Significant Deficiency Rept 413-414/80-02 Re Three Relays & Trip Devices Not Meeting Relay time-current Characteristic Specs for Application.Caused by Copper Migration within Motorola Scrs.Relays & Trip Devices Will Be ChangedML19312D512 |
Person / Time |
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Site: |
Catawba |
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Issue date: |
02/29/1980 |
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From: |
DUKE POWER CO. |
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To: |
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Shared Package |
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ML19312D508 |
List: |
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References |
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413-414-80-02, 413-414-80-2, NUDOCS 8003240527 |
Download: ML19312D512 (2) |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20203H9891997-12-12012 December 1997 Part 21 Rept Re Potential Manufacturing Defect of Enterprise DSR-4 & DSRV-4 Edgs.Cooper Energy Svcs Supplied 1A-7840 Adjusting Screw to Affected Utils & Sites.River Bend Station Replaced W/Acceptable Assemblies 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 ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause ML20115D2001996-07-0909 July 1996 Part 21 Rept Re Mfg Defect of Enterprise DSR-4 & DSRV-4 Edgs,Originally Mfg by Calcon Corp.Amot Control Corp Purchased Calcon Product Line & Maintains Design & Production.Valves Returned to Cooper Energy Svcs on 960131 ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs 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 B14544, Update to 900827 Rept of Substantial Safety Hazard Re GE Custom 8000 Horizontal Induction Motors,Reported Per 10CFR21 for Unit 3.Util Has Determined,As Part of Review of in 91-007 That Subj GE Motors Also Used at Units 1 & 21993-08-11011 August 1993 Update to 900827 Rept of Substantial Safety Hazard Re GE Custom 8000 Horizontal Induction Motors,Reported Per 10CFR21 for Unit 3.Util Has Determined,As Part of Review of in 91-007 That Subj GE Motors Also Used at Units 1 & 2 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 ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ET-NRC-92-3707, Part 21 Rept Re Degraded Performance Condition of Westinghouse Protection Sys Overtemp Delta Temp Reactor Trip Function.Issue Not Reportable,Per 10CFR21,based on Diversity of Westinghouse Protection Sys,Per WCAP-73061992-06-15015 June 1992 Part 21 Rept Re Degraded Performance Condition of Westinghouse Protection Sys Overtemp Delta Temp Reactor Trip Function.Issue Not Reportable,Per 10CFR21,based on Diversity of Westinghouse Protection Sys,Per WCAP-7306 ML20055E4831990-06-29029 June 1990 Part 21 Rept Re Defective Steam Generators Supplied by Westinghouse.Util Will Continue to Rept Any Defects or Other Info Reportable Under 10CFR21 Upon Discovery &/Or During Litigation ML20043G7641990-05-22022 May 1990 Part 21 Rept Re Potential Defect W/Speed Transmitter in Diesel Engine Control Panel of Dsrv Standby Diesel Generator.Estimate of Completion of Corrective Actions Not Possible,Since Correction Made by Other Companies ML17348A1621990-03-27027 March 1990 Part 21 Rept Re Matls W/Programmatic Defects Supplied by Dubose Steel,Inc.Customers,Purchase Order,Items & Affected Heat Numbers Listed ML19351A2941989-10-0909 October 1989 Part 21 Rept Re Potential of Ambient Compensated Molded Case Circuit Breakers to Deviate from Published Info. Instantaneous Trip Check Will Be Instituted on All Class 1E Thermal/Magnetic Ambient Breakers Prior to Shipment 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 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 ML20207P0451988-10-0505 October 1988 Part 21 Rept 146 Re Defect in Left Intercooler Inlet Adapter on Standby Diesel Engine Generator.Recommends Utils Inspect Left Intake Manifold Drain as Part of Operating Plan.Addl Info Expected by 881015 ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking 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 ML20151A2801988-03-30030 March 1988 Part 21 Rept Re Broken/Cracked Springs in Plant Pressure Valves.Magnetic Particle Exam of Springs from 18 Valves on Unit 2 Performed in Jan 1988 & Spring from Valve BS-02893 Rejected for Linear Indication.Insp Completed ML20236E4851987-07-27027 July 1987 Corrected Part 21 Rept Re Broken/Cracked Springs in Consolidated Type 3787WA Valves.Valves Incorrectly Identified as Type 3727WA in 870203 & 0702 Ltrs.Unit 1 Springs Received Magnetic Particle Exam 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 ML20214E1971987-02-0303 February 1987 Annotated Part 21 Rept Re Cracked D34 Springs in Alco Spring Industries,Inc Type 3727WA Safety Valves.All Springs Being Examined.Springs Displaying Relevant Indications Will Be Replaced 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 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 ML20214D5071986-02-19019 February 1986 Final Significant Deficiency Rept SD 414/86-01 Re Emergency Diesel Engine 2B Main Bearing 7 Failure.Initially Reported on 860116.Caused by Misinstallation by Mfg,Sand Blast Grit &/Or Oil Contamination.Engine Rebuilt ML20137P2381986-01-16016 January 1986 Significant Deficiency Rept SD 414/86-01 Re Failure of Main Bearing Shell 7 During Break in Run of Tdi Unit 2B Diesel Generator.Initially Reported on 851219.Installation Procedures Enhanced.Crankshaft Journal Cleaned ML20137P2411986-01-16016 January 1986 Significant Deficiency & Part 21 Rept SD 414/86-02 Re Valve Spring Failures on Tdi DMRV-16-4 Diesel Engines.Initially Reported on 851217.Springs Will Be Changed During First Appropriate Refueling Outage ML20137N4991985-12-26026 December 1985 Significant Deficiency Rept 414/85-12 Re Missing Spring in Air Actuator of Pressurized Porv.Initially Reported on 851206.Valve W/Missing Spring Replaced.Investigation Continuing ML20137K9601985-12-10010 December 1985 Part 21 Rept Re Actuators Having Only One of Required Two Springs Which Could Result in Reduction of Integrity of Reactor Coolant Boundary.Valves Supplied to McGuire Units 1 & 2 & Catawba Unit 2.Catawba Unit 2 Valve Corrected ML20138B7201985-11-22022 November 1985 Final Significant Deficiency Rept SD 414/85-10 Re Failure of Hydrogen Skimmer Fan Motors Supplied by Joy Mfg Co.Initially Reported on 850626.Cause Undetermined.Fan Motors Reassembled,Retested & Reinstalled 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 ML20136E5821985-11-0505 November 1985 Significant Deficiency Rept 414/85-11 Re High Priority Mods Required Prior to Fuel Loading.Administrative Controls Implemented to Control Personnel Access to Penetration Area During in-core Instrument Movement ML20198C2081985-10-24024 October 1985 Significant Deficiency Rept SD 414/85-11 Re Unconsidered Effects of Radiation Streaming Through Reactor Bldg Penetrations from post-LOCA Atmospheric Activity.Initially Reported on 850924 ML20205F4701985-10-18018 October 1985 Final Part 21 & Significant Deficiency Rept SD 414/85-05 Re Potential Problem W/Starting Air Check Valves in on-engine Modified Starting Air Piping.Initially Reported on 850419. Modified Disk Assemblies Installed ML20235C9361985-09-0404 September 1985 Part 21 Rept Re Consolidated 3787WA Safety Valve Spring Failure for Plant.Investigation Indicated That Presence of Precracks Filled W/Nonmetallic Deposits Combined W/Low Impact Strength to Cause Preservice Failures 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 ML20135E5461985-08-30030 August 1985 Significant Deficiency Rept 414/85-07 Re Required Mods to Battery Racks.Mods to Battery Racks Will Be Implemented & Rejarred Battery Cells Will Be Installed by 851101 ML20134N0441985-08-15015 August 1985 Significant Deficiency Rept 414/85-06.Work on Listed Nonconforming Items Complete ML20133P1511985-07-26026 July 1985 Significant Deficiency Rept SD 414/85-10 Re Failure of Joy Mfg Co Hydrogen Skimmer Fans in Assemblies Designed by Reliance Electronic Co.Initially Reported on 850626.Fans Disassembled for Evaluation.Next Rept Expected by 851101 ML20133N4311985-07-24024 July 1985 Supplemental Significant Deficiency Rept SD 414/85-08 Re Overpressurization of Components of RHR Sys,Boron Recycle Sys & Nuclear Sampling Sys.Only 150 Lb Flanges Require Replacement.Other Piping Acceptable ML20133N8781985-07-24024 July 1985 Supplemental Significant Deficiency Rept SD 414/85-06 Re Chemical & Vol Control Sys.Engineering Evaluation of Undamaged Portions of Sys for Overpressurization Included 1999-04-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H0201999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Catawba Nuclear Station,Units 1 & 2 ML20216E5401999-09-0707 September 1999 Special Rept:On 990826,discovered That Meteorological Sys Upper Wind Speed Cup Set Broken,Causing Upper Wind Channel to Be Inoperable.Cup Set Replaced & Channel Restored to Operable Status on 990826 ML20212B4711999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217H0321999-08-31031 August 1999 Revised Monthly Operating Rept for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20211A9791999-08-20020 August 1999 Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20211C1291999-08-17017 August 1999 ISI Rept Unit 1 Catawba 1999 RFO 11 ML20210R1051999-08-0606 August 1999 Special Rept:On 990628,cathodic Protection Sys Was Declared Inoperable After Sys Did Not Pass Acceptance Criteria of Bimonthly Surveillance.Work Request 98085802 Was Initiated & Connections on Well Anode Were Cleaned or Replaced ML20210S2891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2 ML20212B4871999-07-31031 July 1999 Revised Monthly Operating Rept for July 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20210S2951999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209H4501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209H4561999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20196A0001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206P5201999-05-14014 May 1999 Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206N8391999-05-0404 May 1999 Rev 16 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr ML20206R1811999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20196A0041999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206N8261999-04-22022 April 1999 Rev 15 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr. Page 145 of 270 of Incoming Submittal Not Included ML20205S5551999-04-21021 April 1999 Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20205N3651999-04-12012 April 1999 Safety Evaluation Accepting IPE of External Events Submittal ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20206R1931999-03-31031 March 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20205P9521999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Catawba Nuclear Station,Units 1 & 2 ML20205P9561999-02-28028 February 1999 Revised Monthly Operating Repts for Feb 1999 for Catawba Nuclear Station,Units 1 & 2 ML20204C9111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Catawba Nuclear Station,Units 1 & 2 ML20203A2581999-02-0505 February 1999 Safety Evaluation of TR DPC-NE-3002-A,Rev 2, UFSAR Chapter 15 Sys Transient Analysis Methodology. Rept Acceptable. Staff Requests Duke Energy Corp to Publish Accepted Version of TR within 3 Months of Receipt of SE ML20204C9161999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for Catawba Nuclear Station,Units 1 & 2 ML20199K8711999-01-13013 January 1999 Inservice Insp Rept for Unit 2 Catawba 1998 Refueling Outage 9 ML20199E3071998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Catawba Nuclear Station,Units 1 & 2 ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20205E9441998-12-31031 December 1998 1998 10CFR50.59 Rept for Catawba Nuclear Station,Units 1 & 2, Containing Brief Description of Changes,Tests & Experiments,Including Summary of Ses.With ML20206P2081998-12-31031 December 1998 Special Rept:On 981218,inoperability of Meteorological Monitoring Instrumentation Channels,Was Observed.Caused by Data Logger Overloading Circuit.Replaced & Repaired Temp Signal Processor ML20203A4101998-12-22022 December 1998 Rev 16 to CNEI-0400-25, Catawba Unit 2 Cycle 10 Colr ML20203A4041998-12-22022 December 1998 Rev 14 to CNEI-0400-24, Catawba Unit 1 Cycle 11 Colr ML20198B1341998-12-14014 December 1998 Revised Special Rept:On 980505,discovered That Certain Fire Barriers Appeared to Be Degraded.Caused by Removal of Firestop Damming Boards.Hourly Fire Watches Established in Affected Areas ML20196J8351998-12-0808 December 1998 Safety Evaluation Granting Relief Request Re Relief Valves in Diesel Generator Fuel Oil Sys ML20199E3221998-11-30030 November 1998 Revised MOR for Nov 1998 for Catawba Nuclear Station,Units 1 & 2 Re Personnel Exposure ML20198E3151998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Catawba Nuclear Station,Units 1 & 2 ML20196C0251998-11-27027 November 1998 SER Accepting Clarification on Calibration Tolerances on Trip Setpoints for Catawba Nuclear Station ML20196A6881998-11-25025 November 1998 Safety Evaluation Granting Relief Request 98-02 Re Limited Exam for Three Welds ML20196D4041998-11-19019 November 1998 Rev 1 to Special Rept:On 980618,determined That Method Used to Calibrate Wind Speed Instrumentation Loops of Meteorological Monitoring Instrumentation Sys Does Not Meet TS Definition for Channel Calibration.Procedure Revised ML20195E5521998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Catawba Nuclear Station,Units 1 & 2 ML20198E3261998-10-31031 October 1998 Revised Monthly Operating Repts for Oct 1998 for Catawba Nuclear Station,Units 1 & 2 ML20154M7661998-10-12012 October 1998 LER 98-S01-00:on 980913,terminated Vendor Employee Entered Protected Area.Caused by Computer Interface Malfunction. Security Retained Vendor Employee Badge to Prevent Further Access & Computer Malfunction Was Repaired.With 1999-09-07
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h/., .g CATAWBA NUCLEAR STATION Report No.: SD 413-414/80-02 Report Date: February 29, 1980 Facility: Catawba Nuclear Station - Units 1&2 Identification of Deficiency: Solid State Protective Relays and Trip Devices--Deficiency SCR's Initial Report:
On January 31, 1980, Mr. Milt Hunt of NRC Region II, At_;;ta, Georgia, was notified of this deficiency by Mr. J. R. Wells, B. M. Rice, W. J.
Foley and D. M. Clark of Duke Power Company. -
Supplier and/or Component:
The items found to contain the deficiency were solid state relays manu-factured by Gould-Brown Boveri, Horsham, Pennsylvania and consist of Types 1TE-51L and ITE-51Y overcurrent relays and Type SS46 (Power Shield) solid state trip device. The component that has been identified as causing the deficiency was Motorola, Inc. SCR's types 1379 and 1235.
Additional Gould-Brown Boveri relay types GR-5, Ground Fault Relay, and Type ITB-50, overcurrent relay also contain similar type SCR's.
Description of Deficiency:
During relay and trip device acceptance and system startup testing, it was determined that three relays and trip devices did not meet the Time-Current characteristic specifications of the relay for its application (i.e. , the relay or device would trip at a' lower level of current or time than its setting). Preliminary investigations indicated that the output SCR in the relays was deficient. sone relay was returned to the manufacturer for investigation. The relay manufacturer and SCR manu-facturer have evaluated and analyzed the deficiency and advise that the deficiency has been caused by " copper migration" within the SCR. The copper migration was from the top metal system into the bulk silicon material which would result in its failure. The migration is a direct function of temperature and time. The deficiency is further described
'in a' letter dated February 11, 1980 to Mr. Victor Stello, NRC/0IE, from Mr. D. D. Duvall of Could-Brown Boveri. However, that report incorrectly identifies how or where the deficiencies were detected. The deficiencies were identified initially during testing at McGuire Nuclear Station rather than at Catawba Nuclear Station. The manufacturer is conducting further evaluations to determine if the SCR deficiency is lot or batch related or purely random.
8 00gg y
Analysis of Safety Implication:
Only three relays out of 829 relays have been found deficient and none of these were in safety circuits. The investigation is continuing by Duke and the manufacturar to determine if those in safety-related circuits could be affected by the same problem.
-Corrective Action:
All relays and trip devices containing the specific type of SCR's that are within safety circuits have been identified. The SCR's that were removed from McGuire Nuclear Station are being returned to the manufacturer for further analysis and evaluation to determine if the deff. sacy is confined to a batch, a lot or are random. Upon completion of this evaluation or any identification of deficiencies in the subject relays
.or trip devices in safety-related circuits, action will be undertaken to change out those SCR's and trip devices as required to correct any deficiency. The change out of any SCR's and trip devices identified by-
.the evaluation is anticipated to be completed by January 1, 1981. A final report will be provided at that time.
M 9