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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
- AECM-85-0099, Forwards Final Response to NRC 841212 Request for Addl Info Re BWR Owners Group Rept,In Response to NUREG-0737,Item II.D.1, Analysis of Generic BWR Safety Relief Valve Operability + (ML20100F365)
- ML20100F366 + (ML20100F366)
- ML20100F374 + (ML20100F374)
- ML20100F380 + (ML20100F380)
- ML20100F382 + (ML20100F382)
- ML20100F388 + (ML20100F388)
- 05000325/LER-1996-002, :on 960123,manual Reactor Scram Occurred Due to Main Turbine Vibration.Caused by Rubs in the Lpt Diaphram & Shaft Packing.Addl Vibration Monitoring Equipment Installed + (ML20100F394)
- ML20100F401 + (ML20100F401)
- ML20100F419 + (ML20100F419)
- ML20100F425 + (ML20100F425)
- 2CAN042001, Withdrawal of Inservice Testing Requests for Alternative + (ML20100F427)
- ML20100F430 + (ML20100F430)
- 05000321/LER-1984-024-01, :on 841025,six Safety Relief Valves Failed to Lift within Plus/Minus 1% Tolerance Range Required by Tech Specs.Caused by Corrosion & Removal of Pilot Assembly Bolts by Personnel.Valves Refurbished + (ML20100F431)
- ML20100F432 + (ML20100F432)
- ML20100F434 + (ML20100F434)
- ML20100F440 + (ML20100F440)
- BSEP-95-0668, Provides Results of Confirmatory Testing Response for NRC Bulletin 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode + (ML20100F441)
- ML20100F444 + (ML20100F444)
- 05000333/LER-1984-023, :on 841104,w/reactor at Approx 30% Power Following Outage,Reactor Trip Occurred Due to Reactor Vessel Low Water Level.Caused by Malfunctioning Condensate Bypass Flow Controller + (ML20100F447)
- 05000331/LER-1984-039, :on 841101,during Normal Operation,Reactor Water Cleanup Sys Isolated Due to Momentary Spurious Signal in Reactor Water Cleanup Isolation Logic.Cause Unknown.Sys Free of Valid Isolation Parameters + (ML20100F452)
- ML20100F455 + (ML20100F455)
- ML20100F456 + (ML20100F456)
- ML20100F457 + (ML20100F457)
- 05000247/LER-1984-016, :on 841016,during Rod Withdrawal at Conclusion of Maint Refueling Outage,Steam Generator Delta P Signal Tripped Reactor.Caused by Lifting of Safety Relief Valve on Secondary Side + (ML20100F465)
- ML20100F466 + (ML20100F466)
- ML20100F467 + (ML20100F467)
- RBG-19468, Interim Deficiency Rept DR-203 Re Arc Strikes on Interior Surface of Seven of Eight Air Start Receiver Tanks on Standby Diesel Generators Supplied by Tdi.Next Rept Will Be Submitted by 841220 + (ML20100F469)
- 05000327/LER-1984-055, :on 840817 & 20,during Work on Storage Facility for Plant Maint Insulators,Doors A028 & A029 Left Open. Caused by Personnel Failure to Realize Outer Door Part of Vital Area Boundary.Procedure Revised + (ML20100F472)
- ML20100F473 + (ML20100F473)
- ML20100F474 + (ML20100F474)
- ML20100F475 + (ML20100F475)
- ML20100F480 + (ML20100F480)
- ML20100F483 + (ML20100F483)
- ML20100F484 + (ML20100F484)
- ML20100F485 + (ML20100F485)
- 05000327/LER-1984-068, :on 841104,inadvertent Relay Actuation Caused Auxiliary Bldg Ventilation Isolation.Caused by Relay Not Fully Seated on Terminal Block.Relay Placed Back Into Correct Position.Isolation Reset + (ML20100F486)
- 05000282/LER-1984-010-01, :on 841029,steam Generator Tube Leakage Occurred.Probably Caused by Intergranular Attack in Tubesheet Crevice Region.Leaking Tubes Plugged.Several Tubes Will Be Removed for Analysis + (ML20100F492)
- 05000247/LER-1984-017, :on 841021,reactor Trip Occurred During Turbine Generator Overspeed Test.Caused by Operator Using Wrong Gauge During Test.Facility Stabilized at Hot Shutdown Conditions + (ML20100F496)
- ML20100F497 + (ML20100F497)
- ML20100F501 + (ML20100F501)
- ML20100F502 + (ML20100F502)
- ML20100F512 + (ML20100F512)
- ML20100F513 + (ML20100F513)
- RBG-19470, Interim Deficiency Rept DR-215 Re Uninterruptible Power Supply Inverters Supplied by Elgar Corp.Next Rept Will Be Submitted by 850123 + (ML20100F522)
- 05000255/LER-1984-015, :on 840804,loss of Electrohydraulic Control Fluid Pressure Resulted in Turbine Trip & Automatic Reactor Trip.Caused by Loose Fitting on Discharge Line Due to Personnel Error.Bracket Replaced + (ML20100F524)
- ML20100F526 + (ML20100F526)
- ML20100F531 + (ML20100F531)
- ML20100F532 + (ML20100F532)
- 05000458/LER-1996-004, :on 960115,CI of Various BOP Valves Occurred Due to Inattention to Detail.I&C Technician Counseled + (ML20100F537)
- ML20100F545 + (ML20100F545)
- ML20100F549 + (ML20100F549)