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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
[Table view] |
Text
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-20.220
' /LLINDIS POWER COMPANY CLINTON PCMER STATION. P.O. BOX 678. CLINTON, ILLINOIS 61727 5
January 8, 1990 10CFR50.73 Docket No. 50-461 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Clinton Power Station -l Unit 1 Licensee Event Report No. 89-039-00
Dear Sir:
Please find enclosed Licensee Event Report No. 89-039-00:
Licensed Onerator Misinterpretinc a Note in a Surveillance Procedure Results in Failure to Demonstrate Operability of Hinh Pressure Core Sorav System Suction Valves. This report is being submitted in accordance with the requirements of 10CFR50.73.
Sincerely yours, b /WA D. L. Holtzscher Acting Manager - -i Licensing and Safety
!' RSF/krm Enclosure cc: NRC Resident Office NRC Region III, Regional Administrator INPO Records Center Illinois Department of Nuclear Safety NRC Clinton Licensing Project Manager I
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[Q' 9001180394 900108 .
6 PDR ADOCK 05000461 s PDC
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- N C feem $$$ . U S. NUCLE 431EtuLATORY COMMtsSION
, APPROVED OMO NO. 2190410e LICENSEE EVENT REPORT (LER) 'ka's ersi m 81CILITY NAME (1) DOCEE T NUMBER (2) P AGE 63, ,
Clinton Power Station 0 l5 J 01010 l4 l 611 1 lOFl 015 Licensed Operator Misinterpreting a Note in a Surveillance Procedure Results in Failure to Demonstrate Operability of High Pressure Core Spray System Suction Valves EVENT DATE (61 LER NUMeER 461 REPORT DATE (71 OTHER F ACILITIES INVOLVED 15)
MONTH DAY YEAH YEAR S'gQ ', * ' 7j$ MONTH DAY YEAR F AC'LITY N AMES DOCKEY NUMBERi$1 None 0l6l0l0l0] ; l
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" 8 'O 3 20.402m 20 40st.> so.73.H2 H.: 73.7 t w POWER 20 406toHIH4 50.36 t.10 4 80.73(aH2Hvl 73.11 t.)
'!E0 ' Ol010 20 40st,iti Hiin so.3ei.H2 so.73i.H2Hvas OTHE R ts,.cur <a Aa,,r.c.
20 406toH1 Hell [ 50.734 ell 2Hil 50.73iaH2ilvaiHAl Jif6Al to 406teH1Hiv) 60.73(a H28till 60.73teH2HvedHel 20 400sH1Het 50.736sH2Helil 60,73te42Hal LICENSEE CONT ACT FOR THl$ LER (12)
NAME TELEPHONE NUMBER AREA CODE D. R. Morris, Director-Plant Operations, extension 3205 21117 91315I-I8l8f811 COMPLETE ONE LINE FOR EACH COMPONENT F AILURE DESCRISED IN TH18 REPORT (131
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,s I I I I I I I I I I I l l l l l I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED H4: MONTH OAY YEAR
$UguisasON Y ES III ,es, comporte EXPECTEO Sug4*lS$10N DA TEI NO l l l to:T u CT<o,. ,, u m ,,u.,,,..,,,... .,,,,,,,,, r. <,,,,,,,,,,,a,,a,,,0 1
- On December 12, 1989, with the plant in HOT SHUTDOWN, the Operations Shift Supervisor (SS) was notified that three High Pressure Core Spray (HPCS) system suction valves had not been tested within the maximum surveillance time interval permitted by Technical Specification 4.0.2.b to demonstrate that the valves met operability requirements. In ,
response, the SS declared the three valves and the HPCS system inoperable and immediately initiated the surveillance test to verify operability of the three valves. The surveillance test was completed with satisfactory results. The cause of this event is attributed to a utility licensed operator misinterpreting a note in a surveillance procedure. This resulted in the Assistant Shift Supervisor marking the surveillance sections associated with the three valves as not applicable. Corrective action for this event includes revising appropriate surveillance procedures to delete the note that was misinterpreted, including a description of this event and the findings of the associated investigation in the Operations " night orders", briefing Operations shift crews on the importance of reviewing completed surveillance packages thoroughly and accurately to ensure that applicable requirements are met, and ensuring that. procedures are reviewed for problems such.as human factors concerns. i l
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NoC form 364 E1831 1
EC Psam,3eeA
- . U S. NUCLE 13 RETULAfoRY COMMISSION
.. LICENSEE EVENT Ri PORT (LER) TEXT CONTINUATION uenoveo oue No. siso-o*
pinto.w f ACILif v NAME Hi DOCKET NUM8tR GI LtR NUM8th (6) l'AOS (3) t vtAR e' 3'$ ^4 .C.N,N Clinton Power Station 0 l5 l0 l0 j o l4 l6 l1 8l9 -
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DESCRIPTION OF EVENT on December 12, 1989, the plant was in Mode 3 (HOT SHUTDOWN), at 478 !
degrees Fahrenheit and 570 pounds per square inch gauge, and a planned maintenance outage was in progress. At 1405 hours0.0163 days <br />0.39 hours <br />0.00232 weeks <br />5.346025e-4 months <br />, the Operations Shift Supervisor was notified that three High Pressure Core Spray (HPCS) system (BG) suction valves [V) had not been tested within the maximum surveillance time interval permitted by Technical Specification 4.0.2.b-to demonstrate that the valves met operability requirements.
On November 3, 1989, surveillance procedure 9051.02, "High Pressure Core l Spray (HPCS) Valve Operability Test," was performed in accordance with j Technical Specifications 4.0.5 and 4.6.4.3 to obtain Inservice Inspection-(ISI) data. The Assistant Shift Supervisor incorrectly marked sections 8.1.2 through 8.1.6 of this surveillance as not applicable and, as a result, operators did not perform these sections. Procedure sections ;
. 8.1.2 through 8.1.6 provide instructions for monthly stroke time testing l of valves 1E22-F001 and 1E22-F015, and for monthly verification of' the l torque value required to open the disc of check valve 1E22-F016. Since !
these procedure sections were not performed, valves 1E22-F001, HPCS suction from the Reactor Core Isolation Cooling (RCIC) system (BN) storage tank [TK]; 1E22 F015, HPCS suction from the suppression pool; and l
1E22 F016 HPCS suppression pool suction check valve, were not tested'.
On December 3, 1989, at 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br />, the surveillance interval including the allowable extension specified in Technical Specification 4.0.2.b expired for demonstrating operability of valves 1E22-F001, 1E22 F015, and 1E22-F016. The surveillance interval of this Technical Specification <
specifies that "the combined time interval for any three consecutive surveillance intervals shall not exceed 3.25 times the specified ,
surveillance interval." The failure to perform surveillance testing of I the three valves within the specified time interval constitutes a failure to meet the operability requirements,for the Limiting Condition for '
Operation.
On December 12, 1989, while reviewing ISI data compiled for November, the engineering ISI coordinator noted that test data for valves 1E22-F001, 1E22-F015, and 1E22-F016 had not been provided. The engineering ISI coordinator informed the operations surveillance coordinator that no data was provided for the three valves. The operations surveillance coordinator immediately notified the Operations Shift Supervisor that the three valves had not been tested.
On December 12, 1989, at 1405 hours0.0163 days <br />0.39 hours <br />0.00232 weeks <br />5.346025e-4 months <br />, the Operations Shift Supervisor declared valves 1E22-F001, 1E22-F015, and 1E22-F016, and the HPCS system-inoperable and immediately initiated surveillance 9051.02 to verify operability of the three valves. At 1603 hours0.0186 days <br />0.445 hours <br />0.00265 weeks <br />6.099415e-4 months <br />, the surveillance was completed with satisfactory results and the valves and the HPCS~ system were declared operable.
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NRC Fe.m Se6A U.S. NUCLE 2.3 C.E!ULATORY COMMISSION
+
' LICENSEE EVENT REPORT (LER) TEXT CONTINUATION s.eenovio oMe no. mo-om
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clinton Power Station 0 l5 l0 l0 l0 l4 l 611 8l 9 --
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0l0 0 l3 OF 0 l5 svi a mm ma n nene. a. ne-w ww rw nwonm No automatic or manually initiated safety system responses were necessary to place the plant in a safe and stable condition. No equipment or components were inoperable at the start of this event such that their inoperable condition contributed to this event.
CAUSE OF EVENT The cause of this event is attributed to a utility licensed operator misinterpreting a note that preceded section 8.1.1 of surveillance procedure 9051.02. This resulted in the Assistant Shift Supervisor marking applicable sections of surveillance 9051.02 as not applicable.
The note preceding section 8.1.1 of surveillance procedure 9051.02 .
indicates that section 8.1.1 is only performed in conjunction with !
section 8.3 of surveillance procedure 9051.01, "HPCS System Pump Operability." Sections 8.2 and 8.3 of surveillance procedure 9051.01 each provide a different method for demonstrating HPCS pump operability and each provide instructions for testing different valves. Depending on which of these sections is used to demonstrate HPCS pump operability, section 8.1.1 of surveillance 9051.02 may or may not be applicable because the method of testing used in surveillance 9051.01 determines which valves must be tested in surveillance 9051.02.
On November 3, 1989, while preparing to perform surveillance 9051,02, the Assistant Shift Supervisor incorrectly interpreted the note which preceded section 8.1.1 as being applicable to all of section 8.1 of
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l surveillance 9051.02. Since Section 8.1.1 of surveillance procedure 1 9052.02 was not applicable to the surveillance performed on November 3, i l 1989, the Assistant Shift Supervisor marked all of section 8.1 (sections !
8.1.1 through 8.1.6) as not applicable. Additionally, another Assistant Shift Supervisor who reviewed the completed surveillance 9051.02 did not I recognize that applicable sections of the surveillance were marked as not l applicable. l The formatting of procedure 9051.02, section 8.1, contributed to the 1
Assistant Shift Supervisor misinterpreting the note preceding section 8.1.1.
CORRECTIVE ACTION i
The Assistant Shif t Supervisor who caused this event understands his error in misinterpreting the note in procedure 9051.02; therefore, no specific corrective action was necessary with respect to this individual.
However, Operations shift crews will be briefed on the importance of f reviewing completed surveillance packages thoroughly and accurately to ensure that applicable requirements are met. This briefing is scheduled to be completed by January 29, 1990.
NRC FOXM 366A *U.S. CFog 1986+520 589 00070 19 83)
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IlRC Fum 364A U.S. NUCLE A3 C.EIULATORY COMMISE80N LICENSEE EVENT REPORT (LERI TEXT CONTINUATION unoveo oue no. 3 iso-oio4 EXPIRES: 0/31/8B F ACILi1Y NAMf. (H DOCRET WAISER (28 LER NUM8th (6) . PAGE (3) m.w
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TEXT M more were e regwed, use aMee is/ NRC form J0841,11171 l
Surveillance procedure 9051.02 will be revised to delete section 8.1.1 and the note preceding that section. Surveillance procedure 9051.01 will be revised to include the valve testing requirements from section 8.1.1 of procedure 9051.02. These revisions are scheduled to be completed by February 9, 1990, j
A description of this event and the findings of the investigation of this event were included in the Operations " night orders" on December 26, 1989, to emphasize to shift crews that closer attention must be given to ensure correct marking of procedure sections as not applicable.
Additionally, IP is taking actions to ensure that procedures are effectively reviewed for problems such as human factors concerns. IP is revising the CPS procedure writer's guide,. administrative procedure 1005.01, " Preparation, Review, Approval, and Implementation of and Adherence to Station Procedures and Documents", to incorporate applicable methodology and techniques obtained from the Institute of Nuclear Power Operations (INPO) procedure writer's guide and from procedure programs of other utilities identified by INPO as having good procedures. IP has also established a centralized procedure group consisting of various disciplines. This group is responsible for developing and revising procedures, performing biennial procedure reviews, and incorporating temporary procedure changes into plant staff procedures. This group will be trained on the use of the reviJed procedure writer's guide. Plant staff procedures will be reviewed for human factors concerns during the l normal revision process and during biennial reviews.
1 ANALYSIS OF EVENT This event is reportable under the provisions of 10CFR50.73(a)(2)(1)(B) because of the failure to meet the surveillance interval specified by Technical Specification 4.0.2.b.
The provisions of Technical Specification 4.0.2.b were not met from 1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br /> on December 3, 1989 to 1603 hours0.0186 days <br />0.445 hours <br />0.00265 weeks <br />6.099415e-4 months <br /> on De'cember 12, 1989.
l l Assessment of the nuclear safety consequences and implications of this event indicates that this event was not safety significant for existing
- or other plant conditions. This assessment is based on the completion of-
! sections 8.1.2 through 8.1.6 with satisfactory results at 1603 hours0.0186 days <br />0.445 hours <br />0.00265 weeks <br />6.099415e-4 months <br /> on December 12, 1989.
ADDITIONAL INFORMATION l
l No components failed during this event.
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[ LERs89-015 00 and 88-031-00 discuss similar licensed operator errors involving the failure to implement surveillance procedure steps.
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" U.S. NUCLEA3 EE1ULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION uesoveo ove No. mo.eio8
. EXPIRES: t/31/0B FJ.CILITV NAME (1) DOCKET NUMSLR (2) LER NUM8th (61 PAGE (3) st a AL p;,
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p ygp. s Clinton Power Station 0l5l0jojol4l6l1 8l9 -
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010 0l5 OF g l3 TEXT M awe spece e sewed, use emnons/ NAC Fonn afENsf I1M For further information regarding this event, contact D. R. Morris, Director - Plant Operations at (217) 935 8881, extension 3205.
NRC FOKM M4A *D.$. GP0: 1988 520-509 00070 G $3)
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