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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps 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 ML20198Q6961998-01-12012 January 1998 Part 21 Rept Re Failed Operation of Agastat EGPI004 Relay on 971129,as Reported by Limerick Station.Caused by Insufficient Soldering.Will Notify Customers Who Purchased EPI004 & ETR14XXX004 Relays During June 1996 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 ML20058G5981993-11-17017 November 1993 Part 21 Rept Re Westronics Recorders,Model 2100C.Signal Input Transition Printed Circuit Board Assembly Redesigned to Improve Recorder Immunity to Electromagnetic Interference.List of Affected Recorders & Locations Encl ML20059L9861993-11-11011 November 1993 Part 21 Rept Re Deviation Wherein Fully Open Butterfly Valve Located 15 Pipe Diameters Upstream of Sensors Was Disturbing Flow Profile Enough to Cause Ultrasonic Meter to Indicate 3 to 4% Low.Customers Notified & Valve 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 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 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 ML20059M1751990-09-24024 September 1990 Supplemental Part 21 Rept 1 Re Defect in Coltec Industries, Inc Connecting Rod Assemblies Nuts/Bolts on Model 38TD8-1/8 Emergency Generators.Initially Reported on 851120.Nuts/bolts for Assemblies at Stated Plants Inspected & Replaced ML20006A7141990-01-19019 January 1990 Updated Final Significant Deficiency Rept 107 Re Defective Agastat GP Relays.Initially Reported on 831129.Use of Subj Relays Does Not Represent Safety Concern & Not Reportable as Operational Concern.Test Program Developed 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 ML20245G0411989-08-0808 August 1989 Advises That Corrective Actions for Significant Deficiency & Part 21 Rept Re Unqualified Nupro Valve Seals Completed & Resolved,Per 890707 Rept.Only 98 Nupro Test Valves Furnished on GE Racks & Addl 17 Valves Provided for Other Racks ML20246J6411989-07-0707 July 1989 Supplemental Part 21 & Deficiency Rept L2-89-44 Re Nupro Test Valves,Installed on Instrument Line Racks Furnished by Ge,Not Remaining Leak Tight During DBA Conditions.Initially Reported on 890608.Root Cause Analysis Will Be Performed ML20245K9061989-06-30030 June 1989 Significant Deficiency Repts L2-89-08,38,43 & 45-48 Re Safe Shutdown Analysis.Corrective Actions Completed & Significant Deficiencies Considered Resolved ML20244A5101989-06-0707 June 1989 Final Significant Deficiency Rept SDR-L2-89-39 Re Failure of Stainless Steel Midlock Ferrules.Caused by Isolated Stress Corrosion Cracking Not Affecting Other Penetration Ferrules in Penetration 20JX222 Replaced ML20247Q7341989-05-31031 May 1989 Significant Deficiency Rept L2-89-34 Re Tavis Pressure Differential Transmitters Installed W/O Connecting Internal Heaters.Initially Reported on 890418.Heaters Will Be Connected on All Tavis Pressure Differential Transmitters ML20247N7731989-05-31031 May 1989 Supplemental Significant Deficiency Rept Re Safe Shutdown Analysis self-assessment ML20246F9051989-05-15015 May 1989 Significant Deficiency Rept L2-89-23 Re Essential Equipment Located in Unanalyzed Environ.Installation of Conduit Seals or Reorientation of Conduit Runs Planned to Avoid Moisture Intrusion Into Electrical Equipment Prior to Startup ML20246M3681989-05-0808 May 1989 Significant Deficiency Rept L2-89-06 Re Unavailability of Suppression Pool Indication Due to App R Fire.Caused by Design Error Resulting from Lack of Procedural Guidance. Reportability Evaluation Initiated ML20248F6101989-04-13013 April 1989 Interim Significant Deficiency Rept L2-88-11 Re Inadequate Degraded Grid Undervoltage Relay Setpoints.Event Discussed W/Engineer Involved to Ensure Procedural Adherence & New Undervoltage Relays Will Be Installed ML20248F3571989-04-0303 April 1989 Interim Significant Deficiency Rept SDR-L2-89-17 Re Unavailability of Feedwater Maint Isolation Valve to Support RCIC Operation in Event of App R Fire.Initially Reported on 890303.Cause Under Investigation.Rept to Be Submitted ML20248F9451989-03-28028 March 1989 Part 21 Rept Re Replacement of Circuit Boards for Safeguard Battery Chargers.Initially Reported on 890323.C&D Power Sys Provided Instructions to Change Out 600 Ohm Fixed Resistor w/500 Ohm Variable Resistor in Charger Circuitry ML20246H0951989-03-10010 March 1989 Significant Deficiency Rept L2-88-10 Re Improper Installation of Temporary Support Brackets in safety-related 4 Kv Switchgear.Support Brackets Removed from Switchgear Cubicle Prior to Startup & Procedures Revised ML20235F8601989-02-17017 February 1989 Interim Significant Deficiency Repts SDR-L2-89-03,04 & 05 Re Unavailability of HPCI & RCIC Sys Due to App R Fire. Initially Reported on 890117.Corrective Actions Under Review & Will Be Reported by 890531 ML20196B8281988-12-0202 December 1988 Final Significant Deficiency Rept 250-2 Re Use of Insulated Wire by Westinghouse in safety-related Motor Starters. Initially Reported on 881020.Defective Components Reworked & Corrected.Action to Prevent Recurrence Not Necessary ML20206C1571988-11-0404 November 1988 Interim Deficiency Rept 249-2 Re Nonavailability of Safe Shutdown Capabilities from Outside Control Room in Event of Fire.Initially Reported on 881006.Design Change Will Be Performed.Root Cause of Condition Still Under Evaluation ML20154Q4541988-09-28028 September 1988 Final Significant Deficiency Repts 230-2 & 231-2 Re Failures of Aluminum Vertical Bus & Belleville Washers in Cutler-Hammer Motor Control Ctrs.Aluminum Vertical Bus Replaced W/Tin Plated Copper Bus ML20153B6841988-08-25025 August 1988 Final Significant Deficiency Rept 238-2 Re Use of 600 Volt Type Thhn,Thwn or Thw Wire in 120 Volt Ac Convenience Receptacles & Lighting Circuits for Control Panels.Initially Reported on 880729.Panels,load Ctrs & Switchgear Inspected ML20151F3321988-07-0808 July 1988 Interim Significant Deficiency Rept 219-2 Re Discrepancies in Pgcc Wiring.Approx 130 Addl Minor Errors Out of 10,000 Terminations Discovered During Reinsp.Final Rept Will Be Submitted by 880815 ML20195B7641988-06-15015 June 1988 Final Deficiency Rept 232-2 Re Westinghouse Type Ds Fused Disconnect Switch.Initially Reported on 880415.Mechanical Connectors Integral to Fuse Mounting Assembly Would Not Adequately Secure Some 8 Awg Wires ML20155C3401988-06-0606 June 1988 Significant Deficiency Rept 137-2 Re Potentially Defective Type Hma Auxiliary Relays.Ge Notification Per 10CFR21 Encl. Potentially Defective Equipment Inspected & Corrected Per Field Disposition Instructions from GE ML20154E6381988-05-13013 May 1988 Interim Deficiency Rept Re Aluminum Vertical Bus Failures in Cutler Hammer Motor Control Ctr.Initially Reported During 880415 Telcon W/Nrc Regional Ofc.Evaluating Condition W/ Mfg.Next Rept Will Be Submitted by 880715 ML20154E6561988-05-13013 May 1988 Interim Deficiency Rept Re Use of Mechanical Cable Connectors on Westinghouse Type Ds Fused Disconnect Switches.Initially Reported on 880415.Determination of Extent That Both Wires Terminated W/Connectors Underway ML20154E4641988-05-13013 May 1988 Part 21 & Deficiency Rept Re Belleville Washer Failures in Cutler-Hammer Motor Control Ctrs.Initially Reported During 880415 Telcon.Exam of Failed Washers Showed Failure Due to Intergranular Decohesion.Detailed Rept Expected by 880715 ML20151A7511988-04-0404 April 1988 Final Significant Deficiency Rept 215 Re App R Safe Shutdown Capability for Fire Area 75.Diesel Generator Control Circuits Redesigned & re-reviewed Electrical Schematics & Application of Class 1E Isolation Relay ML20147G3671988-02-23023 February 1988 Final Significant Deficiency Rept 221-2 Re Westinghouse Dc Motor Control Ctrs.All Deficient Wiring in 20D201,20D202 & 20D203 Dc Motor Control Ctr Compartments Reworked to Approved Wiring Drawings ML20149N0931988-02-23023 February 1988 Final Deficiency Rept 221-2 Re Discrepancy Between Internal Control Wiring on Three Westinghouse Dc Motor Control Ctrs & Vendor Supplied Wiring on Schematic Drawings.Initially Reported on 871103.Wiring Compartments Reworked ML20234F5781987-12-31031 December 1987 Interim Deficiency Rept 219-2 Re Wiring within Power Control Complex Found in Configurations Not Specified in Connections Diagrams 865E214TR & 807E560TR.Initially Reported on 871204.Analysis Should Be Completed by 880601 ML20236V6051987-12-0202 December 1987 Interim Deficiency Rept 215 Re Fire Safe Shutdown Commitments as Documented in Section 3.2.1,Item 17 of Fire Protection Evaluation Rept.Initially Reported on 871022. Diesel Generator Control Circuits Redesigned ML20149M0971987-09-18018 September 1987 Final Deficiency Rept 213 Re High Acceleration Values for PSA-10 Snubbers.Initially Reported on 870819.All Snubber Installations That Use Size PSA-10 Snubbers Identified & Snubbers Mfg After June 1985 Will Be Installed ML20238C6301987-09-0101 September 1987 Significant Deficiency Rept 157 Re Asco Solenoid Valves on Velan air-operated Valves.Initially Reported on 840905. Completion Date for Corrective Actions Rescheduled to May 1989 Due to Const Schedule Changes.Model Number Corrected ML20238A2121987-08-24024 August 1987 Significant Deficiency Evaluation Rept 209 Re Limitorque Motor Operators W/Hydraulic Locking.Initially Reported on 870626.Limitorque Motor Operators Being Processed Through Rework Program.Item Not Reportable Per 10CFR50.55(e) ML20236P4971987-08-0505 August 1987 Advises That Corrective Actions Described in Util 870402 Deficiency Rept Complete Except for third-level Util Engineering Review & Util QA Findings.Completion of Review & Findings Anticipated by 871001 ML20236N7091987-07-31031 July 1987 Informs That Paul Munroe Actuators Have Not Been Installed to Correct Actuators Contrary to Statement in 840913 Final Significant Deficiency Rept 120.Other Mfg Being Used ML20206D0971987-04-0202 April 1987 Final Significant Deficiency Rept 198 Re Computer Aided Design & Drafting (Cadd) Conversion of P&ID & QA Diagrams. Initially Reported on 870303.Recheck of CADD-generated P&Ids Completed & Corrected P&Ids Reissued 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D1211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Lgs,Units 1 & 2. with ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers 05000353/LER-1999-010, :on 990820,manual Actuation of Main CR Chlorine Isolation Mode Was Noted.Caused by Faint Chlorine Odor in Reactor Encl.Conducted Investigation & Was Unable to Locate Source of Odor1999-09-16016 September 1999
- on 990820,manual Actuation of Main CR Chlorine Isolation Mode Was Noted.Caused by Faint Chlorine Odor in Reactor Encl.Conducted Investigation & Was Unable to Locate Source of Odor
ML20212A8861999-09-13013 September 1999 Safety Evaluation Authorizing First & Second 10 Yr Interval Inservice Insp Plan Requestss for Relief RR-01 05000352/LER-1999-009, :on 990802,maint Was Performed That Required Disabling Certain Monitoring Capabilities on Safeguard Sys. Caused by Failure to Properly Use Plant Procedure.Monitoring Capability Was Restored to Svc & Tested1999-09-0101 September 1999
- on 990802,maint Was Performed That Required Disabling Certain Monitoring Capabilities on Safeguard Sys. Caused by Failure to Properly Use Plant Procedure.Monitoring Capability Was Restored to Svc & Tested
ML20212A4481999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Limerick Generating Station,Units 1 & 2.With ML20211E9891999-08-20020 August 1999 LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5 05000353/LER-1999-005-02, :on 990712,PCIV Isolation & Esfa Occurred Due to Blown Fuse.Caused by Mechanical Failure of Cold Solder Joing.Reset Isolation within Three Hours & 22 Minutes & Replaced Fuse1999-08-10010 August 1999
- on 990712,PCIV Isolation & Esfa Occurred Due to Blown Fuse.Caused by Mechanical Failure of Cold Solder Joing.Reset Isolation within Three Hours & 22 Minutes & Replaced Fuse
ML20210L7051999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Limerick Generating Station,Units 1 & 2.With ML20210H7391999-07-29029 July 1999 Safety Evalution Supporting Amends 136 & 101 to Licenses NPF-39 & NPF-85,respectively 05000353/LER-1999-004-02, :on 990701,determined That Thirteen MSRVs Failed to Meet 1% Setpoint Tolerance Due to Setpoint Drift.Caused by Corrosion Induced Bonding Between Pilot Disc & Seat.All Fourteen Srvs Pilot Valves Were Replaced1999-07-23023 July 1999
- on 990701,determined That Thirteen MSRVs Failed to Meet 1% Setpoint Tolerance Due to Setpoint Drift.Caused by Corrosion Induced Bonding Between Pilot Disc & Seat.All Fourteen Srvs Pilot Valves Were Replaced
05000352/LER-1999-007, :on 990617,inadvertent Emergency Svc Water Start During Test Equipment Installation Occurred.Caused by Personnel Error.Procedure Revised.With1999-07-14014 July 1999
- on 990617,inadvertent Emergency Svc Water Start During Test Equipment Installation Occurred.Caused by Personnel Error.Procedure Revised.With
05000352/LER-1999-005, :on 990611,RPS & ESF Actuations Were Noted. Caused by Personnel Error During Turbine Routine Testing. Revised Backup Overspeed & Power/Load Unbalance Test Routine Test Procedure.With1999-07-0909 July 1999
- on 990611,RPS & ESF Actuations Were Noted. Caused by Personnel Error During Turbine Routine Testing. Revised Backup Overspeed & Power/Load Unbalance Test Routine Test Procedure.With
05000353/LER-1999-003-02, :on 990607,bypass of RW Cleanup Sys Leak Detection Sys Isolation Functions on Three Separate Occasions Was Noted.Caused by Inadequate Review & Approval of Change to Sys Procedure.Procedure S44.7.C Revised1999-07-0707 July 1999
- on 990607,bypass of RW Cleanup Sys Leak Detection Sys Isolation Functions on Three Separate Occasions Was Noted.Caused by Inadequate Review & Approval of Change to Sys Procedure.Procedure S44.7.C Revised
05000352/LER-1999-004-01, :on 990606,ADS Was Inoperable During Planned Maint & Applicable TS Was Not Met.Caused by Inadequate Review Operability Requirements.Clearance Was Removed from Backup ADS Gas Bottles & Sys Was Returned to Service1999-07-0101 July 1999
- on 990606,ADS Was Inoperable During Planned Maint & Applicable TS Was Not Met.Caused by Inadequate Review Operability Requirements.Clearance Was Removed from Backup ADS Gas Bottles & Sys Was Returned to Service
ML20209G0211999-06-30030 June 1999 GE-NE-B13-02010-33NP, Evaluation of Limerick Unit 2 Shroud Cracking for at Least One Fuel Cycle of Operation ML20209D7741999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 ML20207H8331999-05-31031 May 1999 Non-proprietary Rev 0 to 1H61R, LGS - Unit 2 Core Shroud Ultrasonic Exam ML20195G4651999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Lgs,Units 1 & 2 ML20209D7791999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Limerick Generating Station,Units 1 & 2 ML20209F2381999-05-24024 May 1999 Safety Evaluation Supporting Amends 135 & 100 to Licenses NPF-39 & NPF-85,respectively 05000352/LER-1999-003-01, :on 990420,RPS & PCRVICS Actuations Were Noted, Due to Loss of FW Transient.Caused by Spuriously Opening Breaker.Deep Bed Condensate Deminerlizer Sys Was Replaced1999-05-19019 May 1999
- on 990420,RPS & PCRVICS Actuations Were Noted, Due to Loss of FW Transient.Caused by Spuriously Opening Breaker.Deep Bed Condensate Deminerlizer Sys Was Replaced
ML20206U6911999-05-19019 May 1999 Safety Evaluation Supporting Amend 99 to License NPF-85 05000353/LER-1999-002-03, :on 990419,various ESF Actuations Due to Loss of Power to 2A Rps/Ups Distribution Panel,Occurred.Caused by Loose Bus Bar Connection in RPS Breaker panel.Bus-bar Connection Inspected,Cleaned & re-tightened1999-05-18018 May 1999
- on 990419,various ESF Actuations Due to Loss of Power to 2A Rps/Ups Distribution Panel,Occurred.Caused by Loose Bus Bar Connection in RPS Breaker panel.Bus-bar Connection Inspected,Cleaned & re-tightened
ML20206U4991999-05-17017 May 1999 Safety Evaluation Supporting Amend 98 to License NPF-85 ML20206P8871999-05-14014 May 1999 Safety Evaluation Supporting Amend 97 to License NPF-85 ML20206N5761999-05-13013 May 1999 Safety Evaluation Supporting Amends 134 & 96 to Licenses NPF-39 & NPF-85,respectively ML20195B3021999-05-0606 May 1999 Rev 0 to PECO-COLR-L2R5, COLR for Lgs,Unit 2 Reload 5 Cycle 6 ML20206N2901999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Limerick Generating Station,Units 1 & 2.With ML20195G4761999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Lgs,Units 1 & 2 ML20206D8971999-04-22022 April 1999 Rev 2 to PECO-COLR-L1R7, COLR for Lgs,Unit 2 Reload 7, Cycle 8 ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified 05000352/LER-1999-002-01, :on 990303,failure to Perform TS Surveillance Required Locked Valve Insp Occurred.Caused by Personnel Error.Procedures Revised.With1999-04-0101 April 1999
- on 990303,failure to Perform TS Surveillance Required Locked Valve Insp Occurred.Caused by Personnel Error.Procedures Revised.With
ML20205N9311999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Limerick Generating Station,Units 1 & 2.With 05000352/LER-1999-001-02, :on 990217,old Rev of LGS PSP Was Discovered on Hard Drive of self-contained Computer in Security Ofc Area. Caused by Less than Adequate Ac.Security Force Was Placed on Heightened Awareness to Compensate for Compromise of SG1999-03-16016 March 1999
- on 990217,old Rev of LGS PSP Was Discovered on Hard Drive of self-contained Computer in Security Ofc Area. Caused by Less than Adequate Ac.Security Force Was Placed on Heightened Awareness to Compensate for Compromise of SGI
ML20204G9851999-03-11011 March 1999 Safety Evaluation Re Revised Emergency Action Levels for Limerick Generating Station,Units 1 & 2 ML20207J7461999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Limerick,Units 1 & 2.With ML20199G2371999-01-31031 January 1999 Rev 0 to NEDO-32645, Limerick Generating Station,Units 1 & 2 SRV Setpoint Tolerance Relaxation Licensing Rept ML20199L5301999-01-19019 January 1999 Special Rept:On 981214,seismic Monitor Was Declared Inoperable.Caused by Spectral Analyzer Not Running.Attempted to Reboot Sys & Then Sent Spectral Analyzer to Vendor for Analysis & Rework.Upgraded Sys Will Be Operable by 990331 ML20206R7881999-01-12012 January 1999 Safety Evaluation Supporting Amend 94 to License NPF-85 05000353/LER-1998-008-02, :on 981209,plant Personnel Identified That Unit 2 RCIC Turbine Steam Supply Line warm-up Bypass Valve Had Been in Partially Open Condition.Caused by Intermittment Control Circuit Anomaly.Control Circuit Replaced1999-01-0707 January 1999
- on 981209,plant Personnel Identified That Unit 2 RCIC Turbine Steam Supply Line warm-up Bypass Valve Had Been in Partially Open Condition.Caused by Intermittment Control Circuit Anomaly.Control Circuit Replaced
ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20199F9611998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Limerick Generating Station.With 05000352/LER-1998-019, :on 981202,noted Unescorted Access to Contract Employee Who Had Tampered with Drug Test Specimen.Caused by Incorrect Computer Data Entry for pre-access Drug Screening. Will Develop Formal Training Program for Data Entry Clerk1998-12-23023 December 1998
- on 981202,noted Unescorted Access to Contract Employee Who Had Tampered with Drug Test Specimen.Caused by Incorrect Computer Data Entry for pre-access Drug Screening. Will Develop Formal Training Program for Data Entry Clerk
ML20198A3871998-12-10010 December 1998 Safety Evaluation Supporting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves ML20198C7151998-12-10010 December 1998 Rev 1 to COLR for LGS Unit 1,Reload 7,Cycle 8 ML20206N4061998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Limerick Generating Station,Units 1 & 2.With ML20199E3281998-11-23023 November 1998 Rev 2 to PECO-COLR-L2R4, COLR for Lgs,Unit 2,Reload 4,Cycle 5 ML20195C9771998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Limerick Generating Station,Units 1 & 2.With ML20154J0311998-10-0101 October 1998 Safety Evaluation Supporting Amends 130 & 91 to Licenses NPF-39 & NPF-85,respectively 1999-09-30
[Table view] |
Text
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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET
. [
P.O. BOX 8699 F'HIL ADELPHI A. P A.19101 i:t s) e414 502 jl S. J KOW ALSKI I
vict PREsiotMT seu cks an a ssosais a n eses I
U.S. Nuclear Regulatory Conmission 10CFR50.55(e) a Attn: Document Control Desk Washington, D.C.
20555 June 7, 1989
.i Docket No.: 50-353 CPPR-107
SUBJECT:
Limerick Generating Station, Unit 2 -
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Final Significant Deficiercy Report, Failure of Stainless Steel Midlock Ferrules
/
L '
REFERENCE:
Telecon of May 22, 1989, R. J i.ees (PECo) to H. Williams (NRC) 1 I L FILE: QUAL 2-10-2 (SDR'L2-89-39) q Gentlemen:
/.cl '
By the referenced telecon, Philadelphia Electric Company (PECo) Inforry>d e
l,f you of a reportable condition under 10CFR50.55(e) regarding failure of stainless steel mldlock ferrules in a single containment penetration (20dX222).
/
he are reoviding this final report as indicated in the May 22 telecon.
h fl, A
!. I We have performed a review of penetration records and conducted metallurgical evaluations of ferrules from the failed penetration. Additionally, ffrrules
)
b['I[J sarrpled f rom other penetrations were also evaluated by PECo. Conax, the manu-
.,I facturer, has perfonned field investigation artl testing of the Limerick Unit. 2
.y %
midlock ferrules. On the basis of these reviews, we conclude that the failure
<.. i/
of penetration 20dX222 midlock ferrules was due to an isolated incidence of i
y']
utress corrosion cracking not affecting any other penetration ferrules. We have
)
replaced all ferrules in penetration 20dX222, and it successfully passed a leak
'fl rate test. Our evaluation (contained in the enc 1, re) and the completed
( L M, f corrective action resolve this identified signific-sit deficiency.
i_s ill 1, If you have any further questions at this time, please contact us.
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. ll Sincerely, lI j< ;
6906120051
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Enclosure
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f&A tl tW'/d!m/002
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W. T. Russell, USNRC, Administrator, Pegion I
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T. J. Kenny, USNRC, LGS Senior Resident Inspector
,,f R. J. Clark, USNRC, LGS Project Manager
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G. M.'Leitch LGS MC 200 4
8 L. B. Pyrih N2-1 R. J. Lees-N2-1 G. A. Hunger, Jr.
52A-5 Chesterbrook~
~j E. J. Bradley S23-1 W. J. Boyer,_dr.
N2-1 A. S. McAinsh LGS MC SB3-4 M. S. lyer (Bechtol) 1
- d. F. O'Rourke N2-1 H. D. Honan N2 R. B. Rock N2-1 P. J. Duca, Jr.
LGS-MC AS-1 M. A. - Miller (Tenera) -
N2-1 D. P. Helker/Conmitment Tracking 52A-5 DAC '.
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Enclosure Linerick Generating Station, Unit 2 Significant Deficiency Report Evaluation of Failure of Stainless Steel Midlock Ferrules Description of Deficiency Linerick Unit 2 experienced failure of 10 of 14 midlock ferrules of elec-trical containment penetration 20dX222. These ferrules did not neet leak rate' test criteria due to stress corrosion' cracking (SCC) which caused leaks beyond acceptable limits or linear Indications.
Figure 1 depicts a penetration con-talning midlock ferrules.
Safety Inpilcations Penetration pressure boundary sealing between inside and outside containment is provided by nechanical compression ferrule design. The ferrule is a three-plece Interlocked arrangement' held in place by a threaded midlock cap. The three-plece ferrule consists of a nain seal between the header plate and electrical feedthrough and two seals which are part of a_ leak rate nonitoring and testing system for this nain' seal and the penetration feedthrough end seals.
Fleid Investigation and testing by Conax Buffalo Corporatio'n (the manufacturer) 1 of ferrules at Limerick Unit 2 concluded that the cracks did not' create a-
)
leakage path from inside to outside' contalmnent (Reference.1).
This is because
]
the cracked ferrules were part of the leak rate test systen in all cases and did l
not affect the nain' seal which purpose is to nelntain the contalmnent pressure -
]
boundary. Conax also reported that the cracked-ferrule condition is the first
']
instance of its type in 15 years of use of this ferrule design in thousands of Installations (Reference 2).
l l
4 Corrective Actions All fourteen midiock ferrules of containment penetration 20dX222 were replaced.. In order to confi nn that the failure mechanism was~ caused by -
l SCC two independent laboratories perfonned metallurgical evaluations-of the removed sanples, i
The test laboratory evaluations' by PECo (2 ferrules) and Conax (11 ferrules)
Independently concluded that the midlock ferrules renoved from containment penetration 20dX222 falled due to' SCC (References 3 and 4).
Certain characteristics of these ferrules nede than susceptible to SCC.
For instance, chemical analysis on the ferrules verified that the;naterial is 303 stainless steel (SCC-susceptible reterial), as.specified by the manufacturer. - Also, iron-oxide' dark stains _were present on some ferrules, Indicating that the parts had been wetted at sone tine.
Bechtel and PEco Engineering have reviewed the PEco 'and Conax lab reports and concur that SCC caused the midlock ferrules to fall the leak rate test.
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A review of the penetration records T1.e., storage, instal'ation, 1
testing, etc.) did not identify any unique events wh:ch could have re-suited in the failures or in the wetting of the ferrules (Reference 5). A
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condition did exist where the feedthrough support system through the containment nozzle was out of alignment with the sealing parts of. the header plate by approximately 7" to 10% We do not believe that this. misalignment contributed to the SCC.
Eleven ferrules fr om five additional ' Unit 2 penetrations were renoved an'd sent to the PECo test lab for metallographic examination, chemical analysis, I
~
i and hardness testing'.to determine whether indications of similar SCC existed, Three ferrules were renoved from penetration 20dX230A (the only other wetwell penetration besides 20dX222). The remaining eight ferules were reroved from four drywell penetrations. The ferrules were removed from plugged ports which did not require de-termination and re-termination of electrical connections.
j The plugged port ferrules are installed and treated the same as feedthrough j
ferrules.
]
A sampling inspection approach was utilized using MIL standard 105D. The test lab results indicated zero cracks or defects in all ' sample ferrules examined (Reference 6). The inspection of ferrules from five penetrations of-a total population of 24 penetrations without Identifying any defects consti-tutes an appropriate sample size per MIL Standard'105D.
1 Actions to Prevent Recurrence On the basis of the evaluations of the cracked ferrules and the ferrules I
sampled from other penetrations, we are abic to conclude that the cracking
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problem is not appilcable to any other penetrations in Units' 1 or 2.
We believe that something unique and random occurred to penetration 20dX222 during its manufacture, shipping, storage or installation which caused SCC.
Normally, the penetration ferrules are kept under a pressurized nitrogen blanket which prevents contamination and corrosion. ' During installation, the blanket may be temporarily renoved per manufacturer procedures. The event which caused contamination and ultimately SCC of the ferrules in penetration 20dX222 cannot be detenuined. However, in the unlikely event that such an occurrence should be repeated, normal surveillance testing of penetration pressure gauges and long-tenn leak rate testing (LLRT) during refueling outages will detect any leaks of ferrule and feedthrough seals.
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1 References 1.
Trip report from P. A. Christopher, Conax Buffalo Corporation discussing field investigation of leaking penetration 20dX222 dated April. 27, 1989.
_l 2.
Letter from Thomas P. Schaefer, Conax Buffalo Corporation to Ant i Kar, Bechtel Power Corporation,_ " Electric Penetration No.
20dX222, Limerick-Generating Station," dated May 25, 1989.
3.
Memorandtm from J. F. Delong, PECo to A. S. MacAinsh, PEco,
" Metallurgical Examination of Limerick Unit No. 2, 303 Stainess Steel Ccopression Couplings to Determine the Cause of Failure, Metallurgical Laboratory Note No.89-624," dated May 4,1989.
4.
Transmittal from T. P. Schaefer,_ Conax Buffalo Corporation to Glenn Frank 1in, Bechtel. Construction, Inc., "Fallure Analysis of Three (3) Piece Ferrules," dated May_4, 1989.
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1 5.
Menorandtm from M. S. Iyer, Bechtel Power Corporation to E. R. Nelson, Bechtel, " Interim Report, PECo Finding 2E-554," dated May 25, 1989.
]
i 6.
Memorandtm to R. B. Rock, PECo, from J. F. Delong, PECo, j
" Metallurgical Examination to Determine the Presence of Cracks in
.J Eleven Conax Ferrels Taken from Limerick Unit No. 2, Metallurgical Laboratory Report 89-624," dated May 30, 1989.
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