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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000416/LER-1993-011, Corrected LER 93-011-00:on 931007,loss of Shutdown Cooling & ESF Actuation Occurred.Caused by Operator Error.Event Discussed W/Operations Personnel & Info Labels Placed on Inverter Panels at Power Supply Switch1993-11-0808 November 1993 Corrected LER 93-011-00:on 931007,loss of Shutdown Cooling & ESF Actuation Occurred.Caused by Operator Error.Event Discussed W/Operations Personnel & Info Labels Placed on Inverter Panels at Power Supply Switch 05000416/LER-1993-0071993-08-26026 August 1993 LER 93-007-00:on 930723,violation of OL Condition 2.C.(38) Occurred Due to Access Points Not Clearly Marked to Identify Envelope Boundary.Marked Access panels.W/930826 Ltr 05000416/LER-1993-0061993-08-20020 August 1993 LER 93-006-00:on 930720 & 21,annunciator,specifying High Temp in RHR Sys Equipment Room Received in Cr,Causing RCIC Sys Isolation.Caused by Failure of Equipment Room Differential Temp Switch.Switch replaced.W/930820 Ltr 05000416/LER-1993-0031993-08-12012 August 1993 LER 93-003-01:on 930324,SSW C Sys Pump Motor Failed Due to Movement of Motor Stator End Windings During Motor star-ups.SSW C Pump Replaced & Failed Motor Refurbished by GE & Being receipt-inspected.W/930812 Ltr 05000416/LER-1990-0081990-06-20020 June 1990 LER 90-008-00:on 900521,discovered That Fire Rated Door Required by Tech Spec 3/4.7.7 Not Designated as Tech Spec Door in Ssurveillance Procedures.Caused by Incorrect Interpretation of Tech Spec requirements.W/900620 Ltr 05000416/LER-1987-006, Corrected LER 87-006-00:on 870501,isolation Valve in Steam Supply Piping to RCIC Sys Turbine Inadvertently Isolated. Caused by Personnel Error.Personnel Counseled1987-05-29029 May 1987 Corrected LER 87-006-00:on 870501,isolation Valve in Steam Supply Piping to RCIC Sys Turbine Inadvertently Isolated. Caused by Personnel Error.Personnel Counseled 05000416/LER-1984-050, Corrected LER 84-050-03:on 841102,condition on 841015 Re Safe shutdown-related Cables Found W/Omitted Fire Rated Barriers Determined Outside Design Basis.Design Change Documents Initiated1985-08-15015 August 1985 Corrected LER 84-050-03:on 841102,condition on 841015 Re Safe shutdown-related Cables Found W/Omitted Fire Rated Barriers Determined Outside Design Basis.Design Change Documents Initiated 05000416/LER-1984-020, Revised LER 84-020-01:on 840423,24 & 0514,during Startup, Five Reactor Water Cleanup Sys Isolations Occurred Due to Feedwater Flow Oscillations1984-06-0606 June 1984 Revised LER 84-020-01:on 840423,24 & 0514,during Startup, Five Reactor Water Cleanup Sys Isolations Occurred Due to Feedwater Flow Oscillations 05000416/LER-1984-002, Final LER 84-002-02:on 840107,09,11,14,19 & 20 & 0223 & 24, Reactor Protective Sys Bus Breaker Trips Resulted in Loss of Shutdown Cooling.Trip on 840119 Caused by Circuit Board Failure.Remainder Caused by Voltage Transients1984-05-30030 May 1984 Final LER 84-002-02:on 840107,09,11,14,19 & 20 & 0223 & 24, Reactor Protective Sys Bus Breaker Trips Resulted in Loss of Shutdown Cooling.Trip on 840119 Caused by Circuit Board Failure.Remainder Caused by Voltage Transients 05000416/LER-1984-018, Corrected LER 84-018-00:on 840414,shutdown Cooling Sys Isolation Occurred When Technician Lifted Wrong Lead During Performance of Monthly Surveillance.Technician Reprimanded, Lead Terminated & Shutdown Cooling Restored1984-05-10010 May 1984 Corrected LER 84-018-00:on 840414,shutdown Cooling Sys Isolation Occurred When Technician Lifted Wrong Lead During Performance of Monthly Surveillance.Technician Reprimanded, Lead Terminated & Shutdown Cooling Restored 05000416/LER-1983-136, Updated LER 83-136/03X-4:on 830830,Div 1 Diesel Generator Shut Down Due to Failure of Exhaust Gaskets on RB1 & LB5 Cylinders & Two Broken Welds on Intercoolers.Caused by Loose Manifold Bolts & Turbocharger misalignment.W/8403301984-03-30030 March 1984 Updated LER 83-136/03X-4:on 830830,Div 1 Diesel Generator Shut Down Due to Failure of Exhaust Gaskets on RB1 & LB5 Cylinders & Two Broken Welds on Intercoolers.Caused by Loose Manifold Bolts & Turbocharger misalignment.W/840330 Ltr 05000416/LER-1984-005, Updated LER 84-005-01:on 840119,drywell Purge Compressor Logic a Relay Compressor Inadvertently Started.Caused by Defective Procedure.Memo Written to All Technical Section Engineers Re Adequate Engineering Review1984-03-30030 March 1984 Updated LER 84-005-01:on 840119,drywell Purge Compressor Logic a Relay Compressor Inadvertently Started.Caused by Defective Procedure.Memo Written to All Technical Section Engineers Re Adequate Engineering Review 05000416/LER-1983-078, Updated LER 83-078/03X-2:on 830701,control Room Operator Unable to Maintain Air Receiver Pressure for Diesel Generator 11.Caused by Setpoint Drift & Damaged Valve Seals. Sensing Point to Air Receiving Tanks relocated.W/840330 L1984-03-30030 March 1984 Updated LER 83-078/03X-2:on 830701,control Room Operator Unable to Maintain Air Receiver Pressure for Diesel Generator 11.Caused by Setpoint Drift & Damaged Valve Seals. Sensing Point to Air Receiving Tanks relocated.W/840330 Ltr 05000416/LER-1983-107, Updated LER 83-107/03X-2:on 830726,during Test,Mounting Bolts for Div 1 Diesel Generator Turbocharger Found Loose or Broken & Associated Parts & Welds Cracked.Caused by Misaligned Turbocharger.Longer Bolts installed.W/840327 Lt1984-03-27027 March 1984 Updated LER 83-107/03X-2:on 830726,during Test,Mounting Bolts for Div 1 Diesel Generator Turbocharger Found Loose or Broken & Associated Parts & Welds Cracked.Caused by Misaligned Turbocharger.Longer Bolts installed.W/840327 Ltr 05000416/LER-1983-187, Updated LER 83-187/03X-1:on 831122,maint Technicians Filling Ref Leg Caused Spike on Reactor Vessel Level Transmitters, Resulting in Div 1 Automatic Actuations.Caused by Personnel error.W/840326 Ltr1984-03-26026 March 1984 Updated LER 83-187/03X-1:on 831122,maint Technicians Filling Ref Leg Caused Spike on Reactor Vessel Level Transmitters, Resulting in Div 1 Automatic Actuations.Caused by Personnel error.W/840326 Ltr 05000416/LER-1982-080, Update LER 82-080/01X-4:on 821004,capscrew on Div 2 Standby Diesel Generator Securing Rear Crankcase Cover to Engine Block Cracked.Caused by Fatigue Due to Engine Operation. Capscrews Replaced1984-03-21021 March 1984 Update LER 82-080/01X-4:on 821004,capscrew on Div 2 Standby Diesel Generator Securing Rear Crankcase Cover to Engine Block Cracked.Caused by Fatigue Due to Engine Operation. Capscrews Replaced 05000416/LER-1983-169, Corrected LER 83-169/03X-1:on 831023,nitrogen Pressure Control Rod Scram Accumulators 40-53 & 24-29 Fell Below Tech Specs.Caused by Normal Leakage.Accumulators Recharged.W/ 840321 Ltr1984-03-21021 March 1984 Corrected LER 83-169/03X-1:on 831023,nitrogen Pressure Control Rod Scram Accumulators 40-53 & 24-29 Fell Below Tech Specs.Caused by Normal Leakage.Accumulators Recharged.W/ 840321 Ltr 05000416/LER-1983-190, Updated LER 83-190/03X-1:on 831214,Div 2 Isolation Occurred, Causing Loss of Shutdown Cooling When Pump Suction Valve F009 Isolated.Caused by Temporary Outage Restoration Procedure Error.Procedure retired.W/840321 Ltr1984-03-21021 March 1984 Updated LER 83-190/03X-1:on 831214,Div 2 Isolation Occurred, Causing Loss of Shutdown Cooling When Pump Suction Valve F009 Isolated.Caused by Temporary Outage Restoration Procedure Error.Procedure retired.W/840321 Ltr 05000416/LER-1983-188, Updated LER 83-188/03X-1:on 831201,reactor Protection Sys Bus B & Shutdown Cooling Lost When Power Supply Breaker Tripped.Caused by Isolation Valve on Suction of Pump Closing.Time Delay Setting Increased to 3.5 s.W/840321 Ltr1984-03-21021 March 1984 Updated LER 83-188/03X-1:on 831201,reactor Protection Sys Bus B & Shutdown Cooling Lost When Power Supply Breaker Tripped.Caused by Isolation Valve on Suction of Pump Closing.Time Delay Setting Increased to 3.5 s.W/840321 Ltr 05000416/LER-1983-122, Updated LER 83-122/01X-1:on 830908,valve P64F467 Which Supplies Operating Pressure to CO2 Fire Protection Master Selector Valve Found Closed.Cause Unknown.Valve Now Locked open.W/840321 Ltr1984-03-21021 March 1984 Updated LER 83-122/01X-1:on 830908,valve P64F467 Which Supplies Operating Pressure to CO2 Fire Protection Master Selector Valve Found Closed.Cause Unknown.Valve Now Locked open.W/840321 Ltr 05000416/LER-1983-171, Updated LER 83-171/03X-1:on 831028,fuel Oil Leak & Broken Connector Pushrod Discovered.Caused by Crack in Oil Tubing & Difficulty in Welding Pushrod.Tubing & Pushrod Replaced. W/840316 Ltr1984-03-16016 March 1984 Updated LER 83-171/03X-1:on 831028,fuel Oil Leak & Broken Connector Pushrod Discovered.Caused by Crack in Oil Tubing & Difficulty in Welding Pushrod.Tubing & Pushrod Replaced. W/840316 Ltr 05000416/LER-1983-189, Updated LER 83-189/03X-1:on 831207 & 840201,breaker 152-1704 to Div 3 ESF Bus Tripped.Caused by Broken Current Limiter Resistor Socket for Breaker Position Indicating Light. Agastat Relay 7012 Replaced1984-03-12012 March 1984 Updated LER 83-189/03X-1:on 831207 & 840201,breaker 152-1704 to Div 3 ESF Bus Tripped.Caused by Broken Current Limiter Resistor Socket for Breaker Position Indicating Light. Agastat Relay 7012 Replaced 05000416/LER-1983-126, Updated LER 83-126/01X-1:on 830904,Div 1 Diesel Generator Fuel Line Ruptured,Causing Fire Near Left Bank Turbocharger. Caused by Fatigue Crack Propagation.Fuel Line Support Added to Div 1 & 2 Diesel generators.W/840308 Ltr1984-03-0808 March 1984 Updated LER 83-126/01X-1:on 830904,Div 1 Diesel Generator Fuel Line Ruptured,Causing Fire Near Left Bank Turbocharger. Caused by Fatigue Crack Propagation.Fuel Line Support Added to Div 1 & 2 Diesel generators.W/840308 Ltr 05000416/LER-1983-179, Updated LER 83-179/03X-1:on 831105,Div II Diesel Generator Shut Down Upon Discovery of Fuel Oil Return Line Leak.After Repair During Restart,Generator Tripped Due to Isolation of Fuel Supply Valve F016B.W/840308 Ltr1984-03-0808 March 1984 Updated LER 83-179/03X-1:on 831105,Div II Diesel Generator Shut Down Upon Discovery of Fuel Oil Return Line Leak.After Repair During Restart,Generator Tripped Due to Isolation of Fuel Supply Valve F016B.W/840308 Ltr 05000416/LER-1983-185, Updated LER 83-185/03X-1:on 831201,while in Cold Shutdown, Breaker 552-2105 Tripped,Causing Loss of Power to Div 1 ESF Bus & All Balance of Plant Loads.Caused by Two Shorted Wires in Breaker Hand Switch.Wires altered.W/840302 L1984-03-0202 March 1984 Updated LER 83-185/03X-1:on 831201,while in Cold Shutdown, Breaker 552-2105 Tripped,Causing Loss of Power to Div 1 ESF Bus & All Balance of Plant Loads.Caused by Two Shorted Wires in Breaker Hand Switch.Wires altered.W/840302 Ltr 05000416/LER-1983-156, Updated LER 83-156/03X-1:on 831003,capscrew Securing Starting Air Manifold to Support Plate on Left Bank Cylinder 8 Found Broken Inside Plate.Cause Undetermined.Capscrew replaced.W/840302 Ltr1984-03-0202 March 1984 Updated LER 83-156/03X-1:on 831003,capscrew Securing Starting Air Manifold to Support Plate on Left Bank Cylinder 8 Found Broken Inside Plate.Cause Undetermined.Capscrew replaced.W/840302 Ltr 05000416/LER-1983-181, Updated LER 83-181/03X-1:on 831110,channel C as-found Setpoints for Undervoltage Trip Were 116.2-volt Ac.Cause Unknown.Voltage Adjusted within Desired range.W/840221 Ltr1984-02-21021 February 1984 Updated LER 83-181/03X-1:on 831110,channel C as-found Setpoints for Undervoltage Trip Were 116.2-volt Ac.Cause Unknown.Voltage Adjusted within Desired range.W/840221 Ltr 05000416/LER-1983-180, Updated LER 83-180/03X-1:on 831107,drywell Floor Drain Sump Level & Flow Monitoring Leak Detection Sys Discovered Inoperable.Cause Undetermined.Sys Monitored for 2 Wks W/O Repeating problem.W/840217 Ltr1984-02-17017 February 1984 Updated LER 83-180/03X-1:on 831107,drywell Floor Drain Sump Level & Flow Monitoring Leak Detection Sys Discovered Inoperable.Cause Undetermined.Sys Monitored for 2 Wks W/O Repeating problem.W/840217 Ltr 05000416/LER-1983-109, Updated LER 83-109/03X-2:on 830727,spurious RHR Room High Area Temp or Delta Temp Signal Caused Inboard Shutdown Cooling Valve F009 Closure.Caused by Loose Plug Connection on Riley Temp switch.W/840214 Ltr1984-02-14014 February 1984 Updated LER 83-109/03X-2:on 830727,spurious RHR Room High Area Temp or Delta Temp Signal Caused Inboard Shutdown Cooling Valve F009 Closure.Caused by Loose Plug Connection on Riley Temp switch.W/840214 Ltr 05000416/LER-1983-177, Updated LER 83-177/03X-1:on 831029,1102 & 06,water Collected in Offgas Pretreatment Monitor,Resulting in Improper Flow Through Monitor.Caused by Accumulation of Condensation.Heat Tracing Installed on piping.W/840213 Ltr1984-02-13013 February 1984 Updated LER 83-177/03X-1:on 831029,1102 & 06,water Collected in Offgas Pretreatment Monitor,Resulting in Improper Flow Through Monitor.Caused by Accumulation of Condensation.Heat Tracing Installed on piping.W/840213 Ltr 05000416/LER-1983-128, Updated LER 83-128/01X-1:on 830912 During Routine Maint,Two fire-rated Penetrations Found Unsealed.Caused by Procedural Inadequacy.Penetrations Resealed1983-12-0606 December 1983 Updated LER 83-128/01X-1:on 830912 During Routine Maint,Two fire-rated Penetrations Found Unsealed.Caused by Procedural Inadequacy.Penetrations Resealed 05000416/LER-1983-115, Updated LER 83-115/03X-1:on 830803 & 04,RHR Pump a Failed to Start.Div I Busses Incorrectly Shown Tripped,Annunciator Panels Came On,Optical Isolator Failed & Breakers Tripped. Caused by Incorrectly Terminated Cable1983-11-0303 November 1983 Updated LER 83-115/03X-1:on 830803 & 04,RHR Pump a Failed to Start.Div I Busses Incorrectly Shown Tripped,Annunciator Panels Came On,Optical Isolator Failed & Breakers Tripped. Caused by Incorrectly Terminated Cable 05000416/LER-1983-011, Updated LER 83-011/99X-2:on 830103-24,fire-rated Barriers in Control & Auxiliary Bldgs Opened to Perform Planned Maint.Fire Watches Established.All Fire Barriers Restored1983-09-0808 September 1983 Updated LER 83-011/99X-2:on 830103-24,fire-rated Barriers in Control & Auxiliary Bldgs Opened to Perform Planned Maint.Fire Watches Established.All Fire Barriers Restored 05000416/LER-1983-021, Updated LER 83-021/01T-1:on 830519,determined That Standby Gas Treatment Sys Flow Monitoring Instrumentation Reading in Error.Caused by Incorrect Calibr Range Based on Postulated Instead of Std Conditions.Instruments Recalibr1983-07-18018 July 1983 Updated LER 83-021/01T-1:on 830519,determined That Standby Gas Treatment Sys Flow Monitoring Instrumentation Reading in Error.Caused by Incorrect Calibr Range Based on Postulated Instead of Std Conditions.Instruments Recalibr 05000416/LER-1982-172, Update 2 to LER 82-172/99X-2:on 821210,penetration AE154C in Auxiliary Bldg Opened.Caused by Planned Maint Activity. Hourly Fire Watch Established.Penetration to Be Resealed by 8309101983-07-12012 July 1983 Update 2 to LER 82-172/99X-2:on 821210,penetration AE154C in Auxiliary Bldg Opened.Caused by Planned Maint Activity. Hourly Fire Watch Established.Penetration to Be Resealed by 830910 05000416/LER-1982-180, Final LER 82-180/03L-0:on 821227,isolation Valve for Hose Station in Control Room Replaced Due to Leaking Which Pressurized Hose.Addl Hose Run to Supply Backup Fire Protection.Leaking Valve Replaced.Sys Returned to Svc1983-01-25025 January 1983 Final LER 82-180/03L-0:on 821227,isolation Valve for Hose Station in Control Room Replaced Due to Leaking Which Pressurized Hose.Addl Hose Run to Supply Backup Fire Protection.Leaking Valve Replaced.Sys Returned to Svc 05000416/LER-1982-132, /01T-0:on 830110 Discovered That Control Room Floor Penetration Open Since 821213.Caused by Performance of Planned Maint Work.Incident Noticed While Implementing Corrective Actions to LER 82-132/01T-01983-01-24024 January 1983 /01T-0:on 830110 Discovered That Control Room Floor Penetration Open Since 821213.Caused by Performance of Planned Maint Work.Incident Noticed While Implementing Corrective Actions to LER 82-132/01T-0 05000416/LER-1982-138, Interim LER 82-138/99X-0:on 821112,during Shutdown,Several Duct Covers Could Not Be Installed Due to Cables Extending Through Ducts.Caused by Faulty Design Document.Engineering Evaluation Underway1982-12-16016 December 1982 Interim LER 82-138/99X-0:on 821112,during Shutdown,Several Duct Covers Could Not Be Installed Due to Cables Extending Through Ducts.Caused by Faulty Design Document.Engineering Evaluation Underway 05000416/LER-1982-031, Interim LER 82-031/99X-1:on 820722,HVAC Penetration Seal CV-19G Found Not Installed During Insp.Caused by Const Oversight.Maint Work Order Released to Install Seal & Hourly Fire Watch Established Until Task Completed1982-12-15015 December 1982 Interim LER 82-031/99X-1:on 820722,HVAC Penetration Seal CV-19G Found Not Installed During Insp.Caused by Const Oversight.Maint Work Order Released to Install Seal & Hourly Fire Watch Established Until Task Completed 1993-08-26
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217F9921999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20212F5641999-09-23023 September 1999 SER Concluding That All of ampacity-related Concerns Have Been Resolved & Licensee Provided Adequate Technical Basis to Assure That All of Thermo-Lag Fire Barrier Encl Cables Operating within Acceptable Ampacity Limits ML20211Q3171999-09-0909 September 1999 Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20216E4881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Grand Gulf Nuclear Station.With ML20211A6921999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20209J1961999-07-12012 July 1999 Special Rept 99-001:on 990528,smoke Detectors Failed to Alarm During Performance of Routine Channel Functional Testing.Applicable TRM Interim Compensatory Measure of Establishing Roving Hourly Fire Patrol Was Implemented ML20196K4981999-07-0101 July 1999 Safety Evaluation Authorizing PRR-E12-01,PRR-E21-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01.Concludes That Alternatives Proposed by EOI Acceptable ML20209G0691999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20196A1161999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Grand Gulf Nuclear Station.With ML20206Q4831999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Grand Gulf Nuclear Station Unit 1.With ML20206J1201999-04-30030 April 1999 Redacted ME-98-001-00, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205P8771999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207K5141999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Grand Gulf Nuclear Station,Unit 1.With ML20206T7991999-01-31031 January 1999 Iodine Revolatizitation in Grand Gulf Loca ML20207A8301998-12-31031 December 1998 1998 Annual Operating Rept for Ggns,Unit 1 ML20206R9501998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20206D7721998-12-31031 December 1998 South Mississippi Electric Power Association 1998 Annual Rept ML20198E2481998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20195F4121998-11-13013 November 1998 Rev 16 to GGNS-TOP-1A, Operational QA Manual (Oqam) 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 ML20195C2791998-11-0505 November 1998 BWR Feedwater Nozzle Inservice Insp Summary Rept for GGNS, NUREG-0619-00006 ML20195F4801998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML20154K2391998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Grand Gulf Nuclear Station Unit 1.With ML20155F1961998-09-0101 September 1998 Engineering Rept for Evaluation of BWR CR Drive Mounting Flange Cap Screw ML20153B2161998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Grand Gulf Nuclear Station,Unit 1.With ML20237B6661998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Grand Gulf Nuclear Station,Unit 1 ML20236R0231998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Grand Gulf Nuclear Station,Unit 1 ML20155J0811998-05-31031 May 1998 10CFR50.59 SE for Period Jan 1997 - May 1998 ML20249B1251998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Grand Gulf Nuclear Station,Unit 1 ML20248B6261998-05-11011 May 1998 Rev 6 to Grand Gulf Nuclear Station COLR Safety-Related ML20217Q6701998-05-0606 May 1998 SER Approving Proposed Postponement of Beginning Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) at Grand Gulf for Circumferential Shell Welds for Two Operating Cycles ML20206J1271998-04-30030 April 1998 Pressure Locking Thrust Evaluation Methodology for Flexible Wedge Gate Valves ML20247F3591998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Grand Gulf Nuclear Plant,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) ML20217P0381998-04-0606 April 1998 Safety Evaluation Supporting Amend 135 to License NPF-29 ML20217A0291998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Grand Gulf Nuclear Sation,Unit 1 ML20216J4211998-03-18018 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Grand Gulf Nuclear Station ML20216J2021998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Grand Gulf Nuclear Station,Unit 1 ML20203A2891998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Grand Gulf Nuclear Station ML20247B4111997-12-31031 December 1997 1997 Annual Financial Rept for South Mississippi Electric Power Association ML20203H9741997-12-31031 December 1997 1997 Annual Operating Rept, for Ggns,Unit 1 ML20198P1121997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Grand Gulf Nuclear Station,Unit 1 ML20203B5581997-12-0404 December 1997 Special Rept 97-003:on 971111,valid Failure of Div 2 EDG Occurred,Due to Jacket Water Leak.Failure Reported,Per Plant Technical Requirements Manual Section 7.7.2.2 ML20203K4031997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Grand Gulf Nuclear 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 ML20199F3431997-11-18018 November 1997 SER Accepting Rev 15 of Operational Quality Assurance Manual for Grand Gulf Nuclear Station,Unit 1 1999-09-09
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C. R. Hutchinson August 12. 1993 ' ' " "
U.S. Nuclear Regulatory Commission Mail Station Pl-137 Washington, D.C. 20555 Attention: Document Control Desk
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Loss of Single Train Safety System Function LER C3-003-01 CNRO-93/00099 Gentlemen:
Attached is Licensee Event Report (LER) 93-003-01 which is a final report.
Yours truly,
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CRH/BAB attachment cc: Mr. R. H. Bernhard (w/a)
Mr.11. W. Reiser (w/a) l Mr. R. B. McGehee (w/a) l Mr. N. S. Reynolds (w/a)
Mr. H. L. Thomas (w/o)
Mr. Stewart D. Ebneter (w/a)
( Regional Administrator U.S. Nuclear Regulatory Commission l Reaion II 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30323 Mr. P. W. O'Connor, Project Manager 'w/a)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13113 Washington, D.C. 20555 ,
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- j@C F ORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO.3160 0104 ,
(se3 EXP1RES 5/31/95 ECTIMATED BURDEN PER RESPONSE TO COkPLY WITH THIS l LICENSEE EVENT REPORT (LER) EME" REGARDiNG#" YREN YSNAS 'T$NE l; INFORMATION AND RECORDS MANAGEMENT DRANCH (MNBB 7714L U S NUCLEAR REGULATORY COMMISSION. WASHINGTON. i DC 20ff$.0001, AND TO THE PAPERWORK REDUCTION PROJECT j (3%D.0104). OFFICE OF MANAGEMENT AND WDGET. {
WASHINGTON. DC 20503 j e ACUT y KAME (1) DOC #11 NuMDER (2) PAGE (3)
Grand Gulf Nuclear Station 05000-416 01 of 03 i TITLE {4)
LOSS of Single Train Safety System Function i EVENT DATE (6) LER NUMBER (6) REPORT NUMBER (7) OTHER F ACILITIES INVOLVED (8) 1 MONTH DAY YEAR YEAR SEQuLNf 6AL RE VI5 ION MONTH CAY YEAR F ACluTf fdME QQCriiNUMBER MBER NWBER N/A 05000 ;
F ACILIT Y NAME DOCriT NUMBER 03 24 93 93 003 01 08 12 93 N/A 05000 ,
OPERATANG THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR $ (Check one or more (11)
MODE '9) 1 20.402(b) 20 405(c) { 50.73(a)(2Hiv) 73.71(b) poi /LIR 20.405(a)(1)(i) 50.36(c)(1) 'X 50.73(a)(2)(v) 73.71(c)
LEVEL (10) 100 20 405(a)(1)(ii) 50 36(c)(2) 50.73(a)(2)(vn) OTHER l 20.405(a)(1)(in) 50.73(a)(2)(i) 50.73(a)(2)(viii)(A) g*,*gtf aa8
- l 20 405(a)(1)(iv) 50 73(a)(2)(si) 50.73(a)(2)(viii)(B) !
20 405(a)(1)(v) 50 73(a)(2)(in) 50 73(a)(2)(x) !
LICENSEE CONTAC COR THis LER (12)
NAW. TELDHONE NUMBER (inctuos Area Cooe)
Bruce A. Burke / Licensing Specialist 601-437-6333 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THis REPORT (13) i sysTEu c wcneNT Maur ACTuRER cAuse system cOMPoNun MmufACTuRtR R causE ugTgt 4 age t
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EXPECTED W TH DAY YEAR ;
SUPPLEMENTAL REPORT EXPECTED (14)
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DATE (15) ,
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a G anc' Gulf Nuclear Station (GGNS) Division ll1 standby service water (SSW C) system pump muor failed on March 5 4 1993. The failure occurred approximately five and one-half hours ;
into the weekly eight r T ' circulation run. SSW C provides cooling water for the high !
pressure core spray (: a iumo room coolers and Division 111 standby diesel generator. ;
j i !
The cause of the motor failure was investigated by the motor manufacturer. This investigation f determined that the motor stator end windings apparently were moving during motor start-ups. ;
The end winding movement likely caused a turn-to-turn electrical short which subsequently :
caused a phase-to-phase short in the motor wind;ngs. The motor had an estimated total run time of twenty-five hundred hours. 7ne suspected cause of the motor failure was initially reported as an apparent phase-to-phase or phase-to-ground short in the motor. The motor was ,
reconditioned by the manufacturer. An NPRDS report was submitted for the failed motor.
All safety related equipmer? operated as designed. Safety and health of the general public !
were not compromised tv "i event. !
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, Grand Gulf Nuclear Station 05000-416 93-003-01 2 OF 03 iu r r m.u . wow co, a wc wm mwm A. REPORTABLE OCCURRENCE Grand Gulf Nuclear Station (GGNS) Diviston ill standby service water (SSW C) system [Bl]
pump motor failed on March 24,1993. SSW C provides cooling water for the high pressure core spray (HPCS) system [BG) pump room coolers and Division 111 standby diesel generator cooling system [LB]. This event is reportable per 10 CFR 50.73(a)(2)(v)(A).
B. INITIAL CONDITIONS The plant was in Operational Condition 1 at approximately 100 percent power with reactor water at approximately 530 degrees F and 1027 psig. The weekly SSW C recirculation run was in progress for approximately five and one-half hours when the failure occurred.
C. DESCRIPTION C: OCCURRENCE While performing the weekly recirculation run of SSW C on March 24,1993, the SSW C pump tripped at 0512 hours0.00593 days <br />0.142 hours <br />8.465608e-4 weeks <br />1.94816e-4 months <br /> due to a pump motor failure. The weekly recirculation run is for corrosion protection and microbiological protection of the open recirculating system SSW C loop; chemical additions are made as part of the recirculation run. This motor failure resulted in declaring SSW C and HPCS inoperable.
D. APPARENT CAUSES The 100 horsepower,1,800 rpm three phase motor smelled of burned wiring /insulEtion upon failure. The motor and pump rotated freely following failure, thereby eliminating a fa' led pump or motor bee as causing the motor failure. It was initially suspected that an electrical sh9rt occurred in the motor, either phase-to-phase or phase-to-ground.
The cause of the motor failure was investigated by the motor manufacturer. This investigation determined that the motor stator end windings apparently were moving during motor start-ups.
The end winding movement likely caused a turn-to-turn electrical short which subsequently caused a phase-to-phase short in he motor windings.
Periodic vibration monitoring ensured that the pump-to-motor coupling was aligned. A vibration test had been performed satisfactorily one week prior to the motor failure.
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. ESTMATED BURDEN PER RESPONSE TO COMPLY WrfH THIS LICENSEE EVENT REPORT (LER) cou$EN" REARE
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Grand Gulf Nuclear Station 05000-416 93-003-01 3 OF 03 .
TLKT (W mtre spece se requeed use ea$honel copes of AIRC F9m 306A) 0 7)
The existing operating instruction procedure for this pump limits starts to two successive starts ,
from ambient temperature or one start from operating temperature. Subsequent starts may be' I made after thirty minutes of operation or sixty minutes c' being id!e. These controls comply with l vendor recommendations.
The motor had been in service since commercial operation of GGNS. The weekly eight hour I recirculation run was commenced in mid-1990. The motor had an estimated total run time of approximately twenty-five hundred hours.
E. CORRECTIVE ACTION l Immediate corrective actions included performing the action statement specified in GGNS i Technical Specifications 3.5.1,3.7.1.2, and 3.8.1.1. The SSW C pump motor was replaced with
- a spare unit and retested satisfactorily. Operability of SSW C and HPCS was restored at 2245 i hours on March 24,1993. The failed motor was refurbished by the manufacturer (General ;
Electric) and is being receipt-inspected for return to spare parts inventory. A report was I submitted to the Nuclear Plant Reliability Data System for the motor failure. i F. SAFETY ASSESSMENT !
l l
SSW water carries heat to the SSW cooling towers, the ultimate heat sink ( wm [BS] at GGNS )
for removal of decay hect generated by the reactor core. Divisions I and ll SSW provide cooling water for a variety of auxiliary systems, three common major toads being the respective train of residual heat removal (RHR) system [BO), standby diesel generator cooling system [LB],
and fuel poo' cooling system [DA). Division til SSW is for HPCS support systems (i.e., Division 111 standby diesel generator cooling system and the HPCS pump room coolers). Divisions I and !
111 share the same cooling tower, but each division has its own pump. l HPCS is a single train system without any recognized redundancy However, HPCS is backed up by multiple trains of low pressure emergency core cooling systems and the automatic depressurization system. Additionally, high pressure makeup was available from the reactor core isolation cooling (RCIC) system [BN] The out-of-service time was maintained within the limits of GGNS technical specifications, thereby minimizing any safety significance of this event.
Safety and health of the general public were not compromised by this event. !
G. ADDITIONAL INFORMATION Energy Industry identification System (Ells) codes are identified in the text within brackets [].
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