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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
- ENS 49454 +
- 05000260/LER-2010-003, Regarding Reactor Scram Due to Closure of the Main Steam Isolation Valves and Subsequent Invalid RPS Scram from the Intermediate Range Monitoring System +
- ML15282A240 +
- ML17317B461 +
- L-2017-074, St. Lucie, Unit 1, Updated Final Safety Analysis Report, Amendment No. 28, Chapter 15, Accident Analysis +
- NL-15-169, Browns Ferry, Units 1, 2, and 3, Startup Test Plan +
- ML20010C098 +
- ML20006D861 +
- L-2011-360, Response to NRC Accident Dose Branch Request for Additional Information Regarding Extended Power Uprate License Amendment Request +
- ML19073A001 +
- W3F1-2019-0042, SR-2019-001-00 for Waterford Steam Electric Station, Unit 3 (Waterford 3), Condenser Vacuum Pump High Range Instrument Inoperable for Greater than 7 Days +
- ML20084E500 +
- ML20083R190 +
- ML20081C147 +
- ML20091K481 +
- ML20107D724 +
- ML20106E576 +
- ML20084T967 +
- IR 05000266/1988007 +
- IR 05000271/1987016 +
- ML20149K771 +
- ML20065S202 +
- ML20244E151 +
- IR 05000352/1989012 +
- AECM-87-0065, Requests Review & Concurrence of Proposed Incorporation of Design Review/Quality Revalidation Program Insps.Concurrence Requested by 870803 to Identify Final Scheduling & Manpower Constraints for Upcoming Refueling Outage.Fee Paid +
- AECM-86-0249, Forwards Summary of 860806 Meeting W/Nrc Re 860707 Proposal to Limit Deferral of Certain Insps of Div II Emergency Diesel Generator.Requests Prompt Approval in Order to Support Final Preparations for 860905 Refueling Outage +
- AECM-83-0653, Forwards Applicability of Shoreham Delaval Diesel/ Generator Crankshaft Failure to Grand Gulf Nuclear Station, in Response to IE Info Notice 83-58.Rept Concludes That Failure Will Not Occur at Facility +
- AECM-83-0724, Forwards Partial Response to Request for Addl Info Re Transamerica Delaval,Inc Diesel Generators Supplied to Facility.Steps Taken to Obtain More Detailed Info on Crankshaft Design Analyses & Testing Done by Lilco +
- 05000254/LER-1989-004-07, :on 890417,reactor Manually Scrammed Due to Electromagnetic Relief Valve 1-203-3D Being Stuck Open. Caused by Steam Leakage Past Pilot Valve & Obstruction of Drain Orifice.Relief & Pilot Valves Replaced +
- 05000266/LER-1987-005-01, :on 871121,reactor Coolant Pressure Decreased Resulting in Reactor Trip Due to Low Pressurizer Pressure. Caused by Spray Valve Failure.Broken Solder Connection Repaired & Pilot Valve Steam Replaced +
- 05000352/LER-1987-026, :on 870612,nuclear Steam Supply Shutoff Sys Isolation Signal & Reactor Scram Signal Occurred.Caused by Nondestructive Radiographic Exams Being Performed on Main Steam Line A.Isolation & Scram Signals Reset +
- 05000331/LER-1986-017, :on 860613,at Approx 5% Power,Manual Scram Initiated When Reactor Water Level Approached Low Level Scram Setpoint.Caused by Faulty Position Controllers. Positioners Replaced & Cleaned +
- 05000333/LER-1997-011-01, :on 971024,invalid ESF Actuation & Failure to Perform TS Required Actions Occurred While Performing Required Actions While Troubleshooting Activities.Restored HPCI Sys to Normal IAW Plant Procedures +
- 05000293/LER-1996-005, :on 960419,automatic Scram Occurred Due to Turbine Vibration During Planned Power Reduction.Turbine Vibration Trip Setting That Initiates Trip of Turbine Due to High Vibration Changed +
- 05000331/LER-1984-036, :on 840925,30 & 1020,reactor Water Cleanup Sys Isolated as Result of Momentary Spurious Signals in Leak Detection Logic.Cause Unknown.Sys Verified to Be Free of Actual Leakage +
- 05000374/LER-1990-006-03, :on 900412,loop a Primary Containment Chilled Water Sys Inboard Isolation Valves & Reactor Bldg Closed Cooling Water Sys Inboard Isolation Valve Went Closed.Caused by Inadequate Procedure.Procedures Revised +
- 05000293/LER-1993-004, :on 930313,automatic Scram Occurred Resulting from Load Rejection During Severe Coastal Storm While at 100% Power.Caused by Environ Effects of Storm.Trip Settings of Main Input Circuit Breakers Increased +
- 05000219/LER-1979-030, Revised Attachment to LER 79-030/03L-0:on 790812,control Rod Drive Pump a Removed from Svc for Repair of Pump Vent Piping.Piping Cracked at Bushing at Entry to Pump Casing. Caused by Operator Carelessness.Bushing Replaced +
- 05000219/LER-1979-030-03, /03L-0:on 790812,control Rod Drive Pump Removed from Svc Due to Excessive Leakage from Pump Vent Piping. Piping Was Cracked at Bushing.Caused by Use of Vent Line as Operator Foot Support.Bushing & Pipe Nipple Replaced +
- ML23151A487 +