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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
- ML20203P640 + (ML20203P640)
- ML20203P643 + (ML20203P643)
- ML20203P647 + (ML20203P647)
- 05000327/LER-1986-008, :860401,monthly Channel Check for Steam Generator narrow-range Level Shutdown Instrumentation Not Properly Performed on SI-3 Logs.Caused by SI-3 Incorrectly Written for wide-range Level Instruments + (ML20203P656)
- ML20203P659 + (ML20203P659)
- ML20203P660 + (ML20203P660)
- ML20203P661 + (ML20203P661)
- ML20203P662 + (ML20203P662)
- ML20203P663 + (ML20203P663)
- ML20203P664 + (ML20203P664)
- ML20203P680 + (ML20203P680)
- ML20203P683 + (ML20203P683)
- ML20203P685 + (ML20203P685)
- 2CAN058601, Forwards Vols 1 & 2 of Arkansas Nuclear One Unit 2,CRDR Final Summary Rept, Documenting Activities Re Commitment to Practical Applications of Human Factors Principles + (ML20203P686)
- ML20203P688 + (ML20203P688)
- ML20203P689 + (ML20203P689)
- ML20203P690 + (ML20203P690)
- ML20203P691 + (ML20203P691)
- ML20203P692 + (ML20203P692)
- ML20203P694 + (ML20203P694)
- ML20203P695 + (ML20203P695)
- ML20203P696 + (ML20203P696)
- 05000333/LER-1986-010, :on 860404,full Scram Occurred While Performing Main Turbine Stop Valve Limit Switch Instrument Functional Test.Cause Unknown.Affected Components Replaced & Sys Tested + (ML20203P697)
- W3P86-0066, Forwards Response to SALP Board Rept 50-382/85-30 Transmitted by .Maint Dept Directive Issued in Feb 1985 to Provide Guidance in Minimizing ESFAS Actuations & Plant Trips + (ML20203P700)
- ML20203P701 + (ML20203P701)
- ML20203P706 + (ML20203P706)
- ML20203P707 + (ML20203P707)
- ML20203P708 + (ML20203P708)
- ML20203P713 + (ML20203P713)
- ML20203P714 + (ML20203P714)
- ML20203P716 + (ML20203P716)
- ML20203P719 + (ML20203P719)
- ML20203P720 + (ML20203P720)
- ML20203P721 + (ML20203P721)
- ML20203P722 + (ML20203P722)
- 05000397/LER-1986-005, :on 860401,refueling Mode 5 Entered Prior to Completing Instrument Surveillances Required by Tech Specs. Caused by Inadequate Procedures.Tech Specs Received & Surveillances Performed + (ML20203P724)
- ML20203P725 + (ML20203P725)
- ML20203P726 + (ML20203P726)
- ML20203P727 + (ML20203P727)
- ML20203P728 + (ML20203P728)
- ML20203P729 + (ML20203P729)
- 05000382/LER-1986-007, :on 860406,fire Watch Tour for Fire Impairment 85-232 Not Satisfactorily Performed.Caused by Misnumbered Pages in Fire Watch Log.Responsibilities for Handling Logs Posted + (ML20203P730)
- ML20203P731 + (ML20203P731)
- ML20203P732 + (ML20203P732)
- ML20203P734 + (ML20203P734)
- PNO-III-86-025C, existence of Cracking in Reactor Coolant Pump Shaft Not Yet Confirmed.Ultrasonic Testing & Other Nondestructive Tests,Including Dye Penetrant Testing & Microscopic Exam,Failed to Identify Indications of Cracking + (ML20203P735)
- IR 05000483/1986008 + (ML20203P736)
- ML20203P737 + (ML20203P737)
- ML20203P738 + (ML20203P738)
- ML20203P739 + (ML20203P739)
- ML20203P743 + (ML20203P743)