ML20082U744
From kanterella
| ML20082U744 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 12/06/1983 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, 7713N, 83-05, 83-5, NUDOCS 8312190162 | |
| Download: ML20082U744 (1) | |
Similar Documents at Byron | |
|---|---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217A1691999-09-22022 September 1999
[Table view]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 ML20082Q9491995-04-21021 April 1995 Part 21 Rept Re Notifying Commission of Potential Design Defect of Ksv EDG Sys 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 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 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 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) 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 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 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 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 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 ML20138P5241985-10-25025 October 1985 Revised Final Deficiency Rept 82-03 Re Emergency Diesel Generator Field Relay Failure.Replacement of 120-volt Ac Voltage Sensing Relays Accomplished Using 110-volt Dc Relays ML20133H4611985-10-0404 October 1985 Final Deficiency Repts 85-04(BY) & 85-07(BW) Re Faulty Tachometer Readings on Emergency Diesel Generators.Initially Reported on 850905.Dc-to-dc Regulator Replaced w/dc-to-dc Converter.All Similiar Tachometer Circuits Will Be Revised ML20137M5621985-09-0606 September 1985 Part 21 & Deficiency Rept Re Cooper-Bessemer Diesel Generators.Erroneous RPM Readings Discovered on 840926 & 850706 for Diesel Generators 1B & 2A,respectively.Dc to Dc Converter Will Replace Dc to Dc Regulator ML20135E1161985-09-0505 September 1985 Part 21 Rept Re Use of Connectron non-IEEE Qualified Matl in Spare Part Terminal Blocks Supplied to Facilities. Appropriate Customers Notified.Terminal Blocks Should Be Reviewed to Identify Defective Matl ML20127A4741985-06-14014 June 1985 Final Deficiency Repts 85-02 for Byron Unit 2 & 85-04 for Braidwood Re Seismic Qualification on Containment Floor Drain Valves Mfg by Xomox Corp.Initially Reported on 850516. Brackets Added to Valves to Increase Rigidity ML20127A9751985-06-14014 June 1985 Final Deficiency Rept Re Evaluation for Potential Environ Effects on safety-related Equipment Using Inaccurate Info. Initially Reported on 850516.Temp Monitoring Sys Will Be Installed to Automatically Isolate High Energy Line Sys ML20128G5101985-05-24024 May 1985 Part 21 Rept Re Heat Numbers to Be Added & Deleted from Sublist Sheet A,Based on Review of NRC ML20128M5341985-05-15015 May 1985 Revised Final Deficiency Rept 83-11 Re Anaconda Flexible Conduit.Initially Reported on 831006.Installation Drawings Now Specify Use of Svc Air Co SF65 or SF63 or American Boa Nb Flexible Conduit in Lieu of Anaconda Product ML20127N0621985-05-13013 May 1985 Part 21 Rept Re Incorrect Short Time Delay Band Lever Inadequately Installed in Low Voltage K-line Circuit Breaker Electromechanical Overcurrent Trip Device.Visual Insp to Determine If Correct Lever Installed Recommended ML19302F7581985-04-23023 April 1985 Corrects Typo in Second Interim Deficiency Rept 84-03 Re Installation of Butt Splices in Electrical Connectors.Rept Should Have Indicated That 564 Splices Documented But Not Inspected ML20116H4141985-04-19019 April 1985 Supplementary Part 21 Rept Re Failure of Anchor Darling MSIV Airline Check Valve.Initially Reported on 850321.Caused by Poppet in Valves Cocking on Stem Guide.Valves Replaced W/Parker CPI Check Valve ML20116H3821985-04-18018 April 1985 Final Deficiency Rept 84-02 Re Containment Spray Pump Impellers Being Switched.Initially Reported on 840504.Tags Mounted on Each Pump,Clearly Indicating Either Train a or B ML20100D1141985-03-21021 March 1985 Part 21 & Interim Deficiency Rept Re Defective Parker-Hannifin Co Airline Check Valves in MSIV Actuators. Initially Reported on 850319.Valves Failing Initial Testing Will Be Inspected.Next Rept within 60 Days ML20100A7821985-03-11011 March 1985 Final Deficiency Repts 84-07 & 84-19 Re Crush Strength of Energy Absorbing Matl Supplied by Hexcel & Used in Pipe Whip Restraints.Matl Used in Westinghouse Restraints within Procurement Spec Requirements ML20107H8851985-02-15015 February 1985 Final Deficiency Rept 85-01 Re 10 Amp Motor Control Ctr Breakers W/Low Interrupt Ratings.Initially Reported on 850117.All Affected safety-related Breakers Will Be Replaced Before Fuel Load ML20113D7061985-01-15015 January 1985 Final Part 21 Rept Re Defective Valve Operators.Initially Reported on 841030.Control Valve Failures Resulted from Hydraulic Fluid Contamination & Improper Maint Procedures Which Allowed Aeration of Hydraulic Fluid ML20100J6421984-11-29029 November 1984 Interim Deficiency Repts 84-07 & 84-19 Re Crush Strength of Energy Absorbing Matl Supplied by Hexcel Used in Pipe Whip Restraints.Initially Reported on 841030.Hexcel Requested to Evaluate Matl W/Reduced Crush Strength 1999-09-22 Category:TEXT-SAFETY REPORT MONTHYEARML20217H5221999-09-30030 September 1999
[Table view]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 ML20212B9261999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Byron Station,Units 1 & 2.With ML20210R3431999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Byron Station, Units 1 & 2.With ML20210E2251999-07-21021 July 1999 B1R09 ISI Summary Rept Spring 1999 Outage, 980309-990424 ML20209G1751999-07-0808 July 1999 SG Eddy Current Insp Rept,Cycle 9 Refueling Outage (B1R09) 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 ML20207H7851999-06-30030 June 1999 Rev 0 to WCAP-15183, Commonwealth Edison Co Byron,Unit 1 Surveillance Program Credibility Evaluation ML20207H7771999-06-30030 June 1999 Rev 0 to WCAP-15177, Evaluation of Pressurized Thermal Shock for Byron,Unit 2 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) 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 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) 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 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 ML20204H9941999-03-0303 March 1999 Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20204C7671999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Byron Station,Units 1 & 2.With ML20199G8271998-12-31031 December 1998 Rev 1 Comm Ed Byron Nuclear Power Station,Unit 1 Cycle 9 Startup Rept ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20202F6181998-12-31031 December 1998 Cycle 8 COLR in ITS Format & W(Z) Function ML20206B4001998-12-31031 December 1998 Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors for Byron & Braidwood Stations ML20199E6371998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Byron Station,Units 1 & 2.With ML20202F6021998-12-31031 December 1998 Cycle 9 COLR in ITS Format & W(Z) Function ML20196K6731998-12-31031 December 1998 10CFR50.59 Summary Rept for 1998 ML20207H7731998-11-30030 November 1998 Rev 0 to WCAP-15125, Evaluation of Pressurized Thermal Shock for Byron,Unit 1 ML20207H8011998-11-30030 November 1998 Rev 0 to WCAP-15124, Byron Unit 1 Heatup & Cooldown Limit Curves for Normal Operation ML20198D1501998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Byron Nuclear Power 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 ML20195F8321998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Byron Nuclear Power Station,Units 1 & 2.With 05000454/LER-1998-018, Corrected LER 98-018-00:on 980912,inoperable Unit 1 DG Was Noted.Caused by Low Lube Oil Pressure Condition.Immediately Entered Into Lcoar for AC Sources TS 3.8.1.1,Action a1998-10-0909 October 1998 Corrected LER 98-018-00:on 980912,inoperable Unit 1 DG Was Noted.Caused by Low Lube Oil Pressure Condition.Immediately Entered Into Lcoar for AC Sources TS 3.8.1.1,Action a ML20207H7671998-10-0505 October 1998 Rv Weld Chemistry & Initial Rt Ndt ML20154L5501998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Byron Nuclear Power Station,Units 1 & 2.With ML20197C9051998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Byron Nuclear Power Station,Units 1 & 2.With ML20151Z9651998-08-31031 August 1998 Revised MOR for Aug 1998 for Byron Nuclear Power Station. Rept Now Includes Page 9 Which Was Omitted from Previously Issued Rept ML20238F6551998-08-28028 August 1998 SE Authorizing Licensee Request for Relief NR-20,Rev 1 & NR-25,Rev 0 Re Relief from Examination Requirement of Applicable ASME BPV Code,Section XI for First ISI Interval Exams ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20237B3361998-08-14014 August 1998 B2R07 ISI Summary Rept,Spring 1998 Outage, 961005-980518 ML20237B4841998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Byron Nuclear Power Station Units 1 & 2 1999-09-30 |
Text
N Comm:nw:dth Edison V[i' ) 'One FirstReply Address National Plaza, to: Post OfficeChicago.
Box 767 Ilknois hh y
Chicago. lilinois 60690 December 6, 1983 Mr. James G. Keppler, Regional Administrator U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Byron Generating Station Unit 1 Preservice Inspection Weld Indications NRC Docket No. 50-454 Reference (a): May 26, 1983 letter from E. D. Swartz to J. G. Keppler >
(b): October 27, 1983 letter from T. R. Tramm to H. R. Denton
Dear Mr. Keppler:
This is to provide a final report on several rejectable weld indications in the pressurizer and two steam generators at Byron 1. For NRC tracking purposes this deficiency was assigned number 83-05.
In reference (a) Commonwealth Edison reported that several weld indications had been found during the preservice inspection
- program and we indicated that additional NDE testing would be 4 performed. Reference (b) documented the results of all of the i examinations and our plans repair of indictions in the steam generators. We also provided our basis for not pursuing repair of the pressurizer indications and requested NRC concurrence.
Since reference (b) provides complete details of these indications and our planned corrective actions, that report should suffice as a final report on the 50.55 (e). reportable deficiency.
Please direct further questions to this office Very truly yours, N"
T. R. Tramm
, Nuclear Licensing Administrator bg/1m i
cc: Director of Inspection and Enforcement
! NRC Resident Inspector - Byron ;)[)
7713N 0312190162 831206 Ogg y 0 PDR ADOCK 05000454 8 iS$3 ,
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