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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl ML20077C2801994-11-21021 November 1994 Deficiency Rept Re Defective Yokes P/N 342849 Mfg by Copes- Vulcan,Inc.Affected Utilities Notified & Defective Yokes Will Be replaced.Copes-Vulcan Also re-inspected All Yokes in Inventory & Verified Yokes Acceptability ML20056D7071993-07-15015 July 1993 Part 21 Rept Re Reportable defect-75 PSIG Relief Check Valve 1 Npt,Emd 9521844,Kepner 416C-1-75 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 ML20094F5181991-12-23023 December 1991 Part 21 Rept Re Matl Used in Johnson Kokogawa Corp Wear Plate Blades Not Displaying Sufficient Spring Capabilities to Adequately Hold Rom Chip Pins When Rom Mounted in Socket.Util Advised That Improved Sockets Now Available 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 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 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 ML20153F9661988-04-19019 April 1988 Part 21 Rept Withdrawing 870929 Notification Re Potential Problem W/Saturable Core Transformer ML20195J7421988-01-25025 January 1988 Final Part 21 Deficiency Rept Re Potential Problem W/ Silicone rubber-insulated Cables.Based on Encl Three Test Repts,Tva Concludes That Mfg,Shipping,Receipt & Installation Practices Did Not Reduce Cable Insulation Thickness ML20235R1211987-09-29029 September 1987 Part 21 Rept Re Saturable Core Transformer Installed in Emergency Diesel Generator Set.Problem Developed in Svc. Teardown Insp Performed by Util.Results Noted Inadequate Insulation.Addl Info Will Be Provided ML20234F5261987-09-16016 September 1987 Followup Part 21 Rept Re Defective MIS-5 Actuating Fuses. Initially Reported on 870620.All Defective Fuses Will Be Replaced W/Fuses from Subsequent Lots Before Mode 4 ML20235H0041987-09-10010 September 1987 Part 21 Rept Re Nonconformance of American Insulated Wire Co & Rockbestos Co Silicone rubber-insulated Single Conductor Cables.Initially Reported on 870904.Cause Not Found. Evaluation Continuing ML20238E7721987-09-10010 September 1987 Part 21 Rept Re Special high-potential Withstand Tests on Number of Installed 14 Silicone rubber-insulated Single Conductor Cables.Initially Reported on 870904.Evaluation of Silicone Rubber Cable Continuing ML20214H3961986-11-14014 November 1986 Corrected Part 21 Rept Re MIS-5 Actuating Fuses Mfg by Bussman Mfg.Resistance Value Stated on Page 2 Should Be 55 to 65 Milliohms ML20210G9921985-08-13013 August 1985 Part 21 Rept Re Failure of Isolated Worm Shaft Gear When Certain Critical Speeds Combined W/Repetitive Transfer of Actuator Clutch Mechanism from Manual (Handwheel) to Motor Drive Mode.Two Possible Solutions Noted ML20129B2831985-07-0909 July 1985 Part 21 Rept Re Hk Control Device.Initially Reported by TVA in 850703 Morning Rept.Parts to Be Supplied for Completion of Insp/Adjusting Procedure Included in 830322 Part 21 Rept ML20116G8551985-03-25025 March 1985 Suppl to Final Deficiency Rept Re 460-volt Motor Documentation.Initially Reported on 810413.All Corrective Actions Will Be Completed by 851130 ML20106D8301984-10-0404 October 1984 Interim Deficiency Rept DER 84-67 Re Defective Target Rock Solenoid Valves.Initially Reported on 840907.Bechtel Studying Problem to Determine Reportability & Technical Justification for Corrective Action.Final Rept by 841030 ML20095E5911984-08-13013 August 1984 Part 21 Rept Re Fitting Leaks at Incore Probe Seal Tables at Pwrs,Per IE Info Notice 84-55.Subj Fittings Not Used as Instructed ML20092D9711984-06-15015 June 1984 Part 21 Rept Re Thermal Nonrepeatability & Other Calibr Errors in Barton Lot 1 Transmitters.Initially Reported on 840615.Transmitter Defects Identified & Expected Error Deviations Calculated.Utils Notified ML20090K6211984-05-0909 May 1984 Suppl to Revised Final Deficiency Rept Re Retrievable Info from Valve Tag Number.Drawing 47B601 Must Be Reissued to Include motor-operated Valve Info.Corrective Actions Will Be Complete by 840630 ML20083P9751984-04-12012 April 1984 Interim Deficiency Rept DER 84-07 Re Borg Warner Valve Stem Extensions & Failure to Provide Corrective Action Stated in Deficiency Rept DER 80-21.Initially Reported on 840209. Final Rept Will Be Submitted by 840601 ML20086G7741983-12-19019 December 1983 Interim Deficiency Rept DER 83-54 Re Washers Found in Steam Generators 1 & 2.Initially Reported on 830802.Time Extension Requested to 840118 for Filing Final Rept ML20078N8381983-10-25025 October 1983 Part 21 Rept Re Misloaded Pellets in Sequoyah Unit 2 Fuel Assembly.Initially Reported on 831025.QC Instruction Re Operations of Gamma Scan Unit Modified & Generic Review of Critical Mfg & QC Procedures Initiated ML20024E9261983-08-30030 August 1983 Revised Final Deficiency Rept Re Inability to Readily Retrieve Info from Valve Tag Number.Initially Reported on 801212.All Drawings to Be Revised by 831130 & Kept Current ML20077G6661983-07-27027 July 1983 Part 21 Rept Re Circuit Breakers Mfg Between Nov 1981 & Feb 1982.Breakers Should Be Inspected for Broken Puffer Linkage Studs.Stud Identified as Part Number 192247A.List of Circuit Breakers for Nuclear Plants Encl ML20076A8761983-07-27027 July 1983 Final Deficiency Rept Re 460-volt Motor Documentation. Initially Reported on 810413.Motor Overload Protection Will Cause Motor to Be Tripped from Boards,Should Terminal Voltage Be Too Low for non-IE Motors to Accelerate ML20073K0081983-04-12012 April 1983 Final Deficiency Rept Re Retrievable Info from Valve Tag Number.Initially Reported on 801212.Engineering Change Notice L-5680 Revised Drawing Series 47A365 & 47A366 to Cross Ref Manufacturer Valve Drawing Numbers for QA Valves ML20083P3191983-01-28028 January 1983 Revised Final Deficiency Rept Re Geared Limit Switch Covers Melting in Electrodyne motor-operated Valves.Initially Reported on 810224.Motor Operators Will Be Replaced.Also Reported Per Part 21 ML20069Q5161982-11-30030 November 1982 Seventh Interim Deficiency Rept Re Retrievable Info from Valve Tag Numbers.Initially Reported on 801212.Design Personnel Awaiting Approval of Design Change Request to Revise Drawings.Final Rept Will Be Issued by 830420 ML20027D3621982-10-27027 October 1982 Final Deficiency Rept Re Inadequate Electrical Equipment Documentation Concerning Environ Qualification.Initially Reported on 801024.Environ Design Criteria Developed.Program Will Be Developed to Track Equipment Qualification ML20063H8811982-08-27027 August 1982 Fourth Interim Deficiency Rept Re Undocumented Min Starting Voltage of 460-volt Motors.Initially Reported on 810413.Util Investigating Motor Starting Voltages Available During Accident Conditions at All Plants.Next Rept by 830805 ML20063H9471982-08-27027 August 1982 Supplemental Info to Fourth Revised Final Deficiency Rept Re Inadequate Transfer Canal & Cask Loading Area Spent Fuel Pool Gates.Initially Reported on 800501.Intermediate Restraints Added to Meet Seismic Requirements ML20062D0751982-07-29029 July 1982 Revised Final Deficiency Rept Re Foam Seals in Mechanical Pipe Sleeves.Initially Reported on 810416.Study Indicated No Significant Impact of Seals on Pipe Stresses.Documents Will Be Developed for Sleeve Designers & Piping Analysts ML20055A0281982-07-0606 July 1982 Final Deficiency Rept Re Class IE Electrical Components for Essential Raw Cooling Water Traveling Screens,Initially Reported on 810518.Existing Motors Can Be Qualified to Meet Class IE Criteria.Documentation by 820901 ML20054G7161982-06-16016 June 1982 Final Deficiency Rept Re Potential for Inadvertent Boron Dilution Event at Cold or Hot Shutdown Conditions While on RHR Sys,Initially Reported on 800710.Westinghouse Preventive Operating Procedures Acceptable ML20053C1651982-05-18018 May 1982 Fourth Revised Final Deficiency Rept Re Spent Fuel Pool Gates,Initially Reported 800501.QA Aspects of Gate Seismic Integrity to Be Verified Through Evaluation of Insp & Repair Records,Certificates of Compliance or Testing ML20052C1551982-04-22022 April 1982 Final Deficiency Rept Re Problem of Foam Seals in Mechanical Pipe Sleeves,Initially Reported 810416.Foam Seal Study Conducted to Determine Foam Effect on Piping Stresses & Support Loads.Design Std Will Be Developed by 830331 ML20054B0161982-04-0707 April 1982 Sixth Interim Deficiency Rept Re Revised Drawings of QA Valves,Initially Reported 801212.Design Change Requested to Revise TVA Drawing Series 47A366 to Cross Ref Manufacturer Numbers.Next Rept by 821029 PLA-1032, Part 21 Rept Re Existence of Goldfish in Spray Pond, Initially Reported 820303.Goldfish Elimination Will Be Completed Prior to Summer 1982.Util Will Periodically Examine Pond to Preclude Reintroduction of Fish Population1982-03-0909 March 1982 Part 21 Rept Re Existence of Goldfish in Spray Pond, Initially Reported 820303.Goldfish Elimination Will Be Completed Prior to Summer 1982.Util Will Periodically Examine Pond to Preclude Reintroduction of Fish Population ML20071H5001982-02-19019 February 1982 Third Interim Deficiency Rept Re Class IE Electrical Components for Essential Raw Cooling Water Travelling Screens,Initially Reported 810518.Deficiency Still Under Analysis.Detailed Rept Will Be Submitted by 820604 ML20041D7001982-02-17017 February 1982 Fifth Interim Deficiency Rept Re Foam Seals in Mechanical Pipe Sleeves,Initially Reported 810416.Evaluation of Effects of Foam Seal on Pipe & on Seal Underway.Pipe Movement Data Compiled for Evaluation.Next Rept by 820402 ML20071H5171982-02-12012 February 1982 Revised Final Deficiency Rept Re Response to Severity Level IV Violation & Four Deficiencies.Suppl Rept Submitted on 810924.Emergency Operations Facility Replaced by Local Recovery Ctr PLA-1011, Final Deficiency Rept Re Limitorque Valve Operator Motor Shaft to Pinion Gear Keys,Initially Reported 810817 Per IE Info Notice 81-08.Affected Keys in Smb 3,4 & 5 Operators to Be Replaced & Design Change Package 552,Revision 1,issued1982-02-0404 February 1982 Final Deficiency Rept Re Limitorque Valve Operator Motor Shaft to Pinion Gear Keys,Initially Reported 810817 Per IE Info Notice 81-08.Affected Keys in Smb 3,4 & 5 Operators to Be Replaced & Design Change Package 552,Revision 1,issued ML20039D9641981-12-29029 December 1981 Revised Final Deficiency Rept Re Power Operated Relief Valves Operating Time,Initially Reported on 810424. Administrative Controls Will Be Provided to Preclude Overpressure Transients.Also Reportable Per 10CFR21 ML20069B5541981-12-14014 December 1981 Advises That Revision of 811204 Final Deficiency Rept Re Addl Level of Under or Overvoltage Protection,Initially Reported 810403,will Be Submitted to Conform to IE Procedures ML20038C7341981-12-0404 December 1981 Final Deficiency Rept Re Design of Addl Level of Under or Overvoltage Protection,Initially Reported on 810403.New Design & Tech Spec Changes,Incorporating Degraded Voltage Protection,Will Be Submitted for Review in Early 1982 1997-03-27
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000327/LER-1999-002-03, :on 990916,EDG Started as Result of Cable Being Damaged During Installation of Thermo-Lag for Kaowool Upgrade Project.Caused by Inadequate pre-job Briefing. Involved Individuals Were Counseled on Event1999-10-15015 October 1999
- on 990916,EDG Started as Result of Cable Being Damaged During Installation of Thermo-Lag for Kaowool Upgrade Project.Caused by Inadequate pre-job Briefing. Involved Individuals Were Counseled on Event
ML20217D2721999-10-12012 October 1999 Safety Evaluation Supporting Amends 248 & 239 to Licenses DPR-77 & DPR-79,respectively ML20217B3651999-10-0606 October 1999 Safety Evaluation Supporting Amends 247 & 238 to Licenses DPR-77 & DPR-79,respectively ML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20212A1841999-08-25025 August 1999 Errata Pages for Rev 0 of WCAP-15224, Analysis of Capsule Y from TVA Sequoyah Unit 1 Reactor Vessel Radiation Surveillance Program ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With 05000327/LER-1998-003-01, :on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status1999-05-27027 May 1999
- on 981109,Vital Inverter 1-IV Tripped.Caused by Failed Oscillator Board with Bad Solder Joint,Attributed to Mfg Defect.Replaced Component & Returned Inverter to Operable Status
05000327/LER-1999-001-04, :on 990415,exceedance of AOT Occurred Due to Failure of Centrifugal Charging Pump.Rotating Element Was Replaced,Testing Was Completed & Pump Was Returned to Svc1999-05-11011 May 1999
- on 990415,exceedance of AOT Occurred Due to Failure of Centrifugal Charging Pump.Rotating Element Was Replaced,Testing Was Completed & Pump Was Returned to Svc
ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206G3751999-05-0404 May 1999 Safety Evaluation Supporting Amends 244 & 235 to Licenses DPR-77 & DPR-79,respectively ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205N0361999-04-12012 April 1999 Safety Evaluation Supporting Amend 234 to License DPR-79 ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204E8211999-03-16016 March 1999 Safety Evaluation Supporting Amends 243 & 233 to Licenses DPR-77 & DPR-79,respectively ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20206U4331999-02-0909 February 1999 Safety Evaluation Supporting Amends 242 & 232 to Licenses DPR-77 & DPR-79,respectively ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With 05000327/LER-1998-004-02, :on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check1998-12-21021 December 1998
- on 981120,failure to Perform Surveillance within Required Time Interval,Was Determined.Caused by Leaking Vent Valve.Engineering Personnel Evaluated Alternative Methods for Performing Channel Check
05000327/LER-1998-003-04, :on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced1998-12-0909 December 1998
- on 981109,automatic Reactor Trip Occurred. Caused by Component in Bridge Circuit of Vital Inverter Failed.Inverter Bridge Circuit Replaced
ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20196C4091998-11-19019 November 1998 Safety Evaluation Supporting Amends 238 & 228 to Licenses DPR-77 & DPR-79,respectively ML20196B0231998-11-19019 November 1998 Safety Evaluation Supporting Amends 239 & 229 to Licenses DPR-77 & DPR-79,respectively 05000328/LER-1998-002-05, :on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure1998-11-10010 November 1998
- on 981016,turbine Trip Occurred Followed by Reactor Trip.Caused by Generator Lockout.Mod Being Evaluated to Physically Isolate Relays from Vibration of Transformers & Adding Two of Two Logic for Actuation of Sudden Pressure
ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With 05000328/LER-1998-001-05, :on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays1998-09-28028 September 1998
- on 980827,turbine Trip Occurred Followed by Reactor Trip.Caused by Failure of Sudden Pressure Relay on B Phase Main Transformer.Control Room Operators Responded & Removed,Inspected & Replaced Failed Relays
ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20238F2961998-08-28028 August 1998 Safety Evaluation Supporting Amends 235 & 225 to Licenses DPR-77 & DPR-79,respectively ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 05000327/LER-1998-002-03, :on 980716,inadequate Surveillance Testing Was Discovered.Caused by Misinterpretation of ANSI Standard. Revised Appropriate Procedures to Provide Required Guidance1998-08-14014 August 1998
- on 980716,inadequate Surveillance Testing Was Discovered.Caused by Misinterpretation of ANSI Standard. Revised Appropriate Procedures to Provide Required Guidance
ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept 1999-09-30
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TENNESSEE VALLEY AUTHORITY cq7 1
CHATTANOOGA TENNESSEE 37401 I// r
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400 Chestnut Street Tower II C;
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'Y.!!fi July 6, 1982 8
4g: 30 SQRD-50-328/81-40 U.S. Nuclear Regulatory Commission Region II Attn: James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
SEQUOYAH NUCLEAR PLANT UNIT 2 - CLASS 1E ELECTRICAL COMPONENTS FOR ERCW TRAVELING SCREENS - SQRD-50-328/81 FINAL REPORT The subject deficiency was initially reported to NRC-OIE Inspector R. V. Crlenjak on May 18, 1981 in accordance with 10 CFR 50 55(e) as NCR SQN NEB 8126. Our first, second and third interim reports were submitted on June 17, August 3, 1981 and February 19, 1982, respectively. Enclosed is our final report on the subject deficiency.
If you have any questions, please call R. H. Shell at FTS 858-2676.
Very truly yours, TENNESSEE VALLEY AUTHORITY t
L. M. Mills, Manager Nuclear Licensing Enclosure cc:
Mr. Richard C. DeYoung, Director (Enclosure) l Office of Inspection and Enforcement l
U.S. Nuclear Regulatory Commission Washington, DC 20555 I
TE Af 8207150403 020706 i
PDR ADOCK 05000328 PDR S
l
SEQUOYAH NUCLEAR PLANT UNIT 2 CLASS 1E ELECTRICRL COMPONENTS FOR ERCW TRAVELING SCREENS 10 CFR 50.55(e) i NCR SQN NEB 8126 FINAL REPORT l
Description of Deficiency Electrical components required for the operation of the ERCW traveling screens are not Class 1E.
FSAR section 9.2.2 states that the screens are required for operation of the ERCW system. All electrical components essential to operation of the ERCW system are required to be Class 1E (IEEE Std. 308). This deficiency occurred because either a failure to specify that this equipment be Class 1E during preparation of procurement documents or to the unavailability of qualified equipment.
Safety Implications Electrical and control equipment associated with the ERCW traveling screens could fail and result in the screens not traveling as required.
This failure to travel could result in the screens becoming clogged and I
engineering safety features not being provided with cooling water. This condition could result in multiple failure of safety-related systems,
{
thus endangering the safe operation of the plant.
Corrective Action TVA had previously evaluated the electrical components for the ERCW traveling screens and determined that the following components were not designed and procured as Class 1E.
(1) Differential level diaphragms (2) Low speed detector switches (3) Traveling screen drive motors The final corrective actions will be as follows:
(1) TVA has reevaluated the differential level diaphragm and associated components and determined that its electrical components are Class 1E.
Certain mechanical components associated with the differential level detection system cannot be seismically qualified. However, they have been installed in a fail safe operation. Therefore, these components will not need to be replaced.
i (2) For the low speed detector switches, TVA has performed a failure I
evaluation and determined that the failure mode of these components could result in the failure of the circuit feeding the drive motors.
In order to prevent this type of failure, TVA will rewire the low speed detector switches so that their failure will not affect the operation of the screen drive motors. If a low speed detector switch was to fail and the traveling water screen became inoperable and if debris were to collect on the traveling screens, the i
differential level detection system would detect a flow restriction and alert the main control room. Work will be completed before startup following the end of the first refueling outage.
(3) The traveling water screens drive motors were not initially designed and procured as Class 1E.
Contact with the manufacturer has g
revealed that the existing motors can be qualified to meet Class 1E criteria. Therefore, the existing drive motors will be reclassified as Class 1E and appropriate documentation obtained from the manufacturer by September 1, 1982.
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