LER-1978-030, Forwards LER 78-030/03L-0 |
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| 1551978030R00 - NRC Website |
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CORSum8f8 r
Power
$\\
Company Nb An.;ust 7,1979 4
Mr Ja=es G Keppler, Director Region III US nuclear Re;;;ulatory C-ission 799 2:esevelt Ecad Glen Ellyn, IM * -nis 60137 ECCKE:' 50-153 - LICI:'SZ DFR-6 3IG ECCK FCp;T - LZ2 - RC76-030 On the obverse side is reportable cecurrence 78-03C. -"nis is sub=itted I
in accordance with Technical Specifiestica sectien c.9 2.b.2.
Dayid A Bixel (Sis.ed) r j
Javid A 31xel Nuclear Licensing Administrster i
j CC: Directer, Offi:e of nucles: Reacter 2egulation
~;irector, Offi:e of L spection a: ~~'~~~~'
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| 05000155/LER-1978-001, Forwards LER 78-001/03L-0 | Forwards LER 78-001/03L-0 | | | 05000155/LER-1978-001-03, /03L-0:on 780109,diesel Fire Pump Starting Time Exceeded Core Cooling Criteria.Caused by Cold Weather Conditions.Ventilation Louvers in Screen House Sealed to Reduce Heat Loss in Room.Item Added to Cold Weather Checks | /03L-0:on 780109,diesel Fire Pump Starting Time Exceeded Core Cooling Criteria.Caused by Cold Weather Conditions.Ventilation Louvers in Screen House Sealed to Reduce Heat Loss in Room.Item Added to Cold Weather Checks | | | 05000155/LER-1978-002-03, /03L-0:on 780119,during Monthly Specific Gravity Readings in Reactor Depressurization Sys Battery A,Cell 12 Read Lower than Tech Spec Limit.Caused by Loss of Electrolyte Through Sampling.Electrolyte Added | /03L-0:on 780119,during Monthly Specific Gravity Readings in Reactor Depressurization Sys Battery A,Cell 12 Read Lower than Tech Spec Limit.Caused by Loss of Electrolyte Through Sampling.Electrolyte Added | | | 05000155/LER-1978-002, Forwards LER 78-002/03L-0 | Forwards LER 78-002/03L-0 | | | 05000155/LER-1978-003, Forwards LER 78-003/01T-0 | Forwards LER 78-003/01T-0 | | | 05000155/LER-1978-003-01, /01T-0:on 780120,during Routine Leak Rate Testing of Containment Ventilation Isolation Valves,Supply Valve CV-4097 Leaked in Excess of Tech Specs.Caused by Valve Disc Out of Alignment & Misadjusted Disc Ring | /01T-0:on 780120,during Routine Leak Rate Testing of Containment Ventilation Isolation Valves,Supply Valve CV-4097 Leaked in Excess of Tech Specs.Caused by Valve Disc Out of Alignment & Misadjusted Disc Ring | | | 05000155/LER-1978-004-03, /03L-0:on 780202,emergency Diesel Generator Overall Response Time Exceeded Required Starting Time of 13.9-s.Cause Undetermined.Maint Personnel Continuing Observation of Starting Characteristics | /03L-0:on 780202,emergency Diesel Generator Overall Response Time Exceeded Required Starting Time of 13.9-s.Cause Undetermined.Maint Personnel Continuing Observation of Starting Characteristics | | | 05000155/LER-1978-005-03, /03L-0:on 780203,during Plant Startup,Proper Offgas Sample Monitor Flow Could Not Be Established Using Flow Control Valves in Sample Sys.Probably Caused by Inadequate Cleaning of Flow Instrument by Maint Personnel | /03L-0:on 780203,during Plant Startup,Proper Offgas Sample Monitor Flow Could Not Be Established Using Flow Control Valves in Sample Sys.Probably Caused by Inadequate Cleaning of Flow Instrument by Maint Personnel | | | 05000155/LER-1978-006-03, /03L-0:on 780208,following Abnormal Test Light Indication on Reactor Depressurization Sys Control Sys,One Loop of Sys Channel D Was Made Inoperable to Isolate Cause of Abnormal Indication.Cause Not Stated | /03L-0:on 780208,following Abnormal Test Light Indication on Reactor Depressurization Sys Control Sys,One Loop of Sys Channel D Was Made Inoperable to Isolate Cause of Abnormal Indication.Cause Not Stated | | | 05000155/LER-1978-007-03, /03L-0:on 780209,during Routine Test Operation of Emergency Diesel Generator,Unit Tripped on High Water Temp After 25 Minutes of Operation.Caused by Leakage of Cooling Water Pump Shaft Packing Causing Cooling Sys Suction Los | /03L-0:on 780209,during Routine Test Operation of Emergency Diesel Generator,Unit Tripped on High Water Temp After 25 Minutes of Operation.Caused by Leakage of Cooling Water Pump Shaft Packing Causing Cooling Sys Suction Loss | | | 05000155/LER-1978-008-01, /01T-0:on 780215,during Maint of Reactor Depressurization Sys Control Circuitry,Fire Pump Control Switches Inadvertently Placed in Inhibit Position Incorrectly.Control Switches Marked W/Instructions | /01T-0:on 780215,during Maint of Reactor Depressurization Sys Control Circuitry,Fire Pump Control Switches Inadvertently Placed in Inhibit Position Incorrectly.Control Switches Marked W/Instructions | | | 05000155/LER-1978-009-03, /03L-0:on 780215,following Abnormal Test Light Indication on Reactor Depressurization Sys Control Sys, Each of Four Depressurization Loops Was Made Inoperable to Isolate Cause of Indication.Cause Not Stated | /03L-0:on 780215,following Abnormal Test Light Indication on Reactor Depressurization Sys Control Sys, Each of Four Depressurization Loops Was Made Inoperable to Isolate Cause of Indication.Cause Not Stated | | | 05000155/LER-1978-010-01, /01T:on 780217,during Review of Electrical Equipment Required for Loca,Steam Drum Low Level Switches Deemed Inadequate for High Temp Environ.Caused by Reactor Protection Sys Not Being Evaluated | /01T:on 780217,during Review of Electrical Equipment Required for Loca,Steam Drum Low Level Switches Deemed Inadequate for High Temp Environ.Caused by Reactor Protection Sys Not Being Evaluated | | | 05000155/LER-1978-011-01, /01T-0:on 780217,during Equipment Review, Unqualified Scram Pilot Solenoid Valve NC-27B Was Found Installed in F2 Drive Scram Valve Sys.Pilot Solenoid Was de-energized & Exhaust Function Verified | /01T-0:on 780217,during Equipment Review, Unqualified Scram Pilot Solenoid Valve NC-27B Was Found Installed in F2 Drive Scram Valve Sys.Pilot Solenoid Was de-energized & Exhaust Function Verified | | | 05000155/LER-1978-012-01, /01T-0:on 780217,during Equipment Review,Pilot Solenoid Valve SV-879 Was Deemed Inadequate to Perform in Postulated Accident Environ.Pilot Solenoid Is de-energized & Will Be Mainted in Safe Condition Until Mods Completed | /01T-0:on 780217,during Equipment Review,Pilot Solenoid Valve SV-879 Was Deemed Inadequate to Perform in Postulated Accident Environ.Pilot Solenoid Is de-energized & Will Be Mainted in Safe Condition Until Mods Completed | | | 05000155/LER-1978-013-03, /03L-0:on 780309,following Abnormal Indication on Automatic Test Circuit for Reactor Depressurizing Sys, Channel D Actuation Cabinet Removed from Svc to Facilitate Trouble Shooting | /03L-0:on 780309,following Abnormal Indication on Automatic Test Circuit for Reactor Depressurizing Sys, Channel D Actuation Cabinet Removed from Svc to Facilitate Trouble Shooting | | | 05000155/LER-1978-014-03, /03L-0:on 780311,operator Observed Test Enable Light Indication on Actuation Channel a of Reactor Depressurization Sys.Caused by Defective Electronic Module in Sensor Channel D.Module Repair in Progress | /03L-0:on 780311,operator Observed Test Enable Light Indication on Actuation Channel a of Reactor Depressurization Sys.Caused by Defective Electronic Module in Sensor Channel D.Module Repair in Progress | | | 05000155/LER-1978-015, Forwards LER 78-015/03L-0 | Forwards LER 78-015/03L-0 | | | 05000155/LER-1978-015-32, /03L-0:on 780223,potentially Submerged Electrical Circuitry for Reactor Containment Water Level Indication Was Deemed Marginal by Evaluation.Caused by Original Const.Cable Splicing Retaped W/Waterproof Rubber Tape | /03L-0:on 780223,potentially Submerged Electrical Circuitry for Reactor Containment Water Level Indication Was Deemed Marginal by Evaluation.Caused by Original Const.Cable Splicing Retaped W/Waterproof Rubber Tape | | | 05000155/LER-1978-016-03, /03L-0:on 780320,daily Primary Leakage Exceeded Allowable Limit.Cause Not Stated.Excess Leakage Classified as Identified.Flange O Rings Will Be Replaced During Future Outage | /03L-0:on 780320,daily Primary Leakage Exceeded Allowable Limit.Cause Not Stated.Excess Leakage Classified as Identified.Flange O Rings Will Be Replaced During Future Outage | | | 05000155/LER-1978-017-03, /03L-0:on 780320,during Period of Reduced Power, Control Rod Drive F-2 Scram Pilot Valve Control Switch Was Reset from Tripped Position Contrary to Instructions.Cause Due to Vague Instructions.Procedures Under Review | /03L-0:on 780320,during Period of Reduced Power, Control Rod Drive F-2 Scram Pilot Valve Control Switch Was Reset from Tripped Position Contrary to Instructions.Cause Due to Vague Instructions.Procedures Under Review | | | 05000155/LER-1978-018-03, /03L-0:on 780406,one of Two Low Drum Scram Sensors in Each of Two Reactor Protection Channels Failed to Operate.Caused by Binding of Switch/Pointer Mechanism on Scale Plate Inside Cover.New Cover & Scale Plate Installed | /03L-0:on 780406,one of Two Low Drum Scram Sensors in Each of Two Reactor Protection Channels Failed to Operate.Caused by Binding of Switch/Pointer Mechanism on Scale Plate Inside Cover.New Cover & Scale Plate Installed | | | 05000155/LER-1978-019-03, /03L-0:on 780406,during Investigation of Anomalies Re Load Rejection & Scram from Reduced Condenser Vacuum, Switch PS652 Was Found Out of Tolerance.Caused by Minor Drift.Switch Recalib & Tested | /03L-0:on 780406,during Investigation of Anomalies Re Load Rejection & Scram from Reduced Condenser Vacuum, Switch PS652 Was Found Out of Tolerance.Caused by Minor Drift.Switch Recalib & Tested | | | 05000155/LER-1978-020-03, /03L-0:on 780411,during Power Operation,Off Gas Monitor Sample Flow Was Low & Radiation Monitoring Sys Deemed Inoperable.Caused by Foreign Deposits on Needle Valve Sample Flow Control.Valves Will Be Cleaned Regularly | /03L-0:on 780411,during Power Operation,Off Gas Monitor Sample Flow Was Low & Radiation Monitoring Sys Deemed Inoperable.Caused by Foreign Deposits on Needle Valve Sample Flow Control.Valves Will Be Cleaned Regularly | | | 05000155/LER-1978-021-03, /03L-0:on 780415,during Reactor Power Operation, Reduced Capacity Operation of 138 Kv Offsite Power Source Occured.Caused by Authorized Mods to Offsite Electrical Substation.No Corrective Action Required | /03L-0:on 780415,during Reactor Power Operation, Reduced Capacity Operation of 138 Kv Offsite Power Source Occured.Caused by Authorized Mods to Offsite Electrical Substation.No Corrective Action Required | | | 05000155/LER-1978-022-03, /03L-0:on 780417,138 Kv Line Was de-energized Due to Switching Error.Caused by Deficient Procedure.Switching Procedure Review Requirements Modified by Offsite Personnel | /03L-0:on 780417,138 Kv Line Was de-energized Due to Switching Error.Caused by Deficient Procedure.Switching Procedure Review Requirements Modified by Offsite Personnel | | | 05000155/LER-1978-023-03, /03L-0:on 780504,during Routine Weekly Checks of Fire Pump Diesel Starting Battery a Electrolyte Level Found Below Top of Plates in Cells 1,3 & 5 of Battery Unit 1.Cause Unknown.Battery Unit 2 Replaced on 780516 | /03L-0:on 780504,during Routine Weekly Checks of Fire Pump Diesel Starting Battery a Electrolyte Level Found Below Top of Plates in Cells 1,3 & 5 of Battery Unit 1.Cause Unknown.Battery Unit 2 Replaced on 780516 | | | 05000155/LER-1978-023, Forwards LER 78-023/03L-0 | Forwards LER 78-023/03L-0 | | | 05000155/LER-1978-025, Forwards LER 78-025/03L-0 | Forwards LER 78-025/03L-0 | | | 05000155/LER-1978-025-03, /03L-0:on 780525,electrolyte Level Found Below Top of Plates in Cells 1 & 6 of Diesel Fire Pump Battery Unit 1. Caused by Failure to Maintain Normal Electrolyte Levels. Personnel Instructed to Fill Opening Ring to Provide Ma | /03L-0:on 780525,electrolyte Level Found Below Top of Plates in Cells 1 & 6 of Diesel Fire Pump Battery Unit 1. Caused by Failure to Maintain Normal Electrolyte Levels. Personnel Instructed to Fill Opening Ring to Provide Margin | | | 05000155/LER-1978-026-03, /03L-0:on 780531,following Scram While Still in Power Operation,Condensate Storage Tank Dropped to 61% While Steam Drum Water Inventory Was Maintained by Manual Control. Caused by Personnel Oversight | /03L-0:on 780531,following Scram While Still in Power Operation,Condensate Storage Tank Dropped to 61% While Steam Drum Water Inventory Was Maintained by Manual Control. Caused by Personnel Oversight | | | 05000155/LER-1978-028-03, /03L-0:on 780605,emergency Condenser Outlet Valve MO-7053 Deemed Automatically Inoperable in Closed Position After Manual Tightening of Valve to Stop Leakage.Cause of Leakage Unknown & Will Be Investigated at Future Shutdown | /03L-0:on 780605,emergency Condenser Outlet Valve MO-7053 Deemed Automatically Inoperable in Closed Position After Manual Tightening of Valve to Stop Leakage.Cause of Leakage Unknown & Will Be Investigated at Future Shutdown | | | 05000155/LER-1978-029-03, /03L-0:on 780606,daily Unidentified Primary Sys Leakage Exceeded Allowable Limits.Caused by Drive Flange O Ring Seal Deterioration.Degradation Will Be Investigated & Repaired During Future Outage | /03L-0:on 780606,daily Unidentified Primary Sys Leakage Exceeded Allowable Limits.Caused by Drive Flange O Ring Seal Deterioration.Degradation Will Be Investigated & Repaired During Future Outage | | | 05000155/LER-1978-030-03, /03L-0:on 780712,channel B of Reactor Depressurization Sys Removed from Svc After Trouble Alarm When Battery for Loop Placed on Overcharge.Caused by Blown Fuse Due to Diode Failure in Annunciator Circuitry | /03L-0:on 780712,channel B of Reactor Depressurization Sys Removed from Svc After Trouble Alarm When Battery for Loop Placed on Overcharge.Caused by Blown Fuse Due to Diode Failure in Annunciator Circuitry | | | 05000155/LER-1978-030, Forwards LER 78-030/03L-0 | Forwards LER 78-030/03L-0 | | | 05000155/LER-1978-032-03, /03L-0 on 780819:Failure of Check Valve Providing Containment Integrity in 2 Demineralized Water Line Contributed to Containment of Plant Demineralized Water Sys Check Valve Repaired 780905 | /03L-0 on 780819:Failure of Check Valve Providing Containment Integrity in 2 Demineralized Water Line Contributed to Containment of Plant Demineralized Water Sys Check Valve Repaired 780905 | | | 05000155/LER-1978-032, Forwards LER 78-032/03L-0.W/o Encl | Forwards LER 78-032/03L-0.W/o Encl | | | 05000155/LER-1978-033, Forwards LER 78-033/03L-0 | Forwards LER 78-033/03L-0 | | | 05000155/LER-1978-033-03, /03L-0 on 780829:during Tests of Automatic Containment Isolation Valves,Valve CV/4027 Exhibited Excessive Leakage.Valve & Piping Flushed & Leakage Test Repeated Satisfactorily.(Encl to 7810060072) | /03L-0 on 780829:during Tests of Automatic Containment Isolation Valves,Valve CV/4027 Exhibited Excessive Leakage.Valve & Piping Flushed & Leakage Test Repeated Satisfactorily.(Encl to 7810060072) | | | 05000155/LER-1978-034-03, /03L-0 on 780831:during Monthly Specific Gravity Readings on Reactor Depressurization Sys,Battery A,Cell 12 Read 1.193 Below Limit of 1.200 Specified in Tech Specs. Cause Unknown & Cell Was Replaced.(Encl to 7810060072) | /03L-0 on 780831:during Monthly Specific Gravity Readings on Reactor Depressurization Sys,Battery A,Cell 12 Read 1.193 Below Limit of 1.200 Specified in Tech Specs. Cause Unknown & Cell Was Replaced.(Encl to 7810060072) | | | 05000155/LER-1978-035-01, /01L on 780904:During Test of Containment Ventilation Isolation Valves,Supply Valve CV/4097 Leaked in Excess of TS Criteria.Butterfly Valve Disc Seal Was Readjusted & Valved Returned to Svc. (Encl to 7809190156) | /01L on 780904:During Test of Containment Ventilation Isolation Valves,Supply Valve CV/4097 Leaked in Excess of TS Criteria.Butterfly Valve Disc Seal Was Readjusted & Valved Returned to Svc. (Encl to 7809190156) | | | 05000155/LER-1978-035, Forwards LER 78-035/01L & LER 78-037-01L on 780906 | Forwards LER 78-035/01L & LER 78-037-01L on 780906 | | | 05000155/LER-1978-044-01, /01X-1 on 781019:during Startup,Minor Leak Discovered at 3/4 Inch Vent Pipe Weld Attachment on 3 Inch Return Line from clean-up Sys to Reactor Recirculating Loop 2.Caused by Crack in Stainless Steel.Code Repairs Made | /01X-1 on 781019:during Startup,Minor Leak Discovered at 3/4 Inch Vent Pipe Weld Attachment on 3 Inch Return Line from clean-up Sys to Reactor Recirculating Loop 2.Caused by Crack in Stainless Steel.Code Repairs Made | | | 05000155/LER-1978-044, Forwards LER 78-044/01X-1 | Forwards LER 78-044/01X-1 | | | 05000155/LER-1978-047-03, During Plant Startup, Control Rod Drive Temp on Drive E-2 Exceeded Tech Specs. Caused by Failure of Metal O-Ring Seal at Flange.New Seal Ring Installed Prior to Plant Startup.All O-Rings Replaced | During Plant Startup, Control Rod Drive Temp on Drive E-2 Exceeded Tech Specs. Caused by Failure of Metal O-Ring Seal at Flange.New Seal Ring Installed Prior to Plant Startup.All O-Rings Replaced | | | 05000155/LER-1978-048, Forwards Updated LER 78-048/03X-1 | Forwards Updated LER 78-048/03X-1 | | | 05000155/LER-1978-048-03, During Power Operation, Noted Emergency Condenser Shell Side Temp Was 205 F.Temp Returned to Normal Levels When Inlet Valve in Loop 2 Closed. Caused by Improperly Fitted Gate Valve Disc | During Power Operation, Noted Emergency Condenser Shell Side Temp Was 205 F.Temp Returned to Normal Levels When Inlet Valve in Loop 2 Closed. Caused by Improperly Fitted Gate Valve Disc | |
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