05000313/LER-1983-023, Updated LER 83-023/03X-6:on 830916-1120,fire Protection Deficiencies Discovered.Caused by Inadequate Original Installation Specs & Acceptance Criteria.Walkdown Insp in Progress.Insp Program Being Developed
05000285/LER-1988-020, :on 880903,diesel Oil Storage Tank 7 Day Run Capacity Requirement Exceeded.Review of Design Basis Determined Amount of Diesel Fuel Required.Revised Emergency Planning Procedure to Provide Guidance
05000482/LER-1986-051, :on 860925,spent Fuel Pool Crane Overload Limit Found Improperly Adjusted from 860923-25,while Fuel Moved in & Around Spent Fuel Storage Facility,In Violation of Tech Spec 3.9.7.Caused by Personnel Error
05000440/LER-1986-026, :on 860618,containment Isolation Valves Closed. Caused by Technician Inadvertently Grounding Power Lead During pre-operational Test.Technician Counseled.Testing Instructions to Include Caution Note
05000259/LER-1985-026, :on 850701,field Insp Determined Cable Tray Sections Not Seismically Qualified.Caused by Tray Overfill Condition.Potential Application of Alternate Seismic Approaches Re USI A-46 Considered
05000336/LER-1997-019-02, :on 970422,automatic Test Initiator Sends Repeated Trip Signals to RSST Feeder Breaker Timing Circuit. Caused by Unexpected Interaction Between Unrelated Signals. Noise Interaction Will Be Isolated & Corrected
05000323/LER-1985-018-02, :on 851202,spurious Safety Injection Occurred After Initiation of Manual Reactor Trip in Response to Digital Rod Position Indication Sys Data a Failure.Exact Cause Under Investigation
05000482/LER-1996-005, :on 960314,TS 3.9.4 Violation Occurred Due to Personnel Error.Counseled Involved Personnel,Informed Operation Personnel of Misinterpretation & Revised Affected Procedures
05000275/LER-1985-014, :on 850518,reactor Tripped Followed by Safety Injection.Caused by Failure of Slave 2.S Kva Regulating Transformer.Transformer Replaced & Inverter Returned to Svc
05000213/LER-1985-010, :on 840824,during Surveillance Testing,Both Motor Operated Svc Water Outlet Isolation Valves Failed to Operate When Energized.Caused by Inadequate Maint Records. Motor Operators Repaired & Retested
05000324/LER-1991-020-02, :on 911214,HPCI Turbine Steam Supply Valve E41-F001 Would Not Open from Control Room During Second Overspeed Trip Test Due to Loose Limit Switch Assembly.Valve Limit Switch Assembly Tightened & Adjusted
05000336/LER-1994-015-01, :on 940519,revealed Automatic Auxiliary Feedwater Initiation Control Circuit Does Not Meet Single Failure Criterion Due to Inadequate Interface of Design & Equipment Condition.Design Change Evaluated
05000413/LER-1994-007, :on 940608,operations Discovered Past Due Rept Surveillance Interval Exceeded for TS Surveillance 4.7.6.b for Train A.Caused by Inadequate Verbal Communication.Lead Personnel Instructed to Closely Monitor Test
05000366/LER-1982-077-03, /03L-0:on 820730,standby Liquid Control Tank Vol Found Below Required Limits.Caused by Personnel Error Plus Evaporation Due to Ambient Conditions & Excessive Air Sparging.Water Added to Tank
05000324/LER-1982-054-03, /03L-0:on 820314,reactor Low Level Switch 2-B21-LIS-NO17D-1 Actuated at Level Below Reportable Limit. Caused by Instrument Drift.Switch Recalibr & Returned to Svc
05000324/LER-1982-040-03, /03L-0:on 820217,routine Surveillance Revealed Drywell Floor Drain Flow integrator,2-G16-FQ-K601,was Continuously Counting W/No Pump Running.Cause Not Found. Mod to Vortex Type Flowmeter Will Be Installed
05000324/LER-1981-102-03, /03L-0:on 810930,fire Hose Station SW-1,located on 4-ft Level of Svc Water Bldg Was Inoperable,Preventing Unreeling of Hose Line.Type S-A-F-1 Reel Bent When Hose Station Isolation Valve Was Opened.Reel Replaced
05000416/LER-1982-093-03, /03L-0:on 820929,routine Surveillance Procedure 06-OP-1T42-Q-0001 Revealed Fuel Handling Area Vent Supply Isolation Damper Failed to Cycle Closed in Less than 5-s. Caused by Cup Seal Being Stretched Oversize.Seal Repaired
05000318/LER-1981-036-03, /03L-0:on 810804,during Normal Operation,Reactor Protection Sys Channel B Hi Power,Thermal Margin/Low Pressure & Axial Shape Index Units Were Bypassed.Caused by Nuclear Instrumentation Power Spikes Causing Spurious Trips
05000266/LER-1979-019-01, /01T-0:on 791107,while Filling Steam Generator a Secondary Side W/Water to Perform secondary-to-primary Leak Test,Dilution of RCS Occured.Caused by Leakage from Open Steam Generator Tube Falling Into Primary Outlet Nozzle
05000270/LER-2006-001, Re Loss of Isolation During Pump Instrument Check Results in Reactor Trip