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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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LER-2084-050, 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 Initiated |
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]vostre, ameTresomasse=asTri T] no l l e i AcT ru s e.m a..a . an - m.w no on October 15, 1984, during a special review, certain Unit 1 safe-shutdown j related cable raceways were found with omitted fire rated barriers. Although '
these fire barriers were required by 10 CFR 50 Appendix R and the plant FSAR, they were not included in construction documents. Two areas contair.ing these cable raceways were located on the Unit 2 side of the Control Building where the fire detection system had not been under surveillance. Due to the uncertainty of.the location of these raceways, fire watches in Unit 2 had not been established in a timely manner.
Subsequently, as a result of the continuing special review relative to Appendix R. additional Unit I safe-shutdown related cables were identified on December 12, 1984, as not being in compliance with Appendix R requirements.
Also, other Appendix R discrepancies were identified on May 17 and 18, 1985. A one hour fire wrap required to be installed along certain raceways was found i broken at various supports. One raceway in the Division I Switch Gear Room was found without a one hour fire barrier installed. Nonconformance documents were written for correction of the deficiencies. Fire watches will be maintained until fire protection is installed.
On July 12 1985, additional Appendix R discrepancies were identified. Three E77 system safe shutdown cables were found to have been routed through fire
( sones without the required 3-hour fire wrap. Nonconformance documents were initiated to correct the deficiencies and fire watches will be maintained as required.
8509060083 850815 PDR g
ADOCK 05000416 PDR 4[7q-g 1 j
J13AECM85080901 - 3
Attcchment to AECM-85/0249
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u, ucua. ...utivo., ca LICENSEE EVENT REPORT ILER) TEXT CONTINUATION areaoveo o.e no mes-eie.
_ sme es amas 8ACILITV ABAAIS Ill eOCaET ERJtWG. Of Las espese em .nes 13
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Grand Gulf Nuclear Station - Unit 1 o ls jo jo je j 4l1l6 8 l4 -
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013 0 l2 0F 0 l3 varTn . m .an== =ses .uwnn This is an update to a previous revision submitted June 17, 1985. Changes to the previous report are indicated by a bar in the right hand margin.
On October 15, 1984, during an ongoing Fire Protection System review relative to 10 CFR 50 Appendix R requirements, the design engineering group identified certain Unit 1 safe-shutdown related cable raceways with omitted fire barriers. A Material Nonconformance Report (MNCR) was initiated by engineering and reviewed by the Operations Shif t Superintendent for effects on operation. At 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on October 15, a Limiting Condition for Operation (LCO) report was written to track the hourly fire watch required by Technical Specification 3.7.7. Further information was later required to determine reportability under 10 CFR 50.73. On November 2, 1984, it was determined that this condition was outside the design basis of the plant and it was reported accordingly.
The affected safe-shutdown related cables were those of redundant trains unprotected by fire barriers. This condition is not in accordance with Appendix R requirements. Systems affected were: The Standby Service Water System (SSW), the SSW remote shutdown flow recorder, a Residual Heat Removal
- I (RHR) jockey pump, the Standby Diesel Generator fuel oil transfer' pump, the
' Reactor Core Isolation Cooling System, SSW pump house ventilation, Safeguard Switchgear and Battery Room ventilation, ECCS pump room ventilation, and power feeders or control cables to ESF load centers.
After conferring with Engineering, on November 7, 1984, Operations discovered.
that two of the areas containing the subject cables were located on the Unit 2 side of the Control Building. It was later determined that the cables in one of the two areas met Appendix R requirerants. The fire detection equipment in the Unit 2 areas had not been under surveillance since Technical Specifications did not address these. Also, no fire watches had been established in these areas. Operations, when reviewing the MNCR on October 15, had assumed the cables were located in Unit 1. Fire watches in the Unit 1 Auxiliary and Control Buildings were already in offact due to the nonconforming fire doors reported in Special Report 84-012/2, AECM-84/0478.
Continuous fire watches were established in the Unit 2 areas after discovery of the conditioc. Design Change documents have been initiated to install the required fire barriers.
An engineering investigation revealed four more areas in Unit 2 which contained Unit I safety related components. However, these components were not safe-shutdown cables. The fire detectors in the areas were successfully tested on November 12 and 13, 1984. The fire detectors are being administrative 1y controlled as Technical Specification required instruments until a revised Technical Specification is issued.
J13AECM85080901 - 4 es e _ __. _ _ _ _ _ __ _ _ _ _ ___ _ _ _ __ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ .
Attachasnt to AECM-85/0249 3
==c a men vs. ue6 n ne.vutone -
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION w aoveo ono mo.s,s w ee
_ eneines ames aaciurv mass m ooc ev muneen e, un ma em seas ei vaan ;880d j(84 ij Gr nd Gulf Nuclear Station - Unit 1 o ls j o j o l s l 4 l 1l 6 8 l4 -
015 b -
013 013 0F 0 13 4 vert er- . w.c m me % menw nn 1
In sunsnary, a total of six ateas containing Unit 1 safety related equipment I l
were found located on the Unit 2 side of the Control Building. The fire detection equipment in the Unit 2 areas had not been un' der surveillance. One of the six areas contained safe-shutdown cable raceways with omitted fire barriers.
As a result of the continuing special review relative to Appendix R.
additional Unit I safe-shutdown related cables were identified on December 12, 1984, as not being in compliance with Appendix R requirements. These additional discrepancies were limited to Unit 1. Appropriate nonconformance l
docusedts were initiated and the appropriate Technical Specification actions were carried out. Systems affected by these deficiencies were Containment and Drywell Instrumentation, Emergency Switchgear and Battery Room Ventilation, the Standby Diesel Generators and Residual Heat Removal.
Other Appendix R discrepancies were identified on May 17 and 18, 1985. A one hour fire wrap required to be installed along certain raceways was found broken at various supports. The wrap was installed on either side of the supports but did not always include the portions where support members made contact with the M L raceways. Also, one raceway in the Division I Switchgear Room tras found without a one hour fire barrier installed. Nonconfermance documents were written for correction of the deficiencies. Fire watches will be maintained until the appropriate fire protection is installed.
i On July 12, 1985 Nuclear Plant Engineericg identified additional Appendix R dicerepancies which were subsequently determined reportable on July 17, 1985.
Three 277 system safe shutdown cables were found to have been routed through .
fire sones without the required 3-hour fire wrap. Nonconformance documents l I
were initiated to correct the deficiencies and fire watches will be maintained as required. This is submitted as a final report. ,
4 2
J13AECM85080901 - 5
{ _ _ . _ ,_ _
j MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi 'n a ?3 n 9 ,* f Q 56hihMIMil P. O. B OX 164 0, J AC K S O N, MIS SIS SIP PI 39215-1840 August' 15, 1985 tuCLE AR LICENSING & &AP ETY DEPARTMENT CORRECTED COPY Document Control Desk LER number should be U. S. Nuclear Regulatory Comunission 84-050-3 rather than Washington, D. C. 20555 85-050-3.
Gentlemen:
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 File: 0260/L-835.0 Fire Barriers Omitted From Safe-Shutdown Related Cables LER 84-050-3 AECM-85/0249 Attached is Licenset. Event Report (LER) 84-050-3 which is a final report.
r- Yours truly, L. F. Dale Director
. RM/EBS/SHH:vog i Attachment ec: Mr. J. B. Richard (w/a)
Mr. O. D. Kingsley, Jr. (w/a)
Mr. R. B. McGehee (w/a)
Mr. N. S. Reynolds (w/a)
Mr. C. B. Taylor (w/o)
Mr. R. C. Butcher (w/a)
Mr. James M. Taylor, Director (w/a)
Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 ,
.Dr. J. Nelson Graces Regional Administrator (w/a)
U. S. Nuclear Regulatory Conunission Region Il a a rgia b33
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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 Transients | 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-1984-005, 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 Review | 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-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 Restored | 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-1984-020, Revised LER 84-020-01:on 840423,24 & 0514,during Startup, Five Reactor Water Cleanup Sys Isolations Occurred Due to Feedwater Flow Oscillations | 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-1984-031, Forwards LER 84-031-01 & Rept on Investigation Performed to Determine Unit 1 Dependence on Unit 2 Sys,Structures & Components | Forwards LER 84-031-01 & Rept on Investigation Performed to Determine Unit 1 Dependence on Unit 2 Sys,Structures & Components | | 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 Initiated | 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 | |
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