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| ; DEFECTIVE MCGRAW-EDISON TEMPERATURE DETECTION t CONTROLLERS IN THE STANDBYGAS TREATMENT SYSTEM 10 CFR 50.55(e) REPORT NO. l (FINAL) | | ; DEFECTIVE MCGRAW-EDISON TEMPERATURE DETECTION t CONTROLLERS IN THE STANDBYGAS TREATMENT SYSTEM 10 CFR 50.55(e) REPORT NO. l (FINAL) |
| NCR'S HNP-A-100 AND PBNP-091 On May'14, 1980, TVA informed NRC-0IE, Region II, Inspector T. E. f Burdette of a reportable deficiency under 10 CFR Part 50.55(e) involving l defects in McGraw-Edison electronic temperature detection controllers in l the Standby Gas Treatment System (SGTS) for the Hartsville and Phipps l Bend Nuclear Plants. This deficiency was also reported under 10 CFR ! | | NCR'S HNP-A-100 AND PBNP-091 On May'14, 1980, TVA informed NRC-0IE, Region II, Inspector T. E. f Burdette of a reportable deficiency under 10 CFR Part 50.55(e) involving l defects in McGraw-Edison electronic temperature detection controllers in l the Standby Gas Treatment System (SGTS) for the Hartsville and Phipps l Bend Nuclear Plants. This deficiency was also reported under 10 CFR ! |
| Part 21 to NRC-0IE Region III on April 30, 1980, by CTI-Nuclear, l the STRIDE component supplier for the SGTS. This is the final report I on the deficiency. l Descrip* ton of Deficiency | | Part 21 to NRC-0IE Region III on April 30, 1980, by CTI-Nuclear, l the STRIDE component supplier for the SGTS. This is the final report I on the deficiency. l Descrip* ton of Deficiency TVA was informed by CTI-Nuclear, Cleveland, 0hio, who was previously informed by Edison Electronics Division of McGraw-Edison (Edison) i of Manchester, New Hampshire, that an electronic temperature detection controller (the same type as controllers supplied by Edison to CTI-Nuclear and by CTI-Nuclear to TVA) failed'in service and that other similar controllers ata ententially defective. |
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| | The potentially defective controllers are McGraw-Edison P/N 377-02831 4 and are integral parts of electronic control circuits for detecting high temperatures in the airstream, both upstream and downstream of vertical deep bed carbon adsorbers in the Hartsville and Phipps Bend SGTS. The controllers are also used as part of a control circuit for high temperature thermal cutout of electric air heaters in the same system. These controllers are used on CTI-Nuclear part numbers 4 |
| TVA was informed by CTI-Nuclear, Cleveland, 0hio, who was previously informed by Edison Electronics Division of McGraw-Edison (Edison) i of Manchester, New Hampshire, that an electronic temperature detection controller (the same type as controllers supplied by Edison to CTI-Nuclear and by CTI-Nuclear to TVA) failed'in service and that other similar controllers ata ententially defective. | |
| The potentially defective controllers are McGraw-Edison P/N 377-02831 4 and are integral parts of electronic control circuits for detecting | |
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| high temperatures in the airstream, both upstream and downstream of vertical deep bed carbon adsorbers in the Hartsville and Phipps Bend SGTS. The controllers are also used as part of a control circuit for high temperature thermal cutout of electric air heaters in the same system. These controllers are used on CTI-Nuclear part numbers 4 | |
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| D-31441 and D-31250. | | D-31441 and D-31250. |
| I-TVA SGTS housings (two per nuclear unit at Hartsville and Phipps Bend) each contain five potentially defective controllers (two each in the upstream and downstream high temperature detection panels, No. D-31441, and one in the high temperature cutout panel, No. D-31250). This represents a total of 60 potentially defective controllers, 40 at Harts-ville and 20 at Phipps Bend, in the SGTS equipment delivered to TVA. | | I-TVA SGTS housings (two per nuclear unit at Hartsville and Phipps Bend) each contain five potentially defective controllers (two each in the upstream and downstream high temperature detection panels, No. D-31441, and one in the high temperature cutout panel, No. D-31250). This represents a total of 60 potentially defective controllers, 40 at Harts-ville and 20 at Phipps Bend, in the SGTS equipment delivered to TVA. |
| j Edison attributes the only known failure to use of an acid flux solder j in sealing some of the controls during manufacture. Edison has concluded that there is no convenient method of determining in the field if the | | j Edison attributes the only known failure to use of an acid flux solder j in sealing some of the controls during manufacture. Edison has concluded that there is no convenient method of determining in the field if the control was sealed with acid flux solder. The acid flux reportedly could cause corrosion in the controller and result in failure. The mode of a failure is unpredictable; a failure could cause the controller to_ give _ erroneous indication such as (1) failing to open and not closing at an. alarm point, (2) failing closed and giving a false alarm, or (3) failing at some intermediate step and functioning inaccurately. , |
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| control was sealed with acid flux solder. The acid flux reportedly could cause corrosion in the controller and result in failure. The mode of a failure is unpredictable; a failure could cause the controller to_ give _ erroneous indication such as (1) failing to open and not closing at an. alarm point, (2) failing closed and giving a false alarm, or (3) failing at some intermediate step and functioning inaccurately. , | |
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| Safety Implications Failure of a controller in one of the manners described above could possibly cause or prevent. detection of, through a number of ways depending on which. controller failed and how it failed, loss of charcoal effectiveness through introduction of moisture or fire in the bed, thereby disabling at least one train of the SGTS. However, since other means are available to detect unnsual conditions in the SGTS system (e.g., radiation monitors and moisture detectors downstream of the charcoal beds) loss of one of the controllers may not lead to undesirable consequences. TVA concludes that this deficiency could have jeapordized the safety of operation of the plant. | | Safety Implications Failure of a controller in one of the manners described above could possibly cause or prevent. detection of, through a number of ways depending on which. controller failed and how it failed, loss of charcoal effectiveness through introduction of moisture or fire in the bed, thereby disabling at least one train of the SGTS. However, since other means are available to detect unnsual conditions in the SGTS system (e.g., radiation monitors and moisture detectors downstream of the charcoal beds) loss of one of the controllers may not lead to undesirable consequences. TVA concludes that this deficiency could have jeapordized the safety of operation of the plant. |
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| * controllers will be shipped from TVA sites back to CTI-Nuclear by July 31, 1980. | | * controllers will be shipped from TVA sites back to CTI-Nuclear by July 31, 1980. |
| Means Taken to Prevent Recurrence Edison has verbally indicated that they have informed all of their employees | | Means Taken to Prevent Recurrence Edison has verbally indicated that they have informed all of their employees |
| , who assemble electronic components of the harmful effects of acid flux | | , who assemble electronic components of the harmful effects of acid flux on electronic circuits. These individuals have also been instructed not to use acid flux in any operation. |
| * on electronic circuits. These individuals have also been instructed not to use acid flux in any operation.
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Final Deficiency Rept Re Defective Temp Detection Controller in Standby Gas Treatment Sys.Electronic Temp Detection Controller Failed in Svc.Caused by Acid Flux Solder Sealing Controls.Controllers to Be Replaced W/Certified ControllersML19324A085 |
Person / Time |
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Site: |
Hartsville, Phipps Bend ![Tennessee Valley Authority icon.png](/w/images/c/ce/Tennessee_Valley_Authority_icon.png) |
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Issue date: |
06/13/1980 |
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From: |
TENNESSEE VALLEY AUTHORITY |
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Shared Package |
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ML19324A068 |
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References |
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NCR-HNP-A-100, NCR-PBNP-091, NUDOCS 8006200454 |
Download: ML19324A085 (2) |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating ML20154J4101988-05-12012 May 1988 Addendum 1 to Supplemental Part 21 Rept 145 Re Potential Problem w/F-573-156 Pressure Sensor/Lube Oil Trip.Initially Reported on 880429.Addl 1-1/8-inch Diameter W/Deep Counterbone in Pressure Head Added to Activate Valve ML20153B6191988-04-29029 April 1988 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generators Supplied to Utils.Recommends Return of Subj Components in Onsite Warehouse Storage & Suggests Surveillance of Devices Already Installed ML20205F6141986-08-13013 August 1986 Part 21 Rept Re Connecting Rod Bolts for Dsrv Engines.Listed Procedures Recommended for Next Connecting Rod Insp, Including Replacement of Bolts Due to Cracked Threads & Large Grooves & Galls in Threads ML20206U0591986-07-0202 July 1986 Part 21 Rept Re Potential Defect in Component of Dsrv Standby Diesel Generators,Involving Problem W/Fastening of Engine Connecting Rod Assembly Which Could Result in Engine Nonavailability.Procedure Will Be Issued by 860718 ML20141A1081986-03-31031 March 1986 Part 21 Rept 134 Re Potential Defect in K-1 Relay in Generator Voltage Regulator.Initially Reported on 860219. Corrective Action Must Take Into Account Equipment Operating Range of 100-137.5-volt Dc ML20154N3431986-03-10010 March 1986 Initial Part 21 Rept 135 Re Potential Problem W/Lube Oil Sump Tank Foot Valve of Dsrv Standby Diesel Generator for Facilities.Cause Not Determined.Recommends Utils Inspect Condition of Foot Valve Liners & Notify Tdi of Findings ML20153G1021986-02-19019 February 1986 Part 21 Rept Re Potential Defect in K-1 Relays of Dsr or Dsrv Standby Diesel Generators Mfg by Gould/Ite.Relays Have Incorrect Voltage Range.Dc Voltage Source or Voltage Regulator Circuitry Requires Mod ML20198C4981985-11-0606 November 1985 Part 21 Rept Re Potential Defect in Dsr or Dsrv Standby Diesel Generator Intake & Exhaust Valve Springs Mfg by Betts Spring Co.Users Recommended to Inspect Engines for Broken Springs & Identify Original Mfg ML20084G3531984-04-19019 April 1984 Final Deficiency Rept Re Pacific Scientific Co Shock Arrestor Capstan Spring Tang.Initially Reported on 831013. Bellefonte Snubbers Will Be Replaced & Hartsville Snubbers Returned to Vendor for Repair.Springs Subj to Insp ML20087J6661984-03-0808 March 1984 Followup Part 21 Rept Re Nuclear Valve/Actuator Stroking Time Possibly Lengthened Beyond 15 When Using hydrocarbon-based Lubricants.Ltrs to Affected Utils Encl ML20081C0171984-03-0101 March 1984 First Interim Deficiency Rept Re Loose Drive Hubs on Overspeed Governor Drive Shaft on Transamerica Delaval,Inc Diesels.Initially Reported on 840203.Svc Info Memo Being Reviewed for Approval.Also Reportable Per Part 21 ML20079N5121984-01-23023 January 1984 Final Deficiency Rept Re Delaval Problem W/Starting Air Valve Assembly on Standby Diesels.Initially Reported on 821201.Capscrews Replaced Per Approved Procedure & Drawings Revised to Reflect Shorter Length ML20083H1921984-01-0505 January 1984 First Interim Deficiency Rept Re Transamerica Delaval,Inc QA Program.Initially Reported on 831206.Final Configuration for Control Cabinet Indicates Drawing Revs K,L & M Not Incorporated.Also Reportable Per Part 21 ML20083E1981983-12-20020 December 1983 First Interim Deficiency Rept Re Fuel Oil Line Rupture in Transamerica Delaval,Inc Generator.Initially Reported on 831121.Const Activities Deferred for Hartsville Units 1 & 2. Next Rept Expected by 840413.Also Reported Per Part 21 ML20078B3811983-09-0606 September 1983 Part 21 Rept Re Matrix Actuator Model 33122-SR 80.Mounting Bolts Loosened & Spring Return Cylinder Began to Separate from Ctr Body of Actuator.Investigation Being Conducted by Xomox Corp 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 ML20083L9751983-05-27027 May 1983 Part 21 Rept Re Failure of Circuit Breakers During Environ Testing.Test Results Indicate That Temp Sensitivity Problem May Be Generic to All Ite Imperial Corp thermal-magnetic Circuit Breakers Calibr for 40 C Svc ML20076H1601983-05-23023 May 1983 Pt 21 Rept Re Potential Defect in Transmitter Mfg by Rosemount,Inc Used in Control Sys Components Furnished to Listed Plants.All Components Involved Retrofitted W/New Circuit Boards.Matter Closed ML20074A2041983-04-26026 April 1983 Interim Deficiency Rept Re Misapplication of Ite Gould Circuit Breakers in post-LOCA Hydrogen Recombiners Supplied by Rockwell Intl.Initially Reported on 830328.Matter Under Investigation.Final Rept by 830808.Reported Per Part 21 ML20069K6811983-04-18018 April 1983 First Interim Deficiency Rept Re Pipe Support Spacing Utilizing Alternate Criteria.Initially Reported on 830317. Investigation Postponed Until Design & Const Resumed ML20073J8051983-04-12012 April 1983 Third Interim Deficiency Rept Re Nonconservative Calculation Method for General Const Spec G-32 Violations.Initially Reported on 820528.Design Std Being Revised to Clarify Use of Factors of Safety in DS-C6.1 ML20073P1281983-04-0808 April 1983 Second Interim Deficiency Rept Re Problem W/Delaval Starting Air Valve Assembly on Standby Diesels.Initially Reported on 821201.Util Continuing to Attempt to Acquire Necessary Info from Transamerica Delaval,Inc.Also Reported Per Part 21 ML20072Q9571983-03-28028 March 1983 First Interim Deficiency Rept Re Failure of Util Div of Engineering Design to Provide Bolt Tightening Requirements to Div of Const.Initially Reported on 830228.Const Deferred. Rept to Be Submitted When Const Decision Made ML20072R3291983-03-28028 March 1983 Interim Deficiency Rept 1 Re CF Braun Documentation Control Program Failure to Monitor Closeout of Final Design Change Control Documents.Initially Reported on 830302.Final Rept Due Upon Commencement of Const.Also Reportable Per Part 21 ML20074A2221983-03-11011 March 1983 Part 21 Rept Re Failure of post-LOCA Hydrogen Recombiner Component During IEEE-323 Qualification Program.Circuit Breaker Not Properly Selected for Specific Application.Plant Operators Notified of Deviation ML20028G0821983-01-31031 January 1983 Final Deficiency Rept Re Itt Grinnell Failure to Use Proper Testing Methods.Initially Reported on 810304.Spool Pieces re-examined Per ASME Section III,1974 Edition,Winter Addenda 1975 Code.Condition No Longer Reportable Per 10CFR50.55(e) ML20083M6711983-01-24024 January 1983 First Interim Deficiency Rept Re Potential Deterioration of Isoprene Gaskets on Standby Diesel Generator.Initially Reported on 821217.Transamerica Delaval,Inc Changed Matl for Drive Element to Neoprene.Also Reportable Per Part 21 ML20083M6651983-01-24024 January 1983 First Interim Deficiency Rept Re Residual Stress on Diesel Generator Engine Piston Skirt Castings.Initially Reported on 821215.Removal of Piston Skirt for Insp Deferred Until Restart of Design & Const.Also Reportable Per Part 21 ML20028C2481982-12-30030 December 1982 First Interim Deficiency Rept Re Insufficient Length of Starting Air Valve Assembly Capscrews.Initially Reported on 821201.Transamerica Delaval,Inc Changed Designed Length of Capscrew.Next Rept by 830415.Also Reportable Per Part 21 ML20070F0121982-12-13013 December 1982 Final Deficiency Rept Re Atlas QA Documentation on Auxiliary & Fuel Bldg Structural Steel.Initially Reported on 811113. QA Hold Placed on Suspect Items Until Further Testing Performed.Also Reportable Under Part 21 ML20028A4891982-11-0909 November 1982 Final Deficiency Rept Re Storage & Preventive Maint Program Deficiencies.Initially Reported on 821007.Pipe Caps Replaced,Piping Placed on Support,Tanks Moved to Inside Storage in Upright Position & Conditions & Program Reviewed ML20065R3701982-10-14014 October 1982 Interim Deficiency Rept Re Deferral of Const Activities. Initially Reported on 820623.Commitments Made in Rept,Audit Findings & Response to Violations Deferred Until Restart of Design & Const ML20027B8451982-09-20020 September 1982 First Interim Deficiency Rept Re QA Deficiencies on Allis- Chalmers Butterfly Valves.Initially Reported on 820823.Const Activities Deferred.Final Rept Will Be Submitted After Final Decision Re Completion or Cancellation of Project ML20063L3721982-09-0202 September 1982 First Interim Deficiency Rept Re Failure of Kerotest Valves to Meet Seismic Criteria.Initially Reported on 820804. Negotiations Underway W/Contractor for Return of Valves. Const Activities Deferred.Also Reportable Per Part 21 ML20055A0731982-07-0707 July 1982 First Interim Deficiency Rept Re Nonconformance in Intake Pumping Station Door & Hatch Design,Initially Reported 820604.Final Rept Will Not Be Issued Until Decision to Resume Facility Const Reached ML20055A0791982-07-0606 July 1982 First Interim Deficiency Rept Re Possible Installation of Bolt Anchors in Grant Areas,Initially Reported 820610. Investigation Postponed Until Const Resumed ML20054N0821982-07-0101 July 1982 Final Deficiency Rept Re Excessive Stress on Spray Pond Supply & Bypass Headers,Initially Reported on 820218. Piping Layout Revised & Drawings Revised/Reissued.Seismic Analysis Complete & Isometrics Issued ML20054J9111982-06-23023 June 1982 Part 21 Rept Re Potential Defect in Couplings Drive Element of Dsrv or Dsr Standby Diesel Generator.Affected Licensees Will Be Notified No Later than 820715 ML20054K1531982-06-23023 June 1982 Informs That Final Deficiency Repts for Listed Nonconformances Will Not Be Submitted Until Final Decision Is Made Re Const of Projects ML20054H6821982-06-18018 June 1982 Part 21 Rept Re Pneumatic Actuator Yoke Failure.List of Other Projects W/Similar Equipment Encl ML20054G1121982-06-11011 June 1982 Fourth Interim Deficiency Rept Re Link Rod assembly-Delaval Diesels.Due to Const Deferment Final Deficiency Rept Will Not Be Issued Pending Final Decision on Future of Projects. Also Reportable Per Part 21 ML20054E4111982-06-0101 June 1982 Fourth Interim Deficiency Rept Re Bethlehem Steel Co Galvanized A325 Bolts,Initially Reported on 811029.Const Activities Deferred Until Sufficient Info Indicates Whether Project Should Be Completed or Canceled ML20054E4081982-06-0101 June 1982 First Interim Deficiency Rept Re Split in Biological Shield Wall,Initially Reported on 820429.Investigation Postponed Until Const Activities for Project Resume.No Final Rept Will Be Submitted Until Decision Made Re Continuation of Const ML20053E1201982-05-28028 May 1982 Second Interim Deficiency Rept Re Check Valve Leak in Air Start Sys of Standby Diesel Generators,Initially Reported 820209.Evaluation by Vendor Underway.Also Reported Per Part 21 ML20052A6071982-04-19019 April 1982 Suppl to Final Deficiency Rept Re Standby Gas Treatment Sys Charcoal Absorber,Initially Reported 800508.Util Unable to Meet Corrective Action Completion Date in 811209 Final Rept Due to Deferral of Const.Also Reported Per Part 21 ML20052A5981982-04-12012 April 1982 Final Deficiency Rept Re Incorrect Orifice Size in RHR Discharge Line Indicated on Fabrication Spec,Initially Reported 820304.Typographical Error Corrected Before Hardware Mfg ML20054B1101982-04-0202 April 1982 Fifth Interim Deficiency Rept Re Review of Purchase Request Forms Initiated by Const,Initially Reported 810520.Util in Process of Analyzing Deficiencies.Next Rept Expected by 820715 ML20054C4691982-04-0101 April 1982 Part 21 Rept Re Hma Relays W/Contact Leads Not Fully Insulated,Initially Reported 810708.No Operating BWRs Utilize Subj Hma Relays.All Potential Problems Will Be Corrected Before Startup 1993-12-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating ML20154J4101988-05-12012 May 1988 Addendum 1 to Supplemental Part 21 Rept 145 Re Potential Problem w/F-573-156 Pressure Sensor/Lube Oil Trip.Initially Reported on 880429.Addl 1-1/8-inch Diameter W/Deep Counterbone in Pressure Head Added to Activate Valve ML20153B6191988-04-29029 April 1988 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generators Supplied to Utils.Recommends Return of Subj Components in Onsite Warehouse Storage & Suggests Surveillance of Devices Already Installed ML20205F6141986-08-13013 August 1986 Part 21 Rept Re Connecting Rod Bolts for Dsrv Engines.Listed Procedures Recommended for Next Connecting Rod Insp, Including Replacement of Bolts Due to Cracked Threads & Large Grooves & Galls in Threads ML20206U0591986-07-0202 July 1986 Part 21 Rept Re Potential Defect in Component of Dsrv Standby Diesel Generators,Involving Problem W/Fastening of Engine Connecting Rod Assembly Which Could Result in Engine Nonavailability.Procedure Will Be Issued by 860718 ML20141A1081986-03-31031 March 1986 Part 21 Rept 134 Re Potential Defect in K-1 Relay in Generator Voltage Regulator.Initially Reported on 860219. Corrective Action Must Take Into Account Equipment Operating Range of 100-137.5-volt Dc ML20154N3431986-03-10010 March 1986 Initial Part 21 Rept 135 Re Potential Problem W/Lube Oil Sump Tank Foot Valve of Dsrv Standby Diesel Generator for Facilities.Cause Not Determined.Recommends Utils Inspect Condition of Foot Valve Liners & Notify Tdi of Findings ML20153G1021986-02-19019 February 1986 Part 21 Rept Re Potential Defect in K-1 Relays of Dsr or Dsrv Standby Diesel Generators Mfg by Gould/Ite.Relays Have Incorrect Voltage Range.Dc Voltage Source or Voltage Regulator Circuitry Requires Mod ML20198C4981985-11-0606 November 1985 Part 21 Rept Re Potential Defect in Dsr or Dsrv Standby Diesel Generator Intake & Exhaust Valve Springs Mfg by Betts Spring Co.Users Recommended to Inspect Engines for Broken Springs & Identify Original Mfg ML20084G3531984-04-19019 April 1984 Final Deficiency Rept Re Pacific Scientific Co Shock Arrestor Capstan Spring Tang.Initially Reported on 831013. Bellefonte Snubbers Will Be Replaced & Hartsville Snubbers Returned to Vendor for Repair.Springs Subj to Insp ML20087J6661984-03-0808 March 1984 Followup Part 21 Rept Re Nuclear Valve/Actuator Stroking Time Possibly Lengthened Beyond 15 When Using hydrocarbon-based Lubricants.Ltrs to Affected Utils Encl ML20081C0171984-03-0101 March 1984 First Interim Deficiency Rept Re Loose Drive Hubs on Overspeed Governor Drive Shaft on Transamerica Delaval,Inc Diesels.Initially Reported on 840203.Svc Info Memo Being Reviewed for Approval.Also Reportable Per Part 21 ML20079N5121984-01-23023 January 1984 Final Deficiency Rept Re Delaval Problem W/Starting Air Valve Assembly on Standby Diesels.Initially Reported on 821201.Capscrews Replaced Per Approved Procedure & Drawings Revised to Reflect Shorter Length ML20083H1921984-01-0505 January 1984 First Interim Deficiency Rept Re Transamerica Delaval,Inc QA Program.Initially Reported on 831206.Final Configuration for Control Cabinet Indicates Drawing Revs K,L & M Not Incorporated.Also Reportable Per Part 21 ML20083E1981983-12-20020 December 1983 First Interim Deficiency Rept Re Fuel Oil Line Rupture in Transamerica Delaval,Inc Generator.Initially Reported on 831121.Const Activities Deferred for Hartsville Units 1 & 2. Next Rept Expected by 840413.Also Reported Per Part 21 ML20078B3811983-09-0606 September 1983 Part 21 Rept Re Matrix Actuator Model 33122-SR 80.Mounting Bolts Loosened & Spring Return Cylinder Began to Separate from Ctr Body of Actuator.Investigation Being Conducted by Xomox Corp 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 ML20024C1401983-06-30030 June 1983 Engineering Evaluation Rept:Investigation & Grouting of Leaks Associated W/Tendon Sheaths H32-009 & H32-011,Unit 2 Containment Bldg. ML20073S8641983-05-31031 May 1983 Details of Deferral Plans for Hartsville Nuclear Plant a ML20083L9751983-05-27027 May 1983 Part 21 Rept Re Failure of Circuit Breakers During Environ Testing.Test Results Indicate That Temp Sensitivity Problem May Be Generic to All Ite Imperial Corp thermal-magnetic Circuit Breakers Calibr for 40 C Svc ML20076H1601983-05-23023 May 1983 Pt 21 Rept Re Potential Defect in Transmitter Mfg by Rosemount,Inc Used in Control Sys Components Furnished to Listed Plants.All Components Involved Retrofitted W/New Circuit Boards.Matter Closed ML20074A2041983-04-26026 April 1983 Interim Deficiency Rept Re Misapplication of Ite Gould Circuit Breakers in post-LOCA Hydrogen Recombiners Supplied by Rockwell Intl.Initially Reported on 830328.Matter Under Investigation.Final Rept by 830808.Reported Per Part 21 ML20069K6811983-04-18018 April 1983 First Interim Deficiency Rept Re Pipe Support Spacing Utilizing Alternate Criteria.Initially Reported on 830317. Investigation Postponed Until Design & Const Resumed ML20073J8051983-04-12012 April 1983 Third Interim Deficiency Rept Re Nonconservative Calculation Method for General Const Spec G-32 Violations.Initially Reported on 820528.Design Std Being Revised to Clarify Use of Factors of Safety in DS-C6.1 ML20073P1281983-04-0808 April 1983 Second Interim Deficiency Rept Re Problem W/Delaval Starting Air Valve Assembly on Standby Diesels.Initially Reported on 821201.Util Continuing to Attempt to Acquire Necessary Info from Transamerica Delaval,Inc.Also Reported Per Part 21 ML20079E9911983-03-31031 March 1983 Caseload Forecast ML20072Q9571983-03-28028 March 1983 First Interim Deficiency Rept Re Failure of Util Div of Engineering Design to Provide Bolt Tightening Requirements to Div of Const.Initially Reported on 830228.Const Deferred. Rept to Be Submitted When Const Decision Made ML20072R3291983-03-28028 March 1983 Interim Deficiency Rept 1 Re CF Braun Documentation Control Program Failure to Monitor Closeout of Final Design Change Control Documents.Initially Reported on 830302.Final Rept Due Upon Commencement of Const.Also Reportable Per Part 21 ML20074A2221983-03-11011 March 1983 Part 21 Rept Re Failure of post-LOCA Hydrogen Recombiner Component During IEEE-323 Qualification Program.Circuit Breaker Not Properly Selected for Specific Application.Plant Operators Notified of Deviation ML20028G0821983-01-31031 January 1983 Final Deficiency Rept Re Itt Grinnell Failure to Use Proper Testing Methods.Initially Reported on 810304.Spool Pieces re-examined Per ASME Section III,1974 Edition,Winter Addenda 1975 Code.Condition No Longer Reportable Per 10CFR50.55(e) ML20083M6711983-01-24024 January 1983 First Interim Deficiency Rept Re Potential Deterioration of Isoprene Gaskets on Standby Diesel Generator.Initially Reported on 821217.Transamerica Delaval,Inc Changed Matl for Drive Element to Neoprene.Also Reportable Per Part 21 ML20083M6651983-01-24024 January 1983 First Interim Deficiency Rept Re Residual Stress on Diesel Generator Engine Piston Skirt Castings.Initially Reported on 821215.Removal of Piston Skirt for Insp Deferred Until Restart of Design & Const.Also Reportable Per Part 21 ML20028C2481982-12-30030 December 1982 First Interim Deficiency Rept Re Insufficient Length of Starting Air Valve Assembly Capscrews.Initially Reported on 821201.Transamerica Delaval,Inc Changed Designed Length of Capscrew.Next Rept by 830415.Also Reportable Per Part 21 ML20070F0121982-12-13013 December 1982 Final Deficiency Rept Re Atlas QA Documentation on Auxiliary & Fuel Bldg Structural Steel.Initially Reported on 811113. QA Hold Placed on Suspect Items Until Further Testing Performed.Also Reportable Under Part 21 ML20028A4891982-11-0909 November 1982 Final Deficiency Rept Re Storage & Preventive Maint Program Deficiencies.Initially Reported on 821007.Pipe Caps Replaced,Piping Placed on Support,Tanks Moved to Inside Storage in Upright Position & Conditions & Program Reviewed ML20069Q3771982-10-31031 October 1982 Const Employee Monitoring Errata Rept ML20069Q3701982-10-31031 October 1982 Socioeconomic Monitoring & Mitigation Rept ML20065R3701982-10-14014 October 1982 Interim Deficiency Rept Re Deferral of Const Activities. Initially Reported on 820623.Commitments Made in Rept,Audit Findings & Response to Violations Deferred Until Restart of Design & Const ML20027B8451982-09-20020 September 1982 First Interim Deficiency Rept Re QA Deficiencies on Allis- Chalmers Butterfly Valves.Initially Reported on 820823.Const Activities Deferred.Final Rept Will Be Submitted After Final Decision Re Completion or Cancellation of Project ML20069D5241982-09-10010 September 1982 Socioeconomic Monitoring & Mitigating Rept,Sept 1981 ML20063L3721982-09-0202 September 1982 First Interim Deficiency Rept Re Failure of Kerotest Valves to Meet Seismic Criteria.Initially Reported on 820804. Negotiations Underway W/Contractor for Return of Valves. Const Activities Deferred.Also Reportable Per Part 21 ML20055A0731982-07-0707 July 1982 First Interim Deficiency Rept Re Nonconformance in Intake Pumping Station Door & Hatch Design,Initially Reported 820604.Final Rept Will Not Be Issued Until Decision to Resume Facility Const Reached ML20055A0791982-07-0606 July 1982 First Interim Deficiency Rept Re Possible Installation of Bolt Anchors in Grant Areas,Initially Reported 820610. Investigation Postponed Until Const Resumed ML20054N0821982-07-0101 July 1982 Final Deficiency Rept Re Excessive Stress on Spray Pond Supply & Bypass Headers,Initially Reported on 820218. Piping Layout Revised & Drawings Revised/Reissued.Seismic Analysis Complete & Isometrics Issued ML20054J9111982-06-23023 June 1982 Part 21 Rept Re Potential Defect in Couplings Drive Element of Dsrv or Dsr Standby Diesel Generator.Affected Licensees Will Be Notified No Later than 820715 ML20054K1531982-06-23023 June 1982 Informs That Final Deficiency Repts for Listed Nonconformances Will Not Be Submitted Until Final Decision Is Made Re Const of Projects ML20054H6821982-06-18018 June 1982 Part 21 Rept Re Pneumatic Actuator Yoke Failure.List of Other Projects W/Similar Equipment Encl ML20054G1121982-06-11011 June 1982 Fourth Interim Deficiency Rept Re Link Rod assembly-Delaval Diesels.Due to Const Deferment Final Deficiency Rept Will Not Be Issued Pending Final Decision on Future of Projects. Also Reportable Per Part 21 ML20054E4111982-06-0101 June 1982 Fourth Interim Deficiency Rept Re Bethlehem Steel Co Galvanized A325 Bolts,Initially Reported on 811029.Const Activities Deferred Until Sufficient Info Indicates Whether Project Should Be Completed or Canceled 1993-12-09
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ENCLOSURE HARTSVILLE AND PHIPPS BEND NUCLEAR PLANTS
- DEFECTIVE MCGRAW-EDISON TEMPERATURE DETECTION t CONTROLLERS IN THE STANDBYGAS TREATMENT SYSTEM 10 CFR 50.55(e) REPORT NO. l (FINAL)
NCR'S HNP-A-100 AND PBNP-091 On May'14, 1980, TVA informed NRC-0IE, Region II, Inspector T. E. f Burdette of a reportable deficiency under 10 CFR Part 50.55(e) involving l defects in McGraw-Edison electronic temperature detection controllers in l the Standby Gas Treatment System (SGTS) for the Hartsville and Phipps l Bend Nuclear Plants. This deficiency was also reported under 10 CFR !
Part 21 to NRC-0IE Region III on April 30, 1980, by CTI-Nuclear, l the STRIDE component supplier for the SGTS. This is the final report I on the deficiency. l Descrip* ton of Deficiency TVA was informed by CTI-Nuclear, Cleveland, 0hio, who was previously informed by Edison Electronics Division of McGraw-Edison (Edison) i of Manchester, New Hampshire, that an electronic temperature detection controller (the same type as controllers supplied by Edison to CTI-Nuclear and by CTI-Nuclear to TVA) failed'in service and that other similar controllers ata ententially defective.
The potentially defective controllers are McGraw-Edison P/N 377-02831 4 and are integral parts of electronic control circuits for detecting high temperatures in the airstream, both upstream and downstream of vertical deep bed carbon adsorbers in the Hartsville and Phipps Bend SGTS. The controllers are also used as part of a control circuit for high temperature thermal cutout of electric air heaters in the same system. These controllers are used on CTI-Nuclear part numbers 4
D-31441 and D-31250.
I-TVA SGTS housings (two per nuclear unit at Hartsville and Phipps Bend) each contain five potentially defective controllers (two each in the upstream and downstream high temperature detection panels, No. D-31441, and one in the high temperature cutout panel, No. D-31250). This represents a total of 60 potentially defective controllers, 40 at Harts-ville and 20 at Phipps Bend, in the SGTS equipment delivered to TVA.
j Edison attributes the only known failure to use of an acid flux solder j in sealing some of the controls during manufacture. Edison has concluded that there is no convenient method of determining in the field if the control was sealed with acid flux solder. The acid flux reportedly could cause corrosion in the controller and result in failure. The mode of a failure is unpredictable; a failure could cause the controller to_ give _ erroneous indication such as (1) failing to open and not closing at an. alarm point, (2) failing closed and giving a false alarm, or (3) failing at some intermediate step and functioning inaccurately. ,
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Safety Implications Failure of a controller in one of the manners described above could possibly cause or prevent. detection of, through a number of ways depending on which. controller failed and how it failed, loss of charcoal effectiveness through introduction of moisture or fire in the bed, thereby disabling at least one train of the SGTS. However, since other means are available to detect unnsual conditions in the SGTS system (e.g., radiation monitors and moisture detectors downstream of the charcoal beds) loss of one of the controllers may not lead to undesirable consequences. TVA concludes that this deficiency could have jeapordized the safety of operation of the plant.
Corrective Action CTI-Nuclear has requested that TVA remove the 60 potentially defective controllers and ship them back to CTI-Nuclear,1922 E.107th Street, Cleveland, Ohio 44106. CTI-Nuclear will then forward the controllers back to Edison. All 60 controllers will be replaced' with controllers which have been verified to have been sealed or soldered properly. The
- controllers will be shipped from TVA sites back to CTI-Nuclear by July 31, 1980.
Means Taken to Prevent Recurrence Edison has verbally indicated that they have informed all of their employees
, who assemble electronic components of the harmful effects of acid flux on electronic circuits. These individuals have also been instructed not to use acid flux in any operation.
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