Part 21 Rept Re Failure of post-LOCA Hydrogen Recombiner Component During IEEE-323 Qualification Program.Circuit Breaker Not Properly Selected for Specific Application.Plant Operators Notified of DeviationML20074A222 |
Person / Time |
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Site: |
Hatch, Nine Mile Point, Palo Verde, Fermi, Byron, Clinton, LaSalle, 05000000, Shoreham, Hartsville, Phipps Bend |
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Issue date: |
03/11/1983 |
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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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Shared Package |
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ML20074A205 |
List: |
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References |
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REF-PT21-84-190-000 83ESG-1483, PT21-84-190, PT21-84-190-000, NUDOCS 8305120404 |
Download: ML20074A222 (5) |
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Similar Documents at Hatch, Nine Mile Point, Palo Verde, Fermi, Byron, 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 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 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 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 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 ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20137G6261997-03-25025 March 1997 Svcs Part 21 Rept Re Emergency Generators Installed at Zion Station Which Developed Significant Drop in Crankcase Lube Oil Level.Caused by Crack in Liner Wall,Allowing Jacket Water to Enter Chamber ML20136D5641997-03-0707 March 1997 Part 21 Rept Re Transformer Not Being Stable in No Load Condition & Tripping When Lightly Loaded ML20135E3811997-03-0303 March 1997 Part 21 Rept Re Output Drift W/Increasing Temperature on Several RTD Amplifiers Noted During Installation of RTD by-pass Mod at Station.Action to Identify All Circuit Cards W/Affected Date Codes,Identified 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 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 ML20217F9091999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for LaSalle County Stations,Units 1 & 2.With 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 ML20217H5221999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Byron Station, Units 1 & 2.With ML17300B3811999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pvngs,Units 1,2 & 3.With 991007 Ltr 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 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 ML20217K4631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Nine Mile Point, Unit 1.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 ML17300B3271999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pvngs,Units 1,2 & 3 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 ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 ML20212C4601999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Nine Mile Point Nuclear Station,Unit 1.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 ML20212C4501999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for LaSalle County Station,Units 1 & 2.With ML20212B9261999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Byron 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 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 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 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 ML17313B0611999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pvngs,Units 1,2 & 3.With 990810 Ltr ML20210U4591999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Nine Mile Point, Unit 1.With ML20210R3431999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Byron Station, Units 1 & 2.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 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 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 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 ML20210C1681999-07-0909 July 1999 Seventh Refueling Outage ASME Section XI Summary Rept ML20209G1751999-07-0808 July 1999 SG Eddy Current Insp Rept,Cycle 9 Refueling Outage (B1R09) ML20209D0291999-07-0202 July 1999 Special Rept:On 990621,operator Identified That Number 11 Hydrogen Monitoring Sys (Hms) Chart Recorder Was Indicating Below Normal Operating Range.Cause Indeterminate.Licensee Will Complete Troubleshooting of Subject Hms by 990709 ML17300B3151999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pvngs,Units 1,2 & 3.With 990714 Ltr HL-5805, Monthly Operating Repts for June 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20210B9081999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Nine Mile Point Unit 1.With 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 ML20209H1501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for LaSalle County Station,Units 1 & 2.With ML20207H8071999-06-30030 June 1999 Rev 0 to WCAP-15178, Byron Unit 2 Heatup & Cooldowm Limit Curves for Normal Operations ML20207H7941999-06-30030 June 1999 Rev 0 to WCAP-15180, Commonwealth Edison Co Byron,Unit 2 Surveillance Program Credibility Evaluation 1999-09-30
[Table view] |
Text
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Energy systems Gree >
9900 D. Soto Aenus .b C"** '** C'" ' Rockwell Toisphor* (213) s4* ioco TWX. 91N94-1237 International Teess: 181017 Harch 11, 1983 In reply refer to 83ESG-1483 U.S.,NuciedSRe ft <, s .u , . , m .. 3 . t M[Isd,
~.t
, [l W- i j, f+ ,.3 7 " Region 1Y W " gu a ory 'Concission
' ~' '
' l-c
, 611.Ryan Plaza-Drive-
-Arlington,' Tekas 76012 -
Attention:- Mr. . John Collins, Akin 4trator
. Region IV ,,
. : .. ,: . . - -1
References:
~'ll) I.SG Letter 81ESG-7725 dated Dctcher 21, 1982 ~
- D. C. Espey to John Collins (2) ESG Letter 82ESG-8085 dated November 3,1982 D. C. Empey to John Collins (3) ESG Letter 82ESG-7948 dated November 3,1982 D. C. Empey to John Collins
-(4) ESG Letter 82ESG-8933 dated December 14, 1982 D. C. Empey to John Collins (5) ESG Letter 82ESG-8998 dated December 17, 1982 D. C. Empey to John Collins l
Gentlemen: ,
Subject:
Report of Deviation (10 CFR 21)
During ESG's IEEE-323 qualification program as described in the refer-ences, the post-LOCA hydrogen recombiner component noted below failed to function properly at elevated tecperature. It is concluded from the test results and recent discussions with the manufacturer that the circuit breaker, which was initially selected by an ESG subcontractor who performed the design and fabrication of the BWR power cabinet in 1975-1976, was not properly selected for the specific application.
4 8305120404 830426 PDR ADOCK 05000410
L: : .
d sh 83ESG-1483 Rockwell k rch 11, 1983 Page 2 International
~
l
".ComponentDescription ITE Gould circuit breaker, 3 pole, 600 Y ac, fully enclosed,' thermal 4
magnetic P/N EF3-B015, IEEE No. 79. This component was originally selected in 1975-1976 by Timetrol, the vendor to ESG. The specifica-tion from ESG called for 50'F to 148'F environment. The ITE catalog at that time gave derating data from 40*C (104*F) to 60*C (140*F) and
- extrapolation would indicate that operation at 150'F could be expected C g., . edwith;properdderating. Subsequent reviews'upon.transferrirg fabrica- '
MWA!P @tfoifto'.ESGT.in'.the~ post-1976 time ~ period asszned that the cor4onent
' Q; , c~Q was{sstisfactory.-
A '
' 7 7. .c _ '
.. . Test Results: -
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. Under:the IEEE-323 Envfronmental Quelification Testing, the circuit
- braakerifailed to reset (class) the circuit at 165'F (ILG'F design '
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( temperature plus 15'F s.argin) and post-test at ambient temperature.
during the post-LOCA Er.vironmental Testing. The circuit breakers i
provide 480 V ac power to various recombiner components and control devices. The failure of the circuit breaker would prevent the opera-tion of these circuits and' cause the recombiner to shut down.
An attempt was made on January 28, 1983, to repeat the test conditions i
during w11ch the circuit breaker had failed. This test was conducted on a new EF3-8015 circuit breaker. The test which was completed on January 31, 1983,- demonstrated that in post-LOCA environmental condi-tions, i.e., a high relative humidity and 169'F the circuit breaker will automatically trip without any current load. The 169'F tempera-ture was the circuit breaker case temperature during a transient to 212*F. An additional no load test conducted on March 9,1983, on the same breaker showed that the breaker would trip at 147'F. The discrepancy in the trip temperature measured is due to the heating ramp rate and indicates that although the exterior of the case was at 169'F the internals were still at a lower temperature.
l Further testing was performed to establish the temperature where the.
EF3-8015 circuit breaker would carry the required load without trip .
ping. The tests were conducted at 3.5 amperes simulating the worst case load of the two operating BWR plants (Hatch and LaSalle). The other BWR plant requirements are enveloped by this test. The circuit breaker failed by tripping after 13 minutes at 140'F while carrying 3.5 amperes. At 130*F the breaker had not tripped after several days while carrying the 3.5 ampere load. Based on engineering judgment l
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46 832SG-1483 Rockwell r March 11, 1983 Page 3 International this time period is believed to be sufficient to h ue achieved
" temperature stabilization and indicates that this load can be carried l continuously for the specified 60-day recombiner post-LOCA operating l duration.
Corrective Action / Comments The results of the tests conducted from January-March 1983 on the EF3-B015, and discussion with ITE Geutd personnel, indicates thst this i
problem may be comon to several lines of ITE thermal magnetic.cfreuit breakers when applied at temperatures >120'F. This includes EF2-B.
EF3-B HE3-B, and JL3-B, all of which hue been used in recombinar i apolications.
ESG is currently conducting a review and some further testing to :
investigate the behavior of the EF-tB. EF3-3, HE3.B. and JL3-B circuit breakers. A further report and recomended corrective actions will be
,e - made If the testing veriffes that these other circuit breakers are not operable in the required environment.
l BWR Recombine. s (Hatch 2, taSalle 1 and 2, Femi-2, Shoreham 1,iMne ~ '
Mile Point-2) ,
As an interim fix, the circuit breaker should be bypassed. Another alternative is to relocate the power cabinet or to provide supplemen-tal cooling of the power cabinet to reduce the temperature to less than 140*F nonoperating (this number includes a 7'F margin). The maximum power cabinet ambient during operation must be determined by measuring the temperature rise in the individual power cabinets under startup conditions and subtracting this value from the 130'F maximum breaker operating temperature. It is expected that the temperature rise in the cabinet is approximately 20'F. Installation of properly sized magnetic breakers is currently considered the permanent correc-tive action.
- i PWR Recombiners (Hartsville & Phipps Bend, Clinton 1 and 2, Byron,;
Palo Verde 1, 2, and 3) ,
l The maximum specified ambient temperature for PWR power and control cabinets is 122*F. The worst case load on the EF3-B015 breaker in PWR :
, applications is the cooling fan motor. A test was conducted to deter-i mine the maximum operating temperature for this breaker in the PWR application. The test condition was 33 amperes applied for 5 seconds to simulate the motor in rush (locked rotor current) imediately followed by 5.6 amperes continuous (full-load running current). Under these conditions the breaker will trip at 130*F. At 120*F local l breaker ambient, the load was carried for several days.
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Mb-83ESG-1483 Rockwell Harch 11, 1983 Page 4 International The temperatureIrise in PWR power and control cabinets has been
] seasured at a cabinet ambient of 72*F and was found to be 20*F.
As an interim fix, the circuit breaker should be bypassed. Another
, alternative is to relocate the power and control caninet or to provide supplemental cooling of the power and control cabinet to reduce the ambient to <100'F. Replacement of the thermal magnetic breakers with magnetic only breakers is being considered as the permanent fix.
Affected Plants .
WRC Licensed ~
Customer Name Facility / Activity M Dete Shipped Detroit Edison Feral 2 ES 6 08 76(2)
Long Island Lighting Company Shorehac 1 NPS 6 02-22-77(2)
- I Georgia Power Company Hatch 2 MPS 6 06-14-77(l)
Niagara Mohawk Power Nine Mile 6 02-23-73(2) '
Corporation . Point 2 NFS ,
! Cocnonwealth Edison LaSalle County 1 4 08-29-78'il .2) and 2 NPS l
Tennessee Valley Authority Hartsville & 8 02-23-79(3)
Phipps Bend HPS Illinois Power Clinton 1 and 2 10 02-08-80(3)
NPS Comonwealth Edison Company Bryon NPS 22 09-09-80(3)
Arizona Public Service Palo Verde 1, 2 12 02-22-79(3)
Company and 3 HPS (1) Operating plant (2) BWR Mark 1 or 2 plants. The recombiner power cabinet for BWR Mark 1 and 2 plants has a maximum post-LOCA ambient operating l temperature requirement of 150*F.
l (3) The recombiner power and control cabinets for PWR and BWR Mark 3 l plants have a maximum post-LOCA ambient temperature requirements of 122'F. The cabinet temperature rise mutt be considered to determine the icipact of PWR* systems. At an ambient temperature of 72*F. the measured value of cabinet temperature rise is 20'F.
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83ESG-1483 Rockwell March 11, 1983 Page 5 International l - Notifications ~
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l Concurrent with this report, each listed plant operator is being notified of our test results and will receive our continuing test results as well. We will further request each plant operator to
. review the actual ambient temperature requirements for his particular I facility in order to more positively define the magnitude of the problem. .
Additional components which failed to function preperly as a' result of our qualification program are given in the references.
If you require further information or clarification, please call me at (213) 700-3326.
Very truly yours. .
N g lI.
J D. C. Empe Dir or ,
Quality Assurance Energy Systems Group 6891A/cp cc: Director, Office of Inspection and Enforcement (3)
U.S. Nuclear Regulatory Comission .
Washington, DC 20555 ,
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