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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

• 05000251/LER-1985-001, :on 850102,containment Isolation Valve SV-2819 Failed to Close at 100% Power Upon Receiving Containment Ventilation Isolation Signal.Caused by Dirt Buildup on Contacts in Lockout Relay.Contacts Cycled  + (ML20102A005)
• 05000454/LER-1985-004, :on 850102,during Mode 5,component Cooling Sys Surge Tank Level Rapidly Decreased Due to Const Personnel Unbolting RHR Sys HX Flange.Caused by Improper Review of out-of-svc Procedures  + (ML20102A019)
• ML20102A021  + (ML20102A021)
• B14184, Documents Commitment in 920303 Application for Amend to License NPF-49,revising TS Re Surveillance Requirements for Reactor Trip Sys & Esfas,Per 920624 Telcon W/Nrc.Review Will Be Performed of Plant Past 1 Yr Surveillance Records  + (ML20102A023)
• ML20102A024  + (ML20102A024)
• ML20102A025  + (ML20102A025)
• 05000293/LER-1992-007, :on 920618,during Quarterly Functional Test, RCIC Sys Made Inoperable Per TS Due to Loose Temp Switch Terminal.Caused by Repeated Torquing of Terminal Screw. Circuitry to Be Changed for Frequent Calibr  + (ML20102A057)
• PY-CEI-NRR-0184, Forwards Rev 3 to 1958, Fire Protection Evaluation Rept. Rev Provides Updated Info on Fire Protection Features, Including Fire Barriers,Suppression & Detection Sys.Rept Will Be Updated as Necessary After Safe Shutdown Analysis  + (ML20102A067)
• ML20102A079  + (ML20102A079)
• 05000416/LER-1992-013, :on 920618,reactor Scram Occurred Due to Turbine Control Fluid Filter Maint.Caused by Lack Of/Poor Communication.Preventative Maint Program Will Be Established  + (ML20102A083)
• ML20102A146  + (ML20102A146)
• ML20102A161  + (ML20102A161)
• ML20102A164  + (ML20102A164)
• ML20102A173  + (ML20102A173)
• ML20102A188  + (ML20102A188)
• ML20102A195  + (ML20102A195)
• ML20102A206  + (ML20102A206)
• ML20102A208  + (ML20102A208)
• RBG-20-034, Forwards Change to FSAR Section 6.2.6.5.1 Re Upcoming Drywell Bypass Leakage Test.Change Provides Max Allowable Leakage Rates & Revised Min Duration for Tests.Min Test Duration Reduced Per Listed Bases  + (ML20102A209)
• ML20102A218  + (ML20102A218)
• ML20102A220  + (ML20102A220)
• ML20102A223  + (ML20102A223)
• HL-2225, Application for Amends to Licenses DPR-57 & NPF-5,revising TSs to Add Addl Electrical Sys Requirements,Per Generic Ltr 91-11, Resolution of Generic Issues 48, LCOs for Class 1E & 49, Interlocks & LCOs for Class 1E Tie Breakers..  + (ML20102A226)
• ML20102A234  + (ML20102A234)
• ST-HL-AE-4155, Forwards Change QA-010 to Operations QA Plan.Change Will Be Incorporated in Operations QA Plan in Next Annual Update  + (ML20102A235)

• ML20102A237  + (ML20102A237)

• ML20102A239  + (ML20102A239)
• ML20102A241  + (ML20102A241)
• ML20102A242  + (ML20102A242)
• ML20102A248  + (ML20102A248)
• B14180, Forwards Rev to 911017 Requests for Relief from Second 10-yr Inservice Insp Testing Program.Encl Describes Alternate Testing for Centrifugal Charging Pump Measurements & Vibration Monitoring  + (ML20102A249)
• ML20102A250  + (ML20102A250)
• PY-CEI-NRR-1517, Forwards Perry Nuclear Power Plant Individual Plant Exam, Per Generic Ltr 88-20.Plant Improvements Made Due to Individual Plan Exam Insights Listed on Encl  + (ML20102A251)
• ML20102A256  + (ML20102A256)
• ML20102A258  + (ML20102A258)
• 05000321/LER-1992-017, :on 920626,determined That Requirements of Unit 1 TS Table 3.2-8,item 3 Not Being Met.Caused by Less than Adequate Procedures.Wiring Changes Will Be Implemented & Procedure 57SV-D11-007-2S Will Be Revised  + (ML20102A270)
• 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)