Part 21 Rept Re Cracking of Engine Cylinder Heads.After Each Shutdown,All Indicator Cocks Should Be Opened & Engine Slowly Rotated to Look for Signs of Cooling Water Cracks. Part 21 Rept Will Not Be SubmittedML20215N581 |
Person / Time |
---|
Site: |
Cooper |
---|
Issue date: |
10/29/1986 |
---|
From: |
Lambert W COOPER BESSEMER CORP. |
---|
To: |
Haass W NRC |
---|
References |
---|
REF-PT21-86 QCG-3277, NUDOCS 8611070027 |
Download: ML20215N581 (7) |
|
|
---|
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 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 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 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 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 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 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 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 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 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 ML20094J4681992-03-0202 March 1992 Part 21 Rept Re Amot Valve (Amot Part 1476B0212A3).Valve Originally Supplied as Part Number 2-05V-153-004 in Overspeed Shutdown Assembly KSV-72-7.Production of Valve Discontinued & Advises That Alternate Assemble Available ML20094F5211992-02-18018 February 1992 Part 21 Rept Re Defect in Amot Control Corp Safety Trip Valves for Use in Edgs.Defective Overspeed Trip Valve Removed from DG 1.Replacement & Existing Amot Overspeed Trip Valve on DG 2 Inspected & Determined Not to Contain Defect ML20079L4911991-10-29029 October 1991 Part 21 & Deficiency Rept 158 Re Potential Defect in Component of DSRV-16-4 Standby Diesel Generator Sys. Drawing Rev to Increase Gear Tooth Hardness Completed. Recommended Corrective Actions for Sites Listed ML20028H3531990-12-13013 December 1990 Part 21 Rept Re Cable Assemblies Failing to Meet IEEE-383 Section 3 Flammability Tests.Results of Tests Conducted on 901206 Encl.Corrective Actions Include Applying Flame Retardant Covering to Cable or Cable Replacement ML17348B5061990-10-0909 October 1990 Part 21 Rept Re Zener Diode VR2 on Power Supply Board 9 1682 00 106 Possibly Being Installed Backwards ML20005G4391990-01-10010 January 1990 Provides Addl Info on Part 21 Rept Re Defect in Six Instrument Cracks.Licensee Will Not Assume Liability for Defects After Expiration of Warranty 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 ML19324C1131989-11-0202 November 1989 Part 21 Rept Re Defects in Instrument Racks for Use in Hatch,Inc Supplied Emergency Diesel Generator Starting Air & Lube Oil Sys.Verification of All Tube Fittings in Instrument Rack Completed & All Discrepant Fittings Corrected ML20207P0151988-10-0404 October 1988 Part 21 Rept Re Fuel Nozzle Tips in Standby Diesel Generator KSV-20-T W/Cracks Permitting Diesel Fuel to Be Sprayed Into Cylinders.Heavy Vapors Observed Emitting from Breathers on Some Cylinder Heads ML20153B2811988-02-22022 February 1988 Part 21 Rept Re Defect in Operation of Gas Monitors Using Fixed Filters.Initially Reported on 880212.Caused by Error in Software for Monitors.Vendor Testing Mod to Software & in Interim Recommends Changing Filters Every 48 H ML20215N5811986-10-29029 October 1986 Part 21 Rept Re Cracking of Engine Cylinder Heads.After Each Shutdown,All Indicator Cocks Should Be Opened & Engine Slowly Rotated to Look for Signs of Cooling Water Cracks. Part 21 Rept Will Not Be Submitted ML20137X3891986-02-27027 February 1986 Part 21 Rept Re Possible Defect in Model KMG-HRH Noble Gas Radiation Monitor W/Enhanced Detector Model KDGM-HR. Initially Reported on 860222.Vendor Will Request Utils for Listed Plants to Determine If Monitors Defective ML20140A5281985-12-19019 December 1985 Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl ML20064J5801982-11-0808 November 1982 Part 21 Rept Re Matl That May Not Be in Compliance W/ 10CFR50,App B,Section Viii Requirements.Matl Supplied to Ne Public Power District & Omaha Public Power District.Qa Depts Contacted Re Resolution of Nonconformance Situation 1999-09-22
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217G7401999-10-14014 October 1999 Forwards MOR for Sept 1999 for Cooper Nuclear Station. Rept Includes Documentation of Challenges to Safety/Relief Valves,Iaw TS 5.6.4 ML20216J8061999-09-20020 September 1999 Forwards Rev 37 to Safeguards Plan,Iaw Provisions of 10CFR50.(p).Rev Withheld,Per 10CFR73.21 ML20212C4921999-09-15015 September 1999 Forwards Monthly Operating Rept for Aug 1999 for Cooper Nuclear Station.Rept Includes Operating Data Rept,Unit SD Rept & Documentation of Challenges to Safety/Relief Valves ML20211N5271999-09-0202 September 1999 Responds to NRC 990823 RAI Re Y2K Readiness at Cooper Nuclear Station,Per GL 98-01,Suppl 1 05000298/LER-1999-006, Forwards LER 99-006-00 for Cns.Commitments Made by Util Encl1999-08-26026 August 1999 Forwards LER 99-006-00 for Cns.Commitments Made by Util Encl ML20211F1311999-08-24024 August 1999 Forwards Rev 1 to Calculation Nedc 97-044, NPSH Margins for RHR & CS Pumps, in Support of 990615 Proposed Amend to DPR-46 Re Containment Overpressure Contribution to ECCS Pumps NPSH Requirements 05000298/LER-1999-003, Informs That Commitment Re Insp Rept 50-298/98-15 & LER 99-003,to Bound Extent of Condition & Take Appropriate C/As Is Now Complete.Addl Time Is Required to Accommodate Training of Engineering Support Personnel1999-08-23023 August 1999 Informs That Commitment Re Insp Rept 50-298/98-15 & LER 99-003,to Bound Extent of Condition & Take Appropriate C/As Is Now Complete.Addl Time Is Required to Accommodate Training of Engineering Support Personnel ML20210R0301999-08-12012 August 1999 Forwards Monthly Operating Rept for July 1999 for Cooper Nuclear Station,Iaw Guidance Provided by GL 97-02.Rept Also Includes Documentation of Challenges to Srvs,Per TS 5.6.4 ML20210P6761999-08-10010 August 1999 Requests That Following Changes Be Made to Distribution on NRC Correspondence ML20210K6071999-08-0202 August 1999 Submits Withdrawal of Proposed License Amend Re Secondary Containment Isolation Description & Refueling Accident Analysis Results ML20210K3811999-08-0202 August 1999 Forwards Listed Info,Which NPPD Believes Demonstrates Ability to Obtain Funds in Amount of $10 Million for Payment of Such Premiums within Specified Three Month Period,Iaw 10CFR140.21 ML20210G5101999-07-28028 July 1999 Forwards fitness-for-duty Program semi-annual Performance Rept for Period of 990101-0630,per Provisions of 10CFR26.71(d) 05000298/LER-1999-005, Forwards LER 99-005-00 for Cns.Commitments Made by Util Encl1999-07-0101 July 1999 Forwards LER 99-005-00 for Cns.Commitments Made by Util Encl ML20209B7851999-07-0101 July 1999 Forwards Corrected Occupational Radiation Exposure Repts, for Cys 1996 & 1997.Util Stated That Repts Did Not Properly Tabulate Number of Personnel Receiving Exposures Less than 100 Mrem by Work & Job Functions in CY96 & CY97 05000298/LER-1999-004, Forwards LER 99-004-01.Commitments Made by Util Are Encl1999-06-28028 June 1999 Forwards LER 99-004-01.Commitments Made by Util Are Encl ML20209B5451999-06-28028 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl ML20196H0331999-06-24024 June 1999 Informs NRC of Deletion of 1991 Commitment Contained in Ltr Re Feedwater Nozzle Bypass Leakage Monitoring at Plant ML20209A7221999-06-23023 June 1999 Submits Revised Pages to Proposed Change to Plant TS Previously Submitted in ,Per 990615 Telcon with NRC ML20196F5331999-06-22022 June 1999 Forwards Examination Summary Rept for FW Nozzle Examinations Performed During 1998 Fall Refueling Outage at Cooper Nuclear Station.Rept Covers Past Examinations Up to & Including 1998 Fall Refueling Outage ML20196B4681999-06-17017 June 1999 Forwards TS Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610.List of Effective Pages for TS Bases, Encl ML20195H8891999-06-14014 June 1999 Forwards Response to NRC 990315 RAI Re GL 95-07, Pressure Locking & Thermal-Binding of SR Power-Operated Gate Valves, 180-day Response Submitted by District on 960213 ML20195E2351999-06-0808 June 1999 Forwards Response to NRC 990517 RAI Re Util Proposed Change to TS Re Calibr Frequency of Reactor Recirculation Flow Transmitters Associated with APRM ML20207A0701999-05-19019 May 1999 Forwards Rev 3 to CNS Strategy for Achieving Engineering Excellence, Which Provides Effective Tool for Overall Engineering Work Mgt.Commitments Made by Util,Encl ML20206R7601999-05-17017 May 1999 Forwards Annual Radiological Environ Rept,Radiological Environ Monitoring Program,Jan-Dec 1998,per TS 5.6.2 ML20206P9681999-05-13013 May 1999 Forwards Monthly Operating Rept for Apr 1999 for Cooper Nuclear Station.Rept Includes Documentation of Challenges to Safety/Relief Valves ML20206J0741999-05-0404 May 1999 Forwards Rev 14 to CNS QA Program for Operation, Per 10CFR50.54(p) & 10CFR50.71.None of Changes Represent Reduction of Commitments.Summary of Changes,Encl ML20206J2331999-05-0303 May 1999 Forwards CNS Annual Radioactive Effluent Release Rept for 1998 & Offsite Dose Assessment Manual ML20206F2021999-04-30030 April 1999 Informs That NPPD Now Anticipates LAR Committed in Will Be Submitted by 990615.Operability Evaluations Presently in Effect Ensure That ECCS Pumps Are Operable But Nonconforming & Are Capable of Fulfilling Safety Functions ML20206E5461999-04-29029 April 1999 Forwards Cooper Nuclear Station Occupational Radiation Exposure Rept for 1998. Numbers Reported Reflected Tabulation of All Personnel on Site by Work & Job Function. Repts Will Be Corrected & Resubmitted by 990701 ML20205K1151999-04-0101 April 1999 Submits Extension of Commitment Date for Rev to Plant Strategy for Achieving Engineering Excellence from 990331 to 990519.Licensee Requires Addl Time to Finalize & Approve Rev 3 to Plant Strategy for Achieving Engineering Excellence ML20205E4331999-03-31031 March 1999 Forwards First Biennial Rept of Financial Assurance for Decommissioning for Cns,Per 10CFR50.75(f)(1) ML20205A0561999-03-23023 March 1999 Provides Info Detailing Property Insurance Coverage Maintained by NPPD & Midamerican Energy Co for Cns,In Compliance with 10CFR50.54(w)(3) 05000298/LER-1999-001, Forwards LER 99-001-00,including List of NRC Commitments Made by Util1999-03-22022 March 1999 Forwards LER 99-001-00,including List of NRC Commitments Made by Util ML20204G8811999-03-22022 March 1999 Forwards CNS Inservice Insp Summary Rept,Fall 1998 Refueling Outage (RFO-18), IAW Provisions of 10CFR50.55a. Analytical Evaluation for RPV Shell Weld Indications & Augmented Exam Results of RPV Also Included ML20204J4841999-03-19019 March 1999 Requests NRC Review & Approval of CNS ISI Relief Request (RR) PR-04,rev 1.ISI RR PR-04,rev 0 Required CNS to Perform Visual Insp of RPV Head Flange Seal Leak Detection Line. Approval Is Required Because Test Methodology Was Changed 05000298/LER-1998-013, Forwards LER 98-013-01 Re Missed Surveillance of Secondary Containment Isolation Valve.List of NRC Commitments Encl1999-03-16016 March 1999 Forwards LER 98-013-01 Re Missed Surveillance of Secondary Containment Isolation Valve.List of NRC Commitments Encl ML20204C9641999-03-15015 March 1999 Forwards Monthly Operating Rept for Feb 1999 for Cooper Nuclear Station.Rept Includes Documentation of Challenges to Srvs,Per TS 5.6.4 ML20207J5811999-03-10010 March 1999 Forwards Rev 1 to Calculation Nedc 98-024, APRM - RBM Setpoint Calculation ML20207F9661999-03-0101 March 1999 Responds to NRC Re Violations Noted in Insp Rept 50-298/98-08.Corrective Actions:Circumstances Surrounding Four Examples Have Been Discussed with Individuals Involved & Counseled,Where Appropriate ML20203C6961999-02-0808 February 1999 Forwards fitness-for-duty Program semi-annual Performance Rept for Period of 980701-1231,per 10CFR26.71(d) ML20202H6721999-02-0202 February 1999 Informs of Changes in Schedule Affecting Four Commitments in ,By Greater than One Month & Notifies of Plans to Issue Rev 3 to Strategy for Achieving Engineering Excellence ML20202E2231999-01-28028 January 1999 Forwards Response to NRC 980603 RAI Re NRC Ongoing Review of IPEEE for Cooper Nuclear Station,Submitted 961030 ML20199K6721999-01-19019 January 1999 Requests Extension of Present Due Date to 980202,as Addl Time Is Required to Resolve Issues Raised on Corrective Actions During Senior Mgt Review of Insp Rept 50-298/98-15 05000298/LER-1998-011, Forwards LER 98-011-00,per 10CFR50.73(a)(2)(v).Commitments Made by Util,Encl1999-01-19019 January 1999 Forwards LER 98-011-00,per 10CFR50.73(a)(2)(v).Commitments Made by Util,Encl ML20199E6281999-01-14014 January 1999 Forwards Monthly Operating Rept for Dec 1998 for Cooper Nuclear Station.Rept Also Includes Documentation of Challenges to Safety/Relief Valves,Iaw TS 5.6.4 ML20206P4171998-12-31031 December 1998 Informs of Extended Completion Due Date of Third Commitment Re EOP Calculations,Per Licensee 980723 Response to Violations Noted in Insp Rept 50-298/98-02.Date Has Been Extended to 990228 ML20199D2251998-12-30030 December 1998 Forwards 1998 CNS Simulator Certification Rept,As Required by 10CFR55.45.Rept Describes Performance Tests Conducted from 1995-98,discusses Performance Test Discrepancies from 1995-98 & Provides Revised Test Plan for 1999-2002 ML20198K2491998-12-23023 December 1998 Discusses RAI Re Response to NRC GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps ML20205A4411998-12-17017 December 1998 Forwards Initial Exam Outline for RO Written Exam to Be Given Week of 990208.Preliminary Copies of License Applications for Candidates Encl ML20196C4011998-11-20020 November 1998 Forwards Rev 1 to Cooper Nuclear Station COLR Cycle 19. Licensee Discovered That COLR Submitted with Contained Incorrect Max Average Planar Linear Heat Generation Rate Curves Specified in Figures 1 to 4 1999-09-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212K9781999-09-30030 September 1999 Safety Evaluation Accepting USI A-46 Implementation Program ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217G7461999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Cooper Nuclear Station 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 ML20212C5001999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cooper Nuclear Station 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 ML20210R0381999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Cooper Nuclear Station ML20210J2921999-07-29029 July 1999 Special Rept:On 990406,OG TS & Associated Charcoal Absorbers Were Removed from Svc.Caused by Scheduled Maint on Hpci. Evaluation of Offsite Effluent Release Dose Effects Was Performed to Ensure Plant Remained in Compliance ML20209H8281999-07-15015 July 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Cooper Nuclear Station ML20211A9981999-07-12012 July 1999 Draft,Probabilistic Safety Assessment, Risk Info Matrix, Risk Ranking of Systems by Importance Measure ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209E1061999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Cns.With ML20196B3851999-06-17017 June 1999 Summary Rept of Facility Changes,Test & Experiments,Per 10CFR50.59 for Period 970901-990331.Summary of Commitment Changes Made During Same Time Period Also Encl ML20195K2851999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Cooper Nuclear Station.With ML20206P0481999-05-12012 May 1999 Safety Evaluation Concluding That NPP Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at CNS & Adequately Addressed Actions Requested in GL 96-05 ML20206J0811999-05-0404 May 1999 Rev 14 to CNS QA Program for Operation ML20206P9751999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Cooper Nuclear Station ML20205Q0891999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Cooper Nuclear Station.With ML20204G8951999-03-15015 March 1999 CNS Inservice Insp Summary Rept Fall 1998 Refueling Outage (RFO-18) 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 ML20204B3701999-03-11011 March 1999 SER Accepting Third 10-year Interval Inservice Insp Plan Requests for Relief for RI-17,Rev 1 and RI-25,Rev 0.Request for Relief RI-13,Rev 2 Involving Snubber Testing & Is Being Evaluated in Separate Report ML20204C9751999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Cooper Nuclear Station ML20199E6751999-01-14014 January 1999 Monthly Operating Rept for Dec 1998 for Cooper Nuclear Station ML20195B9191998-12-31031 December 1998 1998 NPPD Annual Rept. with ML20196J9641998-12-0707 December 1998 Safety Evaluation Accepting Licensee Third 10-yr Interval Inservice Insp Plan Request for Relief RI-27,rev 1 ML20198D2471998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Cooper Nuclear Station.With ML20196A2861998-11-23023 November 1998 SER Re Core Spray Piping Weld for Cooper Nuclear Station. Staff Concluded That Operation During Cycle 19 Acceptable with Indication re-examined During RFO 18 ML20196A5241998-11-23023 November 1998 Safety Evaluation Accepting Proposed Alternative to Use UT Techniques Qualified to Objectives of App Viil as Implemented by PDI Program in Performing RPV Shell Weld & Shell to Flange Weld Examinations ML20196A5061998-11-23023 November 1998 Safety Evaluation Re Flaw Indication Found in Main Steam Nozzle to Shell Weld NVE-BD-N3A at Cns.Plant Can Be Safely Operated for at Least One Fuel Cycle with Indication in as-is Condition ML20196C4241998-11-20020 November 1998 Rev 1 to Cooper Nuclear Station COLR Cycle 19 ML20195H1761998-11-17017 November 1998 SER Authorizing Proposed Alternative in Relief Requests RV-06,RV-07,RV-09,RV-11,RV-12 & RV-15 Pursuant to 10CFR50.55a(a)(3)(ii).RV-08 Granted Pursuant to 10CFR50.55a(f)(6)(i) & RV-13 Acceptable Under OM-10 ML20195F8601998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Cooper Nuclear Station.With ML20155D9961998-10-31031 October 1998 Rev 0 to GE-NE-B13-01980-24, Fracture Mechanics Evaluation on Observed Indication at N3A Steam Outlet Nozzle to Shell Weld at Cooper Nuclear Station ML20154Q5661998-10-0505 October 1998 Rev 0 to CNS COLR Cycle 19 ML20154L5381998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Cooper Nuclear Station.With ML20151Z6141998-09-16016 September 1998 SER Accepting Util Responses to NRC Bulletin 95-002 for Cooper Nuclear Station ML20154F7931998-08-31031 August 1998 Rev 0 to J11-03354-10, Supplemental Reload Licensing Rept for CNS Reload 18,Cycle 19 ML20153B1101998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Cooper Nuclear Station ML20237E7771998-08-20020 August 1998 Revised COLR Cycle 18 for Cooper Nuclear Station ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML20237C0591998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Cooper Nuclear Station ML20236R9131998-07-20020 July 1998 SER Accepting Rev 13 to Quality Assurance Program for Operation Policy Document for Plant ML20236P2971998-07-0707 July 1998 Rev 2 to NPPD CNS Strategy for Achieving Engineering Excellence ML20236R0931998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Cooper Nuclear Station ML20249A7701998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Cooper Nuclear Station 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 ML20247G0951998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Cooper Nuclear Station ML20237B6861998-04-24024 April 1998 Vols I & II to CNS 1998 Biennial Emergency Exercise Scenario, Scheduled for 980609 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 ML20216G5331998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Cooper Nuclear Station 1999-09-30
[Table view] |
Text
i 50-298 COOPER BESSEMER RECIPROCATING w.w October 29, 1986 Our Ref: QCG-3277 U. S. Nuclear Regulatory Commission Mailstop_EWW332 Washington, D.C. 20555 Attn: Mr. W. P. Haass
Dear Mr. Haass:
SUBJECT:
Nebraska Public Power District Cooper Nuclear Station Standby Diesel / Generators We are sending you herewith a copy of our repcrt covering the cracking of engine cylinder heads. Please note from the report that because this problem is not generic, we do not propose to submit a 10CFR Part 21 Report.
W. If. A. Lambert Manager, Quality Control File: S0-8585 Encl.
kll 8611070027 DR 861029 ADOCK 05000298 Uncoln Avenue PDR k\
Grove City, eennsylvania 16127 .
(412)458-8000 Telex: 86-6613
.monmso,se cournessons . ooron.on,us cournessons . eome eso,~es 4F l
3 %\ -
October 23, 1986 QCG-3268 REPORT .
NEBRASKA PUBLIC POWER DISTRICT (NPPD)
Cooper Nuclear Station, Brownville, Nebraska KSV-16-T Cylinder Head Cracking-Copy Distribution D. T. Blizzard-Director of Engineering, G.C.
D. E. Brazeal-Aftermarket, Tulsa P. R. Danyluk-Manager, Engine Engineering,'G.C.
T. O. Garrison-Aftermarket, Ddessa V'?iP;TNaass-Nuclear Regulatory Commission - Washington, D.C.
G. Horn-Divison Manager, Nuclear 0perations, Nebraska Public Power District J. M. Horne-Manager, Analytical and Compressor Engineering, G.C.
T. W. Kearns-Manager, Application Engineering, G.C.
G. L. Miller-Aftermarket, Mt. Vernon C. Rousselle-Aftermarket, New Orleans M. A. Schleigh-Supervisor, Design Engineering, G.C.
B. R. Sedelmyer-Director of Operations, G.C.
R. L. Spetka-Manager, Aftenmarket, G.C.
K. R. Young-Aftermarket, Mt. _ Vernon 4
6 9
e 6
9
October 23, 1986 QCG-3268 REPORT ,
~
NEBRASKA PUBLIC POWER DISTRICT (NPPD)
Cooper Nuclear Station, Brownville, Nebraska
! KSV-16-T, Cylinder Head Cracking -
i 1.0 Introduction 1.0 Two standard connercial KSV-16-T's were built in 1970 to provide -
standby power at the Cooper Nuclear Station. These engines, rated at 4000 KW (5560 BHP) at 600 RPM, went into service in 1973 and have performed with minimal difficulty. Both engines were built before current NRC regulations became effective, and therefore, manufacturing traceability was not required.
1.2 1e engines are identified as follows:
C-B Serial No. NPPD Engine No.
7102 2 7103 1 1.3 Hours run and number of starts as of October 18, 1986:
Engine No. 1 Engine No. 2 No. of Starts 785 761 No. of Hours 1434 1215 -
1.4 During the current " refueling outage" at Brownville, NPPD had scheduled preventative maintenance programs for each engine. Engine No. 2 was removed from service early October and a diagnostic was performed. Two heads were removed for the purpose of inspecting the _
valve seats. With the two heads removed from the engine, cracks were observed on the fire dome surfaces. Subsequently,- all 16 heads were removed and delivered to the Cooper-Bessemer facility in Tulsa i for inspection. Twelve had cracks in evidence. A crisis developed because sufficient heads to replace all 12 cracked ones were not available, and quoted deliveries would take 25 weeks.
i e
y .e, m e--- ,
. Page 2 QCG-3268 October 23, 1986 2.0 Discussion 2.1 All cylinder heads are subjected to thermal stresses of varying magnitudes which are conditioned by their internal structure. These stresses are tempered by occasional / transient combustion upsets as.
well as external considerations such as load (overload), valve and fuel timing (high peak pressures), cooling water temperature, air manifold temperature, etc.
2.2 In 1970 when these engines were built the state-of-the-art head was a " gas / diesel" (Part No. G18-11-6Af 2) configuration as opposed to a straight diesel head which is currently available. The original head contained gas passages, not required for a diesel head, and therefore, the internal structure was more complicated. While the " gas / diesel" head has proved itself under optimum conditions, it has also demonstrated an inability to withstand abnormal combustion chamber upsets. It should be noted that the most common combustion
. upset arises from incorrect fuel timing which results in high peak pressures and high temperatures associated with this. (Pressure rise is a consequence of temperature rise).
2.3 Ab; ormal thermal cycling leads to high compressive stresses which, upon shutdown (when the heat is turned off) and due to the hysterisis phenomina of cast iron, results in a tensile stress which, if high enough, will cause a crack. Initially such a crack is likely to be hairline in nature, and following many adverse cycles could slowly propogate to the cooling water jacket. From the foregoing, it can be concluded that if a crack were to progress into the water jacket, an internal water leak would be readily detectable shortly after shutdown by rolling the engine with the indicator cocks open. It can further be deduced that by knowing the extent of cracks, cracked heads can be safely run with the limitation being crack propogation to the extent of a detectable water leak.
3.0 Observations 3.1 All 16 heads from Engine No. 2 were magnaflux tested and were hydrostatically tested for one hour at 90 psi with an initial temperature of approximately 200 0 F These tests were witnessed'and recorded by NPPD personnel with copies sent to interested parties.
Appendix "A" shows.a head layout with typical cracking. The results are summarized as follows:
e
,--.,e, - - , - , - , +,-. - -, _ . . ~ - --
e, , ,,,- . - . .- - , , -- - - . - - - - - , . - w-
Pag 3 3 QCG-3268
. October 23, 1986 Left-Ban k -Right-Bank 1.-No cracks, no leaks -Ok. 1. No cracks, no leaks - Ok.
- 2. Cracks, no leaks. Exten- 2. Cracks, no leaks - Ok.
sive pitting- Rejected.
- 3. Minor cracks, no leaks-0k. 3. Cracks, no leaks - Ok.
- 4. Cracks, leaks - Rejected. 4. Craclis, leaks - Rejected'. -
- 5. No cracks, no leaks -Ok. 5. Cracks, no leaks - Ok.
- 6. Cracks, no leaks - Ok. 6. Cracks, no leaks. Extensive
' pitting - Rejected .
- 7. Cracks, no leaks - Ok. 7. Cracks,'no leaks - Ok.
, 8. No cracks, no leaks- Ok. 8. Cracks, no leak - Ok.
4 SUM 4ARY t-4 Heads - No cracks, no leaks - Ok.
8 Heads - Cracks, no leaks- Ok.
i 2 Heads - Cracks, leaks - Rejected.
2 Heads - Cracks .no leaks, pitting - Rejected.
l f 4.0 Recomendations ,
4.1 The eight cracked heads referred to in Paragraph 3.1 as "0K" may be returned to service. Due to the nature of the cracks, they will not propogate while the engine is running, only during cooldown after shutdown. Therefore, after_each shutdown open all indicator cocks, slowly rotate the engine, and look for signs of cooling water leaks.
This procedure may be followed any time after the first hour following a shutdown. This recomendation should be.followed any time
" gas / diesel" heads are in service.
l 4.2 Install new " diesel" heads (part no. KSV-11-6A#1) instead of
" gas / diesel" heads when possible.
4.3 When installing new diesel heads convert to 30 0valve ' seats from 450 in order to minimize valve seat recession and wear.
- 4.4 As soon as Engine No. I becomes available, subject all heads to a i magnaflux and hydrostatic test using the.same procedures and acceptance criteria as for Engine No. 2's heads (Paragraph 3.1).
, 4.5 Repair of cracked h'eads by metal-stitching or any other process is not recommended.
,m .,e------.---~ .---- , +-- .-4 ,,..~..-.,4-.o.---%----- . . . ,-- ,- - - . -- - - . - - - , - , - - - - --- -..
Page 4 !
I
.QCG-3268 October 23, 1986 ,
l l
4.6 Following initial start-up after the rebuilding of the engines, and '
with operating parameters stabilized, peak firing pressures should be measured and recorded. This will confirm that combustion is proper or a need to " tune" the fuel system. In'the process a base-line is established for future reference. Subsequently peak firing pressures should be checked at least twice between refuelling outages. It should be noted that examination of peak firing pressures can reveal problems developing with fuel systems as well as mechanical problems (low pressure may indicate a bent rod caused by the admission of cooling water into a cylinder).
4.7 For the long term, consideration should be given to controlling the aftercooler water system niore closely to maintain an air inlet manifold temperature of 90 - 120 F.
4.8 The NPPD engines are the only ones currently in nuclear. service with the " gas / diesel" cylinder head. The problem of-head cracking is unique to NPPD and, therefore, is not generic. Consequently, Cooper-Bessemer will advise the circumstances to the NRC by copy of this report and does not propose to submit a 10 CFR Part 21 Report.
W. H. E ambert File: S0-8585 K5f Misc.
11-1 7-. - -
. _ . . - . . . . ~ , . - - - -
?,
wr
, QCG-3268 APPENDIX "A" October.23, 1986 I e 2 < t g' 2 3 4 E h Q 3 *
< ;;2 :
g -
Ea be
.@g E c ',
e 0 y h .
I
! l lE l 8 r f ,
I I HpWI& l -_ y
- 1. Spring Itatsiner 3. Spring Keeper 6. Inlet Valve
- 2. Spring Keeper Sesi
- 4. ' valve Guide- .
- 7. Exhaust Valve
- 5. Compression Srring 8. Valve Seat Composite of typical '
cracks. Ilot every head is as extensively cracked as shown here.
- f. % ,
2
( 1 e
Air Q @' Inlet Side
,D 4'
/
2
\
--Air Start Yalve View on Fire Deck (Unnecessary Detail Omitted) .
l P
_ _