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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20154E2171998-09-28028 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 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 L-98-041, Interim Part 21 Rept Re Notification to Dlc Thorugh Stone & Webster Corp.Senior Flexonics Expansion Joints Installed in Unit 2 Service Water Sys,Were Evaluated for Effects of Increased Stiffness Due to Expansion Joint Tie Rods1998-03-0909 March 1998 Interim Part 21 Rept Re Notification to Dlc Thorugh Stone & Webster Corp.Senior Flexonics Expansion Joints Installed in Unit 2 Service Water Sys,Were Evaluated for Effects of Increased Stiffness Due to Expansion Joint Tie Rods L-97-059, Interim Part 21 Rept Re Evaluation of Senior Flexonics Expansion Joints.Work on Small Piping Resource Intensive. Rept Date for Conclusions Scheduled by 9802151997-11-14014 November 1997 Interim Part 21 Rept Re Evaluation of Senior Flexonics Expansion Joints.Work on Small Piping Resource Intensive. Rept Date for Conclusions Scheduled by 980215 ML20141K7741997-04-24024 April 1997 Part 21 Rept Re Auxiliary Feedwater Check Valve Failure. Concluded Thermal Gradient Conditions Created by Flowing Cold Water Through Hot Valve Created Rapid Cooldown of Seat Ring,Allowing Ring to Displace 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 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 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 ML20112D0101996-05-30030 May 1996 Part 21 Rept Re Possible Matl Defect in Certain Stainless Steel Swagelok Tube Fittings.List of Three Addl Shipments to Nuclear Facility of Parts Included in Investigation Encl 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 ML20092H3811995-09-12012 September 1995 Part 21 Rept Re Addl Defective Lot of 3/8-16x11/2 Hex Capscrews ASTM-A-193 Grade B7 from Which Orders Had Been Processed & Sold to Customers by Licensee ML20092H3761995-09-11011 September 1995 Part 21 Rept Re Mechanical Failures Discovered When Conducting Suppl Testing on Lot 3/8-24 X 2 A-193 B7 Hex Capscrews Identified by Head Markings ML20092A0361995-08-29029 August 1995 Part 21 Rept Re Mechanical Failures Discovered When Conducting Suppl Testing on 3/8-24 x2 A-193 B7 Hex Capscrews Identified by Head Markings ML20086T1761995-07-19019 July 1995 Part 21 Rept Re Potential Problem W/Type 51's & 87T Relays. Potential Problem Identified as Defective Tap Block. Recommends That Users Identified on Attachment 1 Page Verify Testing Per Instruction Listed on Encl Product Advisory Ltr ML20072S4611994-09-0505 September 1994 Part 21 Rept Re Ssps semi-automatic Tester at Plant 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 ML20059E9081993-12-29029 December 1993 Part 21 Rept Re Decreases in Valve Actuator Motor Starting Torques Resulting from Increasing 3-Phase Actuator Motor Temp.Concludes Valves Capable of Performing Intended safety- Related Function ML20058K6431993-12-10010 December 1993 Part 21 Rept Re Potential for Unacceptable Recirculation Spray Sys Operation for Supporting Long Term Core Cooling Capability.Caused by Disc of motor-operated Valve on Suction of Pump Not Engaged to Motor Operator ML20058H0791993-12-0303 December 1993 Part 21 Rept Re BVPS Unit 2 Suction Valves for Rs Pumps Supplied by Henry Pratt Co,W/Regard to Inadequate Discharge Pressure.Temporary Mod Made to Four Affected Suction Valves Which Will Properly Position & Retain Spline Adapter ML20046B1321993-07-23023 July 1993 Interim Part 21 Rept Re Decreases in MOV Motor Starting Torques Resulting from Increasing Motor Temp.Valves Mfg by Limitorque Corp.Mfg in Process of Revising Recommended Torque Degradation Calculation at Degraded Voltage ML20128H4561993-01-25025 January 1993 Followup Part 21 Rept Re Disintegration of Balston 21554-1 Automatic Drain Float & Air Piping Filter Assemblies Mfg Prior to Nov 1989.Caused by Contaminants in Air Start Sys. Customers Should Order Air Filters Mfg After Nov 1989 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 ML20116D1241992-10-29029 October 1992 Supplemental Part 21 Rept Re Byron Jackson River Water Pump Couplings.Initially Reported on 921101.Caused by Lack of Matl Toughness.Replacement Couplings Were Screened to Insure Adequate Toughness & Purchase Spec Amended ML20101R3691992-07-0707 July 1992 Final Part 21 Rept Re Failure of Byron Jackson River Water Pump Couplings.Initially Reported on 911121.Couplings Failed in Svc Due to Lack of Toughness.Couplings Examined & Suspect Matl Removed from Svc ML20079L8031991-11-0101 November 1991 Part 21 Rept Re 910620 Failure of Coupling in River Water Pump 1A Supplied by Byron Jackson.Caused by Mechanical Failure of Shaft Coupling.Metallurgical Analysis of Suspect Coupling Will Be Performed & Couplings Replaced ML20082P6871991-09-0404 September 1991 Revised Part 21 Rept Re Failure of Crosby Spring Relief Valves During Testing.Valve Prematurely Lifted During Sixth & Seventh Refueling Outages Due to Use of Stainless Instead of Carbon Steel.Springs,W/New Matl,Installed at Facility ML20077L5661991-08-0505 August 1991 Part 21 Rept Re Crosby Spring Relief Valve Failures Experienced During Testing at Facility.Evaluation Conducted to Determine If Safety Hazard Could Exist.Spring Changed to ASTM-A638 Grade 660,correcting Problem at Facility ML20055E8221990-07-0505 July 1990 Part 21 Rept Re Abb 27/59 Relays Deteriorated Due to Thermal Stress.Initially Reported on 900222.Units W/Listed Identification Numbers to Be Inspected & Replaced If Signs of Overheating Present ML20043A8491990-05-11011 May 1990 Part 21 Rept Re Contactors Used on Diesel Generator Immersion Heater Mfg by Cutler-Hammer.All Contactors W/Date Code Before 890522 Suspect.Dimensions Changed to Correct Problem.Formal Rept Will Be Sent Next Wk ML20011F5971990-02-22022 February 1990 Part 21 Rept Re Solder Connections in Abb 27/59 Relays Deteriorated Due to Thermal Stress,Causing Bonding of Printed Wiring Pattern to Glass Epoxy Circuit Board.Interim Circuit Board W/Larger Pads & Higher Wattage Will Be Used ML20011F1941990-02-22022 February 1990 Part 21 Rept Re Abb 27/59 Relay Catalog Series 211L.Solder Connections to Printed Wiring Runs on Bottom of Circuit Board Deteriorated Due to Thermal Stress.No Actual Failure Occurred & Relays to Be Changed at Next Outage 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 ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking ML20236C7981987-10-22022 October 1987 Part 21 Rept Re Defect Concerning Modulating Solenoid Valve Supplied by Target Rock Corp.Valve Has Been Reassembled Using Proper Spiral Pin ML20237H8281987-08-0707 August 1987 Final Potential Significant Deficiency Rept 87-18 Re Failure of Emergency Switchgear & Diesel Generator Room Supply Fans to Start by Actuation of Switches on Alternate Shutdown Panel.Initially Reported on 870803.Control Switch Replaced ML20235M3651987-07-0101 July 1987 Deficiency Rept 87-09 Re Linear Indication on Reactor Vessel Weld.Initially Reported on 870301. Boat Sample Removed by Westinghouse for Vertical Linear Indication.No Addl Repts Anticipated ML20235H1811987-06-17017 June 1987 Final Deficiency Rept 87-16 Re Improper Installation of Bisco LOCA Seals in Conduits Containing Rockbestos Cable. Initially Reported on 870518.Rework on All Seals Completed ML20215C5771987-06-10010 June 1987 Part 21 Rept Re Small Leak in Unit B Cooling Water Header Lower Pipe in Right Bank of Emergency Diesel Generators. Affected Water Header Pipes Replaced W/Upgraded Matl & Unit a Water Header Pipes Visually Inspected for Leakage ML20215A9951987-06-0202 June 1987 Potential Significant Deficiency Rept 87-15 Re Failure of Main Steam Valve Area Supply Fans to Start Automatically. Initially Reported on 870508.Diesel Sequencer Interlock Rewired to Open Dampers.No Addl Repts Anticipated ML20215B0511987-06-0202 June 1987 Significant Deficiency Rept 87-14 Re Lack of Documentation Certifying Modes 5 & 6 N-1 Operation.Initially Reported on 870507.Appropriate Documentation Expected to Be in Place When Full Power License Received.No Addl Repts Required ML20215A3451987-05-29029 May 1987 Final Deficiency Rept 87-10 Re Linear Indications Identified During Preservice Insp of Reactor Vessel Studs.Initially Reported on 870501.Corrective Actions Include Blending/ Grinding of Surface Indications to Remove Distress Marks ML20214U9511987-05-28028 May 1987 Revised Final Deficiency Rept 87-08 Re Containment Isolation Phase B-initiated Timers for Control Room Emergency Pressurization Fans.Initially Reported on 870327.Correct Date for Completion Is 870504 Instead of 870411 ML20216C9341987-05-28028 May 1987 Potential Significant Deficiency Rept 86-14 Re Outside Containment Flood Analysis.Initially Reported on 860917. Outside Flood Analysis Calculation Revised to Elevate Lines Previously Exempted from Analysis ML20214J4911987-05-25025 May 1987 Interim Significant Deficiency Repts 87-16 & 87-17 Re Conduit Sealing of 50 Class 1E Items.All Physical Work Re Re Environ Qualification Program Complete W/Exception of Four Bisco Seals ML20214V0571987-05-21021 May 1987 Final Significant Deficiency Rept 87-07 Re High Head Safety Injection/ Charging Pump Operating Below Min Operating Curve.Initially Reported on 870323.Pump Rotating Assembly Replaced W/Spare Rotating Assembly & Satisfactorily Tested ML20214H4091987-05-14014 May 1987 Final Deficiency Rept 87-13 Re Pressure Locking & Thermal Binding of Westinghouse Gate Valves.Initially Reported on 870415.S&W Review Resulted in Initiation of Advance Change Notice D-0266 to Correct Discs in 10 Valves 1998-09-28
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARL-99-154, Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with L-99-139, LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With1999-09-0202 September 1999 LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With L-99-140, Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with L-99-126, Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With L-99-107, Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with ML20209D9531999-06-27027 June 1999 Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999 L-99-096, Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with L-99-078, Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable1999-05-0303 May 1999 Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable L-99-079, Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With ML20205L0401999-04-0909 April 1999 SER Accepting Util Relief Requests for Inservice Insp Second 10-year Interval for Beaver Valley Power Station, Unit 2 L-99-054, Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite1999-04-0505 April 1999 Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite L-99-058, Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with ML20196K7981999-03-25025 March 1999 Rev 4 to COLR, for Cycle 8 L-99-038, Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with ML20203E1181999-02-10010 February 1999 SER Accepting Proposed Revs to Plant,Units 1 & 2 Quality Assurance Program Description L-99-019, Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced1999-02-0505 February 1999 Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced ML20196F7011999-01-31031 January 1999 BVPS Unit 2 Heatup & Cooldown Limit Curves During Normal Operation at 15 EFPY Using Code Case N-626 ML20203D4811999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Bvps,Units 1 & 2, in Accordance with NRC GL 97-02.With ML20207E6631999-01-28028 January 1999 Rev 0 to EMECH-0713-1, Operational Assessment of SG Tubing at Beaver Valley Unit 1,Cycle 13 ML20210G7041999-01-22022 January 1999 BVPS Unit 1 Facility Changes,Tests & Experiments for 980123-990122 ML20207E5861998-12-31031 December 1998 Annual Rept 1998 for Toledo Edison ML20207E5601998-12-31031 December 1998 Annual Rept 1998 for Pennpower ML20198B9021998-12-31031 December 1998 BVPS Unit 1 Simulator Four Yr Certification Rept for 1995-1998 ML20207E5901998-12-31031 December 1998 Dqe 1998 Annual Rept to Shareholders ML20199C9971998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Bvps,Units 1 & 2. with ML20207E5521998-12-31031 December 1998 Annual Rept 1998 for Ohio Edison ML20207E5761998-12-31031 December 1998 Annual Rept 1998 for Illuminating Co ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199F5341998-12-29029 December 1998 Safety Evaluation Granting Relief Requests 1-TYP-3-B3.140-1, 1-TYP-3-B5.70-1,1-TYP-3-RH-E-1-1,1-TYP-3-B-G-1, 1-TYP-3-APP-I-1,1-TYP-3-UT-1,1-TYP-3-N-509,1-TYP-3-N-521, 1-TYP-3-N-524,1-TYP-3-B3.120-1 & 1-TYP-3-C6.10-1 ML20198K8551998-12-21021 December 1998 SER Granting Relief Request PRR-5 for Third 10-year Inservice Testing for Beaver Valley Power Station,Unit 1 ML20198A1631998-12-0909 December 1998 SER Approving Implementation Program to Resolve USI A-46 at Facility That Has Adequately Addressed Purpose of 10CFR50.54(f) Request L-98-229, Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with ML20195J3131998-11-12012 November 1998 Safety Evaluation Granting First & Second 10-yr Interval Inservice Insp Request for Relief L-98-210, Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with ML20206G0291998-10-31031 October 1998 BVPS Unit 2 Facility Changes,Tests & Experiments for Period 971101-981031 ML20154R9121998-10-20020 October 1998 Safety Evaluation Accepting Proposed Changes to QA Program Description in Chapter 17.2 of BVPS-2 Ufsar.Proposed Changes Would Modify QA Organization to Allow Warehouse QC Inspectors to Report to Manager of Nuclear Procurement Dept ML20154P7491998-10-19019 October 1998 SE Accepting Second ten-year Interval Inservice Insp Request for Relief RR-1-TYP-2-B5.40-1,Rev 0,for Plant, Unit 1 ML20198F7611998-10-0606 October 1998 Duquesne Light Co,Beaver Valley Power Station 1998 Emergency Preparedness Ingestion Zone Exercise, Conducted on 981006 ML20154C6711998-10-0101 October 1998 Safety Evaluation Concluding That Revised Model Identified in Dl Submittal Was Appropriate for Analysis of Installed Conduit Ampacity Limits.Determined That There Are No Outstanding Safety Concerns with Respect to Ampacity ML20154D5001998-09-30030 September 1998 Special Rept on Overview of BVPS-1 & BVPS-2 TS Compliance Issues & Corrective Action Taken L-98-197, Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With 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 L-98-188, Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure1998-09-21021 September 1998 Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure L-98-178, Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with ML20155B5871998-08-28028 August 1998 Non-proprietary Rev 1 to 51-5001925-01, Risk Assessment for Installation of Electrosleeves at BVPS & Callaway Plant 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 L-98-168, Monthly Operating Repts for July 1998 for Bvps,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Bvps,Units 1 & 2 L-98-157, Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product1998-07-29029 July 1998 Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product L-98-139, Monthly Operating Repts for June 1998 for Bvps,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Bvps,Units 1 & 2 L-98-119, Monthly Operating Repts for Bvps,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for Bvps,Units 1 & 2 1999-09-30
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M 2NRC-7-169 Beaver Vall o. 2 Unit Project Organization Telecopy 1 E Ext.160 P.O. Box 328 July 1, 1987 Shippingport, PA 15077 United States Nuclear Regulatory Commission ;
I Region I 631 Park Avenue f King of Prussia, PA 19406 ATTENTION: Mr. William T. Russell Administrator l
SUBJECT:
Beaver Valley Power Station - Unit No. 2 ,
Docket No. 50-412 l Linear Indication Identified on Reactor Vessel Weld During PSI Examination Potential Significant Deficiency Report 87-09, Final Report l
Gentlemen: l l
This Potentially Reportable Significant Deficiency Report is being submitted pursuant to the requirements of 10CFR50.55(e). It is anticipated t h at no additional reports will be required.
DUQUESNE LIGHT COMPANY By b ao
'J. J. Carey u Vice President DLC/ijr NRC/DLC/SDR/8709 Attachment AR/NAR cc: Mr. P. Tam, Project Manager (w/a)
Mr. J. M. Taylor, Director (3) (w/a)
Mr. J. Beall, Sr. Resident Inspector (w/a) l Mr. L. Prividy, NRC Resident Inspector (w/a) ^
INP0 Records Center (w/a)
NRC Document Control Desk (w/a) j l
- $?fSSb$
S 0$0Uh4 1 1 -
. o 1
ATTACHMENT l
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- 1. Summary l During the performance of the Preservice Inspection (PSI) remote ultra-sonic test (UT) of the Reactor Vessel, an indication was found on the .
outside diameter (0D) on the longitudinal weld (weld #6) located above the J '
loop 1 inlet nozzle. Subsequent surface examination from the OD using '
magnetic particle testing (MT) confirmed the indication.
- 2. Immediate Action Taken An Inservice Inspection Department (ISID) Deficiency Report and a Noncon- {
formance and Dispositon Report (N&D) were written.
Mr. L. M. Rabenau, Lead Compliance Engineer, Beaver Valley Power Station i
Unit No. 2, notified Mr. D. Limrot h , NRC Region I, of this concern on j
l April 1, 1987. An In*.erim Report, 2NRC-7-103, was issued on May 1,1987.
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- 3. Description of Deficiency The PSI examination of the Reactor Vessel identified an approximately 2 inch vertical linear indication on the 0. D. of the vessel at Weld #6, which is located above the loop 1 inlet nozzle. Additionally, three (3) 3/8 inch curvilinears and four (4) curvilinears of various lengths were also identified as a result of the MT.
- 4. Analysis of Safety Implication The results of the UT appear to exceed ASME XI acceptance criteria, IWB Category B-A 1980 - Winter 1980.
- 5. Corrective /ction To Resolve the Deficiency, ,
i A " Boat" sample, approximately 4" long by 1" wide and .75 inches deep, was I removed by Westinghouse NSTD for the vertical linear indication. This area and the areas containing the curvilinear indications have been blend-ed to meet the acceptance criteria of ASME XI, IWB Category B-A 1980 -
Winter 1980. Ultrasonic and magnetic particle examinations confirmed removal of the indication.
The metallurgical evaluations conducted at the Westinghouse research j f acilities were centered around the boat sample containing the axial UT !
indication, as well as several surf ace replicas taken from the shallow-curvilinear indications (with the surface prepared in the polished and etched condition). The evaluations on the boat sample included surf ace examinations by low power light optical microscopy, metallographic and fractographic examinations by light optical and scanning electron :
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microscopy and chemistry evaluations by energy dispersive X-ray analysis techniques. The evaluation of the shallow curvilinear indications was restricted to the vanning electron microscopy examination of the surface j
' replicas from the indications, which were prepared by gold sputtering under vacuum for enhanced imaging characteristics.
The results of the surf ace examination of the boat sample suggested the presence of an approximately 1.85 inch long crack on the boat surf ace. No evidence of a crack could be confirmed on the cut faces of the boat. The examinations indicated no evidence of corrosive attack or deposits on the i boat surface. The results of the metallographic examinations conducted ,
I l (on the boat surf ace as well as on a series containing transverse sections to the crack) in the "as-polished" and " polished and etched" conditions J confirmed that the cracking consistently followed the weld heat affected zone of the top weld pass. The crack measured only 0.05 inches at its deepest location, corresponding to approximately the mid-section along the crack length. The metallography results also confirmed that the crack ,
I followed prior austenite grain boundarios. The crack faces were covered with a thick layer of oxide. The crack tips were rather rounded and Evidence of inadequately tempered martinsite was found near the blunt.
top surface of the boat. A secondary crack initiated at approximately one {
third way down from the top end of the crack was seen arrested approaching j the coarse grained region of the weld heat affected zone. j i
The results of the fractographic examination conducted on the freshly I opened cracks showed that the fracture faces are covered with thick oxide deposits. Light optical color fractography revealed that the oxide i appearance corresponded to a dark grey color suggesting that the cracking may have occurred at temperatures appreciably higher than 1000*F. The thickness of the oxide layer and its color in fact suggested that the cracking may have occurred during the fabrication process. Fractographic examinations of the "as-opened" fracture faces by scanning electron micro-scopy showed that the oxide morphology resembled that ' of iron oxide.
Chemistry evaluation of the crack deposits by energy dispersive X-ray analysis failed to confirm any evidence of detrimental element s. The oxide primarily consisted of iron. Fractographic examination of the "endoxed" (oxide cleaned) fracture faces revealed surface attack and pit-ting morphology characteristic of high temperature surface oxidation.
Scanning electron microscopy examinations conducted on the gold sputtered surface replicas taken from the surface polished curvilinear indications l l
on the vessel OD surface corresponded to surface cracking associated with {
i weld repair process in most cases. Evidence of dissimilar weld micro- i structures on either side of the cracks was seen. l l 3 The results of the metallurgical evaluation on the boat sample showed that the recorded UT indication is associated with a crack measuring approxi-mately 1.85 inches long and 0.05 inches deep at its deepest location. The i crack is located in the seam weld and is contained in the weld heat affected zone of the top weld pass. The results showed that the cracking '
was most likey induced at temperatures in excess of 1000*F.
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Evaluation of the surface replicas from the curvilinear indications k suggested that the indications are associated with surface cracking i induced most likely during a weld repair process in the region. MT exami- !
nations of these indications during subsequent ~ blending showed that these !
curvilinear indications were very shallow.
In summary, the boat sample has been extracted and proved' of no impact on BV-2. No other unacceptable indications have been observed and the R/V is available to be in operation.
- 6. Additional Reports No additional reports are expected, i
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