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 OutagesML20140G448 |
Person / Time |
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Site: |
Perry, Catawba, Harris, Grand Gulf, Columbia, River Bend, Vogtle, San Onofre, Comanche Peak, Rancho Seco, Bellefonte, Shoreham |
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Issue date: |
05/01/1997 |
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From: |
Cote R AFFILIATION NOT ASSIGNED |
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To: |
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
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References |
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REF-PT21-97 NUDOCS 9705090133 |
Download: ML20140G448 (6) |
|
Similar Documents at Perry, Catawba, Harris, Grand Gulf, Columbia, River Bend, Vogtle, San Onofre, Comanche Peak, Rancho Seco, Bellefonte, Shoreham |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20206H2611999-05-0505 May 1999 Part 21 Rept Re Defect Found in Potter & Brumfield Relays. Sixteen Relays Supplied in Lot 913501 by Vendor as Commercial Grade Items.Caused by Insufficient Contact Pad Welding.Relays Replaced with New Relays 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 ML17292B5341999-01-15015 January 1999 Part 21 Rept Re Incorrect Modeling of BWR Lower Plenum Vol in Bison.Defect Applies Only to Reload Fuel Assemblies Currently in Operation at WNP-2.BISON Code Model for WNP-2 Has Been Revised to Correct Error ML17292B5331999-01-15015 January 1999 Part 21 Rept Re XL-S96 CPR Correlation for SVEA-96 Fuel. Defect Applies Only to WNP-2,during Cycles 12,13 & 14 Operation.Evaluations of Defect Performed by ABB-CE ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods 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 ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20236N3871998-07-0909 July 1998 Part 21 Rept Re Deficiency Identified in Event 32725, Corrected by Mgp Instruments Inc.Licensee Verified,Affected Equipment Has Been Reworked & Tested at Sce.Design Mod Completed ML20248A1671998-05-22022 May 1998 Interim Part 21 Re Enterprise DSR-4 & DSRV-4 Emergency diesel.Post-installation Testing Revealed,High Em/Rfi Levels Affected New Controllers,Whereas Original Controllers Were unaffected.Follow-up Will Be Provided No Later than 980731 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20198E0631998-01-0707 January 1998 Part 21 Rept Re Shipment by Dubose National Energy Svcs,Inc, of 40 Pieces of 4 inch,90 Degree Elbows Which Did Not Meet ASME Section II SA-234 Requirements 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 ML20203H9891997-12-12012 December 1997 Part 21 Rept Re Potential Manufacturing Defect of Enterprise DSR-4 & DSRV-4 Edgs.Cooper Energy Svcs Supplied 1A-7840 Adjusting Screw to Affected Utils & Sites.River Bend Station Replaced W/Acceptable Assemblies 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 ML17309A6211997-09-29029 September 1997 Part 21 Rept Re Final Disposition of Masterflow 713 & Embeco 636 Grout Nonconformance Reported by Master Builders,Inc. Licensee Continuing to Monitor shelf-life of Masterflow 713 & Embeco 636 Grouts Produced at Rancho Cucamonga 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 ML20217K5991997-08-11011 August 1997 Part 21 Interim Rept Re Fafnir S7K Bearing Discrepancies. Further Evaluation of Deviation Is Required & Will Be Completed by 971111 ML20217H0511997-08-0505 August 1997 Part 21 Rept Re Discovery That Radiation Monitoring Sys Power Supply Circuit Board Subject to Premature Electronic Component Failure ML18153A1431997-06-10010 June 1997 Part 21 Rept Re Possible Machining Defect in Certain Stainless Steel Swagelok Tube Fitting Bodies.Facilities Have Been Notified About Possible Problem ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20137F3221997-03-26026 March 1997 Part 21 Rept Re Perry Nuclear Power Plant Experiencing False Trip of K600S K-Line Low Voltage Circuit Breaker w/SS-5 Solid State Trip Device.Breaker Removed from Svc & Returned to Abb for Analysis LD-97-002, Part 21 Rept Re Piping Line Loss Between SG & MSIV Inlet When MSSVs Area Activated.Recommends That Utils Confirm Proper Adjustment of MSSV Blowdown Settings So as to Preclude Valve Chatter & Related Structural Concerns1997-01-17017 January 1997 Part 21 Rept Re Piping Line Loss Between SG & MSIV Inlet When MSSVs Area Activated.Recommends That Utils Confirm Proper Adjustment of MSSV Blowdown Settings So as to Preclude Valve Chatter & Related Structural Concerns 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 ML20135D8011996-11-26026 November 1996 Part 21 Rept Re Two Safety Related Valves Supplied by Velan Valve Corp Were Not in Compliance W/Originally Supplied QA Documentation.Returned Valves to Velan in May 1996 & on 961120 Velan Advised That Valves Had Been Misplaced ML20134H3361996-11-0505 November 1996 Part 21 Rept Re Defective Inner Thrust Bearing 1801461-01 Used in PSA 35 Mechanical Shock Arrestor Used as Restraint on Piping Sys for Nuclear Generating Plant.Lot of Defective Parts Located & Isolated to Three Customers ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology ML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl 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 ML17292A2141996-05-0808 May 1996 Part 21 Rept Re Capscrews Supplied to Wppss by Now Defunct Cardinal Industrial Products,Lp (CIP) Having Nonconforming Hardness.Failed Lots & Any Remaining Product Found to Have Been Heat Treated by CIP Scrapped & Removed from Premises 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 ML20100L7411996-02-29029 February 1996 Final Part 21 Rept Re Fan Motor Bearing Indications,Updating Status of Evaluation of Deviation.Bearings for Unit 2 Fcus Inspected & No Linear Indications Noted.Unit 1 Fcu Bearings Will Be Inspected Prior to Upcoming Refueling Outage ML20097A5641996-01-31031 January 1996 Final Part 21 Rept Re Ball Valves Supplied by Cardinal Industrial Products Containing Suspect Pressure Boundary Bolting.Valves Containing Suspect Bolts Returned to Canadian Worcester Controls Ltd to Have Bolting Replaced TXX-9603, Interim Part 21 Rept Re Linear Indication on Fan Motor Bearings Mfg by Fafnir.Bearings Provided as Spares for Four UPS Room Fan Coil Units.Further Evaluation Required & Evaluation Will Be Completed by 9602291996-01-29029 January 1996 Interim Part 21 Rept Re Linear Indication on Fan Motor Bearings Mfg by Fafnir.Bearings Provided as Spares for Four UPS Room Fan Coil Units.Further Evaluation Required & Evaluation Will Be Completed by 960229 ML20094M6251995-11-21021 November 1995 Final Part 21 Rept of Investigation & Analysis of Suspect Fasteners Event 29257.B&G-Cardinal Discontinued Using Heat Treatment Equipment at Cardinal Facility Until Such Time That Satisfactory Mods Made to Hardware & Procedures ML18022A9701995-09-29029 September 1995 Part 21 Rept Re Failure of Charging SI Pump Miniflow Check Valves.Caused by Cocking of Piston Towards Valve Outlet Port Due to Large Hydraulic Surge.Valves That Experienced Failures Replaced ML20092H3641995-09-13013 September 1995 Part 21 Rept Re 3/4 Inch ASME Section III Class 2 Ball Valves Supplied by Canadian Worcester Controls Ltd (Cwcl) ML20086N9981995-07-21021 July 1995 Part 21 Rept Re Mdr Relays W/Potentially Damaged Internal Contact Arms 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 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 ML17291A2571994-07-22022 July 1994 Part 21 Rept Re Westinghouse Containment Penetration Modules Scotchcast Strain Relief & Varglas Insulated Conductors. Replaced Six of 12 RPIS Scotchcast/Varglas Modules & Three Scotchcast/Okonite Modules During Refueling Outage (R-9) ML17291A2351994-07-15015 July 1994 Deficiency Rept Re Material Defects in Facility Containment Penetration Modules.Initially Reported on 940715.Modules Were Replaced ML17290B2001994-05-26026 May 1994 Part 21 Rept Re Automatic Switch Co Replacement Solenoid Pilot Valve Diaphragms Supplied by GE Nuclear Energy.Unusual Combination of Scram Soleniod Pilot Valve Pressure & Exhaust Diaphragm Degradation Caused Failure of Rod to Scram ML20064G3441994-03-0707 March 1994 Part 21 Rept Re RTP Universal I/O Controller Interface Card Utilized in Universal I/O Controller Supplied for Installation at Comanche Peak.Design Corrected Through Engineering Change Order Adding Two Filter Capacitors ML20064G3391994-03-0707 March 1994 Part 21 Rept Re RTP Universal I/O Controller Interface Card Utilized in Universal I/O Controller,Supplied for Installation at Comanche Peak & Yonggwang Nuclear Power Plant,Units 3 & 4.Two Filter Capacitors Added to Design 1999-05-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17284A9001999-10-31031 October 1999 Rev 0 to COLR 99-15, WNP-2 Cycle 15,COLR ML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML18017A9181999-10-0808 October 1999 LER 99-008-00:on 991008,CR Emergency Filtration Sys Tech Specs Occurred.Caused by Site Personnel Failed to Recognize That Blocking Open CR Emergency Filtration Sys.Procedures Revised.With 991008 Ltr ML20217E8021999-10-0707 October 1999 CPSES Unit 1 Cycle 8 Colr GO2-99-177, LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With1999-10-0101 October 1999 LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With ML17284A8941999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for WNP-2.With 991012 Ltr RBG-45144, Monthly Operating Rept for Sept 1999 for River Bend Station. with1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for River Bend Station. with ML20217K4591999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20217K7741999-09-30030 September 1999 Rev 1 to Vegp,Unit 1 Cycle 9 Colr ML20217K8041999-09-30030 September 1999 Rev 1 to Vegp,Unit 2 Cycle 7 Colr ML20217F9921999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20217G4151999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Cpses,Units 1 & 2 ML20217E3381999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Songs,Units 2 & 3 ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico ML18017A9151999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Shearon Harris Npp. with 991012 Ltr ML20217H0201999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Catawba Nuclear Station,Units 1 & 2 PY-CEI-NRR-2437, Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With ML20212F7671999-09-24024 September 1999 SER Granting Relief Request C-4 Pursuant to 10CFR50.55a(g)(6)(i) for Unit 2,during First 10-year ISI Interval & Relief Requests B-15,B-16 & B-17 Pursuant to 10CFR50.55a(g)(6)(i) 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 ML20216J5701999-09-16016 September 1999 Rev 2 to CPSES Unit 2 Cycle 5 Colr ML20212A1471999-09-13013 September 1999 Special Rept:On 990904,condenser Monitor Was Declared Inoperable.Difficulties Encountered During Component Replacement Precluded SCE from Restoring Monitor to Service within 72 H.Alternate Method of Monitoring Was Established ML18017A8671999-09-10010 September 1999 LER 99-007-00:on 990811,determined That Cvis ARMs High Alarm Setpoints Were Not within TS Limit.Caused by Not Having Procedure to Verify If Cvis ARM High Alarm Setpoints Were within TS Requirements.Revised Procedures.With 990910 Ltr ML20216G1201999-09-0909 September 1999 Rev 3 to Rbs,Cycle 9 Colr 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 ML20216E5401999-09-0707 September 1999 Special Rept:On 990826,discovered That Meteorological Sys Upper Wind Speed Cup Set Broken,Causing Upper Wind Channel to Be Inoperable.Cup Set Replaced & Channel Restored to Operable Status on 990826 ML20211N0511999-09-0303 September 1999 SER Approving Exemption from Certain Requirements of 10CFR50.44 & 10CFR50 App A,General Design Criterion 41 to Remove Requirements from Hydrogen Control Systems from SONGS Units 2 & 3 Design Basis ML20211Q8201999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Songs,Units 2 & 3. with ML20216E4881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Grand Gulf Nuclear Station.With ML20216E5061999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Vegp,Units 1 & 2. with ML20212B4711999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate PY-CEI-NRR-2429, Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With ML18017A8621999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Harris Nuclear Plant.With 990908 Ltr ML20217H0321999-08-31031 August 1999 Revised Monthly Operating Rept for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML17284A8801999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for WNP-2.With 990910 Ltr RBG-45110, Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With TXX-9920, Monthly Operating Repts for Aug 1999 for Cpses.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Cpses.With ML20211H8621999-08-23023 August 1999 Safety Evaluation Accepting Licensee Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20211A9791999-08-20020 August 1999 Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2 ML20211C1291999-08-17017 August 1999 ISI Rept Unit 1 Catawba 1999 RFO 11 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20211H7921999-08-13013 August 1999 Safety Evaluation Supporting Amend 126 to License DPR-54 ML20210P4791999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 3 ML20210P4731999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 2 NUREG-1482, SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant1999-08-0909 August 1999 SE Approving Licensee Relief Requets PR-2,PR-3,PR-6,VR-6, VR-7,VR-10,PR-4,PR-5,VR-4,VR-5,VR-9,VR-1 & VR-3 Related to Inservice Testing Program,Second ten-year Interval for Perry Nuclear Power Plant ML20210R1051999-08-0606 August 1999 Special Rept:On 990628,cathodic Protection Sys Was Declared Inoperable After Sys Did Not Pass Acceptance Criteria of Bimonthly Surveillance.Work Request 98085802 Was Initiated & Connections on Well Anode Were Cleaned or Replaced ML20211M2981999-08-0606 August 1999 Rev 1 to CPSES Fuel Storage Licensing Rept, CPSES Credit for Soluble Boron & Expansion of Spent Fuel Storage Capacity, Consisting of Revised Title Page and 4-1 RBG-45087, Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection1999-08-0606 August 1999 Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection ML18016B0481999-08-0404 August 1999 LER 99-006-01:on 981124,noted Failure to Comply with TS 4.0.4 & TS 3/4.6.3, Civs. Caused by post-maint Testing That Did Not Adequately Test Control Circuitry & Verify Isolation Time Following Maint.Procedure Was Revised 1999-09-09
[Table view] |
Text
, 150 Lincoln Avenue Grove City. PA 16121 1898 I
. Tel 412 458 8000 I
, . Fax 412 458 3574 Ajax9 COOPER cab rra*
ENERGY SERVICES Ue"*,',i'e*"*"*
En-Tronic@
Penn Superior @
May 1,1997 i Our Ref: OCG-10382 Document Control Desk I Enterpnse U.S. Nuclear Regulatory Commission Washington, D.C. 20555 P end en 1 l
Dear Sir:
In accordance with the requirements of the Nuclear Regulatory Commission Title 10, Chapter 1, Code of Federal Regulations, Par 121, Cooper Energy Services, a division of Cooper Cameron Corporation, hereby notifies the Commission of a re-emphasis of a previously ,
reported potential defect in a component of a DSRV and DSR Enterprise Standby Diesel !
Generator System. There exists a potential problem with intake and exhaust power valve springs which could result in engine non availability.
Cooper Energy Services has supplied these parts as replacement components to the j following sites: '
l UTILITY SITE SERIAL NO. MODEL LILCO Shoreham 74010-12 DSR-48 )
ENTERGY Grand Gulf 74033-36 DSRV-16-4 4 GULF STATES River Bend 74039-40 DSR-48 i CP&L Shearon Harris r 4046-49 DSRV-16-4 DUKE Catawba 75010-13 DSRV-16-4 SO CAL ED San Onofre 75041-42 SDRV-20-4 CLEVELAND ELEC Perry 75051-54 DSRV-16-4 ;
TVA Bellefonte 75080-83 DSRV-16-4 i WPPSS WPPSSI 75084-85 DSRV-16-4 TU ELECTRIC Comanche Peak 76001-04 DSRV-16-4 GEORGIA POWER Vogtle 76021-24 DSRV-16-4 TVA Hartsville 77024 35 DSRV-16-4 SMUD Rancho Seco 81015-16 DSR-48
- f' 000012
\qg gyggg,1 M') 1 L 9705090133 970501 DR ADOCK 050002 6
- -.- . - - . - . - . .~. -- . . . - - - - - _ ..
Pago2 OCG-10382
- May 1,1997 3 i The specific springs under discussion are manufactured by Associated Spring in Corry,
- I Pennsylvania. They are installed as a subcomponent of spare cylinder heads (4 springs l per cylinder head) or provided as individual spare components by Cooper Energy Services.
4 ,
j' 10 CFR 21 Report #157 was issued by Cooper Energy Services on June 19,1991 to ,
j.
describe surface deficiencies found on valve springs in Cooper Energy Services !
inventory. These deficiencies, characterized by draw marks exceeding the depth .(
allowed by specification, were noted on springs from a 1986 manufacturing lot. There l
- had been no reported failure of valve springs in nuclear or commercial service. Action u
- was taken to inspect all springs in CES inventory, enhance supplier inspection 4
procedures and recommend periodic inspection of all springs in service. ,
i During the summer of 1996 a broken valve spring was found at Duke Power's Catawba l Station during a routine maintenance inspection. No affect on engine performance had -
been noted. This spring, recently returned to CES for analysis, was found to be of the !
, same 1986 vintage as those previously described in Report #157. CES has reviewed i this failure and believes it to be an isolated case but is issuing Report #157 Amendment
- 1 to inform those affected of this failure and to re-emphasize the recommended corrective action.
- As previously reported, it is recommended that the subject springs be inspected on a i periodic basis, such as during refueling outages. Any springs with a visible draw mark !
2 on its I.D. or any physical anomaly of concern should be removed, discarded and ;
- replaced. This inspection should be in each plant's mechanical maintenance !
l procedures and should be considered to apply to all valve springs on Enterprise j Engines regardless of their original manufacturer.
{ lt should also be noted that a correction should be made to the original 10CFR21 i
Report #157 wording Page 2, Para. 5 read as follows," The number of operating hours is of concern as the fatigue failure resulting from such an indication should occur within i-approximately 740 hours0.00856 days <br />0.206 hours <br />0.00122 weeks <br />2.8157e-4 months <br /> (10' operating cycles)."
! A copy of this letter will be sent to all of the sites referenced in Paragraph 2 of this letter
- as indicated by the copy list.
i l Our evaluation of this potential problem was completed on March 26,1997, i
Sincerely,
! ~
COOPER CAMERON CORPORATION i
i ItAY R. M. Cote Vice President and General Manager 4
~
Page 3
.OCG-10382 May 1,1997 cc: D. T. Blizzard - CES/GC J. M. Horne - CES/GC R. G. Billig- CES/GC R. L. Nimmo - CES/ Alameda File: K5fa41 - Assoc. Spring Intake & Exh. Power Valve Springs -
Mr. Walter Haass - NRC One White Flint North Mailstop 9D4 Washington, DC 20555 Carolina Power and Light Harris Nuclear Project P. O. Box 165, State Rd.1134 New Hill, NC 27562 Attn: William Robinson Vice President Carolina Power and Light P. O. Box 1551 Raleigh, NC 27602 Attn: Mgr. Nuclear Licensing Carolina Power and Light Co.
Harris Nuclear Project P. O. Box 165, State Rd.1134 New Hill, NC 27562 Attn: Dept. Manager Carolina Power and Light Co.
Robinson Nuclear Project SC Hwy 151 and 23, Eox 790 Hartsville, SC 295.',0 Attn: Department Manager Cleveland Electric illuminating Perry Nuclear Power Plant P. O. Box 97 Perry, OH 44081 Attn: Russell J. Tadych Manager, Quality Contro'
Page 4
- .OCG-10382 May 1,1997 Cleveland Electric illuminating Perry Nuclear Power Plant P. O. Box 97 Perry, OH 44081 !
Attn: Harold M. Coon l
Cooper-Enterprise Clearinghouse i Duke Engineering & Service )
230 South Tryon St. !
P.O. Box 1004 i Charlotte, NC 28201-1004 Attn: G. A. Harrison Duke Power Co.
Nuclear Generation Dept. ,
P. O. Box 1007 l Charlotte, NC 28201-1007 Attn: Mgr., Nuclear Safety i Duke Power Co.
Nuclear Generation Dept.
P. O. Box 1007
! Charlotte, NC 28201-1007 Attn: W. T. Robertson V. P. Procurement )
i Entergy P. O. Box 429 Echelon One i 1340 Echelon Parkway ;
Jackson, MS 39286-1995 Attn: F. W. Titus Vice President, Engineering l Entergy i j P. O. Box 756 i
Port Gibson, MS 39150 Attn: C. R. Hutchinson Vice Pres., Operations-GGNS i Entergy i
- P. O. Box 756 - l
> Port Gibson, MS 39150 Attn: D. L. Pace, Director Design Engineering-GGNS l
E ' !
1 Pag @5 i-
.OCG-10382 May 1,1997 i
! Entergy i P. O. Box 756
- Port Gibson, MS 39150 !
i Attn: M. J. Meisner -
' Director, NS & RA l l
\
Manager, Quality Services j Entergy Operations ;
Box 756 .- .
- Port Gibson, MS 39150 !
i' !
Southern Nuclear Operating Company ;
Vogtle Project j i P. O. Box 1295 !
Birmingham, AL 35201 l l Attn: Mgr., Engineering l
and Licensing !
) Georgia Power Co. !
- Plant Vogtle !
. P. O. Box 1600
- . Waynesboro, GA 30830 l
- - Attn
- Mr W. B. Shipman .!
General Manager .
Gulf States Utilities
- P. O. Box 220 I
! St. Francisville, LA 70775 j Attn: L. A. England >
Director Nuclear Licensing ,
} Long Island Power Authority !
! Shoreham Nuclear Power Station !
North Country Rd.
Wading River, NY 11792 Attn: . Mgr. Licensing & Regulatory l Compliance Department i i Southern Califomia Edison
! San Onofre Nuclear Generating Station a P. O. Box 128 .
j San Clemente, CA 92672-0128 Attn: Manager, Nuclear Oversite Div.
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May 1,1997 Southern California Edison San Onofre Neulear Generating Station P. O. Box 128 San Clemente, CA 92672-0128 l Attn: ISEG Supervisor Sacramento Municipal Utility Disrict
- Rancho Seco Nuclear Power Plant ;
! 14440 Twin Cities Road l Herald, CA' 95638 l Attn: Vice Pres. & Gen. Mgr. t Tennessee Valley Authority :
- 1101 Market Street, LP 4F .
Chattanooga,TN 37402 :
Attn: Operating Experience Manager i TU Electric - Production Division ,
Group Vice President - Nuclear Skyway Tower .
400 North Olive Street, L.B. 81 <
Dallas, TX 75201
- Attn
- C. L. Terry I
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