Final Deficiency Rept 84-01 Re Failure of Gould-Rundel four- Position Selector Switches.Initially Reported on 830824 & 840111.All Defective Switches Will Be ReplacedML20086N064 |
Person / Time |
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Site: |
Wolf Creek, Callaway, 05000000 |
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Issue date: |
02/09/1984 |
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From: |
Seiken S BECHTEL GROUP, INC., STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
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To: |
Jay Collins, James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
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References |
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84-01, 84-1, SLNRC-84-0028, SLNRC-84-28, NUDOCS 8402170209 |
Download: ML20086N064 (10) |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
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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. 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Initially Reported on 890825.Switches Put on QC Hold Until Final Disposition of Switches Determined 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 ML20244D2901989-06-0101 June 1989 Part 21 Rept Re Buchanan 724 Terminal Blocks Supplied by Limitorque Corp,Rather than Correct Buchanan 524 Terminal Blocks.Caused by Error in Order Processing.Training Held to Ensure That Procedures Followed Correctly ML20246N7911989-05-10010 May 1989 Part 21 Rept Re Room Cooler Vents & Drains Mfg by Carrier Corp Per Bechtel Specs,W/Galvanic Corrosion at Interface w/90-10 copper-nickel Room Cooler Supply & Return Headers. 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Resolution to Problem Requires Increasing Pilot Valve Capacity & Reworking of Plug to Enlarge Pilot Flow Area ML20235Y4811989-03-0303 March 1989 Part 21 Rept Re Cracked Welds Discovered on Striker Plates of GE Circuit Breakers.Initially Reported on 890130.GE Advised Util That Striker Plates Subj to Impact Loading Only When Breaker in Racked Out & Operated in Test Position ML20195F6191988-11-18018 November 1988 Part 21 Rept Re GE Magne-Blast Circuit Breakers.Initially Reported on 881116.Welds on All safety-related Breakers Will Be Repaired Prior to Entry Into Hot Shutdown 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 ML20151W7841988-08-16016 August 1988 Part 21 Rept Re Cracking of Slides Used in Four Way Valves Furnished on Actuators for MSIVs Due to Brazing/Heat Treating of Slide Matl.All Sites Using Actuators Will Be Formally Notified by 880826.List Encl 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 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 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 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 ML20151B4291988-04-0101 April 1988 Part 21 Rept Re Inconsistencies in Gould,Inc Certificate of Compliance Received W/Class 1E Fuses Procured from Planned Maint Sys Due to Fuses Not Being Qualified for Certain Specs.Initially Reported on 880329.Fuses Remain on Hold 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 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 ML20237G5781987-08-0707 August 1987 Part 21 & Deficiency Rept 142 Re Defect in Starting Air Distributor Sys of Dsr Standby Diesel Generator.Drain Sys Will Be Permanently Installed in Start Air Distributor ML20236N7131987-08-0505 August 1987 Part 21 Rept Re Potential Problem W/Vibration in Lube Oil & Jacket Water Sys.At Rancho Seco Site,Fatigue Cracks Found in Welds of Support Members in Lubricating Oil Sys.Cracks Due to Vibration in Lube Oil Sys.Addl Preventive Action Taken ML20234C7351987-06-23023 June 1987 Supplemental Part 21 Rept Re Silicone Foam Seal Anomolies at Wolf Creek Generating Station ML17261A5301987-06-18018 June 1987 Part 21 Rept Re Potential Util Failure to Comply W/Component Containment Isolation Licensing Commitment If Proposed Mods to Component Cooling Water Sys Instituted.Utils Advised to Evaluate Containment Isolation Sys 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 1996-06-04
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E2691999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Callaway Plant,Unit 1.With ML20217G1521999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Wolf Creek Generating Station.With ML20212D0711999-09-14014 September 1999 Safety Evaluation Re GL 88-20, Individual Plant Exam for Severe Accident Vulnerabilities ML20212A3361999-09-14014 September 1999 1999 Biennial RERP Exercise, for Callaway Plant. Pages 7,8 & 9 (of 9) in Mini Scenario 1 Section of Incoming Submittal Not Included ML20211N0161999-09-0202 September 1999 Safety Evaluation Supporting GL 95-07 to License NPF-42 ML20211N0451999-09-0202 September 1999 Safety Evaluation Concluding That Util Has Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant That Are Susceptible to Pressure Locking & Binding ML20212A0251999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Wolf Creek Generating Station.With ML20212A0201999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Callaway Plant,Unit 1.With ML20217P6451999-08-30030 August 1999 Requests Commission Approval to Publish Encl Pr,Rg & SRP & to Issue Encl Ltr to Parties of Wolf Creek Transfer Proceeding Re Disposition of Existing Antitrust License Conditions in Event OL Transfer Approved ML20210P0441999-08-10010 August 1999 Safety Evaluation Granting Licensee Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code,For Second 10-year Interval ISI at Plant,Unit 1 ML20210Q8331999-08-0505 August 1999 Rev 4 to Callaway Cycle 10 Colr ML20210T9481999-08-0303 August 1999 Informs Commission Re Status of Issues Related to Risk Informed Decision Making That Were Raised During Staff Review of License Amend Approving Electrosleeve SG Tube Repair Method for Ue Callaway Plant,Unit 1 ML20210R5741999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Wolf Creek Generating Station ML20210T4451999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Callaway Plant,Unit 1.With ML20216D8791999-07-31031 July 1999 Rev 3 to Callaway Cycle 10 Colr ML20210H6531999-07-30030 July 1999 SER Accepting Relief Request to Second Ten Year Inservice Insp Plant for Plant,Unit 1 ML20210J1561999-07-29029 July 1999 Rev 0 to Wolf Creek Generating Station,Unit 1 Pressure & Temp Limts Rept ML20209H0821999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Wolf Creek Generating Station ML20210R5921999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Wolf Creek Generating Station ML20209H0881999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Callaway Plant,Unit 1.With ML20195D5261999-06-0202 June 1999 Safety Evaluation Approving Proposed ISI Program Alternative for Limited Reactor Vessel Shell Weld Exams & Relief Request from Requirements of ASME Code,Section XI ML20195H4831999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Callaway Plant,Unit 1.With ML20210R5871999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Wolf Creek Generating Station ML20195K1021999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Wolf Creek Generating Station ML20206P8261999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Wcgs.With ML20196L3401999-04-30030 April 1999 Rev 1 to WCGS Cycle 11 Colr ML20210R5841999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Wolf Creek Generating Station ML20195K1071999-04-30030 April 1999 Revised MOR for Apr 1999 for Wolf Creek Generating Station ML20206R7111999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Callaway Plant Unit 1.With ML20205Q5561999-04-19019 April 1999 Safety Evaluation Accepting Relief for Request from Certain ASME Section Requirements for Containment Insp ML20205Q0761999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Wolf Creek Generating Station.With ML20205S5791999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Callaway Plant Unit 1.With ML20207A7401999-03-30030 March 1999 Draft, Evaluation of Risk of Induced Steam Generator Tube Rupture, for Callaway Plant ML20205G4071999-03-25025 March 1999 Security Event Rept:On 990304,failure to Properly Compensate for Loss of Safeguards Equipment That Could Have Resulted in Undetected Intrusion Into Protected or Vital Area,Was Discovered.Caused by Msk 325 Failure.Replaced Msk 325 ML20207K5991999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Wolf Creek Generating Station.With ML20204B6741999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Callaway Plant,Unit 1.With ML20207K9761998-12-31031 December 1998 Annual SER 14,for Period 980101-1231, for WCGS ML20199E6531998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Wolf Creek Generating Station.With ML20195B9901998-12-31031 December 1998 Western Resources Annual Rept for 1998 ML20195C0011998-12-31031 December 1998 Ks City Power & Light Co 1998 Annual Rept & Financial Statements as of 981231 & 1997 for Ks Electric Power Cooperative,Inc ML20199E7011998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Callaway Plant.With ULNRC-03990, 1998 Annual Rept for Ameren Corp/Union Electric Co. with1998-12-31031 December 1998 1998 Annual Rept for Ameren Corp/Union Electric Co. with ML20198D9811998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Callaway Plant,Unit 1.With ML20198D7321998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Wolf Creek Generating Station.With ML20195H9801998-11-17017 November 1998 Safety Evaluation Supporting Proposed Changes to WCGS Radiological Emergency Response Plan ML20195C8341998-11-10010 November 1998 Rev 20 to Operating QA Manual ML20195E7591998-11-10010 November 1998 WCNOC Proposed PASS Function Reduction ML20195C8181998-11-0909 November 1998 Rev 19 marked-up Changes to Operating QA Manual ML20195D6931998-10-31031 October 1998 Non-proprietary Rev 3 to Electrosleeving Qualification for PWR Recirculating SG Tube Repair ML20195D3581998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Callaway Plant,Unit 1.With 1999-09-30
[Table view] |
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SNUPPS Standardized Nuclear Unit Power Plant System s choke ch.,ry Road February 9, 1984 Rockwine, Maryland 20050 SLNEC 84-0028 FILE: 0491.10.2 SUBJ: Final Report: Gould/Rundel Selector Switch Failures, 10CFR50.55(e)
Report 84-01 Mr. James C. Keppler Administrator, Region III <
U.S. Nuclear Regulatory Commission 799 Roosevelt Road M@20W2 %
Glen Ellyn, Illinois 66137 3W dMr 900h'rP TNollins, y Administrator, Region IV -
U.S. Nuclear Regulatory Commission Suite 1000, Parkway Central Plaza Arlington, Texas 76012 Docket Nos. STN 50-482 and STN 50-483
Reference:
KGE Letter, G.L. Koester to W.C. Seidle dated 9/23/83:
Potential 10CFR50.55(e) Report-Gould/Rundel Handswitches Gentl emen:
Enclosed is a report concerning the failure of Gould-Rundel 4-position selector switches at the Callaway and Wolf Creek plants. The report is being submitted on behalf of Ur. ion Electric Company and Kansas Gas and Electric Company as a final Significant Deficiency Report as re-quired by 10CFR50.55(e).
The failure of the subject switches was initially reported to NRC Region IV (Johnson) for Wolf Creek on August 24, 1983, with the refer-enced interim report submitted on September 23, 19d3. A report on similar problems at Callaway was telephoned to NRC Region III (Pelke) by Union Electric Company (Laux) on January 11, 1984.
On the basis of further investigation, the 4-position selector switch failures were judged to be generic in nature resulting from a design deficiency in the switches. As ' indicated in the enclosed report, all; Callaway and Wolf Creek 4-position selector switches will be replaced
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by switches of modified design. The manufacturer, Gould/Rundel, will-be requested to notify other nuclear utilities of the problem with these switches and to consider reportability of these items under Part 21 regulations.
8402170209 840209 PDR ADOCK 050004P2 h
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SLNRC 84-0028 Page Two Please do not hesitate to call should there be any questions concerning this report.
Very trulp yours, a
S. J.VSeiken QA Manager RPW/dck/12b28 Enclosure cc: D. F. Schnell UE G. L. Koester KGE D. T. McPhee 4 CPL W. S. Schum NRC/WC J. H. Neisler fiRC/ CAL B. H. Little NRC/ CAL R. C. DeYoung NRC/IE: HQ J. E. Konklin NRC/IE: III
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FINAL REPORT-ON i
j SELECTOR SWITCH FAILURE PER
- 10CFR 50.55(e) i i
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SNUPPS PROJECT ~
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.PECHTEL POWER CORPORATION i
~GAITHERSBURG. MARYLAND L
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TABLE OF CONTENTS PACE 1
1.0 Introduction 2.0 Description of Selector Switch 2 and Deficiency 3
3.0 Safety Implications 5
4.0 Resolution and Corrective Action 6
5.0 Conclusions 2
l i ,
t'
1.0 INTRODUCTION
In August and September of 1983, during startup testing of the containment ventilation systems, deficiencies were discovered with I local selector switches provided by Gould in the SNUPPS Motor Control Centers at the Callaway (Union Electric) and Wolf Creek (Kansas Gas & Electric) stations.
In August of 1983, problems were encountered during startup testing of the Containment Air Coolers at the Wolf Creek station with the 4-position Gould-Rundel selector switches that were used as local handswitches. It was noticed that the switch cam became bound and improper contact operation resulted when the switch was operated.
In September 1983, similar problems were encountered during startup testing of the Hydrogen Mixing Fans at the Callaway station with identical switches. There, the selector switches exhibited erratic behavior such as binding, inconsistent continuity and indeterminant switch positioning.
The problems were documented on Startup Field Reports (SFR) at both sites (1-GN-4 at Wolf Creek and 2-GN-014A at Callaway). Upon learning of the deficiencies, the Kansas Gas and Electric Company reported this matter to the NRC as a potential significant deficiency under 10 CFR 50.55(e) criteria. A similar report was provided to the NRC by the Union Electric Company. The plant designer, Bechtel Power Corporation, has since determined that the j l
l
failure of the switches could prevent the Containment Air Coolers and Hydrogen Mixing Fans from starting upon receiving an automatic
( actuation signal, thus resulting in a deficiency requiring a report per 10CFR50.55(e) .
2.0 DESCRIPTION
'0F SELECTOR SWITCH AND DEFICIENCY The Gould-Rundel 4-position selector switches are installed on the motor control centers for the purpose of providing a local means of operating the Containment Air Coolers and Hydrogen Mixing Fans.
The switch consists of a knob, head block unit, an operating unit, one or more contact blocks and an end plate. A shaft in the head block assembly engages a shaft coupling in the operating unit that in turn engages the first contact block mechanism via another shaft coupling. Successive shaft couplings in each contact block engage, in sequence, the next contact block.
Eight failed switches from the Callaway site were returned to the supplier (Gould) for analysis. Geuld reported that their examination of the failed switches revealed three possible failure modes: (1) Dirt accumulation on the contacts had rendered the contacts susceptible to arcing when they closed, (2) excessive force had been applied to the switch, shearing off the cams on the shaf t couplings in the contact blocks, rendering the switch position indeterminant and aggravating the problem of dirty f contacts, and (3) the design of the switch is such that, through sequential actuation of the contact blocks, the entire cam assembly
. - _ _ - - - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ f
on switches utilizing four or more contact blocks becomes susceptible to operating force-induced twisting, causing improper or delayed contact switching. (Note: The SNUPPS Switches are designed with 6 and 8 contact blocks.)
It is Bechtel's judgement that the underlying cause of the SNUPPS 4-position selector switch failures is design related, i.e.,
failure mode No. 3. Due to distortion of the long switch assembly i
during operation, proper contact making force was not applied. j Additional operating force was necessary to obtain the required electrical continuity. This force caused the switch cams to shear and the switch became non-functional. The SNUPPS Utilities concur with the Bechtel assessment of the failures.
3.0 SAFETY IMPLICATIONS The affected Gould-Rundel selector switches are used in the control circuits of the Callaway and Wolf Creek Containment Air Coolers'and the Hydrogen Mixing Fans. The design of the control circuit is such that proper operation of a contact block is required in order for these loads to start under automatic actuation.
Four Containment Air Coolers and four Hydrogen Mixing Fans are provided in the generic SNUPPS design. Failure to start of up to two air coolers and up to two mixing fans would have no safety impact since only two of each is required in order to perform i
L
the intended safety functions. However it must be postulated that more than two Containment Air Coolers and/or more than two Hydrogen Mixing Fans may fail to start upon an accident signal due to the generic design deficiency described.
The loss of all 4 Hydrogen Mixing Fans is not a major concern following a LOCA. The fans serve only to enhance the uniform mixing of the containment atmosphere. The action of the containment sprays, the open design of the containment and the expected natural convection currents would ensure adequate mixing to preclude adverse concentrations of hydrogen to form in local areas.
The loss of all 4 Containment Air Coolers has not been specifically analyzed; however, the redundant and diverse containment spray system would provide pressure and temperature control for the containment atmosphere. A preliminary review of the heat removal l capability of the containment spray system acting alone indicates that the resultant containment pressure following a DBA would not likely exceed the containment design pressure of 60 PSIG. However, the resultant long-term containment temperature would, in all liklihood, exceed the maximum long-term qualified temperature profile of selected safety-related equipment needed to mitigate a DBA. Should this occur, operation of the required safety loads l
could not be assured during the long-term recovery period. On this basis, the defective switches are judged to have an adverse safety
. l l
impact reportable under 10CFR50.55(e) criteria. Consequently, these items will be replaced with modified switches of a sound design.
4.0 RESOLUTION AND CORRECTIVE ACTION As indicated above, the MCC supplier will replace the affected switches with switches of a modified design. The new switches will be designed with a common steel shaft (in lieu of shaft couplings) running the length of the switch assembly. This will change the operation of the switch such that all contact blocks will be actuated simultaneously rather than sequentially. Thus the use of this steel shaft, resulting in the need to apply only a normal operating force to the switch mechanism, will assure proper switch operation, regardless of the additional contact blocks used. All replacement switches will be continuity tested and their design reviewed and confirmed at the time of changeout.
The new switches will be shipped to both sites and installed prior to fuel load. Direction and authorization to perform this rework has been furnished to each SNUPPS site and will be initiated upon receipt of the replacement switches.
The conclusion that the 4-position selector switches are susceptible to malfunction when utilizing an excessive number of contact blocks has caused concern as to whether other Gould switches used on the MCCs at either SNUPPS plant could be susceptible to similar malfunction. These switches are of the
2-position and 3-position design and contain up to 10 contact blocks. Although there have been no experienced failures of the 2-and 3-position switches to date, this matter is being pursued with Gould. If the 2- and 3-position switches are determined to be suseptible to similar malfunction, appropriate corrective actions will be taken and the NRC so advised.
The MCC supplier will be requested to inform othcr users of these 4-position selector switches of the problems experienced at Wolf Creek and Callaway so that corrective action can be taken if similar switches are found to be used in safety-grade nuclear systems.
5.0 CONCLUSION
S The SNUPPS Motor Control Centers supplying the Containment Air Coolers and Hydrogen Mixing Fans were found to have a selector switch of faulty design which, if left uncorrected, could potentially compromise the ability to maintain e.he station in a safe condition. The early detection and implementation of suitable l
)
corrective action assures that these essential safety loads will l 1
function as designed and perform their intended safety function. I l
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