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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

• ML18153A940  +
• ML20028H844  +
• ML20064E715  +
• 05000311/LER-1984-010, Corrected LER 84-010-00:on 840423,during Startup Operations, Turbine Trip & Reactor Trip Occurred.Caused by hi-hi Level in Steam Generator 23.Feedwater Flow Nozzle Replaced & All Sys Performed as Designed  +
• ML20140H044  +
• ML20137T144  +
• 0CAN059903, Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with  +
• 2CAN129202, Monthly Operating Rept for Nov 1992 for Arkansas Nuclear One Unit 2  +
• U-602193, Special Rept:On 930927,valid Failure of Div II DG Occurred During Surveillance Testing.Caused by Insufficient Contact Pressure Between Contacting Surfaces.Contact Pressure Checks to Improve Component Reliability Implemented  +
• 05000413/LER-1989-007, :on 890127,turbine Driven Auxiliary Feedwater Pump Failed.Caused by Stress Corrosion Cracking at Key Slot of Final Stage Shaft Sleeve.Shaft Replaced & Feedwater Pump Returned to Svc  +
• 05000382/LER-1988-004, :on 880303,required Environ Seal (Es) Found Missing from Valve Position Indication (Vpi) Conduit.Vpi May Not Have Complied W/Reg Guide 1.97.Caused by Personnel Error Due to Improper Review.Es Installed  +
• 05000293/LER-1997-007, :on 970401,safeguard Buses Were de-energized Due to Severe Storm.Replacement of Microprocessor Control Units Installed in Voltage Regulating Transformers  +
• 05000346/LER-1997-010, :on 970504,Main Transformer Deluge Sys Automatically Actuated Due to Degraded Temp Sensor in Transformer Fire Detection Sys.Replaced Damaged Main Transformer & Sensors That Actuate Deluge Sys  +
• 05000311/LER-1984-011, :on 840428,during Testing Resulting from Two Reactor Trips,Steam Generator 23 Feedwater Flow Indication Channels Unresponsive.Both Channels Declared Inoperable. Feedwater Flow Nozzle Replaced  +
• 05000311/LER-1984-010-01, :on 840423,during Startup Operations,Turbine Trip & Reactor Trip Occurred.Caused by high-high Level in Steam Generator 23.Feedwater Flow Nozzle Replaced & All Sys Performed as Designed  +
• ML20092H085  +
• 05000368/LER-1994-001-01, :on 940312,TS Requirements for Logarithmic Power Level Instrumentation Operability Not Met Due to Inadequate post-maint test.Post-maint Test for Other Channels Tested During Outage in Progress Revised  +
• 05000414/LER-1991-002, :on 910106,work Completed on Valve 2NM-197B & Valve Declared Operable Although Surveillance Expired on 901218.Caused by Inappropriate Action.Valve Stroke Time Tested & Printouts Will Be Reviewed  +
• 05000259/LER-1990-011-01, :on 900720,deenergization of Reactor Protection Sys Bus 1B Occurred.Caused by Inadequate Design of Circuit Protector Setpoint.Setpoints Adjusted to Upper End of Allowable Band & Design Changes Implemented  +
• 05000368/LER-1994-001-04, :on 940312,TS Requirements for Logarithmic Power Level Instrumentation Operability Not Met Due to Inadequate post-maint test.Post-maint Test Methods Enhanced  +
• ML20053A591  +
• 05000440/LER-1993-014, :on 930703,TS 3.0.3 Entered Due to Failure of Racs Power Supply.Replaced 5 Volt Power Supply in Racs Cabinet  +
• 05000336/LER-1991-004-01, :on 910216,unexpected Trip of B Steam Generator Feed Pump & Subsequent Manual Reactor Trip Occurred.Cause Unknown.Monitoring Capability Added to SGFP Circuitry & Design Change Made  +
• 05000311/LER-1989-022-02, :on 891117,determined That Control Power Lockout Circuit for RHR Pump Cold Leg Discharge Valves Did Not Meet Single Failure Criteria.Caused by Inadequate Review.Enhanced Training Program Continuing  +
• 05000369/LER-1981-067, Forwards LER 81-067/03L-0.Detailed Event Analysis Encl  +
• 05000281/LER-1996-005-01, :on 960803,manual Reactor Trip.Caused by Loss of Electro Hydraulic Control Pressure.Repaired Two Compression Fitting Union Connections on Leaking Fitting & Performed Evaluations on Other Tubing  +
• 05000388/LER-2012-004, Regarding Automatic Scram Due to Low Reactor Pressure Vessel Level  +
• 05000269/LER-2011-002, For Oconee Nuclear Station, Regarding Completion of a Shutdown Required by Technical Specifications for an Inoperable Containment Isolation Valve  +
• 05000260/LER-2010-005, For Browns Ferry, Unit 2, Regarding High Pressure Coolant Injection System Isolation Experienced During Performance of High Pressure Coolant Isolation Steam Supply Low Pressure Functional Test  +
• 05000413/LER-1998-011, :on 980723,discovered That Two RWST Level Channels Were Inoperable.Caused by Ground Currents from Lightning Strikes.Level Transmitters Were Replaced & Recalibr & Initiated Compensatory Measures  +
• ML20234E318  +