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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 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 ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected 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 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 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 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 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 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 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 ML20095J7981992-04-29029 April 1992 Part 21 Rept Re Failure of Anchor Darling Swing Check Valve to Move Freely Through Entire Range of Motion.Caused by Insufficient Clearance Between Swing Arm & Shaft Bushings. Valve Repaired Onsite by Vendor ML20090L8801992-03-18018 March 1992 Part 21 Re Cracked Piston Castings Received from Acme Foundry,Fairbanks Morse & General Casting.Magnetic Particle Insp of All Pistons Will Be Performed.List of Affected Plants Encl 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 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 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 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 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 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 ML20247M5851989-07-27027 July 1989 Part 21 Rept Re Failed Globe Valve Stem on 890405.Caused by Improper Heat Treatment of 410 Stainless Steel Alloy Used in Stem Which Increased Susceptibility to Stress Corrosion Cracking.Larger Shaft Modified by Machining Radius 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 1999-04-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8831999-10-21021 October 1999 Safety Evaluation Supporting Proposed Alternatives to Code Requirements Described in RR-V17 & RR-V18 ML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20217G2041999-10-13013 October 1999 Safety Evaluation Supporting Amend 179 to License DPR-28 BVY-99-127, Monthly Operating Rept for Sept 1999 for Vermont Yankee Nuclear Power Station.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Vermont Yankee Nuclear Power Station.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 ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico ML20212C2551999-09-17017 September 1999 Safety Evaluation Supporting Amend 175 to License DPR-28 BVY-99-112, Monthly Operating Rept for Aug 1999 for Vermont Yankee.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Vermont Yankee.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 BVY-99-109, Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 9908311999-08-19019 August 1999 Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 990831 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 BVY-99-102, Monthly Operating Rept for July 1999 for Vermont Yankee. with1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Vermont Yankee. with ML20210J3851999-07-28028 July 1999 Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval ML20209J0081999-07-14014 July 1999 Special Rept:On 990615,diesel Driven Fire Pump Failed to Achieve Rated Flow of 2500 Gallons Per Minute.Pump Was Inoperable for Greater than 7 Days.Corrective Maint Was Performed to Reset Pump Lift Setting BVY-99-090, Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With 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 ML20196G5071999-06-23023 June 1999 Vynp Assessment of On-Site Disposal of Contaminated Soil by Land Spreading 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 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 BVY-99-077, Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.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 BVY-99-068, Monthly Operating Rept for Apr 1999 for Vynp.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Vynp.With ML20206E8741999-04-29029 April 1999 SER Determined That Flaw Evaluation Meets Rules of ASME Code & Assumed Crack Growth Rate Adequate for Application 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 ML20206D9301999-04-27027 April 1999 1999 Emergency Preparedness Exercise 990427 Exercise Manual (Plume Portion) ML20206D7911999-04-23023 April 1999 Rev 6 to PDB-F0001, COLR for Pnpp Unit 1 Cycle 8,Reload 7 ML20205S4211999-04-16016 April 1999 Non-proprietary Version of Revised Page 4-3 of HI-981932 Technical Rept for Vermont Yankee Spent Fuel Pool Storage Expansion 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 ML20205K7581999-04-0707 April 1999 Safety Evaluation Supporting Alternative Proposal for Reexamination of Circumferential Welds with Detected Flaw Indications in Plant RPV BVY-99-046, Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With ML20205G4221999-03-31031 March 1999 Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 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 ML20206D8461999-03-31031 March 1999 Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7 Cycle 8 ML20205C3761999-03-26026 March 1999 Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 ML20205D3101999-03-26026 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-58 ML20205F6631999-03-0404 March 1999 Jet Pump Riser Weld Leakage Evaluation 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 BVY-99-035, Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With ML20205P8241999-02-28028 February 1999 Rev 2 to Vermont Yankee Cycle 20 Colr ML20203H9881999-02-18018 February 1999 SER Accepting Alternative to 10CFR50.55a(g)(6)(ii)(A) Augmented Reactor Vessel Exam at Vermont Yankee Nuclear Power Station.Technical Ltr Rept Encl ML20203A6951999-02-0404 February 1999 Revised Rev 2,App B to Vermont Yankee Operational QA Manual (Voqam) 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 ML20203A5211999-01-27027 January 1999 Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps ML20199K7151999-01-21021 January 1999 Corrected Safety Evaluation Supporting Amend 163 Issued to FOL DPR-28.Pages 2 & 3 Required Correction & Clarification 1999-09-30
[Table view] |
Text
e MNMED corporation I
2300 WALDEN AVE.
- BUFFALO, NY 14225 716 8044600 TELEX:91-275 CAME:CONAXC0 Q ACOMCOM*AW March 5,1985 Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 i
Subject:
Corrective Action of Defect Conax Power Lead ("PL") Gland Assemblies Qualified for Nuclear Service
Reference:
- 1. Conax Notification of Potential Defect 8/31/84 (Attached) l 2. Conax IPS-1233, Orig. (Enclosed)
Gentlemen:
in accordance with Reference No. 1 (attached), Conax has completed
! its evaluation of the potential reported defect of the subject Power Lead l Gland Assemblies. The results are documented in Conax Report IPS-l 1233, " Power Lead (P/L) Gland Assembly- Design Engineering Investigation" (Reference #2, enclosed), as summarized below.
l l Cause:
l
! The primary cause of the reported potential defect was determined to be an "over compression" of the power lead gland sealant during factory assembly, which eventually lead to a reduction in conductor cross sectional area at the conductor-sealant interface, and eventual conductor separation. This "over compression" was determined to have been caused by both the method with which thread lubricant was applied and the tools used to torque the gland midlock cap to the body during factory production.
All threads of the Vermont Yankee assembly component parts were lubricated prior to final assembly by dipping them in a freon /vydax solution (2 coats) . The Perry assemblies were lubricated prior to final assembly by brushing on the freon /vydax solution (1 coat).
Conax has determined that the dipping technique results in a thicker coat of lubricant material as compared to the brushing method, which would reduce thread friction during the torquing assembly process and subsequently transfer more of the applied torque to be translated l
into sealant compression.
( Compounding this process, the torque. wrench used to assemble both the Vermont Yankee and Perry glands indicated applied torque through t a " dial type" indicator gauge. This wrench design would therefore i
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S S'i, e ew am saw, s; pg4
Director March 5,1985 Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Page 2 allow torquing in excess of the required production parameters without automatically halting the operation, as would a presettable ratchet type wrench. The torquing operation was therefore not adequately controlled to within the tolerance specified in the factory assembly procedure. When the Vermont Yankee glands were evaluated, there was a strong indication that many of them may have been initially overtorqued during the factory assembly process.
Also, a contributing factor to the cause of the reported possible defect was determined to be the overextended service temperature to which the Vermont Yankee glands were exposed. By attempting to operate their power lead glands at a service temperature of 260 F, rather than the Conax recommended, (and previously qualified) '
service temperature of 150 F, Vermont Yankee had caused the already overcompressed sealants to thermally expand, thereby further contribu-ting to the eventual conductor separation mechanism. I 11 Corrective Action:
All of the Vermont Yankee Power Lead glands were removed from service and returned to Conax.
Forty-one (41) Power Lead Glands were returned to Conax by Perry for evaluation. Based on that evaluation, it was determined that the Perry Power Lead Glands did not contain the same possible defect reported by Vermont Yankee and would therefore be acceptable, provided they were operated at the original required normal operating service temperature (not to exceed 144 F) .
til Preventative Action i Conax will revise all drawings and assembly procedures to specify that one (1) coat of the thread lubricant shall be applied only by the brushing technique and not the dipping methodology. i l Conax will remove all dial indicator type torque wrenches from factory assembly service and will replace them with presettable ratchet type torque wrenches. In addition, Conax will revise all assembly pro-cedures to permit only the use of the ratchet type torque wrench.
For further clarification of our position or any additional information, please contact me directly.
Very truly yours, AX O CORPORATION
' JMZJ6 J f/
Itobert A. Fox President RAF/cas
Director March 5, 1985 Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Page 3 cc: Boyce H. Grier, Director, Region 1 Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 631 Park Ave.
King of Prussia, PA 19406 Mr. Richard Pagodin Engineering Support Supervisor Vermont Yankee Nuclear Power Corporation P. O. Box 157 Vernon, VT 05354 Mr. George Hengerly Yankee Atomic Electric Company 1671 Worcester Rd.
Framingham, MA 01701 Mr. Paul Martin General Supervisory Engineer PAQS The Cleveland Electric illuminating Company Perry Nuclear Power Plant, Units 1 and 2 P. O. Box 85 Perry, OH 44081 CONAX BUFFALO CORPORATION: M. W. Connell J. 'E. Adams W. S. Rautio D. P. Jensen W. C. Federick R. E. Duiski R. L. Duroure R. E. Farchmin S. M. Dale G. P. Wittmann Attachment (i)
Enclosure (1)
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=h , =>:4i w.:e.nm. m 3 CONAX CORPORATION.2300 WALDEN AVENUE, BUFFALO, NEW YORK 14225 TEL.716-684-4500 TELEX 275 1
1 August 31, 1984 Director Office of Inspection and Enforcement U.S. N; clear Regulatory Commission Washington, D.C. 20555
Subject:
Notification of a Potential Defect Conax Power Lead (PL) Gland Assemblies Qualified For Nuclear Service Gentlemen: _
Your attention is directed to our telephone communication with your Mr. Harry Kisteo of Regional Office 1 on August 29, 1984 concerning reasonable indica-tion of a defect. A conditioned situation exists which Conax has designated a potential defect.
This formal communication is submitted as timely evloence of our compliance to the requirements of 10 CFR Part 21, Paragraph 21.21, b(2), with the following information being provided to the extent known to date per items i through viii of paragraph 21.21, b(3), of 10 CFR Part 21. .
! I) Reporting Inoividual:
l W. S. Rautio Presioent Conax Buffalo Corporation 2300 Walden Avenue Buffalo, New York 14225 (716) 684-4500
, II) A. Component Identification l Conax Qualified Nuclear Service Power Lead Gland Assemblies l
l Conax Part Numbers: 7092-11000-01, -02, -03, -04 7D92-1.1001-01, -02, -03, -04, -05 N-11150-01 N-lll51-01
-INU10-70
, .. . - . . . .. : L.. . . . , .. . - . . . . . . . . - . . . .. .
/
l B. Facility Identification .
- 1. Vermont Yankee Nuclear Plant -
Governor Hunt Road Vernon, VT 05354
- 11. Perry Wclear Power Plant, Units 1 & 2 Perry, Ohio 44081 (P.O. Box 85)
III) Component Supplier Conax Buffalo Corporation 2300 Walden Avenue Buffalo, New York 14225 IV) Nature of Potential Defect The nature of the potential defect, as designated by Conax, is a loss of electrical continuity, resulting from a gradual reduction in the cross-sectional area of the conductors in the internal sealant area of the gland and eventually leading to total conductor separation in some cases. The phenomea appears to be related to time, temperature, and initial assenbly torquing and may be unique to Vermont Yankee's normal operating environment.
The result of phenomea could affect the electrical performance of safety related equipment into which these assemblies have been installed.
V) Date of Information This potential defect was brought to my attention in a meeting held on August 27, 1984 by S. M. Dale, Chief Engineer of our Industrial Products Division and W. C. Federick, Manager of our Nuclear Products Division.
VI) Number and Location of Components A. Forty-six (46) Power Lead Gland Assenblies, as follows, were supplied to Vermont Yankee Nuclear Plant in July,1984
- 26 pcs - 2 conductor /16 AWG (Conax P/N N-11150-01) 20 pcs - 8 conductor /14 AWG (Conax P/N N-lll51-01)
- 8. Eicfit hundred and twenty-one (821) Power Lead Gland Assemblies, as follows, were supplied to Perry Wclear Power Plant, thiits 1 and 2, in March thru June of 1984.
69 pcs - 2 conductor /14 AE (Conax P/N 752-11000-01) 128 pcs - 4 conductor /14 AWG (Conax P/N 7D92-11000-02) . i 57 pcs - 6 conductor /14 AWG (Conax P/N 7D92-11000-03)' l 9 pcs - 8 conductor /14 AWG (Conax P/N 7D92-11000-04) l 294 pcs - 2 conductor /16 AWG (Conax P/N 7092-11001-01) 55 pcs - 4 conductor /16 AWG (Conax P/N 7092-11001-02) 3 pcs - A conductor /16 AWG (Conax P/N 752-11001-03) l 9 pcs - 8 conductor /16 AWG (Conax P/N 7D92-11001-04) 197 pcs - A conductor /16 AWG (Conax P/N 7092-11001-05)
VII) Corrective Action Both Vermont Yankee Nuclear Plant and Perry Nuclear Power Plant, Units 1 and 2, were notified on August 27, 1984 concerning the potential defect and of our requirement to report to the NRC. At that point, Vermont Yankee had already removed all their Power Lead Gland Assemblies from service. Within the next 180 days, Conax will complete an evaluation of the parameters that may cause this potential defect and will advise the Perry Nuclear Power Plant of the results. ,
VIII) Recommendations and Advice Until the causes of the potential defect are determined, Conax is unable to fully evaluate the existance of a safety hazard for the Perry Nuclear Power Plant. Conax will provide information as it becomes available to the Perry Nuclear Power Plant for their assessment of the situation.
Conax recommends that the Power Lead Glands not be utilizeo in any safety related circuits until the evaluation is complete.
For further clarification of our position or any additional information, please contact me directly.
Very truly yours, CONAX BUFFALO CORPORATION b S. Rautio President WSR/ct
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.4 cc: Boyce H. Grier, Director, Region 1 Office of Inspection and Enforcement -
U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Mr. Richard Pagodin Engineering Support Supervisor Vermont Yankee Nuclear Power Corporation P.O. Box 157 Vernon, VT 05354 Mr. George Hengerly Yankee Atomic Electric Company 1671 Worcester Road Framingham, MA 01701 MR. Paul Martin General Supervisory Engineer PAQS The Clevelano Electric Illuminating Company Perry Nuclear Power Plant, Units 1 ano 2 P. O. Box 85 Perry, Ohio 44081 Conax Buffalo Corporation: M. W. Connell J. E. Adams R. A. Fox
- 0. P. Jensen W. C. Federick R. L. Duroure R. E. Farchmin S. M. Dale l
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