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MONTHYEARL-16-034, Distribution Notice for License Amendment Request to Adopt NFPA Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition).2016-02-0202 February 2016 Distribution Notice for License Amendment Request to Adopt NFPA Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition). Project stage: Request ML16047A1452016-02-22022 February 2016 Supplemental Information Needed for Acceptance of License Amendment Request to Adopt National Fire Protection Associated Standard 805 Project stage: Acceptance Review 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 Project stage: Supplement ML16074A1232016-03-15015 March 2016 Acceptance of License Amendment Request to Adopt National Fire Protection Associated Standard 805 Project stage: Acceptance Review L-16-088, Conservatisms in the Fire Probabilistic Risk Analysis2016-03-17017 March 2016 Conservatisms in the Fire Probabilistic Risk Analysis Project stage: Request ML16075A1112016-03-23023 March 2016 Online Reference Portal for License Amendment Request to Adopt National Fire Protection Associated Standard 805 Project stage: Other ML16126A2362016-05-0505 May 2016 NRR E-mail Capture - Davis-Besse NFPA 805 Portal Project stage: Other ML16130A7182016-05-0909 May 2016 NRR E-mail Capture - Davis-Besse NFPA 805 Portal Project stage: Other L-16-170, Online Reference Portal for Review of National Fire Protection Association (NFPA) Standard 805 License Amendment Request2016-05-31031 May 2016 Online Reference Portal for Review of National Fire Protection Association (NFPA) Standard 805 License Amendment Request Project stage: Request ML16172A0312016-06-20020 June 2016 NRR E-mail Capture - Davis-Besse NFPA 805 Portal Project stage: Other ML16190A0752016-07-0808 July 2016 NRR E-mail Capture - Davis-Besse NFPA 805 Portal Project stage: Other ML16201A0172016-07-20020 July 2016 Regulatory Audit in Support of the License Amendment Request to Implement Risk-Informed, Performance-Based, Fire Protection Program as Allowed by Title 10 CFR, Paragraph 50.48(c) Project stage: Other L-16-232, Correction of Fire Probabilistic Risk Analysis (PRA) Results2016-07-28028 July 2016 Correction of Fire Probabilistic Risk Analysis (PRA) Results Project stage: Other ML16256A0662016-10-18018 October 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Associated Standard 805 Project stage: RAI 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 Project stage: Response to RAI 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 Project stage: Response to RAI ML17100A1732017-04-19019 April 2017 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Associated Standard 805 Project stage: RAI 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 Project stage: Response to RAI ML17257A1402017-09-14014 September 2017 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805 Project stage: RAI ML17258A1462017-09-20020 September 2017 Summary of September 12, 2017, Meeting with Firstenergy Nuclear Operating Company Regarding Its Licensing Amendment Request to Adopt National Fire Protection Association Standard 805 at Davis-Besse Nuclear Power Station, Unit No. 1 Project stage: Meeting 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 Project stage: Supplement ML17355A3722017-12-21021 December 2017 NRR E-mail Capture - Davis-Besse Nuclear Power Station, Unit No. 1 - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805 Project stage: RAI 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 Project stage: Supplement ML18201A4122018-07-19019 July 2018 NRR E-mail Capture - Davis-Besse - Request for Additional Information Regarding License Amendment Request to Adopt NFPA 805 Project stage: RAI L-18-249, Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052018-11-20020 November 2018 Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 Project stage: Supplement ML19106A2512019-04-16016 April 2019 NRR E-mail Capture - Davis-Besse - Proposed License Condition and Draft Safety Evaluation for the License Amendment Request to Adopt NFPA 805 Project stage: Draft Approval ML19100A3062019-06-21021 June 2019 Issuance of Amendment No. 298 to Adopt National Fire Protection Association Standard 805 Project stage: Approval 2016-07-28
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Category:Fire Protection Plan
MONTHYEARML20302A3102020-09-25025 September 2020 9 to Fire Hazards Analysis Report, Section 8, Operating Specifications ML20302A2972020-09-25025 September 2020 9 to Fire Hazards Analysis Report, Section 4, Appendix 4, Section Iii.G. Evaluation and Fire Hazard Evaluation, Part 2 of 2 ML20302A2982020-09-25025 September 2020 9 to Fire Hazards Analysis Report, Appendix B-2, Circuit/Subcomponent Location Summary by Fire Area ML20302A3002020-09-25025 September 2020 9 to Fire Hazards Analysis Report, Appendix C-2, Associated Circuit Location Summary by Fire Area ML20302A3012020-09-25025 September 2020 9 to Fire Hazards Analysis Report, Section 9, Fire Protection Safety Analysis ML20302A3032020-09-25025 September 2020 9 to Fire Hazards Analysis Report, Appendix C-1, Associated Circuit Location Summary by Power Source ML20302A3042020-09-25025 September 2020 9 to Fire Hazards Analysis Report, Section 1, Introduction and Summary ML20302A3062020-09-25025 September 2020 9 to Fire Hazards Analysis, List of Effective Pages ML20302A3072020-09-25025 September 2020 9 to Fire Hazards Analysis Report, Section 5, Associated Circuits ML20302A3082020-09-25025 September 2020 9 to Fire Hazards Analysis Report, Appendix C-3, Breaker/Fuse Coordination Summary ML20302A3112020-09-25025 September 2020 9 to Fire Hazards Analysis Report, Section 4, Appendix 4, Section Iii.G. Evaluation and Fire Hazard Evaluation, Part 1 of 2 ML20302A3122020-09-25025 September 2020 9 to Fire Hazards Analysis Report, Appendix a, Safe Shutdown Components List ML20302A3142020-09-25025 September 2020 9 to Fire Hazards Analysis Report, Section 2, References ML20302A3152020-09-25025 September 2020 9 to Fire Hazards Analysis Report, Appendix B-1, Circuit/Component Location Summary by System ML20302A3162020-09-25025 September 2020 9 to Fire Hazards Analysis Report, Section 6, Emergency Lighting and Communications ML20302A3172020-09-25025 September 2020 9 to Fire Hazards Analysis Report, Section 7, Oil Collection System for Reactor Coolant Pumps ML20302A3222020-09-25025 September 2020 9 to Fire Hazards Analysis Report, Section 3, Safe Shutdown Systems, Components and Circuits ML20302A3232020-09-25025 September 2020 9 to Fire Hazards Analysis Report, Appendix D, BTP-APCSB 9.5-1, Appendix a Response L-18-249, Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052018-11-20020 November 2018 Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 ML0426101352004-05-12012 May 2004 Email, J. Lara to J. Strasma, Reporter Questions Relating to Davis-Besse Fire Protection Issues 2020-09-25
[Table view] 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:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-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 CP-202300157, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-14014 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML22277A6012022-10-14014 October 2022 Issuance of Amendment No. 304 Revising the Design Basis for the Shield Building Containment Structure L-20-163, License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications2020-07-27027 July 2020 License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, Into the Facility Technical Specifications L-20-188, ISFSI, Davis-Besse Unit 1, and ISFSI, Perry, Unit 1, and ISFSI, Decommissioning Trust: Amendments to Decommissioning Trust Agreements to Update Company Names2020-06-26026 June 2020 ISFSI, Davis-Besse Unit 1, and ISFSI, Perry, Unit 1, and ISFSI, Decommissioning Trust: Amendments to Decommissioning Trust Agreements to Update Company Names L-19-233, License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b2019-11-14014 November 2019 License Amendment Request for Adoption of TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5b L-19-219, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-09-25025 September 2019 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-19-200, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-08-29029 August 2019 ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML19130A1952019-05-0808 May 2019 Letter - FEMA Review of Proposed Changes to DBNPS Emergency Plan for Permanently Defueled Condition L-19-073, ISFSI, Davis-Besse, Unit 1, ISFSI, and Perry, Unit 1, ISFSI - Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-04-26026 April 2019 ISFSI, Davis-Besse, Unit 1, ISFSI, and Perry, Unit 1, ISFSI - Application for Order Consenting to Transfer of Licenses and Conforming License Amendments 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 L-18-271, License Amendment Request - Proposed Post-Shutdown Emergency Plan2019-02-0505 February 2019 License Amendment Request - Proposed Post-Shutdown Emergency Plan 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 L-18-249, Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 8052018-11-20020 November 2018 Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 L-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 L-18-203, Supplemental Information Regarding a Pending Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement2018-08-23023 August 2018 Supplemental Information Regarding a Pending Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement L-17-159, Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement2017-05-18018 May 2017 Administrative License Amendment Request to Reflect a Change in the Entity Providing a $400 Million Support Agreement L-17-026, Regarding MRP-227-A Applicant Action Item 8: Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years2017-01-23023 January 2017 Regarding MRP-227-A Applicant Action Item 8: Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years L-16-304, Supplement to Request for License Amendment Approval Delay2016-10-25025 October 2016 Supplement to Request for License Amendment Approval Delay L-16-020, Request for Licensing Action to Revise the Emergency Plan2016-02-17017 February 2016 Request for Licensing Action to Revise the Emergency Plan L-16-030, Request for an Amendment to Revise Technical Specification 5.5.3, Radioactive Effluents Controls Program.2016-02-0909 February 2016 Request for an Amendment to Revise Technical Specification 5.5.3, Radioactive Effluents Controls Program. L-15-341, License Amendment Request to Modify Technical Specifications 5.3.12015-11-19019 November 2015 License Amendment Request to Modify Technical Specifications 5.3.1 L-15-309, License Renewal Application Amendment No. 602015-10-0606 October 2015 License Renewal Application Amendment No. 60 L-15-214, License Renewal Application Amendment No. 59 - Annual Update2015-06-29029 June 2015 License Renewal Application Amendment No. 59 - Annual Update L-15-192, Supplemental Information for the Review of the License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 582015-06-12012 June 2015 Supplemental Information for the Review of the License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 58 L-15-166, Supplemental Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, Reactor Vessel Internals Inspection Plan (TAC No. ME4640) and License Renewal Application Amendment No. 562015-05-20020 May 2015 Supplemental Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, Reactor Vessel Internals Inspection Plan (TAC No. ME4640) and License Renewal Application Amendment No. 56 L-15-120, Notification of Completion of License Renewal Commitments Related to the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application and License Renewal Application Amendment No. 552015-04-0808 April 2015 Notification of Completion of License Renewal Commitments Related to the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application and License Renewal Application Amendment No. 55 L-15-117, License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage and Frequency Surveillance Requirements2015-04-0101 April 2015 License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage and Frequency Surveillance Requirements L-14-407, Request to Amend Technical Specification 5.5.15, Containment Leakage Rate Testing Program2014-12-19019 December 2014 Request to Amend Technical Specification 5.5.15, Containment Leakage Rate Testing Program L-14-297, Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 532014-09-16016 September 2014 Reply to Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application (TAC No. ME4640) and License Renewal Application Amendment No. 53 L-14-206, License Renewal Application Amendment No. 50 - Annual Update2014-06-23023 June 2014 License Renewal Application Amendment No. 50 - Annual Update L-14-085, License Renewal Application (TAC No. ME4640) Amendment No. 482014-02-19019 February 2014 License Renewal Application (TAC No. ME4640) Amendment No. 48 L-13-330, License Renewal Application Amendment No. 46 - Annual Update2013-09-20020 September 2013 License Renewal Application Amendment No. 46 - Annual Update L-12-397, Request to Amend the Price-Anderson Indemnities and Notification of a Name Change to Documents of Regulatory Interest2013-02-19019 February 2013 Request to Amend the Price-Anderson Indemnities and Notification of a Name Change to Documents of Regulatory Interest L-13-040, License Amendment Request for Proposed Revision of Technical Specification (TS) 3.4.17, Steam Generator (SG) Tube Integrity; TS 3.7.18, Steam Generator Level; TS 5.5.8, Steam Generator Program; and TS 5.6.6..2013-01-18018 January 2013 License Amendment Request for Proposed Revision of Technical Specification (TS) 3.4.17, Steam Generator (SG) Tube Integrity; TS 3.7.18, Steam Generator Level; TS 5.5.8, Steam Generator Program; and TS 5.6.6.. ML12229A1392012-08-0909 August 2012 License Renewal Application Amendment 30 - Annual Update L-12-070, License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels2012-05-23023 May 2012 License Amendment Request to Revise Emergency Diesel Generator Minimum Voltage Surveillance Requirements, and Add Figure Axis Labels ML1126402462011-09-20020 September 2011 License Amendment Request to Change the Name of an Owner Licensee to Firstenergy Nuclear Generation, LLC L-11-097, License Amendment Request to Modify the Special Visual Inspection Requirements of Technical Specification 5.5.8, Steam Generator (SG) Program.2011-05-20020 May 2011 License Amendment Request to Modify the Special Visual Inspection Requirements of Technical Specification 5.5.8, Steam Generator (SG) Program. ML1024505632010-08-31031 August 2010 Enclosures to Davis-Besse, Unit 1, Letter L-10-221, License Renewal Application, Section 3.5 Through Appendix E, References 2.3-1 L-10-221, Enclosures to Davis-Besse, Unit 1, Letter L-10-221, License Renewal Application, Appendix E, Section 2.4 Through References E.112010-08-31031 August 2010 Enclosures to Davis-Besse, Unit 1, Letter L-10-221, License Renewal Application, Appendix E, Section 2.4 Through References E.11 L-09-143, License Amendment Request to Exclude Source Range Neutron Flux Instrument Channel Preamplifier from Channel Calibration Requirements of Technical Specification 3.3.9, Source Range Neutron Flux, & TS 3.9.2, Nuclear Instrumentation.2009-06-0202 June 2009 License Amendment Request to Exclude Source Range Neutron Flux Instrument Channel Preamplifier from Channel Calibration Requirements of Technical Specification 3.3.9, Source Range Neutron Flux, & TS 3.9.2, Nuclear Instrumentation. L-09-072, License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr.2009-04-15015 April 2009 License Amendment Request to Incorporate the Use of Alternate Methodologies for Development of Reactor Pressure Vessel Pressure-Temperature Limit Curves and Request for Exemption from Certain Requirements Contained in 10 Cfr. L-09-025, ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.2009-03-25025 March 2009 ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. L-08-159, Supplement to License Amendment Request: Conversion of Current Technical Specifications (CTS) to Improved Technical Specifications (ITS) - Volumes 5, 6, 7, 9, 11, and 15, TAC No. MD63982008-05-16016 May 2008 Supplement to License Amendment Request: Conversion of Current Technical Specifications (CTS) to Improved Technical Specifications (ITS) - Volumes 5, 6, 7, 9, 11, and 15, TAC No. MD6398 ML0814804712008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 15, (Revision 1), Chapter 4.0 - Design Features ML0814804692008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 11, (Revision 1), Section 3.6 - Containment Systems ML0814804682008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 9, (Revision 1), Section 3.4 - Reactor Coolant System (RCS) ML0814804672008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 7, (Revision 1), Section 3.2 - Power Distribution Limits ML0814804662008-05-16016 May 2008 Improved Technical Specification Conversion License Amendment Request, Volume 6, (Revision 1), Section 3.1 - Reactivity Control Systems 2023-09-12
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FENOC Davrs-Besse Nuclear Power Sfation 5501 North Sfafe Route 2 Oak Hafior, Ohio 43449 FittEnqgy Nuclcil Walini Ctlp{nf November 20, 2018 L-18-249 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 Supplemental lnformation Regarding License Amendment Request to Adopt National Fire Protection Association (NFPA) Standard 805 (CAC No. MF7190, EPID L-2015-LLF-0001)
By Ietter dated December 16, 2015 (ADAMS Accession No. ML153504314), as supplemented by letters dated March 7,2016, July 28,2016, December 16,2016, January 17,2017, June 16,2017, October9,2017, April 2,2018, and September 11, 2018 (Accession Nos. ML16067A195, M116210A422, ML163514330, M1170174504, ML17170A000, ML17284A190, ML18094A798, and ML18254A073 respectively),
FirstEnergy Nuclear Operating Company (FENOC) submitted a license amendment request (LAR) to change the Davis-Besse Nuclear Power Station (DBNPS), Unit No. 1 fire protection program to one based on the National Fire Protection Association (NFPA)
Standard 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating PIants," 2001 Edition.
FENOC requests a revised implementation schedule for the plant modifications and specific activities required for implementation of the Iicense amendment. The October 9, 2017 letter requested thatthe modifications listed in l-AR Attachment S, Table S-1 be completed by the startup of the first refueling outage following issuance of the license amendment. lt is hereby requested that the single remaining modification be completed within two years following issuance of the license amendment request.
The only remaining modification involves providing fire protection for emergency feedwater system control cables within one of the fire compartments in which they are routed. The probabilistic risk assessment (PRA) model that was used to support the LAR assumed this modification would be installed prior to implementation. A PRA sensitivity study was subsequently pedormed that conservatively estimated the impact of delaying this modification or removing it entirely from the scope of the model by assuming the control cables fail for any fire scenario originating in this compartment.
Davis-Besse Nuclear Power Station, Unit No. 1 L-18-249 Page 2 The sensitivity study resulted in very small increases in the core damage frequency (CDF) and large event release frequency (LERF) per Regulatory Guide 1.174"An Approach for Using Probabilistic Risk Assessment in Risk-lnformed Decisions on Plant-Specific Changes to the Licensing Basis." This sensitivity study did not include multiple compartment fire propagation scenarios. Although multiple compartment scenarios that impact this compartment exist in the PRA model, recent refined fire modeling analyses show there are no fire scenarios from any compartment that can propagate and detrimentally impact this compartment. Therefore, the multiple compartment scenarios that impact this compartment will be removed from the PRA. Although, based on the sensitivity study, it is acceptable from a risk perspective to permanently continue to operate with the existing configuration, FENOC intends to complete the modification in accordance with the proposed license conditions.
Furthermore, proposed modification DB-2061 has been removed from Table S-1 in the attached LAR Attachment S. The fire risk evaluation of the variances from deterministic requirements associated with DB-2061 determined that the modification is not necessary and that the risk of not performing the modification is minimal.
The October 9, 2017 letter also requested that the specific activities listed in LAR Attachment S, Table S-2 be completed within one year following issuance of the license amendment. lt is hereby requested that the specific activities be completed within two years following issuance of the license amendment request.
Additional time is requested to coordinate with the permanent cessation of power operations at DBNPS that was certified to the Nuclear Regulatory Commission (NRC) in FENOC letter dated April 25, 2018 (ML18115A007).
Section 5.5 of the LAR is hereby changed to:
The following schedule for transitioning DBNPS to the new fire protection licensing basis requires NRC approval of the LAR in accordance with the following schedule.
a lmplementation of the new NFPA 805 fire protection program to include procedure changes, process updates, and training to affected pianipersonnel. This will occur within two years following issuance of the license amendment. LAR Attachment S Table S-2 has additional detail.
a LAR Attachment S, Table S-1 provides a listing of plant modifications associated with the transition to NFPA 805. Modifications will be completed within two years following issuance of the license amendment. Appropriate compensatory measures will be maintained until modifications are complete.
Finalfy, FENOC letter dated April 2,2018 submitted a revised LAR Attachment S that added item DB-2120 to Table S-2. However, subsequent FENOC letter dated
Davis-Besse Nuclear Power Station, Unit No. 1 L-18-249 Page 3 September 1 1,2018 submitted a revised LAR Attachment S that inadvertently rernoved item DB-2120 from the table. This issue has been entered into the FENOG Gonective Action Program. A conected Attachment S is provided that has added item DB-2120 back into Table S-2.
The information provided by this submittal does not invalidate the significant hazards consideration analysis provided in the December 16, 2015 letter.
There are no regulatory comrnitments included in this submittal. If there are any questions or if additional information is required, please contact Mr. Phil H. Lashley, Acting Manager - Nuclear Licensing and Regulatory Affairs, at (330) 3156808.
I declare undq penalty of perjury that the foregoing is true and conect. Executed on November zP ,2018.
Sincerely B Huey Director, Site Performance lmprovement Attachment S: I-AR Attachment S - Modifications and lmplementation ltems cc: NRC Regional Administrator - Region lll NRC Resident Inspector NRC Project Manager Utility Radiological Safety Board Branch Chief, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
Attachment S L-18-249 LAR Attachment S - Modifications and lmplementation ltems (7 pages, excluding this page)
FENOC Attachment $ - Modifications and Implementation ltems S Modifications and lmplementation Items 6 Pages Attached Davis-Besse Page S-1
FENOC Attachment S - Modifications and lmplementation ltems Table S-1, Plant Modifications Committed, provided below, include a description of the modifications along with the following infomation:
. Risk ranking of the modification,
. A problem statement,
. A description of the proposed modification,
. An indication if the modification is currently included in the FPRA,
. A statement if compensatory measure is in place; and
. A risk-informed charac{erization of the modification and compensatory measure.
. The following legend should be used when reviewing the tables:
o High = Modification would have an appreciable impact on reducing overall fire CDF.
o Medium = Modification would have a measurable impact on reducing overall fire CDF.
o Low = Modification would have either an insignificant or no impact on reducing overall fire CDF.
Table S-1 Plant Modifications Committed ln Comp ltem Rank Problem Statement Proposed Modification FPRA Measure Risk lnformed Characterization DB-1421 H Fire damage could result ECP 13-0195 installs the emergency water Yes No This modifieation provides an in loss of both steam storage tank and facility. This provides alternate source of feedwater by driven auxiliary feedwater emergency power sources and makeup water. providing a diesel-driven power pumps. This could ECP 13-0196 installs the diese!-driven emergency source and expanded emergency challenge the NSPC for feedwater pump and auxiliary equipment. water storage.
decay heat removal. ECP 16-0332 provides fire protection for control cables in the emergency feedwater system Davis-Besse Page S-2
FENOG Attachment S - Modifications and lmplementation ltems Table S-2, ltems provided below are those items (procedure changes, prooess updates, and training to affected plant personnel) that will be completed prior to the implementation of new NFPA 805 fire protection program.
Table S-2 lmplementation ltems Item Description LAR Section/Source D8-0341 Revise Pre-Fire PIans and Associated Training Modules to lnclude Action for Radioactive Release Attachment E and D8-0538 Scenarios; Review Pre-Fire Plans Against Safe Shutdown Analysis and Revise as Necessary; Attachment A1, Sections 3.4.3(a), 3.4.2, DB-1074 Revise Pre-Fire Plans to lnclude Rooms 330,317A,605, and 417A; Develop Pre-Fire Plan for and 3.4.2.1 DB-1093 Potential Radioactive Release Areas.
DB-1095 DB-0463 Update DB-OP-02501 to Reference Ammeters for Runout Detection Attachment C DB-0492 Generate an Inspection Procedure for the Ceramic Fiber used in Trays. Attachment V D8-0525 Revise DB-FP-00007 for Combustible and Transient Loading Program Requirements and to Attachment A1, Sections 3.3.1.2 and DB-1058 lnclude Duration Limits Based on Fire Modeling. 3.3.1.2(4)
DB-0540 Revise Transformer lnspection Procedure for Gravel Bed Drainage. Attachment Al, Section 3.3.9 FPE RAI 01.02 DB-0541 Revise Fire Brigade Policies and Practices Based on the NFPA 600 Code Review Attachment A1, Sections 3.4.1(a),
3.4.3(a), and 3.4.4 DB-0557 Revise Fire Brigade Drills to lnclude Areas Essential to Plant Operation, Safe Shutdown Areas, Attachment A1, Sections 3.4.3(b) and and to Control Radioactive Release. 3.4.3(c)
DB-0572 Revise Affected Procedures to lnclude Credited NFPA 805 Fire Protestion Equipment. Attachment 41, Section 3.2.3(2)
D8-0573 Revise Performance-Based lnspection Requirements to Include NFPA 805 Credited Fire Attachment Al, Sections 3.11.1 and D8-0600 Protection Equipment. 3.2.3(1)
DB-0582 Assess Current Transformer Fire Effects Due to Open Secondary Circuits. Attachment B, NEI Section 3.5.2.1 DB-0759 Revise Control Room Fire Alarm Response Procedure DB-OP-02529. Attachment A1, Section 3.4.1(d)
D8-0779 Revise the DBNPS Fire Protection Program, or equivalent replacement procedure, to List NRC as Attachment Al, Section 3.2.2.4 AHJ. FPE RAI 01.02 Davis-Besse Page S-3
FENOC Attachment S - Modifications and lmplementation ltems Table S-2 lmplementation ltems Item Description LAR Section/Source DB-1147 Develop a Monitoring Program as Required by NFPA 805. 4.6.2, Attachment E, and Attachment V DB-1744 DB-1949 DB-1591 Revise Documents to Include Fire Protection Water System Connections. Attachment A1, Section 3.5.16 DB-1603 Review of MOVs for Crediting CPT. Attachment V DB-1695 Revise PRA to reflect the transitioning plant: If the resulting risk estimates exceed RG 1.174 Attachment V criteria, then model refinements, plant modifications, and/or procedure changes will be made as PRA RAt 02.d.01 necessary prior to the use of the model.
DB-1696 Update the lgnition Frequency Calculation and Fire Modeling for the following: Implementation of Attachment V DB-2013 the DAFW System and FLEX, Add the Satellite phone Equipment That Will be Added to the EFWF DB-2014 and MCR per ECP-14-0465; Evaluate for lmpacts on the lmplementation of NFPA 805E for CP 14-0646 that Adds New Sound Powered Phone Equipment.
DB-1810 Revise lnterior Finish Procurement Specifications to lnclude Radiant Heat Flux. Attachment A1, Section 3.3.3 DB-1812 Revise Procedures to Trip RCPs During a Serious Fire Event. Attachment C DB-1825 Revise DBNPS EEEEs including NPE-98-00081 or its replacement (to remove credit for 4.2.2 sprinklers). FPE RAI 01 FPE RAI 06 DB-1838 Create a NFPA 13 and NFPA 72 Code Compliance Review for SBO Diesel Generator Building. Attachment 42, Fire Compartment OS D8-2041 FPE RAI 01.02 SSA RAI 01 DB-1878 Verification of Fire Damper Rating. Attachment A2, Fire Compartment ll-04 DB-1900 Update Combustible Loading Analysis to include SBO Diesel Building and Review SBO DG Day Attachment A1, Section 3.3.8 Tank to NFPA 30. FPE RAI 01.02 DB-1908 Revise Procedures and Conduct Training to lmplement NPO Requirements for NFPA 805. Attachment D DB-1912 Include inspection of Dampers 1203 and 1204 in Fire Damper lnspection Procedure. Attachment A2, Fire Compartments BG-01 and ll-01 FPE RAI 01.02 Davis-Besse Page S,il
FENOG Attachment S - Modifications and lmplementation ltems Table S-2 lmplementation ltems Item Description LAR Section/Source DB-1915 Revise Pre-Fire Plans and Training Materials to Address Radioactive Release. Attachment E DB-1941 Revise Procedures lncluding Fire Brigade Training and Drills to Incorporate Recovery Actions. Attachment G DB-1943 Review and Revise Fire PRA Human Reliability Analysis Upon Completion of Procedure Updates, Attachment G Modifications, and Training.
DB-1964 ReviseCableSpecifications. Attachment A1, Sections 3.3.5.1 and 3.3.5.3 FPE RAI 01 DB-1988 Update SAFE to Document ECP 13-0406 Fuse Protection for DB Ammeters Attachment C DB-2005 Perform NFPA 58 Code Review of the Permanent Propane Tanks lnstallation. Attachment A1, Section 3.3.7.1 DB-2015 Revise the Level 1 Failure Reports to Reflect Where Normal Control Power is Available Attachment C and Attachment V D8-2020 Resolve the Non-enclosed Power Wiring for the Emergency Backup Lighting in Fire Compartment Attachment A1, Section 3.3.5.1 cc-o1.
D8-2029 Create Analysis Assessment to create the Data Set and Testing Criteria due to Modification of Attachment V EFW and FLEX.
D8-2031 Update documentation due to addition of power converters for the Auxiliary Feedwater and Motor Attachment C and Attachment V Driven Feedwater target rock valves.
D8-2035 Update documentation such as SAFE for Containment Spray Modifications and Instrumentation. Attachment C D8-2036 DB-2037 Develop Fire Modeling Qualification Guides and Procedures Attachment V DB-2049 Develop the DBNPS NFPA 805 Design Basis Document. 4.7.1 FPE RAI 01 DB-2050 Develop New NFPA 805 Control Procedures and Processes. 4.7.2 FPE RAI 01 DB-2053 The NFPA 20 Code of Record Compliance Review will be updated to be in the format of an EEEE Attachment 41, Section 3.5.3 FPE RAI 05 Davis-Besse Page S-5
FENOC Attachment S - Modifications and lmplementation ltems Table S-2 Implementation ltems Item Description LAR Section/Source DB-2054 The NFPA 10 Code of Record Compliance Review will be updated to be in the format of an EEEE Attachment A1, Section 3.7 FPE RAI 05 D8-2055 The NFPA 72E Code of Record Compliance Review will be updated to be in the format of an Attachment 41, Section 3.8.2 EEEE. FPE RAI 05 D8-2056 The NFPA 13 and NFPA 15 Code of Record Compliance Review will be updated to be in the Attachment 41, Section 3.9.1 format of an EEEE. FPE RAI 05 D8-2057 The NFPA 80 and NFPA 90A Code of Record Compliance Review will be updated to be in the Aftachment A1, Section 3.1 1.3 format of an EEEE. FPE RAI 05 D8-2062 Update the Conduct of Operations procedure to provide clarification required for fire brigade Attachment 41, Section 3.4.1(c) qualifications necessary to meet NFPA 805 Section 3.4.1(c). FPE RAI 02 D8-2063 Perform a review of the performance-based methods described in EPRI TR-1006756 for Attachment A1, Section 3.2.3(1 );
establishing the appropriate frequencies for inspection, testing, and maintenance procedures, and Attachment L adjust the site program to address and differences identified. FPE RAI 03 DB-z120 Update PRA to address weaknesses identified in PRA RAI 03(d) response: Conseruatism related PRA RAI 03 to Multiple Compartment Scenarios impacting the Cable Spreading Room, overly conservative PORV cable mapping, missing Makeup System logic. lnclude model enhancements using NRC approved methods to maintain risk within acceptable limits. Re-perform Risk and Transition Change in Risk calculations to ensure RG 1.205 risk acceptance guidelines continue to be met with the revised model.
DB-z128 lmplement a means to obtain steam generator level locally during fire scenarios that lnclude PRA RAI 03.01.c Control Room evacuations.
Davis-Besse Page 5-6
FENOC Attachment S - Modifications and Implementation ltems Table S-3, Plant Modifications Completed, provided below, include a description of the modifications along with the following information:
. Risk ranking of the modification,
. A problem statement,
. A description of the proposed modification,
. An indication if the modification is cunently included in the FPRA,
. A statement if compensatory measure is in place; and
. A risk-informed characterization of the modification and compensatory measure.
' The following legend should be used when reviewing the tables:
o High = Modification would have an appreciable impact on reducing overall fire CDF.
o Medium = Modlfication would have a measurable impact on reducing overall fire CDF.
o Low = Modification would have either an insignificant or no impact on rcducing overall fire CDF.
Table S-3 Plant Modifications Gompleted ln Comp Item Rank Problem Statement Proposed Modification FPRA Measure Risk !nformed Characterization DB-1983 H FLEX RCS Charging ECP 13-0463 adds the FLEX RCS Makeup and Yes No This modification will help mitigate Modification Boration System. This includes the two FLEX RCP seal LOCAs should seal RCS charging pumps that are credited in the fire cooling and seal injection or seal PRA model. return be lost through the use of 2 FLEX RCS charging pumps.
DB-2010 H Install Oil Containment Install oil containment systems for the unit sub Yes No The oil collection system is Systems transformers in compartments X-01 and Y-01. currently credited in the FPRA and is used to help prevent the creation of a hot gas layer in fire compartments X-01 and Y-01.
Davis-Besse Page S-7