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MONTHYEARML0515301972005-06-0202 June 2005 6/2/05, Davis-Besse - RAI Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: RAI ML0603807252006-02-0909 February 2006 Request for Additional Information, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-water Reactors Project stage: RAI L-08-036, Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2008-02-28028 February 2008 Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Supplement ML0817803302008-07-10010 July 2008 Request for Additional Information Related to Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Basis Accidents at Pressurized-Water Reactors Project stage: RAI L-10-111, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pwrs.2010-04-30030 April 2010 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pwrs. Project stage: Supplement L-13-157, Generic Safety Issue 191 Resolution Plan2013-05-15015 May 2013 Generic Safety Issue 191 Resolution Plan Project stage: Other L-13-224, Notification of Closure of a Commitment Related to the Generic Safety Issue 191 Resolution Plan for the (DBNPS)2013-07-0303 July 2013 Notification of Closure of a Commitment Related to the Generic Safety Issue 191 Resolution Plan for the (DBNPS) Project stage: Other ML21088A3442021-03-29029 March 2021 Final Supplemental Response to Nuclear Regulatory Commission Generic Letter 2004-02 Project stage: Supplement 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 Project stage: Supplement 2008-07-10
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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:Report
MONTHYEARL-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-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-22-211, 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-22-149, Post Accident Monitoring Report2022-06-23023 June 2022 Post Accident Monitoring Report ML22202A4362022-04-0808 April 2022 Enclosure F: Updated Inputs to 52 EFPY P-T Operating Curves ML22202A4372022-03-0202 March 2022 Enclosure G: Framatome Inc. Document 86-9344713-000, Davis-Besse Reactor Vessel Embrittlement Fluence Reconciliation Through 60 Years IR 05000346/20210902021-12-16016 December 2021 Reissue Davis-Besse NRC Inspection Report (05000346/2021090) Preliminary White Finding ML21322A2892021-12-0909 December 2021 Approval of Plant-Specific Analysis of Certain Reactor Vessel Internal Components in Accordance with License Renewal Commitment No. 53 ML20302A3022020-09-25025 September 2020 1 to Technical Requirements Manual ML19255H0992019-10-10010 October 2019 Staff Assessment of Flooding Focused Evaluation L-19-189, 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension.2019-07-29029 July 2019 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension. ML22262A1522019-05-0101 May 2019 Framatome Inc., Document ANP-2718NP, Revision 007, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station ML22202A4332019-04-30030 April 2019 Enclosure C: Framatome ANP-2718NP, Rev. 7, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station L-18-108, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile....2018-04-12012 April 2018 Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile.... ML18149A2812018-02-16016 February 2018 2017 ATI Environmental Inc. Midwest Laboratory Radiological Environmental Monitoring Program L-17-270, Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.462017-09-0101 September 2017 Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.46 ML17086A0322017-03-31031 March 2017 Enclosure B to L-17-105, Areva Report ANP-3542NP, Revision 1, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years L-17-088, Independent Spent Fuel Storage Installation Changes, Tests and Experiments2017-03-27027 March 2017 Independent Spent Fuel Storage Installation Changes, Tests and Experiments ML17026A0082016-12-31031 December 2016 Areva Report ANP-3542NP, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years (Non Proprietary) L-16-229, Submittal of Pressure and Temperature Limits Report, Revision 32016-07-28028 July 2016 Submittal of Pressure and Temperature Limits Report, Revision 3 L-16-148, Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue)2016-04-21021 April 2016 Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue) L-15-288, Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-10-0202 October 2015 Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML15230A2892015-08-25025 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review L-14-401, First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In2014-12-19019 December 2014 First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In ML14353A0602014-11-0303 November 2014 2734296-R-010, Rev. 0, Expedited Seismic Evaluation Process (ESEP) Report Davis-Besse Nuclear Power Station L-14-289, Pressure and Temperature Limits Report. Revision 22014-09-22022 September 2014 Pressure and Temperature Limits Report. Revision 2 L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML14141A5252014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident L-14-167, Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 20142014-06-18018 June 2014 Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 2014 ML14134A5172014-05-30030 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident L-14-148, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2014-05-19019 May 2014 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML14112A3152014-04-21021 April 2014 Review of Draft Plant-Specific Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding L-14-104, Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-03-11011 March 2014 Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14007A6702014-02-21021 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14042A2942014-02-19019 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Davis-Besse Nuclear Power Station, TAC No.: MF0961 ML13340A1592013-11-26026 November 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix a ML13340A1472013-11-26026 November 2013 Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant - Response to RAI Associated with Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (TAC Nos. MF0116 & MF0 ML13340A1632013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix C to Appendix G ML13340A1622013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (2 of 2) ML13340A1602013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (1 of 2) ML13340A1582013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1 L-13-154, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2013-05-28028 May 2013 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-13-157, Generic Safety Issue 191 Resolution Plan2013-05-15015 May 2013 Generic Safety Issue 191 Resolution Plan ML13009A3752012-12-12012 December 2012 Enclosure B to L-12-444, Calculation No. 32-9195651-000, Equivalent Margins Assessment of Davis-Besse Transition Welds for 52 EFPY - Non-Proprietary. L-12-347, FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-27027 November 2012 FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML13135A2452012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 202 of 379 Through Sheet 379 of 379 ML13135A2442012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 1 of 379 Through Sheet 201 of 379 ML13135A2432012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix a - Resumes and Qualifications ML13135A2422012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Cover Through Page 176 2023-08-07
[Table view] Category:Miscellaneous
MONTHYEARL-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 IR 05000346/20210902021-12-16016 December 2021 Reissue Davis-Besse NRC Inspection Report (05000346/2021090) Preliminary White Finding L-18-108, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile....2018-04-12012 April 2018 Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile.... L-17-088, Independent Spent Fuel Storage Installation Changes, Tests and Experiments2017-03-27027 March 2017 Independent Spent Fuel Storage Installation Changes, Tests and Experiments L-16-148, Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue)2016-04-21021 April 2016 Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue) ML15230A2892015-08-25025 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review L-14-401, First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In2014-12-19019 December 2014 First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In ML14353A0602014-11-0303 November 2014 2734296-R-010, Rev. 0, Expedited Seismic Evaluation Process (ESEP) Report Davis-Besse Nuclear Power Station L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML14141A5252014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident L-14-167, Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 20142014-06-18018 June 2014 Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 2014 L-14-104, Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-03-11011 March 2014 Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML13340A1472013-11-26026 November 2013 Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant - Response to RAI Associated with Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (TAC Nos. MF0116 & MF0 ML13340A1592013-11-26026 November 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix a ML13340A1602013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (1 of 2) ML13340A1582013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1 ML13340A1622013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (2 of 2) ML13340A1632013-10-0909 October 2013 Davis-Besse Nuclear Power Station Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix C to Appendix G L-13-157, Generic Safety Issue 191 Resolution Plan2013-05-15015 May 2013 Generic Safety Issue 191 Resolution Plan L-12-347, FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-27027 November 2012 FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML13008A0312012-08-10010 August 2012 Davis-Besse Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Cover Through Appendix a, Resumes and Qualifications, Page A-39 ML13135A2462012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C - Area Walk-by Checklists (Awcs) Through End ML13135A2452012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 202 of 379 Through Sheet 379 of 379 ML13135A2442012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 1 of 379 Through Sheet 201 of 379 ML13135A2432012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix a - Resumes and Qualifications ML13135A2422012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Cover Through Page 176 L-12-283, Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B, Seismic Walk-Down Checklists, Sheet 364 of 461 Through Appendix C, Area Walk-By Checklists, Sheet 20 of 1392012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B, Seismic Walk-Down Checklists, Sheet 364 of 461 Through Appendix C, Area Walk-By Checklists, Sheet 20 of 139 ML13008A0642012-08-10010 August 2012 Davis-Besse Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B, Seismic Walk-Down Checklists, Sheet 244 of 461 Through Sheet 363 of 461 ML13008A0632012-08-10010 August 2012 Davis-Besse Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B, Seismic Walk-Down Checklists, Sheet 121 of 461 Through Sheet 243 of 461 ML13008A0622012-08-10010 August 2012 Davis-Besse Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B, Seismic Walk-Down Checklists, Page B-1 Through Sheet 120 of 416 ML12213A3372012-07-27027 July 2012 SB-00-20: CR-2011-03346 Evaluation ML12213A3352012-07-27027 July 2012 Review of Technical Assessment Report No. 25539-200 COR-0000-00001 L-12-196, FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 72012-05-14014 May 2012 FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 7 ML12138A0582012-05-14014 May 2012 FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 3 ML12138A0812012-05-14014 May 2012 FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 6 ML12138A0492012-05-14014 May 2012 FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 2 ML12138A0672012-05-14014 May 2012 FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 4 ML12138A0732012-05-14014 May 2012 FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 5 L-12-071, 10 CFR 50.46 Report of Significant Changes or Errors in the Loss of Coolant Accident Evaluation Model2012-03-16016 March 2012 10 CFR 50.46 Report of Significant Changes or Errors in the Loss of Coolant Accident Evaluation Model ML12200A2122011-11-21021 November 2011 Containment Shield Building Issue ML12200A2102011-11-17017 November 2011 Containment System Primary Steel Containment an Shield Building ML12213A3482011-10-28028 October 2011 Table of Contents to Isolated Crack Indication Identified by Impulse Response Testing of the Shield Building L-11-319, Pressure and Temperature Limits Report2011-10-27027 October 2011 Pressure and Temperature Limits Report ML11301A2302011-06-0101 June 2011 Reference: State Energy Consumption Estimates 1960 Through 2009 ML1101007582011-01-10010 January 2011 Pressure Temperature Limits Report Attachment ML11301A2232010-07-31031 July 2010 Chp Regional Application Centers: Activities and Selected Results for Fiscal Year 2009 ML1015201162010-05-26026 May 2010 Field Report Control Rod Drive Mechanism Number 4 Ultrasonic Results ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1005396232010-02-22022 February 2010 Lessons Learned Task Force Action Plan Regarding Stress Corrosion Cracking Dec 2009 (Final Update) L-09-068, Independent Spent Fuel Storage Installation - 10 CFR 72.48 Report of Dry Fuel Storage Facility Changes, Tests, and Experiments2009-02-27027 February 2009 Independent Spent Fuel Storage Installation - 10 CFR 72.48 Report of Dry Fuel Storage Facility Changes, Tests, and Experiments 2023-08-07
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, 5501 NoTth State Route 2 Oak Harbor. Ohio 43449 RrstEnergy Nuclear Operating Company Raymond A Ueb"' 419-321-7676 Vice President. Nuclear Fax: 419-321-7582 May 15, 2013 10 CFR 50.54(f)
L-13-157 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Davis-Besse Nuclear Power Station Docket No. 50-346, License Number NPF-3 Generic Safety Issue 191 Resolution Plan (TAC No. MC4681)
This letter forwards information regarding resolution of Generic Safety Issue 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance, for Davis-Besse Nuclear Power Station (DBNPS). Nuclear Regulatory Commission (NRC) staff has interacted with the industry and stakeholders to develop options for the resolution of Generic Safety Issue 191. The NRC staff paper SECY-12-0093, "Closure Options for Generic Safety Issue 19l, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance," presents closure options for Generic Safety Issue 191.
Attachment 1 provides information regarding the current status of efforts to address Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors," and describes the Generic Safety Issue 191 closure option, resolution plan, and associated implementation schedule for DBNPS. Attachment 2 provides a list of regulatory commitments included in this submittal.
If there are any questions or if additional information Is required, please contact Mr.
Thomas A. Lentz, Manager, Fleet Licensing at (330) 315-6810.
I declare under penalty of perjury that the foregoing is true and correct. Executed on May Is-. 2013.
Sincerely,
Davis-Besse Nuclear Power Station L-13-157 Page 2
Attachment:
- 1. Generic Safety Issue 191, In-Vessel Effects Resolution Plan
- 2. Regulatory Commitment List cc: NRC Region III Administrator NRC Resident Inspector NRC Project Manager Utility Radiological Safety Board
ATIACHMENT1 L-13-157 Generic Safety Issue 191, In-Vessel Effects Resolution Plan Page 1 of7 Introduction FirstEnergy Nuclear Operating Company (FENOC) has selected Option 2, deterministic path, of Nuclear Regulatory Commission (NRC) staff paper SECY-12-0093, "Closure Options for Generic Safety Issue 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance," for Davis-Besse Nuclear Power Station (DBNPS) and intends to pursue refinements to evaluation methods and acceptance criteria. In addition, the resolution schedule defined in SECY-12-0093 will also be adhered to, as described herein. The Nuclear Energy Institute (NEI) closure option template dated November 9, 2012, "Closure Option Templates for Generic Safety Issue 191 (GSI-191), Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance" was used in developing this response. This submittal provides a resolution plan that follows the deterministic path of Option 2 (referred to as NEI template option 2a).
To support use of this path for the period required to complete the necessary analysis and testing, FENOC has evaluated the design and procedural capabilities that exist to identify and mitigate in-vessel blockage. A description of these capabilities is provided later in this document. A summary of the existing margins and conservatisms that exist for DBNPS are also included in this document.
Characterization of Current Containment Fiber Status From the debris generation and debris transport analysis, FENOC has established that a maximum quantity of six cubic feet (6 ft3) of fibrous debris from destroyed insulation could be generated as a result of analyzed breaks, as documented in References 1 and
- 7. At the time of the Reference 1 submittal, all fibrous piping insulation in containment had been removed or replaced with reflective metal insulation (RMI) with the exception of three locations that total less than 1ft3 of Nukon' insulation. The analysis therefore provided at least 5 ft3 of low density fiberglass insulation margin. Subsequent modifications associated with the reactor vessel head replacement have reduced the number of locations with fibrous insulation from three to one, with a total of 0.307 ft3 of fibrous inSUlation with an assumed density of 2.4 pounds per cubic foot.
Within the debris generation and debris transport analysis, FENOC has established that 75 pounds of latent fiber could be generated as a result of analyzed breaks, as documented in References 1 and 7. The 75 pounds of latent fiber is based on a conservative assumption of 500 pounds of latent debris in containment with a maximum 15 percent by weight fiber content, consistent with NEI 04-07, "Pressurized Water Reactor Sump Performance Evaluation Methodology," Volume 2, "Safety Evaluation by L-13-157 Page 2 of7 the Office of Nuclear Reactor Regulation Related to NRC Generic Letter 2004-02, Revision 0, December 6,2004," Appendix VII, "Characterization of Pressurized-Water-Reactor Latent Debris" (Reference 9). This initial conservative assumption of 500 pounds of latent debris was used for analysis purposes, except for analysis of reactor coolant system (RCS) breaks inside the reactor vessel cavity where plant-specific quantification was necessary because of the reduced strainer surface area available.
Sampling of containment latent debris was conducted based on guidance provided in NEI 04-07, as modified by the NRC SER. The latent debris loading in containment was determined to be 46 pounds, with 15 percent, or 6.9 pounds considered fiber. Although not credited, laboratory analysis of DBNPS containment debris samples identified only 1 of 13 samples to contain greater than 10 percent fiber by weight, with an over all containment latent fiber load of 5.5 percent of containment debris, by weight.
The debris types, sizes, transport fractions, and quantities postulated to be transported to the strainers for analyzed break locations are provided in Reference 1. Essentially all fiber has been removed from the DBNPS containment, and thus the limiting fiber loads are generated thru latent fiber. For the DBNPS limiting break scenario, the total calculated quantity of fiber to be transported to the strainers is approximately 9.5 pounds. The fibrous debris sources considered in these analyses include a very small amount of installed Nukon TM insulation and latent fiber consistent with administrative limits for permissible debris within containment.
Characterization of Strainer Head Loss Status FENOC provided the results of the strainer head loss analysis, including the impact of chemical effects, in correspondence dated February 28, 2008 (Reference 1). DBNPS has limited amounts of fibrous insulation postulated to be destroyed in a design basis accident. As a result of having less than a thin bed, clean screen area is expected in all postulated breaks. Thus, while a chemical effects analysis was performed, it did not influence the overall results of the strainer head loss analysis because, when less than a thin bed exists, the chemical products do not contribute to head loss.
The NRC inspection utilizing Temporary Instruction (TI) 25151166, "Pressurized Water Reactor Containment Sump Blockage (NRC Generic Letter 2004-02)," confirmed that FENOC completed the required analyses that were documented in Reference 1 for DBNPS (Reference 8). The inspection report noted that there were no outstanding actions to be completed and, therefore, TI2515/1666 was closed. Subsequent to the completion of this inspection, the NRC staff review of Reference 1 indicated that the staff had no further questions at that time regarding performance of the Davis-Besse emergency core cooling strainers, in part, based on the very low potential debris loading (Reference 3).
L-13-157 Page 3 of7 Characterization of In-Vessel Effects FENOC performed a plant-specific analysis using the 45 percent bypass fraction considered by the staff to be conservative for most typical perforated plate strainer installations where flow patterns do not result in fragmentation of debris (Reference 2).
The DBNPS strainer is made of perforated plate. This analysis resulted in an approximate value of 11 grams of fiber per fuel assembly. FENOC is currently evaluating a plant-specific bypass fraction based on similarity to other strainers that have been tested to eliminate reliance on the staff's conservative value.
To provide design and operating margins, FENOC intends to follow the resolution strategies proposed by the Pressurized Water Reactor Owners Group (PWROG) to establish in-vessel debris limits applicable to the plant design features that exist at DBNPS. This approach is expected to establish in;.vessel debris limits in excess of that currently established in Westinghouse evaluation report WCAP-16793, Revision 2 (Reference 10).
licensing Basis Commitments FENOC has no open regulatory commitments for DBNPS to provide additional updates or information to the NRC regarding GL 2004-02; however, a request for additional information (RAI) was included in Reference 3, which states:
FENOC is requested to report how DBNPS has addressed the in-vessel downstream effects issue within 90 days of issuance of the final NRC staff SE on WCAP-16793.
Reference 3 also stated that the NRC staff had no further questions concerning the FENOC response to the "Davis-Besse Nuclear Power Station, Unit No.1 - Request for Additional Information Related to Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors." The RAI mentioned above is the only outstanding item in response to Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized Water Reactors," and will be provided in accordance with Reference 3.
New regulatory commitments included in this submittal are listed in Attachment 2.
L-13-157 Page 4 of7 Resolution Schedule FENOC will achieve closure of GSI-191 and address GL 2004-02 for the Davis-Besse Nuclear Power Station per the following schedule.
- Reference 3, in part, requests FENOC to submit how DBNPS has addressed the
.in-vessel downstream effects issue within 90 days of issuance of the final NRC staff SER on WCAP-16793. As stated above, a plant-specific analysis has been performed assuming the 45 percent bypass fraction considered by the staff to be conservative for most typical perforated plate strainer installations where flow patterns do not result in fragmentation of debris. This analysis resulted in an approximate in-vessel fiber loading of 11 grams of fiber per fuel assembly.
Follow-up action to close this assumption will validate the DBNPS strainer bypass percentage results is less than or equal to 15 grams of fiber per fuel assembly. FENOC will report on the progress toward confirming the strainer bypass percentage results is less than or equal to 15 grams of fiber per fuel assembly for DBNPS. Since this SER was made available on April 16, 2013, this progress report will be provided by July 15, 2013.
- The final Generic Letter 2004-02 supplemental response for DBNPS will be provided to the NRC 6 months after the NRC approves, by issuance of a safety evaluation, the new PWROG topical report addressing additional in-vessel effects testing efforts that are currently being pursued.
Summary of Actions Completed to Address GL 2004-02 A strairler replacement was installed at DBNPS during the 2002-2004 outage. The new strainer utilizes the Enercon top hat design, which increased the available surface area from approximately 50 square feet to 1226 square feet. The design basis function of the strainer has been incorporated in the Updated Final Safety Analysis Report (UFSAR) in accordance with 10 CFR 50.71 (e).
DBNPS is considered a low fiber plant based on approved industry and NRC standards associated with GSI-191 and Generic Letter 2004-02. This has been accomplished through removal of nearly all installed fibrous insulation from inside containment.
Controls on coatings, insulation, and signage have been established. Procedures have been instituted that require verification of strainer integrity and containment cleanliness prior to entering a mode of operation that requires emergency core cooling system operability.
L-13-t57 Page 50f7 Modifications to the high pressure injection pumps and the cyclone separators for the emergency core cooling system (ECCS) pump seals were implemented to ensure continued operation in the post-LOCA environment. In addition, cyclone separators were installed on the containment spray pump seal supply lines.
Summary of Margins and Conservatlsms for Completed Actions for GL 2004-02 Margins and conservatisms associated with debris generation, debris transport, strainer head loss, chemical effects, and ECCS flow have been summarized in Generic Letter 2004-02 submittals previously submitted for NRC review (Reference 1). Additional Information on margins and conservatisms associated with debris generation, debris transport, strainer head loss, chemical effects, and ECCS flow are provided below.
Debris Generation
- The debris generation and transport analyses assume 6 ft3 of low density fiberglass (Nukon TM insulation) is available to be destroyed in the NPSH analyses for two of three analyzed break locations. The current as-built configuration only includes only 0.307 ftl of installed fiber insulation. This margin may be used to resolve issues relative to ECCS pump performance if additional low density fiberglass insulation is discovered.
Debris Transport
- It was conservatively assumed that all latent debris is in lower containment and would be uniformly distributed in the containment pool at the beginning of recirculation. This is a conservative assumption because no credit is taken for debris remaining on structures and equipment above the pool water level.
Strainer Head Loss
- As noted above, the amount of installed fiber within the plant has been further reduced, increasing the conservatism included in the strainer head loss calculation.
- The containment latent debris load was quantified and found to be less than the allowable amount used in the strainer head loss analysis. In addition, the fiber content of the containment latent debris was assessed and was found to be lower than the 15% fiber assumed in the head loss analyses. Only one sample was found to be greater than 10% fiber.
Attachment 1 L-13-157 Page 6 of7 In-Vessel
- An analysis has been completed using methodology documented in Reference 2.
The analysis used the 45 percent bypass fraction presented in Reference 2, which is considered by the staff to be conservative for most typical perforated plate strainer installations where flow patterns do not result in fragmentation of debris.
- No credit was taken for fiber recirculation through the containment spray system, which removes some of the fiber.
Summary of Defense-In-Depth (DID) Measures The following describes the plant-specific design features and procedural capabilities
. that exist for detecting and mitigating a fuel blockage condition.
- If a condition of inadequate reactor core flow were to develop, then increasing core outlet temperature indication is the primary method expected for detection.
Existing procedural guidance (Reference 5) directs actions to be taken if inadequate core cooling is detected. If initial procedural guidance for verifications and alternate system line-ups results in continued increasing core outlet temperature, existing procedural guidance directs starting one reactor coolant pump per loop. This action is expected to remove any established blockage to the core to once again allow normal recirculation injection flow paths to become effective at maintaining adequate core cooling (Reference 6).
However, if core outlet temperatures continue to rise, ultimately a transition to the severe accident management guidelines will be implemented. Further direction will then be provided by the emergency response organization based on the Davis-Besse Severe Accident Management Guidelines.
Although these measures are not expected to be required based on the very low probability of an event that would result in significant quantities of debris being transported to the reactor vessel that would inhibit the necessary cooling of the fuel, they do provide additional assurance that the health and safety of the public would be maintained. These measures provide support for the extension of time required to completely address GL 2004-02 for DBNPS.
Conclusion The GSI-191 resolution path for Davis-Besse Nuclear Power Station is acceptable based on the information provided in this document along with previous documents submitted to and reviewed by the NRC. The execution of the actions identified in this document will result in successful resolution of GSI-191 and closur~ of GL 2004-02.
L-13-157 Page 7 of 7 References
- 1. FENOC letter to NRC, "Supplemental Response to Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors" (TAC No. MC4681),
February 28, 2008 (Accession No. ML080650368).
- 2. NRC letter to Nuclear Energy Institute, "NRC Review of NEI Clean Plant Acceptance Criteria for Emergency Core Cooling Systems," May 2,2012 (Accession No .. ML120730181).
- 3. NRC letter to FENOC, "Davis-Besse Nuclear Power Station, Unit No.1 -
Request for Additional Information Related to Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (TAC No.
MC4681)," July 10, 2008 (Accession No. ML081780330).
- 4. PWROG letter to NRC, "Submittal of Supplement to WCAP-16793-NP," Revision 2, July 20,2012 (Accession No. ML12207A115).
- 5. Davis-Besse Nuclear Power Station Emergency Procedure titled "RPS, SFAS, SFRCS Trip, or SG Tube Rupture," Revision 26.
- 6. NElletter to NRC, "Defense-In-Depth Measures in Support of GSI-191 Resolution Options," March 5,2012 (Accession No. ML120730654).
- 7. FENOC letter to NRC, "Supplemental Response to Generic Letter 2004-02,
'Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors' (TAC No. MC4681)," dated April 30, 2010 (Accession No. ML101250217).
- 8. NRC Inspection Report 05000346/2008-003 for Davis-Besse Nuclear Power Station, July 21,2008 (Accession No. ML082040478).
- 9. NEI 04-07, "Pressurized Water Reactor Sump Performance Evaluation Methodology," Volume 2, "Safety Evaluation by the Office of Nuclear Reactor Regulation Related to NRC Generic Letter 2004-02, Revision 0, December 6, 2004," Appendix VII, "Characterization of Pressurized-Water-Reactor Latent Debris."
- 10. Westinghouse Report WCAP-16793, Revision 2, "Evaluation of Long-Term Cooling Considering Particulate, Fibrous and Chemical Debris in the Recirculating Fluid," dated October 2011 (Accession No. ML11292A021).
Attachment 2 L-13-157 Regulatory Commitment List Page 1 of 1 The following list identified those actions committed to by FirstEnergy Nuclear Operating Company (FENOC) for Davis-Besse Nuclear Power Station (DBNPS) in this document.
Any other actions discussed in this submittal represent intended or planned actions by FENOC. They are described only as information and are not regulatory commitments.
Please notify Mr. Thomas A. Lentz, Manager - Fleet Licensing, at (330)-315-6810 Regulatory Commitment Due Date
- 1. FENOC will report on the progress July 15, 2013 toward confirming the strainer bypass percentage results is less than or equal to 15 grams of fiber per fuel assembly for DBNPS.
- 2. The final Generic Letter 2004-02 Six months after the NRC supplemental response for DBNPS will approves, by issuance of a safety be provided to the NRC. evaluation, the new PWROG topical report addressing additional in-vessel effects testing efforts that are currently being pursued.
- 3. Updated Final Safety Analysis Report Following NRC acceptance of the changes will be completed to update the final docketed Generic Safety Issue current licensing basis for DBNPS as 191 response for DBNPS.
appropriate.