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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 49623  +
• 05000389/LER-2003-004, Regarding Condensate Pump Motor Bearing Failure That Resulted in Manual Reactor Trip  +
• 05000255/LER-1990-018, :on 900930,flow Rates for Each of Two Primary Coolant Sys Hot Legs Less than Acceptance Criteria of 250 Gpm.Caused by Short Disk Guides & Inefficient Drainage.Hot Leg Check Valves Replaced  +
• RBG-47562, Annual Radioactive Effluent Release Report for 2014  +
• ML20042G891  +
• ML20080C234  +
• ML20079B827  +
• ML20094E264  +
• ML20092F152  +
• ML20092E865  +
• ML20137D238  +
• ML20137C408  +
• ML20141G396  +
• ML20116E016  +
• ML20199D031  +
• ML20207C330  +
• ML20202H639  +
• ML20212G726  +
• ML20247B522  +
• ML20245H384  +
• ML20215N871  +
• IR 05000315/2021002  +
• 05000336/LER-2022-001, Structural Integrity of Reactor Building Component Cooling Water Cracked Threaded Fitting Could Not Be Established Resulting in System Inoperable Longer than Allowed by Technical Specifications  +
• 05000368/LER-1986-007, :on 860426,automatic Reactor Trip Occurred Due to Ground Fault Trip of Reactor Coolant Pump Breaker.Maint Check of Reactor Coolant Pump Motor,Power Leads & Breaker Initiated  +
• 05000354/LER-1987-003, :on 870112,reactor Water Cleanup Sys Isolation Occurred Due to Blown Fuse on Nsss.Caused by Inadequate Access to Steam Leak Detection Panels for Testing & Installation of Test Equipment  +
• 05000285/LER-1992-014, :on 920514,steam Leak Identified Coming from Capped Connection on Turbine Trip Switch on Moisture Separator,Resulting in Reactor Trip.Caused by Communication Problems.Training Provided & Order Issued  +
• 05000338/LER-1991-022-01, :on 911223,unit Shutdown Initiated Due to Indeterminate Status of SGs as Result of Eddy Current re- Review.Comprehensive Eddy Current Insp Plan Developed.W/  +
• 05000293/LER-1991-024, :on 911030,loss of Preferred & Secondary Offsite Power Occurred Due to Severe Coastal Storm While Shut Down.Caused by Flashover Switchyard Insulator. Westinghouse Type Relay 62/5 Will Be Replaced  +
• 05000416/LER-1984-004, :on 840114,shutdown Cooling Suction Valve Isolated.Caused by Fuse Failure During Technician Panel Work.Fuse Replaced  +
• 05000325/LER-1990-024, :on 901124,1 of 2 Reactor Bldg Ventilation Exhaust Dampers Closed & Reactor Bldg Ventilation Supply & Exhaust Fans Tripped.Reactor Bldg Ventilation Restored  +
• 05000336/LER-1982-041-03, /03L-0:on 821019,control Element Assembly 23 Dropped Fully Into Core.Caused by Failure of Coil Power Programmer 5-volt Dc Power Supply.Upper Gripper Power Switch Replaced  +
• 05000293/LER-1993-018, :on 930721,planned Shutdown Initiated Due to Unidentified Leakage of 3 Gpm.On 930722,planned Shutdown Became TS Required Shutdown When Insp Revealed Leakage to Be Rc Pressure Boundary Leakage.Leakage Repaired  +
• 05000461/LER-1990-012, :on 900517,feedwater Sys Flow Channel Failed & Caused Sensed Low Feedwater Flow.Caused by Normal end-of- Life Failure for Converter.Power Converter Replaced & Preventive Maint Tasks Established  +
• 05000285/LER-1990-002, :on 900226,inadvertent Actuation of Containment Isolation Actuation Signal Occurred W/Plant in Refueling Shutdown Condition.Caused by Accidental Actuation of Lockout Relay by Craftsman.Mod Procedure Revised  +
• 05000382/LER-1994-012-01, :on 940907,discovered Failure to Perform TS Surveillance Requirements.Caused by Misunderstanding & Inadequate Technical Reviews.Ts Bases for 3/4.8.1 Will Be Revised  +
• ML20010B479  +
• 05000219/LER-1979-012-03, /03L-0 on 790419:oxygen Level in Suppression Chamber Atmosphere Was Greater than 5%.Caused by Sensitivity of Sampling Sys & Position of Sample Flow Control Valve. Oxygen Analyzer Recalibr;Level Now Below 5%  +
• NUREG-0227, Partial Draft of Nuclear Power Plant Operating Experience - 1978, Section 3.0, Plant Outages. Portions of NUREG-0483, NUREG-0366 & NUREG-0227 (Plant Operating Experience for 1977,1976 & 1974-75,respectively) Encl  +
• 05000346/LER-2014-004, Regarding Deficiency in Loss of Coolant Accident Analysis Adversely Affected Predicted Peak Cladding Temperature  +
• 05000301/LER-2007-007, 0 for Point Beach Nuclear Plant Unit 2, One Overpower Delta T Channel Setpoint Outside Technical Specification Allowed Value  +
• IR 05000395/1998006  +
• ML20212E744  +