LER-1978-056, Forwards LER 78-056/01T-0 |
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i Commonwel Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920
- November 1, 1978 BBS Ltr. #78-1443 James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report //78-056/0lT-O, Docket 11050-237 is hereby suomitted to your office in accordance with Dresden Nuclear Power Station Technical Specification 6.6.B.l.(b), operation of the unit or affected systems when any parameter or operation suoject to a limiting condition is less conservative than the least conservative aspect of the limiting condition for operation estaolished in the technical specifications.
Dresden BBS/deo Enclosure cc:
Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC
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{7*771 LICENSEE EVENT REPOf1T U.-UCL,:;\\H REGULATOl->Y COMl1111:0:510N CON TR 0 L BLOCK: l.__.____.__~_._-.____,l Q 1
6 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION!
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I I I LID I RI s I 2101 0 I 0 I -10 I 0 I 0 I 0 I 0 I 0 I 0 I 0 101 4 I 1 I ] I i I ] 101 I I Gt.
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9 LICE.NSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPC:
- .JO 57 CAT 58 CON'T
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- ~~~~; L1.1©.I o I s I o I o I o I 2 I 3 I 7 101 1 I o I 1 I 2 I z I a IG) I 1 I 1 I a I, I 1 I a I G) 60 61 DOCKET NUMaEA 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION~ND PROBABLE CONSEQUENCES@
I While performing quarterly Surv. DIS 1600-3, Diff. Press. Sw. !sol. Valve for DPIS 2-1622A was found closed.
DPIS 2-1622 A monitors press. betwee.n Torus and Rx. Bld. anq
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is calibrated to trip open at -12.5 +/- 1 in. H20 increasing *. Isolation valvemay hav~
[Q]1J been left closed during previous surv. on 7/13/78.
Safety significance minimal wbile I*
remaining vacuum sw. 2-1622B was operable to actuate redundant vacuum breaker.
10/1/78, redundant vacuum breaker was inoperable for approx. 8 hrs. to replace
- c j 8 I fuse F-16 on panel 902-3.
No previous similar events.
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19 VALVE SUBCODE
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32 80 ACT:ON FUTURE EFFECT SHUT:JC'V'iN ATTACHMENT TA~E'~
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47 44 I Cause unknown.
Surv. DIS 1600-3 requires isolation valve to be opened slowly upon completion of surv.
DIS 1600-3 has been revised to require Inst. Mech. to sign data sheet upon valving isol. valve back into service.
For 90 days, IM supervisors will visually examine "AS LEFT" position of all critical non-indicating safety OITI IL-~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
o:ID I related valves, which are repositioned during surveillances.
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10 12 11 44 ACTIVITY CONTENT
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ATTACHJ1ENT TO LICENSEE EVENT REPORT 78-056/0lT-0 COMHONWEALTH EDISON COHPANY (CWE)
DRESDEN UNIT -2 (IJ.DRS-2)
DOCKET II 050-237 While performing quarterly surveillance DIS 1600-3, the differential pressure switch isolation valve for DPIS 2-1622A was found closed.
The Diff~rential Pressure Switch is designed to monitor theAP between the Torus and Reactor Building and is calibrated to trip open at -12.5 +/- 1 inch n2o vacuum increasing.
Technical Specification 3.7.3.a limits the maximum negativeAP referenced to Torus at -13.7 inches H2o. At -12.5 +/- 1" H20 increasing vacuum, either AO 2-1601-20A is opened by switch DPIS 2-1622A or AO 2-1601-20B opens in response to DPIS 2-1622B (both vacuum breaker valves arranged in parallel).
This relieves the torus negative pressure from the.reactor building.
All trip setpoints in the surveillance were found within the Dresden Tech Spec Limits.
However,** prior to the surveillance the isolation valve upstream of Differential Pressure Switch 2-1622-A, was found closed which caused the switch to be inoperable. It is assumed that the isolation valve was left closed after completion of the previous quarterly surveillance on 7/13/78.
The safety consequence was minimal while the remaining Pressure Suppression to Rx Building Vacuum Switch 2-1622B and vacuum breaker A02-1601-20B were operable.
On 10/1/78, the A0-2-1601-20B valve was also rendered inoperable for approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, however, to replace Fuse F-16 on panel 902-.3.
. During that period, vacuum protecti.on was not available for the torus.
DIS 1600-3 had already correctly contained a step requiring the instrument isolation valve to be opened slowly upon completion of the surveillance.
However, to provide better assurance that the step is completed, DIS 1600-3 has been additionally modified to require the Instrument Maintenance Mechanic assigned to the surveillance to sign the data sheet upon valving the switches back into service.
In addition for the next 90 days an Instrument Maintenance Supervisor will visually examine the "As Left" position of all critical non-indicating Safety-Related valves which are repositioned during instrument surveillances and similarly co-sign each associated surveillance upon its completion.
The Pressure Suppression to Rx Building Vacuum Switches will continue to be tested quarterly to ascertain compliance with the Technical Specifications.
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| 05000249/LER-1978-001, /03L-0 for Dresden 3 Regarding the Discovery IRM Nos. 15 and 16 to Trip at 109% | /03L-0 for Dresden 3 Regarding the Discovery IRM Nos. 15 and 16 to Trip at 109% | | | 05000237/LER-1978-002-01, /01T-0:on 780105,during Normal operation,locked- Open Suction Valve to Standby Liquid Injection Pumps Were Found Closed.Cause Unknown.Monthly Verification Has Been Added to Surveillance DOS 1100-1 | /01T-0:on 780105,during Normal operation,locked- Open Suction Valve to Standby Liquid Injection Pumps Were Found Closed.Cause Unknown.Monthly Verification Has Been Added to Surveillance DOS 1100-1 | | | 05000249/LER-1978-002, /03L-0 for Dresden 3 Regarding the Failure of MO-3-1501-5C to Reopen While Performing DOS 1500-1. the Motor Oper. Suction Valve to C LPCI Pp. Closed But Could Not Be Reopened from Control Room | /03L-0 for Dresden 3 Regarding the Failure of MO-3-1501-5C to Reopen While Performing DOS 1500-1. the Motor Oper. Suction Valve to C LPCI Pp. Closed But Could Not Be Reopened from Control Room | | | 05000249/LER-1978-003, /01T-0 for Dresden 3 Regarding Discovery of Containment Valve Leakages in Excess of Technical Specification 4.7.A Limits | /01T-0 for Dresden 3 Regarding Discovery of Containment Valve Leakages in Excess of Technical Specification 4.7.A Limits | | | 05000237/LER-1978-003, /03L-0 for Dresden, Unit 2 Re Inadequacies in the Implementation of Administrative or Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection Systems | /03L-0 for Dresden, Unit 2 Re Inadequacies in the Implementation of Administrative or Procedural Controls Which Threaten to Cause Reduction of Degree of Redundancy Provided in Reactor Protection Systems | | | 05000237/LER-1978-004-01, T-0 for Dresden, Unit 2 Re Improper 125V DC Cable Separation | T-0 for Dresden, Unit 2 Re Improper 125V DC Cable Separation | | | 05000249/LER-1978-005, /03L-0 for Dresden 3 Regarding the Discovery of a Pin Hole Leak in Minimum Flow Line from 3B Reactor Feedwater Pump Line 3-3205B-6 | /03L-0 for Dresden 3 Regarding the Discovery of a Pin Hole Leak in Minimum Flow Line from 3B Reactor Feedwater Pump Line 3-3205B-6 | | | 05000237/LER-1978-005, /03L-0 for Dresden Unit 2 Regarding the Receipt of a Torus High/Low Level Alarm as a Result of Torus Level Transmitter Instrument Drift | /03L-0 for Dresden Unit 2 Regarding the Receipt of a Torus High/Low Level Alarm as a Result of Torus Level Transmitter Instrument Drift | | | 05000249/LER-1978-006, /03L-0 for Dresden 3 Regarding the Discovery of Vacuum Breaker 1601-32F Binding | /03L-0 for Dresden 3 Regarding the Discovery of Vacuum Breaker 1601-32F Binding | | | 05000010/LER-1978-007, Cancelled | Cancelled | | | 05000249/LER-1978-007, /03L-0 for Dresden 3 Regarding Dis 2300-6 HPCI Area Temperature SW 2371 a Tripped at 284.3 Degrees Fahrenheit | /03L-0 for Dresden 3 Regarding Dis 2300-6 HPCI Area Temperature SW 2371 a Tripped at 284.3 Degrees Fahrenheit | | | 05000249/LER-1978-009-01, /01X-1 on 780320:Cracks Found on end-to-pipe Weld on CRD Return Line.Caused by Intermittent to Low Cooling Water Flow Leaving the CRD Nozzle.Pipe Was Removed & Replaced. (Encl to 7809180035) | /01X-1 on 780320:Cracks Found on end-to-pipe Weld on CRD Return Line.Caused by Intermittent to Low Cooling Water Flow Leaving the CRD Nozzle.Pipe Was Removed & Replaced. (Encl to 7809180035) | | | 05000010/LER-1978-009, Cancelled | Cancelled | | | 05000249/LER-1978-009, /01T-0 for Dresden 3 Regarding an Ultrasonic Inspection of the Safe End-To-Pipe Weld on the CRD Return Line Revealed Indications Which Suggested Cracking | /01T-0 for Dresden 3 Regarding an Ultrasonic Inspection of the Safe End-To-Pipe Weld on the CRD Return Line Revealed Indications Which Suggested Cracking | | | 05000237/LER-1978-009, /01T-0 for Dresden Unit 2 Regarding an Occurrence of a Conductivity Transient Due to Condensate Demineralizer Resin Introduction Into the Rx Vessel | /01T-0 for Dresden Unit 2 Regarding an Occurrence of a Conductivity Transient Due to Condensate Demineralizer Resin Introduction Into the Rx Vessel | | | 05000249/LER-1978-010, /01T-0 for Dresden 3 Regarding Discovery of 6 Hydraulic Snubbers Nos. 18, 19, 20, and 33 in Unit 3 Drywell and Nos. 1 and 3 in Isolation Condenser Pipeway with Less than Required Amount of Fluid | /01T-0 for Dresden 3 Regarding Discovery of 6 Hydraulic Snubbers Nos. 18, 19, 20, and 33 in Unit 3 Drywell and Nos. 1 and 3 in Isolation Condenser Pipeway with Less than Required Amount of Fluid | | | 05000249/LER-1978-011, /01T-0 for Dresden 3 Regarding Cracks Identified in Cladding of CRD Nozzle Inner Radius and Vessel Wall Beneath Nozzle | /01T-0 for Dresden 3 Regarding Cracks Identified in Cladding of CRD Nozzle Inner Radius and Vessel Wall Beneath Nozzle | | | 05000249/LER-1978-012, /01T-0 for Dresden 3 Regarding Disclosure of One Apparent Crack-Like Indication on the 330 Degrees Feedwater Sparger Along with Several Indications on the CRD Nozzle Thermal Sleeve Retainer | /01T-0 for Dresden 3 Regarding Disclosure of One Apparent Crack-Like Indication on the 330 Degrees Feedwater Sparger Along with Several Indications on the CRD Nozzle Thermal Sleeve Retainer | | | 05000249/LER-1978-013, /01T-0 for Dresden 3 Regarding Setpoints Being Set High by 10% During the Quarterly Scheduled Calibration Dis 1700-1 | /01T-0 for Dresden 3 Regarding Setpoints Being Set High by 10% During the Quarterly Scheduled Calibration Dis 1700-1 | | | 05000249/LER-1978-014, /01T-0 for Dresden 3 Regarding 24/48 Vdc Battery Failure to Pass the Refueling Outage Discharge Test | /01T-0 for Dresden 3 Regarding 24/48 Vdc Battery Failure to Pass the Refueling Outage Discharge Test | | | 05000249/LER-1978-015, /03L-0 for Dresden 3 Regarding Discovery of One Snubber in Drywell to Be Functionally Inoperable by Bench Test During Inspection to Check 10% of All Hydraulic Snubbers During Refueling | /03L-0 for Dresden 3 Regarding Discovery of One Snubber in Drywell to Be Functionally Inoperable by Bench Test During Inspection to Check 10% of All Hydraulic Snubbers During Refueling | | | 05000237/LER-1978-015-03, /03X-1 on 770402:CRD L-5 Uncoupled & Overtraveled When W/Drawn to Pos 48.Caused by Unlatched Inner Filter & Abnormally Long Uncoupling Rod.Procedure Rev & QA Coverage Improved to Prevent Future CRD Uncouplings | /03X-1 on 770402:CRD L-5 Uncoupled & Overtraveled When W/Drawn to Pos 48.Caused by Unlatched Inner Filter & Abnormally Long Uncoupling Rod.Procedure Rev & QA Coverage Improved to Prevent Future CRD Uncouplings | | | 05000249/LER-1978-016, /03L-0 for Dresden 3 Regarding Leakage Through Standby Liquid Control Check Valve 3-1101-15 Exceeding the T.S.4.7.A Limit for Single Valve Leakage of 29.38 Scfh | /03L-0 for Dresden 3 Regarding Leakage Through Standby Liquid Control Check Valve 3-1101-15 Exceeding the T.S.4.7.A Limit for Single Valve Leakage of 29.38 Scfh | | | 05000249/LER-1978-017, /01T-0 for Dresden 3 Regarding an NRC Request That Immediate Action Be Taken to Mitigate the Potential for a Spurious Closure of a Recirculation Loop Suction Valve with a LOCA Occurring Between the Loop Discharge and Suction Va | /01T-0 for Dresden 3 Regarding an NRC Request That Immediate Action Be Taken to Mitigate the Potential for a Spurious Closure of a Recirculation Loop Suction Valve with a LOCA Occurring Between the Loop Discharge and Suction Valves | | | 05000249/LER-1978-018, /03L-0 for Dresden 3 Regarding the Discovery of U3 Diesel Oil Storage Tank at 9000 Gal. Which Is Below the 10000 Gal. Limit Required by Technical Specification 3.9.c | /03L-0 for Dresden 3 Regarding the Discovery of U3 Diesel Oil Storage Tank at 9000 Gal. Which Is Below the 10000 Gal. Limit Required by Technical Specification 3.9.c | | | 05000249/LER-1978-019, /03L-0 for Dresden 3 Regarding the Discovery of Ps 504C and 504D Found to Trip at 403 PSI and 405 PSI Respectively | /03L-0 for Dresden 3 Regarding the Discovery of Ps 504C and 504D Found to Trip at 403 PSI and 405 PSI Respectively | | | 05000237/LER-1978-020, /03X-01 for Dresden, Unit 1 Re Cause of Failure of the Diesel Generator to Start | /03X-01 for Dresden, Unit 1 Re Cause of Failure of the Diesel Generator to Start | | | 05000249/LER-1978-020, /03L-0 for Dresden 3 Regarding Discovery of Ps 3-203-3C Tripped at 1148 PSI Rx Pressure Incr | /03L-0 for Dresden 3 Regarding Discovery of Ps 3-203-3C Tripped at 1148 PSI Rx Pressure Incr | | | 05000249/LER-1978-022, /03L-0 for Dresden Unit 3 Regarding Discovery of High Flow Isolation Switches DPIS 261-2C, 261-2N, and 261-2S to Trip at Values Exceeding the Technical Specification Limit | /03L-0 for Dresden Unit 3 Regarding Discovery of High Flow Isolation Switches DPIS 261-2C, 261-2N, and 261-2S to Trip at Values Exceeding the Technical Specification Limit | | | 05000249/LER-1978-023, /01T-0 for Dresden Unit 3 Regarding Source Range Monitors 24 and 21 Being Declared Inoperable on 05/20/1978 | /01T-0 for Dresden Unit 3 Regarding Source Range Monitors 24 and 21 Being Declared Inoperable on 05/20/1978 | | | 05000249/LER-1978-024, /03L-0 for Dresden Unit 3 Regarding the Discovery of PS3-263-53A to Trip at 1178 PSI Which Is Above Technical Specifications | /03L-0 for Dresden Unit 3 Regarding the Discovery of PS3-263-53A to Trip at 1178 PSI Which Is Above Technical Specifications | | | 05000237/LER-1978-025-03, Re While Preforming LPCI and Ccsw Surveillance on Unit 3 Prior to Taking the U-3 D/G Out of Service, a Spike Was Found on the Liquid Process Radiation Monitor for the Service Water Discharge | Re While Preforming LPCI and Ccsw Surveillance on Unit 3 Prior to Taking the U-3 D/G Out of Service, a Spike Was Found on the Liquid Process Radiation Monitor for the Service Water Discharge | | | 05000010/LER-1978-025, Cancelled | Cancelled | | | 05000237/LER-1978-025, /03L-0 for Dresden Unit 3 Regarding Discovery of a Spike on the Liquid Process Radiation Monitor for the Service Water Discharge | /03L-0 for Dresden Unit 3 Regarding Discovery of a Spike on the Liquid Process Radiation Monitor for the Service Water Discharge | | | 05000237/LER-1978-026-03, Re While Performing LPCI Both Indicating Lights Went Out and the Motor Stopped | Re While Performing LPCI Both Indicating Lights Went Out and the Motor Stopped | | | 05000237/LER-1978-027, /03L for Dresden, Unit 2 Re a Sample Taken from Radwaste a WST at 1020 After the Tank Was Filled to 88% | /03L for Dresden, Unit 2 Re a Sample Taken from Radwaste a WST at 1020 After the Tank Was Filled to 88% | | | 05000010/LER-1978-028-03, /03L-0:on 780815,weekly Reactor Protection Sys Functional Operability Test Postponed But Not Rescheduled. Caused by Personnel Error.Personnel re-instructed Re Importance of Scheduled Surveillances.(Encl to 7809260056) | /03L-0:on 780815,weekly Reactor Protection Sys Functional Operability Test Postponed But Not Rescheduled. Caused by Personnel Error.Personnel re-instructed Re Importance of Scheduled Surveillances.(Encl to 7809260056) | | | 05000249/LER-1978-028-03, Re While Performing Surv. Dis 250-1, MSL Hi Flow Isolation Sw. Dpis 3-261-2c Tripped at 117 Psid | Re While Performing Surv. Dis 250-1, MSL Hi Flow Isolation Sw. Dpis 3-261-2c Tripped at 117 Psid | | | 05000237/LER-1978-028, /01X-1 for Dresden, Units 2 and 3 Re NRC Request for Immediate Actions to Be Taken to Mitigate the Potential for a Spurious Closure of a Recirculation Loop Suction Valve with a LOCA Occurring Between the Loop Discharge and Suct | /01X-1 for Dresden, Units 2 and 3 Re NRC Request for Immediate Actions to Be Taken to Mitigate the Potential for a Spurious Closure of a Recirculation Loop Suction Valve with a LOCA Occurring Between the Loop Discharge and Suction Valves | | | 05000010/LER-1978-028, Forwards LER 78-028/03L-0 | Forwards LER 78-028/03L-0 | | | 05000237/LER-1978-029-03, Re Safety Implications Were Minimal Because 1 or More Operable APRMs Per Channel Remained Available as Required by TS 3.2 | Re Safety Implications Were Minimal Because 1 or More Operable APRMs Per Channel Remained Available as Required by TS 3.2 | | | 05000237/LER-1978-030-01, /01X-1 on 780428:During Unit 2 Startup Opers, a LPCI & Core Spray Subsys Were Inadvertantly Rendered Inoper Because Personnel Had Closed LPCI Pump & Discharge Valves on Unit 2 Vice 3.(Encl to 7809180320) | /01X-1 on 780428:During Unit 2 Startup Opers, a LPCI & Core Spray Subsys Were Inadvertantly Rendered Inoper Because Personnel Had Closed LPCI Pump & Discharge Valves on Unit 2 Vice 3.(Encl to 7809180320) | | | 05000237/LER-1978-030, Forwards LER 78-030/01X-1 | Forwards LER 78-030/01X-1 | | | 05000237/LER-1978-031, /03L-0 for Dresden, Unit 2 Re PS-2-1430-1466C Failed to Operate | /03L-0 for Dresden, Unit 2 Re PS-2-1430-1466C Failed to Operate | | | 05000249/LER-1978-032-03, /03L on 780817:room Cooler Fans Failed to Start When Pumps 3B & 3C started.4KV Switchgear 33 & 34 Auxiliary Contacts Were Found Dirty.(Encl to 7809220129) | /03L on 780817:room Cooler Fans Failed to Start When Pumps 3B & 3C started.4KV Switchgear 33 & 34 Auxiliary Contacts Were Found Dirty.(Encl to 7809220129) | | | 05000249/LER-1978-032, Forwards LER 78-032/03L | Forwards LER 78-032/03L | | | 05000237/LER-1978-032, /03L-0 for Dresden, Unit 2 Re During Steady State Operation, Torus to Drywell Vacuum Breaker 2-1601-33E & F Were Found Inoperable During Routine Operability Surveillance | /03L-0 for Dresden, Unit 2 Re During Steady State Operation, Torus to Drywell Vacuum Breaker 2-1601-33E & F Were Found Inoperable During Routine Operability Surveillance | | | 05000010/LER-1978-033, Cancelled | Cancelled | | | 05000237/LER-1978-033, Forwards LER 78-033/03X-1 | Forwards LER 78-033/03X-1 | | | 05000237/LER-1978-033-03, /03X-1 on 780522:during Test Performed on U-2 D/G to Measure Overshoot & Overspeed Setpoint,The Diesel Tripped 4 Times Due to Overspeed Caused by Governor Speed Set Too High | /03X-1 on 780522:during Test Performed on U-2 D/G to Measure Overshoot & Overspeed Setpoint,The Diesel Tripped 4 Times Due to Overspeed Caused by Governor Speed Set Too High | |
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