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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
- 05000255/LER-1983-012-03, /03L-0:on 830130,sample from T-82D (Safety Injection Tank D) Showed Boron Concentration Below Tech Spec Limit of 1,720 Ppm.Caused by Boron Dilution Due to Minor Leak Past Check Valve.Primary Coolant Leak Rate Monitored + (ML20071C897)
- ML20071C899 + (ML20071C899)
- ML20071C901 + (ML20071C901)
- ML20071C902 + (ML20071C902)
- ML20071C903 + (ML20071C903)
- 05000373/LER-1983-006-03, /03L-0:on 830202,steam Observed Leaking from MSIV,1B21-F028A,due to Two Cracks 180 Degrees Apart in Weld Where 1MS20AA-2-inch Drain Line Attached to Valve Body. Caused by Improper Weld Application.Weld Repaired + (ML20071C904)
- 05000254/LER-1983-006, Forwards LER 83-006/03L-0 + (ML20071C905)
- ML20071C910 + (ML20071C910)
- ML20071C911 + (ML20071C911)
- 05000254/LER-1983-006-03, /03L-0:on 830213,during Monthly Surveillance Test on Condenser Pit 5-ft Trip Circuits,Level Switch 1-4441-25B Failed to Give Circulating Water Pump Trip Signal.Caused by Broken Wire in Switch Mechanism.Switch Replaced + (ML20071C913)
- ML20071C917 + (ML20071C917)
- ML20071C921 + (ML20071C921)
- 05000311/LER-1983-003, Forwards LER 83-003/03L-0.Detailed Event Analysis Encl + (ML20071C922)
- ML20071C923 + (ML20071C923)
- TXX-3635, Final Deficiency Rept Re Radiation Monitoring Sys.Initially Reported on 830201.Investigation Complete.Matter Not Reportable Per 10CFR50.55(e) + (ML20071C925)
- 05000311/LER-1983-003-03, /03L-0:on 830111,rod Position Indicator Channel 1SA2 Indicated Approx Half Scale,Contrary to Flux Map Indication That No Change in Rod Position Occurred.Caused by Failed Signal Conditioner.Module Replaced + (ML20071C930)
- ML20071C932 + (ML20071C932)
- ML20071C934 + (ML20071C934)
- ML20071C977 + (ML20071C977)
- ML20071C978 + (ML20071C978)
- ML20071C986 + (ML20071C986)
- ML20071C991 + (ML20071C991)
- ML20071C999 + (ML20071C999)
- ML20071D003 + (ML20071D003)
- 05000387/LER-1983-018, Forwards LER 83-018/03L-0 + (ML20071D009)
- ML20071D012 + (ML20071D012)
- ML20071D017 + (ML20071D017)
- 05000387/LER-1983-018-03, /03L-0:on 830126,during Startup Test Program, Found Inaccurate Value for 100% Rated Recirculation Flow Utilized to Establish Average Power Range Monitor flow-biased Rod Block & Scram Setpoints.Points Reset + (ML20071D027)
- ML20071D029 + (ML20071D029)
- ML20071D035 + (ML20071D035)
- ML20071D038 + (ML20071D038)
- ML20071D041 + (ML20071D041)
- ML20071D053 + (ML20071D053)
- ML20071D056 + (ML20071D056)
- ML20071D069 + (ML20071D069)
- ML20071D071 + (ML20071D071)
- ML20071D075 + (ML20071D075)
- ML20071D080 + (ML20071D080)
- ML20071D081 + (ML20071D081)
- TXX-3632, Advises of Reactor Vessel Preservice Insp in Early Apr 1983. Insp Will Consist of Std ASME Code Section XI Insp & Addl Insp of Beltline Region Welds Utilizing Westinghouse Shallow Angle near-surface Technique + (ML20071D089)
- ML20071D096 + (ML20071D096)
- ML20071D097 + (ML20071D097)
- 05000272/LER-1983-006, Forwards LER 83-006/03L-0.Detailed Event Analysis Encl + (ML20071D100)
- ML20071D103 + (ML20071D103)
- ML20071D107 + (ML20071D107)
- 05000272/LER-1983-006-03, /03L-0:on 830126 & 28 Nonseismically Qualified Components & Power Boxes Discovered Installed in Dc Control Power Feeds to Emergency Diesel Generators.Caused by Personnel Oversight.Power Box Components Replaced + (ML20071D111)
- PM-82-142, Forwards Semiannual Rept:Plant Radioactive Effluent Releases,Jul-Dec 1981 + (ML20071D114)
- ML20071D115 + (ML20071D115)
- ML20071D122 + (ML20071D122)
- ML20071D123 + (ML20071D123)
- ML20071D128 + (ML20071D128)