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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 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 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 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 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 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 ML20097J6351996-01-30030 January 1996 Part 21 Rept Re Intermittent Failure of DG Relay Mfg by Amerace Electronic Components.Suspect Relays at Plants Identified & Replaced.Amerace Indicated That Operators & QC Personnel Made Aware of Need for Proper Soldering ML20096E6511996-01-18018 January 1996 Part 21 Rept Re Failure of MOV Motor Pinion Gear Mfg by Limitorque at Byron Station.Replacement & Insp Activities Initiated for Potentially Impacted Populations of MOVs at Byron & Braidwood Stations ML20094R7391995-11-28028 November 1995 Potential Part 21 Rept Re Ksv EDG Sys Mfg by Cooper-Bessemer Reciprocating Products Div,Div of Cooper Cameron Corp. Recommends That All Utils Verify Open Oil Passage in Assembly ML20082Q9491995-04-21021 April 1995 Part 21 Rept Re Notifying Commission of Potential Design Defect of Ksv EDG Sys ML20077D3431994-11-29029 November 1994 Part 21 Rept Re Suspect Master Connecting Rods & Contains Info Location in Engine for Rods ML20078G3051994-11-0909 November 1994 Rev to Part 21 Rept Re Potential Problem W/Master Power Connecting Rods.Vendor Recommends Listed Utils Perform Visual Insp of Master Rods to Determine Applicability of Rept ML20071J1891994-07-22022 July 1994 Final Part 21 Rept Re Cracks Found in Body to Bonnet Nuts on Copes-Vulcan Airoperated Valves.Operability Evaluation for Byron Units 1 & 2,of Affected Valves W/Nuts of Heat Numbers H & I Completed on 940622 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 ML20059L9861993-11-11011 November 1993 Part 21 Rept Re Deviation Wherein Fully Open Butterfly Valve Located 15 Pipe Diameters Upstream of Sensors Was Disturbing Flow Profile Enough to Cause Ultrasonic Meter to Indicate 3 to 4% Low.Customers Notified & Valve Removed ML20127M5201992-11-24024 November 1992 Final Part 21 Rept Re Reject Lot Serial Numbers of Defective Fuel Nozzle Tips,Consisting of Corrected Page 6 of 921102 Rept Re Reject Lots for Fuel Injector Assembly ML20012A9011990-02-27027 February 1990 Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp ML20011F5971990-02-22022 February 1990 Part 21 Rept Re Solder Connections in Abb 27/59 Relays Deteriorated Due to Thermal Stress,Causing Bonding of Printed Wiring Pattern to Glass Epoxy Circuit Board.Interim Circuit Board W/Larger Pads & Higher Wattage Will Be Used ML20011F1941990-02-22022 February 1990 Part 21 Rept Re Abb 27/59 Relay Catalog Series 211L.Solder Connections to Printed Wiring Runs on Bottom of Circuit Board Deteriorated Due to Thermal Stress.No Actual Failure Occurred & Relays to Be Changed at Next Outage ML18153C1011990-02-0202 February 1990 Part 21 Rept Re Two of Three Pc Cards in GE Type SLV11A1 Over/Undervoltage Relays Failing to Produce Output.Short Between Leads Would Result in Damage to Component 1C5. Sketch of Threshold Detection Board Encl ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N 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 ML19325E0861989-10-16016 October 1989 Followup Part 21 Rept Re Class 1E Battery Chargers W/ Transformers Running at Temps Exceeding Those Used in Qualification Rept When Operating at or Near Full Load Rating of Equipment.Listed Corrective Actions Underway 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 ML19325C9521989-09-29029 September 1989 Part 21 Rept Re Potential Common Failure of SMB-000 & SMB-00 Cam Type Torque Switches Supplied Prior to 1981 & 1976. Vendor Recommends That Switch W/Fiber Spacer Be Replaced 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 ML20246P7111989-07-17017 July 1989 Part 21 Rept Re Quench Cracks in Bar of A-SA-193 Grade B7 Component.Quench Cracks Found in One Bar of Matl.Listed Purchasers Informed of Potential Defect.Next Rept Will Be Submitted When Addl Info Becomes Available ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML20245B6651989-06-15015 June 1989 Part 21 Rept 150 Re Potential Defect in Component of Dsr Standby Diesel Generator.Cause of Failure Determined to Be Combination of Insufficient Lubrication to Bushings.Listed Course of Action Recommended at Next Scheduled Engine Maint 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 ML20244D8161989-04-13013 April 1989 Part 21 Rept Re Failure of Rosemount Transmitters.All Failed Transmitters Replaced,Inservice Test Procedure Prepared & Monthly Test of All 12 Transmitters in RCS Throughout Cycle 2 Operation Will Be Performed.Review Continuing 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 ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys ML20205F3211988-10-10010 October 1988 Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07 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 ML20207P0151988-10-0404 October 1988 Part 21 Rept Re Fuel Nozzle Tips in Standby Diesel Generator KSV-20-T W/Cracks Permitting Diesel Fuel to Be Sprayed Into Cylinders.Heavy Vapors Observed Emitting from Breathers on Some Cylinder Heads 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 ML18093A8281988-05-0606 May 1988 Part 21 & Deficiency Rept Re Asea Brown Boveri,Power Distribution,Inc Low Voltage K-Line Circuit Breakers. Efforts Underway to Define Quantity & Type of Component Parts That May Need to Be Replaced ML20153G0111988-05-0606 May 1988 Part 21 Rept Re Potential Defect in Bussman Buss KTK-R Fuse Blocks W/Part Numbers 2078,2079 & 2080.Purchasing Records Reviewed to Identify If Any Parts Were Actually Used or Shipped to Customers.Results Listed 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 ML20153B2811988-02-22022 February 1988 Part 21 Rept Re Defect in Operation of Gas Monitors Using Fixed Filters.Initially Reported on 880212.Caused by Error in Software for Monitors.Vendor Testing Mod to Software & in Interim Recommends Changing Filters Every 48 H ML20149H8211988-02-11011 February 1988 Final Deficiency Rept 457/87-01 Re Diesel Engine Generator Rocker Arm Failure.Initially Reported on 870217.Util Took Steps to Determine Strength of Rocker Arms.Low Strength Rocker Arms Replaced W/New Rocker Arms ML20196D6281988-02-10010 February 1988 Part 21 Rept Re Potential Defect in Certain Model RTF-480/120-30 Ac Line Regulating Transformers Involving Nuisance Tripping of 100 Ampere Ac Input Circuit Breaker When Initializing Unit.Breaker Should Be Replaced ML20149J0261987-12-21021 December 1987 Part 21 Rept Re Installation of Relay Part B8002DN in Foxboro 62H Controllers in Facilities.Subj Relay Must Be Replaced by Relay Part N0196ZN.Relay B8002DN Not Used in Any Other Plants ML20235U0271987-10-0707 October 1987 Part 21 Rept Re Westinghouse Plant Steam Generator Tubes Susceptible to High Cycle Fatigue Failure Similar to 870715 Event at North Anna Unit 1.Caused by Mean Stress in Tube & Superimposed Alternating Stress ML20237G5781987-08-0707 August 1987 Part 21 & Deficiency Rept 142 Re Defect in Starting Air Distributor Sys of Dsr Standby Diesel Generator.Drain Sys Will Be Permanently Installed in Start Air Distributor ML20236N7131987-08-0505 August 1987 Part 21 Rept Re Potential Problem W/Vibration in Lube Oil & Jacket Water Sys.At Rancho Seco Site,Fatigue Cracks Found in Welds of Support Members in Lubricating Oil Sys.Cracks Due to Vibration in Lube Oil Sys.Addl Preventive Action Taken 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G9961999-10-14014 October 1999 SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 & ML20217H5221999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Byron Station, Units 1 & 2.With BW990066, Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A7441999-09-10010 September 1999 Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety BW990056, Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With ML20212B9261999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Byron Station,Units 1 & 2.With ML20210R6421999-08-13013 August 1999 ISI Outage Rept for A2R07 ML20210U8111999-08-0404 August 1999 SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval Because Relief Applies to Valves Not Required by 10CFR50.55a ML20210R3431999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Byron Station, Units 1 & 2.With BW990048, Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With ML20210K9861999-07-30030 July 1999 Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20210E2251999-07-21021 July 1999 B1R09 ISI Summary Rept Spring 1999 Outage, 980309-990424 M990002, Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function1999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function ML20216D3841999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function ML20209G1751999-07-0808 July 1999 SG Eddy Current Insp Rept,Cycle 9 Refueling Outage (B1R09) ML20209H3711999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Byron Station, Units 1 & 2.With BW990038, Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With ML20207H7771999-06-30030 June 1999 Rev 0 to WCAP-15177, Evaluation of Pressurized Thermal Shock for Byron,Unit 2 ML20207H7851999-06-30030 June 1999 Rev 0 to WCAP-15183, Commonwealth Edison Co Byron,Unit 1 Surveillance Program Credibility Evaluation ML20207H7941999-06-30030 June 1999 Rev 0 to WCAP-15180, Commonwealth Edison Co Byron,Unit 2 Surveillance Program Credibility Evaluation ML20207H8071999-06-30030 June 1999 Rev 0 to WCAP-15178, Byron Unit 2 Heatup & Cooldowm Limit Curves for Normal Operations ML20207H7561999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20207H7621999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20195J8001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Byron Station,Units 1 & 2.With BW990029, Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With ML20209H7481999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2 ML20207B6481999-05-25025 May 1999 SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations ML20206R6991999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Byron Station Units 1 & 2.With BW990021, Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With M980023, Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A)1999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) ML20195C7961999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) BW990016, Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With ML20205P7001999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Byron Station,Units 1 & 2.With ML20205B5091999-03-26026 March 1999 SER Accepting Relief Requests 12R-24,Rev 0 & 12R-34,Rev 0, Related to Second 10-year Interval Inservice Insp for Byron Station,Units 1 & 2 ML20205C5101999-03-21021 March 1999 Revised Safety Evaluation Supporting Improved TS Amends Issued by NRC on 981222 to FOLs NPF-37,NPF-66,NPF-72 & NPF-77.Revised Pages Include Editorial Corrections ML20204G3831999-03-19019 March 1999 Safety Evaluation Accepting Second 10-yr Interval ISI Request for Relief 12R-11 M990004, Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function1999-03-17017 March 1999 Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function ML20206A8831999-03-17017 March 1999 Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function ML20196A0721999-03-16016 March 1999 Cycle 8 COLR in ITS Format & W(Z) Function 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 ML20207J4371999-03-0808 March 1999 ISI Outage Rept for A1R07 ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations BW990010, Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With ML20204C7671999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Byron Station,Units 1 & 2.With ML20206U9011999-02-15015 February 1999 COLR for Braidwood Unit 2 Cycle 7. Page 1 0f 13 of Incoming Submittal Was Not Included BW990004, Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With1999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With ML20202F6181998-12-31031 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function 1999-09-30
[Table view] |
Text
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I
'. ie CommonweaMh EC* son
- j/ C One First National Plaza, Chicago, Ilknois
- k ("O 7 Address Azply to
- Post Office Box 767.
7 Chicago, llhnois 60690 l May 20, 1986 l Mr. James G. Keppler j Regional Administrator .
, Region III '!
) U.S. Nuclear Regulatory Commission j 799 Roosevelt Road -
j Glen Ellyn, IL 60137 I 1
1
Subject:
Byron Station Unit 2 l j Braidwood Station Units 1'and 2 10 CFR 50.55(e) Nos. 86-01 and 86-03 Final Report ,
[ Defective Spot Welds on Cable Tray Hangers l j NRC Docket Nos. 50-455. 50-456 and 50-457 k
References:
(a) A.D. Miosi to J.G. Keppler, dated March 6, 1986 I 1
(b) K.A. Ainger to J.G. Keppler, dated March 12, 1986 i
j
Dear Mr. Keppler:
The above reference provided information concerning a i
deficiency reportable pursuant to 10 CFR 50.55(e) regarding i
! defective spot welds on cable tray hanger strut material at Byron l Unit 2'and Braidwood Stations. This letter provides an update to j our previous response and is considered to be a final report.
DESCRIPTION OF DEFICIENCY t
i During the installation of cable tray in Braidwood Unit 2 i containment,.the Unit 2 electrical contractor, G.K. Newberg
{ (GKN),. identified. installed cable tray hangers which had j discrepant spot welds. GKN initiated Nonconformance Reports !
j (NCR) 331-00001 and 331-00002 which together identified 30 ;
3' cable tray hangers with discrepant spot welds. The cable tray hangers in question were prefabricated by Systems Control Corporation (SCC) utilizing P1004A Unistrut material. The
, P1004A is a spaced.back-to-back channel fabricated out of two- !
j 4
P1000 single channels held together by side ~ plates which are spot welded to the channel at 3 inches on center. Some of the spot welds'on the cable tray hangers which join the side plates j' to the channel as identified by GKN appear to be improperly j fused. GKN submitted the two NCR s to Commonwealth Edison j Company (Ceco)'for their evaluation.
l l
4 1
7 , p0
Upon review of the GKN NCR's 331-00001 and 331-00002, Ceco initiated NCR 793. In performing the 50.55e reportability +
review of NCR 793, Ceco determined that the identified problem was reportable. In addition, CECO notified Unistrut Corporation (Unistrut) of the problem. Unistrut made a visit to the Braidwood site and confirmed.the P1004A material in question was their product and would review their records to help identify the source of the problem.
ANALYSIS OF SAFETY IMPLICATIONS The safety significance of the discrepant spot welds has been fully assessed. An engineering evaluation, based on destructive testing, of hangers with discrepant spot welds and suspect material with no discrepant spot welds indicates that there is no safety significance.
CORRECTIVE ACTION TAKEN-BRAIDWOOD In order to determine the scope of this problem, CECO decided to perform a walkdown of the installed cable tray hangers comprised of P1004A Unistrut members in Braidwood Units 1 & 2.
Sargent & Lundy developed an inspection criteria to be used on the walkdown. Each of the members were inspected for spot weld fusion by observing for gaps between the side plate and base channel and then attempting to pass thin mylar through the welded area. Welds were considered discrepant if the thin mylar could be passed through the welded area.
The hangers in which discrepant welds have been observed were ,
mapped indicating the location of each discrepant weld. The base channel control numbers were recorded for all hangers inspected.
The base channel control number indicates the year it was i rolled, the operator of the rolling machine and the steel coil number. Furthermore, Unistrut QC documentation references the control number. The results of this walkdown are summarized in i the attached table.
The number of hanger members in which discrepant welds were
- found and the total number of hanger members inspected are shown for each control number identified'with discrepant i welds. This information was passed along to Unistrut for their i review. A review of the control numbers of the discrepant i material shows that the majority of the material was manufactured in the 1978 time frame. Unistrut concentrated their efforts on reviewing production and quality control records.
Based on this record review, Unistrut has established that 580 feet of rejected P1004A material was inadvertently shipped to l
SCC and used to supply cable tray hangers for the Byron /Braidwood project which was primarily used for Braidwood Unit 2. This shipment (1,000 feet) was received by SCC in
, August 1979. This material consisted of rejected 20. foot l
pieces of P1004A material that were accumulated for rework l during 1979. This material was partially reworked in July of 1979. The control numbers shown in the attached table with an '
8 prefix would be considered suspect since they were produced in this time period. However, a significant number of adjacent discrepant spot welds have been observed only on. control numbers 8E7806, 8E7829 and 8N7791. It appears that the suspect material was utilized primarily for Braidwood Unit 2 cable tray hangers. This is supported by the results of the walkdown. In addition, Braidwood Unit 2 were the last hangers fabricated by ;
the SCC. Prior to the 1,000 foot shipment, shipments totaling 2,000 feet (1,500 feet - 1977, 500 feet - March 1979) were received by SCC. This 2,000 feet of nonsuspect material would be consumed by the earlier scheduled units (Braidwood 1, Byron 1 & 2) before the suspect material was received by SCC in the August 1979 shipment.
A comprehensive review of records by Unistrut indicates that the inadvertent shipment of 580 feet of discrepant material was an isolated occurrence. Quality Control (QC) records are ;
maintained for all material produced by Unistrut. All material !
which is rejected by QC is tagged and held for disposition. ,
The 580 feet of suspect material was accumulated during 1979, !
tagged as rejected, and held for rework. The walkdown shows that some of the material was partially reworked. The disposition for this reject tag was never completed by Unistrut QC. The material was apparently shipped prior to the completion of the rework and final QC acceptance.- Unistrut QC records show this to be the only case of.a material reject tag with incomplete QC disposition, and therefore, considers it to be an isolated case.
Based on the construction schedule considerations, it was determined to replace the Unit 2 containment hangers which contained discrepant welds. The Unit 1 hangers with discrepant spot welds have been evaluated case-by-case based on a spot weld strength determined from destructive testing of a sample of discrepant material. Even though the' case-by-case review determined the hangers to be acceptable, all of the Unit 1 hangers with the exception of one will be repaired or replaced. The remaining hanger had only one spot weld broken and will be left as is. Hangers with a suspect control' number, but no discrepant spot welds, were evaluated generically based on the allowable spot weld strength determined from testing.
These hangers were determined to be acceptable with a design margin'of 2.0, or more.
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l :
It is apparent that, in addition to the 580 feet of suspect material, there exist occasional discrepant spot welds.
Unistrut expected that occasional discrepant spots may not be detected by their Quality Assurance program. An engineering evaluation was completed to assess this condition on a generic basis. The maximum allowable spacing between intact spot welds was determined to be 9 inches. Therefore, two consecutive spot welds could be discrepant on all four rows of welds and still be acceptable.
In order to confirm our conclusion that this problem is
! isolated to cable tray hangers supplied by SCC, a walkdown was i also completed for all installed conduit and junction box hangers in Units 1 & 2 which utilize Unistrut P1004A. There
.! are 2357 conduit and junction box hangers utilizing P1004A of f
which discrepant welds were observed on only seven hangers.
Due to this low frequency of occurrence, these discrepant welds are considered isolated cases. These hangers will be repaired or replaced. Conduit and junction box hangers have been fabricated in a later time period as compared to cable tray i hangers. They have also been fabricated by a different contractor, Mechanical, Inc. For these reasons, it has been
- concluded that the scope of the P1004A issue is isolated to cable tray hangers received from SCC. Therefore, no further action is planned for conduit and junction box hangers.
CORRECTIVE ACTION TAKEN-BYRON A walkdown of all cable tray hangers comprised of PlOO4A Unistrut members has been completed for Byron Unit 2. The members were inspected using the same inspection technique at Braidwood Station and all discrepant welds were recorded. The results of this walkdown are summarized in the attached table.
4 The number of hanger members in which discrepant welds were found and the total number of hanger members inspected are shown for each control number. Only 13 members of 233 inspected were found to have discrepant welds. Commonwealth Edison Company Nonconformance Report F-1045 has been initiated to track this concern.
The scope of the suspect P1004A material is limited and has been established at Braidwood Station per 55(e) No. 86-03. The suspect material appears to have been utilized primarily for
- cable tray hangers at Braidwood Unit 2. The results of the
- Byron Unit 2 walkdown support this conclusion, t
I
4 The Byron Unit 2 hangers with discrepant spot welds have been evaluated case-by-case, based on a spot weld shear strength 4
determined from destructive testing of a sample of discrepant Hangers with material. They were determined to be acceptable.
a suspect control number but no discrepant spot welds, were evaluated generically based on the allowable spot weld strength i
determined from testing. These hangers were determined to be l
acceptable with a design margin of 2.0, or more.
SUMMARY
In summary, results of the Unistrut PlOO4A. demonstrate that:
- 1. The scope of the issue is 580 feet of discrepant material i
which was inadvertently shipped to SCC and used to fabricate cable tray hangers. Walkdown data, supplemented by vendor information, leads to the conclusion that these i
cable tray hangers were primarily in Braidwood Unit 2.
- 2. Occasional discrepant spot welds are expected by Unistrut for nonsuspect material. An engineering evaluation was i
performed which accepts this condition on'a generic basis.
t
- 3. An engineering evaluation was performed for all cable tray ,
hangers remaining with suspect control numbers. The evaluation was based on a weld strength determined from destructive testing of a sample of discrepant material.
All hangers with suspect control numbers were determined to l
be acceptable.
Please address any questions that you or your staff may I
have concerning this matter to this office.
Very truly yours, k
l i
AnthonV D. Miosi Nuclear Licensing Administrator 1
ADM/ pay
{ 1690K Enclosures i cc: NRC Resident Inspector - Braidwood
" " - Byron I 'I i
4
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l .
ATTACletENT BRAIDWOOD STATION UNISTRUT P1004A WALKDOWN CABLE TRAY HANGERS NUMBER OF HANGER MEMBERS CONTROL DISCREPANT TOTAL NUMBER UNIT 1 UNIT 2 INSPECTED 7P3167 1 0 79k 7P3351 2 0 16 8E7806* O 35 53 8E7829* 1 10 22 8N7791* 1 1 40 8N7792* 1 0 30 8N7830* 2 0 9 Others 0 0 146 TOTAL 8 46 395
o ATTACHMENT BYRON 2 UNISTRUT P1004A WALKDOWN-CABLE TRAY HANGERS NUMBER OF HANGER MEMBERS TOTAL CONTROL INSPECTED NUMBER DISCREPA E 1 47 7P3167 3 48 7P3351 i 15 :
8E7828* 5 3 41 8E7791*
1 44 8N7792*
0 38 l Others ,
13 233 TOTAL j