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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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Mr. James P. O'Reilly, Regional Administrator
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Dear Mr. O'Reilly:
SEQUOYAH NUCLEAR PLANT UNIT 2 - FOAM SEALS IN MECHANICAL PIPE SLEEVES -
SQRD-50-328/81 FINAL REPORT The subject deficiency was initially reported to NRC-0IE Inspector R. V. Crlenjak on April 16, 1981 in accordance with 10 CFR 50.55(e) as NCR CEB 8108. Interim reports were submitted on April 23, June 30, September 18 and November 18, 1981 and February 17, 1982. Enclosed is our final report.
If you have any questions, please get in touch with R. H. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Regulation and Safety Enclosure cc:
Mr. Richard C. DeYoung, Director (Enclosure)
Office of Inspection and Enforcement i
U.S. Nuclear Regulatory Commission Washington, DC 20555 l
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ENCLOSURE SEQUOYAH NUCLEAR PLANT UNIT 2 F0AM SEALS IN MECHANICAL PIPE SLEEVES NCR CEB 8108 SQRD-50-328/81-30 10 CFR 50.55(e)
FINAL REPORT Description of Deficiency Some wall penetration piping sleeves shown on TVA drawing series 47W470 and 47W471 have rigorously analyzed safety-related piping routed through them. Silicone sealants are provided between the pipe and sleeve at certain locations as shown on TVA drawing series 47W472. These seals had not been considered by the piping analyst for most cases and thereby could result in increasec in pipe stresses and support loads for some situations. The maximum pipe movements at the sleeves may cause failure of the sealant to perform its intended design function as a pressure and/or fire protection seal.
There were two causes for this nonconformance:
1.
The drawings indicating the sleeve sealing arrangement were not squadchecked to the piping analysts--a lack of identification and control of interfaces.
2.
There was no design criteria or other documentation to address the consideration of the foam sleeve seals--inadequate procedures to control the analyst's activities.
_ Safety Implication TVA has analyzed this deficiency and determined that there are no loading combinations of design conditions which would render the affected systems unqualified. However, the fire protection criteria of the plant could be compromised due to the separation of the foam seals from the sleeves where large movements are involved which could adversely affect the safe operation of the plant.
Corrective Action The original NCR included loss of water and radiation sealing capabilities as a possible concern. After investigation it was determined that the seals in question are not required to perform any water sealing or radiation sealing function.
To determine the effect of the silicone foam seal material, a previous test program which tested a single sleeve / pipe combination was reviewed. Soring constants based on this previous test program gave what was considered to be overly conservative estimates of loading, and, additionally, the program did not test a range of pipe / sleeve sizes.
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t Page 2 Thus, a second test program was developed to supplement the original serics of tests. The second test program tested an assortment of sleeve and pipe size combinations with the pipe centered in the sleeve in some of the test specimens and offset in other specimens. Offsets evaluated correspond to those reported under NRC-0IE bulletin 79-14.
The test procedure and data recorded will be documented in Civil Engineering Branch report 82-2.
Based on the test data, modeling techniques to represent the effect of the sleeve seal on the pipe in our rigorous analysis have been developed. The modeling techniques account for the foam's resistance to lateral and axial translation and axial rotation. The effect of the foam is greatest where there are large pipe movements. The foam will tend to dampen out dynamic motions and thus is beneficial; however, where large thermal growth or anchor movement growth occurs, the foam would increase the support loads and piping stresses. Two areas were identified for investigation. The first area was the piping attached to the steel containment vessel and penetrating the shield building wall. This piping is subject to large anchor point movements caused by the steel containment vessel responding to design basis accident conditions. The second area of investigation was wher g
a long run of straight pipe makes a 90 turn and runs through a wall and is subjected to high temperatures. In this case the thermal growth drives the pipe laterally against the foam in the sleeve.
To investigate the piping penetrating the shield-building wall, six problems were identified where the sleeve inside diameter to pipe outside diameter ratio is at a minimum relative to pipe movements.
This results in the highest compression of the foam in the sleeves and creates the most significant effect on the piping system. Spring rates based on the initial test program caused some difficulty with support loads in two of the problems. These two problems were redone with the revised spring rates based on the second test program. Based on the revised spring rates, the changes in piping stresses and support loads were insignificant requiring no redesign of the supports or reconfiguration of the piping.
To investigate the sleeves subjected to piping movement due to large 1
thermal growth, an extensive review of Sequoyah Nuclear Plant analysis problems produced only four potential problem locations. The additional loading caused by the thermal growth was determined and was found to have an insignificant effect on piping stresses and support loads.
The conclusion of the study on the effects of the foam sleeve seals on the piping stresses was that no significant impact would be expected.
HowcVer, in current and future piping analysis, the effect of the foam on the piping stresses and supports will be determined and accounted for to assure the accuracy of the analysis. The conclusions of the foam seal study and the modeling techniques to be used in accounting for the foam's effect on the piping stresses and support loads will be documented in CEB report 82-9
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During the second test program the silicone foam on some of the samples separated from some of the sleeve piping. Based on these occurrences it was determined that fireproof, airtight boots would be added to the foam sleeve seals where there are large movements to ensure that the seal is maintained.
To prevent future reoccurrence of these problems, two procedural documents will be developed to guide the sleeve designers and piping analysts. A design standard will be developed by March 31, 1983, to give guidance to the sleeve designers. The design standard will set forth required design considerations and procedures including a requirement that design documents specifying sleeve sizes and sleeve sealing be squadchecked to the groups affected by the design of the sleeve and sleeve seal. This will include the persons responsible for reviewing the fire protection capability and the air sealing capacity and, where rigorous analysis of the piping is performed, the piping analyst. Guidance to the piping analysts will be provided by a checklist that will be required to be filled out for each analysis l
problem. This checklist, committed to as part of the resolution to 3-NCR WBNCEB8112, will be appended to the Sequoyah design criteria SQN-DC-V-13 3.and_will include a requirement that the checker of the rigorous piping analysis problem review the sleeve sealing arrangement and assure that it has been properly modeled into the analysis. This checklist will be provided by June 30, 1982.
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