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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 ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20248A1671998-05-22022 May 1998 Interim Part 21 Re Enterprise DSR-4 & DSRV-4 Emergency diesel.Post-installation Testing Revealed,High Em/Rfi Levels Affected New Controllers,Whereas Original Controllers Were unaffected.Follow-up Will Be Provided No Later than 980731 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML17309A6211997-09-29029 September 1997 Part 21 Rept Re Final Disposition of Masterflow 713 & Embeco 636 Grout Nonconformance Reported by Master Builders,Inc. Licensee Continuing to Monitor shelf-life of Masterflow 713 & Embeco 636 Grouts Produced at Rancho Cucamonga 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 ML20137F3221997-03-26026 March 1997 Part 21 Rept Re Perry Nuclear Power Plant Experiencing False Trip of K600S K-Line Low Voltage Circuit Breaker w/SS-5 Solid State Trip Device.Breaker Removed from Svc & Returned to Abb for Analysis 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 ML20134H3361996-11-0505 November 1996 Part 21 Rept Re Defective Inner Thrust Bearing 1801461-01 Used in PSA 35 Mechanical Shock Arrestor Used as Restraint on Piping Sys for Nuclear Generating Plant.Lot of Defective Parts Located & Isolated to Three Customers 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 ML20083R9101995-04-26026 April 1995 Final Part 21 Rept Re Kepco,Inc Model RMX24-D-20804 Power Supplies in Which Transistors Q15 &/Or Q16 Failed to Open & R1 Was Open.Replacement of Transmitters w/XSIS-095 Along W/ Replacement of Electrolytic Capacitors Provides Solution ML18038A8971994-09-0707 September 1994 Part 21 Rept Re Defect in Latching Mechanism of Potter & Brumfield Relay on C&D High Voltage Shut Down Alarm Assembly Printed Circuit Boards.Pull Test on Relay Reset Button Incorporated Into Receiving Insp Procedures ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical 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 ML20059A7181993-10-19019 October 1993 Part 21 Rept Re Defective Rocker Arms Supplied to TU & Clei. Rocker Arms Machined & Inspected to Incorrect Print & Discovered at Tu.Defective Rocker Arms Recalled from Nuclear Customers.No Corrective Action Required at Respective Utils ML20056D7071993-07-15015 July 1993 Part 21 Rept Re Reportable defect-75 PSIG Relief Check Valve 1 Npt,Emd 9521844,Kepner 416C-1-75 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 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 ML20127D1491992-09-0404 September 1992 Part 21 Rept Re Defect in Component of DSRV-16-4 Enterprise Standby DG Sys Jacket Water Pump Shaft.Caused by Incorrect Tapers Machined on Shaft Due to Vendor Mismatching.All Affected Shafts Recalled & Quality Insp Plans Changed PY-CEI-NRR-1518, Corrected Part 21 Rept Re Defects in MSIV Poppets Supplied by Atwood & Morrill Co,Inc,Originally Submitted Via .Corrects Info in Corrective Action Section to Indicate That Poppet S/N 4 Not S/N 3 Installed at Facility1992-07-0101 July 1992 Corrected Part 21 Rept Re Defects in MSIV Poppets Supplied by Atwood & Morrill Co,Inc,Originally Submitted Via .Corrects Info in Corrective Action Section to Indicate That Poppet S/N 4 Not S/N 3 Installed at Facility ML17289A6971992-06-26026 June 1992 Amend 1 to Part 21 Rept 158 Re gear-wear Induced Failures in engine-driven Jacket Water Pump in DSRV-16-4 Standby DG Sys. Initially Reported on 911029.Grand Gulf Station Observed Wear Characteristics in as Little as 500 Operating Hours ML20102B2071992-06-24024 June 1992 Part 21 Rept Re Cracking of Stellite 21 Hardfacing on Guide Nose of Poppets Supplied as Part of MSIV Leakage Improvement Mod.Initially Reported by Clei on 920522. Recommends That Liquid Penetrant Exam Be Performed ML20101G9211992-06-19019 June 1992 Part 21 Rept Re Rotated Fuel Assemblies Sometimes Inappropriate for Modern Type Fuel Designs.Reevaluation Concluded That Inadvertently Rotated Fuel Assembly for BWR 4/5 C-lattice Plant Could Not Exceed TS Safety Limit MCPR PY-CEI-NRR-1516, Part 21 Rept Re Defects in MSIV Poppets Supplied by Atwood & Morrill Co,Inc.Intially Reported on 920522.Measures Will Be Established to Ensure That Adequate Repair Methods Are Employed During Future Repairs of Modified MSIV Poppets1992-06-19019 June 1992 Part 21 Rept Re Defects in MSIV Poppets Supplied by Atwood & Morrill Co,Inc.Intially Reported on 920522.Measures Will Be Established to Ensure That Adequate Repair Methods Are Employed During Future Repairs of Modified MSIV Poppets ML20097H1531992-05-22022 May 1992 Part 21 Rept Re Defect in MSIV Poppets Supplied to Plant by Atwood & Morrill Co,Inc.Post Weld Heat Treatment Prescribed & Performed for Poppet to Alleviate Concerns Re Residual Stresses Present.Next Rept Will Be Submitted within 30 Days ML20094L1271992-03-13013 March 1992 Amend 1 to Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner.Initially Reported on 920115.Caused by Liner/ Block Fit & Localized Matl Microstructure.All Drawings & Specs Revised to Address Matl Design Requirements ML20087D3191992-01-14014 January 1992 Potential Part 21 Rept Re Problems W/Elmwood/Fasco Contactor Carriers Breaking in Contactor Model 30-FO-30. Caused by Distortion/Shrinkage of Molded Phenolic Contactor Carrier.Replacement Contactors Installed ML20081F6091991-04-23023 April 1991 Part 21 Rept Re Edward Controlled Closure Check Valves & Testable Piston Check Valves Dashplate Bolt Failures Due to Rapid Valve Opening or Impulsive Differential Pressure Surge Across Dashplate.Design Changes Recommended PY-CEI-NRR-1303, Part 21 Rept Re Finding That Nitrile Rather than Ethylene Propylene Diene Monomer (Epdm) Used as Seal Matl in Several E-sys Hydraulic Snubbers.Proper Seal Matl (Epdm) Used to Rebuild Snubbers & Leaking Valves Repaired1991-02-0404 February 1991 Part 21 Rept Re Finding That Nitrile Rather than Ethylene Propylene Diene Monomer (Epdm) Used as Seal Matl in Several E-sys Hydraulic Snubbers.Proper Seal Matl (Epdm) Used to Rebuild Snubbers & Leaking Valves Repaired ML20065T1661990-12-19019 December 1990 Part 21 Rept Re Reportable Event Concerning Chilled Water Sys at Plant.Initially Reported on 901030 & 1130.Util Notified of Results of Evaluation & Reported Addl Details, Per 10CFR50.72 PY-CEI-NRR-1281, Part 21 Rept Re Failure of Several Asco Scram Solenoid Pilot Valves.Initially Reported on 901211.Faulty Valves Limited to Single Production Run.Installed Valves from Subj Production Run Replaced1990-12-14014 December 1990 Part 21 Rept Re Failure of Several Asco Scram Solenoid Pilot Valves.Initially Reported on 901211.Faulty Valves Limited to Single Production Run.Installed Valves from Subj Production Run Replaced ML17262A2621990-11-30030 November 1990 Part 21 Rept Re Chilled Water Sys.Initially Reported on 901030.Evaluation of Perry Plant Will Be Sent by 901230 ML17223A5941990-03-0909 March 1990 Errata to 900126 Part 21 Rept Re Anchor/Darling Actuators Incorporating Use of Teldyne-Republic four-way Valves.Lists Plants Inadvertently Left Out in Original Rept 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 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 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 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 ML20206M4401988-11-21021 November 1988 Deficiency Rept Re Misapplication of Raychem Criteria in Selection of Some Matl Used in Electrical Cable Field Splice Kits.Initially Reported on 880920.Investigation Is in Process.Final Rept Will Be Submitted by 881222 ML20205C9291988-10-18018 October 1988 Part 21 & Deficiency Rept Re Valves Installed Opposite to Direction of Flow,Per 10CFR21 & 50.55 Requirements.Item Being Tracked by MTS EAI B-5115 & Scheduled for Completion 881030 ML20205D6651988-10-18018 October 1988 Part 21 & Deficiency Rept Re Penetration Seals Found Not to Be Watertight.Initially Reported on 880609.Water Leakage Tests Performed on Unit Upper Cable Spreading Room Seals. All Floor Penetration Seal Assemblies Repaired 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 ML20155D6471988-09-28028 September 1988 Deficiency Rept Re Valves Installed Opposite to Direction of Flow.Initially Reported on 880629.Final Rept Delayed Until 881020 ML20207J7361988-09-20020 September 1988 Interim Deficiency Rept Re Misapplication of Vendor Criteria in Selection of Some Matl Used in Electrical Cable Field Splice Kits.Initially Reported on 880601.Final Rept Expected Prior to 881123 ML20153E2271988-09-0101 September 1988 Part 21 & Deficiency Rept Re ESF Filtration Unit Bolts. Initially Reported on 880628.Contractor Conducted Training Session for Personnel to Stress Importance of Clarifying Incomplete Drawing Info & Requirements of Bolting Procedure 1999-04-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20217K8041999-09-30030 September 1999 Rev 1 to Vegp,Unit 2 Cycle 7 Colr ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico ML20217K7741999-09-30030 September 1999 Rev 1 to Vegp,Unit 1 Cycle 9 Colr ML20217K4591999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With PY-CEI-NRR-2437, Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With ML20216E5061999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Vegp,Units 1 & 2. with PY-CEI-NRR-2429, Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With NUREG-1482, SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant1999-08-0909 August 1999 SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant PY-CEI-NRR-2424, Monthly Operating Rept for July 1999 for Perry Npp.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Perry Npp.With ML20210P9841999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20210J3851999-07-28028 July 1999 Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval PY-CEI-NRR-2416, Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With ML20209H1211999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20196A1951999-06-17017 June 1999 Instrument Drift Analysis ML20207G2741999-06-0707 June 1999 Safety Evaluation Concluding That Firstenergy Flaw Evaluation Meets Rules of ASME Code & That IGSCC & Thermal Fatigue Crack Growth Need Not Be Considered in Application ML20195G1731999-05-31031 May 1999 Monthly Operating Repts for May 1999 for VEGP Units 1 & 2. with ML20196F9711999-05-31031 May 1999 Owner Rept for ISI for Vogtle Electric Generating Plant, Unit 1 Eighth Maint/Refueling Outage PY-CEI-NRR-2409, Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2393, Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored1999-05-12012 May 1999 Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored ML20206G6451999-05-0303 May 1999 Safety Evaluation Authorizing Requests for Relief IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp PY-CEI-NRR-2399, Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With ML20206N2141999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20206E2261999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternatives Will Result in Acceptable Level of Quality & Safety.Authorizes Use of Code Case N-504 for Weld Overlay Repair of FW Nozzle Weld at Pnpp & Use of Table IWB-3514 ML20206D7911999-04-23023 April 1999 Rev 6 to PDB-F0001, COLR for Pnpp Unit 1 Cycle 8,Reload 7 ML20206A6561999-04-21021 April 1999 Safety Evaluation Authorizing Licensee Re Rev 9 to First 10-year ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML20205P4371999-04-15015 April 1999 Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding 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 ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205G4221999-03-31031 March 1999 Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 ML20206D8461999-03-31031 March 1999 Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7 Cycle 8 ML20206C2291999-03-31031 March 1999 Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2 ML20205Q8081999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Vegp,Units 1 & 2. with ML20205A9581999-03-31031 March 1999 Rev 0 to VEGP Unit 1 Cycle 9 Colr PY-CEI-NRR-2389, Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With ML20205D3101999-03-26026 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-58 ML20205C3761999-03-26026 March 1999 Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 PY-CEI-NRR-2369, Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 9902271999-03-0303 March 1999 Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 990227 PY-CEI-NRR-2372, Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With ML20207K6051999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20209H3951999-02-15015 February 1999 Rev 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2 ML20209H4091999-02-15015 February 1999 Rev 1 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2 ML20203A5961999-02-0202 February 1999 Safety Evaluation Accepting Licensee Proposed Revs to Responsibilities of Plant Operations Review Committee as Described in Chapter 17.2 of USAR ML20202H9851999-01-29029 January 1999 Safety Evaluation Accepting Rev 8 to First 10-year Interval Inservice Insp Program & Associated Requests for Relief for Vogtle Electric Generating Plant,Unit 1 ML20203A5211999-01-27027 January 1999 Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps ML20199F8041999-01-13013 January 1999 Corrected Pages to VEGP-2 ISI Summary Rept for Spring 1998 Maint/Refueling Outage ML20198R8921999-01-0707 January 1999 SER Accepting Licensee Proposed Amend to TSs to Delete Reference to NRC Policy Re Plant Staff Working Hours & Require Administrative Controls to Limit Working Hours to Be Acceptable ML20199E7561998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20198S1781998-12-31031 December 1998 SER Re Second 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief for Southern Nuclear Operating Co,Inc Units 1 & 2 ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 1999-09-30
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Pa CIFIC SCIENTIFIC HTL/ KIN-TECH DIVISION oVember 51M 22715 Savi Ranch Parkway, P.o. Box 87019 Yorba Linda, CA 92686-8719 Attn: Document Control Desk p,x Q2gj2g U.S. Nuclear Regulatory Commission l Washington, DC 20555 I
Reference:
Event # 3108910/3/96 In accordance with 10CFR 21 - Reporting of Defects and Noncompliance the following report is submitted by:
Pacific Scientific i HTL / Kin-Tech Division 22715 Savi Ranch Parkway Yorba Linda, CA 92887-4609 Steve Kahm Director of Quality Control The defective part is an Inner Thrust Bearing 1801461-01 used in a PSA 35 Mechanical Shock Arrestor 1801112 ** manufactured by Pacific Scientific. The Mechanical Shock Arrestor ( snubber ) is used as a restraint on piping systems for a Nuclear Generating Plant.
The defective Inner Thrust Bearing was supplied by :
Markall 3207 W. Pendleton Ave Santa Ana, CA 92704 '
PSA 35, Cracked Inner Thrust Bearings - P/N 1801461-01 Cracks were found in a PSA 35 Snubber InnerJhrust Bearings -
1801461-01. This indicated a breakdown in the NDT check in manufacturing this part.
ff 120043 Page 1 of 3 9611140064 961105 PDR ADOCK 05000424 S PDR
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l A snubber acts like a rigid strut when activated and limits the piping movement to i .060 inches between 3 to 33Hz at full rated load. The worst case failure mode is for the cracked Inner Thrust Bearing to
, disintegrate or distort under load during a sesmic event and cause the snubber to become a rigid strut. The failed snubber would protect the l piping system. But the piping system would be under stress when the plant returned to a shut down condition. The snubber would not be able to telescope and allow the pipe to return to the cold set position but remain in the hot set position. !
l The following are the dates for this event:
l 10/1/96 Trouble and Failure Report (TFR) was written up on the l_ defective 1801461-01 Thrust Bearing.
l 10/3/96 Called NRC OPERATION CENTER 301 816-5100 Mr. Doug Weaver assigned an Event # 31089.
The defective Inner Thrust bearings has been isolated to three nuclear plants.
l Attached is a location of the plants to which PSA 35 snubbers were supplied with potential defective thrust bearings. The USA plants are returning their snubbers l for inspection, thrust bearing replacement and test. We are still working out the return of the snubbers shipped to Wolsong 3 in Korea.
! The NDT acceptance after heat treat should have rejected the cracked parts.
I This necessitated a review of the approved vendors NDT procedures and personnel. On 10/8/96 Pacific Scientific surveyed the NDT vendor and reviewed their NDT program and tested their present NDT personnel and found their
! program' acceptable. The individual who accepted the bad lot of parts had been l
fired before our visit. i l
L Internal Purchasing and Assembly Outline Procedures will be changed to requiring an additional in-house NDT for parts in question. In addition an assembly visual check of the thrust bearings inspection point for the PSA 35 and L PSA 100 mechanical shock arrestor assemblies will be added. Expect this I procedural changes to be completed 11/14/96.
i
[ Page 2 of 3 1'
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Assembled a PSA 35 with a defective thrust bearing and was successfully tested at different frequencies for a total of 5000 full rated load life cycle. Under these extreme conditions the test unit demonstrated that the snubber still met Design Specification requirements even with a defective thrust bearing. Most snubbers when removed during an outage should normally not see at most 5-10 full rated load cycles. A PSA 35 snubber with a defective thrust bearing is considered operable for a sinale outaae. Recommend that units with a potential defective thrust bearing be returned for examination. But if the unit was installed we recommend that it be removed at the next outage and sent back to the factory for ,
examination.
The lot of defective parts have been located .nd isolated to only three customers. The two USA plants snubbers sere not installed and the units are being returned to Pacific Scientific. For the Korean Wolsong 3 plant we are still working out a replacement schedule.
A final report will be completed by November 30,1996 for submittal.
l Regards,
%\Steve Kahm Quality Assurance Director HTL / Kin-Tech Division !
Page 3 of 3
- LISTING OF UTILITIES WHO HAVE BEEN SHIPPED UNITS ',
WITH SUSPECT 1801461-01 THRUSTBEARINGS .
PSA 35 ~
C of C DATE PIN CUSTOMER ANC QTY S/N COMMENTS 3396 12/21/95 GEORGIA POWER 533 35L -
1801126-05 Vogtle Nuclear Generating St 443981 2 Faxed letter of Notification 3397 1/11/96 534 35L UNITS BEING RETURNED TO PSCO 3401 1/25/96 1801112-13 CLEVELAND ELECTRIC 444738 2 13171-13172 Faxed letter of Notification Perry Nuclear Power Plant UNITS BEING RETURNED TO PSCO 3413 3/19/96 1801112- KOREA ELECTRIC COMPA 443382 9 13173-13181 Faxed letter of Notification Wolsong 3 WAREHOUSED / NOT INSTALLED WORKING WITH UTILITY ON REPLACEMENT SCHEDULE k
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