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

• ENS 44613  +
• ML103260467  +
• ML030990289  +
• 05000311/LER-1993-010, :on 930629 & 30,TS 3.0.3 Entered Due to More than One Inoperable Analog Rod Position Indicator Per Bank. Caused by Sys Design.Signal Conditioning Modules of Affected Rods Adjusted  +
• ML19340E975  +
• NRC-10-0061, Exemption Request from the Biennial Emergency Preparedness Exercise Requirement in 10 CFR 50, Appendix E, Section IV.F.2.b  +
• ML20028G136  +
• L-PI-08-062, Irradiated Fuel Management Plan and Preliminary Decommissioning Cost Estimates  +
• ENS 54417  +
• 3F0512-03, 2011 Annual Radiological Environmental Operating Report  +
• ML041740650  +
• ML032110359  +
• ML020590465  +
• ML20086F627  +
• ML20137G100  +
• ML20133B159  +
• ML20127N822  +
• ML20066D351  +
• ML20249A533  +
• ML20245L629  +
• ML20236W090  +
• ML20216F320  +
• BECO-86-016, Partially Withheld Security Event Rept:On 860215 Security Officer Appeared to Be Asleep at Post at Vital Area Penetration.Unathorized Entry of Vital Area Did Not Occurr. Security Officer Relieved of Duty & Suspended  +
• L-99-126, Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With  +
• BECO-92-002, Special Rept:On 911214,electric Fire Pump Declared Operable. Caused by Electrical Fault in Motor Controller.Temporary Mod Continued to Keep Electric Fire Pump Available Until New Motor Controller Procured  +
• 05000267/LER-1989-011, :on 890623,discovered That Reheat Steam Attemperation Flow Not Accounted for in Secondary Heat Balance Calculation of Reactor Power.Caused by Inadequate Procedures.Procedure Changes Implemented  +
• 05000309/LER-1987-007, :on 870701,main Turbine Manually Tripped Due to High Vibrations at Bearing 5.Cause Unknown.During 1987 Refueling Outage,Low Pressure Main Turbine Disassembled for Insp & Maint Repairs  +
• 05000219/LER-1987-033, :on 870911,Tech Spec Safety Limit Requiring Two Recirculation Loops to Be Fully Opened Violated.Caused by Personnel Error.Addl Training for Operators Will Be Provided & Procedure Revs in Progress  +
• 05000352/LER-1987-006, :on 870218 & 19,control Room Ventilation Sys Isolated & Control Room Emergency Fresh Air Supply Sys Train B Initiated.Caused by Chlorine Analyzer D Falsely Indicating Chlorine Present.Ventilation Isolation Reset  +
• 05000339/LER-1986-002-02, :on 860220,during Mode 3,reactor Tripped on source-range Neutron Detectors N-35 & N-36 High Flux.Cause Unstated.Detectors Returned to Svc.Investigation Continuing  +
• 05000461/LER-1992-001, :on 920104,failure of B Phase Main Power Transformer Led to Turbine Generator Trip & Reactor Scram. Caused by Internal Fault Leading to Transformer Replacement  +
• ML20084R881  +
• 05000373/LER-1994-007-04, :on 940517,RHR Sys Shutdown Cooling Isolation Occurred Due to Procedural Inadequacy.Technical Surveillance Procedures LTS-800-104,LTS-800-105,LTS-800-204 & LTS-800-205 Will Be Revised  +
• IR 05000341/1990013  +
• 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  +
• 05000281/LER-1993-004-02, :on 930823,reactor Tripped Due to Turbine - Generator Trip.Caused by Loss of Field Relay.Reactor Trip Breakers Verified Open & Control Rods Verified Inserted Into Core  +
• 05000311/LER-1993-010-01, :on 930629,reactor Shutdown Initiated Per TS 3.0.3 Due to Inoperability of More than One Control Rod Analog Rod Position Indication Per Control Bank.Signal Conditioning Modules of Affected Rods Adjusted  +
• 05000335/LER-1997-005, :on 970419,reactor Was Shutdown Due to Reactor Coolant Pressure Boundary Leakage.Hot Cracking Was Caused by Weld Contamination.Repairs to RCPB Were Completed & 1A SDC Train Was Restored to Svc  +
• 05000220/LER-2004-001, Re Manual Reactor Scram and Cooldown Rate Exceeding Technical Specification Limits Due to Electrometric Relief Valve Failure to Close  +
• ML25085A005  +