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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
- ML20117L601 + (ML20117L601)
- ML20117L639 + (ML20117L639)
- ML20117L671 + (ML20117L671)
- 05000352/LER-1985-042-01, :on 850402,w/unit in Startup at 2% Power,Esf Actuation Occurred.Caused by Control Room D Chlorine Detector Failure Due to Broken Sample Tape.Mods to Detector Under Investigation + (ML20117L678)
- 05000352/LER-1985-043, :on 850402,hourly Fire Watch Required for Missing Internal Conduit Seals for Telephone Lines Not Performed within Time Specified by Tech Spec 3/4.7.7.Caused by Personnel Error.Individual Counseled + (ML20117L686)
- 05000244/LER-1985-006-01, :on 850406,during Startup from Refueling Outage,Reactor Trip & Turbine Trip Occurred.Caused by Steam Generator B Level Below 30% W/Tripped Feedwater Flow Less than Steam Flow Bistable,Per Procedure CP-477 + (ML20117L705)
- ML20117L717 + (ML20117L717)
- ML20117L718 + (ML20117L718)
- ML20117L721 + (ML20117L721)
- ML20117L727 + (ML20117L727)
- 05000374/LER-1985-014-04, :on 850409,spurious Div I RHR Shutdown Cooling Isolation Occurred.Caused by Momentary Power Loss to Relay 2B21H-K74 During Installation of Environ Qualification Mod M-1-2-84-117.Work Completed 850414 + (ML20117L729)
- ML20117L737 + (ML20117L737)
- ML20117L750 + (ML20117L750)
- ML20117L769 + (ML20117L769)
- ML20117L780 + (ML20117L780)
- 05000244/LER-1985-008, :on 850407,reactor Tripped on Low Steam Generator Level.Caused by Operations Personnel Inability to Maintain Steam Generator Levels Above Trip Setpoints While Transferring Level Control + (ML20117L787)
- 05000373/LER-1985-035-01, :on 850411,main Turbine Tripped from Bearing 11 High Vibration Signal,Causing Reactor Scram.Probable Direct Cause Was Loose Connection,Aggravated by Slight Vibration Detector Miscalibration & Imbalance + (ML20117L797)
- ML20117L799 + (ML20117L799)
- 05000244/LER-1985-007, :on 850406,reactor Tripped & Turbine Failed to Automatically Trip.Caused by Steam Generator Level B Reducing Below 17% Narrow Range Level.Caused by Mechanical Binding of 20ET Trip Solenoid + (ML20117L820)
- ML20117L838 + (ML20117L838)
- ML20117L847 + (ML20117L847)
- 05000278/LER-1985-010-01, :on 850410,diesel Generators E-1 & E-3 Started & Drywell Coolers Tripped After Receiving False Reactor Low Level Signal.Caused by Defective Test Equipment Used During Surveillance Test.Generators Shut Down + (ML20117L853)
- 05000374/LER-1985-017-02, :on 850413,Group 6 Isolation of RHR Shutdown Cooling Suction Inboard 2E12-F009 & Outboard 2E12-F008 Valves & Shutdown Cooling Injection Valve Occurred.Caused by Incorrect Wiring of Pressure Switch + (ML20117L873)
- 05000374/LER-1985-018-02, :on 850413,isolation of Shutdown Cooling Initiated When Broken Lug on Pressure Switch Being Repaired Grounded,Blowing Fuse to Div I Group 6 Isolation Logic.Fuse Replaced & Lug Repaired + (ML20117L891)
- ML20117L901 + (ML20117L901)
- ML20117L918 + (ML20117L918)
- ML20117L927 + (ML20117L927)
- ML20117L928 + (ML20117L928)
- 05000333/LER-1996-006-01, :on 960511,isolation of Reactor Core Isolation Cooling Sys Occurred.Caused by Failure of Master Trip Unit. Master Trip Unit Replaced W/Vendor Current Model + (ML20117L933)
- 3F0996-09, Provides Schedule for Revised Response & Description of Interim LTOP Controls in Place at CR-3,per GL 88-11 + (ML20117L937)
- B11533, Responds to Request for Addl Info Re Matl Engineering Branch Question 250.12 Re Ultrasonic Insp Technique Used as Part of Plant Preservice Insp Program.Ultrasonic Demonstration Perfomed on 841109 Per SER Confirmatory Item 19 + (ML20117L947)
- ML20117L953 + (ML20117L953)
- ML20117L970 + (ML20117L970)
- 05000382/LER-1996-005-01, :on 960323,restricted Air Flow Rendered Wet Cooling Tower Fans Inoperable.Caused by Installation of Temporary Netting.Temporary Netting Removed & Personnel Counseled + (ML20117L974)
- ML20117L979 + (ML20117L979)
- ML20117L999 + (ML20117L999)
- 1CAN069605, Forwards Proprietary B&Wog Rept 51-1240140-00, Reactor Vessel Missile Shield Removal Rept. Rept Withheld Per 10CFR2.790 + (ML20117M030)
- ML20117M047 + (ML20117M047)
- ML20117M059 + (ML20117M059)
- U-602631, Informs of Resignation of Lr Rippy,SOP-31019-1,effective 960913 + (ML20117M060)
- ML20117M078 + (ML20117M078)
- 05000325/LER-1996-010-01, :on 960813,load Side Conductors Installed on EDG 1 Normal DC Control Power Breaker 8 Were Improperly Secured.Cause Not Known.Edg 1 Normal DC Control Power 8 Load Side Conductors Were Properly Terminated + (ML20117M083)
- 05000354/LER-1996-008, :on 920510,plant Operated W/Control Rod Withdrawal Speeds Outside of Design Basis.Caused by mis-adjustment of Control Rod Drive Sys Flow Control Needle Valves.Rods Properly Set within UFSAR Limits + (ML20117M086)
- 05000354/LER-1996-006, :on 920120,side Backdraft Isolation Dampers Installed Backwards.Caused by Construction Error.Restored Backdraft Isolation Dampers to Design Configuration + (ML20117M090)
- 05000353/LER-1996-004-02, :on 960514,reactor Scram Resulted from Main Generator Lockout Due to Actuation of Voltz/Hertz Relay. Caused by Inadequate Design Change Package.Relay 359/381A Drawing Corrected & Relays Inspected + (ML20117M094)
- 05000416/LER-1985-016, :on 850407,reactor Scrammed Due to Full Steam Line Isolation.Caused by Faulty Pressure Transmitter in Div 2,producing Erroneous Isolation Signal.Transmitter Cleaned,Reterminated,Calibr & Returned to Svc + (ML20117M104)
- ML20117M108 + (ML20117M108)
- ML20117M114 + (ML20117M114)
- ML20117M116 + (ML20117M116)
- ML20117M121 + (ML20117M121)
- ML20117M126 + (ML20117M126)