ML19347D967
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| ML19347D967 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/07/1981 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, SQRD-50-328-81, NUDOCS 8104140539 | |
| Download: ML19347D967 (1) | |
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|---|---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20210E3591997-03-27027 March 1997
[Table view]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. 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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. 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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 ML20042A5521982-03-0909 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 ML20040H5531982-02-0404 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 Category:TEXT-SAFETY REPORT MONTHYEARML20212J6311999-10-0101 October 1999
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Text
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TENNE 35EE VALLEY AUTHCo '
c . - a sec n T nessc 27, 400 Chestnut Street Tower II April 7, 1981
?QRD-50-328/81-09 Mr. James . O'Reilly, Director Office of I tepeation and Enforcement U.S. Nuclear % gulatory Cosmiission Region II - Sui 3100 101 Marietta St t Atlanta, Georgia 303
Dear Mr. O'Reilly:
SEQUOYAH NUCLEAR PLANT UNIT 2 - STEEL CONTAINME;NT PENETRATION ASSEMBLY -
SQRD-50-328/81 FINAL REPORT The subject deficiency was initially reported to NRC-0IE Inspector F. Cantrell en December 19, 1980, in accordance with 10 CFR $0.55(e) as NCR SQN CEB 8041.
An interim report was submitted on January 19, 1981.
Enclosed is our final mport.
If you have any questions, please get in touch with D. L. Lambert at FTS 857-2581.
Very truly yours, TENNESSEE VALLEY AIT!HORITY L. M. Mills, Manager Nuclear Regulation and Safety Enclosurw cc: Mr. Victor Stello, Director (Enclosure),v/
Office of Inspection and Enforcement l l U.S. Nuclear Regulatory Constissian washir.gton, DC 20555 30/7
.5 I(
i 0104140539 5-
,a k ENCLOSURE SEQUOYAH NUCLEAR PLANT UNIT 2 STEEL CONTAINMENT PENETRATION ASSEMBLY SQRD-50-328/81-09 10CFR50.55(e)
FINAL REPORT Description of Deficiency The residual heat removal (RHR), main steam, and main feedwater pipes penetrate the steel containment vessel.(SCV) by means of a free-floating bellows penetration assembly. Maximum internal pressure inside the SCV after a loss-of-coolant accident (LOCA) is 12 lbs/in2 . The axial load due to high containment pressure on the effective area of the SCV penetration opening was not considered in the RHR, main steam, and main feedwater piping analysis.
Safety Implications The results of TVA's reanalysis of the affected piping revealed that no design modifications are required and that the present design configuration is adequate to carry all loads. Therefore, this conditions could not have adversely affected the safety of the plant.
Corrective Action TVA reanalyzed the affected piping in order to determine if the present design of the penetration assemblies and pipe rupture restraints was adequate to carry all loads. Resulting piping stresses and support design loads were evaluated and found to be acceptable. Therefore, no design modifications are mquired.
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