Search by property

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

• ML20135D488  + (ML20135D488)
• RC-97-0043, VC Summer Nuclear Station 1996 Annual Operating Rept. W/  + (ML20135D490)
• ML20135D492  + (ML20135D492)
• HL-5271, Requests That NRC Grant Relief from Compliance W/Insp Rule Re Repair & Replacement Activities Which Comply W/Asme Code Section XI,1992 Edition w/1992 Addenda for Class Mc Components.Relief Requested for 1 Year Period  + (ML20135D495)
• 05000321/LER-1996-014, :on 961106,incorrect Circuit Breaker Setting Resulted in Inoperable Edg.Caused by Failure to Incorporate Design Info Into Appropriate Plant Single Line Electrical Drawing.Temporary Plant Mod Will Be Installed  + (ML20135D503)
• ML20135D505  + (ML20135D505)
• 05000364/LER-1995-002, :on 950404,increased Oxide & Deposit Coating on Fuel Was Noted During Visual Exams of Fuel Assemblies.Caused by Fuel Duty & Inherent Variability in Cladding Corrosion Process.Revised Corrosion Models  + (ML20135D506)
• TXX-9704, Ses Annual Operating Rept 1996  + (ML20135D507)
• 05000280/LER-1984-004-03, :on 840225,following Shutdown,Specific Activity Sample of Reactor Coolant Showed Peak Dose Equivalent I-131 Level of 1.77 Mci/Cc,Exceeding Tech Spec 3.1.D.2.Caused by Fuel Element Defects in Reactor Core  + (ML20135D508)
• 05000440/LER-1996-006, :on 960718,MOV Control Circuitry Design Deficiency Resulted in Fire Protection Violation.Fire Impairment Was Issued for Control Room Fire Protection Features & Addl MOVs Considered for Mod  + (ML20135D509)
• 2CAN129607, Forwards Request for Exigent Processing of TS Change Request Re Small Break Loss of Coolant Accident Methodology  + (ML20135D512)
• ML20135D524  + (ML20135D524)
• ML20135D527  + (ML20135D527)
• ML20135D536  + (ML20135D536)
• ML20135D539  + (ML20135D539)
• ML20135D542  + (ML20135D542)
• ML20135D543  + (ML20135D543)
• ML20135D548  + (ML20135D548)
• 05000263/LER-1984-027, :on 840912,while Pulling Wires Into Substation Panel,Large Cable Jarred Adjacent Panel & Tripped 345 Kv Bus Differential Relays,Deenergizing Source for Auxiliary Reserve Transformer,Resulting in Autostart  + (ML20135D553)
• ML20135D557  + (ML20135D557)
• ML20135D560  + (ML20135D560)
• 05000324/LER-1984-017-01, :on 841130,Group 3 Primary Isolation Occurred Due to Erroneous Reactor Water Cleanup Sys Area High Temp Signal.High Temp Signal Caused by Component Breakdown in Instrument Module N600F.Module Replaced  + (ML20135D561)
• ML20135D567  + (ML20135D567)
• ML20135D571  + (ML20135D571)
• ML20135D573  + (ML20135D573)

• ML20135D575  + (ML20135D575)

• ML20135D576  + (ML20135D576)
• 05000338/LER-1984-012-03, :on 840925,Fuel Cycle 5 Moderator Temp Coefficient Determined More Positive than Tech Specs Allow. Interim Control Rod Withdrawal Limits Implemented  + (ML20135D577)
• VPN-075-96, Forwards ISFSI Construction Schedule  + (ML20135D582)
• ML20135D583  + (ML20135D583)
• ML20135D584  + (ML20135D584)
• 05000361/LER-1984-010-02, :on 840223,reactor Power Surge Occurred Due to Partial Loss of Extraction Steam Feedwater Heating.Caused by Spurious Cycle of First Point Level Controller Resulting in High Levels in Point Heaters  + (ML20135D588)
• ML20135D589  + (ML20135D589)
• ML20135D592  + (ML20135D592)
• ML20135D593  + (ML20135D593)
• 05000361/LER-1984-008-02, :on 840211,inadvertent Entry Into Mode 3 Occurred.Caused by Failure of Plant Monitoring Sys (PMS) Due to Incorrect RCS Temp Display.Pms Display Repaired & Returned to Svc  + (ML20135D598)
• 05000263/LER-1984-025, :on 840715,while Isolating Bus 16 for Relay Maint,Emergency Diesel Generator 11 Started When Operator Opened Bus Potential Transformer Door on Rear of Cubicle 152-610 Rather than 152-601  + (ML20135D603)
• ML20135D606  + (ML20135D606)
• ML20135D608  + (ML20135D608)
• 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)