Letter Sequence Supplement |
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EPID:L-2019-LLA-0011, License Amendment Request - Proposed License and Associated Technical Specification Changes for Permanently Defueled Condition (Withdrawn, Closed) |
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MONTHYEARL-18-254, License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition2018-10-22022 October 2018 License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition Project stage: Request ML18320A1272018-11-16016 November 2018 NRR E-mail Capture - Davis-Besse LAR to Change TS Definitions and Administrative Controls for Permanently Defueled Conditions Project stage: Acceptance Review L-18-271, License Amendment Request - Proposed Post-Shutdown Emergency Plan2019-02-0505 February 2019 License Amendment Request - Proposed Post-Shutdown Emergency Plan Project stage: Request L-18-242, License Amendment Request - Proposed License and Associated Technical Specification Changes for Permanently Defueled Condition2019-02-0505 February 2019 License Amendment Request - Proposed License and Associated Technical Specification Changes for Permanently Defueled Condition Project stage: Request ML19043A6962019-02-0808 February 2019 NRR E-mail Capture - Davis-Besse License Amendment Request for the Post-Shutdown Emergency Plan Project stage: Acceptance Review L-19-062, Supplement to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1. Definitions, 5.0., Administrative Controls. for Permanently Defueled Condition2019-02-27027 February 2019 Supplement to License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1. Definitions, 5.0., Administrative Controls. for Permanently Defueled Condition Project stage: Supplement ML19073A1112019-03-14014 March 2019 NRR E-mail Capture - Davis-Besse - Acceptance of License Amendment Request for Permanently Defueled License and Technical Specifications Project stage: Acceptance Review L-19-100, Supplemental Information for the Proposed Post-Shutdown Emergency Plan License Amendment2019-04-10010 April 2019 Supplemental Information for the Proposed Post-Shutdown Emergency Plan License Amendment Project stage: Supplement L-19-150, Supplemental Information Regarding License Amendment Request for Permanently Defueled License and Technical Specifications2019-05-16016 May 2019 Supplemental Information Regarding License Amendment Request for Permanently Defueled License and Technical Specifications Project stage: Supplement ML19149A6202019-05-29029 May 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Approval of the Decommissioning Quality Assurance Program Project stage: Acceptance Review ML19162A3922019-06-11011 June 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request for Permanently Defueled Technical Specifications Project stage: RAI ML19164A1532019-06-13013 June 2019 NRR E-mail Capture - Davis-Besse Nuclear Power Station - Request for Additional Information Regarding License Amendment Request for Post-Shutdown Emergency Plan Project stage: RAI 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 Project stage: Response to RAI ML19179A1382019-06-28028 June 2019 NRR E-mail Capture - Davis-Besse - Request for Additional Information Regarding the Decommissioning Quality Assurance Program Project stage: RAI 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 Project stage: Supplement 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 Project stage: Response to RAI ML19212A1392019-08-0606 August 2019 Withdrawal of Licensing Actions Associated with the Permanent Shut Down of the Plant (Epids L-2018-LLA-0287, L-2019-LLA-0011, L-2019-LLA-0012, L-2019-LLE-0011, and L-2019-LLQ-0000) Project stage: Withdrawal ML19212A1352019-08-0606 August 2019 Federal Register Notice for Withdrawal of February 5, 2019, License Amendment Application for Post-Shutdown Emergency Plan Project stage: Withdrawal ML19212A1362019-08-0606 August 2019 Federal Register Notice for Withdrawal of February 5, 2019, License Amendment Application for Permanently Defueled Technical Specifications Project stage: Withdrawal ML19212A1372019-08-0606 August 2019 Federal Register Notice for Withdrawal of October 22, 2018, License Amendment Application Project stage: Withdrawal 2019-05-16
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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
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FENOC ~
5501 North State Route 2 FirstEnergy Nuclear Operating Com{J811y Oak Harbor, Ohio 43449 Mark B. Bezilla 419-321-7676 Vice President - Nuclear Fax: 419-321-7582 July 8, 2019 L-19-166 10 CFR 50.90 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 No. NPF-3 Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request for Proposed Post-Shutdown Emergency Plan (EPID L-2019-LLA-0011)
By application dated February 5, 2019 (Accession No. ML19036A524), as supplemented by letter dated April 10, 2019 (Accession No. ML19100A000),
FirstEnergy Nuclear Operating Company (FENOC) submitted a license amendment request for Davis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse). The proposed amendment would revise the Davis-Besse emergency plan for the post-shutdown and permanently defueled condition.
On June 13, 2019, the Nuclear Regulatory Commission (NRC) staff requested additional information to complete its review. The FENOC response is contained in Attachment 1. As a result of the FENOC response, Attachment 2 contains updates to the Proposed Post-Shutdown Emergency Plan.
There are no regulatory commitments included in this submittal. If there are any questions, or if additional information is required, please contact Mr. Thomas Lentz, Manager, FENOC Nuclear Licensing and Regulatory Affairs, at (330) 315-6810.
I declare under penalty of perjury that the foregoing is true and correct. Executed on July .../3_, 2019.
f!JU 1')
Sincerely, ,/l._1P
/J tdti _.1. ?//
f Mark B. Bezilla
Davis-Besse Nuclear Power Station, Unit No. 1 L-19-166 Page 2 Attachments:
- 1. Response to Request for Additional Information
- 2. Updated Proposed Post-Shutdown Emergency Plan cc: NRC Regional Administrator - Region Ill NRC Resident Inspector NRC Project Manager Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
Utility Radiological Safety Board
Attachment 1 L-19-166 Response to Request for Additional Information Page 1 of 2 The NRC staff's request for additional information is provided in bold text followed by the FENOC response.
Request for Additional Information (RAI) 1 The Technical Support Center (TSC) Engineering Manager is the only minimum staffing position required for TSC activation which will be retained with this proposed change. Section 5.4.1.b. "Technical Support Center (TSC)," of the proposed post-shutdown emergency plan (PSEP) states, in part:
TSC staff will assess facility conditions, and provide management and technical assistance to the Control Room, as required, to mitigate the effects of the emergency event. The TSC staff will analyze and track parameters relating to the technical [emergency action levels] EALs, and will advise the Emergency Director of the need to reclassify the emergency.
Section 7.2.1, "Technical Support Center (TSC)," of the proposed PSEP states:
"The TSC serves as the workplace for key [emergency response organization]
personnel who, during emergencies, assist the Control Room staff, perform accident assessment, and determine appropriate protective actions."
Explain how the TSC Engineering Manager can provide management and technical support to the control room personnel during emergency conditions without support from other TSC personnel.
Response
As shown on Tables 2.4-1 and 4.5-2 of the Post-Shutdown Emergency Plan (PSEP)
License Amendment Request (LAR), in addition to the TSC Engineering Manager, other augmented positions will respond to the TSC following an emergency declaration.
When the TSC is staffed with the TSC Engineering Manager, the Emergency Plant Manager, the Emergency Assistant Plant Manager (who may report either to the control room or the TSC), and the Emergency RP Manager, the capability exists to assess facility conditions, provide management and technical support to the control room, and mitigate the effects of the emergency.
Table 5-1. B of the Proposed Post-Shutdown Emergency Plan, which was included in the LAR, identified the TSC Engineering Manager and the Emergency Assistant Plant Manager as positions that respond upon declaration of an Alert or higher emergency classification. To ensure the TSC minimum staff can provide management and L-19-166 Page 2 of 2 technical support, the Proposed Post-Shutdown Emergency Plan is revised, as provided in Attachment 2, to add the Emergency Plant Manager and the Emergency RP Manager as minimum staff required for TSC activation with the facility in the permanently shutdown and defueled condition.
RAI 2
Currently, Table 5-1.8 of the emergency plan lists the NRC Liaison as required minimum staff for an alert or higher emergency classification. LAR Section 4.5.2.3, "Emergency Operations Facility Augmenting Positions," states, in part:
The proposed staffing changes includes the elimination of the NRC Liaison position. The primary duty of the NRC Liaison is to establish and maintain communication with the NRC. The Technical Liaison -
EOF [Emergency Operations Facility] Communicator, located in the EOF, is assigned these duties in the post-shutdown emergency plan.
However, the Technical Liaison - EOF Communicator is not listed as minimum staff in the proposed revision to Table 5-1.8.
Explain why the Technical Liaison - EOF Communicator does not need to be a required minimum staff position given that this position will assume the duties of the NRC Liaison. Explain why the current basis for including the NRC Liaison as a minimum staff position is not valid for the permanently shutdown condition.
Response
Table 5-1.B of the Proposed Post-Shutdown Emergency Plan is revised, as provided in , to identify the Technical Liaison - EOF Communicator as minimum staff required for EOF activation with the facility in the permanently shutdown and defueled condition. Since the Technical Liaison - EOF Communicator is assuming the tasks of the NRC Liaison position and will be a minimum staffing position, the basis of the NRC Liaison being a minimum staffing will apply to the Technical Liaison - EOF Communicator.
Attachment 2 L-19-166 Updated Proposed Post-Shutdown Emergency Plan (Four pages follow)
Updated Mark-up Page of the Proposed Post-Shutdown Emergency Plan (One page follows)
5-36 DBNPS Post-Shutdown Emergency Plan Revision ~TBD TABLE 5-1 MANPOWER, LOCATION, AND RESPONSE CON SIDERA TIONS FOR EMERGENCIES Page 2 of2 B. AUGMENTED EMERGENCY RESPONSE STAFFING REQUIREMENTS ALERT, SITE AREA EMERGENCY, UNUSUAL EVENT GENERAL EMERGENCY PERSONNEL TIME PERSONNEL TIME CONTROL ROOM CONTROL ROOM fmergency Assistant Plant Manager (1)~ Alerted Emergency Assistant Plant Manager (1r Nonnal Hours:
30minutes Off Hours:
60 minutes QPERATIONS SUPPORT CENTER OPERATIONS SUPPORT QENTEB OSC Manager (1) Alerted OSCManager (1)
OSC RP Coordinator (1) OSC RP Coordinator (1) Normal Hours:
Mechanical Maintenance (21) 30 minutes I IA6tFUA'l8Rt & G8RtFGI&
Electrical Maintenance Add (2)
(~1)
Total Off Hours:
RP Technician (1) (2) 60minutes Chemi&t,y +8GRRieiaR EO} ~
RP Technician (3j) (iID 1-2 hours GheFRi&tf:'j ::i:eshRisiaA ~ ~
TECHNl~AL §UPPORT CENTER TECHNICAb SUPPQRT CENTER As Required:
TSC Engineering Manager (1) Alerted TSC Engineering Manager (1) Normal Hours:
CeF8/JheFmal MydFauliG EngiR88F (-11 30minute&
fimerg1mcx Plaal Menager ill Off Hours:
EmergenS:)! RP Manager ill 60minutes TSC l&C Engineer ~
TSC Electrical Engineer µ.} 1-2 hours TSC Mechanical Engineer fB Call inas necessarv EMERGENCY OPERATIONS FACILITY EMERGENCY OPERATIONS FACIUTY As Required:
Emergency Director (1) Alerted Emergency Offsite Manager {1) Normal Hours:
Emergency Offsite Manager (1) Dose Assessment Coordinator {1) 60minutes Emergency Planning Advisor (1) Off Hours:
60 minutes RMTs {3) 30-60 minutes Emergency Director (1)
I NRC btai&eATechnir;!!I Liaison - EOF Communicator State/County Communicator (1)
{1) 1-2 hours NOTES : I. All time requirements ere based on optimum response conditions.
- 2. Figure 5-2, Emergency Response Organization, depicts functional levels beyond these augmented staffing requirements.
3 The Emergency Assistant Plant Manager may respond to the TSC
Updated Clean Page of the Proposed Post-Shutdown Emergency Plan (One page follows)
5-36 DBNPS Post-Shutdown Emergency Plan Revision TBD TABLE 5-1 MANPOWER, LOCATION, AND RESPONSE CONSIDERATIONS FOR EMERGENCIES Page 2 of2 B. AUGMENTED EMERGENCY RESPONSE STAFFING REQUIREMENTS ALERT, SITE AREA EMERGENCY, UNUSUAL EVENT GENERAL EMERGENCY PERSONNEL TIME PERSONNEL TJME CONTROL ROOM CONTROL ROOM Emergency Assistant Plant Manager (1 )3 Alerted Emergency Assistant Plant Manager (1)3 Normal Hours:
30 minutes Off Hours:
60 minutes OPERATIONS ~UPPORT CENTER OPERATIONS SUPPORI CENTl;B OSC Manager (1 ) Alerted OSCManager (1) osc RP Coordinator (1} OSC RP Coordinator (1) Normal Hours:
Mechanical Maintenance (1) 30 minutes Electrical Maintenance (1)
Add Total Off Hours:
RP Technician (1) (2) 60 minutes RP Technician (1) (3) 1-2 hours TECHNICAL SUPPORT CENTE;:B TECl:fNl~AL ~uePORT CENTER As Required:
TSC Engineering Manager (1) Alerted TSC Engineering Manager (1) Nonnal Hours:
30 minutes Emergency Plant Manager (1) Off Hours:
Emergency RP Manager (1) 60 minutes TSC l&C Enginee, Call in as TSC Electrical Engineer 1-2 hours necessary TSC Mechanical Engineer EMERGENCY OPERATIO~S FAClblTY EMERGENCY Qf,RATION§ FACIU!X As Required:
Emergency Director (1) Alerted Emergency Offsite Manager (1) Normal Hours:
Emergency Offsite Manager (1) Dose Assessment Coordinator (1) 60 minutes Emergency Planning Advisor (1) Off Hours:
60minutes RMTs (3) 30-60 minutes Emergency Director (1)
Technical Liaison - EOF (1) 1-2 hours Communicator State/County Communicator (1)
NOTES: I. All time requirements are based on optimum response conditions.
- 2. Figure 5-2, Emergency Response Organization, depicts functional levels beyond these augmented staffing requirements.
- 3. The Emergency Assistant Plant Manager may respond to the TSC.