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	Issue date	Title	Topic
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

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