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Issue date | Title | Topic | |
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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 |