|
---|
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
[Table view] |
LER-2083-115, 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 Cable |
Event date: |
|
---|
Report date: |
|
---|
4162083115R00 - NRC Website |
|
text
voc romae us Update Report - Previous Report Date 9/2/83 u.s amare = Am aseutavosnr coansessecas LICENSEE EVENT hEPORT Attachment to AECM-83/0718 Page 1 of 3 cossTaotst.ocK: l. pLaans reserf on Type ALL moeuseeB IIIPOAAAATIOSH l l l @
- olti8i 9hi s UCENSEE 7
l el e COog l si l.J@l 4 is o I ol- 10101 L m same olo A ol-Iolo @5411111111 E$ L M Tv95 3i
@lafCATSl@
I CON'T M
i 8
,on M[Si,0l 51Ol 01Ol 411l 6@S0181013 DOEaLET emmegn G WW com l Bl 3 34@l175 l 11O ngPonTl oATE318 l 3l@ 88 EVE 9tT DEScAIPTHps Age Pensame s rvimimaamimmerse Q o (/3n interconnection between Div. I 120VAC & 125VDC circuits was dis- 1 o leavered on 8/4/83 which cauced the f ollowing on 8/3 & 4/83 - RHR A pump i ..
o 4 jfailod to start, all Div. I busses were incorrectly shown to be tripped j o s Iby annunciators, numerous annunciators on the Div. I C/R panels came on,l RITE i tan optical isolator in the RHR A logic circuits failed, and breaker 1 o 7 [5,2-15501 tripped. This event did not effect the health and safety of thel loublic nor did it threaten plant safety. This is a final report. I o
so 7 ee CoOE SU CODE ComposesT C04E amenns T9 i ElC lh W@ [E,[h l ElL o l ElC 1 Oj N.h 8 Wi Z l@ Z
. . i. is i2 EV988TYEAA set. CoM 18 1 3l l-n -J lill t sj W l 01 3 i x t' O ,"t3mfmo;',oa,;L.n a = = 21 a s, i 3 f A obMT E wouns h ^ b Y pones ws. ' sky naam Nnen l*
u M W @ % 1 3,
I I I I p@ @@ @@ l
- I ' l' l ',1G cAust DescmerTicas Asso connective ACTION 6 @
' @ lA Div. I 125VDC computer cable was incorrectly terminated on the 120 VACl
@ ID/W Recire. Fan A control circuit. This inserted 120VAC onto the Div. I l t
1125 VDC system. The cable was installed during a recent D/W ventilation l g l modification. The cable was disconnected to remove the AC voltage f rom l l
i 4 lthe DC circuits. This is reported pursuant to T.S.6.9.1.13.b. l
' STEN"ss sPowen oTwensTATus h oEn$ oesCovanyossCnierion h i s W@ l 01010 #
$" M l @ Operator Ooservation l
I
- AETiveTV CoErs=Y cetsAseo or asLamas LoCATioNornatsAseh l
i e [ z j @ [,r jglM AnnouwTor ACTrvrry lM hl i v . . i. is . .
PEnSommet Emm
! NuadSSn TYPE DESCalPTiON i i 10101Ol@Lr_j@iM i as 7 s s is is l
Nuusen oesourricah G311170413 831103 PDR ADOCK 05000416 l l
i ln l l 0 l 0 l 0 lh M i~ se is in S PDR ,,
1 9
'T E 9 Es*CYd M E " " " h M
Q l i .s ,.
NRC USE ON -
,,,y ,
Pusu
,h ,
i a o M l I,j ,l l 1 1 l l l l l l 15
, i . e se se se so ;
NAnsE oF PREPARER PHONE:
. _, -- - - - - - - . _- _ _ _ _ _ _ _ _ _ _ _ 1
r Attachment to AECM-83/0718 Page 2 of 3 Supplementary Information to LER 83-115/03 X-1 Mississippi Power & Light Company Grand Gulf Nuclear Station - Unit 1 Docket No. 50-416 Technical Specification Involved: 3.4.9.2; 3.5.2; 3.8.3.2; 3.7.1.1; 3.7.1.3 Reported Under Technical Specification: 6.9.1.13.b Ever.t Narrative On May 27, 1983, a computer cable which provides a signal to the computer when an automatic start of the Drywell Recirculation Fan Unit "A" occurs was incorrectly terminated during a drywell ventilation modification which added the recirculation fan to the system. The cable should have been terminated across a set of isolated relay contacts but was instead incorrectly terminated across the overload (0.L.) device (49) in the 120VAC control circuit for Recirculation Fan Unit "A" in MCC15B42. The power for the computer cable is supplied from 1DA1 125VDC bus thru isolation panel 1H22-P501-1.
The breaker to the recirculation fan was not closed until August 3,1983. It was closed to perform preoperational testing. Therefore, no electrical interconnection between AC and DC existed prior to this date. When the breaker was closed, no adverse effects occurred because the 0.L. device 49 was closed, therefore, no AC voltage flowed into the DC circuits. A ground on the DC did exist thru the fan control circuit and had been previously noted and searched for preceding this event.
As part of the preoperational testing, 0.L. device 49 and the penetration cabinet failure relay 8 contact were opened and closed on the evening of August 3,1983, and the morning of August 4,1983. The opening and closing of these contacts inserted and then removed the 120VAC on the 125VDC bus. This resulted in numerous effects which collectively were:
- 1) A failed optical isolator output card in the RHR "A" pump trip circuit which cauced a continuous pump trip
- 2) A continuous trip to a Standby Service Water System load center breaker, and
- 3) Numerous annunciators on the Division I Control Room panel which incorrectly alarmed.
An investigation discovered the computer cable was incorrectly terminated in MCC15B42. The cable was disconnected. The root cause was construction personnel error.
A program has been initiated to eliminate future construction errors through closer supervision of work activities, training, improved inspections, and clearer work instructions.
MP&L's past experience with the effects and consequences of AC voltage imposed onto a DC voltage circuit was unintentionally gained during several instances in the preoperational phase of startup. These occurred as a result of similar
0
. Attachm:nt to AECM-83/0718 Page 2 of 3 wiring errors by construction and design. It is known that 120VAC on the 125 VDC logic and control circuits will not generally damage wiring, relay coils, contacts, and most instruments if the voltage is not excessive. It can be expected to damage optical isolator output cards and other solid state devices.
Which components are damaged depends on the logic arrangement of the associated circuits during the time the AC is present. Although it will not damage non-solid state devices, it can affect their operation, such as, a relay may not deenergize with AC.present.
The E12-AT7 optical. isolator output card in the RHR pump trip logic circuit was damaged as a result of the AC voltage during the referenced event. AT7 and E12-AT8 are the only two isolators connected directly to the Division I 125VDC b'us. 'AT8 was not damaged because the output card is in parallel with other relay contacts that were closed. The relay contacts parallel with AT7 were open, therefore, the AC current flowed through the output side of AT7 and destroyed the output transistors. .An optical isolator such as AT7 would be expected to fail if AC voltage is present. The isolator output card was manufactured by General Electric. The model number is 204B6188AAG2 and the serial number is TWRE5-17.
The ESF 480V Standby Service Water load center breaker 52-15501 gave dual indication during the time the AC voltage was present on the DC bus and then tripped. The breaker control circuits receive power from the Division I 125VDC bus. The breaker is equipped with a solid state trip device. The presence of AC voltage apparently caused a trip signal from the solid state trip device but no damage to the device was discovered.
MP&L made the decision not to perform an extensive special inspection and test of other components within or affected by the 125VDC Division I system because:
- 1) past experience has shown low AC voltage (less than or equal to 120VAC) does not damage non-solid state devices,
- 2) the 18 month surveillances on the effected circuits and components were expected to be performed within the next 30 days including the 18 month diesel generator LOCA/ LOP tests,
- 3) the time required to develop, approve, and perform such a test vauld take longer than the time in which the surveillances would be completed,
- 4) the solid state trip devices in all of the safety related breakers were scheduled to be inspected, tested and possibly replaced due to an unrelated potential failure reported in LER 83-119/03 L-0,
- 5) daily channel checks and monthly functionals would be adequate to uncover any other damage.
To date no additional damage that can be attributed to the presence of the AC voltage on the Division I 125VDC bus has been discovered either by corrective maintenance or surveillance. All solid state breaker trip devices in Division I have been inspected and tested and no damage was found.
This is reported pursuant to Technical Specification 6.9.1.13.b. This event did not effect the health and safety of the public. It did not threaten plant safety because the effects were limited to Division I with the plant in a Cold Shitdown condition. This is a final report.
l E MISSISSIPPI POWER & LIGHT COMPANY I Helping Build Mississippi P. O. B O X 18 4 0() gK S O N, MIS SIS SIP PI 3 9 20 5 g gPg e er 3, 1983 NUCLEAR PRODUCTION DEPARTMENT U.S. Nuclear Regulatory Commission Region II 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30303 Attention: Mr. J. P. O'Reilly, Regional Administrator
Dear Mr. O'Reilly:
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-13 File: 0260/L-835.0 Update Report - Incorrect Voltage Applied to Division I Control Circuits LER 83-115/03 X-1 AECM-83/0718 This letter submits an update to a previous report submitted on September 2, 1983. The event for which the report was submitted occurred on August 3 and 4, 1983, when an interconnection between the Division I 120VAC and Division I 125VDC circuits caused the insertion of 120VAC onto the Division I 125VDC system. The interconnection was a result of a wiring error made on May 27, 1983, during a drywell ventilation modification which added a drywell recirculation fan to the system. The breaker to the recirculation fan was not closed until August 3, 1983, therefore, no problems evolved from the wiring error or could the wiring error be detected until that date. The breaker was closed to allow performance of preoperational testing and during the course of this testing AC voltage was inserted onto the 125VDC system causing several alarms, trips and component failures.
The purpose of this update is to provide results of an engineering evaluation performed as a result of this event, a detailed account of the event, and the corrective action taken. Also, correction is provided for the previous report where we incorrectly stated that a 120VAC computer cable was incorrectly terminated on a Division I 125VDC circuit in MCC15B42. This is a final report. Attached is LER 83-115/03 X-1 with Supplementary Information.
Yours truly,
/bN L. F. Dale Manager of Nuclear Services EBS/SHH:rg gp,CIAldb Attachment cc: See next page [Mh Member Middle South Utilities System fg L
1
. AECM-83/0718 MISSISSIPPI POWER O L12HT COMPANY Jags 2 cc: Mr. J. B.' Richard (w/a)
Mr. R. B. McGehee (w/o)
~Mr. T. B. Conner (w/o)
Mr. G. B. Taylor (w/o)
Mr. Richard'C. DeYoung, Director (w/a) l Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Document Control Desk (w/a)
U. S._ Nuclear Regulatory Commission Washington, D. C. 20555 i
i n
l.
l
\
!
|
---|
|
|
| | Reporting criterion |
---|
05000416/LER-1983-001, Forwards LER 83-001/01T-0 | Forwards LER 83-001/01T-0 | | 05000416/LER-1983-002, Forwards LER 83-002/01T-0 | Forwards LER 83-002/01T-0 | | 05000416/LER-1983-003, Forwards LER 83-003/01T-0 | Forwards LER 83-003/01T-0 | | 05000416/LER-1983-004, Forwards LER 83-004/01T-0 | Forwards LER 83-004/01T-0 | | 05000416/LER-1983-005, Forwards LER 83-005/03L-0 | Forwards LER 83-005/03L-0 | | 05000416/LER-1983-006, Forwards LER 83-006/03L-0 | Forwards LER 83-006/03L-0 | | 05000416/LER-1983-007, Forwards LER 83-007/03L-0 | Forwards LER 83-007/03L-0 | | 05000416/LER-1983-008, Forwards LER 83-008/99X-0 | Forwards LER 83-008/99X-0 | | 05000416/LER-1983-009, Forwards LER 83-009/03L-0 | Forwards LER 83-009/03L-0 | | 05000416/LER-1983-010, Forwards LER 83-010/99X-0 | Forwards LER 83-010/99X-0 | | 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 Restored | 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-1983-012, Forwards LER 83-012/03L-0 | Forwards LER 83-012/03L-0 | | 05000416/LER-1983-013, Forwards LER 83-013/99X-0 | Forwards LER 83-013/99X-0 | | 05000416/LER-1983-014, Forwards LER 83-014/03L-0 | Forwards LER 83-014/03L-0 | | 05000416/LER-1983-015, Forwards LER 83-015/03L-0 | Forwards LER 83-015/03L-0 | | 05000416/LER-1983-016, Forwards LER 83-016/03L-0 | Forwards LER 83-016/03L-0 | | 05000416/LER-1983-017, Forwards LER 83-017/03L-0 | Forwards LER 83-017/03L-0 | | 05000416/LER-1983-018, Forwards LER 83-018/99X-0 | Forwards LER 83-018/99X-0 | | 05000416/LER-1983-020, Forwards LER 83-020/03L-0 | Forwards LER 83-020/03L-0 | | 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 Recalibr | 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-1983-022, Forwards LER 83-022/03L-0 | Forwards LER 83-022/03L-0 | | 05000416/LER-1983-023, Forwards LER 83-023/03L-0 | Forwards LER 83-023/03L-0 | | 05000416/LER-1983-024, Forwards LER 83-024/03L-0 | Forwards LER 83-024/03L-0 | | 05000416/LER-1983-025, Forwards LER 83-025/03L-0 | Forwards LER 83-025/03L-0 | | 05000416/LER-1983-026, Forwards LER 83-026/03L-0 | Forwards LER 83-026/03L-0 | | 05000416/LER-1983-027, Forwards LER 83-027/99X-0 | Forwards LER 83-027/99X-0 | | 05000416/LER-1983-028, Forwards LER 83-028/03L-0 | Forwards LER 83-028/03L-0 | | 05000416/LER-1983-029, Forwards LER 83-029/03L-0 | Forwards LER 83-029/03L-0 | | 05000416/LER-1983-030, Forwards LER 83-030/99X-0 | Forwards LER 83-030/99X-0 | | 05000416/LER-1983-031, Forwards LER 83-031/99X-0 | Forwards LER 83-031/99X-0 | | 05000416/LER-1983-032, Forwards LER 83-032/03L-0 | Forwards LER 83-032/03L-0 | | 05000416/LER-1983-033, Forwards LER 83-033/99X-0 | Forwards LER 83-033/99X-0 | | 05000416/LER-1983-034, Forwards LER 83-034/03L-0 | Forwards LER 83-034/03L-0 | | 05000416/LER-1983-035, Forwards LER 83-035/01T-0 | Forwards LER 83-035/01T-0 | | 05000416/LER-1983-036, Forwards LER 83-036/03L-0 | Forwards LER 83-036/03L-0 | | 05000416/LER-1983-037, Forwards LER 83-037/03L-0 | Forwards LER 83-037/03L-0 | | 05000416/LER-1983-038, Forwards LER 83-038/03L-0 | Forwards LER 83-038/03L-0 | | 05000416/LER-1983-039, Forwards LER 83-039/99X-0 | Forwards LER 83-039/99X-0 | | 05000416/LER-1983-040, Forwards LER 83-040/03L-0 | Forwards LER 83-040/03L-0 | | 05000416/LER-1983-041, Forwards LER 83-041/03L-0 | Forwards LER 83-041/03L-0 | | 05000416/LER-1983-042, Forwards LER 83-042/99X-0 | Forwards LER 83-042/99X-0 | | 05000416/LER-1983-043, Forwards LER 83-043/03L-0 | Forwards LER 83-043/03L-0 | | 05000416/LER-1983-044, Forwards LER 83-044/99X-0 | Forwards LER 83-044/99X-0 | | 05000416/LER-1983-045, Forwards LER 83-045/99X-0 | Forwards LER 83-045/99X-0 | | 05000416/LER-1983-047, Forwards LER 83-047/03L-0 | Forwards LER 83-047/03L-0 | | 05000416/LER-1983-050, Forwards LER 83-050/03L-0 | Forwards LER 83-050/03L-0 | | 05000416/LER-1983-051, Forwards LER 83-051/03L-0 | Forwards LER 83-051/03L-0 | | 05000416/LER-1983-053, Forwards LER 83-053/99X-0 | Forwards LER 83-053/99X-0 | | 05000416/LER-1983-054, Forwards LER 83-054/03L-0 | Forwards LER 83-054/03L-0 | | 05000416/LER-1983-055, Forwards LER 83-055/03L-0 | Forwards LER 83-055/03L-0 | |
|