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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
- 05000280/LER-2011-001, Regarding Reactor Trip on Both Units Due to Loss of Offsite Power +
- ML19210F002 +
- ML19211C915 +
- ML19337A834 +
- ML19345D655 +
- ML20044C042 +
- ML20077H720 +
- ML20140C349 +
- ML20125D334 +
- ML20149E209 +
- ML20245B737 +
- ST-HL-AE-5393, Special Rept:On 960130,standby DG 11 Valid Failure Caused by Failed op-amp IC Chip on Preposition Board.Voltage Regulator & Preposition Board Replaced +
- ST-HL-AE-5310, Special Rept:On 960130,voltage for Sdg Increased to 4600 Vac Exceeding Expected Emergency Mode Setting of 4160 Vac. Caused by Faulty Instantaneous Preposition Board.Sent Failed Voltage Regulator & Preposition Board Offsite for Analysis +
- 05000414/LER-1988-018, :on 880427,feedwater Isolation Occurred While Cycling Steam Generator power-operated Relief Valve.Caused by Receipt of 2 Out of 4 Channels Indicating Hi Hi Level. Affected Valves Realigned +
- 05000325/LER-1989-011, :on 890404,determined That Reactor Jet Pump Once Per 24 H Operability Surveillance Had Been Missed Prior to Entering Operation Condition 2.Caused by Inadequate Review of Surveillance Rept +
- 05000413/LER-1987-028, :on 870711,reactor Automatically Tripped on Inadvertently Simulated Turbine Trip.Caused by Failure of Disk Dump Valve to Reseat.Mod Installed to Main Turbine Valves & All Disk Valves Will Be Inspected +
- 05000414/LER-1987-009, :on 870312,containment Air Return Isolation Dampers Actuated.Caused by Defective Procedure.Isolation Dampers Closed & Auxiliary Safeguards Test Cabinet Periodic Test Procedure Changed +
- ML20236U446 +
- 05000266/LER-1986-005-01, :on 861117,reactor Tripped Due to Loss of Power on Red Instrument Bus.Caused by Failure of Control Circuit Diode in Bus Inverter.Diodes Replaced +
- 05000414/LER-1988-018-01, :on 880427,steam Generator 2C hi-hi Level Turbine Trip Signal Occurred & Feedwater Isolation Initiated.Cause Unknown.Affected Valves Realigned & Feedwater Isolation Reset +
- 05000413/LER-1997-005-01, :on 970623,violation of TS 4.0.5 Was Determined.Caused by Inadequate Surveillance Procedure. Affected Check Valves Were Successfully Tested for Reverse Flow Prevention +
- 05000331/LER-1985-029, :on 850812,during Diesel Fire Pump Operability Test,Leak Detected in Fire Main Outside Reactor Bldg.Caused by Air Hammer.Portion of Fire Main Isolated to Initiate Repairs +
- 05000395/LER-1985-022, :on 850824,reactor Trip Occurred on Steam Generator a lo-lo Level.Caused by Requirement to Maintain Min Values of Feedwater Flow & Temp During Startup.Feedwater & Condensate Sys Evaluation Program Initiated +
- 05000413/LER-1992-010, :on 920820,emergency Low Level Signal for Nuclear Svc Water Sys Intake Pit B Initiated Automatic Swap to Svc Water Pond.Possibly Caused by Design Deficiency.Pump Secured,Valve Opened & Sys Realigned +
- 05000499/LER-1992-003, :on 920224,feedwater Flow Oscillations Observed on turbine-driven SG Feedwater Pump 23,resulting in Reactor Trip.Caused by Rain Water Leaking Through Expansion Joints.Control Sys Dried Out +
- 05000293/LER-1991-021, :on 911009,RCIC Declared Inoperable Due to Lack of Sufficient Battery Charger Test Data.Caused by Unavailability of Backup Battery Charger.Alarm Response Procedure for Alarm Window I4 Changed +
- 05000272/LER-1981-071-03, /03L-0:on 810720,containment Fan Coil Unit Declared Inoperable.No Svc Water Flow Noted at High Speed & Insufficient Flow at Low Speed.Caused by Equipment Failure. Flow Transmitter FA-3543Z-1 Sensing Line Blown Clear +
- 05000272/LER-1981-071, Forwards LER 81-071/03L-0.Detailed Event Analysis Encl +
- 05000280/LER-1991-020, :on 910821,potential Failure of Charging/High Head Safety Injection Pumps to Start Automatically in DBA Identified.Caused by Inadequate Review of Interlock Design. Operational Changes Being Reviewed +
- 05000400/LER-1995-009-01, :on 951005,unanticipated Actuation of ESF Components While in Refueling Outage 6 Due to Defective Retest Procedure.Revised Temporary Procedure to Reset SI Signal +
- 05000316/LER-1988-004, :on 880420,discovered Six of Twenty Main Steam Safety Valves Lift Setpoints Out of Spec During Surveillance Testing.Caused by Testing Method & Setpoint Drift.Safety Valves Setpoints Reset +
- 05000397/LER-1990-009, :on 900430,three Separate Spurious Trips of RPS Electrical Protection Assembly (EPA) Circuit Breaker Occurred.Caused by Degraded Component in Logic Board of Epa. RPS-EPA-3F Breaker & Logic Board Replaced +
- IR 05000220/1988002 +
- ML16341E326 +
- ML20248M102 +