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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217A1691999-09-22022 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-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-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-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-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-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 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-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 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-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 U-602952, Part 21 Interim Rept 21-98-001:ITT Barton Model 580A Series Dp Indicating Switch Operating Force Concerns.Initially Reported on 980107.Evaluation of Subj Issue Will Be Completed by 9805301998-03-0606 March 1998 Part 21 Interim Rept 21-98-001:ITT Barton Model 580A Series Dp Indicating Switch Operating Force Concerns.Initially Reported on 980107.Evaluation of Subj Issue Will Be Completed by 980530 U-602939, Part 21 Interim Rept 21-97-060 Re Sentry Equipment Corp Commercial Grade Dedication Program Deficiencies.Evaluation of Issue Will Be Completed by 9804041998-02-17017 February 1998 Part 21 Interim Rept 21-97-060 Re Sentry Equipment Corp Commercial Grade Dedication Program Deficiencies.Evaluation of Issue Will Be Completed by 980404 U-602932, Interim Part 21 Rept 21-97-059 Re Several Discrepancies Found During Receipt Insp of Three safety-related W Dhp Circuit Breakers.Sent Subject Circuit Breakers to Nuclear Logistics Inc for Refurbishment1998-02-13013 February 1998 Interim Part 21 Rept 21-97-059 Re Several Discrepancies Found During Receipt Insp of Three safety-related W Dhp Circuit Breakers.Sent Subject Circuit Breakers to Nuclear Logistics Inc for Refurbishment U-602925, Part 21 Rept 21-97-058 Re Oil Leaking Around Diaphragm of Replacement Pressure Reducing/Dump Valve Installed on Itt Barton Hydromotor Actuator.Caused by Poor Workmanship of Valve at Time of Manufacture.Valves Sent to Vendor1998-02-0606 February 1998 Part 21 Rept 21-97-058 Re Oil Leaking Around Diaphragm of Replacement Pressure Reducing/Dump Valve Installed on Itt Barton Hydromotor Actuator.Caused by Poor Workmanship of Valve at Time of Manufacture.Valves Sent to Vendor U-602920, Part 21 Interim Rept 21-97-044/047/048 Re 970929 Failure of safety-related Battery Charger.Caused by Inadequate Soldered Wire Connections.Util Will Issue Rept of Issues IAW Provisions of 10CFR21 & 10CFR50.73 by 9802171998-01-28028 January 1998 Part 21 Interim Rept 21-97-044/047/048 Re 970929 Failure of safety-related Battery Charger.Caused by Inadequate Soldered Wire Connections.Util Will Issue Rept of Issues IAW Provisions of 10CFR21 & 10CFR50.73 by 980217 U-602910, Part 21 Interim Rept 21-97-055,identified Adverse Trend in Auxiliary Switch Operating Assembly Anomalies in W Dhp Circuit Breakers on 971120.Condition Rept 1-97-11-388 Initiated to Track Investigation & Resolution1998-01-16016 January 1998 Part 21 Interim Rept 21-97-055,identified Adverse Trend in Auxiliary Switch Operating Assembly Anomalies in W Dhp Circuit Breakers on 971120.Condition Rept 1-97-11-388 Initiated to Track Investigation & Resolution U-602894, Final Part 21 Rept Re Discrepancies Between GE BWR Reactor Design Requirements Documents & Sys Vendor Manuals.Util Completed Evaluation & Concluded That Issue Is Not Reportable Per 10CFR21 as Reported in 971029 Rept1997-12-18018 December 1997 Final Part 21 Rept Re Discrepancies Between GE BWR Reactor Design Requirements Documents & Sys Vendor Manuals.Util Completed Evaluation & Concluded That Issue Is Not Reportable Per 10CFR21 as Reported in 971029 Rept U-602876, Interim Part 21 Rept Re 970929 Discovery of Deviations in safety-related Battery Chargers.Evaluation of Conditions Under Part 21 Continuing.Update on Resolution Progress Will Be Provided by 9801291997-12-0303 December 1997 Interim Part 21 Rept Re 970929 Discovery of Deviations in safety-related Battery Chargers.Evaluation of Conditions Under Part 21 Continuing.Update on Resolution Progress Will Be Provided by 980129 U-602855, Part 21 Rept Re Discrepancies Between GE BWR Design Requirements Documents & Sys Vendor Manuals.Util Does Not Have Firm Date for Resolving Issue But Will Provide Update on Resolution Progress by 9712181997-10-29029 October 1997 Part 21 Rept Re Discrepancies Between GE BWR Design Requirements Documents & Sys Vendor Manuals.Util Does Not Have Firm Date for Resolving Issue But Will Provide Update on Resolution Progress by 971218 U-602823, Part 21 Rept Re Improper Clearance for W Model 50DHP350 Circuit Breaker Arc Chute Rear Arc Horn.Caused by Installation of Arc Chute Having Potential to Cause Line Pole to Deflect.Replace Deficient Arc Chutes1997-08-28028 August 1997 Part 21 Rept Re Improper Clearance for W Model 50DHP350 Circuit Breaker Arc Chute Rear Arc Horn.Caused by Installation of Arc Chute Having Potential to Cause Line Pole to Deflect.Replace Deficient Arc Chutes ML20149F6031997-07-18018 July 1997 Part 21 Rept Re R47 Incorrectly Installed on Electric Power Assembly.Recommends Evaluation of Timing Delay Requirements Applicable to Reactor Protective Sys ML20136D5641997-03-0707 March 1997 Part 21 Rept Re Transformer Not Being Stable in No Load Condition & Tripping When Lightly Loaded U-602704, Part 21 Rept Re Regulated Power Transformer 1AP75ERT Tripping Several Times.Caused by Addition of Step Load from Low or No Load Condition.Will Disconnect Four Potentially Affected Transformers from Div 2 Electrical Sys1997-02-27027 February 1997 Part 21 Rept Re Regulated Power Transformer 1AP75ERT Tripping Several Times.Caused by Addition of Step Load from Low or No Load Condition.Will Disconnect Four Potentially Affected Transformers from Div 2 Electrical Sys ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause U-602677, Part 21 Rept Re Failure of Westinghouse Dhp Circuit Breaker to Close on Demand During Surveillance Test.Inspected, Cleaned,Adjusted & Lubricated Motor cut-off Switch & Spring Charge Indicator Mechanism in Subject Breaker1996-12-20020 December 1996 Part 21 Rept Re Failure of Westinghouse Dhp Circuit Breaker to Close on Demand During Surveillance Test.Inspected, Cleaned,Adjusted & Lubricated Motor cut-off Switch & Spring Charge Indicator Mechanism in Subject Breaker U-602634, Part 21 Rept Re Failure of Itt Barton Hydramotor Actuator Pump to Develop Hydraulic Pressure During Testing.Initially Identified on 960306.Pump Withdrawn from Stores & Installed During Actuator Overhaul1996-09-20020 September 1996 Part 21 Rept Re Failure of Itt Barton Hydramotor Actuator Pump to Develop Hydraulic Pressure During Testing.Initially Identified on 960306.Pump Withdrawn from Stores & Installed During Actuator Overhaul ML20116B9251996-07-25025 July 1996 Part 21 Rept Re Failure Analysis Concerning Pump Assembly NS109761EQX07 U-602580, Part 21 Rept Re Itt Barton Hydramotor Actuator Pump Assembly Failed to Develop Hydraulic Pressure During Testing.Caused by Pump Not Being Fitted Properly1996-05-0808 May 1996 Part 21 Rept Re Itt Barton Hydramotor Actuator Pump Assembly Failed to Develop Hydraulic Pressure During Testing.Caused by Pump Not Being Fitted Properly U-602579, Part 21 Rept Re Ideal Generators Installed W/Edgs Having Greater Generator Rotor Mass than Originally Calculated. Evaluated Impact of Issue of Generator Frequency & Torsional Vibration Prior to Interim Rept1996-05-0202 May 1996 Part 21 Rept Re Ideal Generators Installed W/Edgs Having Greater Generator Rotor Mass than Originally Calculated. Evaluated Impact of Issue of Generator Frequency & Torsional Vibration Prior to Interim Rept ML20108D1441996-05-0101 May 1996 Part 21 Rept Re Failure of Pump Assembly for Itt Barton Series NH95 Hydramotor Actuator.Did Not Develop Pressure Because Was Not Fitted Properly.Pump Assembly Has Been Returned to Itt Barton for Insp U-602564, Interim Part 21 Rept 21-96-001 Re Egds Rotor Mass Greater than Originally Calculated.Revised Calculation Shows Larger Rotor Mass & Rotational Inertia1996-03-13013 March 1996 Interim Part 21 Rept 21-96-001 Re Egds Rotor Mass Greater than Originally Calculated.Revised Calculation Shows Larger Rotor Mass & Rotational Inertia U-602532, Final Part 21 Rept 21-95-018 Re Failure of Power Shield Type SS-13 Solid State Trip Devices (Sstd) Mfg by Asea Brown Boveri,Ite,Gould & Brown Boveri.Util Inspected & Reworked,As needed,12 Type SS-13 Sstds in safety-related Breakers1995-12-20020 December 1995 Final Part 21 Rept 21-95-018 Re Failure of Power Shield Type SS-13 Solid State Trip Devices (Sstd) Mfg by Asea Brown Boveri,Ite,Gould & Brown Boveri.Util Inspected & Reworked,As needed,12 Type SS-13 Sstds in safety-related Breakers ML20094P5671995-11-20020 November 1995 Part 21 Rept Re Abb Power Shield Trip Units (Pstu),Type SS-13.On 951006,util Reported to NRC That Two Pstus,Type SS-13 Tripped VC & Vx Sys Circuit Breakers.Recommends Insp of Power Shield SS Trip Units Prior to Serial 80,000,in Svc U-602502, Interim Part 21 Rept 21-95-018 Re Failure of Solid State Trip Devices Type SS-13 Mfg by Gould/Ite (Now Abb,Asea Brown Boveri).Investigation Found Return Air Fan Circuit Breaker in Tripped Condition.Breaker Replaced W/Spare Breaker1995-10-0606 October 1995 Interim Part 21 Rept 21-95-018 Re Failure of Solid State Trip Devices Type SS-13 Mfg by Gould/Ite (Now Abb,Asea Brown Boveri).Investigation Found Return Air Fan Circuit Breaker in Tripped Condition.Breaker Replaced W/Spare Breaker U-602497, Part 21 Rept Re Inverter Pwm Drive Logic Card Failure. Inverter Out of Svc to Replace Logic Card W/Revised Card in Accordance W/Scheduled Maint Activity1995-09-26026 September 1995 Part 21 Rept Re Inverter Pwm Drive Logic Card Failure. Inverter Out of Svc to Replace Logic Card W/Revised Card in Accordance W/Scheduled Maint Activity U-602466, Follow-up to 10CFR21 Interim Rept 21-95-010 Re Elgar Inverter Pwm Drive Logic Card (J4) Failure.Elgar Performed Addl Testing of Cards at CPS & Developing Schedule for Evaluating Test Results.Update Will Be Provided by 9509271995-07-12012 July 1995 Follow-up to 10CFR21 Interim Rept 21-95-010 Re Elgar Inverter Pwm Drive Logic Card (J4) Failure.Elgar Performed Addl Testing of Cards at CPS & Developing Schedule for Evaluating Test Results.Update Will Be Provided by 950927 ML20084B0071995-05-22022 May 1995 Part 21 Rept Re Failure of Elgar Inverter Pwm Drive Logic Card on 950324.Cause of Failure Unknown.Subsequent Replacement Logic Card Identified as Deficient.Both Logic Cards Returned to Mfg for Analysis ML20072S0051994-08-18018 August 1994 Part 21 Rept Re Failure of Motor Operated Potentiometer Mfg by Basler Electric.Qualification Testing of Units Revised & Mkw Power Sys Will Perform Site Visit at Basler Electric to Verify Adequacy of Basler Electric C/A U-602305, Part 21 Rept Re Incorrect Size Telephone Coil Current Limiting Resistor in Westinghouse/Asea Brown Boveri CV-2 Voltage Relay1994-06-27027 June 1994 Part 21 Rept Re Incorrect Size Telephone Coil Current Limiting Resistor in Westinghouse/Asea Brown Boveri CV-2 Voltage Relay U-602299, Part 21 Defect 21-94-010 Re Incorrect Internal Wiring of Basler Electric motor-operated Potentiometer (Mop) by Mkw Power Sys.Correct Wiring Scheme Determined & Mop Rewired in Accordance W/Vendor Wiring Diagram1994-06-0606 June 1994 Part 21 Defect 21-94-010 Re Incorrect Internal Wiring of Basler Electric motor-operated Potentiometer (Mop) by Mkw Power Sys.Correct Wiring Scheme Determined & Mop Rewired in Accordance W/Vendor Wiring Diagram JSP-007-94, Part 21 Rept Defect 21-93-028 Re Failure of Instantaneous Trip Function on Ite Gould/Telemecanique Type He Molded Case Circuit Breaker.Deficient Breaker Placed on Hold Pending Disposition Through Plant Corrective Action Program1994-01-11011 January 1994 Part 21 Rept Defect 21-93-028 Re Failure of Instantaneous Trip Function on Ite Gould/Telemecanique Type He Molded Case Circuit Breaker.Deficient Breaker Placed on Hold Pending Disposition Through Plant Corrective Action Program JSP-006-94, Part 21 Rept Re Westinghouse 4160 Volt Alternating Current Breakers Incorrectly Configured & Poorly Constructed. Initially Reported on 931111.Affected Assemblies Placed on Hold Pending Disposition1994-01-0707 January 1994 Part 21 Rept Re Westinghouse 4160 Volt Alternating Current Breakers Incorrectly Configured & Poorly Constructed. Initially Reported on 931111.Affected Assemblies Placed on Hold Pending Disposition U-602227, Part 21 Rept 21-93-029 Re Potential for Motor Pinion Key Failure in Limitorque Actuators Due to Excessive Torque During Valve Backseating & Movats Testing.Initially Reported on 931210.Description of Actuator Should Be Model Sb..1993-12-22022 December 1993 Part 21 Rept 21-93-029 Re Potential for Motor Pinion Key Failure in Limitorque Actuators Due to Excessive Torque During Valve Backseating & Movats Testing.Initially Reported on 931210.Description of Actuator Should Be Model Sb.. JSP-552-93, Part 21 Defect 21-93-029:on 931007,discovered Broken Motor Shaft Pinion Key in Limitorque Actuator of motor-operated HPCS Sys Injection & Outboard Containment Isolation Valve 1E22-F004.Broken Motor Pinion Key Replaced1993-12-10010 December 1993 Part 21 Defect 21-93-029:on 931007,discovered Broken Motor Shaft Pinion Key in Limitorque Actuator of motor-operated HPCS Sys Injection & Outboard Containment Isolation Valve 1E22-F004.Broken Motor Pinion Key Replaced 1999-09-22
[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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U-600824' L14-87( 02- 09)-L 1A.120 ILLINDIS POWER COMPANY CUNTON POWER STATION. P.O. BOX 678. CLINTON, tLLINOIS 61727 FEB 91987 Docket No. 50-461 Mr. James G..Keppler Regional Administrator Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Subject:
Reportable 10CFR50.55(e) Deficiency 55-86-07: Broken Tack Welds on Valves 1G33-F042A and 1G33-F042B
Dear Mr. Keppler:
, On August 28, 1986, Illinois Power Company (IP)-
notified Mr. F. Jablonski, NRC Region III (Ref: IP Record of Coordination Y-203106, dated September 2, 1986) of a potentially reportable deficiency concerning broken tack welds between the valve disc and disc nut on valves 1G33-F042A and 1G33-F042B.. Preliminary investigation and evaluation of this matter has determined that the broken tack welds were caused by vibration created by extreme throttling conditions. Administrative. controls;were implemented for Anchor / Darling throttling' valves having the same design and determined to be potentially impacting.to Technical Specification operability of plant systems. The administrative controls were implemented as an interim measure to preclude throttling of these' valves to less than c 20% of their open position until they could be repaired or determined by the valve vendor'to not have been degraded by
~
their previous throttling history.
Subsequent to submittal of our final reaort on the subject deficiency, a concern was expressed by the NRC Resident Office regarding the adequacy of the justification to assure that following removal of the administrative controls, the throttling valves would not be subject to failure between now and the first refueling outage. Lifting of the administrative controls on the Shutdown Service Water System-(SX) valves is considered acceptable since Sargent &
Lundy (S&L) had determined that the failure of these valves.
would not impact safety, but a more detailed justification is needed for removing the administrative controls on General Electric (GE) designated valves because their failure would be significant to plant safety.
2180j NoO 1 IES .1 1 Jgg7
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- ;U-600824 Ll4-87 ( 02- 09)-L ,
1A.120 ,,
.This letter represents an: amended final report
- regarding the subject reportable deficiency (Ref: IP Letter U-600767, D.lP. Hall to J. G. Keppler: dated November 26, 1986).. This amended final report is being submitted to 4
- provide a more detailed justification for removal of the -
administrative controls on GE. designated valves which' perform a-throttling function. Attachment A provides the .i details of our_ justification for removal of these controls.
An evaluation for.the safety implication and significance. included single and common mode failures of the l valves manufactured by Anchor / Darling. Sargent &'Lundy's- :
evaluation. concluded that the safety of the plant was not R
. - impaired by'the single or simultaneous failure'of S&L i
specified valves ~. Per.GE's evaluation, failure of the GE ,
supplied valves was determined 1to be significant to.the safe operation of Clinton Power Station (CPS) and,~ ' therefore ,
reportable under the provisions of 10CFR50.55(e). .;
'I
, We trust that this amended final report-provides you !
i sufficient background information to perform a general assessment of-this reportable deficiency and adequately 1 describes our overall approach to resolve this issue.
Si re - yours, [
. P. Hall Vice President g RLC/bsa j Attachment cc: NRC Resident Office Illinois Department of. Nuclear Safety INPO Records Center-p i
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Attachm:nt to-
'U-600824 ATTACHMENT A
_ ILLINOIS POWER COMPANY
' CLINTON. POWER STATION 4
DOCKET NO. 50-461-Reportable 10CFR50.55(e). Deficiency 55-86-07:
Broken Tack' Welds on Valves ~IG33-F042A'and 1G33-F042B-AMENDED FINAL REPORT Statement'of Reportable Deficiency / Background On August 28, 1986, Illinois Power Company (IP) notified Mr. F. Jablonski, NRC Region III (Ref: IP. Record of Coordination Y-203106, dated September 2, 1986):of a-potentially reportable deficiency. concerning broken: tack -
welds between-the valve disc and disc nut on valves 1
1G33-F042A and.lG33-F042B. On valve 1G33-F042A the disc. nut l
and disc'were disengaged and.one half of_the stem. retaining ring was missing and had appeared to have entered the
~
r system. On valve 1G33-F042B the disc was-backed out of.the disc nut approximately 1%. inches.
j Investigation Results/ Corrective Action
! -e l Illinois Power's initial investigation into this aatter
- identified 60 Anchor / Darling Valves in use at the Clinton
- j. Power Station 1(CPS) having the.same design as failed valves ,
[' 1G33-F042A and 1G33-F042B.-~However, during final assessment. !
4 of the.60 valves documented in the interim repo'rt U-600722 :
dated September 30, 1986, it was identifiedLthat three (3)
- of the valves were of a different configuration. These i three (3) Anchor / Darling valves (by design) have the disc j staked to the disc nut rather than tack welded. Although
! these valves are staked rather than tack welded, they. ,
'- experience similar degradation _when subjected to extreme
- throttling conditions in that the staking becomes l ineffective allowing the' disc to back out of the disc nut.
! -On this basis, these three (3) valves have been included in thiscreport. Anchor / Darling _ Valve Company was. requested to
- . evaluate the failure of valves 1G33-F042A and 1G33-F042B. '
! The preliminary evaluation of1this matter by' Anchor / Darling ,
determined that the tack weld failures resulted from:
repeated impact loads induced by'. vibration of theLyalve disc due to extreme throttling conditions, i.e., valve. throttled-
~
to less than 20% of its open position.
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- Attachm:nt.to - '
U-600824 l
ATTACHMENT A (continued)
As an interim measure,'pending completion of Anchor / !
. Darling. investigation and evaluation of this m'atter, IP.
3 alaced-administrative controls _cn those valves determined to f ue potentially impacting ~ to Technical Specification.
- operability of plant systems. 1Due administrative controls were implemented to preclude throttling of these valves 1to less than 20% of their open position until they:could be i c ' repaired or determined by the valve vendor to not have been degraded by their previous throttling history. 3 L Based on vendor recommendations, Plant Modification-
- RT-14 was issued to provide a 360* weld between~the disc'and' disc nut'of valves 1G33-F042A and'lG33-F042B. This work was
< performed under Maintenance Work Requests (MWRs)-C-09332 and C-14484.
1111nois Power furnished: Anchor / Darling with. operating j data which_ included inlet pressure, temperature, flow rate, !
- ! and pressure drop across the valves. .This data was'used-by.
i Anchor / Darling to evaluate the remaining _ valves for-a potential failure or degradation of_the. tack welds.
a >
On October 3, 1986, Anchor / Darling completed their. .
initial evaluation of the affected. valves and concluded that l the past operating conditions should not have caused any
- damage to the valves. However, Anchor / Darling recommended .
l inspection of the tack welds on valves lE12-F021 and l lE21-F012 for-further assurance.that these valves had not :
degraded or failed, because the_ Operating data for these l'
- valves was not conservative enough to totally exempt them from possible degradation or failure. Maintenance. Work i Requests (MWRs) C-11753 and C-31433 were initiated to
- perform an inspection of these. valves to verify the tack weld integrity. Valve lE21-F012.was inspected on October 15, 1986, under MWR C-31433. Linear indications (cracks)'
were found on both of the tack welds. ~These cracks.were
. documented on Nonconforming Material Report..(NCMR) No.
02-0989. Plant Modification M-34 was issued which' replaced
!. the tack welds with a full 360* circumferential. weld between-the disc and' disc nut. No linear _ indications wereifound on '
. the tack welds of-valve lE12-F021.
Of the 57 valves identified as having the'same' design as failed valves 1G33-F042A and 1G33-F042B,_35Eare used in
. throttling applications'. To date, 3 of these 35' valves have been repaired (lG33-F042A, 1G33-F042B,tand IE21-F012).- To:
, . provide additional assurance of-the integrity.of the discLto
~
-disc nut tack welds during future operation of the plant,
'the remaining 32 valves performing a throttling function will be' inspected at the first refueling outage.. These valves ~~are expected to function without; degradation'until the first refueling outage based on~the.following:
Page.2 of 5 .
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' Attachment to .
U-600824-ATTACHMENT A (continued) l Anchor / Darling'has performed-an' evaluation of-thel past throttling history ~ associated with these valves:
- and has' determined that the. valves are not1 degraded.
- Sixteen-(16).of.Ithe valves'are. monitored _by CPS In-Service Testing:(IST)l program.
- Anchor / Darling has reporte'd no failures ofIglobe valves supplied to other plants except the failure- .
of:a 24" globe valve in the RHR system in Chi Chan' Plant (Taiwan) and at the Susquehanna Plant.
Anchor / Darling has stated.that the globe' valves may be throttled for short periods of time-to less than
- .20%.of the open position without any-potential.for i cracking of the tack welds.,
Subsequent to submittal of.our. final report on this reportable deficiency, a concern was' expressed by:the NRC 4 Resident Office lregarding the adequacy.of the justification to assure that following removal of the administrative -
j controls, the 32 remaining throttling-valves would not'be L subject to failure between now and the first refueling-outage when the valves will be inspected.. Lifting'of the administrative controls on the 9 Shutdown Service Water- !
L System (SX) valves is considered-acceptable by the NRC since Sargent & Lundy (S&L) has determined'that the failure of these valves would not impact. safety. Lifting of:the l
administrative controls for the remaining throttling valves'-
! is considered acceptable based:on Anchor / Darling's evaluation.
4 General Electric (GE) and Sargent & Lundy were requested to provide the following information:
4
- a) Duration of throttling time from the system process i ' diagrams for the period between now and the-first refueling outage. (Furnished by GE) i
. b) Flow conditions - flow rate, inlet pressure, pressure' drop across the valves.and temperature. . (Furnished by
- S&L) j The above data was. forwarded to Anchor / Darling.for ,
' their evaluation to determine the extent of valve. L degradation / failures during the first.18; months.. Based upon:
Anchor / Darling's evaluation, the valves are expected to function without failure until the first' refueling outage.
However, Anchor / Darling has recommended that valve 11E51-F022 i be monitored for excessive. vibration while being throttled. '
' The line'containing valve 1E51-F022 will.be l Page 3-of:5-
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'Attechm:nt to-4 U-600824 ATTACHMENT A (continued).
tested for vibrations-and the Nuclear Station Engineering
. Department (NSED) will reviewLthe test results. If the
, testing identifies. excessive-vibrations,. appropriate-corrective action will be taken to correct this, condition.
Centralized Commitment Tracking System Item No. 43942:has. '
been initiated to track this action to completion.
- Based upon Anchor / Darling's. detailed evaluation-(Ref:- 1 Anchor / Darling' letters dated January 2, 1987 and January 5, 1987), the-23 valves identified.in Attachment 1 will
' function without failure between:now.and theffirst-refueling outage. On this basis, the administrative controls-established at.the beginning of this investigation will be' removedLfo110 wing-review and concurrence-by the Clinton
-Power Station NRC Resident Office.
The three (3) Anchor / Darling 1 valves.which have their-disc staked rather than tack welded were also reviewed and evaluated as follows:
Valve 1E22-F010: The. failure of this. valve was documented by NCMR No. 01-1960. In accordance with the i-- disposition of'this.NCMR, staking of the' .
[ disc to the disc nut was revised to' apply ,
I three (3) one-inch long-tack welds to
[ preclude recurrence of this deficiency.
1
[ Valve lE22-F011: The throttling limitations.for this valve were evaluated by GE. -GE'sLevaluation included the flow characteristics;from
- Anchor / Darling letter dated March.17,.
! 1986, and the High Pressure' Core Spray (HPCS) system-pump curves to establish.a ;
limiting throttling flow rate.offnot less than 4800.GPM. -This limitation was-procedurally implemente6.(Ref: CPS
., Procedure No. 9051.01). to. preclude ,
degradation of-the disc to disc nut-stake-caused by extreme throttling conditions. ;
, Valve 1E22-F023: Inspection of this valve determined that this valve was'not degraded.. CPS.
procedures do not require.this valve to-perform a--throttling function, therefore, ,
no further corrective action was required.
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Attechment-to U-600824 ATTACHMENT 4 (continued)
Root Cause Illinois Power's root cause investigation of this ratter determined that the stake and tack weld failures resulted from extensive throttling of the valves between 0%
and 20% of the open position. To preclude recurrence,.all replacement or spare valves designated for extreme throttling duty (less than 20% of valve's open position) will be procured from Anchor / Darling under Specification-K-2866A. These valves will be designed for extreme throttling duty applications.
Safety Implication / Significance An evaluation of the safety implications and significance included an evaluation of single and common mode failures of the valves supplied by Anchor / Darling.
Sargent & Lundy's evaluation concluded that the safety of the plant was not impaired by the single or simultaneous failure of S&L supplied valves. Per GE's evaluation, failure of the GE supplied valves was determined t:o be adverse to the safe operation of Clinton Power Station (CPS) and, therefore, reportable under the provisions of 10CFR50.55(e).
Page 5 of-5
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-Attechm:nt.to U-600824' ATTACHMENT [
Valves Performing Throttling Function Valve Number. System-
- 1. 1E12-F003A Residual ~ Heat R'emoval
-2, 1E12-F003B' Residual Heat Removal:
- 3. 1E12-F021 Residual Heat-Removal.-
- 4. 1E12-F023 Residual Heat: Removal ,
- 5. .lE12-F037A. Residual Heat Removal ,
- 6. lE12-F037B Residual Heat' Removal- 'I
'7 . lE12-F040 . Residual Heat Removal .]
!- 8. .lE12-F048A Residual Heat Removal-
- 9. 1E12-F048B Residual Heat Removal.
- 10. 1E12-F052A Residual Heat' Removal .
4
- 11. 1E12-F052B Residual ~ Heat Removal
- 12. 1E12-F053A Residual Heat. Removal.
- 13. lE12-F053B Residual Heat Removal- -
- 14. 1E12-F087A Residual Heat Removal' r L 15. 1E12-F087B Residual Heat Removal-
?
16 .- 1E32-F012 MSIV Leakage' Control:
- 17. 1E32-F013 MSIV Leakage Control ~
- 18. lE51-F022. Reactor Core 11 solation Cooling' .;
- 19. 1G33-F031 Reactor Water Clean-up
- 20. 1G33-F044 Reactor Water Clean-up:
Reactor. Water Clean-up-
^
- 21. 1G33-F103 ;
L22. 1G33-F104 Reactor: Water Clean-up
. 23. 1G33-F107 Reactor: Water Clean-up. :)
a O l 4
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