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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
- IR 05000295/1993005 + (ML20035B925)
- 05000424/LER-1993-002-01, :on 930313,lift Setpoint for Valve 1PSV-8010B Was Found to Be in Excess of TS Allowable Limit.Caused by Two Psvs Failing to Maintain Lift Setpoints within 1% Tolerance.Setpoints & Procedures Revised + (ML20035B926)
- ML20035B927 + (ML20035B927)
- ELV-05354, Responds to SALP Rept & Info Discussed at 930318 Meeting W/ Util.Util Wishes to Make Listed Clarification to Statement on Page 16 Re Code Insp of Vessel Nozzles + (ML20035B929)
- ML20035B930 + (ML20035B930)
- ML20035B931 + (ML20035B931)
- ML20035B932 + (ML20035B932)
- ML20035B934 + (ML20035B934)
- B14414, Forwards SW & ESW Sys Insp/Replacement Strategy for Unit 1. Mod to Sys Based on Ongoing Monitoring of Sys Parameters or Visual & Ultrasonic Insp of Components + (ML20035B935)
- ML20035B936 + (ML20035B936)
- ML20035B941 + (ML20035B941)
- ML20035B942 + (ML20035B942)
- 05000155/LER-1991-010-01, Forwards LER 91-010-01,reactor Protection Sys Pressure Switches Experiencing Setpoint Drift.Util Considered Event Reportable to NRC Per 10CFR50.73(a)(2)(vi) as Potential Generic Problem + (ML20035B943)
- ML20035B946 + (ML20035B946)
- 05000155/LER-1991-010, :on 911215,two Out of Four Reactor Pressure Switches Were Found to Be out-of-tolerance High.Caused by Aging & Corrosion Experienced by Instrumentation.Switches Were Recalibrated in Accordance W/Plant Procedure + (ML20035B948)
- ML20035B949 + (ML20035B949)
- ML20035B950 + (ML20035B950)
- ML20035B951 + (ML20035B951)
- ML20035B953 + (ML20035B953)
- IR 05000334/1993001 + (ML20035B954)
- ML20035B955 + (ML20035B955)
- ML20035B957 + (ML20035B957)
- ML20035B958 + (ML20035B958)
- ML20035B959 + (ML20035B959)
- 05000353/LER-1993-004-01, :on 930303,inadvertent EDG Start as Result of Personnel Error from Misunderstood Verbal Communication During Performance of Procedure.Test Director Counseled Re Event & Importance of Proper Communication + (ML20035B960)
- IR 05000298/1993007 + (ML20035B961)
- ML20035B963 + (ML20035B963)
- ML20035B964 + (ML20035B964)
- 05000352/LER-1993-003-02, :on 930303,A & B Toxic Gas Analyzers Declared Inoperable Since Analyzers Would Not Respond to Presence of Ammonia.Caused by Hardware Deficiency.Reduced Flush Time Incorporated Into Site Procedures + (ML20035B965)
- ML20035B967 + (ML20035B967)
- 05000325/LER-1993-006, :on 930302,identified Several Fire Barrier Penetrations W/Fire Seal Application Discrepancies.Caused by Inadequate Design.Fire Watches Stationed & Will Remain Until Deficient Fire Seals Restored + (ML20035B969)
- IR 05000331/1993003 + (ML20035B970)
- 05000334/LER-1993-005, :on 930302,identified Discrepancy in QA Categorization of Solenoid Valve.Caused by Inappropriate Replacement of Valve During Maint in 1986.Design Change Process Includes Administrative Guidance + (ML20035B971)
- ML20035B972 + (ML20035B972)
- ML20035B974 + (ML20035B974)
- ML20035B975 + (ML20035B975)
- ML20035B976 + (ML20035B976)
- ML20035B977 + (ML20035B977)
- ML20035B978 + (ML20035B978)
- ML20035B980 + (ML20035B980)
- ML20035B982 + (ML20035B982)
- ML20035B984 + (ML20035B984)
- ML20035B986 + (ML20035B986)
- ML20035B987 + (ML20035B987)
- 05000328/LER-1993-001-04, :on 930301,extraction Steam Line Rupture Causes High Generator Output Voltage & Manual Reactor Trip.Caused by Programmatic Failure of Erosion/Corrosion Program.Insps, Repair & Replacements Will Be Performed + (ML20035B988)
- IR 05000155/1993005 + (ML20035B989)
- 05000455/LER-1993-002-08, :on 930311,determines Unit 1 Essential Svc Water Pump Availability to Unit 2 Surveillance Not Complete. Caused by Failure to Complete Requirements of Shift/Daily Operating Surveillance.Surveillance Revised + (ML20035B990)
- ML20035B991 + (ML20035B991)
- ML20035B992 + (ML20035B992)
- ML20035B993 + (ML20035B993)
- ML20035B995 + (ML20035B995)