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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
- IR 05000346/2011005 +
- ML15182A012 +
- ML12058A249 +
- ML12044A361 +
- ML16050A291 +
- ML17320A667 +
- ML091960177 +
- ML18141A057 +
- ML19209C236 +
- ML19260A135 +
- ML19345D398 +
- ML20052G660 +
- ML20052G120 +
- ML112380514 +
- ML20046A389 +
- ML033430329 +
- ML031110294 +
- ML20086G656 +
- ML20085D760 +
- ML20081B969 +
- ML20078K260 +
- ML20094L104 +
- ML20106E576 +
- ML20090J213 +
- ML20112H414 +
- ML20140E959 +
- ML20128K650 +
- ML20069A089 +
- IR 05000412/1986007 +
- ML20234A900 +
- ML20216G820 +
- IR 05000352/1985099 +
- 05000414/LER-1987-030-01, :on 871105,feedwater Isolation Signal Generated in hi-hi Steam Generator.Caused by Technician Failure to Correctly Identify Root Valve Associated W/Inoperable Level Transmitter.Root Valve Reopened +
- 05000245/LER-1986-017-01, :on 860521,during Downpowering of Planned Shutdown,Reactor Pressure Dropped Briefly Then Increased Rapidly to 1,047 Psig,Causing Manual Reactor Scram.Rate Stop Adjustment Screws Replaced +
- 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 +
- 05000293/LER-1992-014, :on 921124,automatic Actuation of Inboard & Outboard RWCU Sys Portion of Primary Containment Isolation Sys Occurred,Resulting in Closing Group 6 Valves.Caused by Procedure Deficiency.Procedure Revised +
- 05000397/LER-1984-125, :on 841127,during Reactor Feed Pump Testing at 95% Power,Reactor Power Fluctuations Resulted in Low Pressure Feedwater Heater 4C High Level Trip.Power Reduced +
- 05000414/LER-1992-001-01, :on 920115,Unit 2 Turbine/Reactor Trip Occurred During Main Turbine Hydraulic Oil Sys Testing.Caused by Possible Equipment Failure/Malfunction.Corrected Maint & Troublingshooting on Sys +
- 05000414/LER-1992-002-01, :on 920115,unexpected ESF Actuation Occurred. Cause Unknown.Recorder Installed to Capture Event Should It Recur While in Steam Pressure Mode +
- 05000254/LER-1992-004-03, :on 920207,Unit 1 Reactor Scram Occurred Due to Group I Isolation.Caused by Spurious Main Steam Line High Flow Trip Due to Unknown Cause.Applicable Instruments Calibr & Functionally Verified +
- 05000269/LER-1983-021-03, /03L-0:on 831225,borate Water Storage Tank Level Channel 1 Failed Low When Moisture in Instrument Airlines Froze,Giving Incorrect Level Indications.Caused by Strip Heaters Deenergizing Due to Tripped Breaker +
- 05000277/LER-1991-025, :on 910728,isolation of HPCI Sys Occurred During Performance of Surveillance Test,Resulting in ESF Actuation.Caused by Failure to Follow Procedures & Procedural Weaknesses.Procedures Revised +
- 05000382/LER-1991-019, :on 910825,reactor Trip Occurred on Loss of Power to Control Element Drive Mechanism Motor Generator Sets.Caused by Unforseen Design Problem.Mod Considered by Sys Engineering to Replace Pushbutton +
- 05000302/LER-1990-011, :on 900705,determined That on 900615 Plant Ascended from Mode Iv,Hot Shutdown to Mode III Hot Standby W/Only One Operable Reactor Bldg Cooler Unit.Caused by Personnel Error.Selectro Switch Realigned +
- 05000368/LER-1993-002-02, :on 931022,discovered That Containment Sump Integrity Inadequate to Prevent Entry of Foreign Matl. Caused by Initial Const Deficiency.Temporary Mod Installed to Provide Plates Over Holes +
- ML20011F135 +
- IR 05000334/1981015 +
- ML19343D001 +
- NUREG-0227, Partial Draft of Nuclear Power Plant Operating Experience - 1978, Section 3.0, Plant Outages. Portions of NUREG-0483, NUREG-0366 & NUREG-0227 (Plant Operating Experience for 1977,1976 & 1974-75,respectively) Encl +
- ML19257B288 +