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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
- ML20064G556 + (ML20064G556)
- ML20064G558 + (ML20064G558)
- ML20064G562 + (ML20064G562)
- ML20064G563 + (ML20064G563)
- ML20064G565 + (ML20064G565)
- ML20064G566 + (ML20064G566)
- ML20064G567 + (ML20064G567)
- 05000336/LER-1978-030, Forwards LER 78-030/03L-0 + (ML20064G568)
- ML20064G580 + (ML20064G580)
- 05000336/LER-1978-030-03, /03L-0:on 781106 CEA 63 in Regulating Group 3 Reed Switch Position Indicator Channel Inoperable.Caused by Intermittent Open in the Reed Switch Assembly Power Supply Lead Which Produced Erratic Indication + (ML20064G585)
- ML20064G589 + (ML20064G589)
- ML20064G590 + (ML20064G590)
- ML20064G591 + (ML20064G591)
- 05000336/LER-1978-031, Forwards LER 78-031/03L-0 + (ML20064G596)
- ML20064G598 + (ML20064G598)
- ML20064G601 + (ML20064G601)
- HL-4515, Semiannual Radioactive Effluent Release Rept for Jul-Dec 1993 + (ML20064G603)
- JSP-110-94, Forwards Revised TS 3/4.4.3.1, RCS Leakage - Leakage Detection Sys, Changing Specific Wording & Location of Footnote + (ML20064G606)
- U-602265, Proposed Tech Spec 3/4.4.3.1, RCS Leakage - Leakage Detection Sys + (ML20064G616)
- 05000336/LER-1978-031-03, /03L-0:on 781107 C Reactor Bldg Closed Cooling Water Temp Was Found Low Due to Failed Svc Water Temp Control Valve Shear Pin Connecting Actuator to Valve. Caused by Sheared Tension Pin + (ML20064G618)
- 05000219/LER-1978-026, Forwards LER 78-026/01T-0 + (ML20064G621)
- 05000219/LER-1978-026-01, /01T-0:on 781121 torus-to-reactor Bldg Differential Pressure Switches DPS-66A & B Had Ruptured Diaphragms.Caused by Excessive Differential Pressure + (ML20064G624)
- 05000333/LER-1982-053, Forwards LER 82-053/03L-0 + (ML20064G625)
- ML20064G627 + (ML20064G627)
- 05000334/LER-1978-053, Forwards LER 78-053/01T-0 + (ML20064G629)
- 05000334/LER-1978-053-01, /01T-0:on 781026,error Noted in Original Piping Stress Analysis for on Steam Infection Line.Error Caused by Misapplication of Simplified Analysis Technique Employed During Original Design.Corrective Action Implemented + (ML20064G636)
- ML20064G637 + (ML20064G637)
- 05000333/LER-1982-053-03, /03L-0:on 821208,during Surveillance Test of LPCI Independent Power Supply Battery B,One Cell Discovered Out of Spec Limits for Cell Voltage.Cause Not Stated.Defective Cell Removed & Replaced W/Temporary Jumper.Sys Restored + (ML20064G639)
- ML20064G645 + (ML20064G645)
- NRC-94-4078, Forwards Rev 4 to AP600 Design Certification Test Program Overview + (ML20064G649)
- ML20064G652 + (ML20064G652)
- ML20064G653 + (ML20064G653)
- ML20064G654 + (ML20064G654)
- ML20064G655 + (ML20064G655)
- ML20064G657 + (ML20064G657)
- ML20064G665 + (ML20064G665)
- ML20064G666 + (ML20064G666)
- ML20064G678 + (ML20064G678)
- ML20064G681 + (ML20064G681)
- ML20064G682 + (ML20064G682)
- ML20064G683 + (ML20064G683)
- ML20064G694 + (ML20064G694)
- ML20064G700 + (ML20064G700)
- ML20064G702 + (ML20064G702)
- 05000267/LER-1978-034, Forwards LER 78-034/03L-0 + (ML20064G704)
- 05000267/LER-1978-034-03, /03L-0 on 781107:during Normal Oper a Release of Reactor Bldg Sump Effluent Req Cooling Tower Blowdown Flow to Increase Above Normal Rate to 4.39 Million Gallons for the Day,Due to Need to Dilute Sump Effluent Discharge + (ML20064G709)
- ML20064G710 + (ML20064G710)
- 05000266/LER-1994-002, :on 940208,both EDG G02 Train B EDG Voluntarily Removed from Svc for Annual Maint.Caused by Power Fluctuations.Damaged Bus Bar & Jumper Wire Replaced + (ML20064G711)
- ML20064G714 + (ML20064G714)
- 05000267/LER-1978-005, Forwards LER 78-005/03X-1 + (ML20064G717)
- ML20064G725 + (ML20064G725)