Search by property
Jump to navigation
Jump to search
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
- ML20058L034 + (ML20058L034)
- 05000354/LER-1990-010-02, :on 900628,ESF Actuation/Rwcu Isolation on High Differential Flow Signal Occurred Due to Procedural Inadequacies & Personnel Error.Caused by Open Drain Path Upstream of Discharge Valve.Isolation Reset + (ML20058L036)
- JAFP-90-0581, Forwards Proposed Rev 6 to IAP-2, Classification of Emergency Conditions, Per Insp Rept 50-333/90-15,Unresolved Item 89-11-03.Rev Incorporates Changes Assuring That Applicable Initiating Conditions,Per NUREG-0654,addressed + (ML20058L037)
- ML20058L040 + (ML20058L040)
- ML20058L041 + (ML20058L041)
- ML20058L042 + (ML20058L042)
- ML20058L045 + (ML20058L045)
- LIC-93-0295, Informs That Util Implemented Necessary Actions Associated W/Listed Open Issues & That Subject to Agreement by Nrc/Nrr Project Manager,Items Considered Ready to Close + (ML20058L049)
- ML20058L051 + (ML20058L051)
- ML20058L052 + (ML20058L052)
- ML20058L053 + (ML20058L053)
- 05000369/LER-1989-010-04, :on 890515,main Feedwater & Auxiliary Feedwater Isolation Valves Determined to Be Potentially Inoperable. Caused by Mfg Deficiency.Emergency Procedures Changed + (ML20058L054)
- ML20058L055 + (ML20058L055)
- 05000029/LER-1990-005, :on 900706,determined That Pressurizer Code Safety Valve Exceeded Tech Spec Lift Tolerance of Nameplate Set Pressure.Caused by Setpoint Drift.Valve Retested & Disassembled + (ML20058L056)
- ML20058L059 + (ML20058L059)
- 05000344/LER-1990-029, :on 900629,control Switches for Safety Injection Pumps Found in Pull-to-Lock Position.Caused by Personnel Error in Failing to Follow Procedures.Pump Control Switches Placed in Auto Position + (ML20058L060)
- 05000412/LER-1990-008-01, :on 900702,reactor Trip Occurred,Resulting from Turbine/Generator Trip.Caused by Personnel Error Which Resulted in Protection Relay Actuation.Event Reviewed W/Personnel & Design Mod Being Reviewed + (ML20058L062)
- ML20058L067 + (ML20058L067)
- TXX-9024, Provides Status of Exam Activity & Revised Completion Schedule for Portion of Exam.Util Deferred Preoperational Testing of Facility Spent Fuel Pool Cooling & Cleanup Sys Until Prior to First Off Loading of Spent Fuel + (ML20058L069)
- 05000425/LER-1990-010-02, :on 900702,observed That Unit 2 Process & Effluent Radiation Monitoring Sys Computer Screen Displayed Active Limiting Condition for Operation Against 2RE-2562C. Caused by Personnel Error.Personnel Counseled + (ML20058L070)
- ML20058L072 + (ML20058L072)
- ML20058L074 + (ML20058L074)
- ML20058L076 + (ML20058L076)
- ML20058L077 + (ML20058L077)
- ML20058L079 + (ML20058L079)
- ML20058L082 + (ML20058L082)
- ML20058L086 + (ML20058L086)
- ML20058L089 + (ML20058L089)
- 05000327/LER-1990-016-03, :on 900629,determined That Containment Purge Had Been Initiated on 900628 W/O Disabling Steam Generator Water Level Environ Allowance Modifier.Caused by Personnel Error.Limiting Condition for Operation Entered + (ML20058L090)
- BSEP-93-0185, Application for Amends to Licenses DPR-62 & DPR-71, Correcting TS Pages Issued for Amend 166 for Unit 1 & Amend 197 for Unit 2 Re Numac Steam Leak Detection Equipment + (ML20058L091)
- IR 05000602/1990004 + (ML20058L092)
- ML20058L096 + (ML20058L096)
- ML20058L099 + (ML20058L099)
- 05000482/LER-1993-014, :on 900501,essential Svc Water Low Flow Prior to Refueling Outage Occurred.Cause Unknown.Reportability Determination Process Revised,Rers Logged & Entered Into Tracking Database + (ML20058L103)
- ML20058L105 + (ML20058L105)
- ML20058L106 + (ML20058L106)
- ML20058L107 + (ML20058L107)
- ML20058L108 + (ML20058L108)
- ML20058L110 + (ML20058L110)
- ML20058L111 + (ML20058L111)
- ML20058L113 + (ML20058L113)
- ML20058L114 + (ML20058L114)
- ML20058L116 + (ML20058L116)
- ML20058L117 + (ML20058L117)
- ML20058L119 + (ML20058L119)
- 05000344/LER-1990-030, :on 900729,containment Ventilation Isolation Occurred Due to Electronic Signal Spike on Process Radiation Monitor 1B.Caused by Loose Connection Between High Voltage Cable & Connector Assembly.Connector Repaired + (ML20058L120)
- RBG-33300, Forwards Schedule for Submittal of Repts Re Reactor Physics Methods & Reactor Transient Analysis Methods Rept,Per 900712 Meeting + (ML20058L121)
- ML20058L122 + (ML20058L122)
- 05000414/LER-1990-010-03, :on 900619,control Room Received Loss of Containment Sample Flow Alarm from Radiation Monitors.Caused by Personnel Error & Lack of Clear Procedure Guidance. Personnel Counseled + (ML20058L123)
- ML20058L124 + (ML20058L124)
- 05000219/LER-1990-009, :on 900703,reactor Isolation Signal Inadvertently Initiated During Surveillance Test.Caused by Design Deficiency.Mods to Facilitate Testing Scheduled to Be Performed During Next Outage + (ML20058L125)