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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
- 05000368/LER-1986-004-01, :on 860421,unit Tripped from 100% Power Due to Core Protection Calculator Generated Low Departure from Nucleate Boiling Ratio Trip in 2 of 4 Channels of Reactor Protective Sys + (ML20211A942)
- LIC-99-0076, Forwards fitness-for-duty Program Performance Data for Six Month Period from Jan-June 1999,IAW 10CFR26.71(d) + (ML20211A943)
- ML20211A944 + (ML20211A944)
- ML20211A945 + (ML20211A945)
- ML20211A946 + (ML20211A946)
- ML20211A948 + (ML20211A948)
- ML20211A950 + (ML20211A950)
- ML20211A951 + (ML20211A951)
- ML20211A953 + (ML20211A953)
- ML20211A955 + (ML20211A955)
- ML20211A959 + (ML20211A959)
- 05000409/LER-1986-029, :on 860918,reactor Scrammed on Low Recirculation Flow When Forced Circulation Pump 1B Tripped. Caused by Closed Seal Inject Supply Valve.Valve Controller Rebuilt & Procedure Change Implemented + (ML20211A961)
- 05000263/LER-1986-011, :on 860509,EFT Sys (Control Room HVAC) Automatically Transferred to Toxic Chemical Mode Due to Hydrogen Chloride Monitor Tape Break.Caused by Small Imperfection on Tape + (ML20211A962)
- ML20211A963 + (ML20211A963)
- ML20211A964 + (ML20211A964)
- ML20211A965 + (ML20211A965)
- ML20211A967 + (ML20211A967)
- ML20211A970 + (ML20211A970)
- ML20211A971 + (ML20211A971)
- ML20211A972 + (ML20211A972)
- ML20211A973 + (ML20211A973)
- ML20211A974 + (ML20211A974)
- TXX-4794, Forwards Public Version of Revised Emergency Plan Procedures,Including Rev 4 to EPP-115, Release of Emergency-Related Info to Public & Rev 5 to EPP-207, Activation of News Ctr.... W/860602 Release Memo + (ML20211A975)
- ML20211A977 + (ML20211A977)
- ML20211A978 + (ML20211A978)
- ML20211A979 + (ML20211A979)
- ML20211A982 + (ML20211A982)
- ML20211A983 + (ML20211A983)
- ML20211A984 + (ML20211A984)
- ML20211A986 + (ML20211A986)
- ML20211A988 + (ML20211A988)
- 05000249/LER-1986-010-05, :on 860422,cribhouse Deluge Sys 2/3 Taken Out of Svc to Complete Portion of App R Mod Work.Testing Completed on 860503.Sys Placed in Svc on 860507 After Readjustment of Deluge Valve + (ML20211A990)
- ML20211A991 + (ML20211A991)
- 05000458/LER-1987-002, :on 870112,reactor Shutdown Initiated for Unidentified Drywell Leakage Exceeding 5 Gpm.Caused by Packing Leaks on Several Valves W/Rhr B Testable Injection Check Valve as Primary Contributer + (ML20211A992)
- ML20211A994 + (ML20211A994)
- RBG-35407, Special Rept:In Jan 1987,quarterly Rept Showed Marker 34 Settlement in Excess of Predicted Value.Cause Attributed to Assumptions in Effect of Const Schedule on Structural Settlement.Normal Survey Frequency Remains in Effect + (ML20211A996)
- ML20211A997 + (ML20211A997)
- ML20211A998 + (ML20211A998)
- ML20211B000 + (ML20211B000)
- ML20211B001 + (ML20211B001)
- ML20211B003 + (ML20211B003)
- ML20211B006 + (ML20211B006)
- ML20211B007 + (ML20211B007)
- 3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05 + (ML20211B009)
- ML20211B010 + (ML20211B010)
- ML20211B011 + (ML20211B011)
- ML20211B012 + (ML20211B012)
- ML20211B015 + (ML20211B015)
- ML20211B016 + (ML20211B016)
- B12396, Forwards Probabilistic Risk Analysis of Events Caused by Internal Flooding,Per 860731 Commitment.Analysis Identifies & Evaluates Consequences of Postulated Accidents Due to Internal Flooding.Insights Gained Listed + (ML20211B017)
- ML20211B019 + (ML20211B019)