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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
- NRC/OCIO +
- Information Notice 1996-33, Erroneous Data from Defective Thermocouple Results in a Fire +
- Information Notice 1996-33, Erroneous Data From Defective Thermocouple Results in a Fire +
- ML17264A679 +
- ML17264A678 +
- ML18121A012 +
- ML18038B697 +
- ML20117K237 +
- NRC-96-0053, Special Rept:Documents Inoperability of Seismic Monitoring Instrumentation Exceeding 30 Days.Caused by Inadequate Surveillance Testing of Active Triaxial Accelerometers & Seismic Trigger.Surveillance Procedures Will Be Revised +
- ML20117J447 +
- ML20117J426 +
- ML20117H607 +
- ML20117H394 +
- ML20117E617 +
- ML20115G405 +
- ML20113A080 +
- ML20113A078 +
- ML20112E891 +
- ML20112E369 +
- ML20112D593 +
- ML20112D009 +
- ML20112C879 +
- ML20112C875 +
- ML20112C869 +
- ML20137P609 +
- ML20137L359 +
- ML20141J303 +
- ML20138M728 +
- ML20134B752 +
- ML20129G835 +
- ML20129G277 +
- ML20129D725 +
- ML20128R013 +
- ML20128N713 +
- ML20217M169 +
- TAC:93873 +
- ULNRC-03383, Forwards New NPDES Discharge Permit for Plant +
- NSD-NRC-96-4730, Forwards Addl Info Re AP600 Instrumentation & Control Software Architecture & Operation Description +
- RC-96-0141, Provides Beginning of Cycle (BOC) & End of Cycle (EOC) Control Rod Test Info in Accordance W/Actions Delineated in NRC Bulletin 96-001 +
- LIC-96-0076, Forwards Fort Calhoun Station Performance Indicators Rept for April 1996 +
- TXX-9637, Forwards Supplemental Response to NRC Bulletin 96-001, Control Rod Insertion Problems +
- 05000321/LER-1996-007, :on 960424,failed Component Results in Inadvertent EDG Start.Caused by Relay Momentarily Binding in Actuated Position.Relay Replaced & Surveillance Completed +
- 05000412/LER-1996-002-01, :on 960220,containment Penetration Not Isolated within Time Limit.Caused by Breakdown in Administrative Controls Governing Document Updates During Initial Plant Const in 1985.Manual Isolation Valves Shut +
- 05000317/LER-1996-003, :on 960423,discovered Holes in Containment Sump Screen Larger than Described in Ufsar.Holes Most Likely Installed During Plant Const.Sump Screens Visually Inspected & Repaired +
- 05000454/LER-1995-011-01, :on 951107,current Insp Results Identified Increased Tube Degradation in Sgs.Cause Unknown.Defective Tubes Removed from Svc by Plugging or Sleeving +
- 05000298/LER-1996-001, :on 960118,potential Inoperability of Emergency Diesel Generators Determined.Caused by Failure of Mgt to Effectively Communicate Installation of Modifications.Tubing & Fittings Removed from SPV Exhaust Ports +
- ML20129K419 +
- 05000397/LER-1996-001, :on 960425,inadvertent ESF Actuations Occurred Due to Tripping of Temporary Power Supply to IN-3.Caused by Personnel Error.Operations Restored to IN-3 Loads & Reset ESF Actuations +
- IR 05000397/1996005 +
- PNO-III-96-032, on 960516,AIT Formed to Review Circumstances Surrounding 960515 Reactor Sram.Caused by Failure of FW Regulating Valve.Issue Being Reviewed for Possible Generic Implications +