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 Issue dateTitleTopic
ML19259B41331 January 1979Monthly Operating Rept for Jan 1979
ML19259B44131 December 1978Suppl Reload Licensing Submittal for Cooper Nuclear Station Unit 1,Reload 4.
ML19260D9844 February 1980Monthly Operating Rept for Jan 1980
ML19262C37921 January 1980Offsite Dose Assessment Manual for Assessment of Gaseous & Liquid EffluentsGrab sample
ML19262C38021 January 1980Proposed Process Control ProgramProcess Control Program
ML19263C91419 January 1979LER 78-040/03L-0 on 781227:during Normal Operation,While Doing Special Test of Drywell Purging Techniques,Primary Containment Vent Valve PC-246AV Leaked Excessively & Was Inoperable Due to Incomplete Valve Closure.Valve Replaced
ML19263C92322 January 1979LER 79-001/03L-0 on 790103:during Operation,Drywell Atmospheric Radiation Monitor Gas Channel (RMV-RM-4C) Failed Downscale.Caused by Detector Failure Caused by Moisture in Detector Chamber.Detector Replaced;Chamber & Lines Dried
ML19269D60725 May 1979Addl Info & Revision to 790109 QA Program for OperationNondestructive Examination
Backfit
ML19270G3306 June 1979Offsite Dose Assessment Manual.Grab sample
ML19270G3336 June 1979Radiological Environ Monitoring Manual.Annual Radiological Environmental Operating Report
ML19270G47823 May 1979LER 79-010/03L-0 on 790424:surface Linear Indication Found in Weld RA5-CF-13,main Steam to a & B RHR Heat Exchangers & HPCI Turbine.Caused by Welding Error.Defect Removed
ML19270G5514 June 1979Monthly Operating Rept for May 1979
ML19274F04218 May 1979LER 79-008/03L-0 on 790420:breaker 1FA Failed to Trip When Control Switch Operated to Trip.Caused by Failure of Auxiliary Switch Contact Mounted Inside Breaker 1FA to Make Proper Electrical Contact.Breaker Inspected & Cleaned
ML19274F04523 May 1979LER 79-011/03L-0 on 790424:reactor Water Cleanup MO-18 Contactor Failed to Close Manually During Cold Shutdown. Caused by Failure of Auxiliary Contact Mechanism.Repairs Completed Per IE Bulletin 78-05
ML19274F04822 May 1979LER 79-009/03L-0 on 790430:four Penetrations Found Leaking Excessively During Local Leak Rate Test.Caused by Defects in Limitorque Operator Torque Switch,Seal Rings & Check Valves. All Defects Repaired
ML19275A1421 August 1979LER 79-015/03X-1 on 790525:breaker 1AS Failed to Close Automatically After Reactor Scrammed.Caused by Improper Operations of Switch 52 in Breaker 1AN.Breaker 1FA Failed to Trip.Caused by Misaligned Trip Coil & Armature
ML19276H0223 August 1979LER 79-018/03L-0 on 790706:during Routine Testing,Reactor Vessel Level Indicating Switch NBI-LIS-58A Was Found W/Trip Point Less than Allowed.Caused by Sediments of Dust & Moisture in Auxiliary Switch
ML19276H5425 November 1979LER 79-028/03L-0:on 791008,during Insp of Cable Spreading Room,One 4-inch Pipe Sleeve Not Sealed.Caused by Inadequate Control of Fire Seals Installation During Microwave Communications Sys Installation.Sleeve Was Sealed
ML19283B6631 March 1979Annual Operating Rept for 1978.Hydrostatic
ML19289C39327 December 1978LER 78-037/03L-0 on 781201:during Normal Operation,Pressure Recorder PC-PR-512A Was Found Reading Full Scale & Declared Inoperable.Cause Was Isolated to a Bad Amplifier Circuit Board
ML19289C40315 December 1978LER 78-036/04T-0 on 781212:discharge of Floor Drain Sample Tank Was Made W/O Effluent Monitoring Required by Tech Specs,Because Flushing Valve of Radwaste Effluent Monitor Was Inadvertently Left Open
ML19289D7606 March 1979Monthly Operating Rept for Feb 1979
ML19290F04113 February 1980LER 80-005-031-0:on 800116,during Normal Operation,Two through-wall Cracks in Welds in Radiant Energy Conversion North Critical Loop Discovered.Caused by Intergranular Stress Corrosion.Welds Will Be Replaced
ML19291B9347 December 1979Monthly Operating Rept for Nov 1979
ML19294B4476 February 1980LER 80-003/03L-0:on 800111,during Valve Realignment Per Special Procedure 80-1,PC-230MV Was Not Closing Completely. Caused by Improper Assembly of Gear Limit Switch in Limitorque Model SMB00 Operator
ML19294B45921 January 1980LER 80-002/03L-0:on 800103,operator Found Valve Stem on HPCI Stop Valve Broken Separating Valve from Operator.Caused by Valve Stem Being Overstressed During Process of Freeing Stop Valve Piston on 790912.Valve Reassembled
ML19294B4778 February 1980LER 80-004/03L-0:on 800115,during Normal Operation, Discovered That RHR Valve M018 Was Inoperable.Caused by Failure of GE Relay Coil,Blowing Valve Control Circuit Fuse. Relay Coil Was Replaced & Correct Operation Verified
ML19295D80331 October 1980Master List of Class IE Equipment.Boric Acid
ML19296B33731 December 1979Supplemental Reload Licensing Submittal for Reload 5.Shutdown Margin
Feedwater Controller Failure
ML19296D37231 December 1979Annual Operating Rept 1979.Hydrostatic
ML19305E82528 April 1980LER 80-009/03L-0:on 800329,during Refueling outage,through- Wall Crack Discovered on Upstream Side of Isolation Valve to REC Noncritical Header.Cracked Weld Characteristic of Intergranular Stress Corrosion.Weld Will Be Repaired
ML19309C8263 April 1980Monthly Operating Rept for Mar 1980
ML19309F18125 March 1980LER 80-007/03L-0:on 800310,during Surveillance Testing of Standby Liquid Control Pumps,Standby Liquid Control Pump 1B Would Pump Only 36.5 Gpm at 1,215 Psig.Caused by Wear & Pitting to Seating Surface
ML19309G06910 April 1980LER 80-008/03L-0:on 800312,during Insp of Reactor Core Isolation Cooling Turbine,Two Buckets on Turbine Wheel Were Discovered Damaged.Caused by Foreign Object Striking Wheel During Operation.Investigation Is Continuing
ML19309G07920 March 1980LER 80-006/03L-0:on 800222,during Normal Operation,While Hydrotesting Reactor Bldg Fire Sprinkler Sys,Gasket in Flow Switch in Water Line Failed & Water Sprayed Into 125 Volt Dc Starter Racks for Reactor Core Isolation Cooling & RHR
ML19309H2271 May 1980Monthly Operating Rept for Apr 1980
ML19312A2042 August 1979LER 79-005/03X-1 on 790216:reactor Recirculation Motor Generator Set a Tripped During Normal Operation.Caused by Failure of Level Switch NBI-LIS-58A Due to Corrosion. Corrosion Cleaned from Inside Switch Case & Switch Replaced
ML19320A94312 June 1980LER 80-012/03L-0:on 800521,during Local Leak Rate Test,Nine Penetrations Found Leaking Excessively.Caused by Normal Wear.Seal Ring Replaced,Seats Polished,Packing Tightened & Ring Seal Cleaned
ML19320A96216 June 1980LER 80-014/03L-0:on 800518,while Performing Sp 6.3.13.1, Relay 14A-K2B Was Found de-energized,preventing Start of Core Spray Pump on Normal Power.Superflous Contacts Were Inadvertently Left Connected in Core Spray Pump Circuits
ML19320A9731 July 1980Monthly Operating Rept for June 1980
ML19320A99413 June 1980LER 80-013/03L-0:on 800516,during Surveillance Procedure on Primary Containment Isolation Valve Timing,Rhr Discharge to Radwaste Inboard Isolation Failed to Close in Time.Caused by Failure to Check Stroke Time After MaintStroke time
ML19320C05414 July 1980LER 79-031 Has Been Cancelled
ML19321B0591 July 1980Corrected Monthly Operating Rept for June 1980
ML19321B1932 July 1980LER 80-015/03L-0:on 800606,during Control Rod Scramtime testing,full-in Control Rods Incorrectly Scrammed & Fully Withdrawn.Caused by Personnel Error.Rod Returned to Correct Position.Procedure Modified
ML19323F1198 May 1980LER 80-010/03L-0:on 800408,subsurface Planar Flax in Weld CSB-BF-12 Core Spray B Loop Found During Augmented Inservice Insp.Caused by Const Defect.Defect Removed,Repaired & Successfully Volumetrically Examined Per ASME Code
ML19323F22412 May 1980LER 80-011/03L-0:on 800418,check Valves Upstream of Accumulators Had Excessive Back Leakage.Caused by BUNA-N Seat Embrittlement Due to Age.Check Valve Seats Replaced W/Ethylene Propylene Matl.Valves Bench Tested
ML19323G9612 June 1980Monthly Operating Rept for May 1980
ML19324C1132 November 1989Part 21 Rept Re Defects in Instrument Racks for Use in Hatch,Inc Supplied Emergency Diesel Generator Starting Air & Lube Oil Sys.Verification of All Tube Fittings in Instrument Rack Completed & All Discrepant Fittings Corrected
ML19325C91730 September 1989Monthly Operating Rept for Sept 1989 for Cooper Nuclear Station.W/891010 Ltr
ML19325E22027 October 1989LER 89-025-00:on 890928,main Turbine Trip Occurred,Followed Immediately by Reactor Scram.Caused by Spurious Actuation of Level Switch Due to Equipment Vibration.Plant Stabilized & Temporary Instruction Re Pump Shifting issued.W/891027 LtrReactor Vessel Water Level
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