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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 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 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 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 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 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 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 ML20210S3151987-02-0404 February 1987 Revised Final Deficiency Rept Re Unsuccessful Attempt to Synchronize Diesel Generator W/Sys.Initially Reported on 860730.Generator Endturns Cleaned & Greased Before Repairs Made.Permissive Sychronization Relay Scheme Installed ML20207Q6461987-01-21021 January 1987 Forwards Two Lists Revising Commitment Completion Dates for Final Deficiency Repts.Encl 1 Lists Items to Be Completed at Least 6 Months Prior to Fuel Load.Encl 2 Lists Items Scheduled to Undergo Peer Review ML20207Q6601987-01-21021 January 1987 Final Part 21 & Deficiency Rept Re Misinterpretation of Pipe Movement Data for Itt Grinnell Designed Pipe Supports. Initially Reported on 840208.Pipe Support Detail Sheet Reviewed & Incorrect Drawings Revised ML20214K5271986-11-17017 November 1986 First Interim Deficiency Rept Re Missing Internal Lockwelds on Anchor Darling swing-check Valves.Initially Reported on 861016.Two Subj Valves Found Thus Far Inspected & Found Acceptable.Final Rept to Be Submitted 1 Yr Before Fuel Load ML20214G0191986-11-10010 November 1986 Revised Final Deficiency Rept Re Target Rock Solenoid Valves on post-accident Sampling Facility Not Meeting Backpressure Requirements.Corrective Action Will Not Be Complete Until 6 Months Before Fuel Load ML20215G5351986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215G6801986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215F3461986-10-0606 October 1986 Final Part 21 & Deficiency Rept Re Failure to Adequately Disposition Reportable Nonconformances in Divs of Nuclear Engineering & Nuclear Const.Initially Reported on 860224. Changes to Corrective Action Program Listed ML20210L7071986-09-22022 September 1986 Interim Deficiency Rept SCR Bln 4949 Re Use of Long Slotted Holes W/O Plate Washers.Initially Reported on 860822. Investigation of Reactor Bldgs & Pipe Support Connections Required to Determine If Corrective Action Needed ML20210T0371986-09-15015 September 1986 Second Revised Final Deficiency Rept Re Attachment of Pipe Supports to 6-inch Strip Plates Lacking Capacity to Withstand Seismic Pipe Support Loads.Initially Reported on 811231.All Affected Supports Identified & Procedure Revised ML20203M0281986-08-19019 August 1986 Part 21 & First Interim Deficiency Rept SCR Bln 4921 Re Closing Assist Spring Failure on Atwood & Morrill Msivs. Initially Reported on 860721.Testing to Assure Soundness of Springs Underway.Next Rept Expected 1 Yr Prior to Fuel Load 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 ML20203K4151986-08-0606 August 1986 Final Deficiency Rept Re Incorrect Insulation Weights for Intake Pumping Station Piping.Initially Reported on 840221. Calculations for Insulation Weights Completed & Documented. Drawings Revised to Reflect New Weights ML20214H1861986-08-0101 August 1986 Final Deficiency Rept Re Error in Seismic Data Used in Auxiliary Control Bldg Design.Initially Reported on 840406. Revised Fixed Damped Response Spectra for Auxiliary Control Bldg Generated ML20212D3311986-07-30030 July 1986 Final Deficiency Repts Ncr Bln 3684 & Ncr Bln 4254 Re Conduit Support Stiffener Plates Not Installed Per Drawing. Initially Reported on 840510.Electrical QC & Engineering Personnel Retrained in Procedures ML20212B2001986-07-18018 July 1986 Final Deficiency Rept Re Unconservative Flange Qualification Analysis.Initially Reported on 841207.Caused by Misinterpretation of ASME Code Section Iii,Subsection NC-3658.1 (S76) ML20212B3731986-07-17017 July 1986 Part 21 & Revised Final Deficiency Rept Ncr Bln 2393 Re High Vibration Levels Measured for Bingham-Willamette Pumps. Initially Reported on 830622.Cause of Deficiency Unknown. Problem Does Not Represent Problem at Any TVA Facility 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 ML20203B9111986-07-0202 July 1986 Part 21 & Final Deficiency Rept Re Foreign Matl in C&D Batteries.Initially Reported on 840822.Batteries Will Be Replaced W/New Batteries Which Do Not Use Reigel Wrap in Const ML20207L1581986-06-18018 June 1986 Final Part 21 & Deficiency Rept Re Design Problems W/B&W Steam Generators.Initially Reported on 820830.Nozzles Supplying Auxiliary Feedwater to Internal Headers Capped Off & New External Headers Installed to Preclude Failures ML20206J8971986-06-11011 June 1986 Final Deficiency Rept Re Erroneous Dimensions for American Boa B1-0 Flexible Conduit Appearing in Electrical Design Std DS-E13.1.7.Initially Reported on 860515.Std Will Be Revised ML20211B1721986-05-28028 May 1986 Final Part 21 & Deficiency Rept Re Ruskin Fire Damper Installation & Closure Problems.Initially Reported on 840411.Caused by Improper Util Installation & Inadequate Testing by Mfg to Establish Closure Criteria ML20198K3101986-05-15015 May 1986 Revised Final Deficiency Rept Re Insulation Weights Assumed in Analyses for Valves & Pipe Fittings.Initially Reported on 840123.All Affected Piping Sys Will Be Reanalyzed. Rigorous Analysis Handbook Will Be Updated by 860601 ML20197H2581986-05-0808 May 1986 Part 21 Rept 135 Re Defect W/Lube Oil Sump Tank Foot Valve of Standby Diesel Generator.Caused by Extrusion of Liner Matl Due to Overpressurization.Corrective Actions Being Developed.List of Affected Sites Modified ML20155J1321986-05-0707 May 1986 Final Deficiency Rept Re Omissions to Auxiliary Feedwater Pump Drawings.Initially Reported on 820225.Required Piping Will Be Designed & Placed on Appropriate Drawings ML20203C2601986-04-0808 April 1986 Final Deficiency Rept Re Defect in Overlap Modeling Techniques.Initially Reported on 840801.Rigorous Analysis Handbook Revised to Incorporate Techniques in NUREG/CR-1980. Corrective Actions Will Be Done 6 Months Before Fuel Load ML20155C2761986-04-0404 April 1986 Final Deficiency Rept Re Use of Nonconservative Analyses of Insulation Weights for Valves & Pipe Fittings.Initially Reported on 840123.Corrective Actions Will Be Completed 6 Months Prior to Fuel Load ML20203A8751986-04-0303 April 1986 First Interim Deficiency Rept Re Failure to Adequately Disposition Reportable Nonconformances.Initially Reported on 850224.Peer Review Continuing.Final Rept Expected 1 Yr Before Unit 1 Fuel Loading ML20205M0251986-03-31031 March 1986 Final Deficiency Rept Ncr 4490 Re Piping Component Support Welds Not Meeting Insp Criteria.Initially Reported on 850927.Visual QA Certification of Inspectors Implemented. Item Not Reportable Per 10CFR50.55(e) ML20202G9741986-03-28028 March 1986 Final Part 21 & Deficiency Rept Re Failure of BIF Butterfly Valve Seats.Initially Reported on 820511.Seat Failures Reworked.Informal Tests Performed After Seat Replacement Show That Leakage Corrected ML20202J0091986-03-27027 March 1986 Final Part 21 & Deficiency Rept Re Failure of Main Steam Lines Due to Main Feedwater Overfill.Initially Reported on 800319.B&W Will Provide Design for safety-grade Main Feedwater Overfill Protection Sys for Steam Generators ML20202J3341986-03-24024 March 1986 Final Deficiency Rept Re out-of-date Design Criteria for DHR & Core Flooding Sys.Initially Reported on 830405.Caused by Deferral of Paperwork.All Design Criteria Documents Reviewed & Revised to Incorporate Outstanding Design Input Memos ML20205L6611986-03-24024 March 1986 Final Deficiency Rept Re Incorrect Installation of Pressure Relief & Safety Valves.Initially Reported on 820305.Relief Valve Piping Will Be Redesigned to Provide Adequate Vent Area 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 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 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 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 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 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 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 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 ML20237K8201987-08-26026 August 1987 TVA Employee Concerns Special Program Bellefonte Nuclear Plant Element Rept BLN-NSRS-2, Review of Nuclear Safety Review Staff Non-Startup Items at Bellefonte ML20237K8081987-07-23023 July 1987 Rev 0 to TVA Employee Concern Special Program Bellefonte Nuclear Plant Element Rept BLN-NSRS-1, Review of Nuclear Safety Review Staff Startup Items at Bellefonte 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 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 ML20210S3151987-02-0404 February 1987 Revised Final Deficiency Rept Re Unsuccessful Attempt to Synchronize Diesel Generator W/Sys.Initially Reported on 860730.Generator Endturns Cleaned & Greased Before Repairs Made.Permissive Sychronization Relay Scheme Installed ML20207Q6461987-01-21021 January 1987 Forwards Two Lists Revising Commitment Completion Dates for Final Deficiency Repts.Encl 1 Lists Items to Be Completed at Least 6 Months Prior to Fuel Load.Encl 2 Lists Items Scheduled to Undergo Peer Review ML20207Q6601987-01-21021 January 1987 Final Part 21 & Deficiency Rept Re Misinterpretation of Pipe Movement Data for Itt Grinnell Designed Pipe Supports. Initially Reported on 840208.Pipe Support Detail Sheet Reviewed & Incorrect Drawings Revised ML20214K5271986-11-17017 November 1986 First Interim Deficiency Rept Re Missing Internal Lockwelds on Anchor Darling swing-check Valves.Initially Reported on 861016.Two Subj Valves Found Thus Far Inspected & Found Acceptable.Final Rept to Be Submitted 1 Yr Before Fuel Load ML20214G0191986-11-10010 November 1986 Revised Final Deficiency Rept Re Target Rock Solenoid Valves on post-accident Sampling Facility Not Meeting Backpressure Requirements.Corrective Action Will Not Be Complete Until 6 Months Before Fuel Load ML20215G6801986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215G5351986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215F3461986-10-0606 October 1986 Final Part 21 & Deficiency Rept Re Failure to Adequately Disposition Reportable Nonconformances in Divs of Nuclear Engineering & Nuclear Const.Initially Reported on 860224. Changes to Corrective Action Program Listed ML20210L7071986-09-22022 September 1986 Interim Deficiency Rept SCR Bln 4949 Re Use of Long Slotted Holes W/O Plate Washers.Initially Reported on 860822. Investigation of Reactor Bldgs & Pipe Support Connections Required to Determine If Corrective Action Needed ML20210T0371986-09-15015 September 1986 Second Revised Final Deficiency Rept Re Attachment of Pipe Supports to 6-inch Strip Plates Lacking Capacity to Withstand Seismic Pipe Support Loads.Initially Reported on 811231.All Affected Supports Identified & Procedure Revised ML20203M0281986-08-19019 August 1986 Part 21 & First Interim Deficiency Rept SCR Bln 4921 Re Closing Assist Spring Failure on Atwood & Morrill Msivs. Initially Reported on 860721.Testing to Assure Soundness of Springs Underway.Next Rept Expected 1 Yr Prior to Fuel Load 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 ML20203K4151986-08-0606 August 1986 Final Deficiency Rept Re Incorrect Insulation Weights for Intake Pumping Station Piping.Initially Reported on 840221. Calculations for Insulation Weights Completed & Documented. Drawings Revised to Reflect New Weights ML20214H1861986-08-0101 August 1986 Final Deficiency Rept Re Error in Seismic Data Used in Auxiliary Control Bldg Design.Initially Reported on 840406. Revised Fixed Damped Response Spectra for Auxiliary Control Bldg Generated ML20212D3311986-07-30030 July 1986 Final Deficiency Repts Ncr Bln 3684 & Ncr Bln 4254 Re Conduit Support Stiffener Plates Not Installed Per Drawing. Initially Reported on 840510.Electrical QC & Engineering Personnel Retrained in Procedures ML20212B2001986-07-18018 July 1986 Final Deficiency Rept Re Unconservative Flange Qualification Analysis.Initially Reported on 841207.Caused by Misinterpretation of ASME Code Section Iii,Subsection NC-3658.1 (S76) ML20212B3731986-07-17017 July 1986 Part 21 & Revised Final Deficiency Rept Ncr Bln 2393 Re High Vibration Levels Measured for Bingham-Willamette Pumps. Initially Reported on 830622.Cause of Deficiency Unknown. Problem Does Not Represent Problem at Any TVA Facility 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 ML20203B9111986-07-0202 July 1986 Part 21 & Final Deficiency Rept Re Foreign Matl in C&D Batteries.Initially Reported on 840822.Batteries Will Be Replaced W/New Batteries Which Do Not Use Reigel Wrap in Const ML20207L1581986-06-18018 June 1986 Final Part 21 & Deficiency Rept Re Design Problems W/B&W Steam Generators.Initially Reported on 820830.Nozzles Supplying Auxiliary Feedwater to Internal Headers Capped Off & New External Headers Installed to Preclude Failures ML20206J8971986-06-11011 June 1986 Final Deficiency Rept Re Erroneous Dimensions for American Boa B1-0 Flexible Conduit Appearing in Electrical Design Std DS-E13.1.7.Initially Reported on 860515.Std Will Be Revised ML20211B1721986-05-28028 May 1986 Final Part 21 & Deficiency Rept Re Ruskin Fire Damper Installation & Closure Problems.Initially Reported on 840411.Caused by Improper Util Installation & Inadequate Testing by Mfg to Establish Closure Criteria ML20198K3101986-05-15015 May 1986 Revised Final Deficiency Rept Re Insulation Weights Assumed in Analyses for Valves & Pipe Fittings.Initially Reported on 840123.All Affected Piping Sys Will Be Reanalyzed. Rigorous Analysis Handbook Will Be Updated by 860601 ML20197H2581986-05-0808 May 1986 Part 21 Rept 135 Re Defect W/Lube Oil Sump Tank Foot Valve of Standby Diesel Generator.Caused by Extrusion of Liner Matl Due to Overpressurization.Corrective Actions Being Developed.List of Affected Sites Modified ML20155J1321986-05-0707 May 1986 Final Deficiency Rept Re Omissions to Auxiliary Feedwater Pump Drawings.Initially Reported on 820225.Required Piping Will Be Designed & Placed on Appropriate Drawings ML20203N4171986-04-30030 April 1986 Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications ML20203C2601986-04-0808 April 1986 Final Deficiency Rept Re Defect in Overlap Modeling Techniques.Initially Reported on 840801.Rigorous Analysis Handbook Revised to Incorporate Techniques in NUREG/CR-1980. Corrective Actions Will Be Done 6 Months Before Fuel Load ML20155C2761986-04-0404 April 1986 Final Deficiency Rept Re Use of Nonconservative Analyses of Insulation Weights for Valves & Pipe Fittings.Initially Reported on 840123.Corrective Actions Will Be Completed 6 Months Prior to Fuel Load ML20203A8751986-04-0303 April 1986 First Interim Deficiency Rept Re Failure to Adequately Disposition Reportable Nonconformances.Initially Reported on 850224.Peer Review Continuing.Final Rept Expected 1 Yr Before Unit 1 Fuel Loading 1997-05-01
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OFFTCIAL COPY
. TENNESSEE VALLEY AUTHORITY - F F: r; , ,1 CH ATTANOOG A, TENNESSEE 37401 400 Chestnut Street Tower II 5f , ,
f ' g ,l l5 June 11, 1981 l
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$0 065 0$$/ ,
- 1. J .1 G- Q Mr. James P. O'Reilly, Director ,-- JUL 3 019815 ~ --
Office of Inspection and Enforcement ' g'. % % ,,
U.S. Nuclear Regulatory Comission mamm oe Region II - Suite 3100 D 9 101 Marietta Street Atlanta, Georgia 30303 9g
Dear Mr. O'Reilly:
BELLEFONTE NUCLEAR PLANT UNIT 2 - NAVC0 SPOOL PIECE RADIOGRAPHIC DEFICIENCY
- NCR 1291 - FINAL REPORT The sub. ject nonconformance was initially reported to NRC-0IE Inspector R. W. Wright on November 14, 1980, in accordance with 10 CFR 50.55(e).
This was followed by our interim reports dated December 15, 1980, and February 25, 1981. A change in the submittal date for the final report was coordinated with R. C. Lewis by telephone on May 5, 1981. Enclosed is our final report. We consider 10 CFR Part 21 to be applicable to this nonconformance.
If you have any questions concerning this matter, please get in touch with D. L. Lambert at FTS 857-2581.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, ager Nuclear Regulation and Safety Enclosure cc: Mr. Victor Stello, Jr., Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Comission Washington, DC 20555
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.c. I j 8107310139 810611 PDR ADOCK 05000439 S PDR An Equal Opportunity Employer
ENCLOSURE BELLEFONTE NUCLEAR PLANT UNIT 2 NAVC0 SPOOL PIECE RADIOGRAPHIC DEFICIENCY NCR 1291 10 CFR 50.55(e)
FINAL REPORT Description of Deficiency During installation of Spent Fuel System piping in the unit 2 reactor building, a vendor weld was noticed to exhibit possible excess root reinforcement. The vendor (NAVCO) was requested to supply radiographs of the weld to assess the problem. TVA's review of tha vendor radiographs indicated possible excess root reinforcement of the weld and indicated as well that the vendor's radiograph / technique was not in keeping with TVA's interpretation of the Winter 1975 Addenda to Article 2 of ASME Section V.
Additional vendor radiogrr.phs (sent to though not requested by TVA) were also found to be suspect. This renders the adequacy of the welds (as well as radiographs) questionable. .
Safety Implications TVA's concern was the indication that the NAVC0 radiograph / technique may have been deficient. In order to preserve TVA's safety bias, the welds which were radiographed would have been considered deficient if the radiographe could not verify otherwise. Had the welds on these spool pieces proved to be inadequate, piping in which the spool pieces were used could have failed to properly maintain designated pressure boundaries.
Corrective Action In order to determine any general implications, as well as to conduct a i
review of NAVCO's radiographic technique, TVA sent inspectors to NAVC0 shops on March 2, 1981. These inspectors reviewed radiographic film previously reviewed by other TVA inspectors and the authorized nuclear inspector on various dates in the years 1976, 1977, 1978, and 1979. A ,
random sampling review of radiographic film was performed which included about 75 percent of the welded pipe joint connections found on 100 pipe L
weld joints. TVA's review of these radiographs did not disclose an obvious example of excessive root reinforcement. The inspectors reviewed to ensure that the density limitation of radiographs was compatible with Section V of j the ASME Code. The vendora's representatives explained that because of the l variation of the thickness and geometries of certain welds (and weld l pieces), a double loaded film pack must be used. These radiographs must be single and/or double viewed in order to obtain the optimum density. TVA's
! inspectors noted that several of the radiographs exceeded 4.0 maximum density when the film was double viewed. These radiographs, when viewed singly, however, were found to be acceptable in terms of the Code. The vendor's technique of film overlapping was also reviewed. Overlapping is used in order to obtain complete coverage,of the entire weld circumference. Thr inspectors observed that the 1 3 minimum density for l
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,c;ach. radiograph and the 2.6 total minimum d:nsity for a co9posito sat, that cannot be met because of overlapping, can readily be interpreted on the next er preceeding radiograph for that portion of the film in which this condition exists. This process of interpretation of overlapping radiographs represents an industrywide practice.
TVA's visual inspection of the initially identified suspect weld (weld No. 437) has revealed that it is, in fact excessively reinforced. As a result of the investigation, TVA concludes that the subject deficient radiograph represented an isolated case of improper density coupled with incorrect interpretation of overlapping. Weld No. 437 has been repaired.
The remaining radiographs of the subject deficiency have been reviewed in light of NAVCO's technique and were found to be within the ASME Code requirements. Therefore, these radiographs, as well as the welds they represent, are no longer considered questionable by TVA.
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