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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 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 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 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 ML20214H8221987-05-15015 May 1987 Interim Deficiency Rept Re Diesel Engine Generator Rocker Arm Failure.Initially Reported on 870217.Test/replacement Program Started,Contingent on Receipt of Replacement Exhaust Rocker Arms from Cooper-Bessemer ML20206Q8821987-04-0202 April 1987 Interim Deficiency Rept Re Diesel Engine Generator Rocker Arm Failure.Initially Reported on 870217.Investigation Emcompasses Both Metallurgical Analysis & Mechanical Interactions.Next Rept Will Be Submitted by 870501 ML20205B6691987-03-17017 March 1987 Deficiency Rept Re Diesel Engine Generator Rocker Arm Failure.Initially Reported on 870217.Diesel Generator Repaired by Honing Out Crosshead to Crosshead Guide Clearance to 0.006 Inches.Next Rept Submitted by 870430 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 ML20212H5451987-01-12012 January 1987 Part 21 Rept Re Break of Master Power Rod at Fractured Surface.Caused by Fatigue Failure Originating in Rod When Iron Plating in Articulated Rod Pin Bore Failed,Resulting in Engine Inoperability.Rod Replaced ML20207P1801986-12-29029 December 1986 Final Deficiency Rept 86-02 Re Rejectable Indications During Preservice Insp on Loop 1 Steam Generator.Actions Necessary to Resolve Items Completed,Per Suppls 1 & 2 to NUREG-1002 ML20212D9721986-12-23023 December 1986 Interim Deficiency Rept 84-14 Re Weld & Grindout Identified During Preservice Insp.Initially Reported on 841121.New Data Demonstrates That Indication Size Meets ASME Section XI 1WB-3512,1977 Edition.Indication Grindout No Longer Needed ML20215F9531986-12-19019 December 1986 Part 21 Rept Re Design Error Uncovered in Certain Safety Shutdown Circuits for Standby Diesel Generator.Switches 12E0-1,12E0-2,33E0-1 & 33E0-2 Not Intended to Initiate Emergency Mode Trip as Drawings Indicate ML20214T5111986-11-26026 November 1986 Deficiency Rept Re Misplaced Radiographs for Westinghouse Equipment.Initially Reported on 861030.Item Not Reportable Per 10CFR50.55(e) ML20215H2231986-10-17017 October 1986 Revised Final Deficiency Rept 84-07 Re Crush Strength of Energy Absorbing Matl Used in Pipe Whip Restraints.Removal of Four Addl Restraints in Unit 1 Took Place on 851004 During Unit 1 Outage ML20210N6561986-09-26026 September 1986 Final Deficiency Rept 85-06 Re Failure of Diesel Generators 1A & 1B to Sustain Adequate Prime During Testing.Initially Reported on 850822.Fuel Oil Sys Modified & Tested ML20214W5641986-09-19019 September 1986 Deficiency Rept Re 860818 Inadvertent Discharge of Water Into Spent Fuel Pit Where 64 New Fuel Assemblies for Initial Core Load Being Stored.Initially Reported on 860819.Event Not Reportable Per 10CFR50.55(e) ML20210F4781986-09-17017 September 1986 Final Part 21 & Deficiency Rept 86-06 Re Fastener Matl Supplied by Cardinal Industrial Products.Initially Reported on 860617.Fastener Matl Met ASME Code Requirements. Documentation of Corrective Actions Available Onsite ML20203N1931986-09-16016 September 1986 Final Deficiency Repts 84-05 & 84-15 Re Inconsistencies in Documentation of Gk Newberg Structural Steel Installations & Welding Program,Respectively.Initially Reported on 840417. Installation Travelers Reviewed.Deficiencies Resolved 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 ML20214P5121986-09-0202 September 1986 Final Deficiency Rept 83-08 Re Fabrication of Pullman Sheet Metal Duct Fittings W/O Approved Design Documentation. Initially Reported on 830630.Unit 1 Fitting Mods Completed on 860501.Reworking of 12 Fittings Remain for Unit 2 ML20205F7211986-08-12012 August 1986 Revised Final Deficiency Rept 84-12 Re Removal of Name Plates from ASME Large Bore Spool Pieces.Initially Reported on 840824.Replacement Identification Plate Not Attached to Installed Spool Pieces.Procedure Revised to Reflect Change ML20212K2741986-08-12012 August 1986 Final Deficiency Repts 84-05 & 84-11 Re Boeing Steam Generator Snubber Failure.Initially Reported on 840628. Snubber Functional Test Results Reviewed & Acceptable. Snubbers Refurbished for Listed Units ML20212B3791986-07-29029 July 1986 Interim Deficiency Rept 86-06 Re Fastener Matl Supplied by Cardinal Industrial Products.Initially Reported on 860617. Matls Over 1 Inch in Diameter Shipped During 840109-850815 & Not Included in Notification Ltrs Acceptable ML20206B1371986-06-11011 June 1986 Final Deficiency Rept 84-04 Re out-of-tolerance Radiographic Film Densities.Initially Reported on 840406. Unit 1 Production Welds Repaired &/Or Reradiographed & Welder Qualifications Evaluated & Confirmed ML20211F1971986-06-0505 June 1986 Final Deficiency Repts 86-03 by & 86-05 Bw Re Cold Leg Safety Injection Pipe Vibration & Cracks.Initially Reported on 860430.D Loops Changed to 5-D Bends & Support Added for Addl Stiffness ML20211E3471986-06-0404 June 1986 Final Deficiency Repts 84-06(BY) & 84-14(BW) Re Large Laminar Indication in Steam Generator Snubber Piston Rod End Blade.Initially Reported on 840731.Rod End & Six End Caps Replaced ML20198E8981986-05-20020 May 1986 Final Deficiency Repts 86-01 & 86-03 Re Defective Spot Welds on Cable Tray Hanger Strut Matl.Initially Reported on 860306.Engineering Evaluation Performed for Hangers Remaining W/Suspect Control Numbers ML20197E8261986-05-0909 May 1986 Final Deficiency Rept 86-04 Re 21 Rejectable Weld Indications Identified During Preservice Insp.Initially Reported on 860409.Relief from Repair Requirements Will Be Requested for 12 Unacceptable Indications ML20210L0441986-04-22022 April 1986 Final Deficiency Repts 86-02 for Byron & 86-04 for Braidwood Re Failures of Diesel engine-generator Rocker Arm.Initially Reported on 860327 by Util & 860311 by Cooper Industries Under Part 21 ML20210E0801986-03-18018 March 1986 Final Deficiency Rept 84-17 Re Concrete Expansion Anchor Installations.Sargent & Lundy Evaluation Complete.No Significant Design Discrepancies Noted.Util Nonconformance Repts 658 & 659 Closed ML20141N8601986-03-12012 March 1986 Interim Deficiency Rept 86-01 Re Discrepant Spot Welds on Cable Tray Hangers Made of P1004A Unistrut Matl.Initially Reported on 860210.Walkdown of Hangers Completed & All Discrepant Welds Recorded ML20141N7901986-03-11011 March 1986 Part 21 Rept Re Inlet Rocker Arm Failure in Cooper Bessemer Corp Engines S/N 7177 & 7178.Broken Rocker Arms Constitute Secondary Failure.Primary Failure Was Seizure of Valve Train Crossheads in Up Position ML20137Z5001986-03-0606 March 1986 Interim Deficiency Rept 86-03 Re Defective Spot Welds on Cable Tray Hanger Strut Matl.Initially Reported on 860121. Unit 2 Containment Hangers Will Be Replaced & Unit 1 Hangers Will Be Repaired or Replaced 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 & 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 ML20217H5221999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Byron 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 ML20212B9261999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Byron Station,Units 1 & 2.With 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 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 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 ML20210R3431999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Byron 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) 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 ML20209H3711999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Byron Station, Units 1 & 2.With ML20207H7561999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) ML20207H7621999-06-28028 June 1999 Pressure Temp Limits Rept (Ptlr) 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 ML20195J8001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Byron Station,Units 1 & 2.With 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 ML20195C7961999-04-28028 April 1999 Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A) 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) 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 ML20206A8831999-03-17017 March 1999 Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function 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 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 ML20199G8271998-12-31031 December 1998 Rev 1 Comm Ed Byron Nuclear Power Station,Unit 1 Cycle 9 Startup Rept 1999-09-30
[Table view] |
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POWER RENCTORE EVENT NUMBER: 29853 1
FACILITY: BYRON REGION: 3 NOTIFICATION DATE: 01/18/96 UNIT: [1] [2] [] STATE: IL NOTIFICATION TIME: 14:04 [ET] ;
RX TYPE: [1] W-4-LP, [2] W-4-LP EVENT DATE: 01/18/96 !
EVENT TIME: 14 : 00 [ CST) 1 NRC NOTIFIED BY: D PETERS'ON LAST UPDATE DATE: 01/18/96 HQ OPS OFFICER: JOHN MacKINNON NOTIFICATIONS EMERGENCY CLASS: NOT APPLICABLE 10 CFR SECTION:
CDEF 21.21(b) (2) DEFECTS / NONCOMPLIANCE i UNIT SCRAM CODE RX CRIT INIT PWR INIT RX MODE CURR PWR CURR RX MODE I
1 N N 0 0 2 N N 0 0 EVENT TEXT FAILURE OF A MOTOR PINION GEAR AT BYRON STATION.
MOTOR PINION GEARS USED IN MOTOR OPERATED VALVES PROCURED FROM WESTINGHOUSE ELECTRIC CORPORATION AND SUPPLIED TO WESTINGHOUSE BY LIMITORQUE CORPORATION. ACTUATOR SIZE:SB-0, MOTOR: 25 Ft-lb. 3600 RPM, MOTOR PINION: 34 TOOTH PART #60-415-0100-1.
THE DEFECT IS RELATED TO THE FAILURE OF A MOTOR PINION GEAR AT BYRON STATION. ON 10/25/95, THE 1CV8105 MOTOR OPERATED VALVE AT BYRON STATION FAILED MID-STROKE WHEN IT WAS BEING CLOSED DURING NORMAL PLANT OPERATIONS. l SUBSEQUENT TROUBLESHOOTING INDICATED THAT THE FAILURE WAS DUE TO SHEARED MOTOR PINION GEAR. MATERIAL ANALYSIS IF THE FAILED MOTOR PINION GEAR DETERMINED THAT THE GEAR WAS MADE OF AN IMPROPER MATERIAL. THE MATERIAL ,
USED WAS 11B44 VERSUS 4140, 4320, OR 86L20 MATERIAL THAT SHOULD HAVE BEEN l USED FOR THIS SIZE OPERATOR. AISI 11B44 MATERIAL IS A FREE-MACHINING, i RE-SULFERIZED, BORON-BEARING CARBIDE STEEL. BASED ON THE RESULTS OF THE I MATERIAL ANALYSIS, IT APPEARS AS IF THE FAILED MOTOR PINION GEAR WAS MACHINED FROM CAST STOCK. THE MOTOR PINION GEAR FAILURE WAS ATTRIBUTED TO l THE POOR MECHANICAL PROPERTIES OF THE PART AND THE INABILITY OF THE GEAR TO I SUSTAIN SERVICE LOADS. THE USE OF THE IMPROPER MATERIAL IN THE MOTOR PINION l GEAR DIRECTLY LED TO THE FAILURE OF THE 1CV8105 VALVE TO OPERATE.
BRAIDWOOD STATION ALSO PURCHASED 6 OF THESE MOTOR PINION GEARS (IDENTIFIED IN THE 1CV8105 VALVE). j PART 21 WAS FACSIMILED TO VERN HODGE NRR/PCEB.
9601220338 960118 PDR ADOCK 05000454 S PDR gq Ut ;
SENT BY; 1-18-36 1:04PM : COM ED CENTRAL FILE- 301 8165151:: 1 o.ininonwc.ath toron i.o.nn.iny Hyron Genenstute Stacit.o
+ 40 NonlHiennan t:hurch Rimi il 3nm. II.C.inin 9M s Tei m . n r .i .
January 18.1996 I
l LTR: BYRON 96-0016 FILE: 2.01.0703 U. S. Nuclear Regulatory Commission Washington, DC 20555 1
l
- Attention
- Document Contml Desk l l
[
Subject:
Byron Station Units I and 2 '
Braidwood Station Units 1 and 2 j 10 CFR Part 21 Notification i improper Material in Motor Operated Valve Motor Pinion Gear NCR Dockets 50-454 and 50-455 l l
NCR Docketr 50-456 and 50-457 Applicability This notification is submitted in accordance with the requirements of 10 CFR Part 21, Section 21.21(b),21.3a(3), and 21.3d(4).
Identification of Facilities and Comnonents -
Byron Nuclear Generating Station Units 1 and 2 Braidwood Nuclear Generating Station Units 1 and 2 Motor Pinion Gears used in Motor Operated Valves (MOVs) procured from Westinghouse Electric Corporation and supplied to Westinghouse by I.imitorque Corporation.
Actuator Size: SB-0 Motor: 25 Ft.-lb. 3600 RPM Motor Pinion: 34 tooth part #60-415-0100-1 Identifiention of Comnonent Manufacturer /Sunolier Limitorque Corporation 5114 Woodall Road BYRON NUCLEAR POWER STATION j,a p,a-G P.O. Box 11318
% W6TMMi9).Pf5 W M Lynchburg, Virginia 24506-1318 (m E D ~ 3 1 M ._
- s. a r i. . .. . i ar a. . < s.......a,.
Fev e ., , ,,,,e t'.,#
" % MI544(
Fan 8
'SENT BY: 1-18-96 : 1:04PM : COM ED CENTRAL FILE- 301 8165151:e 2-Byron Ltr. 96-0016
- Page 2
, January 18,1996 Nature of Defect The defect is related to the failure of a motor pinion gear at Byron Stadon. On 10/25/95, the ICV 8105 motor operated valve (MOV) at Byron Station failed mid-stroke when it was being closed during normal plant operations. Subsequent troubleshooting indicated that the failure was due to a sheared motor pinion gear. Material analysis of the failed motor pinion gear determined that the gear was made of an improper material. The !
material used was 11 B44 versus the 4140,4320, or 86L20 material that should have been used for this size operator. ATSI 11B44 material is a free-machining, re-sulferized, boron-bearing carbide steel. Based on the results of the material analysis, it appears as if the failed motor pinion gear was machined from cast stock. The motor pinion gear failure was attributed to the poor mechanical properties of the part and the inability of the gear to sustain service loads. The use of the improper material in the motor pinion gear directly l
led to the failure of the ICV 8105 valve to operate.
Time of Discovery The failure of the ICV 8105 valve ocO2rred on 10/25/95. Comed determined that the failure was a potential defect subject to the provisions of 10CFR21 on 11/21/95. Final determination that the defect was reportable per 10CFR21 was made on 1/12/96. i l
Ntimber and Location of All Defective ComponenlE l
The only known defective motor pinion gear was identified in the 1CV8105 valve at ;
i
. Byron Station. The 1CV8105 valve at Byron Station was one (1) of 12 MOVs that were l
- purchased as a group from Westinghouse Electric Corporation for Comed's Byron and I Braidwood Stations (6 MOVs for cach station). The actuators / motors for these twelve (12) valves were purchased from Limitorque Corporation by Westingbouse and supplied to Comed.
l Corrective Actions:
l l Comed initiated replacement and inspection activities for the potentially impacted l population of MOVs at Byron and Braidwood Stations including testing of 14 spare I
replacement motor pinion gears in Comed Stores of that particular gear size. To date,20 of 21 gears tested have been determined to be of the correct material. The only identified use of the improper material was in the motor pinion gear that was removed from the ICV 8105 valve at Byron Station. Two (2) MOVs at Braidwood Station from the suspect purchase order were subsequently determined to have different gear ratios and not be impacted by this defect. From the original lot of MOVs purchased together, two (2)
MOVs at Byron Station and one (1) MOV at Braidwood Stadon remain to have their motor pinion gears replaced and inspected. These MOVs are on operating units at the respective stations.
I l . . . . . .. .
SENT BY: 1-18 96 1:04PM :_bOhEDCENTRALFILE- 301 8165151:# 3 Byron Ltr. 96-0016 Page 3 January 18,1996 i
The inspection and replacement activitics will take place prior to or during the next l -outage on each unit. These actions are being tracked by the station's respective corrective
! action programs.
At this time, based on conversations with the vendor, Limitorque Corporation, and the positive inspection results of other potentially impacted components, Comed believes that the presence of the defective material in the ICV 8105 valve at Byron Station was an isolated incident. Beyond the inspection of'the thrc'e (3) remaining motor pinion gears at
^
Byron and Braidwood Stations, no further actions are anticipated. However, it is Comed's understanding that the vendor is currently evaluating this defect for any generic applicability and will notify licensees, as appropriate. .
10 CFR 21 Evalmtian The 1CV8105 valve at Byron Station is a safety related valve in the Chemical and Volume Control System (CVCS) that is used as an isolation valve during nonnal charging activities. The specific failure of the 1CV8105 valve on 10/25/95 did not lead to an incident of significant magnitude. However, there was a potential for a more significant event. There is a redundant valve (ICV 8106)in series with the 1CV8105 valve that is capable of performing the same design function. However, the presence of !
the improper material'in the ICV 8105 did represent a reduction in the inherent design margin of the system.
Therefore, Comed has determined that the procurement of the motor pinion gear with the improper material does constitute a defect per the fcquirements of 10CFR21 and is providing this notification to the NRC.
enmiummacw iam
-- .. . - - . . - . . - .- =~.
!SEhTBy:.- 1-18-96 1:05PM : COM ED CENTRAL FILE- 301 8165151;# 4 i:
l -
\ . .
l _ Byron Ltr 96-0016 Page 4 January 18,1996 i Contact Questions pertaining to this notification should be addressed to:
Bradley J. Adams Site Engineering
- Comed Byron Station -
4450 N. Gennan Chuich Road Byron, Illinois 61010 (815) 234-5441 x2979 Sincerely, K. L. Graesser Site Vice President t
Byron Nuclear Station l KLG/BAltp cc: H. Miller, Regional Administrator-RIII H. Peterson, Senior Resident inspector (Byron) i C. Phillips, Senior Resident Inspector (Braidwood)
G. Dick - NRR R. Assa - NRR Office of Nuclear Facility Safety - IDNS l
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