LER-1979-018, /03L-0 on 790727:indicating Lights Failed for Reactor Bldg to Torus Vacuum Breaker,Fcv 2-64-21.Valve Inoperative Contrary to Tech Specs.Caused by Control Circuit Fuse Blowing Due to Failure of Coil for Relay 16A-K40 |
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| 2601979018R03 - NRC Website |
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text
'l REGULATORY INFORMATION DISTRIB TION SYSTEM (RIDS)
AC(.OSSIAN NBR:7908280742 C,DATE; 79/08/24 NOTARIZE,:
NO DOCKET FACIL:50-260 Browns Ferry.Nuclear Power Station~
Unit 2~
Tennessee 05000260 AUTH'AME AUTHOR AFFILIATION Tennessee Valley Authority RECIP ~ NAME RECIPIENT AFFILIATION Region 2i Atlanta'ffice of the Director
SUBJECT:
LER 79-018/03L 0
on 790727lindicating lights failed for FCV 2 64"21ireactor bldg to torus vacuum breaker, Valve inoperative contrary to Tech/Specs'aused by control circuit fuse blowing due to failure of coil for relay 16A K40, DISTRIBUTION CODE:
A002S COPIES RECEIVEDeLTR Q
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SIZE:
TITLEt INCIDENT REPORTS N
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A RECIPIENT ID CODE/NAME" ACTION:
05 BC y~ 3
. INTERNAL: 01 EG FIL 09 14 TA/EDO 16 EEB 18 PLANT SYS BR 20 AD PLANT SYS 23 ENGR BR 25 PNlR SYS BR 27 OPERA LIC BR 29 AUX SYS BR HANAUERpS ~
TMI H STREET EXTERNAL: 03 LPDR 29 ACRS COPIES LTTR ENCL 1
1 2
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1 1
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16 16 RECIPIENT ID CODE/NAME 02 NRC PDR 11 MPA 15 NOVAK/KNIEL 17 AD FOR ENGR 19 ILC SYS BR 22 REAC SAFT BR KREGER 26 AD/SITE ANAL 28 ACDENT ANLYS E, JORDAN/IE STS GROUP LEADR 04 NSIC COPIES LTTR ENCL 1
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TOTAl. NUMBER OF COPIES REQUIRED:
LTTR 48 ENCL 48
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August 24, 1979
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TENNESSEE VALLEYAUTMORITY cHATTANQQGA. TENNEssEE 37401 716 Edney,Building Mr. James P.
O'Re y, Director U.S. Nuclear Re latory Commission Office of Ins ction and Enforcement Region II 101 Mari a Street, Suite 3100 Atlant, Georgia 30303
Dear Mr. O'Reialy:
F TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNIT 2 - DOCKET NO. 50-260 - FACILITY OPERATING LICENSE DPR REPORTABLE OCCURRENCE REPORT BFRO-50-260/7918 The enclosed report provides details concerning a loss of indicating lights for FCV 2-64>>21, reactor building to torus vacuum breaker, during normal operation.
This report is submitted in accordance with Browne Ferry unit 2 Technical Specification 6.7.2.b.2.
Very truly yours, TENNESSEE VALLEY MTHORITY.
J, R. Calhoun Director of Nuclear Power Enclosure (3) cc (Enclosure)!
Director (3)
Office of Management Information and rogram Control U.S. Nuclear Regulatory Commission washington,'DiC.
20555 Director (40)
Office of Inspection and Enforcement.
U.S. Nuclear Regulatory Commission
$1ashington, D.C, 20555 R. P. SuUivan, NRC Inspector, Browne Perry N
'7 908 8 807'3~1 An Equal Opportunity Employer
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9, LICENSEE CODE
{PLEASE PRINT OR TYPE ALLREQUIRED INFORMATION) 6 ZQ3 0
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1 1 1Q4~Q3 14 15 LICENSE NUMBER 25 2G LICENSE TYPE 30 57 CAT 58 QG0 5
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9 QD GO G I DOCKET NUMBER GB 639 EVENT DATE 74 75 REPORT DATE
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80 EVEN'I'ESCRIPTION AND PROBABLE CONSEQUENCES Q10 During normal operation, the control room operator observed a loss of indicating lights for FCV 2-64-21, reactor building to torus vacuum breaker.
Further investigation re-4 l ~os vealed the valve inoperative, contrary to Tech.
Spec 3.7.A.3.a.
There were no sig-nificant resulting occurrences.
There were no previous similar occurrences.
There was no effect on the public health or safety.
Redundant valve FCV-2-64-20 was oper-(pe~]
able.
~08 80 7
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8 SYSTEM
CAUSE
CAUSE COMP VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE
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10 I 'I 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LFR/RO EVENT YEAR REPORT NO.
CODE TYPE NO.
0 M343
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Uo 21 22 23 24 2G 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD'4 PRIME CohIP COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORh1 SUB.
SUPPLIER MANUFACTURER Q18 ~Z Q19
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,CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o
The coil for relay 16A-K40, GE 115V 60 c Model 55-1G failed causing the control cir-cuit fuse for FCV-2-64-21 to blow.
The rela coil was re laced and a new fuse in-
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s't4alled 3
4 7
8 9
FACILITY STATUS
'4 POWER
~
OTHER STATUS Q 0
8 29 NA NAME OF PREPARER 8 O33 7
8 9
'0 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE AMIOUNTOF ACTIVITYQ
~ZQ34 7
8 9
10 44 PERSONNEL EXPOSURES NUI'4BER TYPE DESCRIPTION Q33 3 ~00 0
Q33 Z
Q33 NA 7
8 9
11 12 13 PERSONNEL INJURIES
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NUh1BER DESCRIPTIONQ41 [i'oo o
Q43 7
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11 12 LOSS OF OR OAh'IAGE TO FACILITYQ43 TYPE'ESCRIPTION 9
Z Q42 8
9 10 PUBI,ICITY ISSUED DESCRIPTION ~~
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8 9
10 45 80 80 leos s 607' 80 PHONE'0 NRC USE ONLY O
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80 METHOD OF DISCOVERY DISCOVERY DESCRIPTION
&32
~AQ31 Operator observed loss of con>rol light 45 48 80" LOCATIONOF RELEASE Qs NA
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"1'ennessee Valley Authority Drowns Ferry Nuclear Plant e
LER SUPPLEMENTAL INFORMATION Form BF-17 BF 15. 2 1/10/79 BFRO 260 /
7918 Technical Specification Involved
- 3. 7.A. 3.a and b
Reported Under Technical Specification 6.7.2.b.2 Date of Occurrence 7/27/79 Time of Occurrence 1800 Unit 2
Identification and Descri tion'of Occurrence:
Operator observed that there was a loss of indicator lights for FCV 2-64-21.
Conditions Prior to Occurrence:
Unit at full load and normal operation.
Action specified in the Technical Specification Surveillance Requirements met due to ino erable e ui ment.
Describe.
Tech.
Spec.
3.7.A.3.b allowed seven-day continued operation.
Valve repaired in less than three hours.
~A ~arear Cause of Occurrence:
Coil for relay 16A-K40 failed resulting in the control fuse for FCV 2-64 blowing.
N/A Corr ective Action:
Relay coil and fuse replaced.
Failure Data:
N/A
- ~Retention:
~Revision:
eriod - Lifetime; Responsibility
- - Administrative Supervisor
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| 05000296/LER-1979-001-03, /03L-0 on 790111:switch on LIS-3-56B Failed to Trip Reactor Recirculation Pump Motor Generator.Caused by Misadjusted Switch on Yarway Model 4418CE.Switch Recalibr & Tested Satisfactorily | /03L-0 on 790111:switch on LIS-3-56B Failed to Trip Reactor Recirculation Pump Motor Generator.Caused by Misadjusted Switch on Yarway Model 4418CE.Switch Recalibr & Tested Satisfactorily | | | 05000296/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000259/LER-1979-001, Forwards LER 79-001/01T-0 | Forwards LER 79-001/01T-0 | | | 05000259/LER-1979-001-01, /01T-0 on 790118:reactor Scrammed Due to High Flux Actuating Intermediate Range Monitor high-high Neutron Monitoring Circuit;Reactor Neared Criticality.Caused by Withdrawal of High Reactivity Worth Rod | /01T-0 on 790118:reactor Scrammed Due to High Flux Actuating Intermediate Range Monitor high-high Neutron Monitoring Circuit;Reactor Neared Criticality.Caused by Withdrawal of High Reactivity Worth Rod | | | 05000260/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000260/LER-1979-001-03, /03L-0 on 790113:during Test of high-pressure Injection Coolant Sys,Steam Supply Valve FCV-73-16 Failed to Open,Rendering Sys Inoperative.Caused by Failure of Limitorque Valve Operator Limit Switch | /03L-0 on 790113:during Test of high-pressure Injection Coolant Sys,Steam Supply Valve FCV-73-16 Failed to Open,Rendering Sys Inoperative.Caused by Failure of Limitorque Valve Operator Limit Switch | | | 05000296/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000259/LER-1979-002-03, /03L-0 on 790129:during Normal Operation While Performing Surveillance Test,Standby Liquid Control Pump 1B Relief Valve Opened Below Tech Spec Min.Caused by Valve Seat Surface Deterioration | /03L-0 on 790129:during Normal Operation While Performing Surveillance Test,Standby Liquid Control Pump 1B Relief Valve Opened Below Tech Spec Min.Caused by Valve Seat Surface Deterioration | | | 05000259/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000260/LER-1979-002-03, /03L-0 on 790203:alarm for Fire Protection Panel 25-236 Annunciated in Control Room.Panel Was Not Alarmed Condition.Caused by Normal End of Life Electrical Failure of Annunciator Point Card.Card Replaced & Sys Normalized | /03L-0 on 790203:alarm for Fire Protection Panel 25-236 Annunciated in Control Room.Panel Was Not Alarmed Condition.Caused by Normal End of Life Electrical Failure of Annunciator Point Card.Card Replaced & Sys Normalized | | | 05000260/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000296/LER-1979-002-03, /03L-0 on 790117:during Maintenance of Reset Switch,Short Circuit Damaged Power Supply & Sensor Circuit Board,Rendering Fixed Spray Automatic Initiation Circuit for Fire Protection Inoperable | /03L-0 on 790117:during Maintenance of Reset Switch,Short Circuit Damaged Power Supply & Sensor Circuit Board,Rendering Fixed Spray Automatic Initiation Circuit for Fire Protection Inoperable | | | 05000296/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000259/LER-1979-003-01, /01T-1 on 790120:during Cold Shutdown,Local Leak Rate Test Indicated Excessive Total Leakage.Caused by Leaking Valve Seating Surface in Eight Valves.Valves Repaired & Retested | /01T-1 on 790120:during Cold Shutdown,Local Leak Rate Test Indicated Excessive Total Leakage.Caused by Leaking Valve Seating Surface in Eight Valves.Valves Repaired & Retested | | | 05000259/LER-1979-003, Forwards LER 79-003/01T-1 | Forwards LER 79-003/01T-1 | | | 05000260/LER-1979-003-01, /01T-0 on 790214:rod Position Info Sys Power Supply Ps X-5 Failed,Causing Loss of Rod Position Indication in Bottom Half of Vertical Core Display.Caused by Failure of Cooling Fan in Trygon Model L5B6-70-OVS4989 | /01T-0 on 790214:rod Position Info Sys Power Supply Ps X-5 Failed,Causing Loss of Rod Position Indication in Bottom Half of Vertical Core Display.Caused by Failure of Cooling Fan in Trygon Model L5B6-70-OVS4989 | | | 05000259/LER-1979-003-03, /03L-2 on 790120:during Cold Shutdown,Local Leak Rate Test Revealed Total Leakage Exceeded Allowable 60% La Per 24-h.Caused by Excessive Leakage of Valve Seating Surface.Eight Leaking Valves Were Repaired & Retested | /03L-2 on 790120:during Cold Shutdown,Local Leak Rate Test Revealed Total Leakage Exceeded Allowable 60% La Per 24-h.Caused by Excessive Leakage of Valve Seating Surface.Eight Leaking Valves Were Repaired & Retested | | | 05000296/LER-1979-003-03, /03L-0 on 790202:linear Heat Generation Rate Out of Tech Spec Limits.Caused by Operation Close to Limiting Values & Increase in Reactivity Due to Gadolina Burnup. Greater Margin to Limiting Value Will Be Maintained | /03L-0 on 790202:linear Heat Generation Rate Out of Tech Spec Limits.Caused by Operation Close to Limiting Values & Increase in Reactivity Due to Gadolina Burnup. Greater Margin to Limiting Value Will Be Maintained | | | 05000260/LER-1979-003, Forwards LER 79-003/01T-0 | Forwards LER 79-003/01T-0 | | | 05000260/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000259/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000259/LER-1979-004-03, /03L-0 on 790227:during Normal Operation,Review of Surveillance Test Data Indicated Monthly Samples of Diesel Fuel Taken in Dec 1978 Have Not Been Analyzed.Caused by Loss of Samples in Transit.Will Try to Measure Samples on | /03L-0 on 790227:during Normal Operation,Review of Surveillance Test Data Indicated Monthly Samples of Diesel Fuel Taken in Dec 1978 Have Not Been Analyzed.Caused by Loss of Samples in Transit.Will Try to Measure Samples on Site | | | 05000296/LER-1979-004-03, /03L-0 on 790411:during Normal Operation,Heat Detector Alarmed & Would Not Clear.Alarm Would Have Masked Signals from Other Detector,Required to Be Operational.Caused by Personnel Damaging Detector | /03L-0 on 790411:during Normal Operation,Heat Detector Alarmed & Would Not Clear.Alarm Would Have Masked Signals from Other Detector,Required to Be Operational.Caused by Personnel Damaging Detector | | | 05000260/LER-1979-004-03, /03L-0 on 790414:reactor Bldg,Turbine Bldg & Refueling Zone Vent Exhaust Monitor RM-90-250 Failed Surveillance Test SI 4.8.B-4.3,Section 4e.Caused by Failure of Input Card for Radiation Monitor | /03L-0 on 790414:reactor Bldg,Turbine Bldg & Refueling Zone Vent Exhaust Monitor RM-90-250 Failed Surveillance Test SI 4.8.B-4.3,Section 4e.Caused by Failure of Input Card for Radiation Monitor | | | 05000296/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000296/LER-1979-005, Updated LER 79-005/01T-2:on 790506,RHR Svc Water Supply to RHR HX 2B Isolated Standby Coolant Supply.Caused by Lack of Administrative Control Over Sys Cross Connect Valves. Controls Improved | Updated LER 79-005/01T-2:on 790506,RHR Svc Water Supply to RHR HX 2B Isolated Standby Coolant Supply.Caused by Lack of Administrative Control Over Sys Cross Connect Valves. Controls Improved | | | 05000296/LER-1979-005-01, /01T-1:on 790506,BHR Water Supply Isolation to 2B RHR Heat Exchanger Isolated Standby Coolant Supply to Unit 3.Caused by Lack of Administrative Control Over Sys Cross Connect Valves.Administrative Controls Have Been Improved | /01T-1:on 790506,BHR Water Supply Isolation to 2B RHR Heat Exchanger Isolated Standby Coolant Supply to Unit 3.Caused by Lack of Administrative Control Over Sys Cross Connect Valves.Administrative Controls Have Been Improved | | | 05000259/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000259/LER-1979-005-03, /03L-0 on 790225:reactor,turbine Bldg & Refueling Zone Vent Exhaust Monitor RM-90-250 Became Inoperable.Caused by Moisture Collection in Detector SC-2.-1.S.Detector Replaced & Moisture Removed | /03L-0 on 790225:reactor,turbine Bldg & Refueling Zone Vent Exhaust Monitor RM-90-250 Became Inoperable.Caused by Moisture Collection in Detector SC-2.-1.S.Detector Replaced & Moisture Removed | | | 05000260/LER-1979-005-03, /03L-0 on 790419:broken Terminal Discovered on Shutdown Board D Battery.Cause Unknown.Affected Cells Replaced & Personnel Instructed in Proper Tightening Methods | /03L-0 on 790419:broken Terminal Discovered on Shutdown Board D Battery.Cause Unknown.Affected Cells Replaced & Personnel Instructed in Proper Tightening Methods | | | 05000260/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000296/LER-1979-006-03, During Normal Operation, Erratic Indication of Torus Hydrogen Sensor Observed. Hydrogen Sensor Replaced & Tested Satisfactory.Design Change Request Initiated | During Normal Operation, Erratic Indication of Torus Hydrogen Sensor Observed. Hydrogen Sensor Replaced & Tested Satisfactory.Design Change Request Initiated | | | 05000296/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000260/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000259/LER-1979-006-03, /03L-0 on 790228:reactor,turbine Bldg & Refueling Zone Ventilation Exhaust Monitor RM-90-250 Became Inoperable for 3.5-h.Caused by Moisture in SC-2B Detector & Leaking Flanges.Moisture Removed & Flanges Tightened | /03L-0 on 790228:reactor,turbine Bldg & Refueling Zone Ventilation Exhaust Monitor RM-90-250 Became Inoperable for 3.5-h.Caused by Moisture in SC-2B Detector & Leaking Flanges.Moisture Removed & Flanges Tightened | | | 05000259/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000260/LER-1979-006-03, /03L-0 on 790427:prior to Refueling Shutdown, Drywell Prepurge Tritium Sample Not Taken.Caused by Lack of Understanding Between Operational & Lab Personnel.Operating Instructions Amended to Prevent Recurrence | /03L-0 on 790427:prior to Refueling Shutdown, Drywell Prepurge Tritium Sample Not Taken.Caused by Lack of Understanding Between Operational & Lab Personnel.Operating Instructions Amended to Prevent Recurrence | | | 05000260/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000296/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000296/LER-1979-007-03, /03L-0 on 790612:during Performance of Procedure SI 4.1.A-14,turbine First Stage Permissive Pressure Switches PS-1-81A & B & PS-1-91A & B Setpoints Exceeded Tech Specs. Caused by Setpoint Drift.Switches Recalibr | /03L-0 on 790612:during Performance of Procedure SI 4.1.A-14,turbine First Stage Permissive Pressure Switches PS-1-81A & B & PS-1-91A & B Setpoints Exceeded Tech Specs. Caused by Setpoint Drift.Switches Recalibr | | | 05000260/LER-1979-007-03, /03L-0 on 790503:during Refueling Outage,Five MSIVs Exceeded Leakage Limits.Caused by Irregularities on Valve Seating Surfaces & Entrapment of Debris Under Seating Surfaces.Valves Will Be Repaired & Retested | /03L-0 on 790503:during Refueling Outage,Five MSIVs Exceeded Leakage Limits.Caused by Irregularities on Valve Seating Surfaces & Entrapment of Debris Under Seating Surfaces.Valves Will Be Repaired & Retested | | | 05000260/LER-1979-008-01, /01T-0 on 790504:while Preparing for Refueling Outage,Secondary Containment Integrity Was Not Conclusively Demonstrated Prior to Breaking Primary Containment.Test Improperly Performed Due to Personnel Error | /01T-0 on 790504:while Preparing for Refueling Outage,Secondary Containment Integrity Was Not Conclusively Demonstrated Prior to Breaking Primary Containment.Test Improperly Performed Due to Personnel Error | | | 05000259/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000259/LER-1979-008-03, /03L-0 on 790612:during Normal Operation, Pressure Switches PS-1-81 a & B & PS-1-91 a & B Setpoints Exceeded Tech Specs by 3-15 Psig. Caused by Model B2T-A12SS Switches Drifting | /03L-0 on 790612:during Normal Operation, Pressure Switches PS-1-81 a & B & PS-1-91 a & B Setpoints Exceeded Tech Specs by 3-15 Psig. Caused by Model B2T-A12SS Switches Drifting | | | 05000296/LER-1979-008-03, /03L-0 on 790627:no Speed Indication Noted on Reactor Core Isolation Coolant.Caused by Broken Wires to Magnetic Pickup EG-M Box.Wires Repaired | /03L-0 on 790627:no Speed Indication Noted on Reactor Core Isolation Coolant.Caused by Broken Wires to Magnetic Pickup EG-M Box.Wires Repaired | | | 05000260/LER-1979-008, Forwards LER 79-008/01T-0 | Forwards LER 79-008/01T-0 | | | 05000296/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000296/LER-1979-009-03, /03L-0 on 790717:hydrogen Ignition Damaged HEPA Filters.Caused by Improper Offgas Recombiner Preheater Operation.Sys HEPA Filters & Charcoal Bed Inspected.Three Filters Replaced.Procedures Will Be Revised | /03L-0 on 790717:hydrogen Ignition Damaged HEPA Filters.Caused by Improper Offgas Recombiner Preheater Operation.Sys HEPA Filters & Charcoal Bed Inspected.Three Filters Replaced.Procedures Will Be Revised | | | 05000260/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000296/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | |
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