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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-2083-126, 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 Ltr |
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EveerY DesenrTiose Asso Penmaan a conoscusNCES h TTTU lOn 9-4-83 af ter approximately 8.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> of maintenance operation. a Div.1 o II D/G f uel line' ruptured resultino in a fire near the left bank turbo _j g l charger. The engine was secured and an unusual event was declared f C
- o[sil1447 hours to 1559 hours0.018 days <br />0.433 hours <br />0.00258 weeks <br />5.931995e-4 months <br />. Person (s) responding to the fire noted thai __,_j F5'Ts1 Ithe fire protection deluce valve f ailed to omen. The valve was forced i Q lopen by a mechanic. The fire was reported out amoroximatelv 25 minutna I
[oisilafter starting. This is reported pursuant to T.S.6.9.1.12.1.
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CAdSE DESCRiFTION assOCORRECTIVE ACTIONS h g g (The fuel line failure was due to fatique crack propacation. The cause l g] lof the deluge valve failure was due to rough matino surfaces of the I
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Attachment to l AECM-84/0137 Page 2 of'6 SUPPLEMENTARY INFORMATION TO LER 83-126/01 X-3 Mississippi Power & Light Company Grand Galf Nuclear Station - Unit 1 Docket No. 50-416 Technical Specification Involved: N/A Reported Under Technical Specification: 6.9.1.12.1 Event Narrative:
On September 4, 1983, at 0610 hours0.00706 days <br />0.169 hours <br />0.00101 weeks <br />2.32105e-4 months <br />, Diesel Generator 11 was started for maintenance operation. The engine was manually stopped at 1436 hours0.0166 days <br />0.399 hours <br />0.00237 weeks <br />5.46398e-4 months <br /> and the outside fresh air fans were secured when a fire was reported at the engine.
Approximately 8 personnel were inside the room when the fire occurred. The i room was evacuated and the fire brigade was assembled. The fire brigade responded to the scene with water hoses and necessary equipment. It was noted that the automatic fire water deluge valve had not opened. The manual release was pulled to no avail. A mechanic was able to open the valve by removing the actuator enclosure box cover and striking the top of the weight. The fire was reported to be extinguished at 1501 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.711305e-4 months <br />. An unusual event was declared and
- remained in effect from 1447 hours0.0167 days <br />0.402 hours <br />0.00239 weeks <br />5.505835e-4 months <br /> until 1559 hours0.018 days <br />0.433 hours <br />0.00258 weeks <br />5.931995e-4 months <br />. The diesel failure is considered invalid in accordance with Regulatory Position C.2.e(3) of Regulatory Guide 1.108.
I. Diesel Generator Fuel Oil Line Failure A. Diesel Generator Investigation:
The initial inspection of the diesel engine revealed that the main fuel supply tubing which delivers fuel oil from the Engine Driven Fuel Oil Booster Pump to the left and right bank fuel headers had separated at a tee connection. The separation resulted in fuel oil spraying on a hot exhaust manifold entering the left bank turbo-charger and igniting. The fuel oil flow continued to feed the fire until the engine reached a complete stop. The separation was caused by a crack in the tubing that occurred at the ferrule of the fitting used to connect the tubing to the header tee.
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i A metallurgical evaluation of the failed tubing indicates that the-failure resulted from very high cycle fatigue.- The high cycle fatigue resulted because a vendor supplied tubing support, immedi-ately downstream of the fitting, was not installed.
Representatives from Middle South Services and MP&L Plant Staff performed a thorough examination of the area affected by the fire to
- delineate the fire affected areas. The examination revealed three
[ fire affected areas.
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- 1. Under the left bank turbocharger, l
- 2. The top of the lube oil tank under the lef t bank turbocharger, and
- 3. Under the lube oil cooler, approximately in the middle of the l cooler.
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Attachlant to !
AECM-84/0137 l Page 3 of 6 The metal parts of the engine and pressure vessel exposed to the highest heat were visually examined. No areas of discolored metal, indicating excessive heat. were found. Based on this findins, it was determined that the pressure vessels and engine parts exposed to the highest heat were acceptable for further service. The engine and skid mounted equipment located in the fire areas received varying amounts -
of damage, depending on the amount of exposure to heat, smoke, and water. The wiring, instruments.and tubing located on the front of the engine also experienced heat, smoke, and water damage in varying amounts.
B. Action Taken:
! A support. bracket was added to the Division 1 and 2 Diesel Generator
- fuel oil headers. Components which were located in the fire area j were replaced since the ability to carry out their design function
, was in question. Other components which may have been subjected to heat or water damage were inspected and either replaced or reworked, l depending on the as found condition. Any item whose condition could i not be accurately evaluated was replaced. Maintenance Work Orders were generated to perform all work or replacement of the diesel generator equipment. Appendix "A" to this report lists the items i which were replaced. When rework or replacement of the affected i items was completed, the diesel generator was subjected to a maintenance run to' verify all components were functioning normally.
! After all work had been completed, the diesel generator was subjected
~
to a " maintenance" run. This type of engine operation allowed
, monitoring of engine operating parameters at different power levels,
! and uncovered items which warranted further attention. During the j maintenancc run, the engine was instrumented for. vibratory. analysis.
i The preliminary results of the vibratory analysis revealed that the l engine exhibited vibrations that were well within'the acceptable
! limits for this type of machinery, therefore. no additional vibration i related failures are anticipated.
i f After the successful completion of the maintenance run, the unit was;.
} turned ~over to Operations for operational testing. 1 Following the
- operational retesting,'the unit successfully completed a seven day;
- reliability run. ,
i II. Deluge Valve Failure o A. Deluge Valve Investigation:
t-The failed fire. water deluge valve was a 6 inch Model C, serial
- ' number S10774, manufactured by~ Automatic Sprinkler Corporation of America. -Although a trip signal was received from the local control
- . panel, the valve failed to open.
- The valve and'the release mechanism' ,
i' were tested'and componentsjwere removed and examined. No significant l abnormal ~ conditions were noted. Some excessive friction was noted between the weight and weight guide rod, however, the valve operated
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- ' properly during subsequent testing.
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, Attachment to I
AECM-84/0137 l
Page 4 of 6 Automatic Sprinkler Corporation of America (ASCOA) conducted laboratory tests on a six inch Model C deluge valve and produced a similar failure which was attributed to poor surface finish on the mating surfaces between the clapper nose and latch. Once the mating surfaces were smoothed with 220 grit sandpaper and crocus cloth, a major improvement in the valves' performance was noted.
On December 5, 1983, deluge valve N1P64F77U, which protects Diesel Generator 12, failed to open during performance of a scheduled test.
The valve was inspected and exceptional roughness found on the faces was sanded and refinished until smooth in accordance with ASC0A's recommendations. The valve was then reassembled and tested satisfactorily under normal operating pressure.
Based upon further investigation and research data, it is concluded that the failutes of September 4 and December 5 were due to the condition of the mating surfaces between the clapper nose and latch.
B. Corrective Actions Taken:
- 1. The Model C deluge valves protecting the three emergency diesel generators were corrected using crocus cloth and sandpaper per ASC0A's recommendations. The valves were tested under operating pressure and were found to trip with much more sensitivity.
- 2. All other Model C deluge valves were refinished and tested satisfactorily under normal operating pressure.
- 3. The surveillance procedure was revised to visually verify that the clapper has lif ted and locked open following the test under normal system pressure.
- 4. The testing frequency for Division 1, 2 and 3 Diesel Generator Room deluge valves has been temporarily increased to establish reliability data.
- 5. ASC0A revised their technical information bulletins to address the condition of the mating surfaces and to ensure functional tests are performed with pressure on the clapper.
This is submitted as a final report on the Diesel Generator fuel line failure and on the deluge valve failure. The fuel line failure was also reported,under 10 CFR 21 as PRD 83/17.
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APPENDIX A The items listed below wera replaced after the diesel generator fire. These items either experienced fire or water damage, or were considered suspect since their condition could not be accurately evaluated. Those considered suspect were replaced to support the current schedule.
I. Engine Mounted Equipment Lef t Bank Air Intake Butterfly Valve Front Left Bank Air Start Solenoid Valve
- 1, #2, #3 LB Crankcase Relief Valves Right Bank Turbocharger Right Bank Exhaust Adapter Right Bank Exhaust Expansion Joint Right Bank Intake Adapter Left Bank Turbocharger Left Bank Exhaust Adapter Left Bank Exhaust Expansion Joint Left Bank Intake Adapter Left Bank Intercooler Left Bank Intercooler Inlet Adapter Left Bank Intercooler Outlet Adapter Engine Governor Engine Driven Fuel Oil Booster Pump Overspeed Trip Device
- 1, #2 LB Air Start Manifold Elbows Various Fuel Oil Piping Various Lube Oil Piping Control System Tubing
- 1 LB Air Intake Manifald Elbow Shutdown Cylinder Fuel Oil Switching Valve Fuel Oil Filter Fuel Oil Strainer
- 1, #2 LB High Pressure Fuel Injection Lines Fuel Oil Return Lines on #5 LB and #1 RB Engine Oil Sump to Lube Oil Tank Connector
- 1 LB, #2 LB, #8 LB, #1 RB Fuel Injection Pumps Lube Oil Check Valves F059, F094, F045, F080 i Lube Oil Thermostatic Control Valve l Lube Oil Filter Elements l
l II. Engine Mounted Instrumentation l
Engine tachometer sensor N073A l
Engine tachometer sensor N073C l
Lube Oil Sump Tank Level Switch N026A
- Engine Vibration Switch N164A l Shutdown Cylinder Control Air 3-way Valve l Lube Oil Temperature Element N027A l Lube Oil Temperature Switch N163A Control Air Pressure Regulator Overspeed Trip-Control Air 3-way Valve Shutdown Cylinder Shuttle Valve l
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Attachm2nt to AECM-84/0137 Page 6 of 6 I
Engine Mounted Instrumentation (Continued) j 1
Air Start System Timer Control Control Air Tubing Crankeese. Pressure Switch N160A Crankcase Pressure Switch N160B Crankcase Pressure Switch N160C Lube Oil Pump Pressure Switch N076A Turbocharger Lube Oil Pressure Switch N168C Jacket Water Temperature Switch N162A Turbocharger Lube Oil Pressure Switch N168A Fuel Oil Strainer Differential Pressure Switch N027A Turbocharger Vibration Switch N165A Lube Oil Ou'let t Temperature Thermocouple N029A Lube Oil Pump Pressure Switch N075A Fuel Oil Pump Pressure Switch N019A III. Engine Mounted Electrical Equipment Flex Conduit on C007A Lube Oil Pump Motor on C009A Lube Oil Heater Pump Governor to Terminal Box Wiring Magnetic Pick-Up to Terminal Box Wiring Sealtight from Terminal Box #4 to Condulet S.O. Cord from Terminal Box #4 to Governor Conduit and Sealtight from F507B to Terminal Box #1 Sealtight from Terminal Box #2 to N073A and N073C All Sealtight Straps Sealtight and wiring from Lube Oil Level switch to Terminal Box Sealtight and wiring from Lube Oil pressure switches to Terminal Box Sealtight and wiring from crankcase pressure switches to Terminal Box
-Bearing on Right Bank Crankcase fan motor Generator Brushes Lube Oil Heater IV. Miscellaneous Items Fire Damper Fuseable Links HVAC & Piping Insulation Engine Lubrication Oil Division I D/G Room Sprinkler Heads Gauges on Valve P71F543 Temperature Switch X77N010 Aftercooler Temperature Switch N011A Fire Detectors in Division I D/G Room
. Fire Detector 802A and 802E Sealtight on C013A Air Compressor Bus Bar on X31E001A Overhead Crane Overhead Lighting Emergency Lighting Intake Air Filter Oil Lubrication Oil in Air Compressors ,
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E MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi P. O. B 1 g4rO. J A C K S O N, M I S S I S S I P P I 3 9 2 0 5 gH '
tarch 8, 1984 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 - Division 1 Diesel Generator Fire, Failure of Fire Protection Deluge Valve to Open LER 83-126/01 X-3 AECM-84/0137 This letter submits an update to previous reports submitted on September 16, 1983, October 20, 1983, and December 30, 1983. The event for which the report was submitte ! occurred on September 4,1983, when a Division 1 Diesel Generator fuel line ruptured resulting in a fire near the lef t bank turbocharger. The engine was secured and an unusual event was declared from 1447 hours0.0167 days <br />0.402 hours <br />0.00239 weeks <br />5.505835e-4 months <br /> to 1559 hours0.018 days <br />0.433 hours <br />0.00258 weeks <br />5.931995e-4 months <br />. Personnel responding to the fire noted that the fire protection deluge valve failed to open. The valve was manually opened.
The fire was extinguished approximately 25 minutes after starting. The event was reported pursuant to Technical Specification 6.9.1.12.1.
Our investigation into the cause of the fuel line failure and corrective action associated with the Division 1 and 2 Diesel Generators is complete.
Our investigation into the cause of the deluge valve failure and corrective action associated with the deluge valves protecting the three emergency diesel generators is complete. This is a final report. Attached is LER 83-126/01 X-3 with Supplementary Information.
Yours truly,
. h. e L. F. Dale Manager of Nuclear Services EBS/SHH: sad Attachment .
NFFTCIAL COPYd .-
cc: (See Next Page) g 2'2,[ g 1 I Member Middle South Utilities System
AECM 4/0137 l Page 2 i MISS120IPPI POWER Q Ll2HT COMPANY cc: Mr. J. E. 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)
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
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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 | |
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