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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected 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 ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause ML20115D2001996-07-0909 July 1996 Part 21 Rept Re Mfg Defect of Enterprise DSR-4 & DSRV-4 Edgs,Originally Mfg by Calcon Corp.Amot Control Corp Purchased Calcon Product Line & Maintains Design & Production.Valves Returned to Cooper Energy Svcs on 960131 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 ML20085J6591995-06-15015 June 1995 Potential Part 21 Rept Re Failure of Air Cylinder Mfg by Bellofram Corp at Ggns.Failure Discussed W/Mfg & Judged to Be Isolated Incident W/No Further C/A Required at Affected Utils or Cooper-Bessemer ML18038A8971994-09-0707 September 1994 Part 21 Rept Re Defect in Latching Mechanism of Potter & Brumfield Relay on C&D High Voltage Shut Down Alarm Assembly Printed Circuit Boards.Pull Test on Relay Reset Button Incorporated Into Receiving Insp Procedures ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML17289A6971992-06-26026 June 1992 Amend 1 to Part 21 Rept 158 Re gear-wear Induced Failures in engine-driven Jacket Water Pump in DSRV-16-4 Standby DG Sys. Initially Reported on 911029.Grand Gulf Station Observed Wear Characteristics in as Little as 500 Operating Hours ML20101G9211992-06-19019 June 1992 Part 21 Rept Re Rotated Fuel Assemblies Sometimes Inappropriate for Modern Type Fuel Designs.Reevaluation Concluded That Inadvertently Rotated Fuel Assembly for BWR 4/5 C-lattice Plant Could Not Exceed TS Safety Limit MCPR ML20090L8801992-03-18018 March 1992 Part 21 Re Cracked Piston Castings Received from Acme Foundry,Fairbanks Morse & General Casting.Magnetic Particle Insp of All Pistons Will Be Performed.List of Affected Plants Encl AECM-90-0196, Final Part 21 Rept Re Automatic Switch Co MSIVs Failing to Close Upon Demand from Automatic & Remote Manual Actuation Signals.Initially Reported on 890914.Dual Solenoid Valves Replaced W/Two Single Solenoid Valves1990-11-21021 November 1990 Final Part 21 Rept Re Automatic Switch Co MSIVs Failing to Close Upon Demand from Automatic & Remote Manual Actuation Signals.Initially Reported on 890914.Dual Solenoid Valves Replaced W/Two Single Solenoid Valves ML20043F3431990-06-0808 June 1990 Part 21 Rept Re Circumferential Grove of Varying Depth Up to 0.200 Inches on Inside Surface of Journal Above Attachment Weld to Impeller.Failure of Journal Could Result in Major Damage to Pump.Disassembly Scheduled Over Next 18 Months ML20043G7641990-05-22022 May 1990 Part 21 Rept Re Potential Defect W/Speed Transmitter in Diesel Engine Control Panel of Dsrv Standby Diesel Generator.Estimate of Completion of Corrective Actions Not Possible,Since Correction Made by Other Companies 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 ML19332E2971989-11-22022 November 1989 Revised Part 21 Rept Re MSIV Failure to Close Due to Disk Matl for Dual Solenoid Valve Extruding Into Exhaust Port of Valve.Initially Reported on 890914.Dual Solenoid Valve Replaced or Refurbished Prior to Restart AECM-89-175, Part 21 Rept Re Failure of MSIV to Close Due to Malfunction of Valve.Initially Reported on 890914.Dual Solenoid Valves on All MSIVs Replaced or Refurbished Prior to Restart.Update to Be Submitted by Startup from Fourth Refueling Outage1989-09-18018 September 1989 Part 21 Rept Re Failure of MSIV to Close Due to Malfunction of Valve.Initially Reported on 890914.Dual Solenoid Valves on All MSIVs Replaced or Refurbished Prior to Restart.Update to Be Submitted by Startup from Fourth Refueling Outage AECM-89-0175, Part 21 Rept Re Failure of MSIV to Close Due to Malfunction of Valve.Initially Reported on 890914.Dual Solenoid Valves on All MSIVs Replaced or Refurbished Prior to Restart.Update to Be Submitted by Startup from Fourth Refueling Outage1989-09-18018 September 1989 Part 21 Rept Re Failure of MSIV to Close Due to Malfunction of Valve.Initially Reported on 890914.Dual Solenoid Valves on All MSIVs Replaced or Refurbished Prior to Restart.Update to Be Submitted by Startup from Fourth Refueling Outage 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 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 AECM-88-0190, Part 21 Rept Re Diesel Generator Left Bank Intercooler Tubes,Mfg by Imo Delaval.Leaks Initiated When Tubes Ruptured by Diffuser Plate in Inlet Adaptor.Initially Reported on 880930.Intercooler Replaced1988-09-30030 September 1988 Part 21 Rept Re Diesel Generator Left Bank Intercooler Tubes,Mfg by Imo Delaval.Leaks Initiated When Tubes Ruptured by Diffuser Plate in Inlet Adaptor.Initially Reported on 880930.Intercooler Replaced 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 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 ML20215G2441987-06-16016 June 1987 Part 21 Rept Re Failure of Load Sequencing Equipment Supplied in Aug 1977 During Scheduled Testing.Caused by Open Electrical Connection on One Crimp Lug.Since 1978,insulated Lugs Used on All Equipment ML20216E4721987-05-28028 May 1987 Part 21 Rept 140 Re Potential Defect in Air Pressure Regulators Mfg by Bellofram.Dripwell Gasket May Fail Due to Mismachining of Gasket Seating Surface Causing Loss of Control Air & Starting Air Pressure AECM-86-0409, Informs That Testing Program for Final Reportability Determination on as-found Conditions of Sealed Splices Delayed Until Feb 1987,per 861212 Telcon.Program Includes Raychem Tube Configurations Found in BWR & PWR Applications1986-12-19019 December 1986 Informs That Testing Program for Final Reportability Determination on as-found Conditions of Sealed Splices Delayed Until Feb 1987,per 861212 Telcon.Program Includes Raychem Tube Configurations Found in BWR & PWR Applications AECM-86-0400, Deficiency Rept Re Wiring in Environmentally Qualified Actuators on air-operated Valves.Initially Reported on 861117.Matl Analysis of Wiring Samples Underway. Reportability Determination Will Be Completed in Jan 19871986-12-18018 December 1986 Deficiency Rept Re Wiring in Environmentally Qualified Actuators on air-operated Valves.Initially Reported on 861117.Matl Analysis of Wiring Samples Underway. Reportability Determination Will Be Completed in Jan 1987 AECM-86-0376, Final Deficiency & Part 21 Rept 4 Re Low Flow Condition Through Standby Svc Water (SSW) Pump A.Initially Reported on 820415.Procedures to Ensure That Min Pump Flow Provided When SSW Sys Automatically Started,Issued1986-11-25025 November 1986 Final Deficiency & Part 21 Rept 4 Re Low Flow Condition Through Standby Svc Water (SSW) Pump A.Initially Reported on 820415.Procedures to Ensure That Min Pump Flow Provided When SSW Sys Automatically Started,Issued ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires ML20195D2171986-05-27027 May 1986 Rev 1 to Part 21 Rept Re Dowel Displacement on Connecting Rod Bearings Purchased During Nov 1985 - Apr 1986.Initially Reported on 860421.Rod Bearings Will Be Inspected Dimensionally.Further Info Forthcoming ML20203A0431986-04-0707 April 1986 Part 21 Rept Re Problem Which May Affect Operation of Model C Deluge Valve for Fire Protection Sys.Ie Info Notice 84-16 Issued on 840302 to Describe Failure of Valves to Operate. All Shipments of Model C Valves Stopped ML20154Q3141986-03-10010 March 1986 Final Part 21 Rept Re Possible Defect on Inflatable Door Seals for Personnel Air Locks Used in Plant Reactor Containment Sys.Program to Supply Environmentally Qualified Inflatable Seals Should Be Completed by mid-1986 ML20154N4361986-03-10010 March 1986 Part 21 Rept Re Defect on Inflatable Door Seals for Personnel Air Locks Used in Reactor Containment Sys of Nuclear Power Plants.Initially Reported on 830919.Environ Qualification Testing of New Seal Design Completed ML20154N3431986-03-10010 March 1986 Initial Part 21 Rept 135 Re Potential Problem W/Lube Oil Sump Tank Foot Valve of Dsrv Standby Diesel Generator for Facilities.Cause Not Determined.Recommends Utils Inspect Condition of Foot Valve Liners & Notify Tdi of Findings ML20153D8861986-02-17017 February 1986 Part 21 Rept Re Failure of Penetration & Conduit Seal Configurations During Fire Tests.Initially Reported on 860214.Evaluation of Number & Location of Defective Seals in Progress.Nrc Assistance Requested AECM-86-0050, Final Part 21 & Deficiency Rept RD-85/04 Re Inadequate Cooling in Tdi Diesel Generator Control Panels.Initially Reported on 850429.Linear Reactors on Panels Replaced & Cooling Air Supply Installed1986-02-14014 February 1986 Final Part 21 & Deficiency Rept RD-85/04 Re Inadequate Cooling in Tdi Diesel Generator Control Panels.Initially Reported on 850429.Linear Reactors on Panels Replaced & Cooling Air Supply Installed ML20138A7391985-11-27027 November 1985 Interim Deficiency Rept PRD-83/12 Re Failure of Agastat GP Series Relays to Switch.Initially Reported on 830906. Requests Further Update Be Delayed Until Const Restart ML20198C4981985-11-0606 November 1985 Part 21 Rept Re Potential Defect in Dsr or Dsrv Standby Diesel Generator Intake & Exhaust Valve Springs Mfg by Betts Spring Co.Users Recommended to Inspect Engines for Broken Springs & Identify Original Mfg ML20135H7751985-09-17017 September 1985 Part 21 Rept,Correcting Final Deviation Disposition Request Status Re Unqualified Test Switch.No Changes Planned Since Emergency Buses Found to Have Adequate Separation ML20132B0261985-09-0303 September 1985 Part 21 Rept Re Possibility of Engine Ingestion of Unwelded Part in American Air Filter Standby Diesel Generator Intake Silencer.Immediate Hold Should Be Placed on Diesel Engines/Intake Silencers Not Yet in Svc ML20127E6261985-06-17017 June 1985 Part 21 Rept Re Failure to Follow Design Control Procedures Resulting in Misapplication of Switch CR2940 on Standby Liquid Control Sys Which May Cause Failure of Class 1E Equipment.Design Drawing Change in Progress ML20140G0901985-06-13013 June 1985 Part 21 & Final Deficiency Rept PRD-84/04 Re Failure of Automatic Sprinkler Corp of America Deluge Valves to Open. Condition Not Reportable Under 10CFR50.55(e) or Part 21 ML20127H5411985-05-17017 May 1985 Part 21 Rept Re Potential Defect in Engine Generator Control Panels of Dsr or DSRV-16 Standby Diesel Generator.Review of Generator Control Panel Installation by Each Facility Recommended AECM-85-0142, Part 21 & Second Interim Deficiency Rept RD-85/03 Re MSIV Failure to Remain Closed Due to Failure of Automatic Switch Co Dual Solenoid to Transfer When Deenergized.Initially Reported on 850321.Next Rept by 8506301985-04-30030 April 1985 Part 21 & Second Interim Deficiency Rept RD-85/03 Re MSIV Failure to Remain Closed Due to Failure of Automatic Switch Co Dual Solenoid to Transfer When Deenergized.Initially Reported on 850321.Next Rept by 850630 AECM-85-0133, Part 21 & Final Deficiency Rept 85-02 Re Tdi Diesel Generator Air Start Header Check Valve Failure.Design Change Initiated to Replace Eight Existing Check Valves on Div I & II W/Appropriate Check Valves Suitable for Design1985-04-26026 April 1985 Part 21 & Final Deficiency Rept 85-02 Re Tdi Diesel Generator Air Start Header Check Valve Failure.Design Change Initiated to Replace Eight Existing Check Valves on Div I & II W/Appropriate Check Valves Suitable for Design 1999-04-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F9921999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20212F5641999-09-23023 September 1999 SER Concluding That All of ampacity-related Concerns Have Been Resolved & Licensee Provided Adequate Technical Basis to Assure That All of Thermo-Lag Fire Barrier Encl Cables Operating within Acceptable Ampacity Limits ML20211Q3171999-09-0909 September 1999 Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20216E4881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Grand Gulf Nuclear Station.With ML20211A6921999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20209J1961999-07-12012 July 1999 Special Rept 99-001:on 990528,smoke Detectors Failed to Alarm During Performance of Routine Channel Functional Testing.Applicable TRM Interim Compensatory Measure of Establishing Roving Hourly Fire Patrol Was Implemented ML20196K4981999-07-0101 July 1999 Safety Evaluation Authorizing PRR-E12-01,PRR-E21-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01.Concludes That Alternatives Proposed by EOI Acceptable ML20209G0691999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20196A1161999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Grand Gulf Nuclear Station.With ML20206Q4831999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Grand Gulf Nuclear Station Unit 1.With ML20206J1201999-04-30030 April 1999 Redacted ME-98-001-00, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205P8771999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Grand Gulf Nuclear Station,Unit 1.With 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 ML20207K5141999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20206T7991999-01-31031 January 1999 Iodine Revolatizitation in Grand Gulf Loca ML20207A8301998-12-31031 December 1998 1998 Annual Operating Rept for Ggns,Unit 1 ML20206R9501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20206D7721998-12-31031 December 1998 South Mississippi Electric Power Association 1998 Annual Rept ML20198E2481998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20195F4121998-11-13013 November 1998 Rev 16 to GGNS-TOP-1A, Operational QA Manual (Oqam) ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20195C2791998-11-0505 November 1998 BWR Feedwater Nozzle Inservice Insp Summary Rept for GGNS, NUREG-0619-00006 ML20195F4801998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML20154K2391998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Grand Gulf Nuclear Station Unit 1.With ML20155F1961998-09-0101 September 1998 Engineering Rept for Evaluation of BWR CR Drive Mounting Flange Cap Screw ML20153B2161998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20237B6661998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Grand Gulf Nuclear Station,Unit 1 ML20236R0231998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Grand Gulf Nuclear Station,Unit 1 ML20155J0811998-05-31031 May 1998 10CFR50.59 SE for Period Jan 1997 - May 1998 ML20249B1251998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Grand Gulf Nuclear Station,Unit 1 ML20248B6261998-05-11011 May 1998 Rev 6 to Grand Gulf Nuclear Station COLR Safety-Related ML20217Q6701998-05-0606 May 1998 SER Approving Proposed Postponement of Beginning Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) at Grand Gulf for Circumferential Shell Welds for Two Operating Cycles ML20206J1271998-04-30030 April 1998 Pressure Locking Thrust Evaluation Methodology for Flexible Wedge Gate Valves ML20247F3591998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Grand Gulf Nuclear Plant,Unit 1 ML20217M8951998-04-30030 April 1998 QA Program Manual ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) ML20217P0381998-04-0606 April 1998 Safety Evaluation Supporting Amend 135 to License NPF-29 ML20217A0291998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Grand Gulf Nuclear Sation,Unit 1 ML20216J4211998-03-18018 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Grand Gulf Nuclear Station ML20216J2021998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Grand Gulf Nuclear Station,Unit 1 ML20203A2891998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Grand Gulf Nuclear Station ML20247B4111997-12-31031 December 1997 1997 Annual Financial Rept for South Mississippi Electric Power Association ML20203H9741997-12-31031 December 1997 1997 Annual Operating Rept, for Ggns,Unit 1 ML20198P1121997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Grand Gulf Nuclear Station,Unit 1 ML20203B5581997-12-0404 December 1997 Special Rept 97-003:on 971111,valid Failure of Div 2 EDG Occurred,Due to Jacket Water Leak.Failure Reported,Per Plant Technical Requirements Manual Section 7.7.2.2 ML20203K4031997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Grand Gulf Nuclear Station,Unit 1 ML20199H3711997-11-19019 November 1997 SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50 ML20199F3431997-11-18018 November 1997 SER Accepting Rev 15 of Operational Quality Assurance Manual for Grand Gulf Nuclear Station,Unit 1 1999-09-09
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MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi E dellaliddE P. O . B O X 1640, J A C K S O N, MIS SIS SlP PI 3 9 2 05
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Office of Inspectie Enforcement gr s/$
U. S. Nuclear Reg .t.ory Commission g yff ,
Region II 101 Marietta Street, N.W.
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Suite 3100 2_" SEP2 2 1933, gj Atlanta, Georgia 30303 - u. s. i,u , , , , ,
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Attention: Mr. J. P. O'Reilly, Director
Dear Mr. O'Reilly:
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SUBJECT:
Grand Gulf Nuclear Station Units 1 and 2 Docket Nos. 50-416/417 File 0260/15525/15526 PRD-80/39, Final Repc .
Defective Terminations in ITE/ Brown Boveri Electric Breakers and Switchgear AECM-81/338
References:
- 1) AECM-80/177, 8/1/80
- 2) AECM-80/276, 11/6/80
- 3) AECM-81/70, 2/17/81 On July 3, 1980, Mississippi Power & Light Company notified Mr. R.
Wright, of your office, of a Potentially Reportable Deficiency (PRD) at the Grand Gulf Nuclear Station (GGNS) construction site. The deficiency concerns defective terminations in ITE/ Brown Boveri Electric breakers and switchgear.
We have determined that this deficiency, had it remained uncorrected, cotid adversely affect the safety of operations of the nuclear power plant and is reportable under the provisions of 10CFR50.55(e). The systems containing the deficient equipment have been turned over to MP&L, but the affected equip-ment lad been identified prior to turnover so the deficiency is not reportable under 10CFR21.
Atteched is our final report giving all necessary information.
Yours truly, 7
J. P. McGaughy, Jr. TO y KDS/ MAL:dr ll ATTACHMENT cc: See page 2 8109220667 810915 PDR ADOCK 05000416 g PDR Member Middle South Utilities System J
. _ _ - _ - _ _ ~ . - . -... -
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Mr. J. P. O'Reilly AECM-81/338 NRC Page 2 I
cc: Mr. N. L. Stampley Mr. R. B. McGehee Mr. T. B. Conner j
Mr. Victor Stello, Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 2055.'3 Mr. G. B. Taylor South Miss. Electric Power Association P. 0.. Box 1589.
Hattiesburg, MS 33401 k
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. . Atts:chment to AECM-81/338 Paga 1 of 2 FINAL REPORT FOR PRD-80/39 I. Description of Deficiency _
Vendor terminations (ring tongue terminal lugs) in the 4.16 KV metal clad switchgear and 480 volt load centers manufactured by Brown Boveri Electric, Inc. were found to have faulty crimps.
After this deficiency was noted, our Constructor undertook, with the equipment vendor, Brown Boveri Electric, Inc., an inspection of all lugs in the switch-gear to verify that the conductors are visible inside the lug barrel, and that a crimp has been placed properly on each barrel.
During this inspection program several other deficiencies were noted such as:
- 1. Lugs for #10 and #12 wire were used on #14 wire.
- 2. Some lugs were bent and/or deformed.
- 3. Some terminal lugs had been trimmed ar cut to fit into the terminal strips.
- 4. Wires were inserted too far and protruded past the end of the lug barrel.
- 5. Individual strands were bent back and protruded from the rear of the lug barrel.
t Several other problems were also identified during the inspection of the circuit breakers on nine (9) of the breakers. These included deficient vendor wires , cables , contacts, and lugs. The scope of this PRD was expanded to
! include these breakers.
The deficient equipment is in the 4.16 KV Switchgear and Load Shedding and Sequencing Panels, (R21). Most of the other plant systems are affected also.
i The deficiency affects both Unit 1 and Unit 2. .
The cause of the deficiency was improper workmanship at the manufacturer's shop. This deficiency does not apply to the NSSS supplier.
l II. Analysis of Safery Implications Approximately fifteen (15) lugs were noted which had wire not visible in the end of the barrel, and/or which had loose wires. One of these deficient tera-inations could have af fected the overcurrent protection of the equipment and cause a failure. Therefore, these deficiencies are reportable under the pro-visions of 10CFR50.55(e).
- The deficient ' equipment had been identified prior to turnover to MP&L by our Constructor, so this deficiency-is not reportable under 10CFR21.
Brown Boveri Electric Inc. has reported this condition to the NRC under the I
provisions of 10CFR21. - This was by letter from D. D. Duvall, Vice President and General Manager, to Mr. Victor Stello, Jr., Director, Office of Inspection
, and Enforcement, U. S. Nuclear Regulatory Commission, Washington, D. C., April 3, 1981.
Attcchment to AECM-81/338
. . pig 2 2 cf 2 III. Corrective Actions Taken The cause of the deficiency was improper workmanship at the manufacturer's shop. All safety-related medium voltage switchgears and 480 volt load centers supplied by Brown Bove:1 Electric for Unit 1 (4.16 KV Buses 15AA and 16AB and 480 Volt Load Centers 15BA1 through 15BA6 and 16BB1 through 16BB6) have been inspected and reworked as necessary. In all cases where a defective lug was found, the affected lug was cut off and reworked to our Constructor's standards. The dravout circuit breakers in the 480 volt load centers were given an inspection of al' lugs which could be readily seen without disassembly of the breaker. It was decided that full breater disassembly was not required since most deficient terminations were in the cabinets, not in the breakers.
Further, the breakers were manufactured in a different factory under a more rigid QA/QC program. This inspection also covered the breakers for the deficiencies noted in IE Information Notice No. 81-06, March 1,1981.
All corrective actions for Unit I with the exception of nine (9) circuit breakers have been completed. These will be repaired during future plant switchgear outages prior to Unit i fuel load. Our Constructor has issued Nonconformance Report (NCR) 5173 to track this.
Brown Boveri Electric Switchgears and Load Centers for Unit 2 will be inspected at a future date. Management Corrective Action Report (MCAR) 117 will track this inspection. All corrective actions for Unit 2 will be completed prior to Unit 2 fuel load.
Actions to preclude future recurrence have been undertaken by Brown Boveri, Inc. as outlined in their letter of April 3, 1981, to the Nuclear Regulatory Commission, which is attached.
l r
. . . . r 1; d
bbe: Mr. D. C. Lutken Mr. J. Leatherman.
Dr. D. C. Gibbs Manager of BWR-6 Licensing Mr. J. N. Ward General Electric Company Mr. J. P. McGaughy, Jr. 175 Curtner Avenue i Mr. J. D. Heaton San Jose, CA. 95125 Mr. R. .
Trickovic Mr. J. W. Yelverton Mr. L. F. Dale -Mr. D. M. Houeton Mr. C. K. McCoy
. U. S. Nuclear Regulatory Commission '
Mr. T. H. Cloninger Division of Licensing f.
Mr. R. A. Ambrosino Washington, D. C. 20555 ,
Mr.'A. J. Iosue /
Mr. G. B. Rogers Mr. S. H. Hobbs Mr. J. Matore Mr. L. E. Ruhland U. S. Nuclear Regulatory Commission Mr. D. L. Hunt Division of Licensing. / '
Mt. A. G. Wagner Washington, D. C. 20555 Mr. P. A. Taylor PRD File File
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Brown B(. :n. Electn.c, Inc.
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Manufacturer of I.T E Ek ctrical Pc,wer Eoucment YTSIf April 3, 1981 b N- k i
RECEVED .
Mr. Victor Stello, Jr. APR - 61981 Director, Region II -
Of fice of Inspection & Enforcement U. S. Nuclear Regulatory Cor:r.iission t e D.O. ;
. Washington, D. C. 20555
Dear Mr. Stello:
This report is a follow-up to a 10CTR50.55(e) report issued by the Mississippi Power & Light Company on the Crand Culf Nuc] car Station with respect to problems noted with ring tongued wire terminals in medium vol-tage metal-clad switchgear and 480V load centers supplied by Brown Boveri Electric, Inc., (formerly known as I-T-E). -
This ondition was documented in NCR 4851 by Bechtel who is both Engineer s and Constnictor for the Crand Culf Nuclear Station. Initially, it was .
reported that two (2) crimped wire teminals came loose from their control wires in safety related switchgear. BBEL and Bechtel mutually agreed that an inspection should be made to detemine that there were no other loose wire teminals in the s,afety related switchgear wiring. Prior to this inspection an inspection criteria was established. This inspection criteria was to make a visual inspection of the crimped wire terminals to determine 'that the stranded wire was visible in the barrel of the terminal.
If the wire were not visible, this crimped termination was not acceptable.
This criteria was verified by tests performed by BBEL. ,
The results of this inspection which was performed by Bechtel show that there were approximately 15 wire teminals in which the wire was not virible e l
in the end of the barrel, or which had loose wires. Bechtel reported that l
one of these wires could have affected the overcurrent protection of the
- equipment.
During the course of this equipment inspection program at the jobsito, there were other wire terminal anomalies which were detected. These included the items listed below.
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- 1. No.10-12 wire teminals had been crimped to a No. 14 wire.
l 2. Some wire teminals were bent or deformed.
- 3. Some wire teminals had been trimmed or cut to fit into a teminal board connection.
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. 0 bitchgear Systems Divis;oa h Spring %,e. PA 19477 e (215) 528 7400 -
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Page 2 April 3, 1981
- 4. Wire was protruding too far from the end of the barrel.
- 5. In some cares, individual wire strands were bent back and protrudinr, from the rear end of the wire terminal.
Although the wire terminal anomalics listed above do not represent perfect workmanship, the nature of these anomalies is such that they would not result in a safety related problem. It should be noted that the equipment inspection reference so far, and the deficiencies and annmalics noted sere found in Unit #1 switchgear which was manufactured during the period of late 1975 through carly 1977 at the EBEL Chalfent, Pa. Switchgear Systems Division Operation.
On the average, during the manufacturing of a single cubic 3e of lou-voltage switchgear there are some 282 wite terminal connections which are crimped.
In the metal-clad switchgear there are some 240 connections per cubicle in the SHK equipment and some 297 connections per cubicle in 15HK equipment.
In the Unit 1 switchgear at Grand Gulf there are approximately 36,000 wire terminal connections and approximately one-half of these are in safet?
related circuits. These figures are based on the "as built" drawings for the switchgear but there have been many additional circuits added te the equipment during field modifications.
Although the deficient wire terminal connections at Crand Gulf are less than 0.1 of one percent, other users should determine the need for inspecting the safety related cirtufts to assure that wire terminals are not loose and that wirc strands are visible when looking into the end of the crimped wire
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terminal. ,
The cause of the deficiency at Grand Gulf is improper workmanship. During the time sp,an of manufacturing of the switchgear for Grand Gulf, inspec-tion was performed on a sampling basis. Early in 1977 BBEL procured new and improved crimping tools. These tools were identified by individual serial numbers and were issued to wiring personnel in accordance with a controlled plan. Wiring personnel were retrained in accordance with the tool manufacturers instructions.
Wire terminal inspection procedures were revised and updated. Crimping tool calibration and procedures were revlacd and updated and during the second quarter of 1977, the wire terminal inspection criteria was changed from a sampling inspection to a 100% inspection for safety related switch-gear. .
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April 3, 1981 Unit #2 switchgear at Grand Culf has also been furnished by BBEL. This equipment was manufactured during 1978 and early 1979. A cursory inspection of the equipment was performed at the jobsite during a recent visit and a few minor ancmalies such as a single strand of wire protruding from the rear of the wire terminal were no.ted. BBEL will propose r.o Bechtel to per-form a sample inspection of Unic A2 switchgear wire terminals to determine if any further action is required.
Although the majority of the safety related switchgear has been manufac-tured at the BBEL Chalfont, ?a. Operation, equipment of the same design has been manufactured at the BBEL Tulsa, Oklahoma Operation and a small amount of equipment has been manufactured at the BBEL Sanford, Florida Operation.
If you require any additional details in this matter, please feel free to contact Mr. E. W. Rhoads at 215-628-7660.
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\ *< t 4 ;1L ff1 LL Vic'e President & General Managcr Switchgear Systems Division EWR/ja ec: J. P. O'Reilly Director, Region II ,
Office of Inspection and Enforcement
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