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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
- IR 05000296/1979018 + (ML18024B197)
- ML18024B197 + (ML18024B197)
- 05000296/LER-1979-023, Forwards LER 79-023/03L-0 + (ML18024B198)
- ML18024B199 + (ML18024B199)
- 05000296/LER-1979-023-03, /03L-0:on 791202,diesel Generator 3C Tripped Following Start of RHR Pump 3B.Caused by Excessive Voltage Output of Frequency Generator Due to Component Drift.Voltage Output Corrected & Speed Sensing Panels Calibr + (ML18024B200)
- ML18024B201 + (ML18024B201)
- ML18024B203 + (ML18024B203)
- ML18024B204 + (ML18024B204)
- ML18024B205 + (ML18024B205)
- IR 05000259/1979027 + (ML18024B207)
- ML18024B210 + (ML18024B210)
- ML18024B212 + (ML18024B212)
- ML18024B214 + (ML18024B214)
- ML18024B215 + (ML18024B215)
- 05000260/LER-1979-025, Forwards LER 79-025/03L-0 + (ML18024B216)
- ML18024B217 + (ML18024B217)
- 05000260/LER-1979-025-03, /03L-0:on 791205,while Performing Std Instruction 4.2.A-7,main Steam Line High Flow Switch PDIS-1-50D Exceeded Tech Spec Limit.Caused by Switch Drift.Switch Recalibr + (ML18024B218)
- 05000296/LER-1979-026, Forwards LER 79-026/03L-0 + (ML18024B219)
- ML18024B220 + (ML18024B220)
- 05000296/LER-1979-026-03, /03L-0:on 791207,during Refueling Outage,Reactor Core Isolation Cooling Failed to Reach Rated Flow Per Tech Specs.Caused by Defective High Trim Potentiometer in Reactor Core Isolation Cooling Sys.Egm Box Replaced + (ML18024B221)
- 05000296/LER-1979-022, Forwards LER 79-022/03L-0 + (ML18024B222)
- ML18024B223 + (ML18024B223)
- 05000296/LER-1979-022-03, /03L-0:on 791208,following Return to Svc After refueling,drywell-to-suppression Chamber Differential Pressure Could Not Be Maintained Per Tech Spec.Caused by Leak at Hatch Door Due to Loosened Bolts + (ML18024B224)
- 05000296/LER-1979-024, Forwards LER 79-024/03L-0 + (ML18024B225)
- ML18024B226 + (ML18024B226)
- 05000296/LER-1979-024-03, /03L-0:on 701208,following Return to Svc After Refueling,Excessive Local Leakage Detected at Southeast Drywell Equipment Hatch Door.Caused by Unevenly Tightened Bolts.Bolts Retightened + (ML18024B227)
- IR 05000296/1979021 + (ML18024B229)
- ML18024B229 + (ML18024B229)
- ML18024B233 + (ML18024B233)
- ML18024B234 + (ML18024B234)
- ML18024B236 + (ML18024B236)
- 05000296/LER-1979-025, Forwards LER 79-025/03L-0 + (ML18024B237)
- ML18024B238 + (ML18024B238)
- 05000296/LER-1979-025-03, /03L-0:on 791212,following Return to Svc After Refueling Outage,Reactor Core Isolation Cooling Failed to Reach Rated Flow.Caused by Short in Reactor Core Isolation Cooling Egm Box.Ground Wire Causing Short Removed + (ML18024B239)
- ML18024B242 + (ML18024B242)
- IR 05000259/1979033 + (ML18024B244)
- ML18024B248 + (ML18024B248)
- IR 05000259/1979035 + (ML18024B250)
- ML18024B251 + (ML18024B251)
- ML18024B254 + (ML18024B254)
- 05000296/LER-1979-027, Forwards LER 79-027/03L-0 + (ML18024B255)
- ML18024B257 + (ML18024B257)
- 05000296/LER-1979-027-03, /03L-0:on 791216,while Performing SI 4.2.C.1A, Average Power Range Monitor B Scram Setting Found to Be Greater than 120% for Simulated Flow of 125%.Caused by Instrument Drift.Trip Channels Adjusted + (ML18024B258)
- 05000296/LER-1979-028, Forwards LER 79-028/03L-0 + (ML18024B259)
- ML18024B260 + (ML18024B260)
- OIG-03-A-15, Status of Recommendations: Audit of NRCs Regulatory Oversight of Special Nuclear Materials, Dated January 24, 2017 + (ML18024B261)
- 05000296/LER-1979-028-03, /03L-0:on 791218,while Performing SI,PS-3-74A & B & PS-68-95 (Reactor Pressure) Did Not Actuate at Correct Setpont.Caused by Drifting of Barton Model 288 & Barksdale B2T-M12SS.Switches Readjusted + (ML18024B262)
- ML18024B263 + (ML18024B263)
- ML18024B265 + (ML18024B265)
- ML18024B266 + (ML18024B266)
- ML18024B267 + (ML18024B267)
- 05000260/LER-1980-002, Forwards LER 80-002/03L-0 + (ML18024B270)