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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

• ENS 43708  + (Safety System Valve Did Not Operate as Expected)
• ENS 50778  + (Safety System Will Not Function as Required)
• ENS 51006  + (Safety Systems Declared Inoperable Due to Equipment Malfunction)
• Information Notice 1993-17, Safety Systems Response to Loss of Coolant and Loss of Offsite Power  + (Safety Systems Response to Loss of Coolant and Loss of Offsite Power)
• ML19332F454  + (Safety Team Audit on 890724-0804.No Regulatory Findings Noted.Several Concerns Re Potential Interfacing Sys LOCA (ISLOCA) Events Identified.Areas Audited:Equipment, Activities & Human Performance Re ISLOCA)
• IR 05000456/1989018  + (Safety Team Insp Rept 50-456/89-18 on 890612-0706.No Violations or Deviations Noted.Major Areas Inspected: Instrumentation Sys for Assessing Plant Conditions During & Following Accidents as Specified in Reg Guide 1.97,Rev 3)
• ML20262K195  + (Safety Valve & Atmospheric Relief Piping. Sheet 1)
• 05000298/LER-2018-003, Safety Valve Failure Results in Loss of Safety Function  + (Safety Valve Failure Results in Loss of Safety Function)
• ML20262J964  + (Safety Valve Piping - Main Coolant System, as-built.Sheet 1)
• ML20262J965  + (Safety Valve Piping - Main Coolant System. Sheet 2)
• ML17324A228  + (Safety Valve for Main Stream Service)
• Information Notice 1999-26, Safety and Economic Consequences of Misleading Marketing Information  + (Safety and Economic Consequences of Misleading Marketing Information)
• ML24207A174  + (Safety and Regulatory Considerations for On-Site Hydrogen Production Facilities Co-located with Nuclear Power Plants)
• ML20059A742  + (Safety of Nuclear Power Plants in Russia & Eastern Europe)
• ML19322C385  + (Safety of Nuclear Reactors, Presented at United Nations 550808-20 Conference on Peaceful Uses of Atomic Energy in Geneva,Switzerland)
• IR 05000254/2023011  + (Safety-Conscious Work Environment Issue of Concern Team Inspection Report 05000254/2023011 and 05000265/2023011)
• 05000254/FIN-2011009-03  + (Safety-Related Battery Charger Testing and Maintenance Procedures Did Not Include Steps for Electrolytic Capacitor Replacement)
• 05000338/FIN-2010002-02  + (Safety-Related Breaker Cubicle Fire Issue)
• 05000424/LER-2020-001, Safety-Related Electrical Bus Deenergizing Results in Emergency Diesel Generator Starting  + (Safety-Related Electrical Bus Deenergizing Results in Emergency Diesel Generator Starting)
• Information Notice 1994-68, Safety-Related Equipment Failures Caused by Faulted Indicating Lamps  + (Safety-Related Equipment Failures Caused by Faulted Indicating Lamps)
• ML20003H194  + (Safety-Related Equipment Qualification Post-NRC Audit Documentation, Vol 6)
• ML20003A834  + (Safety-Related Equipment Qualification:Post-NRC Audit Documentation)
• ML20071D637  + (Safety-Related Instrument Setpoint Methodology for Balance of Plant Equipment)
• ML17276B098  + (Safety-Related Mechanical Equipment List:Seismic Qualification Info)
• 05000259/FIN-2009008-03  + (Safety-Related Molded Case Circuit Breakers)

• ML20214K681  + (Safety-Related Motor-Operated Valve Program)

• ML19308C235  + (Safety-Related Operator Action, Draft.Prepared for DOE & NRC)
• ML20031A211  + (Safety-Related R&D for C-E PWRs 1979/80 Program Summaries)
• ML20150A820  + (Safety-Related R&D for Westinghouse Pwrs,Program Summaries)
• ML19257C468  + (Safety-Related Reactor Physics Studies of Nasap Heavy Water Reactor, Informal Rept for Oct 1979)
• ML19290E851  + (Safety-Related Reactor Physics Studies of Nasap Heavy Water Reactor)
• Regulatory Guide 1.243  + (Safety-Related Steel Structures and Steel-Plate Composite (Sc) Walls for Other than Reactor Vessels and Containments)
• ML24080A099  + (Safety-Relief Valve Failure Mechanism ROP March 2024 (Scarbrough) Final.Pptx)
• 05000302/LER-1983-053-03, Safety-related Hydraulic Snubber MSH-252 Declared Inoperable When Lack of Oil Level Indication Noted in Sightglass.Caused by Loose jam-nut on Stationary End of Snubber,Allowing Rotation  + (Safety-related Hydraulic Snubber MSH-252 Declared Inoperable When Lack of Oil Level Indication Noted in Sightglass.Caused by Loose jam-nut on Stationary End of Snubber,Allowing Rotation)
• ML18087A737  + (Safety-related, Response Time Test of Solid State Protection Sys Logic-Reactor Trip,Train a)
• ML18087A738  + (Safety-related, Response Time Test of Solid State Protection Sys Logic-Reactor,Train B)
• ML18087A730  + (Safety-related, Solid State Protection Sys Train A,Reactor Trip Breaker UV Coil Functional Test)
• ML18087A732  + (Safety-related, Solid State Protection Sys Train B,Reactor Trip Breaker UV Coil Functional Test)
• ML20266C166  + (Safety/Relief Valve B Air Supply Upgrade)
• JPN-90-017, Safety/Relief Valve Challenges & Failures for 1989  + (Safety/Relief Valve Challenges & Failures for 1989)
• ML20266C186  + (Safety/Relief Valve F Air Supply Upgrade)
• ML20027D262  + (Safety/Relief Valve Quencher Loads:Evaluation for BWR Mark II and III Containments)
• ML20127N722  + (Safety/Safeguards Interactions During SAFETY-RELATED Emergencies at Nuclear Power Reactor Facilities)
• Information Notice 2005-33, Safety/Security Interface - Managing Risk  + (Safety/Security Interface - Managing Risk)
• 05000263/FIN-2014009-04  + (Safety/Security Interface Assessment Failure)
• ML19218A010  + (Safkeg 3977A, Structural Evaluation)
• ML19218A017  + (Safkeg-HS 3977A, Acceptance Tests and Maintenance Program)
• ML19218A012  + (Safkeg-HS 3977A, Containment)
• ML19218A015  + (Safkeg-HS 3977A, Criticality Evaluation)
• ML19289A806  + (Safkeg-HS 3977A, General Information (Redacted))
• ML19218A016  + (Safkeg-HS 3977A, Package Operations)