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

• 05000440/LER-2001-003  +
• 05000293/LER-2001-006  +
• 05000272/LER-1981-018, Forwards LER 81-018/03X-1.Detailed Event Analysis Encl  +
• ML19274D154  +
• ML20040A217  +
• 05000272/LER-1981-018-03, /03X-1:on 810214,diesel Generator 1A Was Declared Inoperable Due to Cooling Water Leak.Caused by Cracked & Leaking Nipple Connecting Jacket Water Valve 1DA45A & Jacket Water Pipe.Nipple Replaced  +
• L-03-096, May 2003 Monthly Operating Report for Beaver Valley, Units 1 & 2  +
• ML20094J251  +
• ML20072N012  +
• ML20066D865  +
• ML20247D145  +
• BECO-90-120, Monthly Operating Rept for Sept 1990 for Pilgrim Nuclear Power Station  +
• BECO-LTR-91-151, Monthly Operating Rept for Nov 1991 for Pilgrim Nuclear Power Station  +
• 05000254/LER-1995-007-07, :on 951020,CRD Scram Discharge Vol Control Logic Failed to Meet Single Failure Criteria.Caused by Design Deficiency.Pif 95-2685 Written to Investigate Cause of Design Deficiency  +
• 05000287/LER-1984-004-02, :on 840607,w/unit at 20% Power,Turbine Generator/Reactor Anticipatory Trip Occurred.Unit Stabilized at Hot Shutdown Conditions.Cause Unknown.Unit Restarted & Reached 100% Power on 840609  +
• 05000482/LER-1994-006, :on 940615,Limitorque Actuators on MOVs in ESW Lines to & from Component Cooling Water HXs Changed Out in Both Safety Trains.Caused by Inadequate Job Scoping. Performance Improvement Request Initiated  +
• 05000461/LER-1994-007, :on 940808,identified That Section 8.3 of Surveillance Test CPS 9031.14 Not Completed Prior to Entry Into Startup Mode Due to Inattention to Detail.Section 8.3 of Surveillance Test CPS 9031.14 Completed  +
• 05000461/LER-1995-001, :on 950105,FW Heater Train Operation During Removal of FW Heater from Svc Was Not Understood & Resulted in Decreased FW Temp,Loss of Heater Level Control & Manual Scram.Plugged 5B FW Heater Tubes  +
• 05000293/LER-1990-013, :on 900902,unplanned Manual Reactor Scram Initiated W/Reactor Power at 60%.Fuse Blew in Feedwater Control Circuit Power Supply Causing Feedwater Regulating Valves to Lockup.Trip Linkage Repaired  +
• 05000293/LER-1990-014, :on 900903,automatic Closing of Primary Containment Sys Group 3 Isolation Valves Occurred While Shut Down.Caused by Transient That Actuated Stated Pressure Switches  +
• 05000271/LER-1993-005, :on 930406,concluded Control Rod Scram Times Not in Compliance W/Ts Section 3.3.C.Caused by Faulty Scram Solenoid Pilot Valves.Solenoid Valves Rebuilt  +
• ML20062K069  +
• 05000293/LER-1993-004, :on 930313,automatic Scram Occurred Resulting from Load Rejection During Severe Coastal Storm While at 100% Power.Caused by Environ Effects of Storm.Trip Settings of Main Input Circuit Breakers Increased  +
• 05000334/LER-1990-008, :on 900401,RCS Letdown Isolation/Esf Actuation Occurred.Erratic Automatic Response of Condenser Steam Valve PCV-MS-106A Caused RCS Temp to Decrease Below Tech Spec Min. Operators Took Manual Control & Shut Valve  +
• 05000353/LER-1990-003, :on 900112,primary Containment & Reactor Vessel Isolation Control Sys Isolation Signals Initiated, Closing Inboard & Outboard Isolation Valves for Rwcu.Caused by Lifting Relief Valve.Opening Time Reset  +
• 05000334/LER-1981-035-03, /03L-0:on 810415,all Three Chlorine Detectors Failed to Meet Min Electrolyte Drip Rate Criteria Specified in Surveillance Test.Caused by Flow of Electrolyte Being Blocked.Wicks Replaced & Glass Orifices Cleaned  +
• 05000346/LER-1979-027-03, /03L-0 on 790216:absolute Position Indication Amplifer for Rod 9 of Group 5 Was Inoperable.Caused by Failure of Integrated Circuit Chip in Amplifier.Integrated Circuit Chip Replaced  +
• 05000281/LER-1993-002-03, :on 930620,automatic Trip Occurred Due to Low SG Water Level Coincident W/Steam/Feedwater Flow Mismatch Resulting from Main FW Pump Trip.Cr Operators Promptly Initiated Appropriate EOPs  +
• 05000316/LER-1987-008-01, :on 870722,ESF Actuation Occurred Due to Extreme High Level in Steam Generator 24.Caused by Erratic Response of Main Feedwater Pump Delta P Controller. Plant Procedures Implemented  +
• 05000316/LER-1994-005-01, :on 940815,unit 2 Received Reactor Trip Signal from Steam Generator Number 23 Low Feedwater Flow Coincident W/Low SG Level.Caused by Zebra Mussels within Circulating Water Sys That Blocked Cooling Flow  +
• 05000445/LER-2016-002, Regarding Unanalyzed Condition Involving Potential Moderate Energy Line Break  +
• 05000271/LER-1991-014, Hearing - Entergy Exhibit 19, LER 1991-014-00, Vermont Yankee, Reactor Scram Due to Loss of 345KV Switchyard Caused by Defective Off-Site Carrier Equipment  +
• ML031690051  +
• ML112240823  +