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A list of all pages that have property "Title" with value "Final Precursor Analysis - Palisades". Since there have been only a few results, also nearby values are displayed.

Showing below up to 26 results starting with #1.

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List of results

  • ML20087N344  + (Final Potentially Reportable Deficiency 157 Re Broken/ Cracked Corbel Supporting Missile Shield Above Main/ Emergency Feed Line.Initially Reported on 840224.Condition Not Reportable Per 10CFR50.55(e))
  • W3P85-1442, Final Potentially Reportable Deficiency Rept 180 Re Failure to Maintain Adequate Control of Vendor Manuals.Initially Reported on 840918.Preventive Maint Program Implemented.Item Not Reportable Per 10CFR50.55(e)  + (Final Potentially Reportable Deficiency Rept 180 Re Failure to Maintain Adequate Control of Vendor Manuals.Initially Reported on 840918.Preventive Maint Program Implemented.Item Not Reportable Per 10CFR50.55(e))
  • ML20072C086  + (Final Potentially Reportable Deficiency Rept 99 Re Magnetrol Model Ldn Level Switch Design.Level Switches Not Class IE Devices & Not Required for Safe Shutdown.Condition Not Reportable Per 10CFR50.55e)
  • ML20087F871  + (Final Potentially Reportable Deficiency Rept 150 Re Problem W/Alarm Setpoints for Low Temp Protection Sys.Initially Reported on 840210.Condition Not Reportable Per 10CFR50.55(e))
  • ML20083N183  + (Final Potentially Reportable Deficiency Rept 153 Re Boston Insulated Wire & Cable Co QA Program Deficiencies.Initially Reported on 840215.Program Audited & Deemed Satisfactory. Item Not Reportable Per 10CFR50.55(e))
  • ML20087Q106  + (Final Potentially Reportable Deficiency Rept 154 Re Possible Inadequate Circuit Design That Could Prevent Reactor Trip. Initially Reported on 840216.Further Evaluation Indicates Condition Not Reportable Per 10CFR50.55(e))
  • ML17346A085  + (Final Pre-App TS Markups)
  • ML102700473  + (Final Precursor Analysis - Braidwood 2- Loss of Offsite Power Coincident with Reactor Trip Due to Loss Reactor Coolant Pump)
  • ML051790348  + (Final Precursor Analysis - Brunswick)
  • ML081350025  + (Final Precursor Analysis - Brunswick 2 (LER 324/06-001))
  • IR 05000317/2004008  + (Final Precursor Analysis - Calvert Cliffs 2, LER 318/04-001-00; IR 05000317-04-008 and 05000318-04-008 - Excessive Steam Demand - Reactor Trip Due to Low Steam Generator Water Level After Feed Pump Trip)
  • ML062710039  + (Final Precursor Analysis - Columbia Generating Station, LER 397/05-004)
  • ML060240407  + (Final Precursor Analysis - Dresden Unit 3 - Unit 3 Scram Due to Loss of Offsite Power and Subsequent Inoperability of the Standby Gas Treatment System for Units 2 and 3)
  • ML050950555  + (Final Precursor Analysis - Fermi Grid Loop)
  • ML050950565  + (Final Precursor Analysis - Fitzpatrick Grip Loop)
  • ML050960036  + (Final Precursor Analysis - Ginna Grid Loop)
  • ML062710045  + (Final Precursor Analysis - Grand Gulf, Unit 1)
  • ML051190633  + (Final Precursor Analysis - Hope Creek)
  • ML062710037  + (Final Precursor Analysis - Hope Creek Nuclear Generating Station, Manual Reactor Scram Due to Moisture Separator Reheater Drain Line Failure)
  • ML050960041  + (Final Precursor Analysis - IP-2 Grid Loop)
  • ML050960051  + (Final Precursor Analysis - IP-3 Grid Loop)
  • ML060240375  + (Final Precursor Analysis - Kewaunee Nuclear Power Plant - Both Emergency Diesel Generators Inoperable for 28 House)
  • ML050960242  + (Final Precursor Analysis - NMP-1 Grid Loop)
  • ML050960252  + (Final Precursor Analysis - NMP-2 Grid Loop)
  • ML051190518  + (Final Precursor Analysis - Nine Mile Point 1)
  • ML060240389  + (Final Precursor Analysis - Palo Verde 1, 2, 3 - Emergency Core Cooling System Piping Voids May Have Prevented Fulfillment of Safety Function)
  • ML051790379  + (Final Precursor Analysis - Palo Verde Nuclear Generating Station, Units 1, 2, & 3)
  • ML060240384  + (Final Precursor Analysis - Peach Bottom, Unit 3 - Automatic Reactor Scram Due to Momentary Loss of Offsite Power)
  • ML060240394  + (Final Precursor Analysis - Peach Botton 3 - Loss of High Pressure Coolant Injection System Function as a Result of an Inoperable Flow Controller)
  • ML051190665  + (Final Precursor Analysis - Perry)
  • ML050960263  + (Final Precursor Analysis - Perry Grid Loop)
  • ML062710038  + (Final Precursor Analysis - River Bend Station, LER-458/04-005-01, Automatic Reactor Trip Due to Loss of Non-Vital 120V Instrument Bus)
  • ML062710041  + (Final Precursor Analysis - Saint Lucie Units 1 and 2 (LER 355/04-004)Dual Unit Loss of Offsite Power During Hurricane Jeanne)
  • ML051790376  + (Final Precursor Analysis - Surry 1 & 2 Unanalyzed Condition Related to Loss of RCP Seal Cooling During an Appendix R Fire Event)
  • ML082610715  + (Final Precursor Analysis - Surry 2 (LER 281/06-002))
  • ML062710030  + (Final Precursor Analysis - Vogtle Electric Generating Station Unit 2 (LER 425/04-004)Automatic Reactor Trip Followed by Safety Injection)
  • ML051190648  + (Final Precursor Analysis - Waterford)
  • ML062710035  + (Final Precursor Analysis - Waterford Plant Loss of Offsite Power in Mode 4 During Hurricane Katrina)
  • ML13060A208  + (Final Precursor Analysis Catawba)
  • ML060720146  + (Final Precursor Analysis, LER 341/03-002, Automatic Reactor Trip and Loss of Offsite Power Due to the August 14, 2003, Transmission Grid Blackout)
  • ML13059A525  + (Final Precursor Analysis, Transformer and Breaker Failures Cause Loss of Offsite Power, Reactor Trip, and De-Energized Safety Buses)
  • ML112411358  + (Final Precursor Analysis: Concurrent Unavailabilities - EDG B Inoperable Due to Failed Output Breaker and EDG a Unavailable Due to Testing and Maintenance)
  • ML112411359  + (Final Precursor Analysis: Electrical Fault Causes Fire and Subsequent Reactor Trip with a Loss of Reactor Coolant Pump Seal Injection and Cooling)
  • ML112411361  + (Final Precursor Analysis: Manual Reactor Scram Due to Leakage from the Circulating Water System and Subsequent Flooding of the Condenser Bay)
  • ML21237A463  + (Final Presentation Slides for August 26, 2021 Advanced Reactor Stakeholder Public Meeting)
  • ML20133B970  + (Final Programmatic EIS for Uranium Mill Tailings Remedial Action Ground Water Project. Vols I & II)
  • ML19343C359  + (Final Programmatic Environmental Impact Statement Related to Decontamination and Disposal of Radioactive Wastes Resulting from the March 28,1979,ACCIDENT at Three Mile Island Nuclear Station,Unit 2)
  • ML20003C732  + (Final Programmatic Environmental Impact Statement Related to Decontamination and Disposal of Radioactive Wastes Resulting from the March 28,1979,ACCIDENT at Three Mile Island Nuclear Station,Unit 2)
  • ML11168A164  + (Final Progress Report, Radiological Environmental Monitoring Program for Davis-Besse Nuclear Power Station, January-December, 2010)
  • ML091480343  + (Final Progress Report, Radiological Environmental Monitoring Program, Oak Harbor, Ohio, Reporting Period: January - December, 2008)
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