Search by property

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 44385  +
• ML17317A743  +
• ML20024F102  +
• ML072640612  +
• ML19274D154  +
• ML043020589  +
• ML20097B492  +
• ML20117K960  +
• ML20116K233  +
• ML20140H676  +
• ML20065K013  +
• IR 05000213/1987002  +
• ML20248B542  +
• IR 05000346/1985023  +
• ML20217B985  +
• 05000338/LER-1987-016-01, :on 870814,determined That Redundant Butterfly Valves in Turbine Overspeed Protection Sys Would Not Have Properly Isolated Steam Between 870629-870710.Caused by Inadequate Maint Procedures.Procedures Revised  +
• IR 05000354/1987008  +
• 05000400/LER-1987-006, :on 870123,charging/safety Injection Pumps 1B-SB & 1C-SAB Declared Inoperable Due to Failed Attempts to Automatically Start Train 1B-SB Chiller.Caused by Chiller Tripping on Overload.Plant Cooldown Initiated  +
• 05000254/LER-1986-037, :on 861205,butt Splices Supplied W/Ge Penetration Assemblies Failed to Remain Intact During Qualification Testing Performed by Wyle Labs.Caused by Use of Nylon Insulation.Butt Splices Taped  +
• 05000316/LER-1986-016, :on 860429,in Mode 6 W/Core Unloaded,Esf & Reactor Trip Signals Received.Caused by Shorted Control Power Wires to power-range Nuclear Instrument Drawer.Insps of Electrical Connectors Conducted  +
• 05000293/LER-1992-014, :on 921124,automatic Actuation of Inboard & Outboard RWCU Sys Portion of Primary Containment Isolation Sys Occurred,Resulting in Closing Group 6 Valves.Caused by Procedure Deficiency.Procedure Revised  +
• 05000265/LER-1995-006-07, :on 951004,feed Breaker for Motor Control Ctr at Switchgear Tripped from Current Overlaod.Caused by Trip Setting Too Low for Given Plant.Motor Control Ctr Restored & Exit LCO  +
• 05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified  +
• 05000423/LER-1990-020, :on 900614,both Trains of Quench Spray & High Pressure Safety Injection Declared Inoperable.Caused by Deficient Surveillance Procedure.Surveillance Procedure on Svc Water Sys HXs Changed  +
• 05000414/LER-1990-009-03, :on 900723,source Range Neutron Flux Monitors (Srnf) Discovered to Be Operating W/O Audible Count Rate Indication.Caused by Failure to Ensure That Srnf Monitors Audible Multiplier Switch Positioned on  +
• ML19344E393  +
• ML19337A508  +
• NUREG-0227, Partial Draft of Nuclear Power Plant Operating Experience - 1978, Section 3.0, Plant Outages. Portions of NUREG-0483, NUREG-0366 & NUREG-0227 (Plant Operating Experience for 1977,1976 & 1974-75,respectively) Encl  +
• 05000311/LER-1990-029, :on 900628,reactor Trip Occurred Following Loss of Generator Feedwater Pumps Resulting from Failure of Volt Transformer.Caused by Inadequate Preventive Maint.Design Change Concerns Reviewed by Mgt  +
• 05000296/LER-1998-004-01, :on 981007,primary Containment Allowable Leak Rate Was Exceeded.Caused by Failure of Check Valve to Fully Seat Following Shutdown of Rbbccw Sys for Llrt.Valve Was Retested During Next Refueling Outage.With  +
• ML17193A638  +
• 05000499/LER-2015-001, Regarding Technical Specification Action Statement Time Exceeded Due to Turbine-Driven Auxiliary Feedwater Pump Test Failure Not Recognized  +
• ML19305E734  +
• ML19318B125  +
• ML20049J384  +
• 05000254/LER-1992-011-03, :on 920530,Unit 1 in Shutdown Mode Performing Cooldown to Cold Condition for Maint Outage.Caused by Procedural Inadequacy.Cooldown Rate Minimized & Thermocouple Replaced  +