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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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l 1-* .s j GULF STATES UTILITIES " OMPANY RNER SEND STU10N PO$f OFFICE BOX 220 $1 FRANCISVILLI.LOVistANA 70775 AREA CODE 604 635 6094 346 8651 January 19, 1988 RBC- 27313 File Nos. G9.5, G9.25.1.2 Regional Administrator ' @[?IllW/[s[f'
~ * ' ~ ~
m U.S. Nuclear Regulatory Commission l' l Region IV : JAN29 M 611 Ryan Plaza Drive, Suite 1000 I ,
Arlington, TX 76011 O
Gentlemen:
River Bend Station - Unit 1 Docket No. 50-458 Pursuant to the requirements of 10CFR21.21(b)(2), Gulf States Utilities Company (GSU) is submitting this written report of a defect in safety-related Limitorque valve operators at River Bend Station. Initial notification of this defect was provided by telephone on January 14, 1988 to Mr. Glen Madsen of the NRC-Region IV from Mr. Rick J. King of GSU. t The attached report provides the information required by 10CFR21.21.
Sincerely, Vl n J. C. Deddens Senior Vice President River Bend Nuclear C: cup JCD/J
,/
RG/
L[Mffl[
(RH/UNL/ch a 1) o$$ Attachment 00""
00 cc: Director
$c Office of Nuclear Regulatory Regulation g U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Q
oc o
f ca NRC Resident Inspector P.O. Box 1051
$$ St. Francisville LA 70775 coa.tn Mr. Pat McQuillian Limitorque Corporation P.O. Box 11318 j,, -
g Lynchburg, VA 24506-1318 jf
o,- .
ATTACHMENT Gulf States Utilities Ccapany River Bend Station - Unit 1 Report of a Defect Per 10CFR21.21
- 1. Name and address of individual (s)"informing the NRC.
Written notification is provided by this report from Mr. J.C. Deddens, !
Senior Vice President.
Address: Gulf States Utilities Post Office Box 220 St. Francisville, LA 70775
- 2. Identification of the facility, the activity or the basic component supplied for the facility or activity within the United States which l fails to comply or contains a defect.
l The defect was found in five safety-related valve operators at River l Bend Station - Unit 1. The valves which were found to contain the :
defect were three main steam shutoff valves (Mark Nos. IB21*MOVF098A, j B,C) and two feedwater isolation valves (Mark Nos. IB21*MOVF065A and IFWS*MOV7A).
1
- 3. Identification of the firm constructing or supplying the basic component which fails to comply or contains a defect.
The wire lugs were contained in valve operators supplied during initial !
construction of River Bend Station by Limitorque Corporation.
?' l
- 4. Nature of the defect or failure to comply and the safety hazard which !
is created by the defect or failure to comply.
During functional testing of main steam shutoff valve, 1B21*MOVF098B, the valve failed to fully close. The motor operator experienced a high current surge and tripped its motor overload heater. During investigation, two motor leads were found burned and separated from the
, wire lugs. The third lug was easily pulled from the wire lead after removing heat shrink insulation. The lugs were found to be oversized for the motor lead conductors. Also, while performing maintenance on feedwater isolation valve, IFWS*MOV7A, a lug on one motor lead was found to be oversized for the conductor and not crimped.
The lugs were marked "T&B Navy 23-30 E-6" and were sized for use with a
- 5-6 AWG conductor. The motor leads were #10 stranded conductor.
- Further investigation found that both valves used Limitorque SMB-4 operators with terminal blocks that had one-quarter inch diameter terminal screws. The lugs were the correct size for the one-quarter i
l 1.
1
' C;4
-.. - ai inch screw, 6ut -not the cerrect size for the conductor. This is the only size of Limitorque operator ar 4RBS 't. hat uses a quarter-inch terminal screw. /
All safety related SMB-4 operators were inspected to determine lug size. Of a total of ten operatorp in safety related service, five were found with oversized Irgs and were deemed to be unreliable although
, chey passed surveillances requirenents. The logs were repaired by .
replacing them withc'orrectly sized lugs. !
The lugs could potentially cause the valves to fail to operate when required, ast was the case during the testing of IB21*MOVF0988, a main steam shutoff valve used in conjunction with main steam isolation valve
- posit'he 4 leakage control system (MSIV-PLCS) to limit leakage from the main steam lines to the environment following an accident. Failure of these valvef' to close would cause 'the outboard division of MSIV-PLCS to be inoparable. The feedwater isolation valves are used to isolate one feedwater intet line to the/ reactor vessel. These valves, along with the penetration valve leakag'e control system (PVLCS), are used to limit leakage from the. feedwater line following an accident. The potential failure of these. valves to cicoe would cauce PVLCS to be inoperable for one feedwater line.' If these ' events o c cu c-::d following a loss of coolant accident, Ioakage control systems vould not function properly, ,
potentially leading' to radipactive releases to the environment. '
a,\
- 5. The date on which the informecion
of the defect or failure to comply was obtained. ;
e ,
The initial condition was fou'nd on December 7, 1987 as reported in Condition Report CR 37-1640. / Subsequent evaluation determined the condition to be reportable pe; {0CFR21 on January 14, 1988. .
- 6. In the case "vf a basic component which contains a defect or fails to ,
comply, the number and location of all the components in use at, i supplied for, or being supplied for one or more facilities or activities subject to the regulations of 10CFR21. i
' )
. l A total of ten Limitorque SMB-4 operators are used in safety related applicaqions at River Bend Station. The function of those valves containing i the defect is given in Sections 2 and 4 above.
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- 7. The correctize action wht:b has been, or will be taken; the name of the
' ihdividual or organization responsible for the action; and the length of time that has been or vill be taken to complete the action.
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GSU has replaced the defective lugs with correctly sized lugs. This l s work was performed by Maintenance Work Orders 118783, 113618, and 111336. This corrective action was completed on December 12, 1987. In i addition, receipt inspection of Limitorque motor operators is being I revised to includL inspection of lug size on motor leads eo prevent r
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reoccurence of this condition. Revision of procedures controlling this activity will be completed by February 29, 1988.
GSU believes the condition is only applicable to SMB-4 operators.
However, due to potential generic concerns with applicability of this condition to other size Limitorque motor operators, CSU will also inspect a sample of other operator sizes. This sampling program will be performed per MIL-STD-105D and will be completed prior to start up following the second refueling outage.
- 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.