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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20029A6421991-02-20020 February 1991 LER 91-001-00:on 910121,automatic Closure of Inboard MSIV 1B21-F022 A,B,C & D & Inboard Main Steam Drain Line Isolation Valve 1B21-F016 Occurred.Caused by Personnel Error.Maint Work Request Mwr D09786 revised.W/910220 Ltr ML20043H9231990-06-18018 June 1990 LER 90-012-00:on 900517,feedwater Sys Flow Channel Failed & Caused Sensed Low Feedwater Flow.Caused by Normal end-of- Life Failure for Converter.Power Converter Replaced & Preventive Maint Tasks established.W/900618 Ltr ML20043G1151990-06-14014 June 1990 LER 90-011-00:on 900514,during Routine Testing,Diesel Generators 1A Tripped on High Coolant Temp.Caused by Lack of Procedures for Correctly Positioning Diesel Generator SX Throttle Valves.Caution Tags replaced.W/900614 Ltr ML20043E4911990-06-0505 June 1990 LER 90-010-00:on 900508,Divs I & II Emergency Diesel Generators Declared Inoperable Due to Expansion Joints Not Having Required tie-rods Installed to Prevent Expansion. Caused by Const/Installation error.W/900605 Ltr ML20043C0211990-05-23023 May 1990 LER 89-038-01:on 891212,discovered That Only Two of Four Conductors of Cable to Div II Nuclear Sys Protection Sys Inverter Connected.Caused by Design Error.Design Drawings reviewed.W/900523 Ltr ML20043B5741990-05-21021 May 1990 LER 90-009-00:on 900427,discovered That Moving Filter Paper in Leak Detection Sys Drywell Air Particulate Sample Panel Not Collecting on take-up Reel.Caused by Loose Set Screw on Gear Train.Set Screw tightened.W/900521 Ltr ML20043A2351990-05-11011 May 1990 LER 90-008-00:on 900408,attempt Made for 14 Control Rod Withdrawals While Main Turbine Bypass Valves Were Open & Reactor Power Was Greater than Low Power Setpoint.Caused by Personnel Error.Reactor Shut down.W/900511 Ltr ML20042F4111990-04-30030 April 1990 LER 90-007-00:on 900331,inadequate Determination of Equipment Status Resulted in de-energization of Nuclear Sys Protection Sys.Caused by Personnel Error.Fact Sheet on Operation Issued & Personnel retrained.W/900430 Ltr ML20042E6781990-04-23023 April 1990 LER 90-005-00:on 900322,containment Penetration Identified to Have motor-operated Valve W/Inadequate Actuator on Inboard Isolation Valve.Caused by Failure to Consider Design Capabilities of Actuators.Actuators reworked.W/900423 Ltr ML20042E6791990-04-23023 April 1990 LER 90-006-00:on 900321,process Radiation Monitor Placed in Svc W/O Required Filter Due to Inadequately Specified Job Steps for Plant Mod.Caused by Personnel Error.Procedure 1502.01 to Be revised.W/900423 Ltr ML20042E1581990-04-0909 April 1990 LER 90-003-00:on 900212,determined That 13 safety-related Transmitters Inoperable Due to Housing Covers Found W/Torque Values Less than Required to Meet Environ Qualification. Corrective Actions Program enhanced.W/900409 Ltr ML20042E1551990-04-0606 April 1990 LER 90-004-00:on 900307,review of NRC Info Notice 88-024 Re Failures of air-operated Valves Determined Pressure Differential of 73 solenoid-operated Valves Less than Max Instrument Air Sys Pressure.Valves replaced.W/900406 Ltr ML20012C5831990-03-13013 March 1990 LER 90-001-00:on 900212,drywell Purge Sys Containment Penetration Failed Local Leak Rate Test.Caused by Failure to Remove Cosmolene from Surface of Valve Prior to Initial Installation.Valves replaced.W/900313 Ltr ML19354E1031990-01-18018 January 1990 LER 89-042-00:on 891219,false RCIC Div I Steam Line Differential Pressure High Signal Caused RCIC Turbine Steam Supply Isolation Valve to Shut & RCIC Sys to Trip.Caused by Sensor Design Error.Field Alteration begun.W/900118 Ltr ML19354D9161990-01-17017 January 1990 LER 89-041-00:on 891122,unit Entered Tech Spec 3.0.3 When RCIC & HPCS Sys Inoperable Simultaneously for 37 Minutes. Chiller Condensing Unit Tripped Due to Low Refrigerant Pressure.Refrigerant in Chiller recharged.W/900117 Ltr ML20005G3211990-01-11011 January 1990 LER 89-038-00:on 891212,discovered That Only 2 of 4 Cable Conductors for Div II Nuclear Sys Protection Sys Power Supply Connected.Caused by Design Drawing Deficiency.Power Supply Configurations reviewed.W/900111 Ltr ML20005G2811990-01-0808 January 1990 LER 89-040-00:on 891206,discovered That Mode Limitations from Surveillance Procedure Omitted,Resulting in Inoperable ATWS Recirculation Pump Trip Sys Instrumentation.Caused by Inadequate Procedure.Surveillance revised.W/900108 Ltr ML20005G2951990-01-0808 January 1990 LER 89-039-00:on 891212,operations Shift Supervisor Notified That Three HPCS Suction Valves Not Tested within Max Surveillance Time Interval.Caused by Personnel Error. Surveillance Procedure revised.W/900108 Ltr ML20042D3011989-12-29029 December 1989 LER 89-037-00:on 891129,inboard Drywell post-LOCA Vacuum Relief Valve Failed to Indicate Fully Open During Valve Stroke Testing.Caused by Worn O-rings Allowing Air to Leak Around Solenoid piston.O-rings Replaced.W/Undated Ltr ML19354D6621989-12-21021 December 1989 LER 89-035-00:on 891129,during Channel Functional Test of ECCS Drywell Pressure Channel,Operator Selected Wrong Channel for Testing,Causing Isolation of Instrument Air Sys. Caused by Personnel Error.Briefing conducted.W/891221 Ltr ML19332F8981989-12-13013 December 1989 LER 89-036-00:on 891113,incorrect Connection of Source to Terminals Directly Below Correct Terminals Caused Div 1 Isolation of RCIC Sys.Caused by Personnel Error.Personnel Briefed on Need to Use ladders/stools.W/891213 Ltr ML19325E5841989-11-0101 November 1989 LER 89-034-00:on 891004,discovered That Inservice Station HVAC Exhaust Stack Process Radiation Monitor Had Not Been Verified as Operable,Contrary to Tech Spec 3.3.7.12.Caused by Lack of Training & Inadequate communication.W/891101 Ltr 1991-02-20
[Table view] Category:RO)
MONTHYEARML20029A6421991-02-20020 February 1991 LER 91-001-00:on 910121,automatic Closure of Inboard MSIV 1B21-F022 A,B,C & D & Inboard Main Steam Drain Line Isolation Valve 1B21-F016 Occurred.Caused by Personnel Error.Maint Work Request Mwr D09786 revised.W/910220 Ltr ML20043H9231990-06-18018 June 1990 LER 90-012-00:on 900517,feedwater Sys Flow Channel Failed & Caused Sensed Low Feedwater Flow.Caused by Normal end-of- Life Failure for Converter.Power Converter Replaced & Preventive Maint Tasks established.W/900618 Ltr ML20043G1151990-06-14014 June 1990 LER 90-011-00:on 900514,during Routine Testing,Diesel Generators 1A Tripped on High Coolant Temp.Caused by Lack of Procedures for Correctly Positioning Diesel Generator SX Throttle Valves.Caution Tags replaced.W/900614 Ltr ML20043E4911990-06-0505 June 1990 LER 90-010-00:on 900508,Divs I & II Emergency Diesel Generators Declared Inoperable Due to Expansion Joints Not Having Required tie-rods Installed to Prevent Expansion. Caused by Const/Installation error.W/900605 Ltr ML20043C0211990-05-23023 May 1990 LER 89-038-01:on 891212,discovered That Only Two of Four Conductors of Cable to Div II Nuclear Sys Protection Sys Inverter Connected.Caused by Design Error.Design Drawings reviewed.W/900523 Ltr ML20043B5741990-05-21021 May 1990 LER 90-009-00:on 900427,discovered That Moving Filter Paper in Leak Detection Sys Drywell Air Particulate Sample Panel Not Collecting on take-up Reel.Caused by Loose Set Screw on Gear Train.Set Screw tightened.W/900521 Ltr ML20043A2351990-05-11011 May 1990 LER 90-008-00:on 900408,attempt Made for 14 Control Rod Withdrawals While Main Turbine Bypass Valves Were Open & Reactor Power Was Greater than Low Power Setpoint.Caused by Personnel Error.Reactor Shut down.W/900511 Ltr ML20042F4111990-04-30030 April 1990 LER 90-007-00:on 900331,inadequate Determination of Equipment Status Resulted in de-energization of Nuclear Sys Protection Sys.Caused by Personnel Error.Fact Sheet on Operation Issued & Personnel retrained.W/900430 Ltr ML20042E6781990-04-23023 April 1990 LER 90-005-00:on 900322,containment Penetration Identified to Have motor-operated Valve W/Inadequate Actuator on Inboard Isolation Valve.Caused by Failure to Consider Design Capabilities of Actuators.Actuators reworked.W/900423 Ltr ML20042E6791990-04-23023 April 1990 LER 90-006-00:on 900321,process Radiation Monitor Placed in Svc W/O Required Filter Due to Inadequately Specified Job Steps for Plant Mod.Caused by Personnel Error.Procedure 1502.01 to Be revised.W/900423 Ltr ML20042E1581990-04-0909 April 1990 LER 90-003-00:on 900212,determined That 13 safety-related Transmitters Inoperable Due to Housing Covers Found W/Torque Values Less than Required to Meet Environ Qualification. Corrective Actions Program enhanced.W/900409 Ltr ML20042E1551990-04-0606 April 1990 LER 90-004-00:on 900307,review of NRC Info Notice 88-024 Re Failures of air-operated Valves Determined Pressure Differential of 73 solenoid-operated Valves Less than Max Instrument Air Sys Pressure.Valves replaced.W/900406 Ltr ML20012C5831990-03-13013 March 1990 LER 90-001-00:on 900212,drywell Purge Sys Containment Penetration Failed Local Leak Rate Test.Caused by Failure to Remove Cosmolene from Surface of Valve Prior to Initial Installation.Valves replaced.W/900313 Ltr ML19354E1031990-01-18018 January 1990 LER 89-042-00:on 891219,false RCIC Div I Steam Line Differential Pressure High Signal Caused RCIC Turbine Steam Supply Isolation Valve to Shut & RCIC Sys to Trip.Caused by Sensor Design Error.Field Alteration begun.W/900118 Ltr ML19354D9161990-01-17017 January 1990 LER 89-041-00:on 891122,unit Entered Tech Spec 3.0.3 When RCIC & HPCS Sys Inoperable Simultaneously for 37 Minutes. Chiller Condensing Unit Tripped Due to Low Refrigerant Pressure.Refrigerant in Chiller recharged.W/900117 Ltr ML20005G3211990-01-11011 January 1990 LER 89-038-00:on 891212,discovered That Only 2 of 4 Cable Conductors for Div II Nuclear Sys Protection Sys Power Supply Connected.Caused by Design Drawing Deficiency.Power Supply Configurations reviewed.W/900111 Ltr ML20005G2811990-01-0808 January 1990 LER 89-040-00:on 891206,discovered That Mode Limitations from Surveillance Procedure Omitted,Resulting in Inoperable ATWS Recirculation Pump Trip Sys Instrumentation.Caused by Inadequate Procedure.Surveillance revised.W/900108 Ltr ML20005G2951990-01-0808 January 1990 LER 89-039-00:on 891212,operations Shift Supervisor Notified That Three HPCS Suction Valves Not Tested within Max Surveillance Time Interval.Caused by Personnel Error. Surveillance Procedure revised.W/900108 Ltr ML20042D3011989-12-29029 December 1989 LER 89-037-00:on 891129,inboard Drywell post-LOCA Vacuum Relief Valve Failed to Indicate Fully Open During Valve Stroke Testing.Caused by Worn O-rings Allowing Air to Leak Around Solenoid piston.O-rings Replaced.W/Undated Ltr ML19354D6621989-12-21021 December 1989 LER 89-035-00:on 891129,during Channel Functional Test of ECCS Drywell Pressure Channel,Operator Selected Wrong Channel for Testing,Causing Isolation of Instrument Air Sys. Caused by Personnel Error.Briefing conducted.W/891221 Ltr ML19332F8981989-12-13013 December 1989 LER 89-036-00:on 891113,incorrect Connection of Source to Terminals Directly Below Correct Terminals Caused Div 1 Isolation of RCIC Sys.Caused by Personnel Error.Personnel Briefed on Need to Use ladders/stools.W/891213 Ltr ML19325E5841989-11-0101 November 1989 LER 89-034-00:on 891004,discovered That Inservice Station HVAC Exhaust Stack Process Radiation Monitor Had Not Been Verified as Operable,Contrary to Tech Spec 3.3.7.12.Caused by Lack of Training & Inadequate communication.W/891101 Ltr 1991-02-20
[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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20.220 CLINTON POWER STATION. P.O. DOX 678, CLINTON, ILLINOIS 61727 0678, TELEPilONE (217) 935 8881, j F May 21,;1990 10CFR50.~73 Docket No~.50 461 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. . 20555
Subject:
~
Clinton Power Station - Unit 1 Licensee Event Reoort No. 90-009-00
Dear Sir:
- Please find enclosed Licensee Event Report No.- 90 009 00: Loose' Set.
Screw on Cear Train of Moving Filter Paner Drive Mechanism Results in Paner=
Not Movine and Inonerable Leak Detection Drywell Air Particulate Samnle Panel, This report is being submitted in accordance with the requirements of
-100FR50.73.
Sincerely yours,
( .
F.A.Sphngenb g, II Manager - Licensing and Safety RSF/ cam s
Enclosure
? cc: NRC Resident Office d NRC Region III, Regional Administrator m IUPO Records Center Illinois Department of Nuclear Safety NRC Clinton Licensing Project Manager 1
I 9003300239 900521 DR ADOCK 0500 1 gQg ip
i W C Form 3e4 U 5 NUCLEAR MOULATDM COMMISSION APPROVED OMB NO 3 % 0 0104 LICENSEE EVENT REPORT (LER) " a ' 5 ' ' 3""
f ACILITV NAME 01 DOCR E T NUM8t R (2) > AGE s3' Clinton Power Station 0j5jojolol4]6l1 1 loFl015 mms's Set Screw on Gear Train of Moving Filter Paper Drive Mechanism Results in Paper Not Movinn and Inoperable Leak Detection Drywell Air Particulate Sample Panel t ytNT DATE (61 LER NUM3g R 16) REPORT DATE (71 OTHE R 8 ACILITIES INVOLVED 18)
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20 406teH1 Hel 60 73tell2 Hoe) 60 736eH2Her LICENsEt CONT ACT FOR THis LE R H21 N AMt ' T E LEPHONE NUMBER ANE A CODE S. E. Rasor, Director - Plant Maintenance, extension 3204 2l1l7 9l3 i51 1 8l 8 811 1 COMPLE TE ONE LINE FOR E ACH COMPONE Nv F AiLURE OfSCRl3E D IN THis REPOR T 113i
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On April 27 1990, with the plant in Mode 1 (POWER OPERATION) a technician discovered the moving filter paper in the Leak Detection system drywell air particulate sample panel lE31-P002 was not collecting on the take-up reel. The Shift Supervisor was notified of this and he declared the panel inoperable. He also directed the drywell atmosphere be manually sampled and analyzed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The length of time the filter paper had not been moving could not be determined.
This condition was determined to be prohibited by Technical Specification 3.4.3.1. Troubleshooting of 1E31-P002 identified a loose set screw on the normal speed gear train of the filter paper drive mechanism as the cause of this event. The loose screw had allowed one gear to slip out of aligrunent resulting in insufficient gear engagement. Corrective actions included realigning the gear; tightening the set screw; verifying proper filter paper movement; revising a preventive maintenance task to require inspection of the gear assembly for proper gear engagement and set screw tightness, and provide better dira tion on verifying proper filter paper movement; and investigating methods to ensure proper operation of the filter paper drive mechanism without requiring disassembly of the sample pane 1.
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I 4,AC Pere 3064 UA. NUCLEAR RGOULAf0av COMMessiog LICENSEE EVENT REPORT (LER) TEXT CONTINUATION maovso oMe No. mo-oio. ';
EXPsRES: t/31/M f ACitiTV hAME Hi DoCE8T NUMet A ul Lt A NUMeER I6I PACE (31 vaan .
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On April 27, 1990, a Control and Instrumentation:(C61) technician .
discovered the moving filter _[FLT) paper in Leak Detection (LD) system 1
-[IJ) .drywell air particulato sample panel-[PL) 1E31-P002 was not '
collecting on the take up reel'and therefore the panel was inoperable.
This condition was determined to be prohibited by Technical Specifivation 3.4.3.1 which requires the drywell atmosphere particulate radioactivity ,
monitoring system, the drywell sump flow monitoring system, and either the drywell atmosphere gaseous radioactivity monitoring system or the drywell air coolers condensate flow rate monitoring system to be' operable in Modes 1 (POWER OPERATION), 2 (STARTUP) and 3 (HOT SHUTDOWN),
On April 4, 1990, with the plant in Mode 4 (COLD SHUTDOWN), a C61 technician performed' Preventive Maintenance (PM) task PCILDW001 on 1E31 P002. This PM task requires replacement of the sample panel's- 'E moving-filter paper at approximately two week intervals. The technician verified the fil_ter paper was moving properly following replacement and then de energized the panel since it.was not required to be operable in ,
-Mode 4.
l: The sample panel monitors air particulate of the drywellLfor.-
radioactivity. The panel does this by receiving-a reprnsentative sample
!? of gaseous and effluent particulates from the drywell and trapping the l
particulate matter on moving filter paper. The filter paper is designed to retain the particulates and is passed in front of a scintillation detector [DET) where any radioactivity is detected. The panel provides-continuous indication and activates alarms in the Main Control Room.
l On April 7, 1990, at approximately 1537 hours0.0178 days <br />0.427 hours <br />0.00254 weeks <br />5.848285e-4 months <br />, the plant entered Mode 2 l and in accordance with the Mode 2 startup checklist 1E31-P002 was a energized.
On April 10, 1990, at approximately 1825 hours0.0211 days <br />0.507 hours <br />0.00302 weeks <br />6.944125e-4 months <br />, the plant entered Mode 1.
On April 13, 1990, unrelated to this event, the Vice President directed g the plant be shut down. This shutdown is discussed in LER 90-008-00.
l On April 15, 1990, at approximately 0545 hours0.00631 days <br />0.151 hours <br />9.011243e-4 weeks <br />2.073725e-4 months <br />, the plant entered Mode 4 l' and lE31-P002 was not required to be operable.
On April 18, 1990, with the plant in Mode 4, C61.again per' formed PM task PCILDW001 on lE31 P002. At this time, the sample panel was de-energized L
for performance of the PM task. The technician did not replace the filter paper during this task because he noted the take-up reel had not ,
collected any filter paper and the roll of filter paper on the feed spool was almost full. At this point the technician did not question the
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< -unc w.mn p operability.of the sample panel since-it was found in a de energized.
status and was not required to.be operable. I On April 22, 1990, at approximately 1850 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br />, the plant entered Mode 2, and 1E31-P002 was again energized in accordance with the Mode 2 startup- ,
checklist.
On April 27, 1990, at approximately 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, with the plant in Mode 1 at approximately seventy percent power, while again per' forming PM task PCILDW001, the C&I technician noted the filter paper had not moved since the last performance of PCILDWOO1 on April 18, 1990 In response to this finding, the technician immediately informed his supervisor of the filter paper movement problem. The supervisor notified the Shift Supervisor
.(SS) of the problem at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />.
In response to the notification, the SS declared 1E31-P002 inoperable and' directed the drywell atmosphere be manually sampled and analyzed at least ,
once per twenty-four hours in accordance with the. ACTION of Technical Specification 3.4.3'.1. The SS further directed the PM task be completed
.and proper operation of'the filter paper be ensured prior to closing the panel.
L The technician completed the PM task and verified proper filter paper L movement.by. momentarily operating the paper drive mechanism in fast speed ,
l to ensure proper take up on the take-up reel. The technician then I
shifted the drive mechanism to normal (slow) speed and marked the paper.
Approximately six hours later, a C&I technician again verified proper filter paper movement by noting the mark on the paper and the distance l the paper had moved. (The filter paper drive mechanism consists of two l motors mounted side by side in a single housing. Each motor advances the L filter paper.at a different speed. The paper moves approximately 1.5 ,
- inches per hour in normal speed and approximately 6 inches per minute in j fast speed.)
No automatic or manually initiated safety system responses were necessary to place the plant in a safe and stable condition. No other equipment or components were inoperable at the start of this event such that their inoperable condition contributed to this event, i
CAUSE OF EVENT The cause of this event is attributed to equipment failure.
Maintenance Work Request (HWR) D15183 was initiated on April 30, 1990, to investigate 1E31-P002 and determine if a mechanical failure had caused the filter paper drive mechanism.to fail. On May 1, 1990, 22,'*"" ~~ .o m i. ..um.4.
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troubleshooting in accordance with the MWR identified a loose set screw on the normal speed gear train of the filter paper drive mechanism had allowed'one gear to slip-out of alignment on its shaft.' This resulted in an insufficient amount of gear engagement to ensure-continuous, reliable ,
operation of the normal speed gear drive assembly, t CORRECTIVE ACTION .I The gear that had slipped out of alignment was realigned and the set ,
screw was tightened. The filter paper drive mechanism war reassembled and filter paper was replaced in accordance with PM task PCILDW001.
Proper paper movement was verified at both. normal and fast speeds and the
-sample panel was restored at 2159 hours0.025 days <br />0.6 hours <br />0.00357 weeks <br />8.214995e-4 months <br /> on May 3, 1990.
PM task PCILDW001 has.been revised to require inspection of the gear assembly for proper gear engagement and tightness of set screws, and to provide better direction on verifying proper filter paper movement.
As currently configured, the sample panel must be partially disassembled p to verify filter paper is moving properly. For this reason, -II will-investigate methods to ensure proper operation of the filter paper drive mechanism without requiring disassembly of the sample panel. This investigation is scheduled to be completed by August 31, 1990.
ANALYSIS OF EVENT ;
This event is reportable under the provisions of .10CFR50.73(a)(2)(1)(B) ;
because the plant was operated in a condition prohibited by Technical j Specification 3.4.3.1.
The length of time the filter paper had not been moving cannot be determined, however, the amount of filter paper on the take-up reel ;
provides sufficient indication that the sample panel had been inoperable during some of the times when it was required to be operable. These times were April 7, 1990 at 1537 hours0.0178 days <br />0.427 hours <br />0.00254 weeks <br />5.848285e-4 months <br /> until April'15, 1990 at 0545 hours0.00631 days <br />0.151 hours <br />9.011243e-4 weeks <br />2.073725e-4 months <br />, and April 22, 1990 at 1850 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br /> until' April 27, 1990 at 1400 )
hours when the SS was notified of the condition and he directed drywell atmosphere be manually sampled and analyzed at least once per twenty-four hours.
The sample panel was restored to operable status at 2159 hours0.025 days <br />0.6 hours <br />0.00357 weeks <br />8.214995e-4 months <br /> on May 3, 1990.
Analysis of the safety consequences and implications of this event indicates this event was not nuclear safety significant. At the time of the event, other instrumentation was available and operable to provide both continuous indication and activate alarms in the Main Fonu seaa e U S.0Po'1986 0 624 636/455
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0l 0 0l5 0F 015 1 xt 4, m = nac s m.w nn Control Room (MCR) if-unidentified reactor coolant leakage had exceeded specified limits, This instrumentation included the drywell air cooler condensate flow rate monitoring system, drywell atmosphere gaseous radioactivity monitoring system and the drywell sump flow monitoring system. During this event.there was no unidentified leakage.
ADDITIONAL INFORMATION Drywell fission products monitor lE31-P002 is model number 133D9025G manufactured by General Electric.
No LERs have been initiated at Clinton Power Stc tion fcr similar events, For further information regarding this event', contact S. E. Rasor, Director - Plant Maintenance, at (217) 935 8881, extension.3204, s
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