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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
- ML13092A100 +
- ML17318A630 +
- ML17317A665 +
- ML20011E697 +
- PNP 2019-016, & Big Rock Point - 2018 Annual Radioactive Effluent Release and Waste Disposal Report +
- ML19323F154 +
- ML031420491 +
- ML20073F269 +
- ML20100R429 +
- ML20135G249 +
- IR 05000266/1988007 +
- ML20133F483 +
- ML20214C805 +
- ML20216G820 +
- ML20058K863 +
- ML24107B149 +
- ML23332A046 +
- 05000341/LER-1999-004, :on 990913,HPCI Sys Was Noted Inoperable.Caused by Failed HPCI Room Temp Switches.Replaced Temp Switches & HPCI Was Restored to Operable Status.With +
- 05000249/LER-1986-017-07, :on 861014,Group I Isolated & Subsequent Reactor Scram Occurred.Caused When Contractor Inadvertently Jarred Msivs.Personnel Counseled +
- 05000282/LER-1997-014, :on 971028,maint Shop Fire in Service Building Occurred.Caused by Spark or Hot Molten Particle Drawn Into Air Filtration Device Which Ignited 1 of 2 Paper Filters. Evacuated Turbine Bldg +
- 05000285/LER-1988-026, :on 881014,emergency Diesel Generator 2 Automatically Started to Idle Speed.Caused by Personnel Error Compounded by Procedure Inadequacy.Relay Work Scheduled During Bus or Equipment Outages +
- 05000341/LER-1985-010, :on 850427,reactor Protection Sys Tripped. Caused by APRM E Upscale Trip Due to Recorder Door Malfunction.Lprm Cables & Connectors Repaired & Chart Recorder Door Modified +
- 05000265/LER-1991-014-06, :on 911218,2A RHR Heat Exchanger Support Beams Found to Be Outside Basis During Lifting Due to Notches in Flange Area.Work Request Q96769 Initiated to Reinforce Degraded Support Beams +
- 05000254/LER-1991-006, :on 910219,ESF Actuation Occurred Due to Unexpected Loss of Power to Channel B of Reactor Protection Sys,Causing Primary Containment Isolation.Caused by Mechanical Vibration.Power Reestablished +
- 05000346/LER-1990-002, :on 900126,reactor Tripped from 73% Power. Caused by Spurious Reactor Coolant Pump Monitor Signal Indicating Only One Pump Running in Each Loop.Pump Seal to Be Replaced During Sixth Refueling Outage +
- 05000400/LER-1988-003-01, :on 880121,peak Reactor Power of 103% Reached. Caused by Jumper Wire Installed in Train a of solid-state Protection Sys Cabinet.Extensive Wire Check Conducted for Addl Wiring Errors & Evaluation of Safety +
- 05000397/LER-1993-029, :on 930805,discovered Primary Coolant Steam Leak.Caused by Weld Defect.Weld Crack Repaired on 930806. Weld Record for Applicable Weld Also Reviewed & No Discrepancies Identified +
- BVY-04-108, September 2004 Monthly Operating Report for the Vermont Yankee Nuclear Power Station +
- ML16214A216 +