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 Issue dateTitleTopic
ML20042E64318 April 1990Special Rept:On 900305,east Cable Vault Exhaust Damper VS-D-180 Failed to Close During Trip Testing of Fire Dampers Under Air Flow Conditions.Caused by Inadequate Spring Closure Mechanism.Springs Replaced W/Helical Coil Springs
ML19324C2948 November 1989Special Rept:On 891026,inservice Insp of Tubing in Steam Generators Completed.Degradation Mechanisms of Steam Generator Tubing Falls In,Cold Leg Support Plate Thinning & Hot Leg Support Plate DamageBoric Acid
ML18041A19024 April 1989Special Rept:On 890414,triaxial Time History Accelerometer Horizontal Trigger Circuits Identified as Inoperable. Caused by Incorrect Calibr Procedure.Surveillance Procedure Immediately Revised to Reflect Correct Setpoint Values
ML20042B44915 March 1982ROs 82-007/01P & 82-008/01P:during Update of Analysis Required by IE Bulletin 79-14,overstress Condition Found on a Steam Generator Steamline.Condition Analyzed in FSAR & Addressed Through Emergency Procedures
ML20004F7408 June 1981RO 81-047/01P:on 810606,during Normal Plant Tour,Primary Auxiliary Bldg Operator Found High Head Safety Injection Pump Emergency Cooling Water Supply Valve Unlocked & Closed. New Chain & Lock Installed
ML20004C48129 May 1981Ro:On 810527-29,during Routine Review of Surveillance Records,Discovered That Sample of Gaseous Waste Discharge Path Not Taken on 810528 as Required When Radiation Monitor Was Out of Svc.Required Samples Taken on 810527-29
ML20049A5874 May 1981RO 81-32/01P:on 810502,feedwater Vibrations on a Steam Generator Feed Line Damaged Snubbers,Shims & Shim Retainer of Vertical Energy Constraint.Cause Under Investigation. Steam Release Calculations Will Be Refined
ML19350C74126 March 1981RO 81-029:on 810312,discrepancy Noted Between Plant Mod Manual & Tech Specs During Review of Inservice Insp Requirements for Mods Recently Completed on 0.75 & 1-inch Branch Connection on RCS & Safety Injection SysHydrostatic
ML19345B80024 November 1980RO 80-086/01P:on 801121,Tech Specs 6.9.1.8.i Analysis of Structures Has Less Conservatism than Originally Calculated. Overstress Condition Exists on Seal Injection Header from Discharge of High Head Safety Injection Pumps
ML20049A33517 November 1980RO 80-078/01P:on 801114 It Was Discovered That Code Safety Valves Challenged W/Water Loop Seal on Inlets Would Result in Overstress of Pressurizer Safety & Power Operated Relief Valve Piping.Drainage of Seals Would Prevent ConditionLoop seal
ML19347B6738 October 1980RO:80-075/01P:on 801008,analysis Revealed Overstress Condition Existed at Pipe Support H-43 on Reactor Coolant Fill Header from High Head Charging Pumps.Cause Not Determined.Mod Will Be Completed Prior to Plant StartupDesign basis earthquake
ML19338E84429 September 1980RO 80-071/01P:on 800926,during Surveillance Test to Verify Equipment Operating Times,Control Room Isolation Times Determined Not in Accordance W/Tech Specs.Caused by Tech Spec Error in Specified Response Time
ML19338F12929 September 1980RO 80-071/01P-0:on 800925,during Surveillance Test to Verify Equipment Operating Times,Control Room Isolation Times Determined Contrary to Tech Spec.Caused by Tech Spec Error in Required Time Determination
ML19338F02626 September 1980Ro:On 800925,diesel-driven Fire Pump Auto Started.Caused by Hole in Section of Pipe from Back Hoe Operator Digging Up Portion of Fire Main Yard Loop.Leak Isolated & Backup Water Made Available.Pipe Section Repaired
ML19347A85323 September 1980RO 80-070/01P:on 800922,born Dilution Discovered During RCS Initial Fill & Vent,Causing Unplanned Reactivity Insertion to Exceed Tech Specs Limits.Caused by Procedural Deficiency.Boric Acid Blender Total Flow Setpoint ChangedBoric Acid
Shutdown Margin
ML19347B10122 September 1980RO 80-069/01P-0:on 800920,motor Driven Fire Pump Began Smoking & Leaking Oil After Surveillance Test.Investigation Showed Cooling Water Lost from Upper Bearing Cooler.Cause Undetermined.Temporary back-up Pumps Available
ML19338D11915 September 1980Ro:Evaluation & Analysis Required by IE Bulletin 79-14 Revealed Piping & Supports Have Less Conservatism During Seismic Events.Mods Will Be Made Prior to StartupDesign basis earthquake
Earthquake
ML19344F5348 September 1980Ro:Evaluation & Reanalysis Required by IE Bulletin 79-14 Revealed That Certain Piping & Supports Have Less Conservatism than Assumed for Safety Analysis.Cause Unstated.Pipe Support Will Be Added Prior to Startup
ML19330B42428 July 1980RO 80-052/01P:on 800726,diesel Fire Pump auto-started Below Rated RPM & Pressure.No Specific Cause Found.Fuel Oil Filter Changed & Pump Tested Successfully
ML19318D07330 June 1980RO 80-044/01T:design for Steam Generator Snubber Embedment Found Not to Reflect as-constructed Condition, Resulting in Nonconservative Loads for Anchors.Caused by Assumption That Load Was Applied to Normal Surface
ML19318B33620 June 1980RO 80-037/01T:during Review of Radiographs of Reactor Containment Liner Seam Welds,Portion of One Weld Is Code Rejectable.Authenticity of Other Seam Weld Radiographs Questionable.Investigation Continuing
ML19323H6729 June 1980Ro:On 800529,meteorological Instrumentatiion Computer Channels Found Not Responding Properly to Automatic Calibr Signals.Caused by Output Resistors Not Being Removed During 800515 Move.Resistors Removed & Sys Calibr VerifiedMet Tower
ML19323F15021 May 1980RO 80-031/01T:on 800521,while Energizing RHR motor-operated Isolation Valves,Suction Valve Closed.Caused by False High Pressure Signal Input Due to de-energized Instrument Loop. RHR Pump Shut Down.Sys Isolated for Repairs
ML19323F15420 May 1980RO-80-030/01T:on 800519,during Test of Diesel Driven Fire Pump High Temp Alarm Occured.Cause Unknown.Temporary Fire Pump Hooked Up.Investigation Underway
ML19309E78216 April 1980RO 80-025/01T:during Tank Mod Project,Field Engineers Reported That Weld on 12-inch Nozzle Penetrations to Refueling Water Storage Tank Does Not Conform W/Manufacturer Design.Addl Penetrations Are Being Checked
ML19323A09611 April 1980RO 80-023/01T:during Operational Mode 5,w/steam Generators & RCS Level at mid-span in Loops,Complete Loss of RHR Flow Occurred While Plant Operators Were Increasing Heat Exchanger Flow.Procedure Rewritten
ML19305D2858 April 1980RO 80-22/01T:on 800407,during Operational Mode 5,complete Loss of RHR Flow Occurred During Attempt to Increase Flow. Operating Procedure Changed to Require Venting RHR During Flow Increase
ML19309D7513 April 1980Ro:On 800225,two Frequencies on Peak Shock Annunciator Sys Actuated Visual Alarms.Cause Unknown.Problem w/70% (OBE) Visual Alarms May Have Been Caused by Reed Switches or Alarm Circuitry.Investigation Is ContinuingEarthquake
ML19305A97112 March 1980RO 80-12/01T:on 800312,during Operations Audit,Tech Spec Surveillance 4.3.3.5 Found to Be Violated.Required Channel Check Not Performed Since Jul 1976.Requirement Deleted Due to Meter Reading of Zero During Normal Operation
ML19344D3075 March 1980Ro:On 800226,fire Pump Removed from Svc Due to Suspicion of Water in Pump Oil.Cause Unstated.Oil Cooler Checked & Hydroed Satisfactorily.Motor Bearing Will Be Replaced & Returned to Svc
ML19296D16525 February 1980RO 80-08/01T:on 800225,during Cable Tray & Conduit as-built Configuration Review,Preliminary Framing Beam Analysis Indicated Potential Floor Beam Overstress.Caused by Conduit & Tray Support Horizontal AccelerationEarthquake
ML19305A76422 February 1980RO 80-7/01P:on 800221,condition Found Resulting in No Supplementary Leak Collection & Release Flow Through Main Filter Banks During Fuel Movement.Caused by Procedure Inadequacy.Procedures Revised
ML19257C63724 January 1980RO-80-3/01P:on 800124,analysis Showed That,During Postulated Seismic Event,Pipe Support H-95 on Component Cooling Water Sys Line CC-323 Would Receive Overstress.Support H-95 Will Be Altered to 3-way Restraint
ML19291C26717 January 1980LER 80-02/01T:on 800117,while in Operational Mode 5,received Indication of Low Residual Heat Removal Sys Flow When Low Flow Alarm Was Annunciated & Low Pump Amps Noted.Caused by Steam Generator Burp.Air Eductor Installed
ML19291C25711 January 1980Suppl to 790718 RO Re Fire Main Sys Rupture.Problem at Facility Not Considered Generic.Piping Was Probably Struck Sharp Blow During Const or Installation of Nearby Conduit Which Contributed to Failure
ML19210E40528 November 1979RO 79-46/01P:on 791127 Flowpath to Charging Pumps Closed Due to Planned Removal of Emergency Diesel Generator.High Head Injection Would Have Not Been Available If Needed.Error Corrected When Valve Opened to Increase Flow Path to Pumps
ML19254F92313 November 1979LER 79-47/01P:on 791110,review of Plant Operator Logs & History of Containment Vacuum Pumps Suggested Air Leak Into Containment.Caused by Particulate Monitor Leak.Leak Repaired.Monitor Returned to SvcGrab sample
ML19210C1145 November 1979RO 79-49/01P:on 791105,during Routine Review of Operations, Samples of Containment Atmosphere Gaseous Monitor Could Not Be Taken.Activity Levels Could Still Be Monitored.Addl Info in Followup Rept
ML19256A14727 October 1978RO 78-053/01P:on 781026 During Review of Stresscalculations for Safety Injection Piping Inside Containment,Errors in Piping Stress Analysis Were Discovered.Caused by Error in Hand Calculating Method