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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
- 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)
- ML20070F744 + (ML20070F744)
- ML20070F748 + (ML20070F748)
- ML20070F750 + (ML20070F750)
- 05000387/LER-1982-005, Forwards LER 82-05L/03L-0 + (ML20070F751)
- ML20070F755 + (ML20070F755)
- ML20070F758 + (ML20070F758)
- 05000387/LER-1982-051-03, /03L-0:on 821107,during Startup Testing of RCIC Sys,Controller Functioning But Could Not Be Transferred to Automatic Mode.Caused by Controller Not Being Tuned at Rated Conditions.Controller Calibr & Testing Completed + (ML20070F765)
- ML20070F774 + (ML20070F774)
- 05000293/LER-1982-054, Forwards LER 82-054/03L-0 + (ML20070F788)
- PY-CEI-NRR-1322, Submits Revised Schedule Commitment for Submittal of Hydrogen Control Final Analysis Rept.Based on Hydrogen Control Owners Group Schedule,Rept Will Be Submitted within 6 Months After Generic Response Submittal Date + (ML20070F797)
- ML20070F800 + (ML20070F800)
- 05000339/LER-1982-074, Forwards LER 82-074/03L-0 + (ML20070F804)
- ML20070F807 + (ML20070F807)
- RBG-34-559, Rev 1 to Ro:On 900905,discovered Cracked Turbocharger Axial Strut Support Plate on South End of Diesel Mfg by Transamerica Delaval,Inc.Caused by Improper fit-up Between Plate & Pipe Strut.Support Plate Redesigned & Installed + (ML20070F814)
- ML20070F825 + (ML20070F825)
- ML20070F829 + (ML20070F829)
- ML20070F834 + (ML20070F834)