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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARU-603232, Special Rept:On 990531 Lpms Was Declared Inoperable Due to Receipt of High Vibration & Loose Parts Alarm Which Did Not Clear.Lpms Was Restored to Operable Status on 990707 After Alignment & Tension on Recorder Tape Drive Was Adjusted1999-07-0909 July 1999 Special Rept:On 990531 Lpms Was Declared Inoperable Due to Receipt of High Vibration & Loose Parts Alarm Which Did Not Clear.Lpms Was Restored to Operable Status on 990707 After Alignment & Tension on Recorder Tape Drive Was Adjusted U-603101, Special Rept:On 980918,discovered That Triaxial Seismic Accelerometers Had Not Been Properly Calibrated.Caused by Inadequate Calibration Procedure.Calibration to Be Performed off-site1998-10-28028 October 1998 Special Rept:On 980918,discovered That Triaxial Seismic Accelerometers Had Not Been Properly Calibrated.Caused by Inadequate Calibration Procedure.Calibration to Be Performed off-site U-603014, Special Rept:On 980512,lightning Struck Primary Meteorological Monitoring Instrumentation Tower Damaging 60- Meter Wind Speed & Associated Transmuter Circuit Card. Surveillance Testing Performed1998-05-28028 May 1998 Special Rept:On 980512,lightning Struck Primary Meteorological Monitoring Instrumentation Tower Damaging 60- Meter Wind Speed & Associated Transmuter Circuit Card. Surveillance Testing Performed U-602940, Ro:On 980213,alert Emergency Classification Was Declared IAW EPIP EC-02, Emergency Classifications. Caused by Tripped Inverter.Rhr a Was Restored at Approx 0945 H & Emergency Terminated at 1004 H Per EPIP EC-04, Alert1998-02-20020 February 1998 Ro:On 980213,alert Emergency Classification Was Declared IAW EPIP EC-02, Emergency Classifications. Caused by Tripped Inverter.Rhr a Was Restored at Approx 0945 H & Emergency Terminated at 1004 H Per EPIP EC-04, Alert U-602921, Special Rept:On 980113,operations Personnel Declared Meteorological Tower Wind Direction Instrumentation Inoperable.Consistent Difference Suspected to Have Been Caused by Rotation of Either or Both of Wind Sensor1998-01-29029 January 1998 Special Rept:On 980113,operations Personnel Declared Meteorological Tower Wind Direction Instrumentation Inoperable.Consistent Difference Suspected to Have Been Caused by Rotation of Either or Both of Wind Sensor U-602599, Special Rept:On 960516,Loose Parts Monitoring System Declared Inoperable.Caused by Intermittent Alarms.Removed Temporary Mod & Restored Alarm Feature for Channel Three1996-06-21021 June 1996 Special Rept:On 960516,Loose Parts Monitoring System Declared Inoperable.Caused by Intermittent Alarms.Removed Temporary Mod & Restored Alarm Feature for Channel Three U-602534, Special Rept:On 951206,determined Facility May Have Been Operated Above Max Power Level Authorized by License Due to Error in Reactor Heat Balance.Util Will Bias CRD Sys Flow Process Computer Point1996-01-0303 January 1996 Special Rept:On 951206,determined Facility May Have Been Operated Above Max Power Level Authorized by License Due to Error in Reactor Heat Balance.Util Will Bias CRD Sys Flow Process Computer Point U-602527, Special Rept:On 951103,reactor Water Cleanup Sys Flow Rate Computer Valve Substituted W/Value of Zero & Sys Actually Operating.Caused by Lack of Attention.Shift Technical Advisor Immediately Restored Computer1995-12-0505 December 1995 Special Rept:On 951103,reactor Water Cleanup Sys Flow Rate Computer Valve Substituted W/Value of Zero & Sys Actually Operating.Caused by Lack of Attention.Shift Technical Advisor Immediately Restored Computer U-602426, Ro:On 950301,plant Was Operating at Approx 75% Fire Was Reported in a turbine-driven Reactor Feed Pump Room1995-03-0303 March 1995 Ro:On 950301,plant Was Operating at Approx 75% Fire Was Reported in a turbine-driven Reactor Feed Pump Room U-602421, Ro:On 950216,Div 2 125 Volt Dc Electrical Power Sys Declared Inoperable.Caused by Failure of Silicon Controlled Rectifier Firing Board in Div 2 Battery Charger.Battery Charger Repaired1995-02-22022 February 1995 Ro:On 950216,Div 2 125 Volt Dc Electrical Power Sys Declared Inoperable.Caused by Failure of Silicon Controlled Rectifier Firing Board in Div 2 Battery Charger.Battery Charger Repaired U-602348, Special Rept:On 940906,CPS Declared Loose Parts Monitoring Sys Out of Svc.Caused by False Alarms.Util Will Recalibrate Channel Six1994-10-10010 October 1994 Special Rept:On 940906,CPS Declared Loose Parts Monitoring Sys Out of Svc.Caused by False Alarms.Util Will Recalibrate Channel Six U-602311, Special Rept:On 940624,inoperabilities of Meteorological Monitoring Instrumentation Channels for More than 7 Days Identified.Personnel Worked Expeditiously to Return Meteorological Instrumentation to Operable Status1994-07-12012 July 1994 Special Rept:On 940624,inoperabilities of Meteorological Monitoring Instrumentation Channels for More than 7 Days Identified.Personnel Worked Expeditiously to Return Meteorological Instrumentation to Operable Status U-602308, Special Rept:On 940607,determined Valid Failure of Div 1 EDG Had Occurred Due to Excessive Current.Replaced Failed Relay1994-07-0707 July 1994 Special Rept:On 940607,determined Valid Failure of Div 1 EDG Had Occurred Due to Excessive Current.Replaced Failed Relay U-602193, Special Rept:On 930927,valid Failure of Div II DG Occurred During Surveillance Testing.Caused by Insufficient Contact Pressure Between Contacting Surfaces.Contact Pressure Checks to Improve Component Reliability Implemented1993-10-12012 October 1993 Special Rept:On 930927,valid Failure of Div II DG Occurred During Surveillance Testing.Caused by Insufficient Contact Pressure Between Contacting Surfaces.Contact Pressure Checks to Improve Component Reliability Implemented U-602189, Follow-up Special Rept on Progress of Investigation Into Diesel I DG Test Failures That Occurred on 930623,0721 & 0803.Current Number of Valid Failures in Last 100 Valid Tests of DG1A Is Seven.Testing for DG1A Conducted1993-09-24024 September 1993 Follow-up Special Rept on Progress of Investigation Into Diesel I DG Test Failures That Occurred on 930623,0721 & 0803.Current Number of Valid Failures in Last 100 Valid Tests of DG1A Is Seven.Testing for DG1A Conducted U-602181, Special Rept:On 930812-30,differential Air Temp Instrumentation Inoperable.Caused by Problem W/Power Supply Panel 0EM01J.Replacement Power Supply Unavailable. Engineering Change Request ECN 28103 Processed1993-08-30030 August 1993 Special Rept:On 930812-30,differential Air Temp Instrumentation Inoperable.Caused by Problem W/Power Supply Panel 0EM01J.Replacement Power Supply Unavailable. Engineering Change Request ECN 28103 Processed U-602174, Special Rept:On 930721 & 0803,valid Test Failures of Div I DG Occurred Due to Problem W/Contacts within Breaker Control Switch & Failed Coil in B-C Phase Undervoltage Relay, Respectively.Subj Parts Will Be Replaced During DG Outage1993-08-20020 August 1993 Special Rept:On 930721 & 0803,valid Test Failures of Div I DG Occurred Due to Problem W/Contacts within Breaker Control Switch & Failed Coil in B-C Phase Undervoltage Relay, Respectively.Subj Parts Will Be Replaced During DG Outage U-602163, Special Rept:On 930623,Div I DG (DG1A) Failed to Synchronize W/Associated Safety Bus & Generator Output Breaker Tripped on Reverse Power Signal Due to Faulty Reverse Power Relay. DG1A Reverse Power Relay Replaced W/Newer Model1993-07-23023 July 1993 Special Rept:On 930623,Div I DG (DG1A) Failed to Synchronize W/Associated Safety Bus & Generator Output Breaker Tripped on Reverse Power Signal Due to Faulty Reverse Power Relay. DG1A Reverse Power Relay Replaced W/Newer Model U-602068, Ro:On 921107,ORIX-PR008 Was Declared Inoperable Due to Lo Fail Signal Received for Channel 3 Which Was Unable to Be Reset.Preplanned Alternate Method of Monitoring HVAC Stack Initiated1992-11-24024 November 1992 Ro:On 921107,ORIX-PR008 Was Declared Inoperable Due to Lo Fail Signal Received for Channel 3 Which Was Unable to Be Reset.Preplanned Alternate Method of Monitoring HVAC Stack Initiated U-602057, Special Rept:On 920921,generator Output Breaker Failed to Close on Four Attempts.Caused by Bent Protective Cover Over Auxiliary Switches & anti-pump Coil.Output Breaker Racked to Test Position & Sucessfully Cycled Three Times1992-10-20020 October 1992 Special Rept:On 920921,generator Output Breaker Failed to Close on Four Attempts.Caused by Bent Protective Cover Over Auxiliary Switches & anti-pump Coil.Output Breaker Racked to Test Position & Sucessfully Cycled Three Times U-602049, Ro:On 920922,Control Room Received Notification That Employee Working in Radwaste Sort Tent Had Been Injured & Potentially Contaminated.Ambulance Called to Respond.Hosp Notified Util That Victim Was Not Contaminated1992-09-28028 September 1992 Ro:On 920922,Control Room Received Notification That Employee Working in Radwaste Sort Tent Had Been Injured & Potentially Contaminated.Ambulance Called to Respond.Hosp Notified Util That Victim Was Not Contaminated U-602035, Special Rept:On 920717 & 0807,output Breaker Failed to Close During Periodic Testing of Dg.Caused by Failure of H1 trunk-operated Contact Switch Due to Slight Breaker Movement.Vendor Manual for Switchgear Will Be Reviewed1992-08-19019 August 1992 Special Rept:On 920717 & 0807,output Breaker Failed to Close During Periodic Testing of Dg.Caused by Failure of H1 trunk-operated Contact Switch Due to Slight Breaker Movement.Vendor Manual for Switchgear Will Be Reviewed ML20216J2861992-08-0808 August 1992 Special Rept:On 920712,determined That Valid Failure of Div 1 EDG Occurred.Caused by B-C Phase CV-2 Relay Telephone Coil Failing Due to Excessive Current.Design Change Mod Initiated.Also Reportable Per Part 21 U-601991, Ro:On 920522,discovered That External Vessel Surface Was Hot & Chart Recorder Indicated Absorber Bed Temp Greater than 300F.Fire Brigade Was Activated.Sampling Process Established to Monitor Purge Exhaust Composition1992-06-0101 June 1992 Ro:On 920522,discovered That External Vessel Surface Was Hot & Chart Recorder Indicated Absorber Bed Temp Greater than 300F.Fire Brigade Was Activated.Sampling Process Established to Monitor Purge Exhaust Composition U-601970, Special Rept:On 920328,diesel Generator 1B Manually Started But Stabilized Outside TS Range of 60 + or - Hz. Caused by Failure of Power Supply for Electronic Speed Controller.Power Supply Replaced1992-04-24024 April 1992 Special Rept:On 920328,diesel Generator 1B Manually Started But Stabilized Outside TS Range of 60 + or - Hz. Caused by Failure of Power Supply for Electronic Speed Controller.Power Supply Replaced U-601946, Special Rept:On 920302,meteorological Tower Differential Air Temp Instrumentation Declared Inoperable to Facilitate Troubleshooting Re Discrepancy in Meteorological Data. Missing Ducting Tube from Aspirator Installed1992-03-0606 March 1992 Special Rept:On 920302,meteorological Tower Differential Air Temp Instrumentation Declared Inoperable to Facilitate Troubleshooting Re Discrepancy in Meteorological Data. Missing Ducting Tube from Aspirator Installed U-601942, Revised Special Rept Re non-valid Test Failure of Div I DG, Describing Correct Steps Involved in Synchronizing DG W/ Offsite Power.Dg Output Voltage Adjusted Such That It Is Slightly Higher than Offsite Power Voltage1992-03-0202 March 1992 Revised Special Rept Re non-valid Test Failure of Div I DG, Describing Correct Steps Involved in Synchronizing DG W/ Offsite Power.Dg Output Voltage Adjusted Such That It Is Slightly Higher than Offsite Power Voltage U-601931, Special Rept:On 920109,diesel Generator 1A Tripped Due to Reverse Power.Caused by Improper Manual Loading Following Synchronization W/Offsite Power.Dg 1A Manually Started to Demonstrate Operability Per Surveillance Procedure 9080.011992-02-0505 February 1992 Special Rept:On 920109,diesel Generator 1A Tripped Due to Reverse Power.Caused by Improper Manual Loading Following Synchronization W/Offsite Power.Dg 1A Manually Started to Demonstrate Operability Per Surveillance Procedure 9080.01 U-601893, Special Rept:On 911001,ORIX-PRO12 Declared Inoperable in Order to Perform Channel Calibr in Accordance W/Ts Surveillance Requirement 4.3.7.5.Calibr Initially Performed by day-shift C&I Crew,Then Backshift Crew1991-10-17017 October 1991 Special Rept:On 911001,ORIX-PRO12 Declared Inoperable in Order to Perform Channel Calibr in Accordance W/Ts Surveillance Requirement 4.3.7.5.Calibr Initially Performed by day-shift C&I Crew,Then Backshift Crew U-601834, Special Rept:On 910404,during Surveillance Diesel Generator 1A Reached Required Voltage & Frequency But Failed to Close & Phase Undervoltage Relay B-C Tripped.Cause Not Determined.Racking Mechanism Will Be Inspected & Lubricated1991-05-0606 May 1991 Special Rept:On 910404,during Surveillance Diesel Generator 1A Reached Required Voltage & Frequency But Failed to Close & Phase Undervoltage Relay B-C Tripped.Cause Not Determined.Racking Mechanism Will Be Inspected & Lubricated U-601788, Special Rept:On 910106,Div II Diesel Generator Failed During Test.Caused by Malfunction of A-3 Relay Tachometer. Preventive Maint Task Will Be Issued to Remove,Inspect & Bench Test A-3 Relay Every Two Yrs1991-02-0505 February 1991 Special Rept:On 910106,Div II Diesel Generator Failed During Test.Caused by Malfunction of A-3 Relay Tachometer. Preventive Maint Task Will Be Issued to Remove,Inspect & Bench Test A-3 Relay Every Two Yrs U-601309, Ro:On 881111,generator Trip W/Reactor Scram Occurred Due to Sudden Pressure Actuation on 1C Main Power Transformer & Fire on Insulator of 1C Main Power Transformer Discovered. Fire Extinguished1988-11-12012 November 1988 Ro:On 881111,generator Trip W/Reactor Scram Occurred Due to Sudden Pressure Actuation on 1C Main Power Transformer & Fire on Insulator of 1C Main Power Transformer Discovered. Fire Extinguished U-601298, Ro:On 881026,Tech Spec 3.0.3 Entered Due to Declaring Control Room Ventilation Train a Inoperable.Caused by Faulty Flow Transmitter.Reactor Power Was Reduced & Calibr on Train a Flow Transmitter Performed1988-10-27027 October 1988 Ro:On 881026,Tech Spec 3.0.3 Entered Due to Declaring Control Room Ventilation Train a Inoperable.Caused by Faulty Flow Transmitter.Reactor Power Was Reduced & Calibr on Train a Flow Transmitter Performed U-601265, Ro:On 880901,HPCS Initiated & Injected Water Into Reactor for 28 During Maint Surveillance Activities on Reactor Water Level Transmitter.Injection Valve & HPCS Pump Secured. Notification of Unusual Event Lasted Approx 10 Minutes1988-09-0202 September 1988 Ro:On 880901,HPCS Initiated & Injected Water Into Reactor for 28 During Maint Surveillance Activities on Reactor Water Level Transmitter.Injection Valve & HPCS Pump Secured. Notification of Unusual Event Lasted Approx 10 Minutes U-601258, Special Rept:On 880803,accident Monitoring Instrumentation for HVAC Stack Declared Inoperable for More That 72 H.Caused by Underway Work to Perform Routine Channel Calibr.Plant Condition Rept Initiated1988-08-22022 August 1988 Special Rept:On 880803,accident Monitoring Instrumentation for HVAC Stack Declared Inoperable for More That 72 H.Caused by Underway Work to Perform Routine Channel Calibr.Plant Condition Rept Initiated U-601219, Ro:On 880623,maint Technician Badly Burned in 762-ft Radwaste Evaporator Vapor Body Room.Caused by Performing Work on Wrong Evaporator.Evaporator Secured & Technician Given Medical Attention1988-06-24024 June 1988 Ro:On 880623,maint Technician Badly Burned in 762-ft Radwaste Evaporator Vapor Body Room.Caused by Performing Work on Wrong Evaporator.Evaporator Secured & Technician Given Medical Attention U-601173, Special Rept:On 880329,discovered Failure of Wind Velocity & Direction Sensors on Facility Meteorological Tower.Caused by Inadvertent Exposure of Sensors to Weather.Sensor Assembly, Including Retaining Device Replaced1988-04-15015 April 1988 Special Rept:On 880329,discovered Failure of Wind Velocity & Direction Sensors on Facility Meteorological Tower.Caused by Inadvertent Exposure of Sensors to Weather.Sensor Assembly, Including Retaining Device Replaced U-601026, Summary Rept:On 870828,notification of Unusual Event Declared Per Emergency Plan Implementing Procedures EC-02. Personnel Informed of Bomb Threat Made Against Util.Security Levels Tightened & Searches Performed.No Explosives Found1987-08-31031 August 1987 Summary Rept:On 870828,notification of Unusual Event Declared Per Emergency Plan Implementing Procedures EC-02. Personnel Informed of Bomb Threat Made Against Util.Security Levels Tightened & Searches Performed.No Explosives Found U-601015, Ro:On 870816,protected Area Intrusion Detection Sys Deactivated Due to Severe Weather.Compensatory Measures in Place.Security Personnel Removed from Post booths.Closed- Circuit Television Observers Posted Until Weather Cleared1987-08-21021 August 1987 Ro:On 870816,protected Area Intrusion Detection Sys Deactivated Due to Severe Weather.Compensatory Measures in Place.Security Personnel Removed from Post booths.Closed- Circuit Television Observers Posted Until Weather Cleared U-601017, Ro:On 870819,bomb Threat Received.Security Levels Tightened. State of Il,Nrc Incident Response Ctr & NRC Resident Inspector Notified.No Explosives Located1987-08-20020 August 1987 Ro:On 870819,bomb Threat Received.Security Levels Tightened. State of Il,Nrc Incident Response Ctr & NRC Resident Inspector Notified.No Explosives Located U-601004, Ro:On 870804,notification of Unusual Event Declared Due to Inoperability of Channel 1B21-N697A,LPCS,LPCI & RHR B. Functional Test of Channel Performed & Device,Lpcs & LPCI Declared Operable.Notification of Unusual Event Terminated1987-08-0505 August 1987 Ro:On 870804,notification of Unusual Event Declared Due to Inoperability of Channel 1B21-N697A,LPCS,LPCI & RHR B. Functional Test of Channel Performed & Device,Lpcs & LPCI Declared Operable.Notification of Unusual Event Terminated ML20236B5881987-07-17017 July 1987 Special Rept:On 870610,loose Parts Monitoring Sys Channels Went Into Alarm & Could Not Be Reset.Caused by Flow Noise from Reactor Recirculation Sys Flow Control Valve in Throttled Position.Alarm Temporarily Disabled U-600977, Ro:On 870704,protected Area Intrusion Detection Sys Deactivated Due to Severe Weather.Compensatory Measures Not Taken Due to Personnel Safety.Util Will Review Area of Formal Communications & Take Corrective Actions1987-07-11011 July 1987 Ro:On 870704,protected Area Intrusion Detection Sys Deactivated Due to Severe Weather.Compensatory Measures Not Taken Due to Personnel Safety.Util Will Review Area of Formal Communications & Take Corrective Actions U-600970, Special Rept:On 870608,plant Failed to Reach Rated Voltage & Rated Speed in Equal to or Less than 12 S.Caused by Linkage Connecting Shaft to Fuel Rack Out of Alignment.Alignment Requirements & Linkage Reworked1987-07-0808 July 1987 Special Rept:On 870608,plant Failed to Reach Rated Voltage & Rated Speed in Equal to or Less than 12 S.Caused by Linkage Connecting Shaft to Fuel Rack Out of Alignment.Alignment Requirements & Linkage Reworked U-600964, Special Rept:On 870610,earthquake Estimated to Be 5.0 on Richter Scale Noted.Walkdowns of Plant Structures & Sys Conducted.No Damage or Abnormal Conditions Observed.Related Info,Including Sargent & Lundy ...Seismic...Rept, Encl1987-06-19019 June 1987 Special Rept:On 870610,earthquake Estimated to Be 5.0 on Richter Scale Noted.Walkdowns of Plant Structures & Sys Conducted.No Damage or Abnormal Conditions Observed.Related Info,Including Sargent & Lundy ...Seismic...Rept, Encl U-600956, Final Status of Repair & Anticipated Schedule for Restoration of Remaining Out of Svc Annunciators.One Annunciator Listed in Groups 1 & 2 of Util Remain to Be Repaired1987-06-11011 June 1987 Final Status of Repair & Anticipated Schedule for Restoration of Remaining Out of Svc Annunciators.One Annunciator Listed in Groups 1 & 2 of Util Remain to Be Repaired U-600947, Notification of Unusual Event:On 870524,motor-driven Feed Pump Regulating Valve 1FW-F004 Malfunctioned,Increasing Reactor Water Level.Cause Under Investigation.Valve Shifted to Manual Control W/No Response.Event Terminated Same Day1987-05-26026 May 1987 Notification of Unusual Event:On 870524,motor-driven Feed Pump Regulating Valve 1FW-F004 Malfunctioned,Increasing Reactor Water Level.Cause Under Investigation.Valve Shifted to Manual Control W/No Response.Event Terminated Same Day U-600941, Special Rept:On 870411,operator Discovered No Power to Play Back Pens (All Lights Out) of Playback Unit.Caused by Blown Fuses of Recorder,Playback & Analyzer.Sensor & Portion of Circuit Boards Have Been Replaced1987-05-21021 May 1987 Special Rept:On 870411,operator Discovered No Power to Play Back Pens (All Lights Out) of Playback Unit.Caused by Blown Fuses of Recorder,Playback & Analyzer.Sensor & Portion of Circuit Boards Have Been Replaced U-600928, Ro:On 870506,reactor Manually Scrammed When Reactor Pressure Vessel Level Began to Rise.Caused by Failure of Feedwater Valve Controlling Flow of Water to Reactor to Open.Reactor Shut Down.State of Il & NRC Response Ctr Notified1987-05-0606 May 1987 Ro:On 870506,reactor Manually Scrammed When Reactor Pressure Vessel Level Began to Rise.Caused by Failure of Feedwater Valve Controlling Flow of Water to Reactor to Open.Reactor Shut Down.State of Il & NRC Response Ctr Notified U-600890, Ro:On 870322,containment Isolation Occurred on Instrument Air Sys During Surveillance of ECCS Reactor Water Level Channel Functional Checklist.Cause Not Stated.Reactor Shut Down1987-03-23023 March 1987 Ro:On 870322,containment Isolation Occurred on Instrument Air Sys During Surveillance of ECCS Reactor Water Level Channel Functional Checklist.Cause Not Stated.Reactor Shut Down 1999-07-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARU-603277, Monthly Operating Rept for Sept 1999 for Clinton Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Clinton Power Station,Unit 1.With ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers U-603267, Monthly Operating Rept for Aug 1999 for Clinton Power Station,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Clinton Power Station,Unit 1.With U-603245, Monthly Operating Rept for Jul 1999 for CPS Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for Jul 1999 for CPS Unit 1.With ML20211C9621999-07-26026 July 1999 ISI Summary Rept U-603232, Special Rept:On 990531 Lpms Was Declared Inoperable Due to Receipt of High Vibration & Loose Parts Alarm Which Did Not Clear.Lpms Was Restored to Operable Status on 990707 After Alignment & Tension on Recorder Tape Drive Was Adjusted1999-07-0909 July 1999 Special Rept:On 990531 Lpms Was Declared Inoperable Due to Receipt of High Vibration & Loose Parts Alarm Which Did Not Clear.Lpms Was Restored to Operable Status on 990707 After Alignment & Tension on Recorder Tape Drive Was Adjusted U-603233, Monthly Operating Rept for June 1999 for Clinton Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Clinton Power Station,Unit 1.With U-603222, Monthly Operating Rept for May 1999 for Clinton Power Station.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Clinton Power Station.With ML20210K8391999-05-11011 May 1999 British Energy Annual Rept & Accounts 1998-99 ML20206H1231999-05-0505 May 1999 Illinois Power Co CPS Main CR Simulator Certification Rept U-603210, Monthly Operating Rept for Apr 1999 for Cps,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Cps,Unit 1.With U-603204, Final Part 21 Rept 21-99-003 Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier Trentec for Westinghouse Breaker 1AP05EH.Issue Determined Not Reportable Per 10CFR211999-04-30030 April 1999 Final Part 21 Rept 21-99-003 Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier Trentec for Westinghouse Breaker 1AP05EH.Issue Determined Not Reportable Per 10CFR21 U-603192, Monthly Operating Rept for Mar 1999 for Clinton Power Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Clinton Power Station,Unit 1.With U-603182, Part 21 Rept Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier, Trentec.Condition Rept 1-99-01-136 Was Initiated to Track Investigation & Resolution of Issue1999-03-12012 March 1999 Part 21 Rept Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier, Trentec.Condition Rept 1-99-01-136 Was Initiated to Track Investigation & Resolution of Issue U-603176, Monthly Operating Rept for Feb 1999 for Clinton Power Station,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Clinton Power Station,Unit 1.With ML20207F2031999-02-10010 February 1999 Rev 1 to CPS COLR for Reload 6 Cycle 7 ML20202J0181999-02-0303 February 1999 SER Accepting Changes in Quality Assurance Program,Which Continues to Meet Requirements of App B to 10CFR50 U-603144, Monthly Operating Rept for Dec 1998 for Clinton Power Station,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Clinton Power Station,Unit 1.With U-603223, Illinova Corp 1998 Annual Rept. with1998-12-31031 December 1998 Illinova Corp 1998 Annual Rept. with U-603115, Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps in Supplying SR Parts to Npps.Issue Is Not Reportable Under 10CFR21. Dedication Process Did Not Affect Ability of Components1998-12-0404 December 1998 Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps in Supplying SR Parts to Npps.Issue Is Not Reportable Under 10CFR21. Dedication Process Did Not Affect Ability of Components U-603124, Monthly Operating Rept for Nov 1998 for Clinton Power Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Clinton Power Station,Unit 1.With U-603114, Part 21 Rept 21-98-049 Re W Dhp Circuit Breaker Refurbished by Nuclear Logistics,Inc Which Failed to Operate.Caused by Trip Latch out-of-adjustment & Incorrectly Sized Ratchet Lever Assembly Bushing.Breakers Were Returned to Vendor1998-11-25025 November 1998 Part 21 Rept 21-98-049 Re W Dhp Circuit Breaker Refurbished by Nuclear Logistics,Inc Which Failed to Operate.Caused by Trip Latch out-of-adjustment & Incorrectly Sized Ratchet Lever Assembly Bushing.Breakers Were Returned to Vendor U-603103, Monthly Operating Rept for Oct 1998 for Clinton Power Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Clinton Power Station,Unit 1.With U-603101, Special Rept:On 980918,discovered That Triaxial Seismic Accelerometers Had Not Been Properly Calibrated.Caused by Inadequate Calibration Procedure.Calibration to Be Performed off-site1998-10-28028 October 1998 Special Rept:On 980918,discovered That Triaxial Seismic Accelerometers Had Not Been Properly Calibrated.Caused by Inadequate Calibration Procedure.Calibration to Be Performed off-site ML20154F8701998-10-0606 October 1998 Safety Evaluation Authorizing Proposed Alternative to Requirements of OMa-1988,Part 10,Section 4.2.2.3 for 21 Category a Reactor Coolant Sys Pressure Isolation Valves U-603091, Monthly Operating Rept for Sept 1998 for Clinton Power Station,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Clinton Power Station,Unit 1.With ML20153F9871998-09-17017 September 1998 Safety Evaluation Accepting 980225 Proposed Rev 26 to Illinois Power Nuclear Program Qam ML20151U1391998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Clinton Power Station,Unit 1 ML20237E3991998-08-27027 August 1998 SER Accepting Licensee Response to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode, for Clinton Power Station ML20237A1521998-08-0707 August 1998 SER Re Mgt Services Agreement at Clinton Power Station. Approval Under 10CFR50.80 Not Required ML20151Y6591998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Clinton Power Station,Unit 1 U-603033, Part 21 Rept 21-98-039 Re Shrinkage of Medium & High Density Silicone Seals Designed & Installed by Bisco Using Dow Corning Sylgard 170 Matl.Caused by Coefficient of Thermal Expansion.Will Inspect & Rework/Repair Suspected Seals1998-07-20020 July 1998 Part 21 Rept 21-98-039 Re Shrinkage of Medium & High Density Silicone Seals Designed & Installed by Bisco Using Dow Corning Sylgard 170 Matl.Caused by Coefficient of Thermal Expansion.Will Inspect & Rework/Repair Suspected Seals U-603041, Monthly Operating Rept for June 1998 for Clinton Power Station,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Clinton Power Station,Unit 1 ML20151U1501998-06-30030 June 1998 Revised Monthly Operating Rept for June 1998 for Clinton Power Station,Unit 1 U-603023, Monthly Operating Rept for May 1998 for Clinton Power Station,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Clinton Power Station,Unit 1 U-603014, Special Rept:On 980512,lightning Struck Primary Meteorological Monitoring Instrumentation Tower Damaging 60- Meter Wind Speed & Associated Transmuter Circuit Card. Surveillance Testing Performed1998-05-28028 May 1998 Special Rept:On 980512,lightning Struck Primary Meteorological Monitoring Instrumentation Tower Damaging 60- Meter Wind Speed & Associated Transmuter Circuit Card. Surveillance Testing Performed ML20236E7991998-05-26026 May 1998 Final Part 21 Rept Re W Dhp Circuit Breaker Auxillary Switch Operating Assembly Anomalies.Caused by Loss of Breaker Safety Function.Dhp Circuit Will Be Inspected ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted U-603004, Part 21 Rept Re 980107 Determination That Itt Barton Model 580A Series Differential Pressure Indicating Switches Operating Forces Too Low.Manufacturing Sys Allowed Switches to Be Mixed.Evaluation Concludes Issue Not Reportable1998-05-15015 May 1998 Part 21 Rept Re 980107 Determination That Itt Barton Model 580A Series Differential Pressure Indicating Switches Operating Forces Too Low.Manufacturing Sys Allowed Switches to Be Mixed.Evaluation Concludes Issue Not Reportable ML20216A9601998-05-0808 May 1998 Part 21 Rept Re Failure of 12 Volt DC Inverter Power Supply. Caused by Inadequately Sized Output Transistor Pair Combined W/Degraded Capacitors.Licensee Plans to Replace All Output Transistors & Degraded Capacitors U-602995, Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps During Use of Portable Metal Analyzer.Util Identified Discrepancies Which Are Acceptable W/Some Exception of Some Replacement Parts1998-05-0505 May 1998 Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps During Use of Portable Metal Analyzer.Util Identified Discrepancies Which Are Acceptable W/Some Exception of Some Replacement Parts U-603006, Monthly Operating Rept for Apr 1998 for Clinton Power Station,Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Clinton Power Station,Unit 1 U-602994, Part 21 Rept Re Final Rept 21-98-008,on 980113,reliance Electric Motors Supplied by Rockwell International for Hydrogen Recombiner Cooling Fans Do Not Have nameplate- Specified High Temperature Bearings.Fan Motors Acceptable1998-04-29029 April 1998 Part 21 Rept Re Final Rept 21-98-008,on 980113,reliance Electric Motors Supplied by Rockwell International for Hydrogen Recombiner Cooling Fans Do Not Have nameplate- Specified High Temperature Bearings.Fan Motors Acceptable ML20216B1351998-04-21021 April 1998 Rev 0 to Illinois Power Co Clinton Power Station SVC Design Rept U-602979, Final Part 21 Rept 21-97-059 Re Discrepancies Found During Receipt Insp of Three Refurbished safety-related W Dhp Circuit Breakers.Util Completed Evaluation,Per 10CFR21 & Concludes That Condition Is Not Reportable1998-04-0707 April 1998 Final Part 21 Rept 21-97-059 Re Discrepancies Found During Receipt Insp of Three Refurbished safety-related W Dhp Circuit Breakers.Util Completed Evaluation,Per 10CFR21 & Concludes That Condition Is Not Reportable U-602976, Monthly Operating Rept for Mar 1998 for Clinton Power Station1998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Clinton Power Station ML20217H5771998-03-27027 March 1998 Safety Evaluation Concluding That No Significant Safety Hazards Introduced at CPS for Net 32% Ampacity Derating Factor for 1 H & 3 H Conduit Fire Barrier Sys & 1 H Cable Tray Fire Barrier Sys.Requests Response Addressing Issue U-602968, Interim Part 21 Rept 21-97-055 Re Westinghouse Dhp Circuit Breaker Auxiliary Switch Operating Assembly Anomalies. Initially Reported on 980116.Util Currently Evaluating Suppliers Response to Questions Re Issue1998-03-24024 March 1998 Interim Part 21 Rept 21-97-055 Re Westinghouse Dhp Circuit Breaker Auxiliary Switch Operating Assembly Anomalies. Initially Reported on 980116.Util Currently Evaluating Suppliers Response to Questions Re Issue U-602960, Part 21 & Deficiency Rept Re Commerical Grade Dedication Program of Sentry Equipment Corp.Initially Reported on 980217.IP Performed an Addl Assessment at Sentry Facility on 980226.Next Rept Will Be Submitted by 9804111998-03-12012 March 1998 Part 21 & Deficiency Rept Re Commerical Grade Dedication Program of Sentry Equipment Corp.Initially Reported on 980217.IP Performed an Addl Assessment at Sentry Facility on 980226.Next Rept Will Be Submitted by 980411 U-602954, Interim Part 21 rept,21-98-008 Re Identification That Bearings Installed in Hydrogen Recombiner B Cooling Fan Motor 0HG04CB Were Not Same as Bearings Specified on Motor Nameplate.Will Complete Evaluation of Issue by 9805131998-03-0909 March 1998 Interim Part 21 rept,21-98-008 Re Identification That Bearings Installed in Hydrogen Recombiner B Cooling Fan Motor 0HG04CB Were Not Same as Bearings Specified on Motor Nameplate.Will Complete Evaluation of Issue by 980513 1999-09-30
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Text
liknois Power Company 8
. P.O. Box 678 Chnton. IL 61727 Tel 217 935-5623
. Fax 217 935-4632 John G. Cook n.uness' **"u !G P(MR uo-95(12-05 31.9 1 A.120
.JGC-513-95 December 5, 1995 Docket No. 50-461 Document Control Desk Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Clinton Power Station - Unit 1 Maximum Thermal Power Level Exceeds Ooerating License Requirements
Dear Sir:
Attached is a special report required by Section 2.G of the Clinton Power Station (CPS) Operating License. This report details a violation of Section 2.C.(1) of the CPS Operating License " Maximum Power Level."
Sincerely yours,
[ &
J.G. Cook -
j Vice President MRS/csm Attachment cc: NRC Clinton Licensing Project Manager NRC Resident Office, V-690 Regional Administrator, Region III, USNRC Illinois Department of Nuclear Safety INPO Records Center 110G91
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to U-602527I !
ABSTRACTz On November 3,1995, the plant was in Mode 1, power operation, at about 100% reactor power. The oncoming Shift Technical Advisor (STA) noticed that the reactor water cleanup (RT) [CE]' system flow rate computer point [FI] value had been substituted with a .
value of zero and that the RT system was actually operating. ' RT system flow is used as l an input in the reactor power calculation. As a result of the substitution of zero for the !
' RT system flow computer point, the actual reactor power was 2894.9 megawatts (MW) ,
over an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> weighted average period. This is 0.9 MW over the licensed limit set forth .
l . in section 2.C.(1) of the CPS Operating License. The cause of this event was attributed to l
' l the lack of attention to detail in logging and turnover to subsequent shifts of the removal of the RT flow computer point from service. Corrective actions for this event include:
i revising CPS No. 3512.01, " Display Control System (DCS)/ Performance Monitoring i System (PMS)" and 3512.01F002, "CX/CZ Database Alteration Log Form" to require i
notification of the Shift Supervisor and Line Assistant Shift Supervisor when computer points which affect reactor power calculations are taken out of service or have alternate
- values substituted for the normal output, and briefing main control room personnel, including the STA, on this event.
DESCRIPTION OF EVENT ;
At about 0920 on October 30,1995, with the plant operating at about 100% power, the !
reactor water cleanup (RT) [CE] system was isolated by Operations personnel for 1 scheduled maintenance. When the system was isolated the computer point that displays l RT system flow showed that it had failed because the plant process computer [ID] system l will not acknowledge a RT flow rate of zero as a valid reading. The RT system flow rate ;
computer point [FI] is one input that the plant process computer uses in the heat balance calculation to determine reactor power. The plant process computer checks the output of :
each computer point against a stored upper and lower limit for reasonability. A flow rate !
of zero for RT system flow was below the lower reasonability limit. When the plant !
process computer did not have a valid reading of RT system flow it would not perform the i j heat balance calculation that is typically displayed for use by main control room personnel. -
j However, the heat balance calculation used in calculating plant thennal power limits i
l would continue to calculate reactor power with the last reasonable value that it had received. In order to resolve the problem with the heat balance calculation not functioning, the on-duty Shift Technical Advisor (STA) was able to remove the computer point for RT system flow from service and manually substitute a value of zero for the RT
) system flow computer point. These actions were performed in accordance with procedure
. CPS No. 3512.01, " Display Control System (DCS)/ Performance Monitoring System l (PMS)" which requires approval of the Shift Supervisor, a licensed senior reactor -l operator, to substitute data for a computer point. These actions allowed the plant process !
3 computer to perform the heat balance calculation. When these points are substituted they are still identified as failed on the hourly and 10 minute reactor power computer printouts in the main control room area. The STA noted in the STA log that the computer point 4 ,
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_ Page 2 of 4 )
I had been taken out of service and that a value of zero had been substituted for the
- computer point value. The STA turnover sheet recorded that the RT flow sensor was
- shown as bad on the reactor power computer printouts and that this was because of the RT system outage. The turnover log did not note that this affected the reactor power . -
E calculation; The out of service point was not mentioned or identified during STA shift turnovers. Although not required, removing the computer point from service and 3
substituting a value of zero for RT system flow was not documented in'either the Shift Supervisor's log or Main Control Room Journal.
Flow was restored through the RT system heat exchangers at about 1308 on November 2,
. 1995. When the RT system was restored the on duty STA, the same STA that removed
- . the RT system flow computer point from service, did not restore the RT system flow computer point to service. At about 0650 on November 3,1995, a STA was reviewing i the reactor power computer logs as part of shift turnover and recognized that a value of zero was still being substituted for RT system flow even though the RT system had been
[ restored on November 2,1995. The Line Assistant Shift Supervisor, as well as the Shift Supervisor for the oncoming shift, both licensed senior reactor operators, were
! immediately informed that the RT system flow data was still being substituted and that this
. would impact the reactor power calculation in a non-conservative manner. The STA then l restored the RT system flow computer point to normal operation at about 0655 on November 3,1995. A nuclear engineer from the Nuclear Station Engineering Department
- - was then requested to review the reactor power history for the period that the reactor power calculat
- on was being performed using a RT system flow of zero when the system !
was actually operating. On November' 7,1995, at about 1540 the nuclear engineer informed the Shift Supervisor that the plant operated at an average power level of 2896
- megawatts (MW) thermal power during the period of 0000 to 0655 on November 3,
[ 1995. This is 2 MW thermal or 0.07% over Clinton Power Station's licensed power level i of 2894 MW thermal power. After the initial review by the nuclear engineer was y completed, a more critical review of the data was conducted and it was determined that )
the maximum average overpower for a time weighted 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period was about 0.9 MW thermal power or .03%, not 2 MW thermal power or 0.07%.
I
- CAUSE OF EVENT l 4
The cause of the failure to restore the RT system flow indication computer point to
- normal when the RT system was restored to service was a lack of attention to detail on the i part of the STA that removed the computer point from service. The STA logged that the computer point had been taken out of service and that the output of the computer point
' had been substituted with a value of zero. However, the STA turnover sheet entry only
- . noted that the RT flow computer point, as well as the system inlet and outlet temperatures, were shown as bad on the computer log printout of reactor power due to i the RT system outage. The out of service computer point and the substituted value were l - not identified during the STA's turnover to the following shifts. Also, main control room W
4
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Page 3 of 4
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- personnel failed to recognize the condition for more than two shias. Computer logs of reactor power that print out hourly and identify out of service computer points were available in the main control room but were not reviewed carefully enough to identify this condition until about twenty hours after the RT system was returned to service. Also .
contributing to this event was the lack of a formal tracking system for computer points
. that affect reactor power calculations which are removed from service or have substitute values instituted. The STA documented that the computer point had the value of zero substituted on CPS No. 3512.01F002, "CX/CZ Database Alteration Log Form." Neither this log or the associated procedure, CPS No. 3512.01, " Display Control System _
(DCS)/ Performance Monitoring System (PMS)" provided guidance for tracking or ' l 4
keeping visible to main control room personnel computer points that affect reactor power that have been taken out of service or have had the output value substituted.
CORRECTIVE ACTION -
I The STA immediately restored the RT system flow computer point to service in order for
! the reactor power computer calculation to operate properly Main control room
! personnel, including the STA's, will be briefed on this event with emphasis placed on documentation and communication of shift activities. Also, CPS No. 3512.01, " Display
, Control System (DCS)/ Performance Monitoring System (PMS)" and CPS No.
3512.01F002, "CX/CZ Database Alteration Log Form" will be revised to require notification of the Shift Supervisor and Line Assistant Shift Supervisor when any 4
computer points that affect reactor power are removed from service or have had values substituted into the process computer for actualindication. CPS No. 1401.01F002, " Shift Turnover and Relief-Status Report," will be revised to require that out of service computer points or computer points with substituted values which affect reactor power calculations be recorded on this form. This will ensure that these items remain visible to the plant operators. As an interim action, pending completion of the procedure revisions mentioned above, an Operations Night Order was issued directing that all computer points which affect reactor power calculations which are taken out of service or have substitute 4
values implemented be documented in the MCR Journal as a " Red Arrow" entry item to draw attention to the fact that these points are not operating at their normal mode.
ANALYSIS OF EVENT This event is reportable under Section 2.G of the Clinton Power Station (CPS) Operating License for violating the requirement of Section 2.C.(1) of the CPS Operating License for exceeding the maximum allowable reactor power level permitted by the CPS Operating
. License.
Assessment of the safety consequences and implications of this violation of the CPS Operating License indicates that this event is not safety significant. This assessment was based on the fact that the unit operated at only 2894.9 MW thermal or slightly over 100%
. - - _ . . . ~ - . - - , _ - . _ . . . .- .- .
L 4, .O Ap Attachment to U-602527 ;
Page 4 of 4 the rated thermal power licensed limit _of 2894 MW thermal. The analyses and evaluation !
used to support the CPS Operating License was made for a power level of 3015 MW i thermal.
i i L ADDITIONAL INFORMATION=
No equipment or components failed as a result of this event. ;
lilinois Power reported a violation of exceeding licensed maximum reactor power level for
- an incident that occurred on April 15,1994. However, this event was not related to the substitution of data into the plant process computer heat balance calculation. -
l For additional information about this event, contact Phil Short, Shift Technical Advisor, at
- (217) 935-8881, extension 3485. j i I
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