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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 05000395/1989010 + (ML20246P840)
- ML20246P841 + (ML20246P841)
- ML20246P843 + (ML20246P843)
- ML20246P844 + (ML20246P844)
- ML20246P850 + (ML20246P850)
- 05000412/LER-1989-008, :on 890403,determined That Pressurizer Code Valve Lift Setting Less than Tech Spec Limit.Caused by Combination of Setpoint Drift & Seat Leakage.Seat Leakage Corrected by Lapping Seating Surfaces + (ML20246P852)
- ML20246P853 + (ML20246P853)
- ML20246P854 + (ML20246P854)
- ML20246P857 + (ML20246P857)
- ML20246P859 + (ML20246P859)
- ML20246P862 + (ML20246P862)
- ML20246P863 + (ML20246P863)
- ML20246P868 + (ML20246P868)
- ML20246P870 + (ML20246P870)
- ML20246P871 + (ML20246P871)
- ML20246P872 + (ML20246P872)
- NL-89-556, Monthly Operating Rept for June 1989 for Rancho Seco Nuclear Station + (ML20246P874)
- ML20246P875 + (ML20246P875)
- ML20246P876 + (ML20246P876)
- ML20246P878 + (ML20246P878)
- ML20246P880 + (ML20246P880)
- ML20246P883 + (ML20246P883)
- ML20246P884 + (ML20246P884)
- ML20246P886 + (ML20246P886)
- ML20246P888 + (ML20246P888)
- ML20246P890 + (ML20246P890)
- ML20246P891 + (ML20246P891)
- ML20246P895 + (ML20246P895)
- ML20246P896 + (ML20246P896)
- ML20246P898 + (ML20246P898)
- ML20246P899 + (ML20246P899)
- IR 05000206/1989008 + (ML20246P900)
- ML20246P903 + (ML20246P903)
- ML20246P906 + (ML20246P906)
- ML20246P909 + (ML20246P909)
- 05000267/LER-1985-003, :on 850304,during Loss of Offsite Power & Turbine Trip Surveillance,Both Diesel Generator Tie Breakers Failed to Close.Caused by Faulty Cell on Station Battery 1A. Batteries Replaced w/lead-antimony Batteries + (ML20246P910)
- ML20246P912 + (ML20246P912)
- ML20246P914 + (ML20246P914)
- ML20246P916 + (ML20246P916)
- ML20246P917 + (ML20246P917)
- 05000456/LER-1989-002-09, :on 890416,main Steam Line Low Pressure Reactor Trip,Safety Injection & Main Steam Isolation Occurred.Caused by RCS Pressure Above 1,1930 Psig & Main Steam Pressure Less than 640 Psig.Heatup Procedure Will Be Revised + (ML20246P918)
- ML20246P919 + (ML20246P919)
- ML20246P921 + (ML20246P921)
- ML20246P923 + (ML20246P923)
- ML20246P925 + (ML20246P925)
- NRC-89-0163, Informs of Change to Independent Safety Engineering Group (Iseg) Reporting Responsibilities.Line Responsibility for Iseg Will Be Vice President of Nuclear Engineering & Svc + (ML20246P926)
- ML20246P929 + (ML20246P929)
- ML20246P930 + (ML20246P930)
- ML20246P931 + (ML20246P931)
- 05000424/LER-1987-082, :on 871017,insp of Breaker Installed in Main Reactor Trip Breaker Cubicle B Indicated That Weld on Breaker Pole Shaft Lacked Proper Fusion.Caused by Procedural Inadequacy.Procedure Revised Re Response Time + (ML20246P934)
- ML20246P936 + (ML20246P936)