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 41692  +
• 05000325/LER-2005-004  +
• ML14093A189  +
• ML13297A103  +
• ML073320364  +
• RA-05-021, Co. 2004 Radiological Reports  +
• ML19320B998  +
• ML050460289  +
• ENS 45986  +
• ML031480618  +
• ML031130008  +
• ML042080125  +
• ML20077Q127  +
• ML20095C699  +
• IR 05000250/2020002  +
• ML20149E864  +
• ML20238E459  +
• ML20237E620  +
• ML20235T020  +
• NL-89-046, Forwards Rept of 1988 Annual Emergency Exercise Conducted on 881003.Exercise Included Util & Offsite Agency Participation & Was Evaluated by NRC & FEMA  +
• JAFP-87-0534, Reactor Containment Bldg Integrated Leakage Rate Test Types A,B & C Periodic Test  +
• RBG-43-503, Forwards Nonroutine Repts Sent to Other Agencies,Per App B (Environ Protection Plan) to River Bend Station License NPF-47  +
• 1CAN098305, Monthly Operating Rept for Aug 1983  +
• ML23251A016  +
• 05000416/LER-1989-006, :on 890505,reactor Tripped on Low Reactor Water Level.Caused by Vessel Overfeed Due to Feedwater Heater Outlet Valves Not Fully Closed But Indicated as Closed. Design Changes to Feedwater Logic Evaluated  +
• 05000293/LER-1999-008-02, :on 990805,automatic Scram Occurred While at 100% Power Due to Automatic Turbine Trip.Caused by Malfunction of Moisture Separator Drain Tank a Drain Valve Controller.Level Controllers Replaced.With  +
• 05000461/LER-1986-024, :on 861210,Group I Containment Isolation Signal Generated Resulting in Closure of Main Steam Drain Valves B21-F016 & B21-F019.Caused by Failure of Maint Planners to Review Documents When Preparing Impact Matrix  +
• 05000413/LER-1986-028, :on 860606,unidentified RCS Leakage Exceeded Tech Spec Limit of 1 Gpm.Caused by Seal 2 Becoming Unseated. Reactor Coolant Drain Tank Level Transmitter Recalibr & Seal 2 Reseated  +
• 05000414/LER-1998-006-04, :on 981021,rod Control Sys Malfunction Occurred Due to Failed Card Leading to Manual Reactor Trip & Esf. Reactor Startup Was Suspended & Troubleshooting Efforts Were Initiated & Slave Cycler Lift Decoder Card Was Replaced  +
• 05000498/LER-1988-019, :on 880212 & 13 Unit Cooldown to Satisfy Tech Spec 3.0.3 Prematurely Terminated.Caused by Personnel Error. Addl Guidance for Determining Equipment Operability & Special Training Held  +
• 05000331/LER-1985-044, :on 851105,RCIC Taken Out of Svc to Modify RCIC-to-vessel Inject Valve Circuitry.Repair Completed.On 851107,RCIC Tripped on Electrical Overspeed.Caused by Setpoint Drift on Overspeed Trip Monitor  +
• 05000397/LER-1985-033, :on 850525,noise Spike in Intermediate Range Monitor Channels Resulted in Reactor Protection Sys Actuation.Caused by Movement of Intermediate Range Monitor by Water Spray.Caution Signs to Be Put in Area  +
• 05000265/LER-1995-005-09, :on 950825,Units Experienced Automatic Reactor Scram During EHC Pressure Regulator fail-over Test.Caused by Inadequate EHC Sys Pressure Regulator Setpoint Bias.Adjusted EHC Sys Pressure Setpoint Bias & Time Lag Constants  +
• 05000353/LER-1990-015-02, :on 900910,reactor Scram Occurred Due to Spurious Trip Signal from Steam Leak Detection Sys Temp Switch.Caused by Equipment Failure.Temp Switch TTS-25-216D Was Replaced  +
• 05000272/LER-1981-062, Forwards LER 81-062/03l-0.Detailed Event Analysis Encl  +
• ML20030A487  +
• PLA-8058, Annual Radiological Environmental Operating Report (PLA-8058)  +
• 05000397/LER-1993-002, :on 930121,low RPV Level Reactor Scram Initiated by RPS in Response to Low Water Level Condition. Caused by Inadvertent Actuation of Deluge Sys.Plant Procedure PPM 8.3.120 Will Be Revised  +
• 05000397/LER-1993-003, :on 930121,determined That Under Certain Ac Electrical Distribution Sys Alignments,Fault Could Result in Unavailability of Both Offsite Power Sources.Caused by Inadequate Sys Analysis.Delay Times Revised  +
• 05000280/LER-2010-003, For Surry Power Station, Regarding Loss of Vital Bus Due to Human Error Results in Automatic Reactor Trip  +
• BSEP 05-0059, Request for Notice of Enforcement Discretion Technical Specification 3.4.5, RCS Leakage Detection Instrumentation  +
• 05000293/LER-1999-008-01, Regarding Automatic Scram at 100 Percent Power Due to Turbine Trip  +
• BVY-04-036, March 2004 Monthly Operating Report from Vermont Yankee  +
• 05000389/LER-2003-006, Regarding Long-Standing 2C TDAFW Pump Design Issue Resulted in Condition Prohibited by Technical Specifications  +
• 05000389/LER-2003-005, Regarding Automatic Reactor Trip Due to Loss of Turbine Generator Excitation  +
• ML16214A216  +
• 05000272/LER-1983-026-03, /03L-0:on 830530,containment Fan Coil Unit (Cfcu) 17 Svc Water Flow Observed Below Tech Specs.Cfcu Declared Inoperable.Caused by Valve 15SW57 Being Plugged W/Shells & Debris from Cleaning of Svc Water Sys  +
• ENS 57925  +