IR 05000346/2021090 | 16 December 2021 | Reissue Davis-Besse NRC Inspection Report (05000346/2021090) Preliminary White Finding | Significance Determination Process Preliminary White Finding |
L-05-056, Firstenergy Nuclear Operating Company Requests Authorization to Use Delta Protection Supplied-Air Containment Suits as Respiratory Protection Equipment and Assignment of a Protection Factor, Pursuant to 10CFR20.1703 and 10CFR20.1705 | 6 December 2005 | Firstenergy Nuclear Operating Company Requests Authorization to Use Delta Protection Supplied-Air Containment Suits as Respiratory Protection Equipment and Assignment of a Protection Factor, Pursuant to 10CFR20.1703 and 10CFR20.1705 | Mururoa |
L-06-071, Revised Financial Information Associated with an Order Approving Transfer of Licenses to Firstenergy Nuclear Generation Corp | 30 May 2006 | Revised Financial Information Associated with an Order Approving Transfer of Licenses to Firstenergy Nuclear Generation Corp | |
L-08-005, Submittal of the 2007 Organizational Safety Culture and Safety Conscious Work Environment Independent Assessment Report for Davis-Besse | 27 January 2008 | Submittal of the 2007 Organizational Safety Culture and Safety Conscious Work Environment Independent Assessment Report for Davis-Besse | Fitness for Duty Temporary Modification |
L-08-036, Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors | 28 February 2008 | Supplemental Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors | Boric Acid Packing leak Mission time Safe Shutdown Earthquake Hydrostatic Coatings Operating Basis Earthquake Foreign Material Exclusion Exemption Request Maintenance Rule Program Scaffolding |
L-08-105, Reactor Head Inspection Report | 11 April 2008 | Reactor Head Inspection Report | Boric Acid VT-2 |
L-08-152, Submittal of Technical Specification 6.9.1.12 Steam Generator Tube Inspection Report for January 2008 15th Refueling Outage | 25 July 2008 | Submittal of Technical Specification 6.9.1.12 Steam Generator Tube Inspection Report for January 2008 15th Refueling Outage | Nondestructive Examination |
L-08-194, First Energy Nuclear Operating Company Submittal of Engineering Program Effectiveness Assessment Plan for the Davis-Besse Nuclear Power Station - Year 2008 | 24 June 2008 | First Energy Nuclear Operating Company Submittal of Engineering Program Effectiveness Assessment Plan for the Davis-Besse Nuclear Power Station - Year 2008 | Boric Acid Probabilistic Risk Assessment Temporary Modification |
L-08-251, 2008 Independent Corrective Action Program Assessment Report, March 2004 Confirmatory Order | 15 September 2008 | 2008 Independent Corrective Action Program Assessment Report, March 2004 Confirmatory Order | |
L-09-068, Independent Spent Fuel Storage Installation - 10 CFR 72.48 Report of Dry Fuel Storage Facility Changes, Tests, and Experiments | 27 February 2009 | Independent Spent Fuel Storage Installation - 10 CFR 72.48 Report of Dry Fuel Storage Facility Changes, Tests, and Experiments | |
L-10-132, 0800368.408, Revision 0, Summary of Weld Overlay Ultrasonic Examinations for Reactor Coolant Pump Suction and Discharge Nozzle Welds, Core Flood Nozzle Welds, and Cold Leg Drain Nozzle Welds | 25 April 2010 | 0800368.408, Revision 0, Summary of Weld Overlay Ultrasonic Examinations for Reactor Coolant Pump Suction and Discharge Nozzle Welds, Core Flood Nozzle Welds, and Cold Leg Drain Nozzle Welds | Weld Overlay Dissimilar Metal Weld |
L-11-319, Pressure and Temperature Limits Report | 27 October 2011 | Pressure and Temperature Limits Report | Hydrostatic Pressure and Temperature Limits Report |
L-12-071, 10 CFR 50.46 Report of Significant Changes or Errors in the Loss of Coolant Accident Evaluation Model | 16 March 2012 | 10 CFR 50.46 Report of Significant Changes or Errors in the Loss of Coolant Accident Evaluation Model | Fuel cladding |
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 7 | 14 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 | High winds Finite Element Analysis |
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 139 | 10 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 | Scaffolding |
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 Accident | 27 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 | Safe Shutdown Unanalyzed Condition Boric Acid High winds Safe Shutdown Earthquake Internal Flooding Hydrostatic Probabilistic Risk Assessment Coatings Locked High Radiation Area Fukushima Dai-Ichi Earthquake |
L-13-154, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models | 28 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 Plan | 15 May 2013 | Generic Safety Issue 191 Resolution Plan | Coatings Severe Accident Management Guideline |
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 Accident | 11 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 | Fukushima Dai-Ichi Earthquake |
L-14-148, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models | 19 May 2014 | CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models | |
L-14-167, Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 2014 | 18 June 2014 | Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 2014 | Incorporated by reference Turbine Missile |
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) | 28 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) | FLEX Spent Fuel Pool Instrumentation |
L-14-289, Pressure and Temperature Limits Report. Revision 2 | 22 September 2014 | Pressure and Temperature Limits Report. Revision 2 | Hydrostatic Pressure and Temperature Limits Report |
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 In | 19 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 | |
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 Accident | 2 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 | High Radiation Area Ultimate heat sink Emergency Lighting FLEX Fukushima Dai-Ichi Severe Accident Management Guideline |
L-15-328, Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 7 of 7 | 30 July 2012 | Enclosure B, Bechtel Report No. 25593-000-G83-GEG-00016-000, Effect of Laminar Cracks on Splice Capacity of No. 11 Bars Based on Testing Conducted at Purdue University and University of Kansas for Davis-Besse Shield Building. Part 7 of 7 | Earthquake |
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) | 21 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-16-229, Submittal of Pressure and Temperature Limits Report, Revision 3 | 28 July 2016 | Submittal of Pressure and Temperature Limits Report, Revision 3 | Pressure and Temperature Limits Report |
L-17-088, Independent Spent Fuel Storage Installation Changes, Tests and Experiments | 27 March 2017 | Independent Spent Fuel Storage Installation Changes, Tests and Experiments | |
L-17-270, Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.46 | 1 September 2017 | Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.46 | |
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.... | 12 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.... | Safe Shutdown Unanalyzed Condition Boric Acid High winds Tornado Missile Enforcement Discretion Probabilistic Risk Assessment FLEX Tornado Generated Missile Tornado Missile Protection |
L-19-189, 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension. | 29 July 2019 | 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension. | Hot Short Safe Shutdown High winds Internal Flooding Probabilistic Risk Assessment FLEX Tornado Generated Missile Thermoset Large early release frequency |
L-22-149, Post Accident Monitoring Report | 23 June 2022 | Post Accident Monitoring Report | Post Accident Monitoring |
L-22-211, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report | 29 September 2022 | Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report | Nondestructive Examination |
L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 4 | 27 September 2022 | Submittal of Pressure and Temperature Limits Report. Revision 4 | Hydrostatic Pressure and Temperature Limits Report |
L-22-253, Submittal of Pressure and Temperature Limits Report, Revision 5 | 10 January 2023 | Submittal of Pressure and Temperature Limits Report, Revision 5 | Hydrostatic Pressure and Temperature Limits Report |
L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments | 7 August 2023 | Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments | Cyber Security Safeguards Contingency Plan Fire Protection Program |
ML020920750 | 29 March 2002 | International Nuclear Event Scale (INES) Event Rating Form for Davis-Besse Event | |
ML021160410 | 8 April 2002 | Safety Significance Assessment of the Davis-Besse Nuclear Power Station, Unit 1 Reactor Pressure Vessel Head Degradation - Non-Proprietary Version | Safe Shutdown Boric Acid Shutdown Margin Anticipated operational occurrence Probabilistic Risk Assessment Finite Element Analysis Large early release frequency |
ML021210583 | 25 April 2002 | License Condition 2.C(7) Report for Thirteenth Refueling Outage | |
ML021210594 | 16 April 2002 | Firstenergy Corp Annual Report from Randy Scilla Retrospective Premium Guarantee | |
ML022030464 | 12 July 2002 | Transmittal of Revision 1 to Return to Service Plan | Boric Acid Non-Destructive Examination Coatings Maintenance Rule Program |
ML022270104 | 9 August 2002 | Submittal of Semiannual Fitness-for-Duty Report, January - June 2002 from Firstenergy Nuclear | Fitness for Duty |
ML022380419 | 20 August 2002 | Return to Service Update August 20, 2002 | Boric Acid Packing leak Tornado Missile Coatings Temporary Modification Foreign Material Exclusion Code Reconciliation |
ML022390598 | 31 August 2002 | Report Titled Results of Visual Examination of Reactor Head CRDM Nozzle Penetrations Performed in 1996, 1998 and 2000. | Finite Element Analysis |
ML022750125 | 23 September 2002 | Confirmatory Action Letter - Revision 1 to Root Cause Analysis Report Regarding Reactor Pressure Vessel Head Degradation at the Davis-Besse Nuclear Power Station | Boric Acid Time of Discovery Packing leak Non-Destructive Examination Hydrostatic Coatings Nondestructive Examination VT-2 Finite Element Analysis Condition Adverse to Quality Fuel cladding Pressure Boundary Leakage Through-Wall Leak Through Wall Leak Power change |
ML022750405 | 21 August 2002 | Confirmatory Action Letter Response - Management & Human Performance Root Cause Analysis Report on Failure to Identify Reactor Pressure Vessel Head Degradation | Boric Acid Time of Discovery Packing leak Non-Destructive Examination Hydrostatic Past operability Probabilistic Risk Assessment Temporary Modification VT-2 Condition Adverse to Quality Pressure Boundary Leakage Scaffolding Downpower |
ML022760172 | 30 September 2002 | Degradation of the Davis-Besse Nuclear Power Station Reactor Pressure Vessel Head Lessons-Learned Report | Boric Acid Time of Discovery Packing leak Hydrostatic Enforcement Discretion Nondestructive Examination Temporary Modification VT-2 Condition Adverse to Quality Significance Determination Process Large early release frequency Systematic Assessment of Licensee Performance New Senior Resident Inspector Fuel cladding Pressure Boundary Leakage Pressure boundary leak Generic Issues Program Fire Watch Unidentified leakage Unidentified leak |
ML022760189 | 30 September 2002 | Degradation of the Davis-Besse Nuclear Power Station Reactor Pressure Vessel Head Lessons-Learned Report - Appendices A-D | Boric Acid Packing leak Hydrostatic Enforcement Discretion Nondestructive Examination Temporary Modification VT-2 Significance Determination Process Systematic Assessment of Licensee Performance License Renewal Pressure Boundary Leakage Generic Issues Program Through-Wall Leak Unidentified leakage |
ML022760219 | 30 September 2002 | Degradation of the Davis-Besse Nuclear Power Station Reactor Pressure Vessel Head Lessons-Learned Report - Appendices E-F | Boric Acid Packing leak Weld Overlay Nondestructive Examination Locked High Radiation Area Liquid penetrant Pressure Boundary Leakage Pressure boundary leak Through-Wall Leak Through Wall Leak |