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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 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 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 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 ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20101R0641992-07-0808 July 1992 Part 21 Rept Re Defect in Forged Elbow SA234 Wpc.Initially Reported by Util on 920625.Connex Will Audit Quality Sys Prior to Awarding Purchase Orders to Ram Forge to Verify Measurements Taken on Elbow ML20101H5291992-06-25025 June 1992 Part 21 Re Forged Elbow Purchased by Connex Pipe Sys.Elbow Return to Connex to Be Repaired.Elbow Returned to Gulf States Util River Bend Station Unit 1 Along W/Associated Documentation ML20101G9211992-06-19019 June 1992 Part 21 Rept Re Rotated Fuel Assemblies Sometimes Inappropriate for Modern Type Fuel Designs.Reevaluation Concluded That Inadvertently Rotated Fuel Assembly for BWR 4/5 C-lattice Plant Could Not Exceed TS Safety Limit MCPR RBG-37042, Deficiency Rept:Employee Informed NRC of Defect in Forged Replacement Elbow Involving Numerous Areas Where Required Code & Design Min Wall Thickness Was Not Maintained.Licensee Returned Forged Elbow to Supplier1992-06-18018 June 1992 Deficiency Rept:Employee Informed NRC of Defect in Forged Replacement Elbow Involving Numerous Areas Where Required Code & Design Min Wall Thickness Was Not Maintained.Licensee Returned Forged Elbow to Supplier ML20094L1271992-03-13013 March 1992 Amend 1 to Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner.Initially Reported on 920115.Caused by Liner/ Block Fit & Localized Matl Microstructure.All Drawings & Specs Revised to Address Matl Design Requirements ML20043A6091990-04-27027 April 1990 Part 21 Rept Re Defective Axial Cracks in Pump Shaft in Region Immediately Above Impeller & in Reactor Recirculation Pumps.Probably Caused by Crack Growth as Thermal Fatigue. Technical Advisory Bulletin Will Be Sent to Each Util ML19325E7271989-10-20020 October 1989 Part 21 Rept Re Defect in Eight GE Type CR 2940 Control Switches at Plant.Initial Condition Found on 890930.Contacts 3 & 4 for All Switches in Plant Sys Verified to Be in Correct Position for Intended Application RBG-31618, Part 21 Rept Re Defect in Standby Diesel Engine Replacement Rocker Arm Assembly Supplied by Cooper Industries.Caused by Use of Oversized Casting.Rocker Arm Assembly & Corrector Rod Replaced & Exhaust Valve Stems Readjusted1989-10-13013 October 1989 Part 21 Rept Re Defect in Standby Diesel Engine Replacement Rocker Arm Assembly Supplied by Cooper Industries.Caused by Use of Oversized Casting.Rocker Arm Assembly & Corrector Rod Replaced & Exhaust Valve Stems Readjusted RBG-31583, Part 21 Rept Re Slow Closure of One Main Turbine Control Valve.Caused by Turbine Control Valve Assumed to Close Due to Unspecified Failure in Turbine Control Circuit.Standing Order Issued to Change Max Critical Power Ratio Limit1989-10-0202 October 1989 Part 21 Rept Re Slow Closure of One Main Turbine Control Valve.Caused by Turbine Control Valve Assumed to Close Due to Unspecified Failure in Turbine Control Circuit.Standing Order Issued to Change Max Critical Power Ratio Limit ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating RBG-31189, Supplemental Part 21 Rept Re Defect in safety-related Limitorque Valve Operators.Initially Reported on 880119.List of Limitorque Operators W/Wire Lug Defaults Encl.All Defects Corrected Prior to Restart1989-06-30030 June 1989 Supplemental Part 21 Rept Re Defect in safety-related Limitorque Valve Operators.Initially Reported on 880119.List of Limitorque Operators W/Wire Lug Defaults Encl.All Defects Corrected Prior to Restart ML20245B6651989-06-15015 June 1989 Part 21 Rept 150 Re Potential Defect in Component of Dsr Standby Diesel Generator.Cause of Failure Determined to Be Combination of Insufficient Lubrication to Bushings.Listed Course of Action Recommended at Next Scheduled Engine Maint ML20154J4101988-05-12012 May 1988 Addendum 1 to Supplemental Part 21 Rept 145 Re Potential Problem w/F-573-156 Pressure Sensor/Lube Oil Trip.Initially Reported on 880429.Addl 1-1/8-inch Diameter W/Deep Counterbone in Pressure Head Added to Activate Valve ML20153B6191988-04-29029 April 1988 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generators Supplied to Utils.Recommends Return of Subj Components in Onsite Warehouse Storage & Suggests Surveillance of Devices Already Installed RBG-27313, Part 21 Rept Re Defect in safety-related Limitorque Valve Operators.Initially Reported on 880114.Defective Lugs Replaced W/Correctly Sized Lugs & Rev of Procedures Underway to Include Insp of Lug Size on Motor Leads1988-01-19019 January 1988 Part 21 Rept Re Defect in safety-related Limitorque Valve Operators.Initially Reported on 880114.Defective Lugs Replaced W/Correctly Sized Lugs & Rev of Procedures Underway to Include Insp of Lug Size on Motor Leads ML20237G5781987-08-0707 August 1987 Part 21 & Deficiency Rept 142 Re Defect in Starting Air Distributor Sys of Dsr Standby Diesel Generator.Drain Sys Will Be Permanently Installed in Start Air Distributor ML20236N7131987-08-0505 August 1987 Part 21 Rept Re Potential Problem W/Vibration in Lube Oil & Jacket Water Sys.At Rancho Seco Site,Fatigue Cracks Found in Welds of Support Members in Lubricating Oil Sys.Cracks Due to Vibration in Lube Oil Sys.Addl Preventive Action Taken ML20234C7351987-06-23023 June 1987 Supplemental Part 21 Rept Re Silicone Foam Seal Anomolies at Wolf Creek Generating Station ML20216E4721987-05-28028 May 1987 Part 21 Rept 140 Re Potential Defect in Air Pressure Regulators Mfg by Bellofram.Dripwell Gasket May Fail Due to Mismachining of Gasket Seating Surface Causing Loss of Control Air & Starting Air Pressure ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20211B8381987-02-11011 February 1987 Part 21 Rept Re Misoperation of Ite 50D Overcurrent Relay Due to RCA Pnp Transistor Which Developed Abnormally High Leakage Rate Over Time.Relay Replaced.Rca Failure Analysis of Transistor Indicated Leakage Caused by Ionic Mobility ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires ML20154N4361986-03-10010 March 1986 Part 21 Rept Re Defect on Inflatable Door Seals for Personnel Air Locks Used in Reactor Containment Sys of Nuclear Power Plants.Initially Reported on 830919.Environ Qualification Testing of New Seal Design Completed ML20154Q3141986-03-10010 March 1986 Final Part 21 Rept Re Possible Defect on Inflatable Door Seals for Personnel Air Locks Used in Plant Reactor Containment Sys.Program to Supply Environmentally Qualified Inflatable Seals Should Be Completed by mid-1986 ML20154N3431986-03-10010 March 1986 Initial Part 21 Rept 135 Re Potential Problem W/Lube Oil Sump Tank Foot Valve of Dsrv Standby Diesel Generator for Facilities.Cause Not Determined.Recommends Utils Inspect Condition of Foot Valve Liners & Notify Tdi of Findings ML20198C4981985-11-0606 November 1985 Part 21 Rept Re Potential Defect in Dsr or Dsrv Standby Diesel Generator Intake & Exhaust Valve Springs Mfg by Betts Spring Co.Users Recommended to Inspect Engines for Broken Springs & Identify Original Mfg RBG-22-514, Final Deficiency Rept DR-193 Re post-LOCA Passive Failure in ECCS Suction Line in Auxiliary Bldg Crescent Area.Initially Reported on 850114.Suppression Pool Pumpback Sys Intended to Mitigate post-LOCA Passive Failures1985-11-0101 November 1985 Final Deficiency Rept DR-193 Re post-LOCA Passive Failure in ECCS Suction Line in Auxiliary Bldg Crescent Area.Initially Reported on 850114.Suppression Pool Pumpback Sys Intended to Mitigate post-LOCA Passive Failures RBG-22395, Final Deficiency Rept DR-314 Re Fluid Leakage from Pump Seals to Pump Drive Motor in Borg-Warner Electrohydraulic Operators for Copes-Vulcan Modulating Valves.Initially Reported on 850830.Actuator Assemblies Repaired1985-10-16016 October 1985 Final Deficiency Rept DR-314 Re Fluid Leakage from Pump Seals to Pump Drive Motor in Borg-Warner Electrohydraulic Operators for Copes-Vulcan Modulating Valves.Initially Reported on 850830.Actuator Assemblies Repaired ML20205C6891985-09-17017 September 1985 Part 21 Rept Re Potential Defect in Centerline,Inc Lube Oil Check Valves of Dsr Standby Diesel Generator Which Could Result in Engine Nonavailability.Valve Seat Matl Will Be Changed to Buna N.List of Tdi Part 21 Repts Encl RBG-22-116, Revised Final Part 21 Rept DR-259 Re Split Terminal Blocks Mfg by Underwriters Safety Device Co.Engineering & Design Coordination Rept Initiated & Corrective Maint Procedure 1026 Changed Re Replacement of Restraints1985-09-16016 September 1985 Revised Final Part 21 Rept DR-259 Re Split Terminal Blocks Mfg by Underwriters Safety Device Co.Engineering & Design Coordination Rept Initiated & Corrective Maint Procedure 1026 Changed Re Replacement of Restraints RBG-22-121, Interim Deficiency Rept DR-314 Re Leakage of Fluid Fyrquel from Pump Seals to Pump Drive Motor in Borg-Warner Electrohydraulic Operators for Copes-Vulcan Modulating Valves.Interim or Final Rept Will Be Provided by 8510161985-09-16016 September 1985 Interim Deficiency Rept DR-314 Re Leakage of Fluid Fyrquel from Pump Seals to Pump Drive Motor in Borg-Warner Electrohydraulic Operators for Copes-Vulcan Modulating Valves.Interim or Final Rept Will Be Provided by 851016 ML20135A8381985-09-0505 September 1985 Part 21 Rept Re Environ Qualification Failure of Reliance Class Rh Ac Motors During Qualification Testing.Item Not Reportable Per Part 21 ML20132B0261985-09-0303 September 1985 Part 21 Rept Re Possibility of Engine Ingestion of Unwelded Part in American Air Filter Standby Diesel Generator Intake Silencer.Immediate Hold Should Be Placed on Diesel Engines/Intake Silencers Not Yet in Svc ML20135F1761985-08-30030 August 1985 Corrected Interim Deficiency Rept DR-314 Re Leakage of Fluid Fyrguel for Copes-Vulcan Modulating Valves.Initially Reported on 850718.Valves Replaced,Motor Reoriented & Visual Exams Conducted.Interim or Final Rept by 850916 RBG-22-003, Final Deficiency Rept DR-322 Re Loss of Water from Standby Cooling Tower.Initially Reported on 850823.Galvanized Angle Bolted to Concrete Walkways Installed at Each of Four Air Intake Cells of Standby Cooling Tower1985-08-30030 August 1985 Final Deficiency Rept DR-322 Re Loss of Water from Standby Cooling Tower.Initially Reported on 850823.Galvanized Angle Bolted to Concrete Walkways Installed at Each of Four Air Intake Cells of Standby Cooling Tower RBG-22-002, Final Deficiency Rept DR-314 Re Leakage of Fluid Fyrguel from Pump Seals to Borg-Warner Pump Drive Motor Operators for Copes-Vulcan Valves.Initially Reported on 850718.Next Rept by 8509161985-08-30030 August 1985 Final Deficiency Rept DR-314 Re Leakage of Fluid Fyrguel from Pump Seals to Borg-Warner Pump Drive Motor Operators for Copes-Vulcan Valves.Initially Reported on 850718.Next Rept by 850916 RBG-21903, Interim Deficiency Rept DR-314 Re Leakage of Fluid Fyrquel from Pump Seals to Pump Drive Motor in Borg-Warner Electrohydraulic Operators for Copes-Vulcan Modulating Valves.Next Rept Will Be Submitted by 8509061985-08-20020 August 1985 Interim Deficiency Rept DR-314 Re Leakage of Fluid Fyrquel from Pump Seals to Pump Drive Motor in Borg-Warner Electrohydraulic Operators for Copes-Vulcan Modulating Valves.Next Rept Will Be Submitted by 850906 ML20210G9921985-08-13013 August 1985 Part 21 Rept Re Failure of Isolated Worm Shaft Gear When Certain Critical Speeds Combined W/Repetitive Transfer of Actuator Clutch Mechanism from Manual (Handwheel) to Motor Drive Mode.Two Possible Solutions Noted RBG-21762, Forwards Supplemental Response to 840613 Request for Addl Info Re Status of Corrective Action on Five Recent 10CFR21 Notices Issued by Tdi1985-07-31031 July 1985 Forwards Supplemental Response to 840613 Request for Addl Info Re Status of Corrective Action on Five Recent 10CFR21 Notices Issued by Tdi RBG-21677, Final Deficiency Rept DR-319 Re Corroded Torque Switches in motor-operated Valves Supplied by Limitorque.Valves Repaired.Condition Not Reportable Per 10CFR50.55(e)1985-07-25025 July 1985 Final Deficiency Rept DR-319 Re Corroded Torque Switches in motor-operated Valves Supplied by Limitorque.Valves Repaired.Condition Not Reportable Per 10CFR50.55(e) RBG-21659, Final Deficiency Rept DR-290 Re Leak Rates of Charcoal Filtration Sys Ductwork.Initially Reported on 850724.All Affected Ductwork Retested Using Fan Pressures Taken from vendor-supplied Fan Performance Curves1985-07-24024 July 1985 Final Deficiency Rept DR-290 Re Leak Rates of Charcoal Filtration Sys Ductwork.Initially Reported on 850724.All Affected Ductwork Retested Using Fan Pressures Taken from vendor-supplied Fan Performance Curves 1998-09-28
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARRBG-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 ML20216G1201999-09-0909 September 1999 Rev 3 to Rbs,Cycle 9 Colr 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 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 ML20210K4721999-08-0303 August 1999 SER Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves RBG-45091, Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With ML20210C6391999-07-0202 July 1999 Rev 2 to River Bend Station,Cycle 9 Colr RBG-45055, Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With ML20196J8031999-06-24024 June 1999 Rev 1 to Rbs,Cycle 9 Colr RBG-45028, Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With RBG-45016, Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With ML20206A2111999-04-21021 April 1999 Safety Evaluation Authorizing Pump Relief Request PRR-001 & Valve Relief Request VRR-001 & Denying Valve Relief Request VRR-002 RBG-44969, Monthly Operating Rept for Mar 1999 for River Bend Station, Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for River Bend Station, Unit 1.With ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205D5481999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Exam Weld AA with Weld Volume Coverage of 62 Percent for First 10-year Insp Interval Pursuant to 10CFR50.55a(a)(3)(ii) & 10CFR50.55a(g)(6)(ii)(A)(5) RBG-44930, Monthly Operating Rept for Feb 1999 for River Bend Station, Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for River Bend Station, Unit 1.With RBG-44826, Monthly Operating Rept for Dec 1998 for River Bend Station Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for River Bend Station Unit 1.With ML20198K2701998-12-22022 December 1998 Rev 1 to RBS Cycle 8 Colr RBG-44773, Monthly Operating Rept for Nov 1998 for River Bend Station, Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for River Bend Station, Unit 1.With RBG-44727, LER 98-S01-00:on 981021,identified That Contract Employee with Temporary Access Authorization Failed to Disclose Complete Criminal & Employment History.Individual Denied Access to Plants for Five Years.With1998-11-17017 November 1998 LER 98-S01-00:on 981021,identified That Contract Employee with Temporary Access Authorization Failed to Disclose Complete Criminal & Employment History.Individual Denied Access to Plants for Five Years.With ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20155H3491998-11-0303 November 1998 Safety Evaluation Granting Requests for Relief RR2-0001, RR2-0002 & RR2-0003 RBG-44719, Monthly Operating Rept for Oct 1998 for River Bend Station, Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for River Bend Station, Unit 1.With ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual RBG-44677, Monthly Operating Rept for Sept 1998 for River Bend Station, Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for River Bend Station, Unit 1.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 ML20151S5421998-09-0303 September 1998 Safety Evaluation Opposing Licensee Thermal Model as Currently Implemented.Evaluation Recommended to Be Used in Any follow-up Site Insp RBG-44629, Monthly Operating Rept for Aug 1998 for River Bend Station, Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for River Bend Station, Unit 1.With 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 RBG-44600, Monthly Operating Rept for July 1998 for River Bend Station1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for River Bend Station RBG-44564, Monthly Operating Rept for June 1998 for River Bend Station, Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for River Bend Station, Unit 1 ML20249A6431998-06-12012 June 1998 SER Accepting 980427 Request for Change to River Bend QA Manual Program Description,Per 10CFR50.54(a)(3) RBG-44539, Monthly Operating Rept for May 1998 for River Bend Station, Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for River Bend Station, Unit 1 RBG-44501, Monthly Operating Rept for Apr 1998 for River Bend Station, Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for River Bend Station, Unit 1 ML20217M8951998-04-30030 April 1998 QA Program Manual ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) RBG-44458, Monthly Operating Rept for Mar 1998 for River Bend Station, Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for River Bend Station, Unit 1 RBG-44423, Monthly Operating Rept for Feb 1998 for River Bend Station Unit 11998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for River Bend Station Unit 1 ML20203L6631998-02-11011 February 1998 Rev 0 to River Bend Station,1998 Emergency Preparedness Exercise RBG-44385, Monthly Operating Rept for Jan 1998 for River Bend Station, Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for River Bend Station, Unit 1 RBG-44353, Monthly Operating Rept for Dec 1997 for River Bend Station, Unit 11997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for River Bend Station, Unit 1 RBG-44460, Forwards Annual Radiological Environmental Operating Rept, for Period Jan-Dec 19971997-12-31031 December 1997 Forwards Annual Radiological Environmental Operating Rept, for Period Jan-Dec 1997 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 ML20202E9941997-12-0101 December 1997 ISI Plan Second Ten-Yr Interval (Dec 1,1997-Nov 30,2007) ML20199K9741997-11-30030 November 1997 Brief Aerial Photography Analysis of RBS at St Francisville,LA:1996-1997 RBG-44337, Monthly Operating Rept for Nov 1997 for River Bend Station, Unit 11997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for River Bend Station, Unit 1 ML20202F0191997-11-28028 November 1997 Safety Evaluation Approving Transfer of License NPF-47 for River Bend Station,Unit 1 ML20199H3711997-11-19019 November 1997 SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50 RBG-44295, Monthly Operating Rept for Oct 1997 for River Bend Station Unit 11997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for River Bend Station Unit 1 RBG-44243, LER 97-S03-00:on 970911,contract Employee Was Granted Temporary Access After Failing to List Prior Employment Termination & Access Denial.Caused by Employee Failure to Provide Accurate Info.Updated Info Re Employee1997-10-13013 October 1997 LER 97-S03-00:on 970911,contract Employee Was Granted Temporary Access After Failing to List Prior Employment Termination & Access Denial.Caused by Employee Failure to Provide Accurate Info.Updated Info Re Employee 1999-09-09
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CONNEX tw oma um lat 94 373 m3 PIPE SYSTEMS nu no m m July 8.1992 U.S. Nuclear Regulatory Commission Document Control Desk Washington,DC 20555 REF: Gulf States Utilities Co. ~ Regert of Defect Dated June 18,1992 RBO 37012 File No. 09.5 River Bend Station UN*
Document No. 50-458 Gendemen:
Connex Pipe Systems. Inc. has completed its investipt an of the defect discovered by Gulf States Utilities Co. (GSU) on the 12" Sch. 80 LR 90' Ellmw S A234 V PC and subsequently, reported in accordance with the requirements of 10CFR21. The following is a summary of the steps that were taken during the investigation to determine an adequate co:Tective action.
Initial Corrective Action was to irmove Ram Forge irom Connex's Approved Vendors List until further investigation could be performed. This was documented on Connex's Corrective Action Request (CAR
- 92-007) and verified by copy of Connex's Approved Vendors List.
In addition, Connex was able to determine that the Ram Forge ellow was an isolated occurrence. This was based upon wall thickness measurements taken on numerous elbows at Connex --all of which contained acceptable wall thickness. (See attached Ultrasonic thickness readings)
Connex. accompanied by GSU, went to Rarn Forge to determine the root cause and verify Corrective Action. (See Ram Forge Discrepancy Report) Further investigation while at Ram Forge disclosed the fact
- that this particular eltow required ten (10) heats to form the citow within the dye. This was unusual since they normally require two (2) heats. An excess of scale caused by the additional heats necessitated a great deal of grinding. Consequently, the elbow was gimnd below wall and not visible to the eye. Ram
~
Forge did not question the wall thickness becausc past experience had shown their elbows to be much heavier. This was demonstrated to Connex and GSU from readings taken on a grid pattern on elbows for other customers.
Ram Forge has stated that they will check all elbows for wall thickness on 100% of ASME III orders. The wall thickness measurements will be taken on a grid over the entire elbow. Connex was unable to verify implementation since there were no ASME Ill orders for cibows in house at Ram Forge, L
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VI I A we a e eme cw D DO [
CONNEX nn sonas U.S. Nuclear Regulatory Commission Page 2 of 2 REF: Gulf States Utilities Co. Report of Defect Dated June 18.1992.RBO 37(M2 File No. 09.5 River Bend Statkm Unit #1 Document No. 50-458 Psior to awarding Purchase Orders to Ram Forge. Connes shall audit their Quality System and assure provisions are in place to recomplish Ram Forge's corrective action and verify measurements taken on cibows at that time. Ram Forge will remain off Connes's Approved Vendors List until the audit is performed and is acceptable to Connex.
Siiretely.
OC b, +(
D.J. L iger V.P. Technical Services attachments DJL cak ec: Ram Forge and Steel Inc.
P.O. Box $92 Industrial Park Road Navasota. Texas 77868 Mr. D. C. Deddens Senior Vice President River Bend Nuclear Group Gulf States Utilities P.O. Box 220 St.Francisville,LA 70775 U. S. Nuclear Regulatory Conaission 611 Ryan Plaza Drive Suite 4(X)
Arlington.TX 76011 NRC Resident inspectkm P.O. Box 1051 St.Francisville.LA 70775 i
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teemesu m no i n614.1136463 PIPE SYSTEMS t.u mss rea June 25,1992 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 REF.: Gulf States Utilitic_ Co. - Report of Defect Dated June 18,1992- RBC 37042 File No. C9.5 River Bend Station - Unit 1 Document No. 50-458 Gentlemen:
We have reviewed Gulf States Utilities' Report of Defect per 10CFR21 and offer the following clarifications and additional information:
The forged replacement elbow was purchased by Connex Pipe Systems on Purchase Order E8634-2 Item #1 from Ram Forge and shipped direct to Gulf States Utilities River Bend Station Unit 1 from Ram Forge and Steel Inc., P.O. Box 592, Industrial Park Road, Navasota, Texas 77868.
The elbow was then accepted by Gulf States Utilities River Bend Station -
Unit 1 and was in the process of being machined when the defect was discovered. Upon notification by Gulf States, the elbow was returned to Connex to be repaired.
Connex reworked the elbow in accordance with ASME III NB-4130. The rework of the elbow was documented on Connex sketch E8630-1. The elbow was then returned to Gulf States Utilities River Bend Station Unit 1 along with the associated documentation.
- h. addition, Connex took immediate corrective action by removing Ram Forge from Connex's Approved Vendors List until a fullinvestigation could be completed.
,- -.~ M dOAnjPO YE~J~;[ .
. 'CONNEX PM $ftfl#8 U.S. Nuclear Regulatory Commission June 25,1992 2 of 7 Document Control Desk Washington,DC 20555 i P
Preliminary results o' our investigation indicate that this was an isolated
- occurrence; however, specific cause has yet to be determined.
We hope this additional information will help supplement the report issued by Gulf States Utilities.
- Sincerely, CONNEX P:PE SYSTEMS,INC. -
J ,
- D. Leininger V.P. Technical " i . L - -
DJL:cak cc: U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive Suite 400
' Arlington,TX 76011 l-NRC Resident inspection P.O. Box 1051
' St. Francisville, LA 70775 Mr. D. C. Deddens Senior Vice President 1
. River Bend Nuclear Group Gulf States Utilities P.O. Box 220 St. Francisville, LA 70775.
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June 18, 1992 REG 37012 File No. G9.5 U.S. Nuclear Regulatory Commission Documeni Control Desk Washington, D.C. 20555 Gentlemen:
River Bend Station - Unit 1 Docket No. 50-458 Pursuant to the requirements of 10CFR21.21(c)(3), Gulf States Utilities Company (GSU)is submitting this written report of a defect in a forged replacement elbow.
The specified location for the elbow is in a 12" feedwater line. The attached report provides the information required by 10CFR21,21.
Sincerely, f
J. C. Deddens Senior Vice President
- River Bend Nuclear Group VHO/LM - RH/DNUDCH/NHZ/kym Attachment I
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cc: U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Resident Inspector P.O. Box 1051 St. Francisville, LA 70775 Connex Pipe Systems, Inc.
1115 Gilman Avenue Marietta, OH 45750 Attn: Mr. Kevin Welch m
- __ .m o__ -_ . __ -
t ATTACHMENT GULF STATES UTILITIED COMPANY River Dend Station - Unit 1 Report of a Defect Per 10CFR21 Connex Pipe Systems, Inc.
- 1. Name and address of individual (s) informing the NRC:
Mr. J. C. Deddens, Senior Vice President, Gulf States Utilities Company Address: Post Office Box 220 St. Francisville, LA 70775
- 2. Identification of the facility, the activity, or the basic component supplied for the f acility or activity which f ails to comply or contains a defect:
The basic componaut containing a defect was a forged replacement elbow, Connex sketch E-8634-1. The specified location of the elbow is at the first elbow off of reactor pressure vessel feedwater nozzle N4A.
- 3. Identification of the firm constructing or supplying the basic component which fails to comply or contains a defect:
Connex Pipe Systems, Inc.
1115 Gilman Avenue Marietta, OH 45750
- 4. Nature of the defect or failure to comply and the safety hazard which is created:
The defect, revealed by Ultrasonic testing (UT) of the forged elbow involved numerous areas where the required code and design minimum wall thickness was not maintained. The nominal wall thickness was 0.688 and the code minimum thickness was 0.535". The minimum wall thickness measured was 0.378".
Because GSU discovered this deviation prior to installation there was no operational impact. However, due to the gross reduction in vall thickness a substartial safety hazard could have been created had this defect remained uncorrected because the specified location is the first elbow off of reactor pressure vessel feedwater nozzle N4A, an unisolable portion of the reactor coolant pressure boundary,
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- 5. The date on which the information of the defect or failure to comply was obtained:
A condition report (CR) was issued indentifying the minimum I wall violations on June 5, 1992. GSU's evaluation of the condition per 10CFR21 determined l the condition to be i reportable on June 18, 1992. ,
- 6. In the case of a basic component which contains a de"ect or j f ails to comply, the number and location of all the components ;
in use at, supplied for, or being supplied for one or more facilities or activities subject to the regulations of 10CFR21:
The affected basic component is the forged elbow, Connex sketch E-8634-1, supplied to GSU as a one-time replacement
-part.
7.~ The corrective action which has been, or will be taken; the name'of-the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action:
GSU returned the forged elbow-to the supplier. The component was reworked to ASME III, NB-4130 and returned to GSU.
- 8. Any advice related to the defect or failure to comply about-the facility, activity, or basic component that has been, is being, or will be given to purchasers or licensees:
Not applicable.
i
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' GOLF STATES UTILITIES RIVER' BEND STATION Component Data Report t 53333333848535833333333238385233332555883333333338385235322233333333333333 REFERENCE #: 200322 COMPONENT ID: FWS010037L2 TYPE: Elbow DRAWING No.: EP-17F DESCRIPTION : HWO#R145249 ELBOW (PRESERVICE)
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AVERAGE HEAS: 0.700 REHARKS- FWS010037L2. R145249 (PRE-SERVICE INSPECTION)
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n TEST DATE...: 06/04/92 RING #1 POSITION: 0.00 in. DS 3 INSP. INT. . .: I=-1.03890 (I=Lr/KOc) RING' SPACING....: 2.00 in.
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PM SY311M8 A ==== st me ines = s, JOB: 92-6 AVL TO: L. Evans 3. McConkey ANI R. Davis Estimating DATE: 6-8-92 T. Long M. Huck K. Welch B. Day i C. Knaus-2 R. Nodes D. Sch FROM: D. L. Schaffer
'e r D. Leininger J. Sweeney A ttn Customer P.O.
NOTE: Attached are the following listed documents. Please receipt one copy of this form and return immediately. This is our record of your having received the referenced documen ts.
Received by Date Sign i Return Required YE5 g NO FILMS
_ _ _ CERTIFIED PRINTS Comments: Please sisn & Return PRINTS FOR QA APPRoy AL
_ VELLUM FOR APPROVAL SE PI A PRELIMINA RY xx OTHER M.BIL LS
_ ORIGINAL FINAL INFORMATION ONLY QTY. DOCUMENT NO. AND TITLE REV. QTY. DOCUMENT NO. AND TITLE R E V.
I an. AVL Index 92-6 DELETIONS Ram Forste & Steel. Inc,
. hlb M
S L