|
---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20140G4481997-05-0101 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 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 ML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl 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 ML20077C2801994-11-21021 November 1994 Deficiency Rept Re Defective Yokes P/N 342849 Mfg by Copes- Vulcan,Inc.Affected Utilities Notified & Defective Yokes Will Be replaced.Copes-Vulcan Also re-inspected All Yokes in Inventory & Verified Yokes Acceptability 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 ML20056D7071993-07-15015 July 1993 Part 21 Rept Re Reportable defect-75 PSIG Relief Check Valve 1 Npt,Emd 9521844,Kepner 416C-1-75 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 ML20044G5011993-05-26026 May 1993 Part 21 Rept Re Buffer Amplifier Modules Mfg by Bailey Controls Co Containing Suspect Negative Ref Power Supply Having Safety Implications.Caused by Design Error in Circuitry.Modules Would Not Result in Miscalibration 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 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 ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed 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 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 ML20094F5181991-12-23023 December 1991 Part 21 Rept Re Matl Used in Johnson Kokogawa Corp Wear Plate Blades Not Displaying Sufficient Spring Capabilities to Adequately Hold Rom Chip Pins When Rom Mounted in Socket.Util Advised That Improved Sockets Now Available 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 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 ML20153F9661988-04-19019 April 1988 Part 21 Rept Withdrawing 870929 Notification Re Potential Problem W/Saturable Core Transformer 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 ML20195J7421988-01-25025 January 1988 Final Part 21 Deficiency Rept Re Potential Problem W/ Silicone rubber-insulated Cables.Based on Encl Three Test Repts,Tva Concludes That Mfg,Shipping,Receipt & Installation Practices Did Not Reduce Cable Insulation Thickness 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 ML20235U0271987-10-0707 October 1987 Part 21 Rept Re Westinghouse Plant Steam Generator Tubes Susceptible to High Cycle Fatigue Failure Similar to 870715 Event at North Anna Unit 1.Caused by Mean Stress in Tube & Superimposed Alternating Stress ML20235R1211987-09-29029 September 1987 Part 21 Rept Re Saturable Core Transformer Installed in Emergency Diesel Generator Set.Problem Developed in Svc. Teardown Insp Performed by Util.Results Noted Inadequate Insulation.Addl Info Will Be Provided ML20234F5261987-09-16016 September 1987 Followup Part 21 Rept Re Defective MIS-5 Actuating Fuses. Initially Reported on 870620.All Defective Fuses Will Be Replaced W/Fuses from Subsequent Lots Before Mode 4 ML20235H0041987-09-10010 September 1987 Part 21 Rept Re Nonconformance of American Insulated Wire Co & Rockbestos Co Silicone rubber-insulated Single Conductor Cables.Initially Reported on 870904.Cause Not Found. Evaluation Continuing ML20238E7721987-09-10010 September 1987 Part 21 Rept Re Special high-potential Withstand Tests on Number of Installed 14 Silicone rubber-insulated Single Conductor Cables.Initially Reported on 870904.Evaluation of Silicone Rubber Cable Continuing 1997-05-01
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 ML20199F8531998-01-13013 January 1998 ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation 1999-09-30
[Table view] |
Text
_
t./
.m.
Brown Boven. BBC, eao- --
Switchgear Products Group esc Brown Boveri,Inc.
Spring House, PA 19477 Phone:(215)628-7400 July 9, 1985 Mr. Larry Parker Mail Stop E/W-E Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
BBC Brown Boveri HK Control Device
Dear Mr. Parker:
'Per our telephone conversation of July 9, 1985, enclosed is a copy of an inter-l- nal BBC Brown Boveri letter on the HK control device incident reported by TVA l in the July 3, 1985 Morning Report.
l This letter will be used by our District Office in Knoxville to write 'a report to TVA on the problem they have experienced with the HK control device.
It appears that this is the same problem that was identified in the BBC. Brown Boveri Report to the NRC dated 3/22/83.
We will keep you advised of any chringes in this situation.
I b E. W. RHOADS Manager Quality Assurance EWR/jm
(- Enclosure cc: F. D' Antonio A. Kaiser L. Schmidt G. Taylor F. Wuzzardo 8507150481 850709 PDR ADOCK 05000327 S PDR-g6 I (
~
Erown Boven.
BBC a= ==
Inter-Office Correspondence To C. E. Wood - 5211 From E. W. Rhoads DepuDiv. Quality Assur.
Date 7/1/85 Location Spring House Subject BELLEFONTE NUCLEAR STATION Copies To F . D' Antonio A.O. 33-51014 & 33-54753 L. Schmidt G. Taylor F. Wuzzardo On February 23, 1983, the W. H. Zimmer Nuclear Power Station filed an l interim 10CFR50.55(e) report with Region III of the U. S. Nuclear Reg- l ulatory Commission identifying a potentially reportable deficiency of l a broken limit switch carrier on the HK control device use'd on some l BBC Brown Boveri HK circuit breakers. This particular control device I is used on circuit breaker types 7.5kV through 15kV, 500 through 750 MVA; 5HK350, 3000; and HKV circuit breakers.
On March 33, 1983, BBC Brown Boveri filed a 10CFR Part 21 report with the Office of Inspection and Enforcement of the U. S. Nuclear Regulatory Commission in Washington, D.C. to supplement the information in the re-port filed by CG&E and to clarify the extent of this potential problem at other nuclear power plants.
During the telephone conversation between BBC Brown Boveri and TVA on June 13, 1985, TVA was advised that the BBC Brown Boveri letter of March 22, 1983 to the NRC probably contained the information required to correct the condition they were experiencing with the control device on the 7.5 and 15HK circuit breakers at the Bellefonte Nuclear Station.
At the time of this conversation, TVA noted that some of the control de-vices utilized a spring with a ball and others utilized a spring with a cylinder to retain the contacts in the limit switch carrier of the con-trol device.
A check of production records shows that the ball and spring were used to retain the contacts within the contact carrier until April 12, 1976, at which time an engineering change was made utilizing a cylinder within the spring to retain the contacts. Also, the cylinder was changed back to a ball on May 14,1984 on the 7.5 and 15HK circuit breakers. The ball and spring retention has always been used on the HK1000 MVA and K-Line circuit breakers.
For the HK circuit breakers at the Bellefonte Station, either method of contact retention is acceptable, however, if TVA prefers to use all cy-linders for the sake of uniformity, parts will be furnished by BBC Brown Boveri at no charge.
, 'Ihe inspection / adjusting procedure included in the BBC Brown Boveri 10CFR Part 21 report to the NRC dated March 22, 1983 should be followed by TVA during circuit breaker check-out or maintenance routines.
' 9 esows soveni 7/1/85 BBC Brown Boveri will supply parts if required,- to make adjustments per IB 8303 (included with report to NRC dated March 22, 1985). Please note IB 8303 was revised (Rev. I was issued June 11, 1985). A copy is attached as an enclosure to this letter.
Although the problem w' th the control device (191921-T6) experienced at Bellefonte on three circuit breakers appears to be different than the con-dition described in the BBC Brown Boveri 10CFR Part 21 report of 3/22/83 because of balls or cylinders used with the contact retention springs, the BBC Brown Boveri evaluation of this condition indicates that the primary cause of contact becoming loose is due to the shock created by the lever overtravel as described in I88303. The condition could be caused by lever stop not being short enough to limit the lever travel. Also, the shock to the control device is reduced when the circuit breaker is fully assembled and installed in the compartment. When the arc chutes are removed, as they sometimes are during checkout or maintenance, the shock to the control de-vice during circuit breaker operation can be higher than normally experienced.
As stated above, both balls and cylinders have been used in control devices over many years with satisfactory results. Both types have been tested successfully during several seismic tests.
It should be noted that the changes from the ball ta the cylinder and back to the ball on the 7.5 and 15HK circuit breakers was not related to the fact-ory specification changes of the settings for the limit switch adjustments of the control device. The change back to the ball occurred in May 1984 at which time no changes were made to the limit switch adjustments. A change to the factory specification for limit switch adjustments was made in Novem-ber 1984. These type changes are not normally the type that require customer notification.
The information included in IB8303 was determined to be a design improvement to reduce or eliminate breakage of the limit switch carrier. The change in-cluded in Revision 1 of IB8303 is considered a refinement to further improve the operation of the control device.
It is recommended that IB8303 Rev.1 dated June 11, 1985, be factored into the Bellefo.nte circuit breaker checkout procedures. Lever stops will be furnished by BBC Brown Boveri. Cylinders may be used in place of balls in the contact retention springs (note springs would change also). Both are acceptable for the 7.5 & 15HK control device design. Again, if desired, l
BBC Brown Boveri will provide these parts at no charge.
s.
ee. '
BBC BROWN BOVERi 7/1/85 The circuit breakers at Sequoyah plant are of an earlier configura-tion and therefore, IB8303 is not applicable.
The results of using 188303 at the Zimmer plant of CG&E have resolved their probleit as originally reported. To the best of our knowledge,,
no other problems have been reported. Please keep us informed of your progress in completing the checkout of these circuit breakers.
/}
v ledC E. W. RHOADS EWR/ms Enc.
2'-
R e tr . 1, 6-11-8S snow sonn
, f I
INSTRUCTIONS FOR INSPECTING, ADJUSTING AND/0R REPLACEMENT OF PARTS FOR OBTAINING LIMIT SWITCH ADJUSTMENTS ON BROWN B0 VERI 7.5KV THRU 15KV, 500 THRU 750 MVA; 5HK350, 3000; ALL HKV BREAKERS l
18-8303 l
t o
,, Brown Boveri Electric, Inc.
Martfactufef of I T E Electreal Power Equcment f
F
its-d303 Rev. 1, 6-11-8S INSTRUCTIONS FOR INSPECTING, ADJUSTING AND/0R REPLACEMENT OF PARTS FOR OBTAINING LIMIT SWITCH ADJUSTMENTS ON BROWN B0 VERI 7.5KV THRU 15KV, 500 THRU 750 MVA; SHK350, 3000; ALL HKV BREAKERS (MANUFACTURED BETWEEN MARCH 1974 AND JULY 1978 INCLUSIVE)
- 1. GENERAL 1.1 For general breaker instruction, refer to the appropriate Brown Boveri Instruction Bulletin.
1.2 The breaker must be removed from the switchboard.
1.3 Unless otherwise stated, the breaker is to remain open with closing springs discharged.
1.4 The reason for a gap at Dim. "A" is to insure the "LSa" contact is made.
The gap at Dim. "B" is to insure that the "LSb" contacts are made and to limit the overtravel of the lever so that the limit switch plastic carrier inside the control relay is not broken.
1.5 This Instruction Bulletin supersedes IB-7803.
- 2. INSPECTION AND ADJUSTMENT FOR DIM. "A" (See Fig.1) 2.1 Charge the closing springs electrically or manually.
2.2 Check Dim. "A" with feeler or pin gages.
2.3 If required, readjust the screw (4) to Dim. "A" after first loosening the jam nut (5) and then retightening the jam nut after the adjustment.
l 2.4 Close and open the breaker to discharge the closing springs.
- 3. INSPECTION AND ADJUSTMENT FOR DIM. "B"(See Fig's 1 and 2) 3.1 For this procedure, the breaker is to be open and the closing springs discharged.
3.2 Check Dim. "B" with feeler or pin gages. (See Fig. 2) 3.3 If Dim. "B" is not within dimensions, it is necessary to shim the lever stop(7) up or down as required. This is done by adding or removing shims (2) at the lever stop. (See Fig.1) Note that if all shims are removed and the Dim."B" still exceeds the max. allowed, the length of the lever stop should be checked.
The lever stops made after July 1978 are 217/32 long. Previous to this, the l
length was 2 25/32. If required, install the shorter lever stop (7).
l Ir Brown Boveri Electric,Inc.
Manufacturer of 6.T E Enoctreal Pbwer Equemoru
o 4
' Rev. 1, 6-11-85 BBC
- 4. NEW PART NUMBERS Qty. Per Breaker Notes
- 2. Shim 650451-A27 As req'd (3 est.)
- 7. Lever stop 193392-A 1 217/02 overall length.
Used in breakers built after July 1978.
l l
t I
1 i
lr Brown Boveri Electric, Inc.
! Manufacturer of I.T E Electreal Plower Equemern 9
-8g03 Q1 i
~
LE'lER
( R etr . ,11-85 ADJUST *NG SCREW &
CONTROL LOCCtUT PAN 2 ScagWS 5/;s_13 ;ND'LOCCIUTS
\
L WASH-] ATSHIMS@
@ SHIM AS REQ'O I -, -
. s N i
DIM. A
@ LEVER ASSY.
1/64-1/32 LIMIT '
SWITCH /
SPRING LEVER
@ LEVER STOP - /j-- MOUNTING I
BRACXET O
2 SCREWS AND L. WASHERS 1 TRU ARC RETAINER, OPPOSITE SIDE POSITION SHOWN WITH CLOSING SPRINGS CHARGED.
Fre. 1 Ws N DIM.
"B" N
1/64-1/16 I POSITION SHOWN WITH CLOSING SPRINGS DISCHARGED.
l Fla 2 r., Brown Boveri Bectric,Inc.
Manufacturer of I.T-E Electreal Pbwer Equement r