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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
- ML20133J581 + (ML20133J581)
- ML20133J583 + (ML20133J583)
- ML20133J584 + (ML20133J584)
- BSEP-85-1392, Suppl to Special Rept 1-SR-85-6:fire Barrier Penetration Seal Removed During Plant Mod Work Incorrectly Identified in 850725 Rept.Correct Identification Is Seal CB-2-244-21. Part 21 Related + (ML20133J586)
- 05000261/LER-1985-021-01, :on 850917,reactor Trip Occurred Due to False Low Reactor Coolant Flow Signal.Caused When Bistable for Loop 1 Was Tripped for Testing.No Cause for Voltage Spike Found + (ML20133J590)
- ML20133J597 + (ML20133J597)
- ML20133J601 + (ML20133J601)
- ML20133J603 + (ML20133J603)
- ML20133J604 + (ML20133J604)
- ML20133J605 + (ML20133J605)
- ML20133J606 + (ML20133J606)
- ML20133J609 + (ML20133J609)
- ML20133J610 + (ML20133J610)
- ML20133J612 + (ML20133J612)
- ML20133J613 + (ML20133J613)
- HBL-85-045, Requests Registration as User of Model OH-142 Mki + (ML20133J615)
- ML20133J620 + (ML20133J620)
- ML20133J621 + (ML20133J621)
- ML20133J622 + (ML20133J622)
- PNO-I-85-078A, on 851011,reactor Coolant Spill from RWCU Sys to 779 Ft Elevation of Reactor Bldg Occurred.Caused by Lifting of 150 Psig Precoat Feed Relief Valve.Spill Cleaned & Access to Area Restored + (ML20133J623)
- ML20133J624 + (ML20133J624)
- ML20133J625 + (ML20133J625)
- ML20133J626 + (ML20133J626)
- ML20133J628 + (ML20133J628)
- ML20133J629 + (ML20133J629)
- ML20133J630 + (ML20133J630)
- ML20133J631 + (ML20133J631)
- ML20133J634 + (ML20133J634)
- ML20133J635 + (ML20133J635)
- ML20133J638 + (ML20133J638)
- IR 05000904/2010001 + (ML20133J639)
- ML20133J641 + (ML20133J641)
- IR 05000454/1985039 + (ML20133J643)
- ML20133J646 + (ML20133J646)
- ML20133J648 + (ML20133J648)
- ML20133J649 + (ML20133J649)
- U-600245, Informs That Util Completed Compliance Analysis Review & Identified Need for Listed Variance Requests for NUREG-0737,Action Plan Item II.F.1 Re Addl Accident Monitoring Instrumentation.Variance Requests Encl + (ML20133J650)
- ML20133J652 + (ML20133J652)
- ML20133J653 + (ML20133J653)
- ML20133J655 + (ML20133J655)
- ML20133J657 + (ML20133J657)
- ML20133J658 + (ML20133J658)
- ML20133J659 + (ML20133J659)
- ML20133J660 + (ML20133J660)
- ML20133J661 + (ML20133J661)
- ML20133J663 + (ML20133J663)
- ML20133J664 + (ML20133J664)
- ML20133J665 + (ML20133J665)
- ML20133J666 + (ML20133J666)
- ML20133J667 + (ML20133J667)
- U-600279, Forwards Response to 10CFR50.62 Requirements Re Reduction of ATWS Events for Light Water Cooled Nuclear Power Plants. Installation of ATWS Sys Complete.Tech Spec 3/4.1.5, Standby Liquid Control Sys, Will Be Revised + (ML20133J669)