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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

• 05000397/LER-1989-016, :on 890514,reactor Operator Inadvertently Tripped Div 1 & 2 Offsite Power Supply Feeders Resulting in Loss of Power to Buses SM-7 & SM-4.Caused by Inadvertent Removal of Transformer Fuses.Fuses Reinserted  + (ML17285A559)
• GO2-89-109, Advises NRC That Requirement of Reg Guide 1.97,Rev 2 to Provide Qualified Wide Range Neutron Monitor Satisfied. Requests That Deferral Contained in Be Withdrawn  + (ML17285A560)
• ML17285A561  + (ML17285A561)
• 05000397/LER-1989-005, :on 890311,34 of 185 Control Rods Drifted Inward from One to Seven Notches.Caused by Main Steam Line Radiation Monitor Design Deficiency.Desired Rod Pattern Reestablished  + (ML17285A564)
• 05000397/LER-1989-017, :on 890520,outboard RHR Shutdown Cooling Valve Automatically Isolated,Causing Loss of Shutdown Cooling. Caused by Removal of Relay by Contractor Maint Electrician Installing Mod to Leak Detection Sys  + (ML17285A565)
• 05000397/LER-1989-018, :on 890522,reactor Protection Sys (RPS) a motor-generator Set Failed Resulting in Loss of Power to RPS Bus A.Caused by Component Failure.Motor Replaced  + (ML17285A566)
• 05000397/LER-1989-019, :on 890524,inboard RHR Shutdown Cooling Supply Valve Automatically Isolated When Electrician Lifted Wire Deenergizing Valve Control Relay.Personnel Counseled & Training in Plant Procedures Initiated  + (ML17285A567)
• ML17285A568  + (ML17285A568)
• ML17285A570  + (ML17285A570)
• ML17285A571  + (ML17285A571)
• ML17285A572  + (ML17285A572)
• ML17285A573  + (ML17285A573)
• IR 05000397/1989015  + (ML17285A575)
• GO2-89-110, Discusses Plant ATWS Mod Schedule.Two Issues Re Logic Relays & Topical Rept Need Clarification  + (ML17285A577)
• 05000397/LER-1989-005-01, :on 890311,of 185 Control rods,34 Drifted Inward from One to Seven Notches Due to Momentary Low Scram Air Header Pressure.Caused by Main Steam Radiation Monitor Design Deficiency  + (ML17285A578)
• ML17285A579  + (ML17285A579)
• ML17285A580  + (ML17285A580)
• 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)