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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

• ML17285A581  + (ML17285A581)
• IR 05000397/1989011  + (ML17285A583)
• 05000397/LER-1989-021, :on 890527,electrical Protection Assembly Breaker Tripped Causing Loss of Power to Reactor Protection Sys Bus B.Cause Unknown.Upgraded Breaker Equipment Will Be Installed  + (ML17285A584)
• ML17285A585  + (ML17285A585)
• IR 05000397/1989014  + (ML17285A587)
• GO2-89-114, Application for Amend to License NPF-21,modifying Tech Spec Tables 3.3.7.5-1 & 4.3.7.5-1 Re Accident Monitoring Instrumentation & Surveillance Requirements  + (ML17285A594)
• ML17285A595  + (ML17285A595)
• ML17285A596  + (ML17285A596)
• ML17285A597  + (ML17285A597)
• IR 05000397/1989021  + (ML17285A599)
• 05000397/LER-1989-023, :on 890531,ESF Isolations & Actuations Occurred Due to Loss of Reactor Protection Sys Bus During Testing. Caused by Personnel Error.Logic Sys Functional Test Procedure Revised.Test Engineer Counseled  + (ML17285A601)
• 05000397/LER-1989-022, :on 890530,loss of Secondary Containment During Core Alterations Due to Unisolatable Lines Occurred.Caused by Simultaneous Activities.Rhr Heat Exchanger Isolation Valves Closed to Reestablish Integrity  + (ML17285A602)
• ML17285A605  + (ML17285A605)
• 05000397/LER-1989-020, :on 890527 & 0605,during Local Leak Rate Testing,Valve RHR-V-9 Automatically Isolated.Caused by Procedural Inadequacy & Inadequate Corrective Action Following Second Event.Procedure Modified  + (ML17285A606)
• ML17285A607  + (ML17285A607)
• GO2-89-116, Advises That Final Response to Generic Ltr 88-14, Instrument Supply Sys Problems Affecting Safety-Related Equipment, Including Outage Test Results,Will Be Provided by 890728  + (ML17285A608)
• ML17285A610  + (ML17285A610)
• ML17285A612  + (ML17285A612)
• ML17285A613  + (ML17285A613)
• ML17285A616  + (ML17285A616)
• IR 05000397/1989013  + (ML17285A617)
• GO2-89-118, Provides Justification for Continued Use of Five Installed Items Identified in Insp Rept 50-397/89-21,in Response to Bh Faulkenberry .Final Results & Assessment of Addl Commercial Grade Items Will Be Provided by 890815  + (ML17285A618)
• GO2-89-119, Responds to Concerns Noted in Insp Rept 50-397/89-01 Re Implementation of Root Cause Analysis (RCA) Program & RCA Rept Prepared for 890311 Rod Drift Event.Plans to Combine Elements of Process & Document Results in Incident Rept  + (ML17285A619)
• ML17285A620  + (ML17285A620)
• 05000397/LER-1989-024, :on 890614,secondary Containment Bypass Leakage Found Greater than Allowed by Design Basis.Caused by Equipment Design Deficiency.Check Valves in Common Discharge Line of CRD Pump Installed to Prevent Leakage  + (ML17285A621)

• ML17285A623  + (ML17285A623)

• IR 05000397/1989018  + (ML17285A625)
• 05000397/LER-1989-025, :on 890617 & 18,three Separate But Related Events Occurred Which Caused ESF Isolations & Actuations During Excess Flow Check Valve Testing.Caused by Inadequate Procedure.Procedure Modified  + (ML17285A626)
• ML17285A627  + (ML17285A627)
• ML17285A628  + (ML17285A628)
• GO2-89-123, Forwards Addl Info Re 880726 Response to Generic Ltr 88-01, Per NRC 890516 Request  + (ML17285A629)
• 05000483/LER-1917-002, Regarding Inadequate Protection from Tornado Missiles Identified Due to Nonconforming Design  + (ML17285A630)
• 05000397/LER-1989-026, :on 890619,testing Confirmed That Selected Steam Tunnel Penetrations Could Fail to Perform as Pressure Boundary Following Design Basis Main Steamline Break.Caused by Inadequate Design Mgt.Part 21 Related  + (ML17285A631)
• GO2-89-125, Advises That No Agreements Exist That Contain Restrictive Clauses Re Employee Right to Discuss Potential Safety Issue  + (ML17285A633)
• GO2-89-120, Provides Addl Info Re Acceptability of Five Installed Items for Use in safety-related Applications,Per Insp Rept 50-397/89-21.Items Include,Potter & Brumfield Relays,Anchor Darling Valve Parts & 600 Volt or Less Fuses  + (ML17285A634)
• GO2-89-127, Responds to Generic Ltr 89-06, SPDS, Certifing That Graphic Display Sys Fully Meets Requirements of NUREG-0737, Suppl 1,taking Into Account Info Provided in NUREG-1342  + (ML17285A635)
• ML17285A636  + (ML17285A636)
• GO2-89-129, Responds to NRC Re Violations Noted in Insp Rept 50-397/89-13.Corrective Actions:Radiation Barrier Posting for RWCU HX Room Removed from accordion-style Gate at Entrance to Room & Placed on Rope in Front of Gate  + (ML17285A637)
• GO2-89-128, Forwards Instrument Air Sys Review Response to Generic Ltr 88-14, Per 890706 Commitment  + (ML17285A639)
• ML17285A640  + (ML17285A640)
• ML17285A641  + (ML17285A641)
• 05000397/LER-1989-028, :on 890629,turbine Throttle Valve Closure Reactor Scrammed During Turbine Testing.Caused by Inadequate Procedure.Operator Acted Promptly Tp Place Plant in Safe Shutdown Condition.Training Program Improved  + (ML17285A644)
• ML17285A646  + (ML17285A646)
• IR 05000397/1989016  + (ML17285A648)
• GO2-89-133, Submits Final Response to Suppl 1 to NRC Bulletin 85-003. Measured Thrust Values for Valves Obtained by Analysis of Spring Pack Calibr Signatures & Valves Controlled by Limit Switches W/Open Torque Switches Jumpered Throughout Travel  + (ML17285A649)
• ML17285A650  + (ML17285A650)
• IR 05000397/1989022  + (ML17285A652)
• ML17285A653  + (ML17285A653)
• ML17285A655  + (ML17285A655)
• IR 05000397/1989006  + (ML17285A656)
• 05000397/LER-1989-029, :on 890703,RWCU & RCIC Sys Isolation Occurred When RWCU-V-1 Closed as Part of Group 7 Nuclear Steam Supply Shutoff Sys Isolation.Caused by Inadequate Preparation & Review of Surveillance Test Procedure  + (ML17285A657)