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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] |
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- 1A5-90(04 09)-LP i 20.220 t ILLIN0/8 POWER COMPANY IP CLINTON POWER STAfl0N. P.O. BOK 678. CLINTON. ILLIN0l$ $1727 l
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April 9, 1990 l i
l 10CFR50.73 [
l, Docket No. 50-461- -
U.S.' Nuclear Regulatory Commission o' Document Control Desk
- Washington, D.C. = 20555 l - Subj ect:- Clinton Power Station - Unit 1 Licensee Event Reoort No; 90 003-00 l
-i
.. ?
Dear Sir:
= '
Please find enclosed Licensee Event Report No. 90 003 00:- i Inonerability of 13 Ro'memount Transmitters due to ' loose Covers and a , *
(; Broken Neck Seal. This report is being submitted in4 accordance.with:the -r requirements of.10CFR50.73. .;
Sincerely yours, l
w .14.u ,
F. A. Span jenbe 'III. ;
Manager Dicens g and S fety-DAS/alg l
Enclosure .,
cc: NRC Resident Office :
NRC Region III, Regional Administrator i INPO Records ' Center- t Illinois Department of Nuclear Safety NRC;Clinton Licensing Project Manager i
9004200296 900409
{DR ADOCK 05000461 PDC 1 i
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TITLE tel
, - Inoperability of 13 Rosemount Transmitters due to Loose Covers and a Broken Neck Seal l 'Ev5NT DAYS ISI Lth NUMeth tel REPORT Daft fft OTHth 7 ACILITIES BNv0LV40 IBi M0cTu oAv veAn veAn v iagg,* 6 .
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On March 8, 1990, with the plant.in cold-shutdown, it was determined that 13 safety related transmitters in various systems had been inoperable due to a failure to meet environmental qualification requirernnts. Twelve of the affected transmitters were inoperable because.their housing covers <
were found with torque values less than CPS requires in order to-meet their environmental qualification requirements. The remaining transmitter was inoperable due to a broken neck seal. Seven of these-13 transmitters are required to be operable per the plant's Technical Specifications and four are required to be operable to satisfy the requirements of Regulatory Cuide 1.97 for post-accident monitoring. The remaining two transmitters are provided for monitoring of safety-related systems. The length of time these transmitters were inoperable is indeterminate; however, redundant instrumentation or instrumentation of other parameters remained available to fulfill the safety functions of these transmitters. The operability of these transmitters was restored during the plant shutdown. Additionally, a preventive maintenance task has been generated to periodically _ check the cover torque and neck seal integrity of the 206 environmentally qualified Rosemount transmitters.
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. DESCRIPTION OF EVENT on March 8, 1990, with the plant in cold. shutdown (Mode 4), it was determined that thirteen safety related transmittero [PDT) had been inoperable in various systems due to a failure to meet environmental r qualification requirements. Twelve of the affected transmitters were- 2 ,
inoperable'because their housing covers were. found with- torque values less-than what CPS requires in order to meet their environmental J l qualification requirements. The remaining transmitter was inoperable due i
to a broken neck seal. ,
g On February 12, 1990, the plant was'in Mode 1 (power operation) at }
approximately 100 percent reactor [RCT) power. At approximately 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />,-during a routine plant walkdown, an Illinois Power Company (IP)
Quality Verification (QV)' inspector identified that- the housing cover of L
transanitter 1LT-CH260D-[LT) was loose. This' cover is required _to be tight in order to provide a' seal to prevent noisture from entering the 1 electronics head during Loss of Coolant Accident -(IDCA) conditions.
Transmitter ILT CH260D.is required to be environmentally qualified and is one of twelve transmitters used to measure' wide range-suppression pool level (IK). The'QV inspector initiated a plant condition report and Maintenance Work Request' (HUR) D06747 ' to tighten the housing cover. . -
Because of events unrelated to this report (reference LER 90-001), the plant was placed in' hot shutdown (Mode 3) at 0524 hours0.00606 days <br />0.146 hours <br />8.664021e-4 weeks <br />1.99382e-4 months <br /> on' February 13, '
1990. The plant achioved cold shutdown at 2134 hours0.0247 days <br />0.593 hours <br />0.00353 weeks <br />8.11987e-4 months <br /> on February 13, 1990.
On February 15, 1990, with the plant in cold shutdown, IP determined that a quantitativo check of the environmentally qualified Rosemount transmitters should be performed as a result of the identification of the loose housing cover on ILT-CM260D and because of a similar condition identified in November 1989 which affected the operability of three different transmitters. (Based upon the systems and functions affected, the condition of these three transmitters in November 1989 was determined not to be reportable pursuant to 10CFR50.73.) MWRs'D15049 and D15054 were initiated to check the . cover torque, cover gap, neck seal integrity, and conduit plug installation on the 206 environmentally qualified Rosemount transmitters.. Any loose covers found during these inspections were retorqued to the required 200 inch-pounds. These MWRs were completed during the plant shutdown and the results of these inspections were forwarded to the Clinton Power Station-(CPS) Nuclear. Station Engineering Department (NSED) for evaluation. The'results of the i evaluation performed by NSED are presented below.
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. As a result of the checks performed under the above MVRs, twelve additional transmitters were determined to have been inoperable because they did not meet their environmental' qualification requirements (eleven because of loose housing covers, and one due to a broken neck seal).
These twelve additional transmitters consisted of 1833-N024A and D [FI)
(which provide reactor recirculation [AD) loop "B" flow input to two channels of the Reactor Protection System (RPS) [JC) flow biased high thermal power scram actuation logic), ILT-CM030 and ILT-SM013 [LT) (which
[' provide suppression pool level input to the Division I Suppression Pool Makeup [BT) system' actuation logic), IE12 N062A [PT) (which provides- ,
- containment ~ [NH) pressure input to the Division I' actuation logic for the l , containment spray function of the Residual Heat Removal (RHR) [BO) ,
system), 1PT CM035 [PT) (which provides input to a containment pressure recorder [PR) in the main control room), IPT-CH257 [PT) (which provides input to a high range containment pressure recorder in the main control-room), 1PT-CM064 [PT) (which provides input to a drywell pressure recorder in the main control room), IE12 N015B [FT) (which provides input ,
to the RHR loop *B" flow indicator [FI) in the main control room), 1C41-N004 [PT) (which provides input to the Standby Liquid Control [BR) system i pump [P) discharge header pressure indicator [PI) in the main control' .
room), IPT-IA081 [PT) (which provides input to the Division.II Automatic ,
Depressurization System (ADS) [RV) backup air bottle [LE) header pressure indicator in the main control room), and IPDT-HC052 [PDT) (which provides input to a Containment and Drywell Atmosphere Mixing [BB) system compressor [ CMP) differential pressure indicator [PDI) in the main i control room). j These conditions affected the operability of at least one train or ;
t channel in multiple systems needed for safe shutdown of the plant and to ;
mitigate the consequences of an accident. However, based upon the :
results of the inspections performed in February 1990, redundant !
instrumentation or instrumentation of other parameters for fulfilling each of these safety functions remained available. This determination was made on March 8, 1990 following NSED review of the results of the -
inspections performed under MWRs D15049 and D15054. The affected transmitters were not required to be operable per the plant's Technical Specifications at the time that these conditions were identified (i.e.,
cold shutdown); therefore, no action per the plant's Technical Specifications was required to be taken.
In addition to loose housing covers, other conditions were identified for other transmitters during the performance of HWRs D15049 and D15054 that were subsequently determined not to affect transmitter operability.
These conditions consisted of three additional transmitters with broken neck seals and two additional transmitters with missing conduit seals.
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. 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.
CAUSE OF EVENT L
The root cause of these conditions is indeterminate. However, the
[ corrective action taken following the identification of loose transmitter housing covers in November 1989 was inadequate in that only a qualitative check of cover tightness (i.e., hand-tight) was performed. Further-investigation into the root cause of the loose housing covers is being performed. This investigation will include a review of previous a
maintenance and testing performed on the affected transmitters which required removal of the housing covers. Additionally. the possibility of.
, housing covers loosening over time is being investigated. If any L significant information is determined from this review, a supplemental report will be provided.
CORRECTIVE ACTION As noted above, the corrective action taken in November 1989 was-determined to be inadequate to prevent recurrence. Subsequent.to that event, and due to other actions that'IP has taken to enhance the corrective action program in general, CPS Procedure 1016.01, CPS
- j. Condition Reports, has been revised to require a more structured approach l
to co,rrective actions. Specifically, the procedure now requires correctivo action plans to be approved by the appropriate management staff member with signature agreement of groups responsible for performing tasks in the corrective action plan. Further, Maintenance and Quality Engineering management personnel were briefed on this event and lessons learned.
Loose transmitter covers that were identified during the performance of MWRs D15049 and D15054 were retorqued to the required 200 inch-pounds !
during these checks. The scope of MWRs D15049 and D15054 included 206 environmentally qualified Rosemount transmitters. MWRs were initiated to-rework the four neck seals that were found broken. These MURs have been completed. The two transmitters that were found with missing conduit seals will be deleted from the equipment qualification program since they are associated with the steam condensing mode of the RHR system which is not used at CPS and this RHR operating mode is being deleted from the CPS design.
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. The current surveillance procedures reference the maintenance procedures i which require transmitter housing covers to be torqued to the required 1 200 inch. pounds any time they are removed (these covers may be removed
[ during transmitter calibration). In order to determine if the covers are ;
becoming loose over time, an MUR has been initiated to check the l- breakaway torque of-ten transmitters approximately three months after l
having been torqued to the required 200 inch-pounds. Five of these ,
transmitters will be selected from those that were found with a breakaway ;
torque less than 200 inch pounds during the performance of MWRs'D15049 and D15054'and the: remaining five will be selected from those that were found tight. Similarly, ten different transmitters will be checked approximately six months after having been torquod to the required-200 ;
inch. pounds. Further, a preventive' maintenance task has been initiated
- to verify the cover torque and neck seal integrity of the 206~
environmentally qualified Rosemount transmitters. The initial frequency for this preventive maintenance task is 18 months. . The results of the checks performed after.three months'and six months will be used, as ,
i - appropriate. to revise -the initial frequency of this preventive i
maintenance task. Additionally .an MWR has been. initiated to apply ,
i " Torque Seal" to the neck seals of the 206 environmentally qualified r l Rosemount transmitters. This will facilitate-future neck seal integrity inspections.
ANALYSIS OF EVENT This event is reportable under the provisions of 10CFR50.73(a)(2)(vii)
I because this condition affected the operability of at least one train cr channel in multiple systems required for safe shutdown of the-plant and +
to mitigate the consequences of an accident.
This event is not considered to be safety significant. Seven of the l thirteen inoperable transmitters identified (1B33-N024A and D, ILT-CM030, ILT-SM013, IE12-N062A, IPT-CM035, and 1PT-CM064) are required to be~
l operable by the' plant's Technical Specifications. -Four additional transmitters (1E12-N015B, 1PT-CH257, 1PT-IA081, and'1C41-N004) are required to be operable in order to satisfy the requirements of Regulatory Guide 1.97 for post-accident monitoring capability. The remaining two transmitters (1PDT-HC052 and 1LT-CH260D) are provided for monitoring of safety-related systems. Failure.of these thirteen transmitters alone would not have prevented any safety function from being performed. Based upon the results-of the' inspections performed in February 1990, redundant instrumentation or instrumentation of other parameters for fulfilling each of these safety functions remained available.
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ven* #**MP iiii2 Clinton Power Station o l5 yo go yo dg { 6g l 90 O0 0l6 y O'; 0l 3 g or 0l 7 mi a -* w =. -mc e mew nn s The length of time _ that this condition had existed is indeterminate. The affected transmitters.were not required to be operable per the plant's Technical Specifications at the time these conditions were identified. -
Operability of.the 206 environmentally qualified Rosemount transmitters ,
was restored prior to.startup from the March 1990 plant outage.. (
ADDITIONAL INFORMATION The thirteen environmentally qualified' transmitters -identified above are model 1153 transmitters manufactured by Rosemount. .Inc.
CPS has not previously reported inoperability of Rosemount 1153 transmitters due to loose housing covers, or broken neck seals.
For further information regarding this event, contact T. R. Chitester, ,
Director-Design and Analysis Engineering, at (217) 935-8881, extension '
, 3981.
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