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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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November 1, 1989
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10CFR50,73 j L ;
I Docket No. 50 461
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U.S. Nuclear Regulatory Commissinn l Document Control Desk
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Subject:
Clinton Power Station . Unit 1 .,
Licensee Eventlecort No. 89@i,QQ
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Dear Sir:
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Tlease find enclosed 1Acenree Event Report No,89-034 00:
Lack of. Training. Personnel Irror'and Inadecuagg Con.munieggiqng,.) Ray 3 ,
,(n Failure to Verify Precess Radj,gri.on.. Monitor Ooerobility and to Meet [
Iechnical Soecification Recuirements, This report is being submitted in !
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accordance with the requirements of 10CT1tSO.73. ;
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Sincerely yours, 5 ). W D. L. Holtzscher Acting Manager . -
Licensing and Safety TSA/kra ;
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- ' Enclosure [
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l cc: NRC Resident Office !
L NRC Region III, Regional Administrator i INFO Records Center ;
Illinois Department of Nuclear Safety NRC Clinton Licensing Project Manager i
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- On October 4, 1989, a Radiation Protection Shift Supervisor (RPSS) u discovered that the in service Station Heating, Ventilatinh and Air Conditioning (HVAC) Exhaust Stack Process Radiation Monitor (PRM),
j ORIX PR001 had not been verified as operable. This resulted in a failure l to meet the Limiting Condition for Operation for Technical Specification l (TS) 3.3.7.12. This TS requires that one Station HVAC Exhaust Stack PRM i be operable at all times. At 0826 hours0.00956 days <br />0.229 hours <br />0.00137 weeks <br />3.14293e-4 months <br />, PRM ORIX PR002 was removed from
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service and PRM ORIX PR001 was placed in service. The Radiation ,
1 Protection (RP) technician (tech) transferring the monitors did not perform all of the checks required to verify that PRM ORIX PR001 was ,
operable after piccing it in service. Specifically, the RP tech performed a channel check on the monitor but did not verify flow.
Therefore, the PRM was inoperable. This event was caused by lack of training, personnel error and inadequate communications. The RP tech was not fully qualified and the RPSS failed to direct the RP tech to use applicable procedures when placing PRM ORIX FR001 in service. Corrective l actions include reminding appropriate RP personnel of the need to use and l follow procedures, and counselling RP Shift Supervisors on the need to ensure techs are qualified and on the need to review and status activit.ies affecting RP.
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DESCRIPTION OF EVENI I On October 4, 1989, t.he plant was in Mode 1 (POWER OPERATION) and the reactor [RCT) was at eighty five percent power. On the morning of October 4, 1989, Chemistry personnel contacted the Rad!ation Protection ,
(RP) technician assigned as the Area / Process Radiation Monitor (AR/PR) l operator and requested that Radiation Protection personnel remove the in-service Station Heating, Ventilation, and Air Conditioning (HVAC) Exhaust Stack Process Radiation Monitor (PRM) [IL), ORIX PR002, from service and place the redundant monitor [ MON), ORIX PR001, in service. This monitor ;
transfer is performed weekly to ensure the monitors are used equally and
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to enable Chemistry personnel to replace the ffiters (FLT) in the ;
monitors in accordance with Technias,1 Sp9eification Table 4.3.7.12 1. ,
The technician assigned as the AR,'PR operator had rot previeur',y ,
performod a monitor exchange and therefore requastod direut'on frosn the :
c'ay shif t 'u.diation Protectica Shif t Supetvisor (RPSP.,. The RPSS j explained to the technician the wethodology for removing monitor ,
ORIX PR002 from service ano placing it in "starJbya and the et.hodology.
for placing redundmot monitor ORIX PR001 in service ( normal") . The RTSS directed the technician to note the coepletion of the honLter exchange in i the RP log. The exchange van cogleted at 0826 hours0.00956 days <br />0.229 hours <br />0.00137 weeks <br />3.14293e-4 months <br />. After completing the exchange, the RP techn! clan performt,d s channel [CHA) check on monitor ORIX PR001 by comparing its indication with the last indication of inonitor ORIX PR002. This check verified that monitor ORIX PR001 was in service and was providing accurate data to the Central Control Terminal (CCT) in the RP office.
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At 1944 hours0.0225 days <br />0.54 hours <br />0.00321 weeks <br />7.39692e-4 months <br />, during review of completed surveillance procedure 9911.24, "AR/PR Shiftly/ Daily Surve111ances", the second shift RPSS noted that not all checks required to verify operability of monitor ORIX PR001 were ,
doc'iment ed. :
The RPSS di'tected the second shift RP technician assigned as the AR/PR ,
operator to perform surveillance 9911.24 to verify that monitor ORIX. I PR001 was operable. In accordance with surveillance 9911.24, the RP technician performed a channel check and a sample flow indicator [FI) check. Surveillance 9911.24 was completed at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> with i satisfactory results. (A communications check, which is required to be ,
performed once each shift, was documented as having been completed at '
0741 hours0.00858 days <br />0.206 hours <br />0.00123 weeks <br />2.819505e-4 months <br /> and 1555 hours0.018 days <br />0.432 hours <br />0.00257 weeks <br />5.916775e-4 months <br />.) 6 Since the checks to verify the operability of monitor ORIX PR001 were not performed within one hour of placing monitor ORIX PR001 in service, the Limiting Condition for Operation (LCO) for Technical Specification 3.3.7.12 was not met. Technical Specification 3.3.7.12 requires that one station HVAC exhaust PRM be operable at all times. Operability of ORIX.
PR001 was not verified until 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on October 4, 1989, 1
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Technical Specification 3.3.7.12 permits a Station INAC Exhaust Stack PRM to be placed in an inoperable status for up to one hour for the purpose .
of performing sutveillances. Monitor ORIX PR001 was placed in service at i 0826 hours0.00956 days <br />0.229 hours <br />0.00137 weeks <br />3.14293e-4 months <br />, therefore the LCO for Technical Specification 3.3.7.12 was not met from 0926 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.52343e-4 months <br /> until 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on October 4, 1989.
Ne automatic or manually initiated safety system responses were necersary to place the plant in a safe and stable condition. No other eyvipent o; conponents were inoperabic at the start of this event such that their ,
inoperable condition contributed to this event. l 2 disl Ol' Eff.EI.
The cause of the event is attmibuted to inck of training, personnel artor and inadequatc comtaunications, g Tha RP technician assigned as the AR/PR operator was not fully qualified
, I. for that posit 3on becauce he had not completed all of the required training. He was horever, considered to have sufficient experience and to have demonstrated a level of proficiency sufficient to perform AR/PR i
operator activit.as under the direct supervision of fully qualified personnel.
i The RPSS failed to direct the RP technician to use the procedures governing the operation and testing of the AR/PR monitors when removing monitor ORIX PR002 from service and placing monitor ORIX PR001 in service. Radiation Protection procedure 7410.75, ' Operation of Digital AR/PR Monitors" provides instructions for removing monitors from service, for starting monitors, and for returning monitors to serrice.
Surveillance procedure 9911.24 provides instructions for performing the checks required to verify monitor operability. Neither of these procedures was utilized when transferring the Station INAC Exhaust Stack PRMs and verifying their operability.
Contributing to the failure to meet the LCO for Technical Specification 3.3.7.12 was the lack of involvement of the RPSS in the monitor transfer process. The RPSS was aware that the monitor transfer was to occur because the evolution had been discussed at the Operations shift I
turnover. However, the RPSS did not discuss the monitor transfer with RP l
personnel at the RP shift turnover. The RPSS did not follow up to ensure
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the monitor transfer had been completed satisfactorily.
In addition to performing AR/PR operator duties, the RP technician was acting as the on duty RP office technician performing routine RP office work. The RP technician was required to perform the additional duties because of the high volume of routine RP office work required to be performed in the first few hours of each shif t. Performing the duties of l
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both positions adversely affected the RP technician's performance of his AR/PR operator duties.
Procedure 7410.75 was reviewed following the event and it was determined that even if the applicable proceditres had been used when removing monitor OR1X PR002 from service and placing monitor ORIX PR001 in '
service, all of the checks required to verify operability may not have been performed. Procedure 7410.75 did not address the requirement to ,
perform surveillance 9911.24 when placing AR/PR monitors in service.
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Procedure 7410.75 did not require that the Operatiene Shif t Supervisy r t e notified of monitor operability onu. the AR/PR monitors reyttired te acet a
Technical Specifications were placed in service. Operationa petronnel '
were natified that n.onitor ORIX PR001 was placed in service and that. the ,
monitor was op3 rating properly. Operations personnel believed that when -
RP pers onnel stated tt'at monitor ORIX PR001 was operating properly , i checks required to meet the requirements of Technical Specification 3.3.7.12 had been completed with aatisfactory rvsults.
G,RRECTIVE ACTIQNf3 Radiation Protection Shift Supervisors have been counselled on the need I to ensure that RP technicians are fully qualified for the positions to ,
which they are assigned. The Radiation Protection Shift Supervisors were also ceunselled on the need to review the Daily Activity Schedule for
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upcoming activities which involve or affect Radiation Protection, and on the need to discuss the status of these activities at the RP shift turnover meetings. ,
A night order was issued to appropriate Radiation Protection personnel regarding: the need to use procedures, particularly when placing monitors in service from a " standby" condition; the checks required to be performed in accordance with surveillance 9911.24; and the requirement to '
notify Operations personnel when changing the status of monitors meeting Technical Specification requirements.
A night order was issued reminding appropriate Radiation Protection personnel that whea assigned to a position it is their responsibility to ensure that they meet the requirements of that position prior to assuming any additional duties or positions. This ensures that requirements are met, while at the same time providing for flexibility and reassignment of I personnel.
Proceduren 7410.75 and 9911.24 have been revised to include the steps required to be completed to verify AR/PR monitor operability, and to include a step requiring that operations personnel be notified when a monitor is placed in service and when surveillance procedure 9911.24 has
been satisfactorily completed.
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i ANALYSIS OF EVENT This event is reportable in accordance with the provisions of ;
10CFR50.73(a)(2)(1)(B) due to operation prohibited by Technical I i
Specifications. The 140 for Technical Specification 3.3.7.12 was not met from 0926 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.52343e-4 months <br /> until 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on October 4, 1989.
Aasessment of the nuclear safety consequences and inp11 cations of this i event indicated that this event was not safety significant for existing ,
or other p?. ant conditions. Cumpletion of survet11ance 9911.24 with satisfactory results indies.tes thet.sonitor ORIX.P3001 ess a.ccurately monitoring effluent through the Common HVAC Stack, e&D.LT12ML 1NNP. MAT 10N l
',, liu 88 020 00 discusse(. ttn failure to ensure that a liquid efaturnt .
l roonitor vr.e placed 1,1 an operat,le status prioY to bi-ing dsclared 1 operable. The cause cf this event wars vague coinanications bacween ;
Operations and Rad 16 tion Protection ;eis.onnel regarding whether the annitor was in "normala or " standby'.
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For further information regarding this event, contact D. W. Miller, Director Plant Radiation Protection, at (217) 935 8881, extension 3313.
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