Semantic search

This page or action requires JavaScript to work. Please enable JavaScript in your browser or use a browser where it is supported, so that functionality can be provided as requested. For further assistance, please have a look at the noscript help page.

Search Clear all entries

	Issue date	Title	Topic
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-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-22-149, Post Accident Monitoring Report	23 June 2022	Post Accident Monitoring Report	Post Accident Monitoring
ML22202A436	8 April 2022	Enclosure F: Updated Inputs to 52 EFPY P-T Operating Curves	Hydrostatic
ML22202A437	2 March 2022	Enclosure G: Framatome Inc. Document 86-9344713-000, Davis-Besse Reactor Vessel Embrittlement Fluence Reconciliation Through 60 Years
ML21322A289	9 December 2021	Approval of Plant-Specific Analysis of Certain Reactor Vessel Internal Components in Accordance with License Renewal Commitment No. 53	Aging Management
ML20302A302	25 September 2020	1 to Technical Requirements Manual	Boric Acid Shutdown Margin Grab sample Post Accident Monitoring Functionality Assessment Incorporated by reference Pressure and Temperature Limits Report Annual Radiological Environmental Operating Report Process Control Program Operability Determination Earthquake Offsite Circuit Scaffolding
ML19255H099	10 October 2019	Staff Assessment of Flooding Focused Evaluation	High winds Internal Flooding FLEX Fukushima Dai-Ichi Flooding Focused Evaluation
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
ML22262A152	1 May 2019	Framatome Inc., Document ANP-2718NP, Revision 007, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station	Hydrostatic Pressure and Temperature Limits Report Exemption Request
ML22202A433	30 April 2019	Enclosure C: Framatome ANP-2718NP, Rev. 7, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station	Hydrostatic Pressure and Temperature Limits Report
ML18149A281	16 February 2018	2017 ATI Environmental Inc. Midwest Laboratory Radiological Environmental Monitoring Program	Grab sample
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
ML17086A032	31 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	Aging Management Earthquake
ML17026A008	31 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)	Aging Management Earthquake
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-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-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
ML14134A517	30 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	Unanalyzed Condition 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
ML14112A315	21 April 2014	Review of Draft Plant-Specific Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding
ML14007A670	21 February 2014	Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)	Safe Shutdown Boric Acid High winds Shutdown Margin Ultimate heat sink Tornado Missile Time to boil Safe Shutdown Earthquake Internal Flooding Emergency Lighting FLEX Fukushima Dai-Ichi Frazil ice Battery sizing Earthquake
ML14042A294	19 February 2014	Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Davis-Besse Nuclear Power Station, TAC No.: MF0961	Safe Shutdown Boric Acid High winds Shutdown Margin Ultimate heat sink Tornado Missile Time to boil Safe Shutdown Earthquake Internal Flooding Emergency Lighting FLEX Fukushima Dai-Ichi Frazil ice Battery sizing 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
ML13009A375	12 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.	Incorporated by reference Finite Element Analysis
ML13008A061	10 August 2012	Davis-Besse Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C, Area Walk-By Checklists, Sheet 21 of 139 Through End	Safe Shutdown Earthquake Scaffolding
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
ML15299A150	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 6 of 7
ML15299A149	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 5 of 7
ML15299A148	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 4 of 7
ML15299A147	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 3 of 7
ML15299A146	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 2 of 7	Earthquake
ML15299A144	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 1 of 7
ML12209A260	26 July 2012	Attachment 31, Fauske & Associates, Inc. Technical Bulletin No. 1295-1, BWR MSIV Leakage Assessment: NUREG-1465 Vs. MAAP 4.0.2
ML101740042	4 June 2010	0800368.407, Rev. 0, Summary of Design and Analysis of Weld Overlays for Reactor Coolant Pump Suction and Discharge, Cold Leg Drain, and Core Flood Nozzle Dissimilar Metal Welds for Alloy 600 Primary Water Stress Corrosion Cracking Mitigati	Weld Overlay Nondestructive Examination Stress corrosion cracking Dissimilar Metal Weld DM weld
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 Stress corrosion cracking Dissimilar Metal Weld
ML100250132	11 January 2010	0800368.404, Revision 1, Leak-Before-Break Evaluation of Reactor Coolant Pump Suction and Discharge Nozzle Weld Overlays for Davis-Besse Nuclear Power Station, Enclosure B	Non-Destructive Examination Safe Shutdown Earthquake Weld Overlay Design basis earthquake Stress corrosion cracking Liquid penetrant Dissimilar Metal Weld DM weld Exclusive Use Affidavit
ML11301A222	1 December 2008	Reference: Combined Heat and Power Effective Energy Solutions for a Sustainable Future
ML082190013	7 August 2008	Monthly Operating Reports Second Quarter 2008	Reserve Station Service Transformer Power change
L-08-105, Reactor Head Inspection Report	11 April 2008	Reactor Head Inspection Report	Boric Acid VT-2
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
ML072610565	17 September 2007	Confirmatory Order, 2007 Independent Assessment of Corrective Action Program (FENOC)	Boric Acid Fitness for Duty Packing leak High Radiation Area Weld Overlay Probabilistic Risk Assessment Temporary Modification Cyber Security Finite Element Analysis Condition Adverse to Quality Foreign Material Exclusion Flow Accelerated Corrosion Operability Determination Through-Wall Leak
ML070860280	15 March 2007	Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 10. the Unique Nature of the Davis-Besse Nozzle 3 Crack and the RPV Head Wastage Cavity	Boric Acid
ML070860276	15 March 2007	Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 9. Cfd Modeling of Fluid Flow in CRDM Nozzle and Weld Cracks and Through Annulus	Boric Acid
ML070860271	15 March 2007	Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 8. Stress Analysis and Crack Growth Rates for Davis-Besse CRDM Nozzles 2 and 3	Boric Acid Hydrostatic Finite Element Analysis
ML070860268	15 March 2007	Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 7. FENOC/Davis-Besse Response to CRDM Cracking and Boric Acid Corrosion Issues	Boric Acid Non-Destructive Examination Condition Adverse to Quality Pressure Boundary Leakage
ML070860261	15 March 2007	Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 5. Worldwide Industry Response to CRDM and Other Alloy 600 Nozzle Cracking	Boric Acid Nondestructive Examination
ML070860256	15 March 2007	Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 4. the Davis-Besse March 2002 Event	Boric Acid Non-Destructive Examination Pressure Boundary Leakage
ML070860253	15 March 2007	Review and Analysis of the Davis-Besse March 2002 Reactor Pressure Vessel Head Wastage Event, Section 3. Background	Boric Acid

Semantic search

Query log

Navigation menu