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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEAR3F1099-19, Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated1999-10-13013 October 1999 Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated ML20217B0931999-10-0606 October 1999 Part 21 Rept Re Damaged Safety Grade Electrical Cabling Found in Supply on 990831.Damage Created During Cabling Process While Combining Three Conductors Just Prior to Closing.Vendor Notified of Reporting of Issue ML17292B5341999-01-15015 January 1999 Part 21 Rept Re Incorrect Modeling of BWR Lower Plenum Vol in Bison.Defect Applies Only to Reload Fuel Assemblies Currently in Operation at WNP-2.BISON Code Model for WNP-2 Has Been Revised to Correct Error ML17292B5331999-01-15015 January 1999 Part 21 Rept Re XL-S96 CPR Correlation for SVEA-96 Fuel. Defect Applies Only to WNP-2,during Cycles 12,13 & 14 Operation.Evaluations of Defect Performed by ABB-CE ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods 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 ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed ML20249B7791998-06-22022 June 1998 Part 21 Rept Re Findings,Resolutions & Conclusions Re Failure of Safety Related Siemens 4KV,350 MVA,1200 a Circuit Breakers to Latch Closed ML20217C2481998-04-21021 April 1998 Potential Part 21 Rept Re Failure of Siemens Circuit Breaker to Close Latch in Test Position W/Ge Test Flag Installed. Cause Indeterminate.Will Ship Identified Circuit Breakers to Siemens Mfg Facility in Wendell,Nc for Checking Procedure ML20198E0631998-01-0707 January 1998 Part 21 Rept Re Shipment by Dubose National Energy Svcs,Inc, of 40 Pieces of 4 inch,90 Degree Elbows Which Did Not Meet ASME Section II SA-234 Requirements LD-97-033, Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 9712011997-11-20020 November 1997 Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 971201 LD-97-028, Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys1997-10-13013 October 1997 Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys 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 ML17309A6211997-09-29029 September 1997 Part 21 Rept Re Final Disposition of Masterflow 713 & Embeco 636 Grout Nonconformance Reported by Master Builders,Inc. Licensee Continuing to Monitor shelf-life of Masterflow 713 & Embeco 636 Grouts Produced at Rancho Cucamonga LD-97-024, Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-0041997-08-14014 August 1997 Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-004 ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages 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 ML20134B2301997-01-24024 January 1997 Final Part 21 Rept Re Potential Safety Concern on Matl Used for Fabrication of Permanent Canal Seal Plate.Correpondence W/Fabricator & Matl Supplier Documents Tig Automated Welding Process Used to Fabricate Angle Pieces ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology 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 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 ML17292A2141996-05-0808 May 1996 Part 21 Rept Re Capscrews Supplied to Wppss by Now Defunct Cardinal Industrial Products,Lp (CIP) Having Nonconforming Hardness.Failed Lots & Any Remaining Product Found to Have Been Heat Treated by CIP Scrapped & Removed from Premises LD-96-009, Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power1996-04-15015 April 1996 Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power ML20101N8441996-04-0505 April 1996 Interim Part 21 Rept Re Potential Safety Concern on Matl for Fabrication of Permanent Canal Seal Plate.Licensee Will Provide Final Rept to NRC in Approx Six Months Upon Completion of Evaluation of Welds ML20094M6251995-11-21021 November 1995 Final Part 21 Rept of Investigation & Analysis of Suspect Fasteners Event 29257.B&G-Cardinal Discontinued Using Heat Treatment Equipment at Cardinal Facility Until Such Time That Satisfactory Mods Made to Hardware & Procedures ML20082E7421995-04-0404 April 1995 Part 21 Rept Re Nonconformance in Dresser Industries,Inc (Dresser) MSSV Owned by Entergy Operations,Inc ANO Unit 1. Part Used in Safety Valve That Was Not Mfg to Spec Requirements & Not Mfg Nor Provided by Dresser 3F0295-15, Part 21 Rept Re GE Supplied Constant Voltage Transformers (Cvt).Vendot Supplied FPC W/Instructions on Mod of Cvts Located in Installed VBIT-1D,to Return Output Voltage to Required Values & FPC Modified Cvts1995-02-27027 February 1995 Part 21 Rept Re GE Supplied Constant Voltage Transformers (Cvt).Vendot Supplied FPC W/Instructions on Mod of Cvts Located in Installed VBIT-1D,to Return Output Voltage to Required Values & FPC Modified Cvts ML20080G3271995-01-30030 January 1995 Part 21 Rept Re Furnished Commercial grade/non-safety Related Studs,Nuts & Washers for Use on safety-related Crystal River 5th Yr post-tension Surveillance Program ML20078F5841995-01-27027 January 1995 Part 21 Rept Re Vendor Using Incorrect Acceptance Criteria on Qualification Test Rept & Acceptance Criteria Used Not Not Met by Cvts.Vendor Continues to Seek Resolution of Matter ML20076M8321994-10-28028 October 1994 Submits Followup to 940516 Part 21 Rept Informing of Investigation to Determine Data Supplied in mid-80 Used by Nuclear Utilities to Set Torque Switches in MOV ML20072T0171994-08-30030 August 1994 Final Part 21 Rept Re Gimpel Trip & Throttle valve.Dresser- Rand Changed Nuclear Part Insp Records for Both Coupling & Stem to Require That Parts Be Tagged W/Proper Assembly Instructions ML20072A7691994-08-0808 August 1994 Interim Part 21 Rept 2 Re Weak Link Analysis for Movs.No Evidence to Support Fact of Erroneous Data Discovered. Investigation Continuing ML20072A7871994-08-0505 August 1994 Initial Part 21 Rept 038 Re Failure of Gimpel Trip Throttle Valve to Open During Testing of AFW Pump Turbine at Toledo Edison.Subj Valve Stems Should Be Tagged W/Instructions Defining Proper Procedures for Securing Stem to Coupling ML17291A2571994-07-22022 July 1994 Part 21 Rept Re Westinghouse Containment Penetration Modules Scotchcast Strain Relief & Varglas Insulated Conductors. Replaced Six of 12 RPIS Scotchcast/Varglas Modules & Three Scotchcast/Okonite Modules During Refueling Outage (R-9) ML17291A2351994-07-15015 July 1994 Deficiency Rept Re Material Defects in Facility Containment Penetration Modules.Initially Reported on 940715.Modules Were Replaced ML17290B2001994-05-26026 May 1994 Part 21 Rept Re Automatic Switch Co Replacement Solenoid Pilot Valve Diaphragms Supplied by GE Nuclear Energy.Unusual Combination of Scram Soleniod Pilot Valve Pressure & Exhaust Diaphragm Degradation Caused Failure of Rod to Scram ML20070Q5721994-05-10010 May 1994 Part 21 Rept Re Potential Defect of Samtec,Inc 11-pin Connector Socket in Pro Series Bargraph Instrumentation. All safety-related Bargraphs That May Contain Suspect Connector Have Been Identified & Licensee Notified 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 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 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 ML20056E9751993-08-19019 August 1993 Provides Insp Results & Safety Analysis Re Operational Amplifiers Discussed in 920917 & 23 Ltrs as Potential Safety Issue.Concludes That There Are No Safety Concerns W/Respect to Buffer Amplier Module.Ltr Not 10CFR21 Notification 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 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 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 LD-93-003, Part 21 Rept Re Defect in Potter & Brumfield Model 170-1 Relay.One of Two Rotor Return Springs Broke & Portion of Spring Lodged Between Rotor & Stator.Rotor Springs Supplied by Lewis Spring Co.Info Bulletin Being Prepared1993-01-13013 January 1993 Part 21 Rept Re Defect in Potter & Brumfield Model 170-1 Relay.One of Two Rotor Return Springs Broke & Portion of Spring Lodged Between Rotor & Stator.Rotor Springs Supplied by Lewis Spring Co.Info Bulletin Being Prepared 1999-10-06
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17284A9001999-10-31031 October 1999 Rev 0 to COLR 99-15, WNP-2 Cycle 15,COLR ML20217L8931999-10-31031 October 1999 Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20217G0191999-10-15015 October 1999 Safety Evaluation Concluding That Licensee Followed Analytical Methods Provided in GL 90-05.Grants Relief Until Next Refueling Outage,Scheduled to Start on 991001.Temporary non-Code Repair Must Then Be Replaced with Code Repair ML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program 3F1099-19, Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated1999-10-13013 October 1999 Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated ML20217B0931999-10-0606 October 1999 Part 21 Rept Re Damaged Safety Grade Electrical Cabling Found in Supply on 990831.Damage Created During Cabling Process While Combining Three Conductors Just Prior to Closing.Vendor Notified of Reporting of Issue ML20212L0881999-10-0404 October 1999 SER Accepting Licensee Requests for Relief 98-012 to 98-018 Related to Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp for Crystal River Unit 3 ML20212J8631999-10-0101 October 1999 Safety Evaluation Supporting Licensee Proposed Alternatives to Provide Reasonable Assurance of Structural Integrity of Subject Welds & Provide Acceptable Level of Quality & Safety.Relief Granted Per 10CFR50.55a(g)(6)(i) GO2-99-177, LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With1999-10-0101 October 1999 LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With ML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c ML20217D5441999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Davis-Besse Nuclear Power Station.With 3F1099-02, Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With ML20212E9031999-09-30030 September 1999 FPC Crystal River Unit 3 Plant Reference Simulator Four Year Simulator Certification Rept Sept 1995-Sept 1999 0CAN109902, Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With ML17284A8941999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for WNP-2.With 991012 Ltr ML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20216J6271999-09-27027 September 1999 Rev 0 to CALC-98-R-1020-04, ANO-1 Cycle 16 Colr ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 ML20212E6911999-09-21021 September 1999 Safety Evaluation Supporting Proposed EALs Changes for Plant Unit 3.Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20211L1321999-08-31031 August 1999 EAL Basis Document 3F0999-02, Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With ML20212C1501999-08-31031 August 1999 Non-proprietary Version of Rev 0 to Crystal River Unit 3 Enhanced Spent Fuel Storage Engineering Input to LAR Number 239 ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With 0CAN099907, Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with ML17284A8801999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for WNP-2.With 990910 Ltr ML20211R0811999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20211F4281999-08-25025 August 1999 Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety ML20211B7291999-08-16016 August 1999 Rev 2 to Cycle 11 Colr ML20211B0271999-08-13013 August 1999 SER Accepting Second 10-year Interval Inservice Insp Requests for Relief RR-A16,RR-A17 & RR-B9 for Plant, Unit 1 ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210P1111999-08-0505 August 1999 SER Accepting Evaluation of Third 10-year Interval Inservice Insp Program Requests for Relief for Plant,Unit 3 ML20209F5601999-07-31031 July 1999 EAL Basis Document, for Jul 1999 ML20210U5341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Crystal River,Unit 3 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With 0CAN089904, Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with ML17284A8691999-07-31031 July 1999 Monthly Operating Rept for July 1999 for WNP-2.With 990813 Ltr ML20210Q8541999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20210K8831999-07-29029 July 1999 Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates ML17292B7421999-07-20020 July 1999 LER 99-001-00:on 990628,ESF Signal Closed All Eight MSIVs While Plant Was Shutdown.Caused by Failure of Relay RPS-RLY-K10D.Subject Relay Was Replaced & Tested on 990630. with 990720 Ltr ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML17292B7271999-06-30030 June 1999 Monthly Operating Rept for June 1999 for WNP-2.With 990707 Ltr 0CAN079903, Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With 3F0799-01, Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With ML20210U5411999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Crystal River,Unit 3 ML20209E6231999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Davis-Besse Nuclear Power Station,Unit 1.With ML20195K2871999-06-16016 June 1999 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves 1999-09-30
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l BW B&WNUCLEAR TECHNOLOGIES 3315 Old Forest Road JHT/93-128 P.O. Box 10935 May 26, 1993 Lynchburg VA 24506-0935 Triephone: 804-385-2000 Telecopy 804-385-3663 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Potential Safety Issue Regarding Limitorque Valve Actuator Declutch System Anomaly Gentlemen:
The purpose of this letter is to supplement a notification provided by Limitorque Corporation to the NRC dated December 7, 1992 concerning a Declutch System Anomaly in certain types of valve actuators.
The Limitorque letter (copy attached) advised that certain types of Limitorque valve actuators may not operate during a seismic event.
Following the end of the seismic vibration, the actuator will operate normally. As stated in that letter, Limitorque discovered through actuator testing that the possibility exists for malfunction of two types of actuators under certain conditions of seismic excitation. At certain excitation frequencies,'it was observed in tests that the actuators would not complete a stroke electrically during the dwell time when the actuator was vibrating. I After the excitation stops, the actuator will return to proper ;
operation. The safety concern, therefore, is applicable to motor operated valves which are required to operate during a seismic event.
The basic cause of the problem is the declutch system. The system is imbalanced in the vertical axis, and at certain vibration frequencies, vibration of the declutch 3er.er causes disengagement of the motor. To correct this conditim , Limitorque has designed a new declutch lever which will be avc11able in the first quarter of 1993. In the interim, it is rec pamended that the levers be secured to prevent potential movement.
The affected actuators are the SMB/SF.-000 and SMB/SB/SBD-00 types.
It is likely that the B&W-designed plants were supplied with these types of actuators for the valves shown on the attached list (see Attachment B). These valves would have been in the initial scope of supply and were initially used in safety-related applications.
BWNT also supplied actuators of these types as spares or replacements to several utilities as listed on Attachment A.
02005eu 9306030257 930526
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PDR ADOCK 05000269 f
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. 'l U. S. NRC JHT/93-128 May 26, 1993 Page 2 BWNT is advising the B&W-designed' plants of this concern for their evaluation of its potential effects on the operability of the affected valves and of the safety implications and reportability of the concern under Federal regulations. BWNT will' perform no further evaluation of the concern unless requested and authorized by the utilities.
-BWNT is advising the NRC of'this matter for information. This advisory is not a report under 10CFR21.
You may contact me at 804/385-2817 or Mr. David Mars at 804/385-2852 if you have any questions concerning'this matter.
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/ 01
/
G . Tay r, Manager
/.Licensin Services JHT/bcc Attachment cc: C.R. Gaines, Entergy Operations, Inc.
Manager, Nuclear Safety Assurance, Duke Power Company 1 R. C. Widell, Florida Power Corporation R. S. Harbin, GPU Nuclear Corporation E. C. Caba, Toledo Edison Company R. D. Wells, Tennessee Valley Authority L. C. Oakes, Washington Public Power Supply System I. E. Wilkinson, Limitorque Corporation i
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'g Limitorque Corporation Aut:moted Vcive &c: voters oed J :ms 'of !nd6st'y 6,, 5114 Woodcli Road . P.O. Box 11318 Lynchburg, VA 24506-1318 Fo ,
Q Teepnene (804) 528-4400 . FAX (804) 845-9736 ,
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'" December 7,1992 d. N .
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Sub DasGupta ,
Quality Assurance Manager SUB DASGUPTA B & W Nuclear Service Company 3315 Old Forest Road - P. O. Box 10935 DEC 151992 Lynchburg, VA 24506
Subject:
Potentially Reportable 10 CFR Part 21 Condition SMB/SB-000, SMB/SB/SBD-00 Declutch System Anomaly Please be advised that Limitorque Corporation has discovered througl actuator testing that the possibility exists for malfunction of the subject actuators under cenain conditions of seismic excitation. This situation could potentially be reponable depending on the operating practices of the licensee. Therefore, pursuant to the requirements of Title 10 CFR Part 21.
notification is herein provided of a potential malfunction of the subject actuators.
Identification of Basic Comoonent The affected components are the declu*.ching mechanisms in the SMB/SB-000 and SMB/SB/SBD-00 actuators.
Nature of the Defect A. The Basic Defect When the actuator is vibrated in the vertical axis with sufficient amplitude near the {
natural frequency of the declutch system, oscillations of the declutch system can cause the l motor to become disengaged. MOVs which are required to operate during such a seismic.
event may exhibit longer stroke times. The malfunction only occurs during tne seismic event. After the vibrations stop, the actuator will return to proper operation.
j The SMB/SB/SBD-00 and the SMB/SB-000 share the same basic design of declutch I
system which consists of the declutch lever, shaft, declutch fork, clutch ring, clutch keys. ;
return spring, and tripper lever asambly. The system is imbalanced in the vertical axis because the declutch lever exerts more counter-clockwise torque on the shaft than the other )
parts exert in the clockwise direction. Thus, the lever can provide a driving force causing the d.c..rch system to oscillate with enough amplitude to disengage the motor.
l:. .
i
- Page 2 i December 7,1992-Part 21 Notification 4
I B. Defect Observed in SMB/SB/SBD-00 j Limitorque has on two occasions experienced' malfunctions of the SMB/SB/SBD-00 !
declutch mechanism during seismic testing. The type of test performed was a seismic ~ dwell I test. In this' test the actuator was vibrated at frequencies from 2 hz' to 32 hz in 'one quaner octave intervals with a sinusoidal waveform in a single axis. The acceleration' level was 7.6-
- gs except at some of the lower frequencies where limitations of the shaker tables prevented .
reaching that level. At each frequency, the actuator was vibrated for fifteen seconds.
During each of these fifteen second' dwells, the actuator was electrically operated simulating a close and open valve stroke. This procedure was~ performed with vibrations in the vertical axis of the actuator and in two horizontal axes.
On the occasions in which the malfunction was observed,' the actuatois would not complete a stroke electrically in the expected amount of time during the seismic dwell. ,The problem was only found in the vertical axis, the units operated correctly.in the horizontal axes. Further, the problem.was only found at two specific vertical dwell frequencies: .11.3 - ,
and 13.5 hz. The problem was not seen at the 9.5 hz test and lower frequencies _nor was.it seen at the 16.0 hz test and higher frequencies. q 1
Limitorque has tested SMB 00 actuators in the manner described above on seven occasions. Refer to the table below for a summary. Of these seven tests, the declutch .
j problem was seen in two of the tests (numbered 4 and 6 below). Note that in test 6 the 1 amplitude of the fundamental frequency.did not reach 7.6 'gs at either 11.3 or 13.5 hz but 1 there were spikes of 15 gs present on the waveforms due to difficulties in controlling the -
seismic table. Due to these spikes,Ltest 6 may have been more severe with respect to ,
exciting the declutch system than the other tests which had cleaner waveforms.
SMB-00 Seismic Tests Pertinent to Declutch Problem l t
- Doctutch Test Date Acceteration et Frequencies of Interest Pratten i Fremonsfes 1- none 12/19/s0 7.6 as et-11.4 ha and 13.6 ha i
none 4/14/s1 7.6 gs at 11.6 ha and 13.6 ha 2 !
3 none 2/3/Es 7.6 se et 11.4 ha and 13.6 ha 4 11.3 hr 9/2s/90 '7.6 se et 11.3 ha and 13.5 ha I 5 none 1/s/91 7.6 ss at'11.3 ha and 13.s ha 6 11.3,~ 13.5 ha 8/22/91 see mete 1
.7 none 1/23/92 7.6 se et.11.3 ha and 13.5 ha i
note 1 During teet 86 the fwedsmentet fremency reached en esplitude of 6.s es et 11.3 ha and 7.s pi at.131 ha. . neuever, et beta of these fragencies there were epikes of 1s es present en the nevefona ase to j difficuttles in centreLLlng the seismic teMe. j
-l l
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, - - - -_ , . . . . _ , , . . . , - . _ . - , _ , . . . . = .. _ - _ . ... , , - - , . , _ . .
Page ')
- Dece.mber 7,1992 Part 21 Notification C. Defect Observen t.. SMB/SB-000 1
Limitorque is aware of a similar malfunction in the SMB/SB-000 declutch mechanism during a utility sponsored seismic test. . De type of test performed was a sine beat test. In this test the actuator was vibrated at frequencies from 2 hz to 35 hz in one third octave .
intervals with sine beat excitation of 15 cycles per beat in a single axis. Each sine beat test at each frequency. consisted of a continuous train of sine beats with no pause between beats.
The acceleration level was 4_.5 gs except at some of the lower frequencies where limitations of the shaker table prevented reaching that level. At each frequency, the actuator was vibrated for a minimum of fifteen seconds. - During each fifteen second test, the actuator was electrically operated simulating a close and open valve stroke. ' This procedure was . ;
performed with vibrations in the vertical axis of the actuator and in two horizontal axes. l The SMB-000 tested was reported as operating intermittently during the 12.5 hz and 7 i
16.0 hz tests in the vertical axis. ,The acceleration level reached 4.6 and 4.8 gs respectively !
during these tests. . After the first 16.0 hz test, the declutch lever was prevented from j
vibrating in further tests by being taped to the handwheel. Dus, it is unknown whether the problem would have occurred at the next highest frequency (20.0 hz). It is known that the problem was not seen at the 10.0 hz test and lower frequencies. And, in the horizontal axe the unit operated correctly (the lever was not taped during these axes)' ;
D. Critical Frequencies Based on the above tests, the potential exists for this malfunction to occur in the SMB/SB/SBD-00 at frequencies between 9.5 and 16.0 hz. This represents a maximum range 1
of critical frequencies of three quarters of an octave. The SMB/SB-000 declutch system should have a similar frequency range due to its' similarity with the SMB/SB/SBD-00 system. :
1 For a conservative estimate of the highest potential problem frequency in the SMB/SB-000 iti is calculated that three quarters of an octave above 12.5 hz is 21.0 hz. Thus, the potential exists for this malfunction to occur in the SMB/SB-000 at frequencies between 10.0 and hz. .<
Limitorque does not have adequate data to determine the minimum acceleratio; ,
which could potentially cause the malfunction. Note that the malfunction only occur the scismic event. After the vibrations stop, the actuator will return to proper operation.
E. Actuator Output Torque Can Prevent Malfunction In the observed cases of this malfunction, the actuators had minimal torque load; present. .When torque load is present, side loads are applied to the clu l loads in turn generate frictional forces. These frictional forces oppose clutch key and thus movement of the declutch system.' This is observed, for example, when' a is declutched while under valve seaung load Much more force must be applied.to
- declutch lever than when the valve is~in an unloaded condition. The driving f oscillations of the declutch system is due to the imbalance of the system a 1
.. .. pag g December 7,1992 -
. Part 21 Notification accelerated vertically. If sufficient torque load is present, the frictional forces on the clutch keys will be high enough to oppose the driving force due to the imbalanced lever and oscillations of the system will be prevented. ' At higher acceleration levels _more driving. force is generated and thus higher torque load is required to prevent oscillation.
Limitorque has performed calculations comparing the frictional key forces to the driving force to determine how much torque load is required to prevent shaft oscillations at a given acceleration level. In order to provide a conservative margin of safety 'and allow for uncertainties in the calculations, a factor of safety of approximately 4 is included in the resulting formulas. Torque is measured in ft Ibs and Acceleration is measured in gs.
SMB/SB-000.
Torque = 4 x Acceleration i
SMB/SB/SBD-00 Torque = 7'x Acceleration ,
i Example: For an SMB-000 undergoing a seismic event of 7.6 gs maximum acceleration the ~
l torque calculated is 30 ft lbs. For an SMB-00 at the'same acceleration level the torque-calculated is 53 ft lbs.
These calculations may be used to provide' assurance that an actuator will be able to open a valve from the torque seated condition to a point at which the opening torque drops to the level calculated.
Affected Eauioment The equipment affected are SMB/SB/SBD-00 and SMB/SB-000 actuators.
Limitoroue Comordan Corr =Mve Action To correct this problem, Limitorque has designed a declutch lever which balances the ,
torque of the other components in tb declutch system. With this lever installed, there is nol' imbalance in the' system and thus no driving force to cause oscillations. Levers have been designed for the SMB/SB/SBD-00 and for the SMB/SB 000. ' Such a lever was installed during the course of the SMB 00 test 6 mentioned above. This cured the declutch problem l in that test. ' Also, one of these levers was present in a test of an SB-00 and no declutch problem was observed. ;
Limitorque will make the new levers standard for future orders of SMB/SB/SBD-0 l
ad SMB/SB-000 units for nuclear service. I.ever availability is scheduled during the first quarter of 1993.
f Page5 December 7,1992 Part 21 Notification Licensee Corrective Action 1 Limit 6rque recommends that each licensee evaluate this situation based on the l
- potential of actuator malfunction at the frequencies mentioned above. If a specified valve stroke time is required, it must be assumed that valve motion ceases during a seismic event which includes these frequencies in a vertical orientation relative to the actuators. Herefore, the actual valve stroke time will be increased by the duration of the seismic event. An exception to this is a situation in which the torque load on the actuator is sufficient to create enough frictional forces to prevent declutch shaft oscillations as described in section E.
above. In this case the actuator will function as long as the torque load remains above the ,
critical value.
i Balanced levers may be purchased from Limitorque. For the SMB/SB/SBD-00 the .
new lever is part 0301-059 and fot the SMB/SB-000 the new lever is part 0101-081. In the interim it is tw.ommended that levers be secured to prevent potential movement.
Any questions regarding the above notification may be directed to P. McQuillan, Nuclear /Special Projects Manager at (804) 528-4400 Ext. 714.
Si ned:
Q, M y _
I. E. Wilkinson Vice President of Engineering LIMITORQUE CORPORATION pc: Mr. Mignogna Mr. Kornsey Mr. R. Segen Mr. M. Logan Part 21 Notification File
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ATTACHMENT A i
Soares or ReDlacements SuoDlied to Utilities
.i 1
i CUSTOMER CUSTOMER QZX CONTRACT 8 CUSTOMER B21 i
F./l SHIP DATE 2 788-400327 ANO 07736 S/Ns: 632-1
i 1 788-400346 ANO 23703 635-1 S/N: 12/07/84 [
1 788-7473024 ANO 188059 S/N: 891-1 10/27/88
_______________________________________________________q____________ ;
1 788-400297 ANO 84447 S/N: C507-1 3/22/83 1- 788-221131 TED 082-Q-72145A-M1 S/N: 889-1 8/31/82 1 788-400244 ANO- 76811 5007176 10/28/82 -
.____________________________________________________________________ 1 l
1 788-400444 ANO 14713 S/N: 661 1
12/26/86* l 1 788-7472044 FPC F740090D 0065380373 3/09/89 S/N: 668 i
1
- Our records indicate that this item was re-sold by ANO to TED (TED PO# C602218D90). 1
1 ATTACHMENT'B B&W-Desianed Plants (Oceratina'or Under Construction) I i
Ut111tv ' Plant-Duke Power Company. .Oconee Units"1,.2', 3 Arkansas Nuclear One-Unit.1 ~
~
Entergy Operations Florida Power Corp.- ' Crystal River-3 i
General Public Utilities -
Nuclear' Three Mile Island-Unit 1 Tennessee Valley Authority Bellefonte Units 1, 2.(1).
Toledo Edison' Company Davis-Besse l l
- Washington Public Power ' , l Washington Nuclear Power-Unit 1 Supply system -i (2)- l
,j l
(1) TVA intends to re-activate construction -
(2) WNP-1 is 'in a deferred status of construction l
1
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