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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
- ML20070F484 + (ML20070F484)
- 05000368/LER-1991-005, :on 910201,automatic Reactor Trip Initiated by Core Protection Calculators.Caused by Faulty Racking Motor. Racking Motor Removed from Svc & Inspected,Design Engineering Reviewed & Enhanced Sys Design + (ML20070F485)
- 05000338/LER-1982-077, Forwards LER 82-077/03L-0 + (ML20070F489)
- RBG-34552, Discusses Concern W/Configuration of Automatic Start Signal for Main Control Room Area Ventilation Sys in Emergency Mode of Operations,Identified on 910212.One Charcoal Filter Train Placed in Continuous Operation + (ML20070F493)
- ML20070F504 + (ML20070F504)
- 05000313/LER-1982-024, Forwards LER 82-024/03L-0 + (ML20070F505)
- ML20070F511 + (ML20070F511)
- ML20070F515 + (ML20070F515)
- RBG-34553, Requests That New Date of Submittal of plant-specific Hydrogen Control Final Analysis Be within 6 Months of Hydrogen Control Owners Group Accepted Topical Rept + (ML20070F520)
- 05000313/LER-1982-024-03, /03L-0:on 821104,at 68% Power,Control Rod Drive B Ac Breaker Failed to Trip.Caused by Latch Adjusting Screw Being Improperly Adjusted.Breaker Replaced + (ML20070F521)
- ML20070F524 + (ML20070F524)
- 05000361/LER-1991-001-01, :on 910125,post-accident Cleanup Unit Inlet Duct Heater Found in Off Position,Resulting in Deenergization of Heater.From 910119-22,operability of Heater Pilot Switch Not Satisfied + (ML20070F528)
- 05000338/LER-1982-077-03, /03L-0:on 821119,MOV-1536 Could Not Be Opened After Period Test.Caused by Loose Control Cable Connection at Motor Operator.Loose Connection Tightened + (ML20070F530)
- ML20070F535 + (ML20070F535)
- ML20070F537 + (ML20070F537)
- ML20070F538 + (ML20070F538)
- ML20070F541 + (ML20070F541)
- 05000335/LER-1982-057, Forwards LER 82-057/03L-0 + (ML20070F544)
- RBG-13-927, Interim Deficiency Rept Re Violation of Requirements for Min Spacing Between Drills in Anchors & Adjacent Embedment Plates.Initially Reported on 821109.Investigation Re Reporting Criteria Continuing.Next Rept Expected by 830127 + (ML20070F549)
- ML20070F555 + (ML20070F555)
- 05000416/LER-1982-063-99, /99X-1:on 820902,during Shutdown,Several fire- Rated Cable Penetration Seals Were Broken on Field Termination Cabinets in Control Room to Allow Routing of Addl Cable.Seals Repaired Following Maint Activities + (ML20070F564)
- IR 05000344/1982006 + (ML20070F570)
- 05000335/LER-1982-057-03, /03L-0:on 821114,dose Equivalent I-131 Exceeded Tech Spec 3.4.8.a Limit After Reactor Trip.Caused by Iodine Buildup in Primary Coolant Due to Power Transient After Operation W/Nominal Fuel Leakage + (ML20070F574)
- ML20070F579 + (ML20070F579)
- 05000416/LER-1982-132-01, /01T-0:on 821130 & 1202,several fire-rated Electrical Penetrations Found Open.Penetration Openings Authorized by Maint Work Orders W/O Notifying Control Room. Instructions Issued to Responsible Persons + (ML20070F593)
- 05000368/LER-1982-037, Forwards LER 82-037/03L-0 + (ML20070F598)
- 05000333/LER-1994-005-01, :on 940623,determined That Test Results Exceeded 1 Percent Tolerance Allowed by TS for Valve Actuation.Caused by Leakage.Replaced SRV Pilot Assemblies W/Recertified Assemblies + (ML20070F607)
- 05000321/LER-1982-098-03, /03L-0:on 821108,discovered That Liquid Radwaste Monitor Instrument Procedures Not Performed Monthly.Caused by Inadequate Procedures.Correct Procedures Performed Monthly + (ML20070F611)
- 05000368/LER-1982-037-03, /03L-0:on 821110,during Low Power Testing in Mode 2,breaker to Operating Charging Pump 2P36A Tripped. Caused Unknown.Resistance Checks of All Motor Leads & Windings Revealed No Abnormalities + (ML20070F620)
- ML20070F622 + (ML20070F622)
- ML20070F624 + (ML20070F624)
- 05000250/LER-1982-018, Forwards LER 82-018/01T-0 + (ML20070F635)
- 05000446/LER-1994-007, :on 940617,ESF Actuation Occurred Due to hi-hi Steam Generator Level.Caused by Inadequate Procedures. Procedures Revised to Include Required Parameters for Monitoring Prior to Opening MSIVs + (ML20070F655)
- 05000250/LER-1982-018-01, /01T-0:on 821201,during Full Power operation,3A Load Ctr de-energized Following Trip of 4-kV Breaker 3AA08. Cause Undetermined.Breaker Protective Relays Will Be Tested During Next Outage + (ML20070F657)
- ML20070F664 + (ML20070F664)
- ML20070F666 + (ML20070F666)
- ML20070F669 + (ML20070F669)
- ML20070F671 + (ML20070F671)
- NRC-94-4175, Forwards Nonproprietary & Proprietary AP600 Design Change Description Rept. Proprietary Portion Withheld (Ref 10CFR9.17(a)(4)). Proprietary Portion of Document Sent to Westinghouse + (ML20070F680)
- 05000333/LER-1994-004-01, :on 940609,determined That Single Failure of Reactor Vessel Low Level or High Drywell Pressure Isolation Control Logic.Caused by Inadequate Design Documentation. UFSAR Will Be Updated + (ML20070F695)
- ML20070F707 + (ML20070F707)
- 05000277/LER-1991-004-01, :on 910202,emergency Svc Water Pump B Received Unexpected Automatic Start Signal.Caused by Use of Wrong Control Switch to Close Pump Breaker During Surveillance.Procedure Revised + (ML20070F712)
- 05000416/LER-1982-021-99, /99X-1:on 820720,limiting Condition for Operation Entered Due to Quarterly Test of Radioactive Liquid Effluent Monitoring Sys Not Being Performed by 820720.Caused by Inadequate Sys Design.Design Change Implemented + (ML20070F714)
- 05000336/LER-1982-044, Forwards Updated LER 82-044/03X-1 + (ML20070F724)
- ML20070F729 + (ML20070F729)
- ML20070F732 + (ML20070F732)
- ML20070F734 + (ML20070F734)
- ML20070F735 + (ML20070F735)
- 05000336/LER-1982-044-03, While Performing in-core Detector Alarm Update,Alarm Values Updated Incorrectly, Resulting in Nonconservative Alarm Values for in-core Detectors.Caused by Plant Calorimetric out-of-svc + (ML20070F740)
- 05000259/LER-1991-002-01, :on 910201,discovered That Reactor/Turbine Bldg Ventilation Radiation Monitor 1-RM-90-250 Did Not Contain Particulate Filter & Charcoal Cartridge.Caused by Personnel Error.Filter Holder Assembly Replaced + (ML20070F741)
- 05000265/LER-1994-005-06, :on 940621,reactor Manually Scrammed & Main Turbine Manually Tripped Due to Anticipation of Low EHC Control Oil Pressure.Replacement of EHC Lines to 2 Control Valve & Replaced Flared Fittings + (ML20070F743)