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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 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
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 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 ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept 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 ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage 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 ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With 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 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 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 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 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 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 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 ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept ML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 ML20199F8531998-01-13013 January 1998 ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation 1999-09-30
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TENNESSEE VALLEY ' UTHCRITY CH A TT ANOC S A *E *4 *J E ss. 2742' 400 Chestnut Street Tower II )
November 21, 1980 ,y
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Mr. James P. 'Reilly, Director p f -3 1 ,D 3 'O y Office of Ins tion and Enforcement '
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d U.S. Nuclear R tory Commission Regia II - Suite 00 101 Marietta Street Atlanta, Georgia 303
Dear Mr. O'Reilly:
SEQUOYAH NUCLEAR PLANT UNIT 2 - ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPNENT - NCR'S SQN EEB 8009 THROUGH 8015 AND 8019 - FOURTH INTERIM REPORT The subject deficiency was initially reported to NRC-0IE Inspector C. R. McFarland on June 16, 1980, in accordance with 10 CFR 50.55(e).
Interia m ports were submitted on July 16, August 11, and September 19, 1980. Enclosed is our fourth interim report. We expect to submit our next report by February 25, 1981.
If you have any questions, please get in touch with D. L. Lambert at FTS 857-2581.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Regulation and Safety
, Enclosure /
oo: Mr. Victor Stello, Director (Enclosure)V Office of Inspection and Enforcement" U.S. Nuclear Regulatory Commission I Washington, DC 20555 So/7
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ENCLOSURE SEQUOYAH NUCLEAR PLANT UNIT 2 ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT NCR'S SQN EEB 8009 THROUGH 8015 AND 8019 /
10 CFR 50.55(e) _
FOURTH INTERIM REPORT /
Description of Deficiency The following NCR's pertain to Class IE components for which documenta-tion has not been located to establish their ability to operate in the ambient conditions (temperature, humidity, radiation, and/or pressure) for which they are required.
SQN EEB 8009 - Pressure Switches PS-30-46 A&B, -47 A&B, and -48 A&B -
l These pressure switches are required to operate during l a LOCA at temperatures of 135*F and radiation doses of 7
5 x 10 rads.
I SQN EEB 8010 - Class IE Motors - These motors are required to operate
! in various normal and post-accident environments. See i Attachment 1A.
SQN EEB 8011 - Solenoid Valve FSV-70 This solenoid valve must operate gt a temperature of 202*F, a radiation dose of 3.6 x 10 rads, and a relative humidity of 100 percent.
l SQN EEB S012 - Solenoid Valves PSV-65-81 and PSV-65 These solenoid valves ars, required to operate in an environment of 150*F and 7 x 10' rads.
SQNEEB8013-I/PTransducersPDM-65-80andPDM-65-82-Thesetransjucers --- -
must operate in a post-accident environment of 7 x 10 rads.
SQN EEB 8014 - Portions of the Hydrogen Monitoring System mounted in the Annulus These portions are reguired to operate in an
- _ environment of 150*F and 7-x 10 rads.
l SQN EEB 8015 - DC Vent Fan Motor and Starter - This motor and starter are l
requiregtooperateinanenvironmentof104*Fandless than 10 rads.
Auxiliary Air Compressor Motor and Instrument Rack is -
! required to operate in an environment of 115*F, a relative hugidity of 100 percent, and radiation dose of less than 10 rads.
Pressurizer Heater Transformers are required to operate in a post-accident environment of 115*F, a relative hgmidity of 100 percent, and radiation dose of less chan 10 rads.
t Pressurizer Heater Distribution Cabinet CVRL is required to gperate in an environment of 115'F, a radiation dose of less than 10 rads, and a relative humidity of 100 percent.
Turbine-Driven Auxiliary Feedwater Teugerature Instrument. Panel is requiredtooperateinanenvironmentof150*F,agelativehumidity of 90 percent and a radiation dose of isss than 10 rads.
A/C Circulation Pump Motors El.734 are requi, red to operate in an pogt-accident environment of 115'F, a radiation dose of less than 10 rads, and a relative humidity of 100 percent.
Solenoid Valve FSV-18-12 is required to operate in an envircament of 110*F, g relative humidity of 100 percent, and a radiation dose of 10 rads.
Rotark MOV Model 7A/lRP is required to perate in a post-accident environment of 115'F, a relati e humidity of 100 percent, and a 3
radiation dose of less than 10 rads.
6900V RCP PT and Relay 3oards 1 and 2 are required to operate in anenvironmentof115"F,arelatgvehumidityof100 percent, and a radiation dose of less than 10 rads.
SQN EEB 8019 - Class IE electrical cables, which are located in areas subjected to high energy 'line breaks outside primary con'.ainment, are not qualified to the accident environment profiles defined- for this area.
Safety Implications These components perform critical safety functions that are necessary for the safe operation of the plant. Failure of one or more of these components during a LOCA condition could adversely affect the safety of the p? ant. Without the required environmental documen'.ation, it is not known under what conditions one or more of these systems might fail.
Corrective Action (Final Report on the Following Items)
SQN EEB 8009 - The unqualified pressure switches on this NCR have been replaced wil.i: envittnmentally qualified switches.
SQN EEB 8010 - Class IE motors at coatracts 72C38-92802, 72C38-83537, 76K35-83673-1, and 7.1C30-92695 have been qualified for a period of 5 years; contract 73C38-83532 for 2.5 years; and 71C30-92646 for 40 years. Replacement motors will be purchased and installed before the end of these time spans.
Motors en contract 72C33-92730 have been determined not to be Class IE equipment.
SQN EEB 8011 - TVA has reevaluated the function of the solenoid valve and
- has determined that it is not safety related.
SQN EEB 8012 - The solenoid valves have been esplaced with qualified valves for units 1 and 2.
SCN EEB 8013 - The I/P transducers will be relocated from the containment annulus to an area where they are qcalified.
i ,
SQN EB 8019 - TVA has determined that the low current loads on the cables will allow them to fbnction in the adverse environment without experiencing cable insulation damage. The cables will, therefore, not require replacement.
Interim Progress SQN EB 8014 - An identical hydrogen monitor from Watts Bar unit 2 is being tested. The test results will not be available until December 1, 1980.
SQN EB 8015 - TVA is still gathering enviror. mental qualification docu-mentation on these maponents from their vendors.
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e ATTACllMENT'IA .
SEQUOYAll CLASS IE MOTORS ON NONC011FORilANCE REPORT SQN EEB 8010 Contract Component Integ. Accident 40 Year Enviros ent. Spec. Require.
Dose 1 Year Normal Dose Temp /RH Ambient / Rise Rads Rads C' / % C* C*
6 72C38-92802 Emer. Gas Treatment AllU Neg 10 43.3 30-80 40 90 72C38-92802 Spent Fuel Pit Pump AllU Neg 10 43.3 30-80 40 90 6 6 90 72C38-92802' . RilR Pump Cooler 7.5 x 10 10 43.3 30-80 40 6 6 72C38-92802- SIS Pump Cooler AHU 5.6 x 10 10 43.3 30-80 40 90 6 40 90 72C38-92802 Cent. Charing Pump Cooler AllU 6.6 x 10 10 43.3 30-80 6 43,3 80 72538-92802 AFW & Boric Acid P6mp AllU Neg 10 40 90-72C38-92802 CCS Pump & AFW Pump AHU Neg 10 43.3 30-80 40 90 72C38-92802 Pipe Chase AllU Neg 10 43.3 30 40 90
' 6 . 6 72C38-92802 . Cont. Spray Pump 6 0 7.8 x 10 10 43.3 30-80 40 90
< I- 72C38-92802 Penetration Roon Coolers Neg 10 43.3 30-80 40 90 72C38-83527 A'ux. Bldg. Gas Treat. Fan Neg 10 43.3 30-80 '40 90 l
6 72C38-83527 Emer. Gas Treat. Fan- Neg 10 43.3 30-80 40 90 0
76K35-83673-1480-Volt Board Room AllU . Neg 10 46.1 30-80 40 90 I 71C30-92695 Comp. Cooling Water Pumps Neg Neg 46.1 30-80 84 0 70 73C38-83532 Comp. Cooling Water Booster Pumps Neg Neg 46.1 30-80 40 90 0 6 71C30-92646 Cont. Spray. Pumps 7.8 x 10 10 43.3 30-80 40 90 72C33-92730 Lower Compartment AHU ---
2 x 10 49.8 98 65 90 72C33-92730 CRD Mechanism AllU --- 2 x 10 48.8- 98 65 90 s
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