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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20045A694 | 4 June 1993 | LER 93-003-00:on 930511,turbine Emergency Trip Oil Header Pressure Low Alert Received Followed by Reactor Trip & Turbine Trip Above P-8.Caused by Actuation of Overspeed Trip Relay.Faulty Power Supply Board replaced.W/930604 Ltr | |
| ML20024H204 | 22 May 1991 | LER 91-005-01:on 900817,preoutage Mod Work Initiated W/O Proper Operability Review Due to Programmatic Deficiencies. Daily Const Work Authorization Sheet formalized.W/910522 Ltr | Scaffolding |
| ML20029A646 | 20 February 1991 | LER 90-007-01:on 900612,main Steam Line Isolation Sys Declared Inoperable Due to Failure to Test Manual Initiation Handswitch.Caused by Deficiency in Procedure.Procedures reviewed.W/910219 Ltr | |
| ML18041A225 | 3 October 1990 | LER 90-006-00:on 900903,reactor Containment Fan Cooler 2C, Low Speed Fan Breaker Did Not Close,Resulting in Train a Safety Injection Signal.Caused by Miscommunication & Procedure Deficiency.Procedure revised.W/901003 Ltr | |
| ML20029A690 | 13 September 1990 | LER 90-011-01:on 900819,reactor Trip Occurred Due to Power Surge.Caused by Lightning Strike.Rod Drive Sys Will Be Modified W/New Model of Power Supply Less Likely to Cause Reactor trip.W/910221 Ltr | |
| ML20044B099 | 12 July 1990 | LER 90-007-00:on 900612,discovered That Steam Line Isolation Handswitch on Main Control Board Panel 1PM06J Not Tested During Past Refueling Outages.Caused by Deficient Procedure. All Similar Equipment Will Be reviewed.W/900712 Ltr | |
| ML20044A987 | 11 July 1990 | LER 89-005-01:on 890501,diesel Generator 1A Failed to Load to 5,500 Kw within 60 as Required.Caused by Max Fuel Setting on Fuel Control Sys Being Set Too Low.Vendor Instructions Added to Maint procedures.W/900629 Ltr | |
| ML20043D584 | 1 June 1990 | LER 90-006-00:on 900503,as Surveillance Underway All Indication on Digital electro-hydraulic Computer Panel Was Lost.Caused by Failure of Ampere Fuse Due to Short Circuit in Pushbutton.Lighting Circuit rewired.W/900530 Ltr | |
| ML20042G912 | 8 May 1990 | LER 87-012-01:on 870408,component Cooling Pump 1A Tripped When Surge Tank Level Dropped to Low Level Pump Trip Setpoint.Caused by Breakdown in Communication.Mod to Component Cooling Sys completed.W/900507 Ltr | |
| ML20042E156 | 6 April 1990 | LER 90-003-00:on 900307,individual Cell Voltage for Cell 53 Found to Be at 2.11 Volts,Contrary to Tech Spec Limit.Caused by Electrician Using Improper Acceptance Criteria Format & Inadequate Mgt Review of surveillance.W/900406 Ltr | |
| ML20006F716 | 16 February 1990 | LER 90-001-00:on 900118,determined That Containment Purge Isolation Sys Not Demonstrated Operable 100 H Prior to Start of Core Alterations.Caused by Cognitive Personnel Error. Task Force Formed to Review Tech Specs.W/900109 Ltr | Reactor Vessel Water Level Grace period |
| ML20006E116 | 9 February 1990 | LER 90-001-00:on 900118,during Functional Surveillance on Steam Generator Pressure Channel 526,channel 525 Spiked Low, Causing Reactor Trip & Safety Injection.Caused by Failure of Pressure Transmitter.Transmitter replaced.W/900126 Ltr | |
| ML20006D740 | 5 February 1990 | LER 87-004-01:on 870225,inadvertent Safety Injection Occurred During Maint Troubleshooting.Caused by Cognitive Personnel Error by Control Sys Technician Involved. Disciplinary Action Taken & Counseling done.W/900124 Ltr | |
| ML20005E239 | 26 December 1989 | LER 89-003-01:on 890227,area Radiation Monitor 2RT-AR012 Failed Automatic Checksource Test,Actuating Containment Ventilation Isolation Alarm.Caused by Faulty Detector. Detector Replaced & Monitor Returned to svc.W/891221 Ltr | |
| ML19327B902 | 3 November 1989 | LER 89-009-00:on 891005,conflicting Info Re Signals That Initiate Automatic Isolation of Steam Generator Blowdown Lines Found.Caused by Preservice Design Implementation Deficiency.Lines Isolated & Procedure changed.W/891103 Ltr | High Energy Line Break |
| ML19354D468 | 1 November 1989 | LER 89-008-01:on 890830,one Auxiliary Feedwater Suction Pressure Transmitter Calibr Not Head Corrected & Bases of Original Setpoints Not Questioned.Caused by Inadequate Procedures & Setpoint calculations.W/891101 Ltr |