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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20206H2611999-05-0505 May 1999 Part 21 Rept Re Defect Found in Potter & Brumfield Relays. Sixteen Relays Supplied in Lot 913501 by Vendor as Commercial Grade Items.Caused by Insufficient Contact Pad Welding.Relays Replaced with New Relays 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 ML20236N3871998-07-0909 July 1998 Part 21 Rept Re Deficiency Identified in Event 32725, Corrected by Mgp Instruments Inc.Licensee Verified,Affected Equipment Has Been Reworked & Tested at Sce.Design Mod Completed ML18065B1351998-01-0606 January 1998 Part 21 Rept Re Use of Deltstrat Code for RCS Flow Rate Determination.Code Corrects for Temps to Determine Hot Leg Bulk Coolant Temp 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 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 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 ML20217H0511997-08-0505 August 1997 Part 21 Rept Re Discovery That Radiation Monitoring Sys Power Supply Circuit Board Subject to Premature Electronic Component Failure 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 LD-97-002, Part 21 Rept Re Piping Line Loss Between SG & MSIV Inlet When MSSVs Area Activated.Recommends That Utils Confirm Proper Adjustment of MSSV Blowdown Settings So as to Preclude Valve Chatter & Related Structural Concerns1997-01-17017 January 1997 Part 21 Rept Re Piping Line Loss Between SG & MSIV Inlet When MSSVs Area Activated.Recommends That Utils Confirm Proper Adjustment of MSSV Blowdown Settings So as to Preclude Valve Chatter & Related Structural Concerns ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology LD-96-009, Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power1996-04-15015 April 1996 Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power ML20086N9981995-07-21021 July 1995 Part 21 Rept Re Mdr Relays W/Potentially Damaged Internal Contact Arms ML18038A8971994-09-0707 September 1994 Part 21 Rept Re Defect in Latching Mechanism of Potter & Brumfield Relay on C&D High Voltage Shut Down Alarm Assembly Printed Circuit Boards.Pull Test on Relay Reset Button Incorporated Into Receiving Insp Procedures ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head LD-93-139, Part 21 Rept Re Error in Input to Large Break LOCA Analysis. Paint Thickness Factor of Ten Larger than Intended Used for One of Walls in Containment.Caused by Wrong Value Transcribed & Used in LOCA Analysis1993-09-24024 September 1993 Part 21 Rept Re Error in Input to Large Break LOCA Analysis. Paint Thickness Factor of Ten Larger than Intended Used for One of Walls in Containment.Caused by Wrong Value Transcribed & Used in LOCA Analysis ML20056D7071993-07-15015 July 1993 Part 21 Rept Re Reportable defect-75 PSIG Relief Check Valve 1 Npt,Emd 9521844,Kepner 416C-1-75 ML20128C3971993-01-28028 January 1993 Suppl to 921217 Final Part 21 Rept Re Defect on Cast Steel Cylinder Heads.One Addl Part (1A-7680) Discovered Which Was Supplied to Util.Copy of Rept Also Sent to Affected Util ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20087B8551991-11-0808 November 1991 Part 21 Rept 10CFR21-0058 Re Camshaft Bearing Block Assembly Mounting Bolts Found to Be Shorter than Required Length.All Engines Where Camshaft Work Was Performed Will Be Inspected. All Bolts Shorter than 4.531 Inches Will Be Replaced ML20087D1631991-11-0808 November 1991 Rept 10CFR21-0059 Re One Broken Stud & Three Cracked Studs Found at Drivegear End of Left Bank Camshaft Flange.Caused by Sulphide Inclusions.All Broken or Cracked Dowel Bolts Should Be Replaced ML20087B7491991-10-11011 October 1991 Part 21 Rept Re Failure of Seven Camshaft Bearing Block Assembly Mounting Bolts in Diesel Generator.Caused by Use of Shorter Bolts W/Shorter Tolerance.Issue Under Review ML20087B7641991-10-11011 October 1991 Part 21 Rept Re Eight Camshaft Locating Studs in Diesel Engine Found Broken & Three Studs Found Cracked.Caused by Fatigue Loading & Torsional Vibration.Justification for Continued Operation Encl L-91-002, Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl1991-01-0404 January 1991 Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl ML20043F3431990-06-0808 June 1990 Part 21 Rept Re Circumferential Grove of Varying Depth Up to 0.200 Inches on Inside Surface of Journal Above Attachment Weld to Impeller.Failure of Journal Could Result in Major Damage to Pump.Disassembly Scheduled Over Next 18 Months ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating ML20246K7401989-04-26026 April 1989 Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves ML20247P7991989-04-0404 April 1989 Part 21 Rept Re Atmospheric Dump Valves.Cause of Failure Speculative But Result of Piston Ring That Failed to Seal. Resolution to Problem Requires Increasing Pilot Valve Capacity & Reworking of Plug to Enlarge Pilot Flow Area ML20153F5691988-08-10010 August 1988 Part 21 Rept Suppl Re Cracks Discovered in Crosby Valve & Gage Co Safety Valve Guide & Bearing Assemblies.Initially Reported on 870507.Audit of Crosby Design & Mfg Controls Indicated Inconclusive Results.Assemblies Being Replaced ML20154J4101988-05-12012 May 1988 Addendum 1 to Supplemental Part 21 Rept 145 Re Potential Problem w/F-573-156 Pressure Sensor/Lube Oil Trip.Initially Reported on 880429.Addl 1-1/8-inch Diameter W/Deep Counterbone in Pressure Head Added to Activate Valve ML20153B6191988-04-29029 April 1988 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generators Supplied to Utils.Recommends Return of Subj Components in Onsite Warehouse Storage & Suggests Surveillance of Devices Already Installed ML20215G2441987-06-16016 June 1987 Part 21 Rept Re Failure of Load Sequencing Equipment Supplied in Aug 1977 During Scheduled Testing.Caused by Open Electrical Connection on One Crimp Lug.Since 1978,insulated Lugs Used on All Equipment ML20216E4721987-05-28028 May 1987 Part 21 Rept 140 Re Potential Defect in Air Pressure Regulators Mfg by Bellofram.Dripwell Gasket May Fail Due to Mismachining of Gasket Seating Surface Causing Loss of Control Air & Starting Air Pressure ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20214M3181986-09-0404 September 1986 Potential Part 21 Rept Re Contromatics Actuator W/Jackscrew/ Handwheel Emergency Override Operator.Jackscrew/Handwheel Should Be Used for Emergency Manual Operation Only.Encl Ltr Also Sent to Listed Utils/Ae Firms ML20205F6141986-08-13013 August 1986 Part 21 Rept Re Connecting Rod Bolts for Dsrv Engines.Listed Procedures Recommended for Next Connecting Rod Insp, Including Replacement of Bolts Due to Cracked Threads & Large Grooves & Galls in Threads ML20206U0591986-07-0202 July 1986 Part 21 Rept Re Potential Defect in Component of Dsrv Standby Diesel Generators,Involving Problem W/Fastening of Engine Connecting Rod Assembly Which Could Result in Engine Nonavailability.Procedure Will Be Issued by 860718 ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires NRC-86-3142, Part 21 Rept Re Increased Failure Probability of Coils Used in Class 1E Motor Starters & Contactors Supplied to Nuclear Power Plants by Westinghouse.Replacement Coils Mfg for All Starters & Contactors on Encl List1986-06-19019 June 1986 Part 21 Rept Re Increased Failure Probability of Coils Used in Class 1E Motor Starters & Contactors Supplied to Nuclear Power Plants by Westinghouse.Replacement Coils Mfg for All Starters & Contactors on Encl List ML20154N3431986-03-10010 March 1986 Initial Part 21 Rept 135 Re Potential Problem W/Lube Oil Sump Tank Foot Valve of Dsrv Standby Diesel Generator for Facilities.Cause Not Determined.Recommends Utils Inspect Condition of Foot Valve Liners & Notify Tdi of Findings ML20140A5281985-12-19019 December 1985 Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl ML20198C4981985-11-0606 November 1985 Part 21 Rept Re Potential Defect in Dsr or Dsrv Standby Diesel Generator Intake & Exhaust Valve Springs Mfg by Betts Spring Co.Users Recommended to Inspect Engines for Broken Springs & Identify Original Mfg ML20132B0261985-09-0303 September 1985 Part 21 Rept Re Possibility of Engine Ingestion of Unwelded Part in American Air Filter Standby Diesel Generator Intake Silencer.Immediate Hold Should Be Placed on Diesel Engines/Intake Silencers Not Yet in Svc ML20135E2271985-08-23023 August 1985 Part 21 & Deficiency Rept Re Potential Problems W/Natl Valve & Mfg Co Pipe Clamps.Initially Reported on 850613.Ltrs Sent to Purchasers of Pipe Clamps Encl for Perusal ML20135D4481985-08-15015 August 1985 Part 21 Rept Re Raychem auto-trace 20PTV1 self-regulating Electric Heat Tracers & Associated Derivatives.Licensees Advised of Problem & Procedures to Determine Any Effect on Operation ML20125B1481985-05-15015 May 1985 Followup Part 21 & Deficiency Rept Re Failure of General Motors Corp Camshaft Bearing Support Bracket on Diesel Generator 2G003.Components Replaced & Retorqued & Front Bolt Holes on Support Bracket Enlarged ML20077J6091983-07-29029 July 1983 Part 21 Rept Re Inadequately Machined Oil Ring Groove in Upper Half of Motor Bearings.Initially Reported on 830725. Proper Replacement Bearings Installed in All Motors & Corrective Action Request Issued ML20070C7631982-12-10010 December 1982 Part 21 Rept Re Problem W/Brown Boveri Electric,Inc Low Voltage Circuit Breakers W/Solid State Trip Devices.Units from San Onofre 2 & 3 Failed Due to long-term Degradation of Filter Capacitor C205.Suspect Trip Units Should Be Tested 1999-05-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E3381999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Songs,Units 2 & 3 ML20212A1471999-09-13013 September 1999 Special Rept:On 990904,condenser Monitor Was Declared Inoperable.Difficulties Encountered During Component Replacement Precluded SCE from Restoring Monitor to Service within 72 H.Alternate Method of Monitoring Was Established ML20211N0511999-09-0303 September 1999 SER Approving Exemption from Certain Requirements of 10CFR50.44 & 10CFR50 App A,General Design Criterion 41 to Remove Requirements from Hydrogen Control Systems from SONGS Units 2 & 3 Design Basis ML20211Q8201999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Songs,Units 2 & 3. with ML20211H8621999-08-23023 August 1999 Safety Evaluation Accepting Licensee Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20210P4791999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 3 ML20210P4731999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 2 ML20210Q6521999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Songs,Units 2 & 3 ML20210L2771999-07-30030 July 1999 SONGS Unit 3 ISI Summary Rept 2nd Interval,2nd Period Cycle 10 Refueling Outage U3C10 Site Technical Services ML20209C9281999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Songs,Units 2 & 3. with ML20195D3061999-06-0202 June 1999 Safety Evaluation of TR SCE-9801-P, Reload Analysis Methodology for San Onofre Nuclear Generating Station,Units 2 & 3. Rept Acceptable ML20195H5491999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Songs,Units 2 & 3 ML20196L3221999-05-11011 May 1999 SONGS Unit 2 ISI Summary Rept 2nd Interval,2nd Period Cycle-10 Refueling Outage ML20206H2611999-05-0505 May 1999 Part 21 Rept Re Defect Found in Potter & Brumfield Relays. Sixteen Relays Supplied in Lot 913501 by Vendor as Commercial Grade Items.Caused by Insufficient Contact Pad Welding.Relays Replaced with New Relays ML20206S7281999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Songs,Units 2 & 3 ML20205Q6221999-04-19019 April 1999 Safety Evaluation Authorizing Proposed Alternative to Use Wire Penetrameters for ISI Radiography in Place of ASME Code Requirement ML20205R0371999-04-16016 April 1999 SER Approving Proposed Deviation from Approved Fire Protection Program Incorporating Technical Requirements of 10CFR50,App R,Section III.0 That Applies to RCP Oil Fill Piping ML20205G2611999-04-0101 April 1999 Special Rept:On 990328,3RT-7865 Was Removed from Service. Monitor Is Scheduled to Be Returned to Service Prior to Mode 4 Entry (Early May 1999) Which Will Exceed 72 H Allowed by LCS 3.3.102.Alternate Method of Monitoring Will Be Used ML20205Q0981999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Songs,Units 2 & 3 ML20204F8101999-02-28028 February 1999 Monthly Operating Repts for Songs,Units 2 & 3.With ML20203J1981999-02-12012 February 1999 Safety Evaluation Supporting Amends 149 & 141 to Licenses NPF-10 & NPF-15,respectively ML20202F7041999-01-21021 January 1999 Special Rept:On 990106,SCE Began to Modify 2RT-7865.2RT-7865 to Allow Monitor to Provide Input to New Radiation Monitoring Data Acquisition Sys.Monitor Found to Exceeds 72 H Allowed Bt LCS 3.3.102.Alternate Monitoring Established ML20199F0771998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Songs,Units 2 & 3 ML20206H2101998-12-31031 December 1998 SCE 1998 Annual Rept ML20198A6731998-12-11011 December 1998 Special Rept:On 981124,meteorological Sys Wind Direction Sensor Was Observed to Be Inoperable.Caused by Loss of Communication from Tower to Cr.Sensor Was Replaced & Sys Was Declared Operable on 981204 ML20196D8901998-11-30030 November 1998 Non-proprietary Reload Analysis Methodology for Songs,Units 2 & 3 ML20198C3471998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Songs,Units 2 & 3 ML20195H2471998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Songs,Units 2 & 3 ML20154B7211998-10-0101 October 1998 Safety Evaluation Approving Licensee Request to Implement Alternatives Contained in Code Case N-546 for Current Interval at Songs,Units 2 & 3 Until Code Case Approved by Ref in Reg Guide 1.147 ML20154M7921998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Songs,Units 2 & 3 ML20155F6081998-09-17017 September 1998 Non-proprietary Version of San Onofre 2 & 3 Replacement LP Rotors ML20151Z9851998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Songs,Units 2 & 3 ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers 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 ML20198G4491998-07-31031 July 1998 Rev 1 to WCAP-15015, Specific Application of Laser Welded Sleeves for SCE San Onofre Units 2 & 3 Sgs ML20237B8571998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Songs,Units 2 & 3 ML20236N3871998-07-0909 July 1998 Part 21 Rept Re Deficiency Identified in Event 32725, Corrected by Mgp Instruments Inc.Licensee Verified,Affected Equipment Has Been Reworked & Tested at Sce.Design Mod Completed ML20236R1031998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Songs,Units 2 & 3 ML20249A9431998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Songs,Units 2 & 3 ML20248B8981998-05-26026 May 1998 Updated SG Run Time Analysis Cycle 9 ML20248B9221998-04-30030 April 1998 Rev 0 to AES 98033327-1-1, Updated Probabilistic Operational Assessment for SONGS Unit 2,Second Mid Cycle Operating Period,Cycle 9 ML20247L5181998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Songs,Units 2 & 3 05000361/LER-1998-003, LOCA Evaluation of Safety Significance of Failure of Emergency Sump Valve Linestarter (LER 1998-003)1998-04-0606 April 1998 LOCA Evaluation of Safety Significance of Failure of Emergency Sump Valve Linestarter (LER 1998-003) ML20217Q6161998-04-0505 April 1998 Failure Analysis Rept 98-005,Failure Analysis of 2HV9305 Motor Starter ML20217A0141998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Songs,Units 2 & 3 ML20217D4701998-03-0202 March 1998 Rev 1 to 90459, Failure Modes & Effects Analysis DG Cross- Tie,DCP7048.00SE ML20216J3551998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Songs,Units 2 & 3 ML20203E7301998-02-17017 February 1998 SER Accepting 980105 Request to Use Mechanical Nozzle Seal Assembly as Alternate Repair Method,Per 10CFR50.55a(a)(3)(1) for Plant,Units 2 & 3 ML20203K9141998-02-0303 February 1998 Rev 0 to ESFAS Radiation Monitor Single Failure Analysis. W/96 Foldout Drawings ML20202F9731998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Songs,Units 2 & 3 1999-09-30
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MEL%R4sW1W1155 frax:949-368-7575 May 6 '99 12:20 P.02
, SOUTHERN CAUFORNIA EDISON =g-Ancmsommunouv c ,..,
May 5,1999 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
10CFR Part 21 Notification - Potter & Brumfield Relays San Onofre Nuclear Generating Station, Units 2 & 3 in accordance with 10CFR 21.21(d)(3) and 21.21(d)(4), the attachment to this letter reports a defect found in Potter and Brumfield (P&B) relays. Sixteen P&B relays, model KUP93-14A32-120. were supplied in lot '913501" by the vendor as commercial grade items and were dedicated for nuclear service at San Onofre Nuclear Generating Station by Southern California Edison (SCE). SCE's laboratory analyses of four of these relays determined the contact pads were insufficiently welded to their contact arms and could become detached. Based on a review of relay failure history, SCE has concluded the insufficient contact pad welding is limited to lot 913501.
i SCE replaced these relays with new P&B relays which have contact pads that are riveted to their contact arm, thus precluding contact pad detachment.
l My signature below satisfies the notification requirements of 10CFR21.21(d)(4). If you '
require any additional information, please contact me or Mr. Ken Slagte at (949)368 6631.
I Sincere!
\ : .w I
Attachment 1 cc: E. W. Merschoff, Regional Administrator, NRC Region IV J. A. Sloan, NRC Resident inspector, San Onofre Units 2 and 3 L. Raghavan, NRC Project Manager, San Onofre Units 2 and 3 institute of Nuclear Power Operations (INPO)
P. O. Box 128 San Cicmeme. CA 926744126 #
- 9. 68 490
- NUCLEAR REG AFFAIRS Fax:949-368-7575 May 6 '99 12:21 P.03 4
a Attachment i 10 CFR Part 21 Report on P&B Relays Page 1 of 2 A. CoiTw+,1 Supplier 1
Potter & Brumfield (A Siemens Co.)
200 South Richland Creek Drive Princeton, Indiana 47671 (812) 386-2211 B. Nature of defect:
On March 30,1999, SCE opened the shipping box for new relays, P&B Model .
Number KUP93-14A32-120, and fcund one contact pad was detached from its contact arm in three relays. A review of relay failure history recognized that, in l December of 1998, this same type of relay had failed after 3 years of service. A total of 16 relays from lot '913501"were purchased from Potter & Brumfield as commercial grade items in 1991 and dedicated by SCE for safety related applications.
1 Each relay contains three contact arms with each having four contact pads for a total of twelve contact pads. One of the twelve contact pads was missing in the middle moving arm at the normally closed contact position in these four relays.
Laboratory analysis determined that the contact pads were inadequately fused to the contact arms. Microscopic inspection found only a small weld area between the contact pad and its mating surface on the contact arm. This same condition also existed on the remaining contact pads, although they were still attached. Without a contact pad, there was no make-up connection to close on demand. Therefore, the cause of the defect was insufficient welding of the contact pads to the contact arm.
C. Date defect discovered:
SCE discovered this deviation on March 30,1999, prior to replacement of the rela during preventative maintenance for auxiliary building emergency chiller. On April 29,1999, SCE completed an evaluation and concluded this condition constitutes a defect of a basic component.
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NLLtN kt6 RFFRIRS Fax:919-368-7575 May. 6 '99 12:21 p,04
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Attachment 1 10 CFR Part 21 Report on P&B Relays Page 2 of 2 D. Component location:
A total of 16 relays are installed in each train of auxiliary building emergency chillers, SA1513ME335 and ME336. Eleven of the 16 relays in each train are used for alarming functions only; the remaining 5 relays are used for control functions.
E. Corrective actions:
The installed relays from lot "913501" were replaced with new P&B relays containing contact pads which are riveted to their contact arms.
One of the new replacement relays was checked for contact pad-to contact arm bond integrity. Microscopic inspection found that the new P&B relays have contact pads which are riveted to the contact arm instead of welded. This bonding method does not allow the contact pads to become disengaged from their contact arms.
This defect was determined to be specific to lot 913501 based on the following actions.
1.
A pull test to check contact bonding integrity was performed on six other relay lots. The contact pads could not be dislodged from their contact arms. l 2.
One relay from lot *E9120" was also randomly selected for laboratory analysis. Microscopic inspection found that the contact pads had been fused to the contact arms and could not be dislodged from their contact arms 3.
A review of relay failure history indicated that no s!milar failures have occurred at San Onofre from P&B manufacturing lots other than lot 913501. i SCE will enhance the dedication plan for control relays to measure the conta resistance on all relay contacts.
F. Other pertinent information: '
SCE has not supplied this type of component nor has knowledge of it's use at another facility. However, this type of component may have also been dedica nuclear use by another facility.
F \
OV0WI999 U.S. Nucle:r Regul: tory Commission Oper:tions Center Event Report Pagei Power Reactor Event # 35685 I Site: SAN ONOFRE Notification Date / Time: 05/06/1999 15:12 (EDT) l Unit: 2 3 Region: 4 State : CA Event Date iTime: 05/05/1999 (PDT) ,
Reactor Type: [1] W-3-LP,[2] CE,[3] CE Last Modification: 05/06/1999 Containment Type: DRY AMB DRY AMB NRC Notified by: WILLIAMS Notifications: BILL JONES Pv1 HQ Ops ONker: CHAUNCEY GOULD NRR VERN HOGE (FAX)
Emergency Class: NON EMERGENCY 10 CFR Section:
21.21 UNSPECIFIED PARAGRAPH Unit l Scram Code lRX Critinit Power initial RX Mode Curr Power Current RX Mode 2 N Yes 100 Power Operation 100 Power Operation 3 N No 0 Hot Shutdown 0 Hot Shutdown THE LICENSEE HAS DETERMINED THAT A MANUFACTURING DEFECT IS PRESENT ON SOME OF THE POTTER AND BRUMFIELD (P&B) RELAYS THEY HAVE AT THE SITE.
SIXTEEN P&B RELAYS, MODEL "KUP93-14A32-120", WERE SUPPLIED IN LOT "913501" BY THE VENDOR AS COMMERC!AL GRADE ITEMS AND WERE DEDICATED FOR NUCLEAR SERVICE AT SAN ONOFRE.
THE LICENSEE'S LAB ANALYSIS OF FOUR OF THESE RELAYS DETERMINED THE CONTACT PADS VERE INSUFFICIENTLY WELDED TO THEIR CONTACT ARMS AND COULD BECOME DETACHED. BASED ON l THEIR REVIEW OF RELAY FAILURE HISTORY, THE LICENSEE CONCLUDED THE INSUFFICIENT CONTACT PAD WELDING IS LIMITED TO LOT "913501" THESE RELAYS HAVE BEEN REPLACED WITH NEW P&B RELAYS WHICH HAVE THE CONTACT PADS RIVETED TO THEIR CONTACT ARM, THUS PRECLUDING ANY CONTACT DETACHMENT.
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