintended functions [Ref.
Procedure EN-DP-O15111. Therefore, thiscriterionis met for DBNPS.
Non-StructuralParameters
- 5. To confirmapplicability of the piping All pipingattached to the SFPis seismically qualifiedto evaluation in Section3.2of EPRI SSEin accordance withUSARSection9.1.3.11, except 3002007148, pipingattached to the fivesmallborelinesandan overfillline. Theselinesare SFPup to thefirstvalveshouldhave locatedapproximately 20 ft. abovethe top of activefuel beenevaluated for the SSE. and provideapproximately 147hoursbeforeuncovering the spentfuelandapproximately 178hoursbeforethetop 113of the spentfuelpoolis uncovered perABSConsulting calculation 2734296-C-1 34, Revision 0.
Section3.2of EPRI3002007148 is focusedon the rapid drainingof the SFPsuchthatthereis an uncovering of morethan 113of the spentfuelheightwithin72 hours.
Withgreaterthan72 hoursavailable, thereis no concern of rapiddraindown;therefore, the intent of thiscriterion is metfor DBNPS.
Attachment L-16-323 Page3 of 3 SFPCriteriafrom',EPRI3002007148 Sitepecific Data
- 6. Anti-siphoning devicesshouldbe No anti-siphoning devicesareused. Pipingdesignis such installedon anypipingthatcould to siphonthe spentfuelpoolwater thatit is not possible leadto siphoning waterfromthe leveldownas the resultof a failedpipeor component to a SFP. In addition, for anycases waterlevelbelowI ft. 6 in. abovethetop of the spent fuel whereactiveanti-siphoning devices rack[Ref.USARSection9.1.2.3].Thislevelprovides areattached to 2-inchor smaller adequate shieldingandcoolingof the spentfuelsystem.
pipingandhaveextremely large Sincethe pipingof the SFPcoolingsystemcannotleadto extendedoperators, the valves rapiddraindowndueto siphoning; thiscriterionis metfor shouldbe walkeddownto confirm DBNPS.
adequatelateralsupport. devicesareattached to As described, no anti-siphoning Z-in.or smaller pipingwith extremely large extended operators; thiscriterionis satisfiedfor DBNPS.
therefore,
- 7. To confirmapplicability of the The DBNPSSFPis partof multipleinterconnected pools, sloshingevaluation in Section3.2of alongwiththefueltransfer pool andthe cask pit.
EPRI3002007148, themaximum Combined, thesepoolshavea lengthof lessthan20 ft.,a SFPhorizontal dimension (lengthor widthlessthan53 ft.,anda depthof 39ft. 6 in. basedon width)shouldbe lessthan 125ft., drawingC-0247;therefore, thiscriterionis met.
the SFPdepthshouldbe greater The DBNPSGMRSmaximumspectralacceleration in the than36 ft, andthe GMRSpeakSa frequency rangelessthan0.3 Hz is 0.029fromthe shouldbe <0.19at frequencies equal FirstEnergy NuclearOperating Company(FENOC) to or lessthan0.3 Hz. Expedited SeismicEvaluation Process(ESEP)Reports, Response to NRCRequestfor Information pursuant to 10 CFR50.54(0Regarding Recommendation 2.1of the Near-TermTaskForce(NTTF)Reviewof Insightsfromthe Fukushima Accident(Reference Dai-ichi 9),whichis less than0.19;therefore, thiscriterionis met.
- 8. To confirmapplicability of the Thesurfaceareaof the DBNPSSFPproperis 1,056.96ft2 evaporation lossevaluation in basedon drawingC-0247andUSARSection9.1.3.3, Section3.2of EPRI3002007148, whichis greaterthan500ft2;andlicensedreactorthermal the SFPsurfaceareashouldbe powerfor DBNPSis 2,817MWt[Ref.USARSection1] per greaterthan500ft2andthe licensed unit,whichis lessthan4,000MWtperunit;therefore, reactorcorethermalpowershould thesecriteriaare met.
be lessthan4,000MWtperunit.