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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 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 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 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 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 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 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 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 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 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 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 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 ML20153F3691986-02-11011 February 1986 Interim Deficiency Rept 86-02 Re Rejectable Indications in Weld Seams of Loop 1 Steam Generator & Pressurizer.Initially Reported on 860115.Fracture Mechanics Analysis Performed. Final Rept Will Be Submitted Upon Resolution of Issue ML20153F5811986-02-11011 February 1986 Final Deficiency Rept 86-01 Re Misorientation of Burnable Poison Rods A6P2D in Westinghouse Fuel Assembly C54S. Initially Reported on 860114.Assembly A6P2D Returned to Mfg for Repair.Vendor Will Change Mfg & Insp Practices TXX-4692, Final Deficiency Rept CP-86-03 Re Sealing Techniques Used in Installation of Class 1E Instruments.Initially Reported on 860110.Seal Assemblies Provided for Class 1E Devices W/ Exception of Svc Water Intake Areas1986-02-0707 February 1986 Final Deficiency Rept CP-86-03 Re Sealing Techniques Used in Installation of Class 1E Instruments.Initially Reported on 860110.Seal Assemblies Provided for Class 1E Devices W/ Exception of Svc Water Intake Areas ML20137R7721986-01-29029 January 1986 Final Deficiency Rept 84-16 Re Adequacy of ASME Matl Procurement Documentation.Initially Reported on 841002. Review of Documentation for Approx 4,300 Heat/Lot Numbers Re Site Procured ASME Matls Complete ML20151Y3921986-01-29029 January 1986 Final Deficiency Rept 85-02 Re Tank & HX Welding.Initially Reported on 850221.Util Evaluating Westinghouse Response to Insp Results.Other vendor-supplied Items Submitted to Sargent & Lundy for Evaluation ML20137N5291986-01-21021 January 1986 Final Deficiency Rept 85-03 Re Defects Identified During Instrumentation Installation Reverification Program. Safety-related ASME Section III & Class H Instrument Installations Made Prior to Feb 1984 Reinspected ML20137G7421986-01-13013 January 1986 Final Deficiency Rept 82-07 Re Adequacy of safety-related Mechanical Equipment Installed Prior to Sept 1982.Encl Rept Documents Results of Completed Retrofit Program.Issue Closed ML20137H7241986-01-0707 January 1986 Final Part 21 & Deficiency Rept 84-10 Re Wall Thickness Inadequacies for Small Bore ASME Class Ii,Iii & Class H Piping.Initially Reported on 840720.Util & Sargent & Lundy Program Verified Acceptability of safety-related Piping Sys ML20136G5151985-11-12012 November 1985 Final Deficiency Rept 83-07 Re Matl Traceability Verification Program. Matl Traceability Verification at Braidwood, Encl ML20210A1091985-11-0404 November 1985 Interim Deficiency Rept 84-16 Re Adequacy of ASME Matl Procurement Documentation.Approx 337 Heat/Lot Numbers Needing Addl Documentation or Corrective Action to Conform W/Asme Code Resolved.Final Rept Expected in Jan 1986 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 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 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 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 ML20216D3841999-07-12012 July 1999 Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function 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 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 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 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 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 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 ML20196A0721999-03-16016 March 1999 Cycle 8 COLR in ITS Format & W(Z) Function 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 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 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with BW990001, Monthly Operating Repts for Dec 1998 for Braidwood Generating Station,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Braidwood Generating Station,Units 1 & 2.With ML20206B4001998-12-31031 December 1998 Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors for Byron & Braidwood Stations ML20206U9081998-12-17017 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function BW980076, Monthly Operating Repts for Nov 1998 for Braidwood Generating Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Braidwood Generating Station,Units 1 & 2.With ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB ML20195D3561998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Braidwood Generating Station,Units 1 & 2.With ML20155B6711998-10-26026 October 1998 Safety Evaluation Accepting Requests for Relief Associated with Second 10-yr Interval ISI Program Plan ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20154D4401998-10-0202 October 1998 Safety Evaluation Authorizing Second 10-yr Interval ISI Program Request for Relief 12R-30 for Plant,Units 1 & 2 ML20155C2601998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Braidwood Generating Station,Units 1 & 2 ML20195F5911998-09-11011 September 1998 Special Rept:On 980812,addl Unseated Wires Were Discovered. Cause Is Unknown at Present Time.Util Evaluated Number of Unseated/Ineffective Wires & Determined Effect on Containment Structural Integrity.Commitments,Encl ML20196B3711998-09-0808 September 1998 Cycle 8 Operating Limits Rept (Olr) ML20151X6671998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Braidwood Generating Station,Units 1 & 2.With ML20238F3281998-08-31031 August 1998 SER Approving Second 10-year Interval Inservice Insp Program Request for Relief 12R-14 for Braidwood Station,Units 1 & 2 ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237A1091998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Braidwood Generating Station,Unit 1 & 2 ML20236N7001998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Braidwood Generating Station,Units 1 & 2 ML20198A0151998-06-18018 June 1998 10CFR50.59 Summary Rept 960619 Through 980618, Vols I & Ii,Consisting of Descriptions & SE Summaries for Changes to Procedural UFSAR Changes,Tests & Experiments & FP Rept.Without Fp,Rept ML20249A5451998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Braidwood Generating Station Units 1 & 2 ML20247F7711998-05-0808 May 1998 Special Rept:On 980403 & 980503 Seismic Monitoring Sys Was Declared Inoperable.Caused by 5-volt Power Supply & Regulator Card Failure.Imd & Sys Engineering Are Continuing to Identify & Resolve Problems So Sys Can Be Operable ML20247L7591998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Braidwood Generating Station,Units 1 & 2 ML20217K6331998-04-20020 April 1998 Safety Evaluation Accepting Methodology & Criteria Used in Generating Flaw Evaluation Charts for RPV of Braidwood IAW Section XI of ASME Code ML20216C6621998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Braidwood Generating Station,Units 1 & 2 1999-09-30
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.i _ Edson -
. .Il A E One Fwst Nabonel Plaza, CNcago, Illinois ~
QE Address Reply 10: Post Omco Box 767 CNca00. lilinois 00000 0767
'May'15, 1987' Mr. A.' Bert Davis Regional Administrator U. S. Nuclear Regulatory Commission
~199 Rooseve1t-Road Glen Ellyn, IL 60137
Subject:
Braidwood S'tation Unit 2 10 CFR 50.55(e) Interim Report Diesel Engine-Generator Rocker Arm Failure NRC Docket No. 50-457 References-(a): S. C. Hunsader letter to A. B. Davis-t dated March 17, 1987 i-(b): S. C. Hunsader letter to A. B. Davis dated April 2, 1987
Dear Mr. Davis:
On February 17, 1987, Commonwealth Edison company notified your office of a potential deficiency reportable pursuant to 10 CPR 50.55(e) regarding the subject failure at our Braidwood Station. Reference (a) provided information concerning this matter to fulfill the thirty day reporting requirement. Reference (b) provided an interim report regarding an additional rocker arm failure. For tracking purposes, this deficiency was assigned Number 457/87-01. The purpose of this letter is to provide an interim report regarding our investigation to date on these rocker arm failures. Additionally, this interim report addresses independent actions that commonwealth Edison Company'is taking to improve our confidence in the reliability of the diesel generators.
Should you or your staff have any questions on this, please contact this office.
Respectfully, C Y ._ : k S. C. Hunsader Nuclear Licensing Administrator Attachments cc: NRC Resident Inspector - Braidwood 3091K IfI 8705270511 870515 ADOCK 05000457;.
Ng 20 W l PDR S PDR G
e ., , . .. . . .. . .. .. .. . . ..
.. s,-
4 BRAIDWOOD STATION UNIT 2
( 10 CFR 50.55(e) No. 457/87-01 INTERIM REPORT Cooper-Bessemer Reciprocating (Cooper-Bessemer) the diesel generator manufacturer, has provided a status report, dated April 13, 1987, detailing their investigation into the rocker arm failures at Braidwood Station. The following provides a summary of that investigation:
.On February 6, 1987, Commonwealth Edison reported to NRC Region III that during a 24-hour test run of the 2A Diesel Generator on February 4, 1987 five (5) of twenty.(20) cylinders showed rocker arm damage. At that time NRC Region III generated a preliminary Notification of. Event or Unusual Occurance report. As noted in the April 13, 1987 Cooper-Bessemer report, the February 4, 1987 failure was caused by seized crossheads.
On February 17, 1987 N - mwealth Edison notified NRC Region III of another rocker arm failure on cylinder 5R for the 2A Diesel Generator that occurred on February 13, 1987. Similarly on March 30, 1987 Commonwealth Edison informed NRC Region III of inlet and exhaust rocker arm failure in cylinder SR for the 2B Diesel Generator that occurred on March 29, 1987.
Cooper-Bessemer has advised that the cause of the February 13, 1987 and March 29, 1987 failures remain unexplained at this time. However, based on their previous " serious problem free" history with four cycle engine cylinder heads between 1945 and January, 1987, and that 7 of 8 engines at Byron and Braidwood Stations currently appear to be free from further rocker arm breakage, Cooper-Bessemer has recommended that a 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> proving run be completed on Braidwood Station 2B Diesel Generator to demonstrate rocker arm acceptance. This 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> proving run is planned for late May or early June, 1987. (Attachment 1 provides a summary of diesel generator run hours through April 30, 1987 that show successful long-term operation).
Commonwealth Edison company has conducted an investigation of :
the February 4, 13 and March 29, 1987, Braidwood Station diesel generator l rocker erm failures. The investigation has focused on the tensile strength of rocker arm material. A methodology has been devised which relates Brinell hardness of rocker arm castings to tensile strength using !
portable hardness test equipment. At'this time commonwealth Edison l Company is conservatively concluding that exhaust rocker arms with a tensile strength of less than 20 kai could be susceptible to failure, l
l Based on the investigation results to date, Commonwealth Edison Company has decided to do hardness test on rocker arms in diesel
, generators at the Byron and Braidwood Stations and to replace all exhaust
( rocker arms with a tensile strength of less than 20 ksi. This action is being taken as a conservative measure to improve our confidence in the-reliability of the diesel generators. The test / replacement program has been started at the Byron and Braidwood Stations, contingent on receipt of replacement exhaust rocker arms from Cooper-Bessemer. This program will continued based on the ability to orderly remove the diesel generators from service for testing and to subsequently perform the exhaust rocker arm replacement.
While we did experience corresponding intake rocker arm failures with each exhaust rocker arm failure at Braidwood Station, we believe these intake failures are secondary failures due to the exhaust failures. We believe intake rocker arm low strength is unrelated to intake rocker arm failure at this time. We further believe that the 20 kai replacement threshold at this time is an appropriate threshold. We have experienced rocker arm failures on diesel generators with a low number of run hours. As Attachment 1 also shows, significant successful run hours have been experienced on diesels even with exhaust rocker arms having a 20 ksi or less tensile strength. However, in a longer term effort to further improve our confidence in the diesel generator reliability, we plan to replace rocker arms with less than 30 ksi tensile strength.
Over this testing / replacement period, Commonwealth Edison company considers the Cooper-Bessemer diesel generators at the Byron and Braidwood Stations to be operable based on the Cooper-Bessemer status report letter. The only exception is Braidwood Station 2B diesel generator which is still undergoing preoperational testing and requires a ,
100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> proving run. f Commonwealth Edison Company awaits Cooper-Bessemer's final report addressing the February 13 and March 29, 1987 rocker arm I I
failures. When this information is received, a final report will be submitted.
3091K l
s .
e
.'s ATTACIDEDIT 1
' Diesel Generator Run Hours through April 30, 1987 3
i
- Diesel Generator Run Hours i Byron Station lA 651.6 Byron Station IB 528.7 i
j Byron Station 2A 561.7 4
Byron Station 2B 310.3 i
Braidwood Station lA 415.3 f
Braidwood Station IB 645.7 Braidwood Station 2A 289.5
+ Braidwood Station 2B 139.6 1
I i
i 3091K i
I i
i