Pages that link to "ML14134A517"
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The following pages link to ML14134A517:
Displayed 50 items.
- ML060680432 (← links)
- ML060590258 (← links)
- ML053070512 (← links)
- ML053070500 (← links)
- ML053070376 (← links)
- ML053070374 (← links)
- ML053070331 (← links)
- ML053070319 (← links)
- ML053070315 (← links)
- ML053070310 (← links)
- ML053070304 (← links)
- ML053070297 (← links)
- ML053070295 (← links)
- ML053070290 (← links)
- ML053070287 (← links)
- ML053070285 (← links)
- ML053070275 (← links)
- ML052350470 (← links)
- 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 (← links)
- 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 (← links)
- 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 (← links)
- L-08-005, Submittal of the 2007 Organizational Safety Culture and Safety Conscious Work Environment Independent Assessment Report for Davis-Besse (← links)
- 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.... (← links)
- L-17-270, Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.46 (← links)
- L-16-229, Submittal of Pressure and Temperature Limits Report, Revision 3 (← links)
- 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) (← links)
- L-14-289, Pressure and Temperature Limits Report. Revision 2 (← links)
- L-11-319, Pressure and Temperature Limits Report (← links)
- L-08-152, Submittal of Technical Specification 6.9.1.12 Steam Generator Tube Inspection Report for January 2008 15th Refueling Outage (← links)
- L-08-105, Reactor Head Inspection Report (← links)
- 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 (← links)
- L-17-088, Independent Spent Fuel Storage Installation Changes, Tests and Experiments (← links)
- 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 (← links)
- L-14-167, Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 2014 (← links)
- L-14-148, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models (← links)
- 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 (← links)
- L-13-154, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models (← links)
- L-13-118, Resubmittal of FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Seismic Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima. (← links)
- L-13-157, Generic Safety Issue 191 Resolution Plan (← links)
- 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 (← links)
- L-12-071, 10 CFR 50.46 Report of Significant Changes or Errors in the Loss of Coolant Accident Evaluation Model (← links)
- L-09-068, Independent Spent Fuel Storage Installation - 10 CFR 72.48 Report of Dry Fuel Storage Facility Changes, Tests, and Experiments (← links)
- L-08-251, 2008 Independent Corrective Action Program Assessment Report, March 2004 Confirmatory Order (← links)
- ML053640317 (← links)
- L-19-189, 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension. (← links)
- ML19255H099 (← links)
- L-08-194, First Energy Nuclear Operating Company Submittal of Engineering Program Effectiveness Assessment Plan for the Davis-Besse Nuclear Power Station - Year 2008 (← links)
- 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 (← links)
- ML053420015 (← links)
- ML052380235 (← links)