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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20203H9891997-12-12012 December 1997 Part 21 Rept Re Potential Manufacturing Defect of Enterprise DSR-4 & DSRV-4 Edgs.Cooper Energy Svcs Supplied 1A-7840 Adjusting Screw to Affected Utils & Sites.River Bend Station Replaced W/Acceptable Assemblies ML20140G4481997-05-0101 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 ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause 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 ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs 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 B14544, Update to 900827 Rept of Substantial Safety Hazard Re GE Custom 8000 Horizontal Induction Motors,Reported Per 10CFR21 for Unit 3.Util Has Determined,As Part of Review of in 91-007 That Subj GE Motors Also Used at Units 1 & 21993-08-11011 August 1993 Update to 900827 Rept of Substantial Safety Hazard Re GE Custom 8000 Horizontal Induction Motors,Reported Per 10CFR21 for Unit 3.Util Has Determined,As Part of Review of in 91-007 That Subj GE Motors Also Used at Units 1 & 2 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 ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML13316A1381992-11-25025 November 1992 Part 21 Rept Re Potential Problem W/Cylinder Heads Cast Prior to 840801 in Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Caused by Inadequate Casting Wall Thickness at Tapped Hole.Oil Analysis Should Be Performed Monthly ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ET-NRC-92-3707, Part 21 Rept Re Degraded Performance Condition of Westinghouse Protection Sys Overtemp Delta Temp Reactor Trip Function.Issue Not Reportable,Per 10CFR21,based on Diversity of Westinghouse Protection Sys,Per WCAP-73061992-06-15015 June 1992 Part 21 Rept Re Degraded Performance Condition of Westinghouse Protection Sys Overtemp Delta Temp Reactor Trip Function.Issue Not Reportable,Per 10CFR21,based on Diversity of Westinghouse Protection Sys,Per WCAP-7306 ML13316A0841992-01-15015 January 1992 Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner in Diesel Engine of DSR-48 & DSRV-16-4 Standby Diesel Generator Sys.Investigation Continuing & Expected to Be Complete on 920301 ML13316A0791991-06-19019 June 1991 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generator Sys Involving Intake & Exhaust Power Valve Springs Mfg by Associated Spring.Recommends That Springs Be Inspected on Periodic Basis ML13316A0631990-07-19019 July 1990 Part 21 Rept Re Potential Problem W/Starting Air Admission Valve in Starting Air Sys.Caused by Air Start Piston Sticking in Air Start Valve Cap.Recommendations for Corrective Actions Forthcoming ML20055E4831990-06-29029 June 1990 Part 21 Rept Re Defective Steam Generators Supplied by Westinghouse.Util Will Continue to Rept Any Defects or Other Info Reportable Under 10CFR21 Upon Discovery &/Or During Litigation ML20043G7641990-05-22022 May 1990 Part 21 Rept Re Potential Defect W/Speed Transmitter in Diesel Engine Control Panel of Dsrv Standby Diesel Generator.Estimate of Completion of Corrective Actions Not Possible,Since Correction Made by Other Companies ML20034A0791990-04-0404 April 1990 Problem Investigation Rept 1-C90-0075:on 900203-04,two of Three Pressurizer Safety Valves Removed from Pressurizer.One Valve Failed to Meet Setpoint Requirement.Caused by Setpoint Drift.Also Reported Per Part 21 ML17348A1621990-03-27027 March 1990 Part 21 Rept Re Matls W/Programmatic Defects Supplied by Dubose Steel,Inc.Customers,Purchase Order,Items & Affected Heat Numbers Listed ML20006A3611990-01-17017 January 1990 Part 21 Rept 152 Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generator Sys Supplied to Listed Sites by Cooper Industries.Qualified Replacement Valve in Process of Being Specified.Info Will Be Available by 900215 ML13316A0401989-11-28028 November 1989 Part 21 Rept 151 Re Intake Rocker Arm Assembly of Standby Diesel Generator.Deficiency Covers Potential Interface Between Connector Push Rod & End Socket of Rocker Arm. Initially Reported on 891013.Rocker Arm Sketch Encl NRC-89-3462, 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 Shipment1989-10-0909 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 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 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 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 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 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 ML20151A2801988-03-30030 March 1988 Part 21 Rept Re Broken/Cracked Springs in Plant Pressure Valves.Magnetic Particle Exam of Springs from 18 Valves on Unit 2 Performed in Jan 1988 & Spring from Valve BS-02893 Rejected for Linear Indication.Insp Completed ML16342C3461987-12-0303 December 1987 Followup to Gulf States Utils Part 21 Rept Re Wound Rotor Pole in Generator Unit of Standby Diesel Generator.Generator Mfg by NEI Peebles - Electric Products,Inc & Supplied to Util by Imo Delaval,Inc.Failure Analysis Being Conducted ML20236E4851987-07-27027 July 1987 Corrected Part 21 Rept Re Broken/Cracked Springs in Consolidated Type 3787WA Valves.Valves Incorrectly Identified as Type 3727WA in 870203 & 0702 Ltrs.Unit 1 Springs Received Magnetic Particle Exam 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 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 ML20214E1971987-02-0303 February 1987 Annotated Part 21 Rept Re Cracked D34 Springs in Alco Spring Industries,Inc Type 3727WA Safety Valves.All Springs Being Examined.Springs Displaying Relevant Indications Will Be Replaced ML20214M3181986-09-0404 September 1986 Potential Part 21 Rept Re Contromatics Actuator W/Jackscrew/ Handwheel Emergency Override Operator.Jackscrew/Handwheel Should Be Used for Emergency Manual Operation Only.Encl Ltr Also Sent to Listed Utils/Ae Firms 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 ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires 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 ML20214D5071986-02-19019 February 1986 Final Significant Deficiency Rept SD 414/86-01 Re Emergency Diesel Engine 2B Main Bearing 7 Failure.Initially Reported on 860116.Caused by Misinstallation by Mfg,Sand Blast Grit &/Or Oil Contamination.Engine Rebuilt ML20137P2411986-01-16016 January 1986 Significant Deficiency & Part 21 Rept SD 414/86-02 Re Valve Spring Failures on Tdi DMRV-16-4 Diesel Engines.Initially Reported on 851217.Springs Will Be Changed During First Appropriate Refueling Outage ML20137P2381986-01-16016 January 1986 Significant Deficiency Rept SD 414/86-01 Re Failure of Main Bearing Shell 7 During Break in Run of Tdi Unit 2B Diesel Generator.Initially Reported on 851219.Installation Procedures Enhanced.Crankshaft Journal Cleaned ML20137N4991985-12-26026 December 1985 Significant Deficiency Rept 414/85-12 Re Missing Spring in Air Actuator of Pressurized Porv.Initially Reported on 851206.Valve W/Missing Spring Replaced.Investigation Continuing ML20137K9601985-12-10010 December 1985 Part 21 Rept Re Actuators Having Only One of Required Two Springs Which Could Result in Reduction of Integrity of Reactor Coolant Boundary.Valves Supplied to McGuire Units 1 & 2 & Catawba Unit 2.Catawba Unit 2 Valve Corrected ML20138B7201985-11-22022 November 1985 Final Significant Deficiency Rept SD 414/85-10 Re Failure of Hydrogen Skimmer Fan Motors Supplied by Joy Mfg Co.Initially Reported on 850626.Cause Undetermined.Fan Motors Reassembled,Retested & Reinstalled 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 ML20136E5821985-11-0505 November 1985 Significant Deficiency Rept 414/85-11 Re High Priority Mods Required Prior to Fuel Loading.Administrative Controls Implemented to Control Personnel Access to Penetration Area During in-core Instrument Movement ML20198C2081985-10-24024 October 1985 Significant Deficiency Rept SD 414/85-11 Re Unconsidered Effects of Radiation Streaming Through Reactor Bldg Penetrations from post-LOCA Atmospheric Activity.Initially Reported on 850924 1999-04-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J1891999-10-0101 October 1999 Safety Evaluation Supporting Exemption from 10CFR54.17(c)re Schedule to Apply for Renewed Operating Licenses ML20212A6271999-09-30030 September 1999 Rev 0 to WCAP-15243, Anaylsis of Capsule V & Capsule Y Dosimeters from Duke Energy Catawba Unit 2 Reactor Vessel Radiation Surveillance Program ML20217H0201999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Catawba Nuclear Station,Units 1 & 2 05000414/LER-1999-004-01, :on 980906,error During Tagout Caused de-energization of Vital Bus & Actuation of Ltop.Caused by Inadequate Work Practices.Individuals Involved Were Counseled1999-09-27027 September 1999
- on 980906,error During Tagout Caused de-energization of Vital Bus & Actuation of Ltop.Caused by Inadequate Work Practices.Individuals Involved Were Counseled
05000413/LER-1999-015, :on 990616,discovered That Auxiliary Bldg Filtered Ventilation Exhaust Sys Was Inoperable.Caused by Improperly Positioned Vortex Damper.Damper Was Repositioned Correctly & Sys Was Retested Successfully1999-09-27027 September 1999
- on 990616,discovered That Auxiliary Bldg Filtered Ventilation Exhaust Sys Was Inoperable.Caused by Improperly Positioned Vortex Damper.Damper Was Repositioned Correctly & Sys Was Retested Successfully
ML20212G2511999-09-22022 September 1999 Safety Evaluation Supporting Amends 180 & 172 to Licenses NPF-35 & NPF-52,respectively 05000413/LER-1999-008, :on 990610,operations Prohibited by TS 3.5.2, Was Violated.Caused by Inoperable Centrifugal Charging Pump. Operators Swapped to CCP 1A & Sys Parameters Were Returned to Normal.With1999-09-21021 September 1999
- on 990610,operations Prohibited by TS 3.5.2, Was Violated.Caused by Inoperable Centrifugal Charging Pump. Operators Swapped to CCP 1A & Sys Parameters Were Returned to Normal.With
05000414/LER-1999-005-02, :on 990727,missed Emergency DG TS Surveillance Concerning Verification of Availability of Offsite Power Sources,Was Declared.Caused by Defective Procedure.Revised Affected Procedure1999-09-20020 September 1999
- on 990727,missed Emergency DG TS Surveillance Concerning Verification of Availability of Offsite Power Sources,Was Declared.Caused by Defective Procedure.Revised Affected Procedure
05000413/LER-1999-009, :on 990518,inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits Was Noted. Caused by Inadequate Retest Following Surveillance Test Failure.Valve Was Retested & Returned to Service1999-09-15015 September 1999
- on 990518,inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits Was Noted. Caused by Inadequate Retest Following Surveillance Test Failure.Valve Was Retested & Returned to Service
ML20216E5401999-09-0707 September 1999 Special Rept:On 990826,discovered That Meteorological Sys Upper Wind Speed Cup Set Broken,Causing Upper Wind Channel to Be Inoperable.Cup Set Replaced & Channel Restored to Operable Status on 990826 05000413/LER-1999-014, :on 990816,missed Surveillances & Operation Prohibited by TS Was Noted.Caused by Defective Procedures or Programs Inappropriate TS Requirements.Affected Procedures/ Programs Were Revised & Testing Was Performed1999-09-0101 September 1999
- on 990816,missed Surveillances & Operation Prohibited by TS Was Noted.Caused by Defective Procedures or Programs Inappropriate TS Requirements.Affected Procedures/ Programs Were Revised & Testing Was Performed
05000414/LER-1999-004, :on 990616,CIV 2NM-221A Was Returned to Svc Without Testing,As Required by TS 3.6.3.Caused by Programmatic Deficiency.Test Procedure Has Been Revised & Subject Valve Was Successfully Tested & Returned to Svc1999-09-0101 September 1999
- on 990616,CIV 2NM-221A Was Returned to Svc Without Testing,As Required by TS 3.6.3.Caused by Programmatic Deficiency.Test Procedure Has Been Revised & Subject Valve Was Successfully Tested & Returned to Svc
ML20212B4711999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 05000414/LER-1999-003, :on 990612,unplanned Actuation of ESFAS Occurred Due to a SG High Level.Caused by Inadequate Procedural Guidance.Msiv 2SM-7 Was Closed & SG 2A Level Was Returned to Normal1999-08-31031 August 1999
- on 990612,unplanned Actuation of ESFAS Occurred Due to a SG High Level.Caused by Inadequate Procedural Guidance.Msiv 2SM-7 Was Closed & SG 2A Level Was Returned to Normal
ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20217H0321999-08-31031 August 1999 Revised Monthly Operating Rept for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 05000413/LER-1999-012, :on 990727,adverse Sys Interaction Between Annulus Ventilation Sys & Auxiliary Building Ventilation Sys Was Discovered.Caused by Inadequate Design.Compensatory Actions Developed & Implemented.With1999-08-26026 August 1999
- on 990727,adverse Sys Interaction Between Annulus Ventilation Sys & Auxiliary Building Ventilation Sys Was Discovered.Caused by Inadequate Design.Compensatory Actions Developed & Implemented.With
ML20211A9791999-08-20020 August 1999 Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2 ML20211C1291999-08-17017 August 1999 ISI Rept Unit 1 Catawba 1999 RFO 11 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20210U8341999-08-13013 August 1999 Safety Evaluation Supporting Amends 179 & 171 to Licenses NPF-35 & NPF-52,respectively ML20210R1051999-08-0606 August 1999 Special Rept:On 990628,cathodic Protection Sys Was Declared Inoperable After Sys Did Not Pass Acceptance Criteria of Bimonthly Surveillance.Work Request 98085802 Was Initiated & Connections on Well Anode Were Cleaned or Replaced ML20212B4871999-07-31031 July 1999 Revised Monthly Operating Rept for July 1999 for Catawba Nuclear Station,Units 1 & 2 ML20210S2891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2 05000413/LER-1999-009, :on 990518,inoperability of Containment Valve Injection Water Sys Valve Was Noted in Excess of TS Limits. Caused by Inadequate Testing Following Surveillance Test Failure.Valve Was Retested & Restored to Service1999-07-19019 July 1999
- on 990518,inoperability of Containment Valve Injection Water Sys Valve Was Noted in Excess of TS Limits. Caused by Inadequate Testing Following Surveillance Test Failure.Valve Was Retested & Restored to Service
05000414/LER-1999-004-02, :on 990610,violation of TS 3.6.3 Was Noted Due to CIV 2NM-221A Being Returned to Service Without Testing. Caused by Procedure Deficiency.Civ 2NM-221A Was Tested & Returned to Operable Status1999-07-15015 July 1999
- on 990610,violation of TS 3.6.3 Was Noted Due to CIV 2NM-221A Being Returned to Service Without Testing. Caused by Procedure Deficiency.Civ 2NM-221A Was Tested & Returned to Operable Status
ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation 05000414/LER-1999-003-02, :on 990612,unplanned Actuation of Esfa Sys Due to a SG High Level Was Noted.Caused by Inadequate Procedural Guidance.Long Term Corrective Actions to Prevent Recurrence of Event Are Being Developed1999-07-0808 July 1999
- on 990612,unplanned Actuation of Esfa Sys Due to a SG High Level Was Noted.Caused by Inadequate Procedural Guidance.Long Term Corrective Actions to Prevent Recurrence of Event Are Being Developed
ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20209H4501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2 ML20210S2951999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Catawba Nuclear Station,Units 1 & 2 05000414/LER-1999-002-03, :on 990504,plant Was Forced to Shutdown as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Affected Piping Was Cleaned & Flow Tested1999-06-0303 June 1999
- on 990504,plant Was Forced to Shutdown as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Affected Piping Was Cleaned & Flow Tested
ML20209H4561999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20196A0001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20206P5201999-05-14014 May 1999 Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206N8391999-05-0404 May 1999 Rev 16 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr ML20196A0041999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206R1811999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206N8261999-04-22022 April 1999 Rev 15 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr. Page 145 of 270 of Incoming Submittal Not Included ML20205S5551999-04-21021 April 1999 Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions 05000413/LER-1999-004, :on 990310,operation Prohibited by TSs Was Noted.Caused by Incorrect TS Requirements for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation.Submitted Lar.With1999-04-12012 April 1999
- on 990310,operation Prohibited by TSs Was Noted.Caused by Incorrect TS Requirements for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation.Submitted Lar.With
ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205N3651999-04-12012 April 1999 Safety Evaluation Accepting IPE of External Events Submittal ML20205N2381999-04-0909 April 1999 Safety Evaluation Supporting Amends 178 & 170 to Licenses NPF-35 & NPF-52,respectively ML20205N2121999-04-0808 April 1999 Safety Evaluation Supporting Amends 177 & 169 to Licenses NPF-35 & NPF-52,respectively ML20206R1931999-03-31031 March 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20205P9521999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Catawba Nuclear Station,Units 1 & 2 ML20205B3101999-03-26026 March 1999 Safety Evaluation Supporting Amends 176 & 168 to Licenses NPF-35 & NPF-52,respectively 1999-09-07
[Table view] |
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December 30, 1981 3 7 3-4o s a N
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![)9 g/g Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission l
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Re: Catawba Nuclear Station Unit 2
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%/'jg-pgi Docket No. 50-414
Dear Mr. O'Reilly:
Pursuant to 10 CFR 50.55e, please find attached Significant Deficiency Report SD 414/81-30.
Very truly yours,
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William O. Parker, Jr ROS/php Attachment cc: Director Mr. Robert Guild, Esq.
Office of Inspection and Enforcement Attorney-at-Law U. S. Nuclear Regulatory Commission 314 Pall Mall Washington, D. C. 20555 Columbia, South Carolina 29201 NRC Resident Inspector Palmetto Alliance Catawba Nuclear Station 2135 Devine Street Columbia, South Carolina 29205 AO 0500 f4 PDR
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CATAWBA NUCLEAR STATION REPORT NUMBER: SD-414/81-30 REPORT DATE: December 30, 1981 FACILITY:
Catawba Nuclear Station Unit 2 IDENTIFICATION OF DEFICIENCY:
Material in question is 8" S-40 SA312 TP304 Stainless Steel Pipe, Heat
- 181033 manufactured by SWEPC0 Tube Corporation located in Clifton, New Jersey. Areas of the pipe are below minimum wall thickness.
INITIAL REPORT:
On December 1,1981, A. Ignatonis, NRC Region II, Atlanta, Georgia was notified of the deficiency by W. O. Henry and A. W. Roy of Duke Power Company, Charlotte, North Carolina.
CG4P0NENT AND/0R SUPPLIER:
Material identified as having the deficiency is 20 feet, 8" S-40 SA312 TP304 EFW Stainless Steel Pipe Heat #181033.
Material was supplied, Duke P.O. E-38887, by Gulfalloy Houston, Texas (Distributor) who procured from SWEPC0 Clifton, New Jersey, P.O. #29-27-905551. SWEPC0 S/0 #M-3225-8, Heat #181033.
DESCRIPTION OF DEFICIENCY:
This pipe, along with 14 other pieces of pipe, were sent to ITT Grinnell in Kernersville, NC, to be bent. During their check by UT for wall thick-ness in the bend area, they found some areas below material specification minimum wall thickness.
The pipe in question was returned to Catawba and nonconformed.
Subsequent micrometer measurements showed a portion of this pipe to have wall thickness ranging from a high of.289" to a low of.277".
For this size and schedule of pipe, specifications require a nominal wall thickness of.322" and a minimum wall thickness of.282".
Pipe in some areas is at least.005" below minimum wall thickness (all in the welded area).
Other sections of pipe with this heat number have been checked for wall thickness and found to have similar thinning but with no wall thickness less than.277".
ANALYSIS OF SAFETY IMPLICATIONS:
The starting material for this pipe was ordered to.035" thickness with a minus of.010".
SWEPC0 check of this material upon receipt revealed a minimum of.295".
With this relatively thin starting material, the weld finishing operation reduced the wall thickness in some areas to below mininum thickness required by the material specification.
'e t'...n, g
Based on engineering analysis under Duke system operating conditions, it-has been determined that this thinning would not have led to a pipe failure
'in our applications. The Containment Spray (NS) Systems where this would have been installed have been qualified on the basis of Schedule 20 pipe instead of. Schedule 40 (.205" vs. 322" wall thickness).
CORRECTIVE ACTION:
The piece of pipe in questions is not to be used. The pipe was sectioned and one section is being sent-to SWEPC0 for analysis. Upon completion of-analysis, recommendations will be made to prevent this condition from occurring in the future.. A follow-up report will be submitted to NRC by April 1, 1982.
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