|
---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils NRC-97-0141, Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility1997-12-23023 December 1997 Deficiency Rept Re Malfunction of EDG Number 11 Automatic Voltage Regulator (AVR) Printed Circuit Board Rev B,Due to Failure of Operational Amplifier U8 Chip.Avr Board Rev B Was Sent Offsite to Independent Engineering Facility ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A NRC-97-0005, Part 21 Rept Re 961113,EDG 11 Failed Surveillance Test 24.307.01 for LOP Coincident W/Loca.Avr Board Rev B Was Sent Offsite to an Independent Engineering Test Facility. CA Include More Analysis & Testing of AVR Board1997-02-0606 February 1997 Part 21 Rept Re 961113,EDG 11 Failed Surveillance Test 24.307.01 for LOP Coincident W/Loca.Avr Board Rev B Was Sent Offsite to an Independent Engineering Test Facility. CA Include More Analysis & Testing of AVR Board ML20115F2471996-07-0303 July 1996 Part 21 Rept Re Piping (Small Portion of Unmelted Matl Drawn Lengthwise Into Bar During Drawing Process) Defect That Existed in Bar as Received from Mill.Addl Insp Procedure for Raw Matl Instituted NRC-94-0072, Part 21 Rept Re Improper Installation of Thermo-Lag Fire Barrier Matl Furnished & Delivered by Thermal Science,Inc. Eight of Ten Thermo-Lag Fire Barriers Installed by Pr Sussman Co Being Replaced1994-08-15015 August 1994 Part 21 Rept Re Improper Installation of Thermo-Lag Fire Barrier Matl Furnished & Delivered by Thermal Science,Inc. Eight of Ten Thermo-Lag Fire Barriers Installed by Pr Sussman Co Being Replaced ML20070H1471994-07-15015 July 1994 Part 21 Rept Re Problems W/Thermolag Fire Barriers.Initially Reported on 940715.Replaced Thermolag Fire Barriers ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20058G5981993-11-17017 November 1993 Part 21 Rept Re Westronics Recorders,Model 2100C.Signal Input Transition Printed Circuit Board Assembly Redesigned to Improve Recorder Immunity to Electromagnetic Interference.List of Affected Recorders & Locations Encl ML20057G1511993-10-0707 October 1993 Part 21 Rept Re Westronics Model 2100C Series Recorders. Informs That Over Several Tests,Observed That Recorder Would Reset During Peak Acceleration & Door Being Forced Off Recorder.Small Retaining Clips Added to Bottom of Door ML20044G5311993-05-26026 May 1993 Suppl to 921207 Part 21 Rept Re Declutch Sys Anomaly in Certain Types of Valve Actuators Supplied by Limitorque Corp.Limitorque Designed New Declutch Lever Which Will Be Available in First Quarter 1993 ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20126D7211992-12-16016 December 1992 Potential Part 21 Rept Re Actual Performance of Rosemount Supplied Bailey Bq Differential Pressure Transmitters Differing from Rosemount Original Spec.Bailey Controls Encl.Evaluation Not Yet Performed ML20102B2071992-06-24024 June 1992 Part 21 Rept Re Cracking of Stellite 21 Hardfacing on Guide Nose of Poppets Supplied as Part of MSIV Leakage Improvement Mod.Initially Reported by Clei on 920522. Recommends That Liquid Penetrant Exam Be Performed 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 ML20059M1751990-09-24024 September 1990 Supplemental Part 21 Rept 1 Re Defect in Coltec Industries, Inc Connecting Rod Assemblies Nuts/Bolts on Model 38TD8-1/8 Emergency Generators.Initially Reported on 851120.Nuts/bolts for Assemblies at Stated Plants Inspected & Replaced ML17348A1621990-03-27027 March 1990 Part 21 Rept Re Matls W/Programmatic Defects Supplied by Dubose Steel,Inc.Customers,Purchase Order,Items & Affected Heat Numbers Listed ML20012A9011990-02-27027 February 1990 Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp ML20011F5971990-02-22022 February 1990 Part 21 Rept Re Solder Connections in Abb 27/59 Relays Deteriorated Due to Thermal Stress,Causing Bonding of Printed Wiring Pattern to Glass Epoxy Circuit Board.Interim Circuit Board W/Larger Pads & Higher Wattage Will Be Used ML20011F1941990-02-22022 February 1990 Part 21 Rept Re Abb 27/59 Relay Catalog Series 211L.Solder Connections to Printed Wiring Runs on Bottom of Circuit Board Deteriorated Due to Thermal Stress.No Actual Failure Occurred & Relays to Be Changed at Next Outage ML18153C1011990-02-0202 February 1990 Part 21 Rept Re Two of Three Pc Cards in GE Type SLV11A1 Over/Undervoltage Relays Failing to Produce Output.Short Between Leads Would Result in Damage to Component 1C5. Sketch of Threshold Detection Board Encl ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced NRC-89-0267, Deficiency Rept Re Item 143 on as-built Deviations.Qa Audit Conducted on Category C Deviations in Sept 1989.Remaining Category C Deviations Resolved During Refueling Outage1989-11-30030 November 1989 Deficiency Rept Re Item 143 on as-built Deviations.Qa Audit Conducted on Category C Deviations in Sept 1989.Remaining Category C Deviations Resolved During Refueling Outage ML19325E0861989-10-16016 October 1989 Followup Part 21 Rept Re Class 1E Battery Chargers W/ Transformers Running at Temps Exceeding Those Used in Qualification Rept When Operating at or Near Full Load Rating of Equipment.Listed Corrective Actions Underway ML19351A2941989-10-0909 October 1989 Part 21 Rept Re Potential of Ambient Compensated Molded Case Circuit Breakers to Deviate from Published Info. Instantaneous Trip Check Will Be Instituted on All Class 1E Thermal/Magnetic Ambient Breakers Prior to Shipment ML19325C9521989-09-29029 September 1989 Part 21 Rept Re Potential Common Failure of SMB-000 & SMB-00 Cam Type Torque Switches Supplied Prior to 1981 & 1976. Vendor Recommends That Switch W/Fiber Spacer Be Replaced ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating ML20246P7111989-07-17017 July 1989 Part 21 Rept Re Quench Cracks in Bar of A-SA-193 Grade B7 Component.Quench Cracks Found in One Bar of Matl.Listed Purchasers Informed of Potential Defect.Next Rept Will Be Submitted When Addl Info Becomes Available ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML20245B6651989-06-15015 June 1989 Part 21 Rept 150 Re Potential Defect in Component of Dsr Standby Diesel Generator.Cause of Failure Determined to Be Combination of Insufficient Lubrication to Bushings.Listed Course of Action Recommended at Next Scheduled Engine Maint ML20246K7401989-04-26026 April 1989 Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves ML20244D8161989-04-13013 April 1989 Part 21 Rept Re Failure of Rosemount Transmitters.All Failed Transmitters Replaced,Inservice Test Procedure Prepared & Monthly Test of All 12 Transmitters in RCS Throughout Cycle 2 Operation Will Be Performed.Review Continuing ML20247P7991989-04-0404 April 1989 Part 21 Rept Re Atmospheric Dump Valves.Cause of Failure Speculative But Result of Piston Ring That Failed to Seal. Resolution to Problem Requires Increasing Pilot Valve Capacity & Reworking of Plug to Enlarge Pilot Flow Area ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys ML20205F3211988-10-10010 October 1988 Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07 ML20207P0451988-10-0505 October 1988 Part 21 Rept 146 Re Defect in Left Intercooler Inlet Adapter on Standby Diesel Engine Generator.Recommends Utils Inspect Left Intake Manifold Drain as Part of Operating Plan.Addl Info Expected by 881015 ML20207P0151988-10-0404 October 1988 Part 21 Rept Re Fuel Nozzle Tips in Standby Diesel Generator KSV-20-T W/Cracks Permitting Diesel Fuel to Be Sprayed Into Cylinders.Heavy Vapors Observed Emitting from Breathers on Some Cylinder Heads ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking ML20154J4101988-05-12012 May 1988 Addendum 1 to Supplemental Part 21 Rept 145 Re Potential Problem w/F-573-156 Pressure Sensor/Lube Oil Trip.Initially Reported on 880429.Addl 1-1/8-inch Diameter W/Deep Counterbone in Pressure Head Added to Activate Valve ML18093A8281988-05-0606 May 1988 Part 21 & Deficiency Rept Re Asea Brown Boveri,Power Distribution,Inc Low Voltage K-Line Circuit Breakers. Efforts Underway to Define Quantity & Type of Component Parts That May Need to Be Replaced ML20153G0111988-05-0606 May 1988 Part 21 Rept Re Potential Defect in Bussman Buss KTK-R Fuse Blocks W/Part Numbers 2078,2079 & 2080.Purchasing Records Reviewed to Identify If Any Parts Were Actually Used or Shipped to Customers.Results Listed ML20153B6191988-04-29029 April 1988 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generators Supplied to Utils.Recommends Return of Subj Components in Onsite Warehouse Storage & Suggests Surveillance of Devices Already Installed ML20153B2811988-02-22022 February 1988 Part 21 Rept Re Defect in Operation of Gas Monitors Using Fixed Filters.Initially Reported on 880212.Caused by Error in Software for Monitors.Vendor Testing Mod to Software & in Interim Recommends Changing Filters Every 48 H ML20196D6281988-02-10010 February 1988 Part 21 Rept Re Potential Defect in Certain Model RTF-480/120-30 Ac Line Regulating Transformers Involving Nuisance Tripping of 100 Ampere Ac Input Circuit Breaker When Initializing Unit.Breaker Should Be Replaced ML20196B8481988-01-29029 January 1988 Part 21 Deficiency Rept Re HPCI Suction Pipe Overpressure Transient.Initially Reported on 880129.Caused by Installation of Lift/Plug Check Valve.Potential Water Hammer Condition Corrected by Replacing Valve ML20149J0261987-12-21021 December 1987 Part 21 Rept Re Installation of Relay Part B8002DN in Foxboro 62H Controllers in Facilities.Subj Relay Must Be Replaced by Relay Part N0196ZN.Relay B8002DN Not Used in Any Other Plants 1998-09-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N4381999-10-25025 October 1999 Safety Evaluation Supporting Amend 17 to License DPR-9 ML20217P3551999-10-22022 October 1999 LER 99-S01-00:on 990922,loaded 9mm Handgun Was Discovered on Truck Cargo Area of Vehicle Inside Protected Area.Caused by Inadequate Vehicle Search.Guidance in Procedures & Security Training to Address Multiple Vehicle Searches Was Provided NRC-99-0095, Monthly Operating Rept for Sept 1999 for Fermi 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fermi 2.With NRC-99-0067, Monthly Operating Rept for Aug 1999 for Fermi 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fermi 2.With NRC-99-0065, Monthly Operating Rept for July 1999 for Fermi 2.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fermi 2.With NRC-99-0088, Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with1999-06-30030 June 1999 Detroit Edison Co Enrico Fermi Atomic Power Plant,Unit 1 Annual Rept for Period 980701-990630. with NRC-99-0064, Monthly Operating Rept for June 1999 for Fermi 2.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fermi 2.With NRC-99-0062, Monthly Operating Rept for May 1999 for Fermi 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fermi 2.With ML20206J9301999-05-10010 May 1999 SER Concluding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Powered-Operated Gate Valves ML20206G5081999-05-0505 May 1999 Safety Evaluation Approving Request for Relief PR-8,Rev 2 on Basis That Licensee Committed to Meet All Related Requirements of ASME OM-6 Std & PR-12 on Basis That Proposed Alternative Will Provide Acceptable Level of Safety NRC-99-0022, Monthly Operating Rept for Apr 1999 for Fermi 2.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fermi 2.With ML20205Q7141999-04-15015 April 1999 Safety Evaluation Supporting Amend 16 to License DPR-9 ML20205P9721999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Fermi 2 ML20204E0371999-03-17017 March 1999 Safety Evaluation Accepting Licensee Request for NRC Approval of Alternative Rv Weld Exam,Per Provisions of 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(ii)(A)(5) for Plant,Unit 2 for 40-month Period ML20204D0361999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fermi 2 ML20198S3341999-01-0606 January 1999 Safety Evaluation Supporting Amend 15 to License DPR-9 ML20206P1501999-01-0505 January 1999 LER 98-S03-00:on 981207,security Officer Discovered Uncontrolled Safeguards Info Drawing.Caused by Failure to Follow Established Procedures & Policies.Drawing Was Controlled by Site Security.With ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20205Q9621998-12-31031 December 1998 Revised Monthly Operating Rept for Dec 1998 for Fermi 2 ML20207B7491998-12-31031 December 1998 1998 Annual Operating Rept for Fermi 2 NRC-99-0021, 1998 Annual Financial Rept for Detroit Edison Co. with1998-12-31031 December 1998 1998 Annual Financial Rept for Detroit Edison Co. with NRC-99-0005, Monthly Operating Rept for Dec 1998 for Fermi 2.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Fermi 2.With ML20198E6381998-12-17017 December 1998 LER 98-S02-00:on 981130,security Access Was Revoked Due to Falsification of Criminal Record.Individual Was Escorted from Protected Area & Unescorted Access Was Restricted. with NRC-98-0153, Monthly Operating Rept for Nov 1998 for Fermi 2.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fermi 2.With NRC-98-0160, Monthly Operating Rept for Oct 1998 for Fermi 2.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fermi 2.With ML20154R2331998-10-21021 October 1998 Safety Evaluation Supporting Amend 13 to License DPR-9 ML20154L1031998-10-14014 October 1998 Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode ML20153G4601998-09-30030 September 1998 USI A-46 Seismic Evaluation Rept, Vols 1-2 ML20154H8161998-09-30030 September 1998 Rev 0 to COLR Cycle 7 for Fermi 2 NRC-98-0139, Monthly Operating Rept for Sept 1998 for Fermi,Unit 2.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Fermi,Unit 2.With ML20153B8811998-09-18018 September 1998 Safety Evaluation Accepting Request for Relief from Certain Requirements of ASME Boiler & Pressure Vessel Code,Section Xi,For Plant,Unit 2 ML20151X0651998-09-11011 September 1998 Safety Evaluation Re Inservice Testing Program Relief Request VR-63 for Plant ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML15261A4681998-09-0404 September 1998 Safety Evaluation Supporting Amends 232,232 & 231 to Licenses DPR-38,DPR-47 & DPR-55,respectively ML20153B7921998-08-31031 August 1998 Rev 0 to Fermi 1 Sar NRC-98-0111, Monthly Operating Rept for Aug 1998 for Fermi 2.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Fermi 2.With ML20237E1171998-08-25025 August 1998 Safety Evaluation Accepting Licensee Relief Requests for First 10-yr Interval Inservice Insp Nondestructive Exam Program ML20236X8611998-08-0505 August 1998 SER Related to Revised Feedwater Nozzle Analysis to Facility Operating License NPF-43,Enrico Fermi Nuclear Power Plant, Unit 2 NRC-98-0109, Monthly Operating Rept for July 1998 for Fermi 21998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Fermi 2 ML20236K3261998-07-0101 July 1998 SER Accepting Licensee Response Related to Revised Feedwater Nozzle Analysis to License NPF-43 for Enrico Fermi Nuclear Power Plant,Unit 2 NRC-98-0127, Annual Rept for Period 970701-9806301998-06-30030 June 1998 Annual Rept for Period 970701-980630 NRC-98-0097, Monthly Operating Rept for June 1998 for Fermi,Unit 21998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Fermi,Unit 2 ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity NRC-98-0079, Monthly Operating Rept for May 1998 for Fermi 21998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Fermi 2 NRC-98-0076, Monthly Operating Rept for Apr 1998 for Fermi 21998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Fermi 2 NRC-98-0072, Monthly Operating Rept for Mar 1998 for Fermi 21998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Fermi 2 NRC-98-0050, Monthly Operating Rept for Feb 1998 for Fermi 21998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Fermi 2 NRC-98-0019, Monthly Operating Rept for Jan 1998 for Fermi 21998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Fermi 2 ML20198L4241998-01-0808 January 1998 Safety Evaluation Accepting Proposed Rev 2 to Relief Request VR-51 Under Fermi 2 Pump & Valve Inservice Testing Program Per 10CFR50.55a(f)(6)(i) for First 10-yr Interval ML20247L9041997-12-31031 December 1997 1997 Annual Rept for Duke Energy Corporation & Saluda River Electric Cooperative,Inc,Financial Statements as of Dec 1997 & 1996 Together W/Auditors Rept 1999-09-30
[Table view] |
Text
~
1 -
Brown Boveri Electric, Inc. -
i Manufacturer of l-T-E Electrical Power Equipment
~
-' A 5 3 6 8
===-
145475 :
November 29, 1983 .
. I
~
t Mr. Robert L. Baer, Chief
' Engineering and Generic Comenmfcations Branch }
j ;
Division of Emergency Preparedness >
j and Engineering Response - j Office of Inspection and Enforcement i
United States Nuclear Regulatory !
Commission -
Washington, D. C. 20555
Subject:
Cracked and Broken Piston Bods in Brown Boveri Electric. f (yormerly I-T-E) Type SEK Circuit Breakers -
/!
Dear Mr. Baer:
This letter is in iresponse to your' letter of November 23, 1983 which enclosed !
a Draft NRC 1E Information Notice pertaining to the subject. l
~
\
- Since the submitt'a l 'of the BBE Interim Report on this subject dated October. l 3,1983, some of the broken puffer piston rods were subjected to a micro- i structural analysis wherein the samples were microtomed in the area of the j l failure to enhance the crystaline structure of them for microscopic analysis. ;
l This analysis revealed that there were some material voids in the broken area !
l which suggested that there were venting problems with the tool used to sold :
the puffer piston rod. These voids could also be caused by trapped moisture !
during the molding process which would weaken the part. Another broken sample j revealed a nonhomogeneity of the crystaline structure which would cause local '
areas of high stress which could result in breakage. The most likely cause? !
, of'this problem is a non-uniform tool temperature, which was caused by ope 9-/
' ating the tool while it was in the state of initial heat up for molding clie j
part. The few random problems that have been experienced to date for the l most part could be attributed to problems in processing the material by the -
vendor. The fact that failures have been experienced in very few and random areas reinforces this hypothesis. .
3 i
.. i The failed parts have been limited to those made with the material identified - l as Zytel.101 (Nylon 6/6). Since 1980, the parts have been manufactured with a toughened and reinforced material identified as Nylafil. No problems have been reported on the parts manufactured with the Nylafil material.
Recently some puffer piston assemblies were recovered from the Oconee Nuclear Station at Duke Power. Examination of these parts from circuit breakers manufactured in 1969 revealed no defects whatsoever. It appears that the
- l 8405110160 840330 PDR ADOCK 05000329 S PDR Suneshamar Systones o6seien i Sedag Heine, PA 19477 *(2151 828 7400 ;
l
. . . _ . . . . . _ _ . - . . . . . . . . . . . _ . . . . _ . .. . ....- .t Brown Boveri Electric, Inc.
l h-
- Mr. Bibert L. Beer -
i 4 5@aS c 475 November 29, 1983 .
l Page 2 l
l l
t relatively few processing problems that were experienced are random in nature.' !
It has also been determined that although some parts will crack, they will not necessarily fail. l Some cracked parts returned from Detroit Edison (Farmi 2) I were of cracks. subjected to an endurance test of 1,200 operations without any propagation (
5 !
t The actual number of failed puffer piston push rods (broken) that have been I reported is less than twenty (20). Although others have been reported as being !
cracked, and the parts should be replaced, they are not considered failures. !
The total number of puffer piston assemblies installed in 5HK circuit breakers since 1968 is over 75,000. l' Based on the test result's and other information available at this time, the BBE ,
recommendation is to inspect for cracked or broken puffer piston rods at normal !
maintenance intervals and to replace the puffer piston assembly if this condi-tion is found. .
lr r
In the Draft II Information Notice, the second paragraph under " Description of !
Circumstances" is a correct statement in that spara puffer piston assemblies '
were found to be defective in receiving inspection at the Fermi plant and were returned to BBE. The parts were determined to be defective becausk of shipping {
l damage and ,other concerns which were not related to cracking or breakage of the l puffer piston push rods. As prescated, this infers that BBE is having similar l problems with the parts currently being.used and this is not the case. j i
Enclosed is a list of SEK circuit breakers that are being used in Class 1E i applications at nuclear power plants. The circuit breakers manufactured after 1980 have puffer piston push rods made with the Nylafil material and there is [
l no. reason to suspect that these will be subject to cracking or breakage. In- ;
spection of circuit breakers with manufacturing dates of 1981 or later for '
cracking or breakage should not be necessary.
~ m
.Z&~4 E. W. IBOADS :
Manager Quality Assurance r
( EWE /ja I i
r Enclosure
[
cc: D. D. Duvall
\
C. E. re k.1 '
_ W. E. Laubach t W. Laudan - NRC ,
L. E. Schmidt t A. E. Stringfellow
. (
~
- .r 145475 !
SSINS No.: 6835 IN 83.84 l'45368 UNITED STATES l NUCLEAR REGULATORY COMMISSION l OFFICE OF INSPECTION AND ENFORCEMENT !
WASHINGTON, D.C. 20555 ,
f/ . December 30, 1983 (
t i !
IE INFORMATION NOTICE NO. 83-84:'
CRACKED AND BROKEN PISTON RODS IN BROWN ~l B0VERY ELECTRIC TYPE SHK BREAKERS '
l Addressees: l l
All holders of a nuclear power reactor operating license (OL) or construction !
permit (CP).
Purpose:
.l t
This information notice is provided.as n'otification of a potentially significant [
problem pertaining to Brown Bovery Electric (BBE) type SHK 250/350, 1200/2000 t ampere circuit breakers. Addressees'are expected to review the information for !
applicability to their facilities. No specific action or response i.s required I at this. time. ,
Description of Circumstances: ;
i On March 21, 1983, Detroit Edison notified the NRC under the provisions of 10 i CFR 50.55(e) of a potential problem with BBE 5HK 4160 volt breaker puffer i piston rods at the Fermi 2 nuclear plant. The puffer piston connecting rods I
developed cracks and one shaft failed. The inanufacturer's part number is 193642B. The cracking and failure occurred at the hole in the shaft where the
-linkage is connected by a pin. These breakers were manufactured in 1973. A i total of five breakers were affected at the Fermi 2 site. l l
. ~ On September 12, 1983, Detroit Edison advised an NRC inspector that during a [
receiving inspection at the Fermi plant, spare puffer piston connecting rods were found to be defective. They were all returned to the vendor. BBE informed j l the NRC on November 29, 1983 that the damage tS these puffer piston connecting !
l- rods were a result of shipping problems and were not related to the manufacturing ;
!; process. .
l i
On October 12, 1983, BBE provided the NRC with an' Interim Report pertaining to ;
.the SHK breaker puffer piston. connecting rod problem. The report indicated that at a Southern California Edison (SCE) non-nuclear plant eight puffer !
l piston connecting rods were found to be broken. -
i l Puffer pistons in the BBE SHK breakers perform two functions. For low current -
l l interruptions the puffer is needed to assist the magnetic forces to move the i i
h
==
IN 83-84 145368 I45475 $*6f [.
l'8 arc into the interrupting chamber. The arc may not be extinguished if the puffer piston fatis. ;
The other function performed by the puffer piston is to '
provide a pneumatic cushion which reduces the shock forces imposed on the mechanism and current carrying parts upon opening. A failure of the puffer i piston could reduce the number of operations before maintenance on the breaker would be necessary. !
BBE indicated that no breaker failed because of a broken puffer piston rod, however, the breaker's capability to interrupt at low current may be impaired.
BBE subjected broken piston rods to failure analysis including microscopic l l
analysis of the failed area and found that failed parts were limited to those !
made with the material identified as Zytel 101 (Nylon 6/6). Since 1980, the l
parts have been manufactured with a toughened and reinforced material called "Nylatil." No problems have been reported on Nylatil material parts.
l Based on the test results and presently available information, BBE recommends inspecting for cracked or broken puffer.pf ston rods at normal maintenance l intervals and replacing the puffer piston assembly if this condition is found.
It should be noted that the nozzle of the puffer piston must be removed to inspect the rod properly.
- l Attached is a list provided by BBE of SHK circuit breakers that they supplied i for use in Class 1E applications at nuclear power plants, and which may be '
affected. Since breakers can also be obtained from intermediate sources, the list may not be complete. It is suggested that licensees evaluate their cquipment lists to determine if BBE 5HK breakers are used in safety-related cpplications in their plant. Inspection of circuit breakers with manufacturing ,
dates of 1981 or later for cracking or breakage of puffer piston rods should not be necessary.
If.you have any questions regarding this' matter, please contact the Regional Admittistrator of the appropriate NRC Regional Office, or this Office.
//
01~Ak b award L. Jordan irect r DivisionofEmer[gencyPreparedness I and Engineering Response .
Office of Inspection and Enforcement Technical
Contact:
W. Laudan, IE !;
(301) 492-9759 6 Attachments: '
- 1. List of SHK Breake'r Customers
- 2. List of Recently Issued IE Information Notices i
i
, . i
. s -
! l45368 Attachment 1 l 14547,a in 83-84 December 30, 1983 Page 1 of 3 I l
88E TYPE 5HK BREAKER CUSTOMERS l
- 9 CUSTOMER 88E SALES ORDER DATE OF MANUFACTURE !
i I
. CEI' -
t Perry 1&2 51958 - 8/78, 9/78 l 10/78 ,
t CFE '
- Laguna Verde 53462 11/74 - 1/80 i t !
l CP&L -
l Brunswick 1 .54792 10/81 l
Brunswick 2 47219 11/71 - 8/72 l 49839 3/74 - 3/79 l Cincinnati G&E Zimmer 51828 6/77 - 11/77 [
Commonwealth Edison LaSalle County 1&2 50080 10/75 - 12/75' !
526.12 4/78, 5/78 !
l Zion 1&2 45122 5/70 - 2/71 !
t .
Consumers Power i l Midland 1&2 50382 4/75 - 9/75 l 9/75'- 6/76
' l 8/75 - 9/75 !
Detroit Edison l j, Fermi 2
~
47196 12/73 - 9/74 l l-Duke , ,
. Catawba 1 & 2 50465' 4/78 - 4/79 ;
McGuire 1 & 2 48560 9/72 - 11/74 ;
Oconee 3 44349 8/69 - 8/71 - I Duquesne Light Co. !
Beaver Valley 1&2 46690 8/71 - 8/78 l Florida Power Corp .
Crystal River 3 46256 11/70 f Georgia Power Company -
Vogtle 1 51903 9/81 - 3/82 l Vogtle 2 51904 , 7/81 - 2/83 l
I Attachment 1 IN 83-84 145475 December 30. 1983 Page 2 of 3 145368 BBE TYPE SHK BREAKER CUSTOMERS CUSTOMER BBE SALES ORDER DATE OF MANUFACTURE l
l Gulf States Utilities River Bend 1&2 51126 11/80 - 3/83 )
51128 10/80 - 4/82 Indiana Michigan Electric Co.
Cook 1 44322 8/71 - 3/72 Cook 2 53372 5/79 Mississippi Power & Light Grand Gulf 1&2 50469 1/76 - 5/77 l Northern States Power
! Prairie Island 1&2 44477 2/70 - 1C/71 l
! PE
! Limerick 1&2 47651 3/77 - 5/77
. PSE&G Hope Creek 1&2 52260 10/79 - 1/80 PSI Marole Hill 2 52661 11/80 - 8/82 PSNH Seabrook 1&2 50750 1/77 - 8/77 Portland General Electric Trojan 47354 2/73
,. Sacramento Municipal Utility l . District l Rancho Seco 1 ,
45966 5/71 South Texas Project 1 52769 10/78- 's Project 2 52914 5/79 - 12/79 i Southern California Edison <
San Onofre 2&3 50395 ,
3/76, 4/76 Taiwan Kuo Sheng/ Unit 1&2 50735 5/77 - 12/76, 11/75 - 12/75, 3/76 l
I
. l I45473 Attachment r45368 IN 83-84 oecember 30, 1983 -
LIST OF RECENTLY ISSUED i IE INFORMATION NOTICES Information Date of i
) Notice No. Subject Issue Issued to i I
83-83 Use of Portable' Radio 12/19/83 All power reactor .
, Transmitters Inside Nuclear facilities holding :
Power Plants an OL or CP -!
(
83-82 Failure of Safety / Relief 12/16/83 All power reactor !
Valves to Open at BWR - facilities holding [
Final Report an OL or CP '
83-81 Entry Into High Radiation 12/7/83 All licensees autho- I l Areas From Areas Which Are rized to use portable !
l Not Under Direct Surveillance radiography devices t
+
in radiography (
j programs i l
t i 83-80 Use of Specialized " Stiff" 11/23/83 All power reactor Pipe Clamps facilities holding l
an OL or CP; NSSS 1 and AEs !
83-79 Apparently Improper Use'of 11/23/83 All power reactor Components in Safety-Related facilities holding '
Systems an OL or CP 83-78 Apparent Improper Modifica- 11/17/83 All power reactor i tion of a Component Affect- facilities holding l
. ing Plant Safety an OL or CP {
83-77 Air / Gas Entrainme*nt Events 11/14/83 All power reactor Resulting in System Failures facilities holding an OL or CP i
83-76 Reactor Trip Breaker Malfunc- 11/2/83 All power reactor tions (Undervoltage Trip facilities holding Devices on GE Type AK-2-25) an OL or CP 83-75 Improper Control , Rod Mani- 11/03/83 All power reactor ,
pulation facilities holding ;
an OL or CP .l, I
s !
i OL = Operating License l CP = Construction Permit i
?
?
..~, '
I45475 Attachment 1 I45368 in 83-84 December'30, 1983 Page 3 of 3 BBE TYPE SHK BREAKER CUSTOMERS
( CUSTOMER BBESALESdRDER DATE OF MANUFACTURE VEPCO North Anna 2 48709 9/76, 10/76 WPPSS WNP 1&2 51659 3/78 - 1/79
. e
. \
I. .
9 f
1 i
, _ _ . _ _ _ _ - . _ . _ _ _ _ _ . . . . - . _ _ _ . . _ _ _ . . _ . . ~ _ _ , _ _ _ _ . _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ . _ . _ _ _
T 4,
lll l{ p 12/1/83 l .
Silk BREAKERS
- Customer BBE Sales Order Date of Mfar.
CP&L/ Brunswick 2
i Brunswick 1 54792 10/81 .n- t
, Brunswick 2 . 49839 3/74 - 3/79 ui i co I
Cincinnati G & E/Zimmer 51828 6/77 - 11/77 m co I CEI/ Perry 1 & 2 51958 8/78 [
9/78 __ ;
10/78 , !
C.rt s l
Commonwealth Edison / Zion 1 & 2 45122 5/70 - 2/71 .e- -
i
/LaSalle County 1 & 2 50080 10/75 - 12/75 .N !
! /LaSalle County 1 & 2 52612 4/78, 5/78 ui ,
! i l
i Consumers Power / Midland 1 & 2 50382 4/75 - 9/75 9/75 5/76 li j 8/75 - 9/75 Detroit' Edison / Fermi 2 47196 12/73 - 9/74 Duke /Oconee 3 44349 8/69 - 8/71 !
/McCuAre 1 & 2 48560 9/72 - 11/74 i i
/ Catawba.1 & 2 50465 5 4/78 - 4/79 I i Duquesne Light Co./ Beaver Valley 1 & 2 l 46690 8/71 - 8/7b l
l FloridaPowerCorpICrystalRiver3 46256 11/70 Georgia Power company /Vogtle 1 51903 9/81 - 3/82
{
/Vogtle 2 . 51904 -
7/81 - 2/83 ,
i Gulf States Utilities / River Bend 1 & 2 51126 11/80 - 3/83 i
} 51128 10/80 - 4/82 i l I j Indiana Hichigan Electric
- Co./ Cook 1 44322 8/71 - 3/72 4
/ Cook 2 53372 5/79 .
1 i I
-l l l l 12/1/83 { l' .
.3
~
5HK Brc:ksrc - .
- l. . Page 2 [.$. !
i Customer BBE Sales Order, Date of Mfar. ,
- Hississippi Power & Light / Grand Gulf 1 & 2 50469 1/76 - 5/77 ,
Northern States Power / Prairie Island 1 & 2 44477 2/70 - 10/71 l P.E./ Limerick 1 & 2 47651 3/77 - 5/77 E*
U1 Portland General Electric / Trojan 4735'4 2/73 to !
m 52661 11/80 - 8/82 CD
- PSI / Marble Hill 2 PSNH/Seabrook 1 & 2 50750 1/77 - 8/77 I
) PSE&C/ Hope Creek 1 & 2 52260 10/79 - 1/80 .
l Sacramento Municipal Utility District / !
I Rancho Seco 1 45966 5/71 us ,
Southern California Edison / .a-l i San Onofre 2 & 3 50395 3/76, 4/76 N ,
u, t South Texas / Project 1 52769 10/78 ,
! / Project 2 52914 5/79 - 12/79 1 .
-' 9/76, 10/76 VEP Company / North Anna 2 48709 l
i WPPSS/WNP 1 & 4 51659 3/78 - 1/79 i Taiwan /Kuo Sheng/ Unit 1 & 2 50735 5/77 - 12/76 &.
11/75 - 12/75 &
1 3/76 i * -
CFE/ Laguna Verde 53462 11/74 - 1/80 i
I .
- - - . . . . . -_