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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 ML20211D6491999-08-25025 August 1999 Part 21 Rept Re Nonconformance within LCR-25 safety-related Lead Acid Battery Cells Manufactured by C&D.Analysis of Cells Completed.Analysis of Positive Grid Matl Shows Nonconforming Levels of Calcium within Positive Grid Alloy 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 ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency 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 ML20247G6131998-05-13013 May 1998 Part 21 Rept Re Defect Contained in Automatic Switch Co, Solenoid Valves,Purchased Under Purchase Order (Po) 970161. Caused by Presence of Brass Strands.Replaced Defective Valves ML20217A1531998-04-16016 April 1998 Closure to Interim Part 21 Rept Submitted to NRC on 970929. New Date Established for Completion of Level I & 2 Setpoint Project Committed to in .Final Approval of Setpoint Calculations Will Be Completed by 980531 ML18065B1351998-01-0606 January 1998 Part 21 Rept Re Use of Deltstrat Code for RCS Flow Rate Determination.Code Corrects for Temps to Determine Hot Leg Bulk Coolant Temp ML20203J2521997-12-0101 December 1997 Deficiency Rept Re Failed Mdr Relays at Entergy Operations Inc,Waterford 3 Nuclear Generation Station.Caused by Contaminated Grease.Housekeeping Procedures Formalized & Added Enclosed Booth Isolating Mdr Final Assembly LD-97-033, Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 9712011997-11-20020 November 1997 Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 971201 LD-97-028, Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys1997-10-13013 October 1997 Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys ML20217D4141997-09-29029 September 1997 Interim Part 21 Rept Re Errors Noted During Preparation of ITS Surveillance Test Procedures Using GE Calculated Setpoints.Setpoint Calculations Will Be Reviewed,Corrected & Approved to Establish Significance of Errors LD-97-024, Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-0041997-08-14014 August 1997 Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-004 ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum NSD-NRC-97-5093, Part 21 Rept Re W Identified Defects That Could Create Substantial Safety Hazard Should Defect Remain Uncorrected. Plans to Complete Proper Refurbishment of All of Returned Breakers Being Established1997-05-14014 May 1997 Part 21 Rept Re W Identified Defects That Could Create Substantial Safety Hazard Should Defect Remain Uncorrected. Plans to Complete Proper Refurbishment of All of Returned Breakers Being Established 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 ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML20137G6261997-03-25025 March 1997 Svcs Part 21 Rept Re Emergency Generators Installed at Zion Station Which Developed Significant Drop in Crankcase Lube Oil Level.Caused by Crack in Liner Wall,Allowing Jacket Water to Enter Chamber ML20135E3811997-03-0303 March 1997 Part 21 Rept Re Output Drift W/Increasing Temperature on Several RTD Amplifiers Noted During Installation of RTD by-pass Mod at Station.Action to Identify All Circuit Cards W/Affected Date Codes,Identified 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 ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology ML20117K9731996-09-10010 September 1996 Follow-up Part 21 Rept of Re Failures of Waterford 3 Dedication Testing Process of Seven Commercial Grade Barksdale Pressure Switches ML20116C7031996-07-29029 July 1996 Part 21 Rept Re Failures Identified by Waterford 3 Dedication Testing Process of 7 Commercial Grade Barksdale Pressure Switches 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 LD-96-009, Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power1996-04-15015 April 1996 Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power ML20097J6351996-01-30030 January 1996 Part 21 Rept Re Intermittent Failure of DG Relay Mfg by Amerace Electronic Components.Suspect Relays at Plants Identified & Replaced.Amerace Indicated That Operators & QC Personnel Made Aware of Need for Proper Soldering ML20096E6511996-01-18018 January 1996 Part 21 Rept Re Failure of MOV Motor Pinion Gear Mfg by Limitorque at Byron Station.Replacement & Insp Activities Initiated for Potentially Impacted Populations of MOVs at Byron & Braidwood Stations ML20085J6591995-06-15015 June 1995 Potential Part 21 Rept Re Failure of Air Cylinder Mfg by Bellofram Corp at Ggns.Failure Discussed W/Mfg & Judged to Be Isolated Incident W/No Further C/A Required at Affected Utils or Cooper-Bessemer 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 ML20082Q9491995-04-21021 April 1995 Part 21 Rept Re Notifying Commission of Potential Design Defect of Ksv EDG Sys ML20077D3431994-11-29029 November 1994 Part 21 Rept Re Suspect Master Connecting Rods & Contains Info Location in Engine for Rods ML20078G3051994-11-0909 November 1994 Rev to Part 21 Rept Re Potential Problem W/Master Power Connecting Rods.Vendor Recommends Listed Utils Perform Visual Insp of Master Rods to Determine Applicability of Rept ML20078C2591994-10-19019 October 1994 Part 21 Rept Re Valtek Valves Addressed in NRC Part 21 Log Number 93-325,installed at South Texas Project.Valtek re-designed Trim to Meet All Requirements & Built Parts to Retrofit in Valves 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 ML20071J1891994-07-22022 July 1994 Final Part 21 Rept Re Cracks Found in Body to Bonnet Nuts on Copes-Vulcan Airoperated Valves.Operability Evaluation for Byron Units 1 & 2,of Affected Valves W/Nuts of Heat Numbers H & I Completed on 940622 ML20073S9541994-06-27027 June 1994 Part 21 Rept Re Incorrect Matl Supply Discovered on Unshipped Order.Pump Div Will Notify Enertech W/ Recommendation That Items Supplied W/Incorrect Matl Be Removed & Destroyed ML20070A1441994-06-22022 June 1994 Part 21 Rept Re Conditions Which Affect Hydraulic Valve Operators Supplied by Bw/Ip to Enertech Co & Listed Utils. Vendor Will Notify Enertech W/Recommendations That All Items Supplied W/Incorrect Matl Be Removed & Destroyed LD-94-019, Suppl Part 21 Rept Re Notification of Potential Defect in motor-driven Relays Supplied by ABB-CE to Waterford Steam Electric Station Unit 3.Entergy Oparations Aware of Info1994-03-16016 March 1994 Suppl Part 21 Rept Re Notification of Potential Defect in motor-driven Relays Supplied by ABB-CE to Waterford Steam Electric Station Unit 3.Entergy Oparations Aware of Info LD-93-177, Part 21 Rept Re Potter & Brumfield motor-driven Relays Models 7032,7033 & 7034 Supplied by ABB/C-E to Entergy Operations Waterford Steam Electric Station,Unit 3.Eighty- Two Percent of Affected Relays Tested1993-12-23023 December 1993 Part 21 Rept Re Potter & Brumfield motor-driven Relays Models 7032,7033 & 7034 Supplied by ABB/C-E to Entergy Operations Waterford Steam Electric Station,Unit 3.Eighty- Two Percent of Affected Relays Tested 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 ML20058D7061993-11-24024 November 1993 Part 21 Rept 93-022 Re Itt Std Fluid Technology Corp HX Failure Due to Inadequate Process Control by Mfg.Subj HXs Will Either Be Replaced or Inspected for Proper Rolling Prior to Restart from Current Dual Unit Outage 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 ML20057G1511993-10-0707 October 1993 Part 21 Rept Re Westronics Model 2100C Series Recorders. Informs That Over Several Tests,Observed That Recorder Would Reset During Peak Acceleration & Door Being Forced Off Recorder.Small Retaining Clips Added to Bottom of Door ML18096B2421993-02-0101 February 1993 Part 21 Rept Re Possible Matl Defect in Stainless Steel Swagelock Tube Fittings.Initially Reported on 921218.List of Part Numbers,Heat Codes & Addl Affected Customers Encl 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 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217J4791999-10-18018 October 1999 SER Approving Exemption from Certain Requirements of 10CFR73 for Zion Nuclear Power Station,Units 1 & 2.NRC Concluded That Proposed Alternative Measures for Protection Against Radiological Sabotage Meets Requirements of 10CFR73.55 ML20217K9441999-10-15015 October 1999 SER Accepting Util Alternative Proposed Relief Request RR-ENG-2-4 for Second 10-year ISI Interval at Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20217K9151999-10-15015 October 1999 SER Authorizing Util Relief Request RR-ENG-2-3 for Second 10-year ISI Interval of Stp,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(i) ML20217G2161999-10-15015 October 1999 Errata Pages 2 & 3 for Safety Evaluation Supporting Amend 168 Issued to FOL DPR-63 Issued on 990921.New Pages Change Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217F2891999-10-13013 October 1999 Drill 99-08 Emergency Preparedness Exercise on 991013 ML20212K9781999-09-30030 September 1999 Safety Evaluation Accepting USI A-46 Implementation Program ML20217G7211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Waterford 3 Ses. with NOC-AE-000676, Monthly Operating Repts for Sept 1999 for South Texas Project,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for South Texas Project,Units 1 & 2.With ML20217G7461999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Cooper Nuclear Station ML20217D0531999-09-30030 September 1999 Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr ML20217D0481999-09-30030 September 1999 Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 Colr ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217H5221999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Byron Station, Units 1 & 2.With A99026, Monthly Operating Repts for Sept 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20217F9921999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20216J9251999-09-30030 September 1999 Suppl to Special Rept:On 990621,11 Containment Hydrogen Monitoring Sys Chart Recorder Was Indicating Below Normal Operating Range.Caused by Excessive Wear on Valve Body & Discs of Bypass Pump.Sample Pump Replaced ML20217K4631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Nine Mile Point, Unit 1.With ML17300B3811999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pvngs,Units 1,2 & 3.With 991007 Ltr ML20217P6351999-09-29029 September 1999 Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations ML20212F5641999-09-23023 September 1999 SER Concluding That All of ampacity-related Concerns Have Been Resolved & Licensee Provided Adequate Technical Basis to Assure That All of Thermo-Lag Fire Barrier Encl Cables Operating within Acceptable Ampacity Limits 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 ML20212F7301999-09-21021 September 1999 Special Rept:On 990907,CR Operators Declared 12 Containment Hydrogen Monitoring Sys Inoperable for Planned Maint.Cause of Low Flow Condition Was Determined to Be Foreign Matl. Replaced Sample Pump Valve Discs ML20212B9081999-09-14014 September 1999 Special Rept:On 990901, 12 Containment Hydrogen Monitoring Sys Was Declared Inoperable for Planned Maint.Caused by Planned Maint Being Performed as Corrective Action.Check Valves with O Rings Were Replaced ML20211Q6731999-09-0909 September 1999 Safety Evaluation Accepting First 10-yr Interval ISI Program Plan Request for Relief from ASME Code Case N-498 ML20211P8411999-09-0909 September 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Surface Exam to Perform Boroscopic VT-1 Visual Exam of Pump Casing Welds within Pump Pits for Welds Covered by Relief Request RR-ENG-24 ML20211P7811999-09-0909 September 1999 SER Approving Second 10-year Interval Inservice Insp Program Plan Relief Request RR-ENG-2-8 (to Use Code Case N-491-2) for South Texas Project,Units 1 & 2 ML20211Q3171999-09-0909 September 1999 Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20216E4881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Grand Gulf Nuclear Station.With ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 ML20212C4601999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Nine Mile Point Nuclear Station,Unit 1.With ML17300B3271999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pvngs,Units 1,2 & 3 NOC-AE-000643, Monthly Operating Repts for Aug 1999 for South Texas Project,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for South Texas Project,Units 1 & 2.With A99023, Monthly Operating Repts for Aug 1999 for Zion Nuclear Power Station,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Zion Nuclear Power Station,Units 1 & 2.With ML20211K0401999-08-31031 August 1999 SER Accepting Approval of Defueled Station Emergency Plan & Exemption from Certain Requirements of 10CFR50.47, Emergency Plans for Plants,Units 1 & 2 ML20212E5191999-08-31031 August 1999 Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment ML20212C5001999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cooper Nuclear Station ML20211Q2141999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Waterord 3 Ses.With ML20212B9261999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Byron Station,Units 1 & 2.With ML17313B0751999-08-27027 August 1999 LER 99-002-00:on 990730,test Mode Trip Bypass for EDG Output Breakers Not Surveilled.Cause Under Investigation.Operations Personnel Conservatively Invoked SR 3.0.3 for SR 3.8.1.13. with 990827 Ltr ML20211D6491999-08-25025 August 1999 Part 21 Rept Re Nonconformance within LCR-25 safety-related Lead Acid Battery Cells Manufactured by C&D.Analysis of Cells Completed.Analysis of Positive Grid Matl Shows Nonconforming Levels of Calcium within Positive Grid Alloy ML20211F4531999-08-24024 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative to Defer Partial First Period Exams of flange-to-shell Weld to Third Period & Perform Required Ultrasonic Exams,Both Manual & Automated,During Third Period ML20211F5111999-08-23023 August 1999 Safety Evaluation Supporting Licensee Proposed Alternative Contained in Request for Relief RR-ENG-30 ML20210S0581999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Waterford 3.With ML20210Q6361999-07-31031 July 1999 Corrected Monthly Operating Rept for July 1999 for Waterford 3 ML20210R3431999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Byron Station, Units 1 & 2.With ML20210R3631999-07-31031 July 1999 Monthly Operating Repts for July 1999 for South Tx Project, Units 1 & 2.With ML20210R0381999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Cooper Nuclear Station ML20210C9411999-07-31031 July 1999 Rev 1 to SG-99-07-002, South Tx,Unit 1 Cycle 9 Voltage- Based Repair Criteria 90-Day Rept, Jul 1999 ML17313B0611999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pvngs,Units 1,2 & 3.With 990810 Ltr ML20210U4591999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Nine Mile Point, Unit 1.With 1999-09-09
[Table view] |
Text
_ _ _ _ _ _ . .__ __ _ _ _ . _ _ _ . . _ _
150 Lincoln Avenue
. e Grove City, PA 16127 1898 Tel 412 458 8000 Fax 412 458 3574 Ajame COOPER *'=*
ENERGY SERVICES ln e"J'"""*
- En-Tronic@
Penn*
Superior @
March 12,1999 Fax: 301-816-5151 Our Ref: QCG-10528 i Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Amendment to 10 CFR Part 21 Notification, Cooper-Bessemer KSV Emergency Diesel Generator Power Piston Failure.
Dear Sir- l Following the failure of a KSV power piston due to a hydraulic lock at Commonwealth
/
Edison, Zion Station in January,1997, we issued a part 21 notification letter dated May l 29,1997, our reference OCG-10389 The piston which failed had a minimum crown thickness of 0.040 inches, but had operated successfully for several years, and failed only because of the unusual hydraulic lock event. That letter recommended that KSV '
pistons be inspected for crown thickness by ultrasonic or other methods when the !
pistons were exposed in the course of normal maintenance activities. A conservative v minimum thickness limit of 0.100 inches was established.
In the two years since the Zion failure, L total of 198 or more pistons have been measured at seven different sites. Of these, one was found initially in our plant with a thickness of .070 inches and was destroyed. All other pistons checked have been above the 0.100 inch limit, and the actual measured thickness was recorded for 157 of these. All but seven of those documented have had a minimum thickness of 0.150 inch or greater. The attached graph shows the distribution of minimum thickness for the pistons which have been documented. These results, in combination with the successful operating history of the KSV engine provide reasonable assurance that all l potentially defective pistons have been rcmoved from service.
9903190275 990312 <
PDR ADOCK 05000220%j S PDR ;
' ' U U :,' .1 !
1 L J
.. . i Page 2
- March 12,1999 QCG210528 <
Based on this information, Cooper Bessemer believes it is not necessary to continue to !
measure the thickness of piston crowns during other maintenance activities. If you j have any questions, please call John M. Horne at 724-458-3543 Sincerely,
~
I COOPER CAMERON CORPORATION l
(,. -
4 J. M. Horne ,
Engineering Attachment JMH:kil File: K5fa40 - Piston Failure ;
I I
l l
l l
l i
l i
! KSV PISTON CROWN - MINIMUM MEASURED THICKNESS l
30 -
i
! 25- '
i
, m l @ 20- -
! u i E:
{ $ 15- -
! E i e g 10- - -
i 5- '
i
! 0' I .100- .125- .150- .175- .200- .225-' .250- .275- .300- .325- .350- .375- >.400 l .125 .150 .175 .200 .225 .250 .275 .300 .325 .350 .375 .400
- MEASURED THICKNESS -INCHES i .
, _ - , - - , , , , . . .- , . - , . - . _ _ . - , . _ . - - . , ~ - - , , - - - . - , , - - - - , ,
d Page 3 March 12,1999
! OCG-10528 :
l I
Document Control Desk Section Leader U.S. Nuclear Regulatory Procurement Engineering Commission l'*" , Arizona Public Service Washington, D.C. 20555
- P. O. Box 52034, Mall Station 7990 Phoenix, AZ 85072,2034
, Mr. Stephen Alexander U.S. Nuclear Regulatory Ms. Angela K. Krainik Commission ~ Manager, Nuclear Regulatory QA Vendor insp. & Mainten. Branch Affairs One White Flint North Mallstop 9A1 Arizona Public Service Washington, DC 20555 P. O. Box 52034 Mail Station 7636 Phoeniz, AZ 85072-2034 OER Program Administrator
- Nebraska Public Power District Mr. Arvin Ho
- pg Cooper Nuclear Station Commonwealth Edison Company P. O. Box 98 1400 Opus Place, Suite 400 Brownville, NE 68321 Downers Grove,IL 60515 IRC Supervisor Mr. William Wah i Nebraska Pubile Power District Commonwealth Edison Co. l Cooper Nuclear Station c#ed Byron Nuclear Power Station ,
P. O. Box 98 4450 North German Church Road !
Brownville, NE 68321 Byron,IL 61010 Vendor Manual Specialist Mr. Terry Vandevoort ;
Nebraska Public Power District Commonwealth Edison Co. !
Cooper Nuclear Station t' " Zion Generating Station l P. O. Box 98 101 Shiloh Blvd. '
Brownville, NE 68321 Zion, IL 60099 1 D G System Engineer Entergy Operations Nebraska Public Power District Waterford 3 SES, Highway 18 Cooper Nuclear Station wrTC^M Taft, LA 70006 P. O. Box 98 Attn: Mr. Early Ewing Brownville, NE 68321 Director, NS & RA Mr. Greg Stefl STP Nuclear Operation Company pGW d Niagara Mohawk Power Corp. 3*'^h South Texas Project Electric g Nine Mile Road - Unit 2 M P. O. Box 289 l P.O. Box 63 Wadsworth, TX 77483 l Lycoming, NY 13093 Attn: Director Quality & Licensing j Ms. Kathleen Russo Mr. James Kenny Niagara Mohawk Power Corp. Licensing Group Supervisor Nine Mile Road - Unit 2 Pennsylvania Power and Light P. O. Box 63 Two North Ninth Street Annex NA6-1 Lycoming, NY 13093 Allentown, PA 18101
i i
Page4 1
!- March 12,1999 1 QCG-10528 Mr. Robert Bingman 4
- Pennsylvania Power and Light ~N 'N g g , g />o/ 47 (34wewr3Susquehanna Steam Electric Station s u. s G COM^" g P. O. Box 467 Berwick, PA 18603 gc i o 4 3 Mr. John Kocher -
Pennsylvania Power and Light Co. 6 Y40 M Susquehanna Steam Electric Station )
P. O. Box 467 (NUCSA-3)
Berwick, PA 18603 g9
^
i Entergy 0 " # #g
{ p#> P. O. Box 429 V &#
l j G Echelon One fwp 1340 Echelon Parkway Jackson, MS 39286-1995 W A ~C-6A F0g Attn: Fred W.Titus g g c. y 7VM Vice President, Engineering CA*Pg ggg ,
Entergy Operations P. O. Box 756 .
Port Gibson, MS 39150 )
Attn: Wm. K. Hughey Director, NS&RA INTERNAL COPIES:
B. C. Guntrum - Alameda S. Johnston - Alameda M. Donlin - Alameda R. Johnston - Alameda R. Boyles - Grove City
' R. Billig - Grove City J. M. Horne'- Grove City l
o
,0MIM1999 U.S. Nuclear Reg:latory Commission Oper1tions Center Event Report Psgei GeneralInformation or Other (PAR) Event # 35466 Rep Org: COOPER ENERGY SERVICES Notification Date / Time: 03/12/1999 16:27 (EST)
Supplier: COOPER ENERGY SERVICES Event Date / Time:03/12/199912:00 (EST)
, Last Modification: 03/12/1999 Region: 1 Docket #:
i City: GROVE CITY Agreement State: No 1
' County: License #:
State: PA .
1 NRC Notified by: JOHN M. HORNE Notifications: TOM MOSLAK R1 l 4
HQ Ops Officer: DICK JOLLIFFE RONALD GARDNER R3 l 4
Emergency Class: NON EMERGENCY GARY SANBORN R4 l 10 CFR Section: VERN HODGE NRR l 21.21(c)(3)(i) DEFECTS / NONCOMPLIANCE i
i .
i )
l
, - Amendment to 10 CFR Part 21 - Cooper-Bessemer KSV Emergency Diesel Generator Power Piston Failure -
(R;fer to event #32416 for additional information.)
{ .
) Following the failure of a KSV power piston due to a hydraulic lock at Commonwealth Edison Zion Station in j Jtnuary,1997, Cooper Cameron Corporation issued a Part 21 notification letter dated May 29,1997, reference.
- QCG-10389. The piston which failed had a minimum crown thickness of 0.040 inches, but had operated j successfully for several years, and failed only because of the unusual hydraulic lock event. That letter ,
recommended that KSV pistons be inspected for crown thickness by ultrasonic or other methods when the pistons ;
j were exposed in the course of normal maintenance activities. A conservative minimum thickness limit of 0.100 ;
l inches was established. l i
7 l In the 2 years since the Zion failure, a total of 198 or more pistons have been measured at seven different sites.
j Of these, one was found initially in our plant with a thickness of 0.070 inches and was destroyed. All other pistons i checked have been above the 0.100-inch limit, and the actual measured thickness was recorded for 157 of these.
4 All but seven of those documented have had a minimum thickness of 0.150 inch or greater. The distribution of minimum thickness for the pistons has been documented to be from 0.100 to >0.400 inches. These results, in '
combination with the successful operating history of the KSV engine, provide reasonable assurance that all pot:ntially defective pistons have been removed from service.
B: sed on this information, Cooper-Bessemer believes it is not necessary to continue to measure the thickness of piston crowns during other maintenance activities.
This 10 CFR Part 21 Amendment applies to the following plants:
Region 1 - Nine Mile Point and Susquehanna Region 3 - Byron and Zion Region 4 - Cooper, Palo Verde, Waterford, South Texas and Grand Gulf.
(Cill the NRC Operations Center for a contact telephone number.)
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NUMBER OF PAGES INCLUDING COVER: ,b PLEASE CALL (724) 458-3575, IF YOU DID NOTRECEIVE ALL OF THE PAGES l
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i PLEASE NOTE eOUR NEW FAX NUMBER IS 724-458-3461.