ML20084S909
ML20084S909 | |
Person / Time | |
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Site: | Robinson |
Issue date: | 05/31/1976 |
From: | Tollison A CAROLINA POWER & LIGHT CO. |
To: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
References | |
BSEP-77-609, NUDOCS 8306200068 | |
Download: ML20084S909 (1) | |
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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20084S9121977-03-25025 March 1977
[Table view]Telecopy Ao:On 770324,containmet Spray Pump a Out of Svc During Training Startup,Violating Tech Spec ML20084S9091976-05-31031 May 1976 Ao:On 770527,HPCI Pressure Switches E41-PSH-NO12 A,B,C & D Exceeded Tech Spec Calibr Limits.Switches Immediately Recalibr ML20086D4211976-02-0909 February 1976 AO 50-261/76-3:on 760128,high Level Alarm Received on Safety Injection Accumulator B.Caused by Check Valve 875 Leaking Resulting in Dilution.Accumulator Partially Drained & Refilled ML20086D4421976-02-0202 February 1976 AO 50-261/76-2:on 760121 & 22,failure of One & Delayed Operation of Two Reactor Trip Relays Occurred.Caused by Open Coil Winding.Three Defective Relays Replaced ML20086D4271976-01-29029 January 1976 Telecopy Ao:On 760128,sample of Safety Injection Accumulator B Indicated Boron Concentration of 1,939 Ppm,Below Tech Specs.Accumulator Partially Drained,Refilled & Verified ML20086D4391976-01-22022 January 1976 Ao:On 760124 & 22,discovered That Reactor Trip Relay RT3 in Reactor Protection Logic Train a Operating Erratically. Further Investigation Revealed That Relays RT-4 & RT-8 on Logic Train B Defective.Relays Replaced ML20086D4471976-01-13013 January 1976 AO 50-261/76-1:on 760102,failure of Boric Acid Transfer Pump Resulted in Failure of One ESF Component That Caused or Threatened to Render Sys Incapable of Functioning.Caused by Damaged Rotor ML20086F5211976-01-0202 January 1976 Ao:On 760102,boric Acid Pump B Stopped Running.Caused by Defective Stator & Damaged Rear Bearing.Investigation Continuing NG-75-2222, AO 50-261/75-20:on 751210,channel 950 of Containment Pressure Protection Found Inoperable.Caused by Open Output Fuse in Comparator PC-950.Fuse Replaced1975-12-23023 December 1975 AO 50-261/75-20:on 751210,channel 950 of Containment Pressure Protection Found Inoperable.Caused by Open Output Fuse in Comparator PC-950.Fuse Replaced NG-75-2210, AO 50-261/75-19:on 751208,boron Concentration Found Below Limits in Safety Injection Accumulator B.Cause Not Stated. Accumulator Partially Drained & Refilled from Refueling Water Storage Tank1975-12-22022 December 1975 AO 50-261/75-19:on 751208,boron Concentration Found Below Limits in Safety Injection Accumulator B.Cause Not Stated. Accumulator Partially Drained & Refilled from Refueling Water Storage Tank ML20086F5161975-12-0808 December 1975 Ao:On 751208,boron Sample from Safety Injection Accumulator B Indicated 1,915 ppm,35 Ppm Below Tech Specs.Cause Unknown. Accumulator Partially Drained & Refilled from Refueling Water Storage Tank NG-75-2017, AO 50-261/75-18:on 751102,auxiliary Feedwater Pump a Failed to Start Following Safety Injection Signal.Caused by Tarnished Contacts.Contacts within Local/Remote Switch Cleaned.Further Investigation Underway1975-11-13013 November 1975 AO 50-261/75-18:on 751102,auxiliary Feedwater Pump a Failed to Start Following Safety Injection Signal.Caused by Tarnished Contacts.Contacts within Local/Remote Switch Cleaned.Further Investigation Underway NG-75-2010, AO 50-261/75-17:on 751101,both Containment Personnel Air Lock Doors Opened Simultaneously W/Rcs Temp Above 200 F, Violating Tech Spec 3.6.1.a.Caused by Broken Rod,Bearing & Cam Follower on Outer Door Mechanism1975-11-12012 November 1975 AO 50-261/75-17:on 751101,both Containment Personnel Air Lock Doors Opened Simultaneously W/Rcs Temp Above 200 F, Violating Tech Spec 3.6.1.a.Caused by Broken Rod,Bearing & Cam Follower on Outer Door Mechanism NG-75-2001, AO 50-261/75-16:on 751028,svc Water Booster Pump B Failed to Start.Caused by Actuation of Pump Suction Pressure Switches Provided to Protect Pumps from Low Npsh.Containment Recirculation Fans Stopped to Prevent Overheating Motors1975-11-11011 November 1975 AO 50-261/75-16:on 751028,svc Water Booster Pump B Failed to Start.Caused by Actuation of Pump Suction Pressure Switches Provided to Protect Pumps from Low Npsh.Containment Recirculation Fans Stopped to Prevent Overheating Motors ML20086F5291975-11-0404 November 1975 Ao:On 751102,motor Driven Auxiliary Feedwater Pump a Failed to Start.Remote Electrical Contacts Cleaned ML20086F5401975-11-0303 November 1975 Ao:On 751101,containment Integrity Broken for Approx 10 Minutes Due to Simultaneous Opening of Both Personnel Air Lock Doors ML20086F5491975-10-29029 October 1975 Ao:On 751028,sequence of Switch Operations Resulted in Breakers for Both Svc Water Booster Pumps a & B Tripping on Overload NG-75-1575, AO 50-261/75-15:on 750921,more than One Inoperable Rod Present W/Reactor at Power as Result of Rod Control Urgent Failure.Caused by Defective Fuse in Ac Power Supply to Rod Control Cabinet 1AC.Fuse Replaced1975-10-0101 October 1975 AO 50-261/75-15:on 750921,more than One Inoperable Rod Present W/Reactor at Power as Result of Rod Control Urgent Failure.Caused by Defective Fuse in Ac Power Supply to Rod Control Cabinet 1AC.Fuse Replaced ML20086F5611975-09-22022 September 1975 Ao:On 750921,urgent Failure Alarm Received.Caused by Phase Failure in Cabinet 1AC Which Rendered 12 Rods Inoperable. Reactor Manually Tripped NG-75-1212, Revised AO 50-261/75-11:on 750527,RCS Oxygen Concentration Found to Be 0.16 Ppm,Exceeding Limit.Caused by Inattention to Hydrogen Concentration & Dilution of RCS to Hot Shutdown Boron Concentration.Vol Control Tank Vented1975-08-0404 August 1975 Revised AO 50-261/75-11:on 750527,RCS Oxygen Concentration Found to Be 0.16 Ppm,Exceeding Limit.Caused by Inattention to Hydrogen Concentration & Dilution of RCS to Hot Shutdown Boron Concentration.Vol Control Tank Vented NG-75-1158, AO 50-261/75-14:on 750715,valve V2-14B Steam Driven Auxiliary Feedwater Pump Discharge to Steam Generator B Failed to Open.Caused by Belleville Spring Being Filled W/Grease.Belleville Spring Packs & Shafts to Be Inspected1975-07-25025 July 1975 AO 50-261/75-14:on 750715,valve V2-14B Steam Driven Auxiliary Feedwater Pump Discharge to Steam Generator B Failed to Open.Caused by Belleville Spring Being Filled W/Grease.Belleville Spring Packs & Shafts to Be Inspected ML20086F5961975-07-16016 July 1975 Telecopy Ao:On 750715,steam Drive Auxiliary Feedwater Pump Discharge Valve V2-14B to Steam Generator B Failed to Open Electrically ML20086F6151975-07-14014 July 1975 Ao:On 750711,control Rod L-5 Dropped,Causing Load Runback to Approx 70% Power.Caused by Defective Stationary Gripper Coil NG-75-1089, Revised AO 50-261/75-8:on 750429,RHR Suction Valve RHR-862A Failed.Caused by Torque Switch on Motor Operator Being Out of Adjustment,Causing Valve to Be Wedged Onto Seat & Preventing Motor from Opening Valve1975-07-11011 July 1975 Revised AO 50-261/75-8:on 750429,RHR Suction Valve RHR-862A Failed.Caused by Torque Switch on Motor Operator Being Out of Adjustment,Causing Valve to Be Wedged Onto Seat & Preventing Motor from Opening Valve NG-75-1044, AO 50-261/75-12:on 750625,boric Acid Transfer Pump a Failed. Caused by Pump Shaft Being Broken at Keyway.Pump Rebuilt & Reinstalled.New Pump Model GVH-10K Will Be Installed Upon Receipt1975-07-10010 July 1975 AO 50-261/75-12:on 750625,boric Acid Transfer Pump a Failed. Caused by Pump Shaft Being Broken at Keyway.Pump Rebuilt & Reinstalled.New Pump Model GVH-10K Will Be Installed Upon Receipt ML20086F6081975-06-26026 June 1975 Telecopy Ao:On 750625,boric Acid Transfer Pump a Noted Off. Caused by Pump Shaft Being Broken at Keyway.Also on 750625, Employee Received Whole Body Dose of 3,080 Mrem for Quarter Ending 750630 ML20086F6741975-06-12012 June 1975 Revised AO 50-261/75-9:on 750501,reactor Coolant Pump Seal Failed,Resulting in Discharge of Reactor Coolant Fluid to Containment Floor.Caused by Pump Running W/Seal Leaking. Seals,Shaft,Impeller & Hearings Replaced ML20086F6201975-06-0606 June 1975 AO 50-261/75-11:on 750527,RCS Oxygen Concentration Noted to Be 0.16 Ppm,Exceeding Limit.Caused by Mixture of Hydrogen & Nitrogen in Vol Control Tank,Limiting Hydrogen to Rcs.Vol Control Tank Vented ML20086F6271975-06-0202 June 1975 AO 50-261/75-10:on 750521,boric Acid Transfer Pump B Failed.Caused by Shaft Being Broken at Keyway & Worn Pump Bearing.Pump Rebuilt ML20086F6231975-05-27027 May 1975 Ao:On 750527,RCS Sample Indicated 0.16 Ppm Oxygen,Exceeding Tech Specs.No Cause Stated.Concentration Reduced ML20086F6301975-05-21021 May 1975 Ao:On 750521,boric Acid Pump B Stopped.Caused by Broken Shaft in Keyway Area ML20086F5791975-05-12012 May 1975 AO 50-261/75-9:on 750501,reactor Coolant Pump Seal Failed, Resulting in Discharge of Reactor Coolant Fluid to Containment Floor.New Seal & Associated Parts Being Installed.Parts Shall Be Certified ML20086F6441975-05-0909 May 1975 AO 50-261/75-8:on 750429,RHR Pump Suction Valve RHR-862A Failed.Caused by Torque Switch on SMB-O Motor Operator Being Out of Adjustment.Torque Switch Adjusted.On 750430,complete Insp of Operator Found Excess Grease.Grease Removed ML20086F6911975-05-0202 May 1975 Telecopy Ao:On 750501,seal 1 on Reactor Coolant Pump C Failed,Producing Leak to Containment Floor.Seal 2 Failed on 750502.Cooldown Initiated.Rcs Depressurized & Drained to Below Pump Seals ML20086F6471975-04-29029 April 1975 Ao:On 750429,valve RHR-862A Failed to Open from RTGB When RHR Sys Being Aligned.Cause Under Investigation.Valve Opened Locally Using Manual Operator & All Flow Paths Restored ML20086F6981975-04-10010 April 1975 AO 50-261/75-7:on 750331,diesel B Tripped Due to Low Lube Oil Pressure.Caused by Lube Oil Filter High Differential Pressure Resulting from Dirty Filters.Lube Oil Filters Replaced ML20086F6961975-04-0101 April 1975 Telecopy Ao:On 750331,emergency Diesel B Tripped.Caused by Low Lube Oil Pressure.Filters Changed & Unit Returned to Svc ML20086F6991975-03-27027 March 1975 AO 50-261/75-6:on 750314,contractor Personnel Exposed to Radiation in Excess of Limits.Caused by Exceeding Stay Time in Localized Field of High radiation.Chem-Nuclear,Inc & Util Investigating Use of Addl Shielding ML20086F7001975-03-0707 March 1975 AO 50-261/75-5:on 750225 & 26,boric Acid Transfer Pump B Failed.Cause Not Identified.Pump Replaced ML20086F7011975-02-14014 February 1975 AO 50-261/75-4:on 750206,reactor Protection Overpower Channel Set I Failed to Generate Rod Stop Signal for Simulated Overpower Condition.Caused by Failure of Comparator Circuit in Dual Circuit Signal Comparator ML20086F7051975-02-0707 February 1975 Ao:On 750206,signal Comparator TO-412B Failed to Operate. Portion of Comparator Which Generates Rod Stop & Turbine Runback Signal Failed While Overpower Reactor Trip Signal Still Generated ML20086F7111975-02-0606 February 1975 AO 50-261/75-3:on 750126,component Cooling Water Pump C Tripped Due to Overcurrent.Caused by Backleakage Through Pump Discharge Side Check Valve Due to Debris.Leaking Mechanical Seal & Status Light Module Replaced ML20086F7201975-01-30030 January 1975 AO 50-261/75-2:on 750120,pressurizer Level Channel II Failed to Generate Reactor Trip Signal or Safety Injection Signal Upon Insertion of Simulated High & Low Levels.Caused by Malfunctioning Filter Capacitor C.3 ML20086F7281975-01-27027 January 1975 AO 50-261/75-1:on 750114,boric Acid Transfer Pump a Failed. Caused by Failed Shaft in Vicinity of Impeller Keyway.Pump Replaced.Replacement Pump Model GVH-10K on Order ML20086F7141975-01-27027 January 1975 Telecopy Ao:On 750126,component Cooling Pump C Failed to Start from Rtgb.Cause Under Investigation.Pump Breaker Racked Out,Inspected & Racked in ML20086F7241975-01-20020 January 1975 Telecopy Ao:On 750120,level Comparator LC-460A Failed to Operate.Cause Not Stated ML20086F7351975-01-15015 January 1975 Ao:On 750114,boric Acid Transfer Pump a Noted to Be in Off Indication at Rtgb.Caused by Broken Shaft ML20085D0621973-07-17017 July 1973 Ao:On 730628-0705 & 09-10,changes Performed on Safeguards Equipment W/O Demonstrating Operability of Redundant Equipment Before Removal.Safety Injection Pumps B & C Tripped & Circuit Breaker Tripped,Respectively ML20085D0661973-07-11011 July 1973 Telecopy Ao:On 730709,two Safety Injection Pumps Experienced Overcurrent Trips.Caused by New Overcurrent Trip Devices Tripping at Lower than Desired Value.Trip Setting Increased ML20085D0771973-07-10010 July 1973 Telecopy Ao:On 730710,circuit Breaker for Containment Cooler Fan 2 Tripped.Caused by Overcurrent Due to Misalignment of Calibr Spring in Overcurrent Trip Device.Spring Realigned 1977-03-25 Category:TEXT-SAFETY REPORT MONTHYEARML20217A1691999-09-22022 September 1999
[Table view]Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers RA-97-0258, LER 97-S12-00:on 971119,discovered Uncompensated Security Zone.Caused by Inattention to Detail by Members of Security Force.Provided Event Info to Security Shift Personnel & Changed Practice Re Zone Review1997-12-19019 December 1997 LER 97-S12-00:on 971119,discovered Uncompensated Security Zone.Caused by Inattention to Detail by Members of Security Force.Provided Event Info to Security Shift Personnel & Changed Practice Re Zone Review ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20217Q2751997-06-30030 June 1997 CP&L Fitness for Duty Program Performance Data for Period 970101-0630 ML14183A6951995-09-18018 September 1995 Safety Evaluation Approving Relocation of Technical Support Ctr ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML17352A8691993-05-31031 May 1993 Technical Rept, Assessment of Aging Degradation of Civil/ Structural Features at Selected Operating Nuclear Power Plants. ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20079H1571991-09-30030 September 1991 Nonproprietary Evaluation of Revised Transfer to Cold Leg Recirculation Procedure,Hb Robinson Unit 2 ML20086T2951991-06-14014 June 1991 Rev 1 to EQ Documentation Package Eqdp 36.0, Boston Insulated Wire Cable ML20086T2861991-03-0808 March 1991 Rev 1 to EQ Documentation Package Eqdp 11.1, Dekoron Instrumentation Cables ML20086T2561991-03-0808 March 1991 Rev 1 to EQ Documentation Package 10.0, Continental Shielded Instrument Cable ML20065K6961990-10-31031 October 1990 Mechanical Licensing Rept for Hb Robinson High Thermal Performance Fuel Assemblies ML20065K6971990-10-31031 October 1990 Thermal Hydraulic Compatibility Analysis of Anf High Thermal Performance Fuel for Hb Robinson,Unit 2 ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML20247E0701989-07-20020 July 1989 Info Rept:On 890717-0804,fire Penetration Seals Will Be Removed from Svc to Allow Access for Ventilation Sys Mod. Addl Fire Barrier Penetrations Will Be Made in Wall Between RHR Pump Pit & Fuel Handling Bldg,Per Tech Spec 3.14.7.2 ML20246E9111989-03-31031 March 1989 PDC-3:Advanced Nuclear Fuels Corp Power Distribution Control for PWRs & Application of PDC-3 to Hb Robinson Unit 2 ML20245H0821989-01-25025 January 1989 Criticality Safety Analysis of Hb Robinson Spent Fuel Pool W/4.2% Nominal Enrichment Fuel Assemblies ML20205T0551988-10-31031 October 1988 Responses to NRC Questions on RTD Bypass Elimination Licensing Rept ML20147E2371988-02-29029 February 1988 1987 Annual Rept - Primary Coolant Iodine Spikes ML20147B1971987-12-31031 December 1987 1987 Annual Rept - Primary Safety & Relief Valve Challenges ML20236K7731987-10-31031 October 1987 Monthly Operating Rept for Oct 1987 ML20235W3781987-09-30030 September 1987 Monthly Operating Rept for Sept 1987 ML20238E2741987-08-31031 August 1987 Monthly Operating Rept for Aug 1987 ML20235H3151987-06-30030 June 1987 Monthly Operating Rept for June 1987 ML17261A5301987-06-18018 June 1987 Part 21 Rept Re Potential Util Failure to Comply W/Component Containment Isolation Licensing Commitment If Proposed Mods to Component Cooling Water Sys Instituted.Utils Advised to Evaluate Containment Isolation Sys ML20214W3241987-05-31031 May 1987 Monthly Operating Rept for May 1987 ML20214R5101987-04-30030 April 1987 Rev 1 to Monthly Operating Rept for Apr 1987,correcting Operation Statistics & Shutdown Experience Due to Mathematical Errors ML20215L4941987-04-30030 April 1987 Monthly Operating Rept for Apr 1987 ML20206F3561987-03-31031 March 1987 Monthly Operating Rept for Mar 1987 ML20210B4141987-03-31031 March 1987 Revised Monthly Operating Rept for Mar 1987 ML20205F6021987-03-23023 March 1987 Special Rept:On 870302,noble Gas Effluent Monitor for Main Steam Line B Declared Inoperable & Svc Not Returned Until 870312.Caused by Defective Detector.Detector Replaced.High Voltage for Detector Adjusted & Sys Operation Checked ML20212P3101987-02-28028 February 1987 Monthly Operating Rept for Feb 1987 ML20214Q7891987-01-31031 January 1987 Cycle 12,SAR ML20210R6341987-01-31031 January 1987 Monthly Operating Rept for Jan 1987 ML20207M2451986-12-31031 December 1986 Monthly Operating Rept for Dec 1986 L-18-120, Rev 0 to Supplemental Info in Support of Conservatisms in Criticality Analysis Performed for Hb Robinson Isfsi1986-12-18018 December 1986 Rev 0 to Supplemental Info in Support of Conservatisms in Criticality Analysis Performed for Hb Robinson Isfsi ML20215C7911986-11-30030 November 1986 Monthly Operating Rept for Nov 1986 ML20213F3121986-10-31031 October 1986 Monthly Operating Rept for Oct 1986 ML20215G1081986-09-30030 September 1986 Monthly Operating Rept for Sept 1986 ML20215F0361986-09-29029 September 1986 Special Rept:On 860902,during Cold Shutdown,Pressurizer PORV Lifted Twice to Prevent Overpressurization.Caused by Inadvertent Action by Unit Operators.Operations Personnel Counseled Re Importance of Breaker Position Indicators ML20211C0641986-09-0909 September 1986 Rev 0 to Final Rept Criticality Safety Analysis Hb Robinson Spent Fuel Storage Racks (Unpoisoned,Low Density) W/4.2% Enriched 15x15 Fuel Assemblies ML20211C0491986-09-0202 September 1986 Rev 0 to Final Rept Criticality Safety Analysis Hb Robinson New Fuel Storage Vault W/4.2% Enriched 15x15 Fuel Assemblies ML20212F5321986-07-31031 July 1986 Monthly Operating Rept for Jul 1986 ML20203D0221986-07-14014 July 1986 Part 21 Rept Re Air Monitoring Sys Probes Exhibiting Blue Tip Rather than Normal White Tip & Insensitive to Chlorine. Caused by Improper Handling/Storage.Advisory Bulletin Encl. Item Not Reportable Per Part 21 ML20202G3371986-06-30030 June 1986 Monthly Operating Rept for June 1986 ML20211B5601986-05-31031 May 1986 Monthly Operating Rept for May 1986 ML20197D2651986-04-30030 April 1986 Monthly Operating Rept for Apr 1986 1999-09-22 |
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, Brunswic1r. SteamJ1ectric FIsat F,,0..Bea 458 Southperii:, W. C. 28461 May 31, 1976 FII2: B3516 SERIAL: BSEF/77-609
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i 8 Mr. Normen C. Moseley, Director :
U.S. Nuclear Reggiatory Cosenission
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- Y Dear Mr. Moseley a f, l P On May 27, 1977, during performance of Periodic Test 2.1.7, EPCI Turbine 4
Exhaust Diaphragn Righ Pressure, pressure switches E41-F55-N012 A, B, C, and D were found to be out of calibration and to exceed Technical a' b Specification Limita. The seritches were immediately recalibrated and the Periodic Test completed satisfactorily. 1 This constitutes a reportable occurrence as defined in Technical Speci-ficatAon 6.11.2.a(5) and was reported to Mr. Cantrell of your office on May 31, 1977.
Yours very truly, ,
t-A. C. Tollison, Jr. Manager Brunswick Steam Electric Flent WEA/ebf ect Mr. B. R. Banks 1
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