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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20132C0751996-12-13013 December 1996 Part 21 Rept Re Testing of Six HFD3045 & HFD3060 Molded Case Circuit Breakers w/125 Volt DC Shunt Trip Devices.Identified Incorrectly Installed DC Shunt Trip Units & Are in Process of Being Returned to Vendor ML20112G3871996-06-0404 June 1996 Potential Part 21 Rept Re Capscrews W/Trace Code of K7 Mfg by Cardinal Industries (Now Known as Accutech) & Distributed by Energy & Process Corp for Plant CP S/N 0194012.Pump/motor Would Remain Operational Throughout Worse Case Scenario 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 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 ML20086G2931991-11-21021 November 1991 Part 21 Rept Re Failure of Model 763 & 763A Static Pressure Transmitters.Caused by Short Circuit in Connector Pin to Adjacent Mounting Screw.Engineering Drawings & Mfg Work Instructions Changed & Stock Purged of Subj Transmitters ML20070A6861991-01-17017 January 1991 Part 21 Rept Re Failure of 4.16 Kv vertical-lift Switchgear Cell Mounted,Auxiliary Contacts to Operate on Demand During Testing of Auxiliary Standby Switchgear at Facility. Initially Reported on 901101.New Test Link Sent to Facility ML20062D9351990-11-0101 November 1990 Part 21 Rept Re Failure of 4.16 Kv Vertical Lift Switchgear, cell-mounted Auxiliary Contacts to Operate on Command During Testing of Standby Switchgear at Plant.Caused When Maladjusted Test Link Inserted Between Breaker & Switch ML20059N5191990-10-16016 October 1990 Part 21 Rept Re Rod & Bearing Assembly Failures Noted by Wolf Creek Nuclear Operating Corp During Testing.Rept Will Be Issued Outlining Root Cause & Corrective Actions to Prevent Recurrence 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 ML20246J0631989-08-29029 August 1989 Part 21 Rept Re Namco Refusal to Certify Design & Matls for Replacement Namco Limit Switches Supplied by Masoneilan. 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. Vents & Drains Will Be Modified During Current Outage 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 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] |
Text
T SNUPPS Standardised Nuclear Unit Power Mont System s chok. cherry Road July 22,1983 Rockviles, Maryland 20050 5"***** SLNRC 83- 040 FILE: 0491.10.2 SUBJ: Significant Deficiency Report (SDR) 83-10: Excessive AC/DC Control Cir-cuit Voltage Drop f W .EJanes-GUKepplers
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Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. John T. Collins 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 Gentlemen:
The enclosed report is forwarded on behalf of the SNUPPS Utilities; i.e.
Union Electric Company and Kansas Gas and Electric Company, as a final Significant Deficiency Report under 10CFR50.55(e) criteria. The defi-ciency involves excessive volt 2ge drop in a number of AC and DC control circuits designed by Bechtei. Since the SNUPPS project utilizes a stan-dardized design for both Callaway and Wolf Creek plants, this deficiency is considered to be generic in nature. As indicated in the enclosure, design modifications have been developed to be implemented in the field by means of Field Change Rework Plans.
The deficiency described in the enclosed report was initially reported to NRC Regions III and IV via telecon on June 23, 1983. Since the de-sign deficiency was indicated to have impact on other Bechtel projects a 10CFR Part 21 report was forwarded by Bechtel to NRC Region I on June 30, 1983.
-If you have any questions regarding the enclosed report, please advise.
Very truly yours, 8308030102 830722 DR ADOCK 05000 B
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h g pD S. J. Seiken Manager, Quality Assurance SJS/dck/18b10 Encl: Final Report on AC and DC Control Circuit Deficiencies p$
cc- 9,9
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.- 9 SLNRC 83-040
- Page Two -
cc: G.~L. Koester, KGE. w/ encl.
D. T. McPhee, KCPL D. F. Schnell, UE "
H. W. Roberds, NRC/WC J. H. Neisler, NRC/ Cal "
J. Konklin, NRC/ Reg. III "
, ' R. C. DeYoung, Dir. 0IE, NRC/ Wash. D.C. w/ encl.
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i FINAL. REPORT ,
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AC AND DC. CONTROL CIRCUITRY PER l 10CFR50. 55 (e) s l'
4 SNUPPS Project i
Bechtel Power Corporation Gaithersburg, Maryland f
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4 TABLE OF CONTENTS s
i PAGE 1.0 Introduction 1 2.0 Description of control Circuits and Deficiency 1 3.0 Safety Implications 3 I
4.0 Resolution and Corrective Action 6 5.0 Conclusions 8 i
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1.0 INTRODUCTION
1 Investigations of the SNUPPS ac and de control circuit,s,have
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revealed a deficiency in the circuit design. The studies indice.te that certain 480 volt Class IE Motor Control Center (MCC) ac control circuits and power circuit breaker de control circuits were
. of an excessive length. Under partially discharged station battery voltage conditions arising from a battery charger failure, and under degraded offsite power system conditions, there could have i beca insufficient voltage at the terminals of specific motor controllers or power circuit breakers to permit operation of
, this equipment. This lack of sufficient voltage results from the long length of the control circuit conductors.
The ac and de control circuit deficiency is common to the Callaway and Wolf Creek stations of the SNUPPS project.
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2.0 DESCRIPTION
OF CONTROL CIRCUITS AND DEFICIENCY c
The SNUPFS 480 V MCCs utilize a separate control power transformer i
i (CPT) for each individual motor starter control circuit. The power (VA) rating of each CPT varies with the rating of the controller to which it is applied, i.e NEMA size 1,2,3,4 or 5. The SNUPPS Class IE 4.16 kV switchgear and 480 volt load centers utilize a 125 V de l
control power source from one of two Class IE 125 V de station batteries.
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The SNUPPS ac control circuits utilize 14 AWG copper wire
- throughout. Each CPT supplies its respective control load. The
control load carried by each CPT is not identical for all CPTs, but generally consists of the associated motor controller and several types of auxiliary loads such as auxiliary relays and indicating lights. Together, the CPT rating, controller rating, minimum
, controller pickup voltage, control circuit conductor size, CPT auxiliary load and minimum MCC voltage establish a maximum permissible length of each individual ac control circuit.
i The SNUPPS dc control circuits also utilize 14 AWG copper wire throughout. Several indicating lights and auxiliary relays constitute a typical auxiliary load for each de control circuit.
Together, the switchgear and load center de control bus voltage, circuit breaker closing current and minimum circuit breaker operating voltage also establish a maximum permissible length of each de control circuit.
i Investigation and quantification of the maximum permissible control circuit lengths revealed that selected Class IE ac and de control circuits lengths were excessive. Under conditions where the MCC bus voltage or station battery voltage was near its respective minimum design or end-of-duty cycle voltage, sufficient voltage to operate the controller or circuit breaker could not be assured at the device terminals. The voltage drop across the control circuit that results when the controller or circuit breaker is energized, in combination with the parameters listed l
above, produces this situation. The result of the excessive circuit lengths is, given the above voltage conditions, that the affected loads could be unavailable for events that require starting for safety systems.
3.0 SAFETY IMPLICATIONS The deficiency described in this report affects the automatic actuation control circuitry of the following loads:
- 1. Hydrogen Mixing Fans
- 2. Motor-driven Auxiliary Feedwater Pump
- 3. Diesel Generator Building Supply Fans
- 4. Travelling Water Screens
- 5. Traveling Water Screen Spray Valves
- 6. ESW Pump Air Vent Release Valves Load Nos. 1, 2 & 3 above are affected on only one load group at both Callaway and Wolf Creek. Loads 4, 5 & 6 above are affected on both load groups at Wolf Creek only. The safety implications of each load being unavailable following a DBE requiring their operation are discussed below.
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- 1. Loss of one load group of Hydrogen Mixing Fans would, in itself, not compromise the safety of the station.
The redundant load group, which is not affected by the deficiency described in this report, would remain available
and perform any required safety function. However if it is further postulated that the redundant load, group is unavailable, due for example to loss of offsite power and failure of its diesel generator to start, none of the Hydrogen Mixing Fans would start automatically. For this condition, sufficient turbulence to preclude the formation of locally high concentrations of hydrogen would be established with the containment spray system and the containment air cooler system in operation. The two affected fans may be readily started locally from their MCC without regard to control circuit voltage drop. If this manual action were done shortly after the postulated DBE, no safety impact would be encountered.
- 2. The Auxiliary Feedwater System is provided to remove decay heat following a loss of offsite power or secondary side line rupture. The loss of a single motor-driven AFW pump due to the control circuit voltage drop would have no safety impact following the postulated DBE. The redundant motor driven pump or the turbine driven AFW pump would be available to perform the safety function of decay heat removal, even with a single failure in the AFW system. For example, if it were further postulated that the unaffected load group was unavailable as outlined above, the turbine driven AFW pump would be available for decay heat
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removal. It should be noted that if the affected motor driven AFW pump circuit breaker is closed locally, or.the redundant train motor driven AFW pump is started (by restoring offsite power or starting its associated diesel generator), at least two AFW pumps would be available, even considering a postulated single failure. Therefore, for this particular load, there is no safety impact on the statien.
- 3. The Icss of one train of Diesel Generator Building Supply Fans would have no safety impact provided that the redundant diesel generator or offsite power is available. However, if it is postulated that all offsite power is lost and that the unaffected load group diesel generator is unavailable, loss of all ac power could result if the affected supply fan were not started locally by manual operator action.
Operation of a Diesel Generator without its associated supply fan running would pose little immediate safety concern.
Upon an accident signal, the Diesel Generator Building exhaust dampers would open. The diesel generator air intake, which is l
located within the diesel generator room, would draw air in through the building intake louvers and exhaust dampers for combustion. However, except for cold weather operation, the temperature of the Diesel Generator Building would rise above design limits after the diesel generator reached equilibrium temperature if the affected supply fan was not started locally.
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4,5 Loss of all ESW travelling water screens and screen spray valves would have no chort term safety impact. -Bowever prolonged operation without these loads could potentially
! result in ESW pump damage from loss of suction pressure if a I
large amount of debris accumulated on both screens. However the screens may readily be started and spray valves opened
, from a control panel in close proximity to these loads, irrespective of the voltage drop in the conductors of the automatic control circuitry.
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) 6. The normally open ESW pump air vent release valves are designed to isolate the air release lines after the air in the pump suction and discharge lines is vented following pump i
start. Once started, the ESW pumps will not be shutdown 4
during a DBA. The control circuit that performs this isolation function is not affected by the deficiency described in this report. However, the excessive control circuit length could cause these valves to remain closed should their associated pump be secured for an unforeseen reason. Such failure to open would result in failure to release air trapped in the ESW piping if the pumps were subsequently re-started. Should an air pocket form in the ESW piping system in the interim period, a dynamic transient could result and potentially l
overstress the piping system.
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n In sununary, the SNUPPS ac and de control circuit ' deficiency would have -
ie no safety impact on the normal power operation of the SNUP{S stations. 3
. 1 However, a DBE coincident with a loss of offsite power and a postulated single failure in the redundant Joad group of safety-related equipment, without local operator action to restore the affected components to service could potentially compromise the abillty to maintain the plan [
in a safe condition during the long term recovery period if'the control circuit deficiency were left uncorrected. '
v 4.0 RESOLUTION AND CORRECTIVE ACTION In order to rectify _the deficient control circuits, the project has initiated appropriate design changes to the affected motor ;
controller and power circuit breaker compartments. Depending on the specific circuit requirement, either larger CPTs (for ac control circuits) or interposing auxiliary relays (for ac and dc . -
control circuits) will be installed. Use of a larger CPT provides the required CPT capacity to carry all CPT control loads and operate the motor controller with minimum permissible voltage
, at the CPT primary for ac control circuits. Where installation of a larger CPT is not feasible, interposing relays are installed.' 1 In this design, the control circuit operates an auxiliary relay instead of the controller. The electrical characteristics of the interposing relay are such that adequate voltage is available for it to operate, considering all required design parameters, with minimum permissible CPT primary voltage. The motor controller follows the action of the interposing relay.
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Interposing ralays'have been similarly applied to all
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affected de control circuits. By designing the control circuit to
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cperate the relay, proper operation of all power circuit breakers is assured under all design basis station battery voltage s
conditions, s Ss ,
- in order to prevent future recurrence of the deficiency, the project has initiated a check in the design process to prevent the release of any control circuit uatil its engineered length
, i s ',
is determined and compared against established maximum control circuit length criteria. This design check is intended to flag m,
all potential control circuit length deficiencies prior to their release.
5.0 CONCLUSION
S s ,
The SNUPPS ac and de control circuits were found to have a deficiency which, if left uncorrected, could potentially compromise the capability to maintain the plant in a safe condition. The implementation of corrective and preventive measures described in this report ensures that all control circuits will be adequate to meet their safety design basis.
A