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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

• ML20102A271  + (ML20102A271)
• ML20102A272  + (ML20102A272)
• ML20102A273  + (ML20102A273)
• BECO-92-075, Responds to NRC Bulletin 92-001, Failure of Thermo-Lag 330 Fire Barrier Sys to Maintain Cabling in Wide Cable Trays & Small Conduits Free from Fire Damage. Thermo-Lag Matl Not Installed at Facility  + (ML20102A276)
• ML20102A280  + (ML20102A280)
• ML20102A283  + (ML20102A283)
• HL-2322, Forwards Response to NRC Bulletin 92-001, Failure of Thermo-Lag 330 Fire Barrier Sys to Maintain Cabling in Wide Cable Trays & Small Conduits Free from Fire Damage. Fire Watch for Drywell Access Room Will Be Performed  + (ML20102A284)
• ML20102A285  + (ML20102A285)
• 05000278/LER-1991-017-01, :on 910924,MSRV SV Wiring Insulation Was Discovered to Be Degraded Due to Improper Installation. Caused by Temp Increase from Insulation Installation.Thermal Insulation Was Properly Reinstalled  + (ML20102A286)
• 05000366/LER-1992-008-01, :on 920620,RWCU Isolation Signal Was Received Resulting in Group 5 Primary Containment Isolation Sys Actuation.Caused by Component Failure.Components Replaced & Controller Was Calibrated Satisfactorily  + (ML20102A289)
• ML20102A293  + (ML20102A293)
• RBG-37217, Forwards Rev 0 to RS-91-137, RCIC Reliability Analysis, River Bend Nuclear Station. Rept Submitted as Followup to Sys Reliability Program Presentation at Facility on 920623 & Will Serve as Addl Info for Remick to Clarify Questions  + (ML20102A297)
• ML20102A298  + (ML20102A298)
• RS-91-137, Rev 0 to RCIC Reliability Analysis,River Bend Nuclear Station  + (ML20102A302)
• ML20102A314  + (ML20102A314)
• ML20102A318  + (ML20102A318)
• ML20102A319  + (ML20102A319)
• HL-2314, Forwards Revs 10C to FSAR Updates for Units 1 & 2  + (ML20102A321)
• ML20102A322  + (ML20102A322)
• ML20102A328  + (ML20102A328)
• ML20102A330  + (ML20102A330)
• ML20102A336  + (ML20102A336)
• 05000331/LER-1992-010, :on 920617,RW Pump Circuit Failure Caused Fire to Break Out in 1B20 Load Center.Caused by Inadequate Review of Breaker Disconnect Compatability W/Load Ctr Cubicle Stabs in Design.Procedural Revisions Re Design Made  + (ML20102A343)
• ML20102A345  + (ML20102A345)
• ML20102A350  + (ML20102A350)

• ML20102A353  + (ML20102A353)

• HL-2315, Responds to NRC Re Violations Noted in Insp Rept 50-321/92-12.Corrective Actions:On 920507 Clearances 1-92-539 & 2-92-381 Were Issued on Control Switches for Excess Flow Check Valves 1B21-F051C & 2B21-F051C  + (ML20102A355)
• ML20102A359  + (ML20102A359)
• JPN-92-040, Forwards Summary of IGSCC Insp During 1992 Refueling Outage. Core Spray Piping B in Primary Containment Replaced w/347 Modified Stainless Steel.Electrochemical Potential Monitoring Sys Installed in Reactor Water Recirculation Sys  + (ML20102A365)
• ML20102A369  + (ML20102A369)
• 05000346/LER-1992-005, :on 920619,hourly Fire Watch of Inoperable Fire Barriers Exceeded Allowable Interval by Five Minutes.Caused by Personnel Error.Importance of Fire Watch Patrol During Surveillance or Maint Reiterated W/Individual  + (ML20102A372)
• ML20102A375  + (ML20102A375)
• ML20102A383  + (ML20102A383)
• ML20102A385  + (ML20102A385)
• ML20102A394  + (ML20102A394)
• 05000278/LER-1992-004-03, :on 920625,HPCI Sy Declared Inoperable Due to High Water Level in Turbine Casing.Level in HPCI Turbine Exhaust Drain Pot Will Be Monitored & Maintained at Normal Level Using Drain Valve  + (ML20102A402)
• ML20102A407  + (ML20102A407)
• ML20102A409  + (ML20102A409)
• ML20102A413  + (ML20102A413)
• RBG-19-972, Forwards Action Plan to Address Addl Containment Issues as Final Response to NRC 820623 & 0723 Ltrs.Ser Confirmatory Item 14 Re Mark III Related Issues Also Addressed.Info from 1/10th Scale Testing Program Included Re Concerns 1.1-1.7  + (ML20102A415)
• ML20102A418  + (ML20102A418)
• ML20102A420  + (ML20102A420)
• ML20102A432  + (ML20102A432)
• ML20102A440  + (ML20102A440)
• ML20102A455  + (ML20102A455)
• ML20102A459  + (ML20102A459)
• 05000498/LER-1992-006-01, :on 920318,discovered That All Four Auxiliary Feedwater Flow Control Valves in Closed Position Following Reactor Trip on 920314.Caused by Inattention to Detail. Valves Opened & Reactor Trip Procedure Revised  + (ML20102A466)
• ML20102A467  + (ML20102A467)
• ML20102A473  + (ML20102A473)
• ML20102A476  + (ML20102A476)
• ML20102A481  + (ML20102A481)