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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- Information Notice 1986-99, Degradation of Steel Containment + (Degradation of Steel Containment)
- ENS 55769 + (Degradation of Technical Support Center)
- Information Notice 1995-41, Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam Generators + (Degradation of Ventilation System Charcoal Resulting from Chemical Cleaning of Steam Generators)
- Information Notice 1988-88, Degradation of Westinghouse Ard Relays + (Degradation of Westinghouse Ard Relays)
- Information Notice 2009-20, Degradation of Wire Rope Used in Fuel Handling Applications + (Degradation of Wire Rope Used in Fuel Handling Applications)
- 05000338/FIN-2009003-01 + (Degradation of a Flood Protection Feature)
- 05000338/FIN-2009004-03 + (Degradation of a Flood Protection Feature)
- ENS 46168 + (Degradation of an Item Relied on for Safety)
- 05000338/FIN-2009002-01 + (Degradation of the Containment Sump)
- ML022760189 + (Degradation of the Davis-Besse Nuclear Power Station Reactor Pressure Vessel Head Lessons-Learned Report - Appendices A-D)
- ML022740211 + (Degradation of the Davis-Besse Nuclear Power Station Reactor Pressure Vessel Head Lessons-Learned Report Memo to: William F. Kane, Deputy Executive Director for Reactor Programs)
- ML022760219 + (Degradation of the Davis-Besse Nuclear Power Station Reactor Pressure Vessel Head Lessons-Learned Report - Appendices E-F)
- ML022760172 + (Degradation of the Davis-Besse Nuclear Power Station Reactor Pressure Vessel Head Lessons-Learned Report)
- ML022760305 + (Degradation of the Davis-Besse Nuclear Power Station Reactor Pressure Vessel Head Lessons-Learned Report - Signature Page)
- ENS 40277 + (Degradation of the Reactor Coolant System (Rcs) Pressure Boundary)
- ENS 49861 + (Degradation of the Technical Support Center Ventilation System)
- Information Notice 1986-79, Degradation or Loss of Charging Systems at PWR Nuclear Power Plants using Swing-Pump Designs + (Degradation or Loss of Charging Systems at PWR Nuclear Power Plants using Swing-Pump Designs)
- Information Notice 1986-79, Degradation or Loss of Charging Systems at PWR Nuclear Power Plants Using Swing-Pump Designs + (Degradation or Loss of Charging Systems at PWR Nuclear Power Plants Using Swing-Pump Designs)
- ENS 55914 + (Degradation to a Fuel Element Cladding)
- ENS 57321 + (Degraded Reactor Vessel Closure Head Penetration)
- 05000259/FIN-2010005-02 + (Degraded 1C RHR Motor Rendered One RHR Subsystem Inoperable Beyond the TS Allowed Outage Time)
- Information Notice 1995-35, Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation + (Degraded Ability of Steam Generators to Remove Decay Heat by Natural Circulation)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in Bwrs + (Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in Bwrs)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in BWRs + (Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in BWRs)
- Information Notice 2015-01, Degraded Ability to Mitigate Flooding Events + (Degraded Ability to Mitigate Flooding Events)
- ENS 46646 + (Degraded Accident Mitigation Due to Safety Injection Out of Service)
- Information Notice 2002-22, Degraded Bearing Surfaces in Gm/Emd Emergency Diesel Generators + (Degraded Bearing Surfaces in Gm/Emd Emergency Diesel Generators)
- ENS 48111 + (Degraded Charging Line Socket Welds Based on Thermal Fatigue Analysis)
- Information Notice 1989-79, Degraded Coatings and Corrosion of Steel Containment Vessels + (Degraded Coatings and Corrosion of Steel Containment Vessels)
- ENS 42547 + (Degraded Condition)
- ENS 56371 + (Degraded Condition)
- ENS 56774 + (Degraded Condition)
- ENS 57369 + (Degraded Condition)
- ENS 57583 + (Degraded Condition)
- ENS 57695 + (Degraded Condition)
- ENS 57906 + (Degraded Condition)
- ENS 58102 + (Degraded Condition)
- 05000251/LER-2025-001-01, Degraded Condition + (Degraded Condition)
- ENS 40689 + (Degraded Condition - Greater than One Percent of Steam Generator Tubes Defective)
- ENS 43172 + (Degraded Condition - 30% Through Wall Indication on Reactor Recirc Nozzle)
- ENS 46379 + (Degraded Condition - 71% Through Wall Indication on Reactor Recirc Nozzle)
- ENS 48772 + (Degraded Condition - Containment Penetration Fails Local Leak-Rate Testing)
- ENS 43369 + (Degraded Condition - Degradation of Principal Safety Barrier)
- ENS 40659 + (Degraded Condition - Greater than One Percent of Steam Generator Tubes Defective)
- ENS 42437 + (Degraded Condition - Indication on Primary Coolant System Pressure Boundary Weld)
- ENS 56434 + (Degraded Condition - Leak Rate Limits Exceeded)
- ENS 41413 + (Degraded Condition - Reactor Building Normal Sump Level Increasing)
- ENS 42003 + (Degraded Condition - Small Leak on Rhr Injection Drain Line)
- ENS 56834 + (Degraded Condition - Two Steam Generator Tube Failures Identified)
- ENS 45719 + (Degraded Condition - Weld Leak Due to Vibrating Valve Attachment Wire)
- ENS 49351 + (Degraded Condition Caused by Rhr Relief Valve Leakage)
- ENS 49796 + (Degraded Condition Discovered on Pressurizer Nozzle Weld During Testing)
- ENS 51747 + (Degraded Condition Discovered on Pressurizer Safety Relief Valve Weld)
- ENS 55506 + (Degraded Condition Discovered on Reactor Vessel Head Penetration)
- ENS 50079 + (Degraded Condition Discovered on Reactor Vessel Head Control Rod Drive Penetration)
- ENS 55706 + (Degraded Condition Discovered on Shutdown Cooling Test Line)
- ENS 56257 + (Degraded Condition Discovered on Shutdown Cooling Test Line)
- 05000255/LER-2012-001, Degraded Condition Due to Control Rod Drive Mechanism Housing Assembly Crack + (Degraded Condition Due to Control Rod Drive Mechanism Housing Assembly Crack)
- ENS 45107 + (Degraded Condition Due to Discovery of Pressure Boundary Leakage)