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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
- ML20135D609 + (ML20135D609)
- ML20135D611 + (ML20135D611)
- BSEP-96-0343, Application for Amends to Licenses DPR-71 & DPR-62,changing Method of Detecting Reactivity Anomalies as Well as Editorial Changes to Bases for TS 3/4.1.2 + (ML20135D613)
- ML20135D615 + (ML20135D615)
- ML20135D618 + (ML20135D618)
- ML20135D620 + (ML20135D620)
- IR 05000416/1985016 + (ML20135D622)
- ST-HL-AE-5519, Forwards Change to Operations QA Plan (QA-030) Per 10CFR50.54(a) + (ML20135D625)
- ML20135D626 + (ML20135D626)
- ML20135D628 + (ML20135D628)
- ML20135D630 + (ML20135D630)
- 05000312/LER-1984-020, :on 840703,tube Leak Experienced in once- Through Steam Generator B.During Cooldown,Unplanned Reactor Trip Occurred on Low RCS Pressure.Caused by Through Wall Defect at 15th Tube Support Plate + (ML20135D632)
- ML20135D634 + (ML20135D634)
- ML20135D635 + (ML20135D635)
- ML20135D639 + (ML20135D639)
- ML20135D643 + (ML20135D643)
- ML20135D645 + (ML20135D645)
- ML20135D650 + (ML20135D650)
- ML20135D652 + (ML20135D652)
- ML20135D658 + (ML20135D658)
- PNO-I-96-087, on 961206,reactor Was Manually Scramed Due to EHC Oil Leak at Turbine Control Valve 2.Licensee Implemented One Wk Maint Outage to Repair EHC Pressure Switch & Several Other Balance of Plant & Drywell Items + (ML20135D660)
- ML20135D661 + (ML20135D661)
- 05000423/LER-1996-044, Forwards LER 96-044-00,documenting Condition That Was Determined at Millstone Unit 3,on 961108.Commitments,encl + (ML20135D662)
- ML20135D663 + (ML20135D663)
- ML20135D666 + (ML20135D666)
- ML20135D669 + (ML20135D669)
- ML20135D671 + (ML20135D671)
- ML20135D674 + (ML20135D674)
- ML20135D676 + (ML20135D676)
- 05000423/LER-1996-044-01, :on 961108,qualification of Containment Sys Noted Following Design Basis Accident.Determined That Fwa Sys Was Not Rated at Containment Design Temp of 280 Degrees. Design Review of Fwa Sys Will Be Performed Prior to Entry + (ML20135D677)
- ML20135D678 + (ML20135D678)
- ML20135D682 + (ML20135D682)
- ML20135D683 + (ML20135D683)
- ML20135D685 + (ML20135D685)
- ML20135D689 + (ML20135D689)
- ML20135D691 + (ML20135D691)
- ML20135D692 + (ML20135D692)
- ML20135D694 + (ML20135D694)
- 05000370/LER-1985-018, :on 850624,reactor Tripped Due to Steam Generator 2C Low Level.Caused by Solenoid Valve Failure. Valve & Piping Replaced.Pipe Hangers Inspected.Rupture Restraint Modified.Welds Will Be Replaced + (ML20135D696)
- ML20135D699 + (ML20135D699)
- ML20135D701 + (ML20135D701)
- ML20135D702 + (ML20135D702)
- ML20135D703 + (ML20135D703)
- ML20135D704 + (ML20135D704)
- ML20135D705 + (ML20135D705)
- ML20135D706 + (ML20135D706)
- ML20135D708 + (ML20135D708)
- ML20135D709 + (ML20135D709)
- PNO-III-96-072, on 961203 & 06,total of Approx 48,000 Ci Co-60 Shipped by Chem-Nuclear,Inc from Advanced Medical Sys to Barnwell,Sc for Disposal.For Entire Project,Total Mrem Was Approx 3,200 Millirems + (ML20135D710)
- ML20135D714 + (ML20135D714)
- ML20135D715 + (ML20135D715)