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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

• L-20-078, Cycle 27-1 Core Operating Limits Report  + (ML20077H432)
• ML20077H434  + (ML20077H434)
• ML20077H441  + (ML20077H441)
• ML20077H450  + (ML20077H450)
• ML20077H452  + (ML20077H452)
• ML20077H453  + (ML20077H453)
• ML20077H456  + (ML20077H456)
• ML20077H457  + (ML20077H457)
• ML20077H458  + (ML20077H458)
• ML20077H459  + (ML20077H459)
• ML20077H460  + (ML20077H460)
• ML20077H461  + (ML20077H461)
• ML20077H463  + (ML20077H463)
• ML20077H464  + (ML20077H464)
• NG-83-2517, Public Version of Rev 1 to Emergency Plan Implementing Procedure EPIP 6.1, Maint of Duane Arnold Energy Ctr Emergency Preparedness,Receipt Form,Rev 8 to Index & Rev 16 to Rev Control Sheet  + (ML20077H493)
• ML20077H511  + (ML20077H511)
• ML20077H513  + (ML20077H513)
• ML20077H521  + (ML20077H521)
• ML20077H525  + (ML20077H525)
• 05000259/LER-1983-040-03, /03L-0:on 830707,during Surveillance,Seismic Event Strong Motion Accelograph Channel 2 Failed to Record. Caused by Faulty Transverse Channel Output Amplifier. Amplifier Replaced  + (ML20077H530)
• ML20077H531  + (ML20077H531)
• ML20077H532  + (ML20077H532)
• ML20077H533  + (ML20077H533)
• 1CAN078308, Provides Addl Info Re NUREG-0737,Item II.E.1.1 Concerining Emergency Feedwater Sys (EFW) Evaluation,Per 820618 Request. Extensive Upgrade of EFW Sys in Progress.Upgrade of EFW Suction Initial Source Under Consideration  + (ML20077H534)
• 05000416/LER-1983-086-01, /01T-0:on 830721,inadvertent Actuation of Div II LOCA Logic Occurred.Caused by Personnel Error.Maint Personnel Accidently Jumped Bus Bars on Back of Trip Units B21-N691B & F.Fuse Replaced  + (ML20077H536)

• 05000293/LER-1983-039-03, /03L-0:on 830702,HPCI Turbine Stop Valve Required More than Normal Time to Open.Hpci Sys Declared Inoperable & Reactor Shutdown Initiated.Caused by Deteriorating Orifice Plate Gasket.Gasket Replaced  + (ML20077H539)

• 05000338/LER-1983-047-03, /03L-0:on 830706,w/unit at 100% Power & One High Head Safety Injection (Nhsi) Pump Undergoing Maint,Second HHSI Pump Removed from Svc Due to High Bearing Temp.First Pump Returned to Svc  + (ML20077H540)
• ML20077H541  + (ML20077H541)
• 05000293/LER-1983-040-03, /03L-0:on 830703,while Conducting Surveillance Tests,Core Spray Injection Valve 1400-25A Would Not Close. Caused by Loose Stem Nut Preventing Valve Operator from Closing Valve.Stem Nut Tightened  + (ML20077H543)
• ML20077H544  + (ML20077H544)
• 2CAN088307, Forwards Analysis of Spurious Actuation of ESF Sys. Consequences of Spurious Actuations of ESF Actuation Sys Combinations Would Be No More Severe than Scenarios Previously Analyzed  + (ML20077H545)
• ML20077H546  + (ML20077H546)
• 05000324/LER-1983-057-03, /03L-0:on 830705,review of Documentation for ECCS-HPCI/CST Level Low Instruments Determined That Eight Tests Performed During 1979-82 Found One or Both Channels Operating Out of Tolerance & Left as Found  + (ML20077H547)
• 05000328/LER-1983-093-03, /03L-0:on 830706,condenser Vacuum Flow Rate Monitor 2-FT-2-257 Declared Inoperable Due to Loss of Readings.Cause Unknown.Investigation Continuing.Annular Bar Flow Element to Be Replaced  + (ML20077H548)
• 05000338/LER-1983-049-03, /03L-0:on 830710,following Reactor Trip from 100% power,I-131 Dose Equivalent Specific Activity Exceeded 1.0 Mci/G.Caused by Minor Fuel Element Defects in Reactor Core.Sampling Frequency Accelerated  + (ML20077H556)
• ML20077H557  + (ML20077H557)
• ML20077H558  + (ML20077H558)
• ML20077H559  + (ML20077H559)
• ML20077H577  + (ML20077H577)
• ML20077H581  + (ML20077H581)
• ML20077H582  + (ML20077H582)
• ML20077H586  + (ML20077H586)
• 05000369/LER-1983-046-03, /03L-0:on 830617,following Identification of burned-out Preheater Element on 830403,outside Air Pressure Filter Train B Declared Inoperable.Caused by Component Failure & Personnel Error.Element Replaced  + (ML20077H589)
• 05000364/LER-1983-027-03, /03L-0:on 830708,train a Manual Trip Channel Declared Inoperable When Control Power Fuses for Reactor Trip Bypass Breaker B Inadvertently Removed.Caused by Personnel Error.Individual Counseled  + (ML20077H594)
• ML20077H595  + (ML20077H595)
• 05000395/LER-1983-077-03, /03L-0:on 830705,train B Solid State Protection Sys Declared Inoperable.Caused by Defective Circuit Board in Logic Circuitry.Board Replaced & Appropriate Surveillance Test Satisfactorily Performed  + (ML20077H596)
• ML20077H597  + (ML20077H597)
• AECM-83-0430, RO 83-061/0:on 830701,listed fire-rated Penetrations Opened to Implement Design Change Packages.Hourly Fire Watches Established within 1 H.Work Tasks Expected to Be Complete by 830910  + (ML20077H598)
• ML20077H601  + (ML20077H601)
• 05000328/LER-1983-095-03, /03L-0:on 830708 & 13,plant Process Computer Failed,Rendering Subcooling Margin Monitor Inoperable.Caused by Power Glitch & Memory Module Loose Connection & Dirty Edge Connector.Module Repaired  + (ML20077H602)
• ML20077H603  + (ML20077H603)