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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
- ML20084C055 + (ML20084C055)
- ML20084C062 + (ML20084C062)
- ML20084C067 + (ML20084C067)
- 05000281/LER-1983-060-03, /03L-0:on 831220,feeder Breaker for Heat Tracing Panel 2B1 Tripped.Caused by Ground Fault That Occurred When Ac Power Supply Fuse Blew.Fuse Replaced & Ground Fault Circuit for Feeder Breaker Removed + (ML20084C071)
- ML20084C076 + (ML20084C076)
- ML20084C085 + (ML20084C085)
- ML20084C090 + (ML20084C090)
- ML20084C092 + (ML20084C092)
- ML20084C095 + (ML20084C095)
- ML20084C097 + (ML20084C097)
- ML20084C098 + (ML20084C098)
- ML20084C100 + (ML20084C100)
- 05000302/LER-1983-056-03, Discovered Governor on Emergency Feedwater Pump 2 Set Incorrectly.Caused by Setting Inadvertently Changed.Proper Setting Checked on Daily Basis & Locking Cover Installed + (ML20084C103)
- ML20084C105 + (ML20084C105)
- ML20084C111 + (ML20084C111)
- ML20084C113 + (ML20084C113)
- ML20084C117 + (ML20084C117)
- ML20084C118 + (ML20084C118)
- ML20084C122 + (ML20084C122)
- ML20084C123 + (ML20084C123)
- ML20084C125 + (ML20084C125)
- NRC-84-0071, Forwards Addl Info Re Comparison of Snupps ECCS Evaluation Model to Recent 1981 Evaluation Model,In Connection w/840417 Ltr on Proposed Rev of Emergency Diesel Generator Start Time from 10 to 12 + (ML20084C126)
- 05000302/LER-1982-033-03, Reactor Bldg Pressure Indicator BS-16-PI Discovered Inoperable.Caused by Instrument Drift.Bailey Transmitters BS-16-PT & BS-17-PT Replaced W/Rosemount Transmitters & Calibr + (ML20084C131)
- ML20084C132 + (ML20084C132)
- 3F0484-16, Responds to 840416 Request for Addl Info Re Reactor Vessel Head Vent.Individual Assigned to Review once-through- integral-sys (Otis) Facility Test Procedure & to Attend 840424 Test.Otis Test Results Expected by 840622 + (ML20084C133)
- ML20084C134 + (ML20084C134)
- ML20084C135 + (ML20084C135)
- 05000296/LER-1984-005-02, :on 840402,during Induction Heat Stress Improvement Program,Linear Root Indication in Heat Affected Zone Found on 6-inch Pipe Weld in Reactor Water Cleanup Sys. Cause Undetermined.Weld Will Be Left as Is + (ML20084C136)
- 05000219/LER-1976-026-01, /01P-0:on 761012,unplanned Radioactive Release to Discharge Canal Not Monitored.Caused by Design Error Routing Relief Valve Discharge Via 1-5 Sump Instead of to Radwaste Facility Via High Conductivity Tank.Valve to Be Rerout + (ML20084C137)
- ML20084C141 + (ML20084C141)
- ML20084C151 + (ML20084C151)
- ML20084C154 + (ML20084C154)
- 2CAN948406, Informs That Lectures Will No Longer Be Given on MW Demand Setter in Shift Technical Advisor Training Program Because Setter Removed from Plant + (ML20084C158)
- ML20084C160 + (ML20084C160)
- 05000277/LER-1984-005-01, :on 840323,partial Actuation of Primary Containment Isolation Sys Occurred.Caused by Power Loss to Portion of Primary Containment Isolation Sys Due to Blown Fuse from Shorted Coil in Relay 1GA-K56 + (ML20084C163)
- 05000244/LER-1976-020-01, /01T-0:on 760709,diesel Generator 1A Supply Breaker Overcurrent Trip Alarm Failed to Clear Following Attempt to Electrically Reset Breaker.Caused by Wear on Hunt Trip Alarm Switch Linkage + (ML20084C164)
- ML20084C170 + (ML20084C170)
- ML20084C173 + (ML20084C173)
- NRC-84-0074, Forwards Rev 0 to Procedure EDP-ZZ-00005, Assessing Core Damage, Re Capability of post-accident Sampling Sys to Meet NUREG-0737,Item II.B.3 Criteria Per Sser 4.Deletion of License Conditions Re post-accident Sampling Requested + (ML20084C177)
- 05000244/LER-1976-018-03, /03L-0:on 760704,B Bank Group 2 Rod Cluster Controls G-5 & 9 Dropped.Replacement of Fuses,Capacitors & Resistors in B Bank Group 2 Stationary Circuitry Recommended + (ML20084C178)
- ML20084C182 + (ML20084C182)
- 05000244/LER-1976-017-03, /03L-0:on 760618,A Accumulator Level Noted Below Tech Spec Limit.Caused by Procedure S-16.11 Not Providing Precautions Re Operator Remaining at Valve Controls During Lowering level.S-16.11 Changed + (ML20084C185)
- 05000244/LER-1976-016-03, /03L-0:on 760520,rod Position Deviation Channel Found Inoperable.Caused by Failure in Computer to Correctly Monitor Rod Position Deviation.Program Reinitialized + (ML20084C193)
- ML20084C203 + (ML20084C203)
- 05000219/LER-1976-013-01, /01P-0:on 760503,secondary Containment Integrity Violated.Caused by Willful Violation of Plant Procedures. Contractor Personnel Instructed on Reactor Bldg Door Interlock Purpose & Seriousness of Event + (ML20084C207)
- 05000244/LER-1976-015-03, /03L-0:on 760424,air Ejector & Blowdown Radiation Monitors Alarmed Due to Iodine Leak from Steam Generator Tubes.Cause Under Investigation.Steam Generator Tubes Above Tube Sheet Plugged + (ML20084C213)
- ML20084C218 + (ML20084C218)
- ML20084C222 + (ML20084C222)
- B15238, Provides Info Committed to in to NRC Re Readiness Assessment Team Insp,Including Major Activities Yet to Be Completed,Startup Criteria & Startup Assessment Team Final Rept + (ML20084C228)
- ML20084C230 + (ML20084C230)
- 05000244/LER-1976-014, Updated LER 76-014/03O-1:on 760412,N44 Power Range Detector High Voltage Power Supply Failed.Caused by Defective Modular Block Part IV-101.Power Supply Recalibr + (ML20084C231)