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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 46656 +
- 05000412/LER-2013-001, Gas Void in Emergency Core Cooling System Pump Suction Header Results in a Condition Prohibited by Technical Specifications +
- 05000311/LER-1991-004-02, :on 910218,radiation Monitoring Sys intermediate-range Vent Monitor 2R45B Spiked High,Causing Channel 2R41 to Deenergize.Caused by Damaged Cable Shield Connection.Detector Cable Replaced +
- ML19340E717 +
- ML20027A590 +
- ML19350A883 +
- ML20004F713 +
- ML20041E313 +
- ML20082F566 +
- ML20081C014 +
- ML20117N648 +
- ML20133H174 +
- ML20129C364 +
- ML20127N210 +
- ML20154H315 +
- ML20206L898 +
- ML20247L784 +
- ML22240A090 +
- ML22240A085 +
- ML22240A084 +
- 05000324/LER-1986-022-01, :on 861003,reactor Shut Down Due to Unsuccessful Restart of Motor Generator Set.Caused by Opened Fuses.Fuse 7 Transformer Replaced,Motor Generator Restarted & Loop Returned to Svc +
- 05000213/LER-1987-002, :on 870301,nuclear Instrumentation Sys Power Range Channel 32 Spuriously Generated Dropped rod-load Runback Signal.Caused by a Degraded High Voltage Vernier Adjust Potentiometer.Channel Drawer Replaced +
- 05000266/LER-1983-002-01, /01T-0:on 830308,emergency Diesel 3D Failed to Start During Testing.On 830309,diesel Declared out-of-svc, Then Successfully Started.Caused by Faulty Type UG8 Woodward Governor.Procedures Revised Pending Replacement +
- 05000269/LER-1985-007-02, :on 850425,reactor Tripped from 94% Full Power When Both Main Feedwater Pumps Tripped on High Discharge Pressure.Caused by Static Inverter & Related Static Transfer Switch.Components Replaced +
- 05000416/LER-1984-057, :on 841221,reactor Scram Occurred When Condensate Pumps & Booster Pumps Tripped.Caused by Inability of Precoat Filters to Provide Required Sys Flow for Pumps. Condensate Operating Instructions Revised +
- 05000336/LER-1996-001, :on 960625,discovered Reactor Coolant Sys Heatup Rate Exceeded Tech Spec.Caused by Design & Procedural Weaknesses Re Plant Heatup Controls.Revised Plant Operating Procedures & Heatup/Cooldown Computer Program +
- 05000374/LER-1984-080, :on 841121,vacuum Breaker 2PC001A Tripped & Containment Venting Occurred.Caused by Primary Containment Chiller Trip.Pressure Equalized & Breaker Closed +
- 05000339/LER-1992-011, :on 920421,unit Entered Mode 3 from Mode 4 Due to SG Channel II Trip.Caused by Personnel Error Due to Failure to Consult Applicable Ts.Channel Returned to Tripped Condition.Ts Change Package Will Be Submitted +
- ML20055J227 +
- 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 +
- 05000412/LER-1990-021, :on 901113,ESF Actuation & Feedwater Isolation Occurred During MSIV Stroke Testing.Caused by Operator Error.Feedwater Isolation Signal Reset & Isolation Valves Reopened +
- ML20028E250 +
- 05000301/LER-1980-012-03, /03L-0:on 801202,slippage Found in Shaft Driven Seal Water Pump Impeller Resulting in Overheating of Throttle Bushing.Caused by Reduced Seal Water Flow Due to Loosening of Pumping Ring.Shaft Sleeve & Bushing Replaced +
- ML20043H721 +
- 05000272/LER-1978-070-01, /01T-0:on 781021,during Mode 4 Operation,While Heating Up to Enter Mode 3,high Flow Through RCP Seals Noted & Alarms Went Off Indicating RCS Leakage.Cause Unknown +
- 05000413/LER-2006-003, Re Technical Specification Violations Associated with Hydrogen Ignition System +
- ML20059F971 +
- NL-20-0843, License Amendment Request to Revise the Required Actions of Technical Specifications 3.8.1, AC Sources - Operating, for One-Time Extension of Completion Time for Unit 1 and Swing Emergency Diesel Generators +
- 05000269/LER-1985-002-02, :on 850122,unit Tripped from 100% Full Power When All Six Intercept Valves Closed for Unknown Reasons Causing High Turbine Header Pressure Which Resulted in High RCS Pressure +
- 05000382/LER-1989-024, :on 891223,reactor Trip Occurred Due to Loss of Feedwater Flow to Steam Generator.Caused by Anomaly in MFRV Pneumatic Control Sys Aggravated by Cold Water.Ia Task Force Reassembled +