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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20115D2001996-07-0909 July 1996 Part 21 Rept Re Mfg Defect of Enterprise DSR-4 & DSRV-4 Edgs,Originally Mfg by Calcon Corp.Amot Control Corp Purchased Calcon Product Line & Maintains Design & Production.Valves Returned to Cooper Energy Svcs on 960131 ML20058K3841993-12-0909 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 ML20044G5311993-05-26026 May 1993 Suppl to 921207 Part 21 Rept Re Declutch Sys Anomaly in Certain Types of Valve Actuators Supplied by Limitorque Corp.Limitorque Designed New Declutch Lever Which Will Be Available in First Quarter 1993 ML20044G5011993-05-26026 May 1993 Part 21 Rept Re Buffer Amplifier Modules Mfg by Bailey Controls Co Containing Suspect Negative Ref Power Supply Having Safety Implications.Caused by Design Error in Circuitry.Modules Would Not Result in Miscalibration ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20126D7211992-12-16016 December 1992 Potential Part 21 Rept Re Actual Performance of Rosemount Supplied Bailey Bq Differential Pressure Transmitters Differing from Rosemount Original Spec.Bailey Controls Encl.Evaluation Not Yet Performed ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20012A9011990-02-27027 February 1990 Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp 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 ML18153C1011990-02-0202 February 1990 Part 21 Rept Re Two of Three Pc Cards in GE Type SLV11A1 Over/Undervoltage Relays Failing to Produce Output.Short Between Leads Would Result in Damage to Component 1C5. Sketch of Threshold Detection Board Encl ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML19325E0861989-10-16016 October 1989 Followup Part 21 Rept Re Class 1E Battery Chargers W/ Transformers Running at Temps Exceeding Those Used in Qualification Rept When Operating at or Near Full Load Rating of Equipment.Listed Corrective Actions Underway ML19351A2941989-10-0909 October 1989 Part 21 Rept Re Potential of Ambient Compensated Molded Case Circuit Breakers to Deviate from Published Info. Instantaneous Trip Check Will Be Instituted on All Class 1E Thermal/Magnetic Ambient Breakers Prior to Shipment ML19325C9521989-09-29029 September 1989 Part 21 Rept Re Potential Common Failure of SMB-000 & SMB-00 Cam Type Torque Switches Supplied Prior to 1981 & 1976. Vendor Recommends That Switch W/Fiber Spacer Be Replaced 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 ML20246P7111989-07-17017 July 1989 Part 21 Rept Re Quench Cracks in Bar of A-SA-193 Grade B7 Component.Quench Cracks Found in One Bar of Matl.Listed Purchasers Informed of Potential Defect.Next Rept Will Be Submitted When Addl Info Becomes Available ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML20245B6651989-06-15015 June 1989 Part 21 Rept 150 Re Potential Defect in Component of Dsr Standby Diesel Generator.Cause of Failure Determined to Be Combination of Insufficient Lubrication to Bushings.Listed Course of Action Recommended at Next Scheduled Engine Maint 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 ML20244D8161989-04-13013 April 1989 Part 21 Rept Re Failure of Rosemount Transmitters.All Failed Transmitters Replaced,Inservice Test Procedure Prepared & Monthly Test of All 12 Transmitters in RCS Throughout Cycle 2 Operation Will Be Performed.Review Continuing ML20247P7991989-04-0404 April 1989 Part 21 Rept Re Atmospheric Dump Valves.Cause of Failure Speculative But Result of Piston Ring That Failed to Seal. Resolution to Problem Requires Increasing Pilot Valve Capacity & Reworking of Plug to Enlarge Pilot Flow Area ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys ML20205F3211988-10-10010 October 1988 Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07 ML20207P0451988-10-0505 October 1988 Part 21 Rept 146 Re Defect in Left Intercooler Inlet Adapter on Standby Diesel Engine Generator.Recommends Utils Inspect Left Intake Manifold Drain as Part of Operating Plan.Addl Info Expected by 881015 ML20207P0151988-10-0404 October 1988 Part 21 Rept Re Fuel Nozzle Tips in Standby Diesel Generator KSV-20-T W/Cracks Permitting Diesel Fuel to Be Sprayed Into Cylinders.Heavy Vapors Observed Emitting from Breathers on Some Cylinder Heads ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking 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 ML18093A8281988-05-0606 May 1988 Part 21 & Deficiency Rept Re Asea Brown Boveri,Power Distribution,Inc Low Voltage K-Line Circuit Breakers. Efforts Underway to Define Quantity & Type of Component Parts That May Need to Be Replaced 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 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 ML20153B2811988-02-22022 February 1988 Part 21 Rept Re Defect in Operation of Gas Monitors Using Fixed Filters.Initially Reported on 880212.Caused by Error in Software for Monitors.Vendor Testing Mod to Software & in Interim Recommends Changing Filters Every 48 H ML20196D6281988-02-10010 February 1988 Part 21 Rept Re Potential Defect in Certain Model RTF-480/120-30 Ac Line Regulating Transformers Involving Nuisance Tripping of 100 Ampere Ac Input Circuit Breaker When Initializing Unit.Breaker Should Be Replaced ML20149J0261987-12-21021 December 1987 Part 21 Rept Re Installation of Relay Part B8002DN in Foxboro 62H Controllers in Facilities.Subj Relay Must Be Replaced by Relay Part N0196ZN.Relay B8002DN Not Used in Any Other Plants ML20235U0271987-10-0707 October 1987 Part 21 Rept Re Westinghouse Plant Steam Generator Tubes Susceptible to High Cycle Fatigue Failure Similar to 870715 Event at North Anna Unit 1.Caused by Mean Stress in Tube & Superimposed Alternating Stress ML20237G5781987-08-0707 August 1987 Part 21 & Deficiency Rept 142 Re Defect in Starting Air Distributor Sys of Dsr Standby Diesel Generator.Drain Sys Will Be Permanently Installed in Start Air Distributor ML20236N7131987-08-0505 August 1987 Part 21 Rept Re Potential Problem W/Vibration in Lube Oil & Jacket Water Sys.At Rancho Seco Site,Fatigue Cracks Found in Welds of Support Members in Lubricating Oil Sys.Cracks Due to Vibration in Lube Oil Sys.Addl Preventive Action Taken ML20234C7351987-06-23023 June 1987 Supplemental Part 21 Rept Re Silicone Foam Seal Anomolies at Wolf Creek Generating Station ML17261A5301987-06-18018 June 1987 Part 21 Rept Re Potential Util Failure to Comply W/Component Containment Isolation Licensing Commitment If Proposed Mods to Component Cooling Water Sys Instituted.Utils Advised to Evaluate Containment Isolation Sys ML20215G2441987-06-16016 June 1987 Part 21 Rept Re Failure of Load Sequencing Equipment Supplied in Aug 1977 During Scheduled Testing.Caused by Open Electrical Connection on One Crimp Lug.Since 1978,insulated Lugs Used on All Equipment ML20216E4721987-05-28028 May 1987 Part 21 Rept 140 Re Potential Defect in Air Pressure Regulators Mfg by Bellofram.Dripwell Gasket May Fail Due to Mismachining of Gasket Seating Surface Causing Loss of Control Air & Starting Air Pressure ML20214A1361987-05-12012 May 1987 Part 21 Rept Re Capacity of Thermal Compensating Accumulator Being Insufficient to Compensate for Thermal Expansions of Hydraulic Fluid During Full Ambient Temp Transient Required by Customer Specs.Interim & Permanent Mods Identified ML20205R5851987-03-31031 March 1987 Part 21 & Deficiency Rept 139 Re Potential Defect in Engine Control Panel Shutdown Circuitry of Dsr & Dsrv Standby Diesel Generator.Corrective Action at Vogtle Already Implemented.Mfg Will Work W/Smud to Implement Mods ML20204F9061987-03-18018 March 1987 Amended Part 21 Rept 138 Re Potential Problem W/Static Exciter Voltage Regulator Reset Design.Initially Reported on 870311.Similar Equipment Delivered to Listed Sites.Generic Info Will Be Provided by 870331 ML20207R7031987-03-11011 March 1987 Part 21 Rept Re Potential Defect in Static Exciter Voltage Regulator (Sevr) Reset Design.Recommends Mod to Control Circuits to Energize Sevr Upon Receipt of Emergency Start Signal.Mods Will Be Completed by 870331 ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20207T8061987-02-20020 February 1987 Part 21 & Deficiency Rept Re Defect in Recirculation Spray Hxs.Initially Reported on 870218.Original HX Design Did Not Consider External Pressurization of Diaphragm Seal Plate W/O Presence of Internal Pressure as Balance.Mods Scheduled 1997-05-01
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20115D2001996-07-0909 July 1996 Part 21 Rept Re Mfg Defect of Enterprise DSR-4 & DSRV-4 Edgs,Originally Mfg by Calcon Corp.Amot Control Corp Purchased Calcon Product Line & Maintains Design & Production.Valves Returned to Cooper Energy Svcs on 960131 ML20058K3841993-12-0909 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 ML20044G5311993-05-26026 May 1993 Suppl to 921207 Part 21 Rept Re Declutch Sys Anomaly in Certain Types of Valve Actuators Supplied by Limitorque Corp.Limitorque Designed New Declutch Lever Which Will Be Available in First Quarter 1993 ML20044G5011993-05-26026 May 1993 Part 21 Rept Re Buffer Amplifier Modules Mfg by Bailey Controls Co Containing Suspect Negative Ref Power Supply Having Safety Implications.Caused by Design Error in Circuitry.Modules Would Not Result in Miscalibration ML18010B0841993-05-0505 May 1993 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20126D7211992-12-16016 December 1992 Potential Part 21 Rept Re Actual Performance of Rosemount Supplied Bailey Bq Differential Pressure Transmitters Differing from Rosemount Original Spec.Bailey Controls Encl.Evaluation Not Yet Performed ML18010A9521992-11-30030 November 1992 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML18094B3211990-02-28028 February 1990 Annual Operating Repts for 1989 for Salem & Hope Creek Generating Stations ML20012A9011990-02-27027 February 1990 Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp 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 ML18153C1011990-02-0202 February 1990 Part 21 Rept Re Two of Three Pc Cards in GE Type SLV11A1 Over/Undervoltage Relays Failing to Produce Output.Short Between Leads Would Result in Damage to Component 1C5. Sketch of Threshold Detection Board Encl ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20006A8231990-01-10010 January 1990 Errata to Rev 3 to BAW-1543, Master Integrated Reactor Vessel Surveillance Program Consisting of Revised Tables 3-20 & E-1 ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML17347B4621989-12-31031 December 1989 App a to USI A-46 & Generic Ltr 87-02. ML18094B1471989-10-25025 October 1989 Emergency Plan Annual Exercise 1989 for Artificial Island on 891025. W/One Oversize Drawing ML19325E0861989-10-16016 October 1989 Followup Part 21 Rept Re Class 1E Battery Chargers W/ Transformers Running at Temps Exceeding Those Used in Qualification Rept When Operating at or Near Full Load Rating of Equipment.Listed Corrective Actions Underway ML19351A2941989-10-0909 October 1989 Part 21 Rept Re Potential of Ambient Compensated Molded Case Circuit Breakers to Deviate from Published Info. Instantaneous Trip Check Will Be Instituted on All Class 1E Thermal/Magnetic Ambient Breakers Prior to Shipment ML20248G8291989-10-0202 October 1989 Rev 19 to YOQAP-I-A, Operational QA Program ML17347B3821989-09-30030 September 1989 Monthly Operating Repts for Sept 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2.W/891016 Ltr ML19327C0681989-09-30030 September 1989 Nuclear Safety & Compliance Semiannual Rept Number 11,Apr- Sept 1989. W/891027 Ltr ML19351A4191989-09-30030 September 1989 Mark-BW Reload LOCA Analysis for Catawba & McGuire Units. ML20248F0001989-09-29029 September 1989 Debris in Containment Recirculation Sumps, Technical Review Rept ML19325C9521989-09-29029 September 1989 Part 21 Rept Re Potential Common Failure of SMB-000 & SMB-00 Cam Type Torque Switches Supplied Prior to 1981 & 1976. Vendor Recommends That Switch W/Fiber Spacer Be Replaced ML20248D1571989-09-13013 September 1989 Rev 56 to QA Program 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 ML20247K2531989-09-11011 September 1989 Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively ML20247E3761989-09-0707 September 1989 Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML17347B3341989-08-31031 August 1989 Monthly Operating Repts for Aug 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2.W/890913 Ltr ML20246D6871989-08-14014 August 1989 Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks ML20248C0731989-08-0303 August 1989 Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants ML17347B2731989-07-31031 July 1989 Monthly Operating Repts for Jul 1989 for Turkey Point Units 3 & 4 & St Lucie Units 1 & 2 ML18008A0311989-07-31031 July 1989 NTH-TR-01 Decrease in Heat Removal by Secondary Sys. ML19327B4011989-07-31031 July 1989 Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel. ML20246P7111989-07-17017 July 1989 Part 21 Rept Re Quench Cracks in Bar of A-SA-193 Grade B7 Component.Quench Cracks Found in One Bar of Matl.Listed Purchasers Informed of Potential Defect.Next Rept Will Be Submitted When Addl Info Becomes Available ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML17347B1851989-06-30030 June 1989 Monthly Operating Repts for June 1989 for St Lucie Units 1 & 2 & Turkey Point Units 3 & 4.W/890717 Ltr ML17347B2741989-06-30030 June 1989 Corrected Monthly Operating Repts for June 1989 for Turkey Point Units 3 & 4 ML20247H0711989-06-30030 June 1989 Description & Verification Summary of Computer Program, Gappipe ML20246D6711989-06-30030 June 1989 Criticality Analysis of Byron/Braidwood Fresh Fuel Racks ML20246L2571989-06-26026 June 1989 Safety Evaluation Supporting Amends 118,33,142 & 36 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20247H0791989-06-22022 June 1989 App to Description & Verification Summary of Computer Program,Gappipe ML18151A5411989-06-21021 June 1989 Updated Operational QA Program Topical Rept. ML20245B6651989-06-15015 June 1989 Part 21 Rept 150 Re Potential Defect in Component of Dsr Standby Diesel Generator.Cause of Failure Determined to Be Combination of Insufficient Lubrication to Bushings.Listed Course of Action Recommended at Next Scheduled Engine Maint ML18101A4931989-06-13013 June 1989 Radiological Emergency Preparedness Exercise Evaluation Rept. 1997-05-01
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' ~$ EU, g 4. v TENNESSEE: VALLEY; AUTHORITY CHATTANOOGA TENN'ES$1EE 37401 400 Chcotnut Street Tower II M Jlf! 10 gotlaMS,1984
.BLRD-50-438/83-64, HTRD-50-518/83-08 BLRD-50-439/83-58 HT3D-50-520/83-08 U.S. Nuclear Regulatory Commission .
Region II Attn: Mr.' James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
BELLEFONTE AND HARTSVILLE NUCLEAR PLANTS UNITS 1 AND 2 - TRANSAMERICA DELAVAL QA PROGEAM DEFICIENCIES - BLRD-50-438/83-64, BLRD-50-439/83-58,.
ElRD-50-518/83-08, HTRD-50-520/83 FIRST INTERIM REPORT i
The subject deficiency was initially reported to NRC-OIE Inspector Linda Watson on December 6,1983 in accordance with 10 CFR 50.55(e) as NCR QDBVA-84-18 Deficiencies 1, 3, and 6. Enclosed is our first interim repor t. We expect to submit our next report by August 24, 1984. We consider 10 CFR Part 21 applicable to this deficiency.
TVA has electea to defer construction activities on Hartsville. Deferral 1
does-not mean that the project will be cancelled but that TVA is minimizing its expenditures and construction efforts until such time that TVA has sufficient information-to indicate whether the project should be completed or cancelled. ThereI* ore, we will not be submitting further information on Hartsville until a final decision is made regarding this project.
If you have any questions, please get in touch with R. H. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY 8401130053 84010S i PDR ADOCK 05000438 - -
.S PDR L. M. Mills,iManager Nuclear Licensing Enclosure cc: Mr. Richard C. Deloung, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Records Center (Enclosure)
Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 OFFICIAL rnW
.1 b b i
1983-TVA SOTH ANNIVERSARY ) )
An Equal Opportunity Employer g j
' ~ -
1 55 Gi 3E JE mg
, ENCLOSURE JE l' '
i!
BELLEFONTE AND HARTSVILLE NUCLEAR PLANTS 'JNITS 1 AND 2 d!
TRANSAMERICA DELAVAL QA PROGRAM DEFICIENCIES ]l BLRD-50-438/83-64, BLRD-50-439/83-58 ;=
HTRD-50-518/83-08, HTRD-50-520/83-08 .-l NCR QDBVA-84-18 DEFICIENCIES 1, 3, AND 6 .
l 10 CFR 50.55(e) i i FIRST INTERIM REPORT :
Description of Deficiency j' o
During a TVA vendor audit ~(QDBVA-84-18) of Transamerica Delaval, I
"i?
Incorporated (TDI), Oakland, California, several deficiencier were noted which indicate noncompliance with their own quality assurance fj program. TDI supplies emergency diesel generators to TVA and their j quality assurance program had previously been accepted by TVA. A }
description of the deficiencies that were found during the audit j]
follows.
2 In the area of design control there exists a lack of a configuration b j;
control program which defines the actual configuration of each control .
panel for the TDI generators. No design baseline exists for the panels. j Control cabinet 77024 (job No. 80043) was inspected / tested between 3 July 27 and August 30, 1981, with final acceptance testing being E accomplished on September 2, 1981. Drawing set 09-500-77024, sheets 3 1-11, reviaion J, was used during these inspections and tests. @
^*
Further, revisions K and L were mandatory changes which were required jj to be made to all the panels, and revision M should have been g incorporated to ensure that all panels were the same. No objective >
evidence was available in engineering, inventory control, or the pa-i. E shop to idettify the actual configuation of panels manufactured with -1 this order. Inventory control records indicate the parts list used T with this order was last revised on September 3,1981, (revision 22) j and that subsequent revisions (23,24, and 25) were not incorporated on --
3 ,. this order. Further, both engineering and inventory records on the d 7.iQq transmittal of the changes have been destroyed in accordance with 4 p y,:p Delaval procedures. Two different types of change notices are used j Xr (drawing change notices for drawings and engineering memorandums for f; 4(:' y g the parts list) neither of which cross references the other. Changes sf . 7 which are not incorporated before shipment are to be incorporated by 3 y
gg the engineering service departmaat. The engineering service i yeg}.T,g department does not receive engineering changes but 13 sent 2 h ~, c i .
memorandums from design engineering. These memorandums also do not j reference the daange documents. There was no documentation in the i service department to indicate that all the changes to be incorporated "
by revisions K and L were accomplished. The only evidence available j on final configuration is the test records which indicate that a revisions K, L, and M were not incorporated.
]
t 45 9
z N
a E
=
a
In th] cren of tar.t control, . Test Procedure 1A-6803 for tasting of tho -
reflCsh board cas;mbly doea not requira any tast data to be recorded, '
I no listing of instruments used, and no evaluation of the test results.
Final acceptance test procedure 77024-500 also does not require test data to be recorded, a listing of instruments used, and an evaluation of test results. Further, completed procedure for the test of unit 77034 indicated that some test items (2 and 4B) had not been signed off as being completed.
No objective evidence was available for review that personnel performing panel tests are qualified.
' Also noted was a failure to ensure that seismic requirements of the contracts have been fully implemented in that:
- 1. No objective evidence was available - for review that indicated changes to the seismically qualified control panel had been reviewed for impact on the qualification test results.
- 2. The control panels themselves are not considered to be safety related by Delaval, and therefore, appropriate quality assurance requirements relating to the panels' manufaciusv (i.e.,
structural) had not been imposed on their subcontractor.
Interim Progress The TVA audit team prepared deviation reports which were discussed with Transamerica Delaval personnel at the postaudit conference. A preliminary copy of each deviation was given to Transamerica Delaval quality assurance personnel at this meeting with the official copy being transmitted with the formal report. Transamerica Delaval was requested to respond with their proposed correctiva action.
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