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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217N3271999-10-21021 October 1999 Part 21 Rept Re non-linear Oxygen Readings with Two (2) Model 225 CMA-X Containment Monitoring Sys at Bsep.Caused by High Gain Produced by 10K Resistor Across Second Stage Amplifier.Engineering Drawings Will Be Revised ML20236P0451998-07-0808 July 1998 Part 21 Rept Re non-conformance & Potential Defect in Component of Nordberg Model FS1316HSC Standby Dg.Caused by Outer Spring Valves Mfg from Matl That Did Not Meet Specifications.Will Furnish Written Rept within 60 Days ML20198J0431997-07-28028 July 1997 Update to Amended Interim Part 21 Rept Re Harness/Positive Plate Lug Disconnect on List Ish Round Cell Battery.Requests 7-10 Day Extension to Complete Review ML20134L1081996-10-10010 October 1996 Part 21 Rept Re Defect in Component of Nordberg Model FS1316HSC Sdg.Nak Engineering,Inc Has Established & Adopted Procedures to Assemble Fuel Oil Lines & Climinate Possible Defective Condition ML20116H2031996-08-0505 August 1996 Part 21 Rept Re Potential Defect on Condition in Component of Nordberg Model FS1316HSC Sdg W/Fuel Injection Line Assembly Which Connects Fuel Pump to Injector.Caused by Loose Fuel Line Sleeve ML20097A5641996-01-31031 January 1996 Final Part 21 Rept Re Ball Valves Supplied by Cardinal Industrial Products Containing Suspect Pressure Boundary Bolting.Valves Containing Suspect Bolts Returned to Canadian Worcester Controls Ltd to Have Bolting Replaced ML20092H3641995-09-13013 September 1995 Part 21 Rept Re 3/4 Inch ASME Section III Class 2 Ball Valves Supplied by Canadian Worcester Controls Ltd (Cwcl) ML20086D9901995-07-0303 July 1995 Part 21 Rept Re Two Failures of Model Vtr 500 Turbochargers Supplied by Abb Turbo Systems Ltd.Failure of Turbocharger Renders Associated EDG Incapable of Providing Rated Output. Seventeen Hole Jet Assist Wall Plates Replaced ML20073S9541994-06-27027 June 1994 Part 21 Rept Re Incorrect Matl Supply Discovered on Unshipped Order.Pump Div Will Notify Enertech W/ Recommendation That Items Supplied W/Incorrect Matl Be Removed & Destroyed ML20070A1441994-06-22022 June 1994 Part 21 Rept Re Conditions Which Affect Hydraulic Valve Operators Supplied by Bw/Ip to Enertech Co & Listed Utils. Vendor Will Notify Enertech W/Recommendations That All Items Supplied W/Incorrect Matl Be Removed & Destroyed ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical 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 ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option 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 ML20095J3061992-04-24024 April 1992 Initial Part 21 Rept Re Defectively Installed Bolting in Emergency Diesel Generator Bldg Internal Wall Seismic Supports.Repairs to Reestablish Seismic Qualification of Walls Continuing & Emergency Buses Declared Inoperable ML20079G8921991-08-27027 August 1991 Part 21 Rept Re Failure of Normally Energized Asco Model L206-832 Solenoid Valves Due to Gelling of Lubricant (Dow Corning 550).Initially Reported on 910826 Via Telcon.Ler 2-91-005 Re ESF Actuations Caused by Transient Encl BSEP-91-0191, Part 21 Rept Re Discrepancy Noted Between Torque Indicated by motor-actuator Characterization Sys & Output Torque Measured by Limitorque Actuator Test Stand.Initially Reported on 910426.Vendor Contacted Re Software Problem1991-04-29029 April 1991 Part 21 Rept Re Discrepancy Noted Between Torque Indicated by motor-actuator Characterization Sys & Output Torque Measured by Limitorque Actuator Test Stand.Initially Reported on 910426.Vendor Contacted Re Software Problem ML20077A4041991-04-29029 April 1991 Deficiency Rept Re Possible Mfg Problems W/Certain Coils Used on Asco Nuclear Qualified Valves.Problems Discussed in NRC Info Notice 86-057.All Purchasers Will Be Notified & Replacement Product Will Be Offered If Item Still in Svc 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 ML20043A6091990-04-27027 April 1990 Part 21 Rept Re Defective Axial Cracks in Pump Shaft in Region Immediately Above Impeller & in Reactor Recirculation Pumps.Probably Caused by Crack Growth as Thermal Fatigue. Technical Advisory Bulletin Will Be Sent to Each Util 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 ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML20011D4321989-12-15015 December 1989 Suppl to Part 21 Rept Re Completion of Replacement of Unit 1 CR205 Series Auxiliary Contacts w/CR305 Contacts.Initially Reported on 871030.Implementation of Five of Six Auxiliary Contacts Extended Until 900131 ML19325E4571989-10-20020 October 1989 Part 21 Rept Re Potential Inconsistencies in Mac Diagnostic Sys Software.Licensee to Review All Smb,Sb & Sbd Size 3 Mac Torque Test Data Using Mac Software Version 2.96 to Insure That Torque Switch Settings Meet Valve Design Requirements 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 BSEP-89-0342, Part 21 Rept Re Problem in Pump Suction & Discharge Valves of Standby Liquid Control Sys.Initially Reported on 890427. Evaluation Found Defect Consisting of Casting Flaws/Surface Irregularities in Valves1989-05-0101 May 1989 Part 21 Rept Re Problem in Pump Suction & Discharge Valves of Standby Liquid Control Sys.Initially Reported on 890427. Evaluation Found Defect Consisting of Casting Flaws/Surface Irregularities in Valves 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 BSEP-87-1205, Part 21 Rept & Deficiency Rept Re Defective GE CR205X Series Auxiliary Contacts.Initially Reported on 871027.Contacts for Loads Listed in Attachment 3 Will Be Replaced on Unit 1 by 880701 & by 881101 on Unit 21987-10-30030 October 1987 Part 21 Rept & Deficiency Rept Re Defective GE CR205X Series Auxiliary Contacts.Initially Reported on 871027.Contacts for Loads Listed in Attachment 3 Will Be Replaced on Unit 1 by 880701 & by 881101 on Unit 2 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 ML20203D0221986-07-14014 July 1986 Part 21 Rept Re Air Monitoring Sys Probes Exhibiting Blue Tip Rather than Normal White Tip & Insensitive to Chlorine. Caused by Improper Handling/Storage.Advisory Bulletin Encl. Item Not Reportable Per Part 21 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 ML20141N8511986-03-11011 March 1986 Part 21 Rept Re Valves W/Improperly Qualified Cardinal Industrial Products Corp Stock Matl Furnished to Listed Customers.Matl Deviated from ASME Section III,NCA-3800. Results of Test Repts of Stock Valves Forthcoming 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 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 BSEP-85-1850, Part 21 & Deficiency Rept Re 12 of 16 Rockwell Edward Valves Exceeding Leak Rate Criteria as Specified by Procurement Documentation.Initially Reported on 850705. Valves Returned to Vendor for Cause Determination1985-10-18018 October 1985 Part 21 & Deficiency Rept Re 12 of 16 Rockwell Edward Valves Exceeding Leak Rate Criteria as Specified by Procurement Documentation.Initially Reported on 850705. Valves Returned to Vendor for Cause Determination ML20134Q1741985-08-29029 August 1985 Part 21 Rept Re Potential Maint Issues Associated w/Anker-Holth Snubbers.Owners of Anker-Holth Snubbers Will Be Informed of Problems & Sent Revs to Technical Instruction Manuals to Include Procedures for Seal & Fluid Maint ML20210G9921985-08-13013 August 1985 Part 21 Rept Re Failure of Isolated Worm Shaft Gear When Certain Critical Speeds Combined W/Repetitive Transfer of Actuator Clutch Mechanism from Manual (Handwheel) to Motor Drive Mode.Two Possible Solutions Noted ML20133N4691985-08-0505 August 1985 Part 21 Rept Re Raychem Wcsf Shrink Sleeving for Sensor/ Connecting Assembly of Safety Relief Valve Monitoring Sys. Testing & Retesting in Progress.Sensor Installation Utilizing Shrink Sleeving Recommended ML20127E3111985-06-19019 June 1985 Part 21 Rept Re Potential Separation of Aluminum Nameplate from Hevi-Duty Type Sbw or Szo Transformers in Nelson Electric Class 1,035-volt Motor Control Ctrs,W/Potential Short Circuit.Initially Reported on 850618 ML20125B1611985-06-0606 June 1985 Supplemental Part 21 Rept Re Addl Circuit Breakers,Furnished as Spares,W/Overcurrent Trip Devices That May Have Short Time Delay Band Lever.Items Require Insp & Replacement If Link Found Incorrect ML20101P2011984-12-26026 December 1984 Deficiency & Part 21 Rept Re Quench Cracks Discovered in Sure Loc,Inc ASME Class 2 Hex Nuts.Supplier Notified.Nuts Will Be Replaced as Necessary ML20093M2391984-10-0303 October 1984 Supplemental Response to Part 21 Rept Re Leak or Break on Certain Piping Sys Outside Pipe Tunnel.Initially Reported in Apr 1982.Mods to Resolve Deficiency Scheduled to Be Consistent W/Resolution of Environ Qualification Issue ML20094D8761984-07-13013 July 1984 Second Interim Deficiency Rept,Item 160 Re Defective Shop Welds on Seismic Restraint Structures.Initially Reported on 840306.Next Rept Anticipated by 850331 ML20091P6771984-06-0808 June 1984 Part 21 Rept Responding to Re QA Problems W/Hvac Equipment Mfg by Bahnson Co.Equipment Will Be Reviewed to Determine Deficiencies,Including Catawba & Oconee Air Handling Units ML20091G2071984-05-24024 May 1984 Part 21 Rept Re Bug in Detector Computer Code Resulting in Possible Miscalculation of Tech Spec Parameters for Enthalpy Rise Peaking Factor.Problem Corrected & Responsible Parties Notified 1999-10-21
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N3271999-10-21021 October 1999 Part 21 Rept Re non-linear Oxygen Readings with Two (2) Model 225 CMA-X Containment Monitoring Sys at Bsep.Caused by High Gain Produced by 10K Resistor Across Second Stage Amplifier.Engineering Drawings Will Be Revised BSEP-99-0168, Monthly Operating Repts for Sept 1999 for Bsep,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Bsep,Units 1 & 2. with ML20217G7951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2 ML20217F3661999-09-22022 September 1999 Rev 18 to McGuire Unit 1 Cycle 14 Colr ML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20212D0431999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Brunswick Steam Electric Plant,Units 1 & 2 ML20216E8851999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2 ML20217G8101999-08-31031 August 1999 Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20210P9441999-08-10010 August 1999 Safety Evaluation Accepting Licensee Assessment of Impact on Operation of Plant,Unit 1,with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210P9181999-08-10010 August 1999 Safety Evaluation Authorizing Request for Reliefs CIP-01,02, 06,07,08,09,10 & 11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Request CIP-04 & 05 Would Result in hardship,CIP-03 Not Required & CIP-11 Denied in Part ML20210N2341999-08-0505 August 1999 SER Accepting Response to NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46 ML20210S2371999-07-31031 July 1999 Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20216E8951999-07-31031 July 1999 Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20210R1191999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Bsep,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 ML20209H1631999-06-30030 June 1999 Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20210S2491999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20210R1311999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Bsep,Unit 2 BSEP-99-0118, Monthly Operating Repts for June 1999 for Bsep,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bsep,Units 1 & 2. with ML20209H1731999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20195K3691999-05-31031 May 1999 Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology BSEP-99-0095, Monthly Operating Repts for May 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20210M8581999-05-14014 May 1999 B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, Rev 0 ML20206N3511999-05-11011 May 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs ML20211L3711999-05-10010 May 1999 Rev 0 to ESR 98-00333, Unit 2 Invessel Feedwater Sparger Evaluation ML20206G1871999-05-0404 May 1999 Safety Evaluation Approving Third 10-year ISI Program Requests for Relief (RR) RR-08,RR-15 & RR-17 ML20206R0891999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20195K3761999-04-30030 April 1999 Revised MORs for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 BSEP-99-0075, Monthly Operating Repts for Apr 1999 for Brunswick Steam Electric Plant,Unit 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Brunswick Steam Electric Plant,Unit 1 & 2.With ML20206N1791999-04-23023 April 1999 Rev 0 to 2B21-0554, Brunswick Unit 2,Cycle 14 Colr ML20205L2341999-04-0505 April 1999 SFP Criticality Analysis ML20206R0931999-03-31031 March 1999 Revised Monthly Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 BSEP-99-0059, Monthly Operating Repts for Mar 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20205P8991999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205F9031999-03-30030 March 1999 Safety Evaluation Supporting Proposed Rev to BSEP RERP to Licenses DPR-62 & DPR-71,respectively ML20205C4171999-03-25025 March 1999 Special Rept 99-02:on 801027,Commission Approved for publication,10CFR50.48 & 10CFR50 App R Delineating Certain Fire Protection Provisions for Nuclear Power Plants Licensed to Operate Prior to 790101.Team Draft Findings Reviewed ML20207K2051999-03-0505 March 1999 Special Rept 99-01:on 990128,DG Tripped After 2 H of Operation During Loaded Operation for Monthly Test.Caused by Several Components That Were Degraded or Had Intermittent Problems.Parts Were Replaced & Initial Run Was Performed ML20204C8911999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206N1831999-02-28028 February 1999 Rev 0 to Suppl Reload Licensing Rept for Bsep,Unit 2 Reload 13 Cycle 14 BSEP-99-0043, Monthly Operating Repts for Feb 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20205P9021999-02-28028 February 1999 Revised Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20203D7061999-02-0909 February 1999 SER Accepting Proposed Alternatives Contained in Relief Requests PRR-04,VRR-04,VRR-13,PRR-01,PRR-03,VRR-01.VRR-07, VRR-08 & VRR-09 Denied ML20204C8961999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for McGuire Nuclear Station,Units 1 & 2 ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept 1999-09-30
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- . g 10/10/96 23:40 3301 818 5101 NRC OPS NRR Part 21 @ 003/005 te,12,% 1siss a unieceme mu-- - 4, H00
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(%2) 90lL NAK Engineering, Inc.
420 AVIATION BLVD., SANTA ROSA, CA 95403 TELEPHONE: (707) 542-9996 FAX: (707) 542-6866 Oct 10,1996 Document Control Desk 4
U.S. Nuclear Regulatory Commis.sion Washington, DC 20555
Dear Sir,
Pursuant to my letter dated Aug. 5,1996 and in accordance with the requirements of Title 10, Chapter 1, Code of Federal Regulations, Part 21, NAK Engineering. Inc. has established and adopted revised procedures to assemble fuel oil lines and climinate the possible defective condition that was found at Mcguire. We have notified each of the affected nuclear stations and furnished copies of the new assembly procedures to the system engineers at McGuire and Brunswick. Through direct communications with the responsible system engineers, we have been advised that the both cites are fully aware of the possible defect or condition and have taken necessary action to examme the afTeeted parts and perform any necessary repairs.
As stated in my letter of Aug. 5,1996, the root cause of the thilure was determined to be an iumlequale tightening value to insure the correct seating of the sleeve that seal the fuelline connection. The revised procedure incorporates specific tightening vahtes, inspection criteria, and acceptance values to determine if the " crimping" of the sleeve is adequate.
1 Should anyone have any questions regarding this condition or corrective action please contact:
s Norman E. Nelson
.N AK Engineering, Inc, 420 AviationBlvd.
Santa Rosa, Ca. 95403 phone: 707-542-9996 fax: 707-542-6666 Sind: rely,
. r-No n E Nc! son Man eer, Quality Assurance
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NAK Engineering, inc.
420 AVIATION BLVD., SANTA ROSA, CA 95403 TELEPHONE: (707) 542 9996 FAX:(707) 542 6666 August 5,1996 Document Control Desk U.S. Nuclear Regulatory Conunission Washington,DC 20555
Dear Sir,
in accordance with the requirements of Title 10, Chapter 1, Code of Federal Regulations, Part 21, N AK Engineering,Inc. hereby notities the Commission of a potential defect or condition in a component of the Nordberg model FS1316HSC Standby Diesel Generator. There exists a potential problem with the fuel injection line assembly which connects the fuel pump to the hQector. .
N AK Engineering, Inc. has supplied these fuelline assemblies to the following sites:
l'TILITY SITE SERIAL N UM RFR(S) MODEL McGuire 1030-1270/1213 FS 1316 HSC l Duke Power Co )
Carolina Power & Light Brunswick 1030 1328/1331 FS 1316 HSC On or about June 20,1996, we were advised of a single leaking fuelline assembly that occurred on McGuire Nuclear Station's Emergency Diesel Generator Unit IB, Cylinder 4R. It was determined that the leak was caused by the fuelline sleeve coming loose which eliminated the fuel connection seal.
f There were no unusual engine noises, temperature. changes, cylinder firing pressure changes noted prior to the fuelline leak. The operator discovered significant fuel spray emitting tirom the fbel pump. l At this time Duke Power initiated a ROOT CAUSE FAILURE ANALYSIS investigation and they determined that the probable cause was inadequate crimping of the ferrule sleeve onto fuelline during assembly. In order to establish corrective action. tests were conducted by Duke Power Co. at their McGuire Nuclear Station's Met Lab to evaluate different torque and tightening l
values to determine the values to achieve optimum " crimping" of the ferrule sleeve. Samples of the same fuel line material, and fermle sleeves, were provided. Duke installed the ferrule sleeves at varying torque values and conducted " pull" tests. It was concluded that the tbelline nut s be tightened 1 1/8-1 1/4 tums past hand tight or 150 ft lbs, of torque to achieve optimum fe A L ,L e~.1 M a ,4 \
w Y' O y' / p i f a-l
_. . . ._. _ . . _ . . . ~ _ . . _ _ - -
4 1 1eIN
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J sleeve crimping.
1 4
While corrective action procedures have been implemented, the fuel line replacement on cylinder l
number 4R was installed before the corrective action procedures were Enn=1 and before corrective action was taken. It was further believed that this was a unique occurrence l i
l On July 30,1996 the replacement fuel line developed the same leaking problem. Since then ali i fuel lines produced and furnished after July 18,1996 have been assembled using the new torque and tightening techniques. l All fuel line assemblies supplied before July 18,1996, either in service , or in site inventories, should either be returned to NAK Engineering, Inc. for examination and the crimping tightening procedures checked and verified or this work should be done on site. A written procedure will be
!brnished within the next 60 days to the affected sites to accomplish the necessary inspection and repairs.
Should anyone have any questions regardirsthis condition or corrective action please contact:
Norman E. Nelson NAK Engineering, Inc, 420 Aviation Blvd.
Santa Rosa, Ca. 95403 phone: 707-542 9996 fax: 707-542-6666 A copy of this letter will be forwarded to all of the affected sites referenced in paragraph 2 of this letter.
Sinq erely, e
ortnan E Nelson Manager, Quality Assurance