Part 21 Rept Re Failure of Circuit Breakers During Environ Testing.Test Results Indicate That Temp Sensitivity Problem May Be Generic to All Ite Imperial Corp thermal-magnetic Circuit Breakers Calibr for 40 C SvcML20083L975 |
Person / Time |
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Site: |
Hatch, Monticello, Nine Mile Point, Palo Verde, Fermi, Byron, Limerick, Clinton, LaSalle, 05000000, Shoreham, Hartsville, Phipps Bend |
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Issue date: |
05/27/1983 |
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From: |
Empey D ROCKWELL INTERNATIONAL CORP. |
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To: |
Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
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References |
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REF-PT21-84-194-000 83ESG-3401, PT21-84-194, PT21-84-194-000, NUDOCS 8404170427 |
Download: ML20083L975 (6) |
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Similar Documents at Hatch, Monticello, Nine Mile Point, Palo Verde, Fermi, Byron, Limerick, Clinton, LaSalle, 05000000, Shoreham, Hartsville, Phipps Bend |
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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 ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results 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 ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc 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 ML20153D0191998-09-18018 September 1998 Part 21 Rept Re Defect in Gap Conductance Analyses for co- Resident BWR Fuel.Initially Reported on 980917.Corrective Analyses Performed Demonstrating That Current Operating Limits Bounding from BOC to Cycle Exposure of 8 Gwd/Mtu ML20153C6771998-09-17017 September 1998 Part 21 Rept Re Defect Relative to MCPR Operating Limits as Impacted by Gap Conductance of co-resident BWR Fuel at Facilities.Operating Limit for LaSalle Unit 2 & Quad Cities Unit 2 Will Be Revised as Listed ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency 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 ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps 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 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 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 ML20198Q6961998-01-12012 January 1998 Part 21 Rept Re Failed Operation of Agastat EGPI004 Relay on 971129,as Reported by Limerick Station.Caused by Insufficient Soldering.Will Notify Customers Who Purchased EPI004 & ETR14XXX004 Relays During June 1996 ML20198K5081998-01-0606 January 1998 Part 21 Rept Re Transient Analyses at Exposures Prior to End of Cycle.Caused by Component Defect.Notified Commonwealth Edison of Defect & Provided Revised Limits by Siemens Power Corp NRC-97-0141, Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility1997-12-23023 December 1997 Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility 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 ML20203B3691997-12-10010 December 1997 Part 21 Rept Re Potential to Exceed Operating Limits.Cycle 8 Delayed Until Fall 1998 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 LD-97-033, Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 9712011997-11-20020 November 1997 Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 971201 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 LD-97-028, Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys1997-10-13013 October 1997 Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected ML17309A6211997-09-29029 September 1997 Part 21 Rept Re Final Disposition of Masterflow 713 & Embeco 636 Grout Nonconformance Reported by Master Builders,Inc. Licensee Continuing to Monitor shelf-life of Masterflow 713 & Embeco 636 Grouts Produced at Rancho Cucamonga 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 LD-97-024, Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-0041997-08-14014 August 1997 Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-004 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 ML18153A1431997-06-10010 June 1997 Part 21 Rept Re Possible Machining Defect in Certain Stainless Steel Swagelok Tube Fitting Bodies.Facilities Have Been Notified About Possible Problem ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum ML20140A4761997-05-27027 May 1997 Provides Addl Info to 970429 Part 21 Rept Re Potential safety-related Problem W/Asco HV 266000-007J Scram Solenoid Pilot Valves.Corrective Actions Also Listed NSD-NRC-97-5093, Part 21 Rept Re W Identified Defects That Could Create Substantial Safety Hazard Should Defect Remain Uncorrected. Plans to Complete Proper Refurbishment of All of Returned Breakers Being Established1997-05-14014 May 1997 Part 21 Rept Re W Identified Defects That Could Create Substantial Safety Hazard Should Defect Remain Uncorrected. Plans to Complete Proper Refurbishment of All of Returned Breakers Being Established 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N4381999-10-25025 October 1999 Safety Evaluation Supporting Amend 17 to License DPR-9 ML20217P3551999-10-22022 October 1999 LER 99-S01-00:on 990922,loaded 9mm Handgun Was Discovered on Truck Cargo Area of Vehicle Inside Protected Area.Caused by Inadequate Vehicle Search.Guidance in Procedures & Security Training to Address Multiple Vehicle Searches Was Provided ML20217G2161999-10-15015 October 1999 Errata Pages 2 & 3 for Safety Evaluation Supporting Amend 168 Issued to FOL DPR-63 Issued on 990921.New Pages Change Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217D3061999-10-13013 October 1999 SER Accepting Licensee Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation ML20217C9121999-10-12012 October 1999 SER Input Authorizing Licensee Proposed Request to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change ML20217F9091999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for LaSalle County Stations,Units 1 & 2.With ML20216J9251999-09-30030 September 1999 Suppl to Special Rept:On 990621,11 Containment Hydrogen Monitoring Sys Chart Recorder Was Indicating Below Normal Operating Range.Caused by Excessive Wear on Valve Body & Discs of Bypass Pump.Sample Pump Replaced ML20217D1261999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Monticello Nuclear Generating Plant.With ML20217K4631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Nine Mile Point, Unit 1.With HL-5845, Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.With ML17300B3811999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pvngs,Units 1,2 & 3.With 991007 Ltr NRC-99-0095, Monthly Operating Rept for Sept 1999 for Fermi 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fermi 2.With U-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 ML20217H5221999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Byron Station, Units 1 & 2.With ML20217D1211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Lgs,Units 1 & 2. with ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations 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 ML20212F7301999-09-21021 September 1999 Special Rept:On 990907,CR Operators Declared 12 Containment Hydrogen Monitoring Sys Inoperable for Planned Maint.Cause of Low Flow Condition Was Determined to Be Foreign Matl. Replaced Sample Pump Valve Discs ML20212B9081999-09-14014 September 1999 Special Rept:On 990901, 12 Containment Hydrogen Monitoring Sys Was Declared Inoperable for Planned Maint.Caused by Planned Maint Being Performed as Corrective Action.Check Valves with O Rings Were Replaced ML20212A6641999-09-13013 September 1999 Safety Evaluation Authorizing Relief Request RR-V-16 for Third 10 Yr Interval Inservice Testing Program ML20212A8861999-09-13013 September 1999 Safety Evaluation Authorizing First & Second 10 Yr Interval Inservice Insp Plan Requestss for Relief RR-01 ML20212B9261999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Byron Station,Units 1 & 2.With ML20212A4481999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Limerick Generating Station,Units 1 & 2.With 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 ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 ML20216E7031999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Monticello Nuclear Generating Plant.With HL-5836, Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With ML20212C4601999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Nine Mile Point Nuclear Station,Unit 1.With ML20212C4501999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for LaSalle County Station,Units 1 & 2.With NRC-99-0067, Monthly Operating Rept for Aug 1999 for Fermi 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fermi 2.With ML17300B3271999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pvngs,Units 1,2 & 3 ML17313B0751999-08-27027 August 1999 LER 99-002-00:on 990730,test Mode Trip Bypass for EDG Output Breakers Not Surveilled.Cause Under Investigation.Operations Personnel Conservatively Invoked SR 3.0.3 for SR 3.8.1.13. with 990827 Ltr ML20211E9891999-08-20020 August 1999 LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5 ML20210Q0521999-08-0404 August 1999 Safety Evaluation Approving Relief Request 10 to License DPR-22 Per 10CFR50.55a(g)(6)(i).Inservice Exam for Relief Request 10,Parts A,B,C,D & E Impractical & Reasonable Assurance of Structural Integrity Provided ML20210J9271999-08-0202 August 1999 SER Finds That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant,Susceptible to Pressure Locking or Thermal Binding ML20210J9631999-08-0202 August 1999 SER Finding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210Q6611999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Monticello Nuclear Generating Plant.With HL-5818, Monthly Operating Repts for July 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20210R3431999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Byron Station, Units 1 & 2.With ML20210L7051999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Limerick Generating Station,Units 1 & 2.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 ML20210U4591999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Nine Mile Point, Unit 1.With NRC-99-0065, Monthly Operating Rept for July 1999 for Fermi 2.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fermi 2.With ML17313B0611999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pvngs,Units 1,2 & 3.With 990810 Ltr ML20210R0671999-07-31031 July 1999 Monthly Operating Repts for July 1999 for LaSalle County Station,Units 1 & 2.With ML20211C9621999-07-26026 July 1999 ISI Summary Rept ML20210E2251999-07-21021 July 1999 B1R09 ISI Summary Rept Spring 1999 Outage, 980309-990424 ML17313B0191999-07-16016 July 1999 LER 99-005-00:on 990618,RT on Low DNBR Was Noted.Caused by Hardware Induced Calculation Error.Cr Operator Was Taken to Place Reactor in Stable Condition IAW Appropriate Operating Procedure ML20210C1681999-07-0909 July 1999 Seventh Refueling Outage ASME Section XI 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 1999-09-30
[Table view] |
Text
- _ _ .-. _._ .-. ___ _ ___- . _ _ _ _ _ . _ _ _ . . _ , __
~
. 4t - '
s' l
4 Energy Systems Group Rockwell cJai == international JtN - Gl983 Telephone:(213) 341-1000 E l
d)
- TWX: 910-494-1237 ' + -
Telex: 181017 May 27,1983 In reply refer to 83ESG-3401 -
U.S. Nuclear Regulatory Commission Region IV i
@@b 611 Ryan Plaza Drive i Mg _ Q% !
Arlington, Texas 76012 Attention: Mr. John Collins, Administrator Region IV s ""
References:
(1) ESG Letter 83ESG-1483 dated March 11, 1983, D. C. Empey to John Collins
}'
(2) ESG Letter 83ESG-3402 dated May 24, 1983, D. C. Empey to John Collins Gentidmen:
Subject:
Status Update on Report of Deviation (10 CFR 21)
Reference (1) provided information regarding failure of circuit breakers during environmental testing. This letter is to update status of our corrective efforts and to complete the listing of suspect model numbers.
Also, please note that Reference-(2) has expanded the problem to similar circuit breakers made by another manufacturer and essentially duplicates i
the corrective action stated herein.
Component Description a) ITE Imperial Corporation circuit breaker,100A frame, 600-Vac, o thermal-magnetic trip,1400 C calibration, EF series.
b) ITEImperialCorporation~gircuitbreaker,'100Aframe,600-Vac, thermal-magnetic trip, 40 C calibration, HE series.
c) ITE Imperial Corporation gircuit breaker,150A frame, 480-Vac, thermal-magnetic trip, 40 C calibration, EH series.
c d) ITE Imperial' Corporation circuit breaker, 225A frame, 600-Vac, I thermal-magnetic trip, 400C calibration, Part No. FJ3-B150.
e) ITE Imperial Corporation circuit breaker, 400A frame, 600-Vac, thermal-magnetic trip,-400 C calibration JL series.
w h l
- . v -
Rockwell 83ESG-3401 International May 27, 1983 Page 2 Test Results During the IEEE 323 Environmental Qualification Testing, an EF3-B015 thermal-magnetfccircuitbreakerfailedtoreset(close)thetest 0 circuit at 165 F with a relative hugidity of 97% (150 F circuit breaker ambient temperature plus 15 F margin; reference ESG Component Qualification Test Report N00lTR700020 and Wyle Laboratories Report NES 58481).
The circuit breaker provides 480-Vac power to various control devices in Rockwell International, Energy Systems Group (ESG), Hydrogen Recom-biners. The failure mode, described above, would prevent the operation of the control devices and cause the Hydrogen Recombiner to shut down.
On January 28, 1983, an attempt was made to repeat the test in which the EF3-B015 circuit breaker had failed. The retest, which was completed on January 31, 1983, ing posj ditions (i.e., high denranstrated relative humiditythat dur[95-100%,}-LOCA environment con-and high temperature 1690F,1650F base temperature plus0 4 F tolerance ), the circuit breaker will automatically trip without a load being applied. Further testing was performed to establish the temperature at which the circuit breaker would trip while carrying a normal electrical load. - The tests were conducted simulating the worse-case loading of 3.5A, as it is used in the Hatch and LaSalle BWR power plants which are now in operation. The circuit breaker failed to carry the 3.5A by tripping after 13 min at 140 F. At 1300 F, .the circuit breaker had not tripped after 239 hours0.00277 days <br />0.0664 hours <br />3.95172e-4 weeks <br />9.09395e-5 months <br /> and 55 min while carrying the 3.5A load. Based on engineering judgment; this time period is sufficient to have achieved circuit breaker tempera-ture rise stabilization and indicates that this load can be carried con-tinuously at this temperature for the required post-LOCA maximum operating duration of one year.
On March 3',1983, additional tests were performed on the EF3-B015 circuit.
breaker to simulate temperature and loading conditions as it is used in PWR power plants. The circuit breaker was. loaded to SA, with a 33A surge for 5 sec to simulate motor starting characteristics. Thegircuitbregker failed to carry the 33A' surge by tripping in 4.5 sec at 130 F. At 120 F, the circuit breaker had not tripped after 91 hours0.00105 days <br />0.0253 hours <br />1.50463e-4 weeks <br />3.46255e-5 months <br /> while carrying the con-tinuous load of SA (the 33A surge for 5 see was applied at the beginning of the test).
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A Rockwell 83ESG-3401 International May 24, 1983 Page 3 The results of the above tests indicated that a temperature sensitivity problem might be generic to all ITE thermal-magnetic circuit breakers calibrated for 40 C service. Therefore, a test program was established to test representative sizes and types of the ITE thermal-magnetic cir-cuit breakers used in the ESG Hydrogen Recombiners (the circuit breakers actually used in the various recombiners are listed in the section entitled "Affected Plants"). A load current analysis was conducted to determine the worse-case loading for the various circuit breakers.
The objective of the test program was to establish the maximum circuit breaker ambient temperature at which the series of breakers could con-sistently carry the required load current. This temperature ss estab-lished to be 120 F.
For the PWR series of power consoles, a temperature rise within the con-sole due to component heating was measured to be 20 F at a console ambient temperature of 72 F. An equivalent rise is estimated for the BWR power consoles due to similarities in design.
The 20 F compartment temperature rise would limit both the BWR and PWR power console external ambient temperature to 100 F for reliable circuit breaker operation.
An investigation was conducted to evaluate replacement devices for the thermal-magnetic circuit breakers. Tests were conducted on representa-tive sizes 0of magnetic (only) trip cirguit breakers to temperatures of 1950F (150 F operating ambient plus 30 F compartment temperature rise (conservative) plus 150 F margin). Verification of operation included both the ability to continuously carry a current load and the ability to trip for simulated fault conditions. The ability to remain0 closed with no load current when subjected to a temperature of 212 F for six hours and then carry load at 195 F temperature was also verified.
In addition, analysis indicates that slow-blow fuses, with proper tem-perature and time derating, are also acceptable replacement devices for the thermal-magnetic circuit breakers.
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i 4k Rockwell 83ESG-3401 International May 24,1983 Page 4 Affected Plants NRC Licensed - 4 Customer Name Facility G.0. Part No. & Notes Detroit Edison Fermi 2 NPS 4056 EF3-B015 2 2 FJ3-B150 2 Long Island Shoreham 1 NPS 4093 EF3-8015 4 2 Lighting Co. EF3-B070 2 FJ3-B150 2 I 4 2 Philadelphia Limerick 182 NPS 4097 HE2-B015 Electric Co. HE3-8010 4 HE3-8030 4 Georgia Power Co. Edwin I. Hatch 2 4154 EF3-B015 4 2, 5 NPS FJ3-B150 2 Niagara Mohawk Nine Mile Point 4193 EF3-8015 4 2 Power Corp. 2 NPS FJ3-B150 2 Commonwealth :LaSalle County 4198' EF3-8015 4 2, 5 Edison 182 NPS FJ3-B150 2 I 2 ' 2, 5 Northern States- Monticello 4377 HE2-B015
'HE3-8015 2 Power Co.
HE3-8050 2' JL3-B175 2 JL3-B225 2 I 2 3 Arizona Public Palo Verde 4160 EF2-B015 Service Co. 1, 2, & 3 NPS EF3-8015 2 EF3-B020 2 EF3-8050 2 EF3-B100 2 a__-___
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Rockwell International 83ESG3401 May 27, 1983 Page 5 NRC Licensed Customer Name Facility G.O. Part No. Qty 4 Notes 1
Tennessee Valley Hartsville & 4210 EF2-B015 4 3 Authority Phipps Bend NPS EF3-B015 4 EF3-B020 4 EF3-8070 4 EF3-B100 4 1
Illinois Power Co. Clinton 1&2 NPS 4245 EF2-B015 2 3 EF3-8015 2 EF3-8020 2 EF3-8070 2 EF3-B100 2 1
Commonwealth Byron NPS 4260 EF2-B015 2 3 Edison EF3-8015 2 EF3-B020 2 EF3-8070 2 EF3-B100 2 ITwo-pole breaker in a three-pole frame _(the center pole is not used)-
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, Boiling. Water Reactor Plant (BWR) 3 Pressurized Water Reactor Plant (PWR)'or BWR MARK-III-4 Quantity does not include spares 5
0perating plants (as of February 1%3)
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Corrective Action /Coninents , s Specific magnetic breakers have now been identified to replace the the#rmo- i t.;
magnetic breakers. Letters have been sent to the plant operators defining '
the replacement parts which may be used of the power cabinet external ambient temperature is determined to exceed 1000F. '(NOTE: The previous interim corrective action identified for operating plants way to bypass the circuit breakers with wire jumpers. This previous action should be superseded as noted above.)
If you require further information or clarification, please call me at (213) 700-3926.
Very truly yours, s--
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D. C.' Empey_
Director Quality Assurance cc: Director, Office of Inspection and Enforcement (3)
U.S. Nuclear Regulatory Commission Washington .DC 20555 e