LER-1982-040, /03L-0:on 820902,short Caused Generator Breakers to Open & Synchronizing Inhibit Timer to Start.Caused by Personnel Short Circuiting Relay During Generator Negative Sequence Relay Testing.Protection Design Reviewed |
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| 3351982040R03 - NRC Website |
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NRC f OAM 384 U.S.NUCLEAM REGULATORY COMMISSION 87 771 LICENSEE EVENT REPORT CCNTRot. SLOCK: l
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$ VENT OESCRtPTt0N ANO PRC8 ASLE CONSECUENCES h ITTTl i At 99% power, while testing a generator trip relay a brief short caused I
- the generator breakers to open and started a synchronizing inhibit timer i
o 3i.i i to start. When the reactor tripped the timer had cycled so transfer of I
gl vital busses (4.16 KV) required OPERABLE by TS 3.8.2.1 to startup power 1
io g i I did not occur. Diesel generators started and loaded properly. Power was j
restored to normal. Due to the transient, iodine buildup (spiking) < ~
,o,,i; occurred. Similar bus loss was LER 79-28. Tenth Iodine spike, See LER 82-38.1 iois i ;
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34 35 36 31 ao el 42 4J 44 41 CAUSE DESCRIPTION AND CORREC.*lvt ACTIONS h 1: 1011 In testino the generator necative secuence relay, relay personnel short I
w I circuited the relay, giving a signal to open the generator breakers. By t
the time the reactor tripped the unit was out of synchronization with 1
gi i,,3i l the grid and the time delay (.17 see) inhibited automatic bus transfer.
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Generator protection design is being reviewed for possible changes.
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Paul Pace (305) 552-3654 94vsospatranEn 8210130562 821004 PDR ADOCK 05000335 S
PDR L
I REPORTABLE OCCURRENCE 335-82-40 LICENSEE EVENT REPORT PAGE 1
-. EVENT DESCRIPTION (Cont)
At approximately 10:28 AM, during normal full power operation, a negative-sequence generator trip relay was inadvertently actuated causing opening of the main generator oil circuit breakers (OCB's),
a separation from the grid, and a turbine trip on over speed. The loss of load caused the turbine and reactor to trip, however since the OCB's had already opened and the unit was out of synchronization with
'the grid, the transfer to the startup switchgear for offsite power could not occur. The diesel generators automatically loaded to provide AC power to the plant vital loads. An Unusual Event was declared at approximately 10:35 AM.
Offsite power and normal plant status was restored at approximately 10:46 AM..
During the return to power the dose equivalent iodine (DEQ) exceeded T.S. 3.4.8.a limit of 1.0 uCi/gm DEQ I-131.
The DEQ iodine was first measured above the limit at 1345 on 9-2-82 and remained above the limit for approximately 15.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The attached sheets contain information required by T.S.
3.4.8.d.
The health and safety of the public was not affected by this event.
CAUSE DESCRIPTION During a determination of the minimum voltage required for the negative sequence relay to actuate, Systems Protection (Relay) personnel short circuited a resistor and relay in the negative sequence relay circuitry.
The negative sequence relay was actuated for a short duration causing the main generator OCB's to open.. The subseq"ent generator lockout caused by the turbine overspeed trip would normally provide a fast transfer of onsite electrical loads from the auxiliary transformers to the startup transformers. Since the OCB's were already open for greater than 170 milli seconds (design circuitry time delay for pro-tection against electrical loading out of synchronization), the automatic transfer did not occur.
After an extended period of power operation with a nominal level of fuel leakage, a reactor scram from full power was a sufficient transient to cause iodine build-up (iodine spiking phenomenon). The DEQ I-131 level decreased to below 1.0 uC1/gm after 15.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and to nominal levels thereafter.
e
.o REPORTABLE OCCURRENCE 3'35-82-40' LICENSEE EVENT. REPORT
- - 2 Page"2
- - SUPPLE >tENTARY INF0PJfATION TECHNICAL SPECIFICATION REPORT DOSE EQUIVALENT IODINE 1.
Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the Eirst sample in which the limit was exceeded.
Average Reactor Average Reactor Average Reactor Time Power 8/31/82 Power 9/1/82 Power 9/2/82 0000 99.23 99.23 0100 99.18 99.15 0200 99.20 99.15 0300
- - 99.23 99.15 0400 99.28 99.15 0500 99.26
'99.18 0600 99.18 99.20 0700-99.23 99.18 0800 99.20-99.20 0900 99.20 99.26 1000 99.20 99.26 1100 2 --
99.18 1200 99.28 1300 99.30 99.30 1400 99.09 99.30 1500
'99.20 99.30 1600 99.20 99.23 1700 99.18 99.20 1800 99.18 99.23 1900 99.18 99.23 2000 99.20 99.20 2100 99.23 99.23 2200 99.23 99.20 2300 99.28 99.20 2.
Fup_1 ikarniin by Core Region See Attachment "A" i
3.
Cleanup Flow History starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample
_in which the limit was exceeded.
Tine Flow Rate (GPl!)
Flow Rate (GP}!)
Flow Rate (CP)f)
B/31/82 9/1/82 9/2/82 0000 87 86 0100 87 86 0200 87 86 0300 87 86 0400 87 86 0500 S6 86 0500 86 86 L
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. REPORTAlit.E OCCt!RRENCE 335-82-40.
I.ICENSEE EVE!.'T REPORT
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Page.3 3.-
Continued Flow Rate (GPM)
Flow Rate (GPM) _
Flow Rate (CPM)
Tim S/31/32:
9/1/82 8/2/82 0700 86 86
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87 86 0800 0900 r
87 86 1000 87 86 87 88 (Trip) 1100 87 88 1200 1300 92 87 86 1400 44 87 1500 83 87 1600 86 87 1700 86 87 1800 90 87 1900 88 87 2000 87 87 2100 87 86 2200 87 87 y
2300 87 87 p
4.
Historv of Degassing Operation, if_ anv. starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceedM.
There vare ndlegassing operations during the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period pri'ar to exceeding the dose equivalent iodine limit.
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5.
The Time _ duration when the specific _ activity of the primarv coolant f
exceeded 1.0 uci/gm dose equivalent I-131.
Data Time.
DEQ I-131 (uci/gn) 9/2/32
- d500, 1.14 E-01 9/2/82 1345 1.68 E 00 9/2/82 1730 1.75 E 00 y
9/2/82 2115 1.46 E 00 9/3/82 0115.
1.24 E 00 9/3/82
.0515 8.69 E-01 The daae equivalcat I-131 exceeded the limit for a period of approxinately 15.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
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NUMBER OF ASSDiBLIES.
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E 3.03 40 29546.9..
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| 05000335/LER-1982-001-03, /03L-0:on 820107,during Refueling Outage & Subsequent Startup Period,Radiation Levels Exceeded Setpoint Rendering Channel 7 Inoperable.Caused by Misunderstanding of Surveys.Training Instituted | /03L-0:on 820107,during Refueling Outage & Subsequent Startup Period,Radiation Levels Exceeded Setpoint Rendering Channel 7 Inoperable.Caused by Misunderstanding of Surveys.Training Instituted | | | 05000335/LER-1982-001, Forwards LER 82-001/03L-0 | Forwards LER 82-001/03L-0 | | | 05000335/LER-1982-002, Forwards LER 82-002/03L-0 | Forwards LER 82-002/03L-0 | | | 05000335/LER-1982-002-03, /03L-0:on 820121,subcooled Margin Monitor Instrument Declared Out of Svc.Cause Not Determined.Monitor Began Operating Properly During Troubleshooting | /03L-0:on 820121,subcooled Margin Monitor Instrument Declared Out of Svc.Cause Not Determined.Monitor Began Operating Properly During Troubleshooting | | | 05000335/LER-1982-003, Forwards LER 82-003/03L-0 | Forwards LER 82-003/03L-0 | | | 05000335/LER-1982-003-03, /03L-0:on 820109,control Room Air Intake Chlorine Monitor CL2-SM-1A Failed & Attempts to Reset Were Unsuccessful.Cause Not Determined.Detector Flushed W/ Demineralized Water & Reset | /03L-0:on 820109,control Room Air Intake Chlorine Monitor CL2-SM-1A Failed & Attempts to Reset Were Unsuccessful.Cause Not Determined.Detector Flushed W/ Demineralized Water & Reset | | | 05000335/LER-1982-004-03, /03L-0:on 820110,at 94% Power,Wide Range Nuclear Instrumentation Channel C Failed.Cause of Failure of Gamma Metrics RCS 200 Neutron Flux Monitor Cannot Be Determined During Power Operation Due to Inaccessibility | /03L-0:on 820110,at 94% Power,Wide Range Nuclear Instrumentation Channel C Failed.Cause of Failure of Gamma Metrics RCS 200 Neutron Flux Monitor Cannot Be Determined During Power Operation Due to Inaccessibility | | | 05000335/LER-1982-004, Forwards LER 82-004/03L-0 | Forwards LER 82-004/03L-0 | | | 05000335/LER-1982-005, Forwards LER 82-005/03L-0 | Forwards LER 82-005/03L-0 | | | 05000335/LER-1982-005-03, /03L-0:on 820204 & 14,during Full Power Operation, Two Out of Three Control Room Air Conditioning Units Out of Svc Simultaneously.Caused by Stuck Dampers & Faulty Linkage & Valves.Units Repaired & Returned to Svc | /03L-0:on 820204 & 14,during Full Power Operation, Two Out of Three Control Room Air Conditioning Units Out of Svc Simultaneously.Caused by Stuck Dampers & Faulty Linkage & Valves.Units Repaired & Returned to Svc | | | 05000335/LER-1982-006, Forwards LER 82-006/03L-0 | Forwards LER 82-006/03L-0 | | | 05000335/LER-1982-006-03, /03L-0:on 820208,small Bore Piping Mechanical Snubber 146 Found Locked Up.Cause Not Determined.Snubber Replaced.Complete Rept of Snubber Insp Available in Response to IE Bulletin 81-01 | /03L-0:on 820208,small Bore Piping Mechanical Snubber 146 Found Locked Up.Cause Not Determined.Snubber Replaced.Complete Rept of Snubber Insp Available in Response to IE Bulletin 81-01 | | | 05000335/LER-1982-007-03, /03L-0:on 820218,while at 98% Power,Heater 6B2 in Ventilation Sys Which Provides Humidity Control Found Inoperable.Caused by Defective Thermocouple Amplifier Which de-energized Heater.Amplifier Repaired & Heater Retested | /03L-0:on 820218,while at 98% Power,Heater 6B2 in Ventilation Sys Which Provides Humidity Control Found Inoperable.Caused by Defective Thermocouple Amplifier Which de-energized Heater.Amplifier Repaired & Heater Retested | | | 05000335/LER-1982-007, Forwards LER 82-007/03L-0 | Forwards LER 82-007/03L-0 | | | 05000335/LER-1982-008-03, /03L-0:on 820226,during Surveillance Testing, MV1403 (Block Valve for Power Operated Relief Valve) Would Not Shut.Cause Will Be Investigated During Next Shutdown | /03L-0:on 820226,during Surveillance Testing, MV1403 (Block Valve for Power Operated Relief Valve) Would Not Shut.Cause Will Be Investigated During Next Shutdown | | | 05000335/LER-1982-008, Forwards LER 82-008/03L-0 | Forwards LER 82-008/03L-0 | | | 05000335/LER-1982-009, Forwards LER 82-009/03L-0 | Forwards LER 82-009/03L-0 | | | 05000335/LER-1982-009-03, /03L-0:on 820317,while Operating at 98% Power, Weekly Surveillance of Core Barrel Movement Required by Tech Spec 3.4.11 Was Not Performed.Surveillance Was Inadvertently Overlooked.Personnel Instructed to Perform Surveillance | /03L-0:on 820317,while Operating at 98% Power, Weekly Surveillance of Core Barrel Movement Required by Tech Spec 3.4.11 Was Not Performed.Surveillance Was Inadvertently Overlooked.Personnel Instructed to Perform Surveillances | | | 05000335/LER-1982-010-03, /03L-0:on 820221,during Surveillance of Hot Shutdown Panel,Steam Generator Level Indicator FP 9009 Showed No Indication.Caused by Sticking Meter Movement of Sigma Model 922-00E.Sys Repaired & Returned to Operation | /03L-0:on 820221,during Surveillance of Hot Shutdown Panel,Steam Generator Level Indicator FP 9009 Showed No Indication.Caused by Sticking Meter Movement of Sigma Model 922-00E.Sys Repaired & Returned to Operation | | | 05000335/LER-1982-010, Forwards LER 82-010/03L-0 | Forwards LER 82-010/03L-0 | | | 05000335/LER-1982-011-03, /03L-0:on 820309,1A Diesel Generator Failed to Start for Surveillance.Caused by Failed 1A Diesel Generator Speed Switch (A16).Switch Replaced W/Dynalco Model SS2396 | /03L-0:on 820309,1A Diesel Generator Failed to Start for Surveillance.Caused by Failed 1A Diesel Generator Speed Switch (A16).Switch Replaced W/Dynalco Model SS2396 | | | 05000335/LER-1982-011, Forwards LER 82-011/03L-0 | Forwards LER 82-011/03L-0 | | | 05000335/LER-1982-012-03, /03L-0:on 820410,while Operating at 99% Power,W/ Charging Pump B Out of Svc,Charging Pump C Exhibited Low Flow & Declared Inoperable.Caused by Faulty Pump Internal Suction & Discharge Valves.Valves Replaced | /03L-0:on 820410,while Operating at 99% Power,W/ Charging Pump B Out of Svc,Charging Pump C Exhibited Low Flow & Declared Inoperable.Caused by Faulty Pump Internal Suction & Discharge Valves.Valves Replaced | | | 05000335/LER-1982-012, Forwards LER 82-012/03L-0 | Forwards LER 82-012/03L-0 | | | 05000335/LER-1982-013, Forwards Updated LER 82-013/03X-1 | Forwards Updated LER 82-013/03X-1 | | | 05000335/LER-1982-014, Forwards LER 82-014/03L-0 | Forwards LER 82-014/03L-0 | | | 05000335/LER-1982-014-03, /03L-0:on 820424,during Power Operation,Rcs Leakage Exceeded Limit of 10 Gpm.Caused by Failed Body to Bonnet Gasket on V-1237 Pressurizer mini-spray Valve.Valve Isolated to Stop Leakage.Gasket Replaced | /03L-0:on 820424,during Power Operation,Rcs Leakage Exceeded Limit of 10 Gpm.Caused by Failed Body to Bonnet Gasket on V-1237 Pressurizer mini-spray Valve.Valve Isolated to Stop Leakage.Gasket Replaced | | | 05000335/LER-1982-015-03, /03L-0:on 820423,during Normal Full Power Operation,Radiation Channel MD Failed Routine Surveillance. Caused by Failure of action-PAK Model 4300-159 E to I Converter.Instrument Repaired | /03L-0:on 820423,during Normal Full Power Operation,Radiation Channel MD Failed Routine Surveillance. Caused by Failure of action-PAK Model 4300-159 E to I Converter.Instrument Repaired | | | 05000335/LER-1982-015, Forwards LER 82-015/03L-0 | Forwards LER 82-015/03L-0 | | | 05000335/LER-1982-017-03, /03L-0:on 820506,dose Equivalent I-131 Exceeded Tech Spec Limit.Caused by 135 Days of Continuous Power Operation.Limit Exceeded for 28-h,19 Minutes | /03L-0:on 820506,dose Equivalent I-131 Exceeded Tech Spec Limit.Caused by 135 Days of Continuous Power Operation.Limit Exceeded for 28-h,19 Minutes | | | 05000335/LER-1982-017, Forwards LER 82-017/03L-0 | Forwards LER 82-017/03L-0 | | | 05000335/LER-1982-018-03, /03L-0:on 820503,reactor Protection Sys Steam Generator Level Channel Bypassed During Power Operation Due to Erroneous Indication of High Level on Channel C.Caused by Instrument Root Isolation Valve Packing Leak.Valve Repack | /03L-0:on 820503,reactor Protection Sys Steam Generator Level Channel Bypassed During Power Operation Due to Erroneous Indication of High Level on Channel C.Caused by Instrument Root Isolation Valve Packing Leak.Valve Repacked | | | 05000335/LER-1982-018, Forwards LER 82-018/03L-0 | Forwards LER 82-018/03L-0 | | | 05000335/LER-1982-020, Forwards LER 82-020/03L-0 | Forwards LER 82-020/03L-0 | | | 05000335/LER-1982-020-03, /03L-0:on 820605,after Short Reduction in Power by 5% While Increasing Power,Dose Equivalent Iodine Exceeded Tech Spec 3.4.8 Limit for 8-h.Caused by Reduction in Power Inducing Iodine Buildup.Nominal Level Reached in 10-h | /03L-0:on 820605,after Short Reduction in Power by 5% While Increasing Power,Dose Equivalent Iodine Exceeded Tech Spec 3.4.8 Limit for 8-h.Caused by Reduction in Power Inducing Iodine Buildup.Nominal Level Reached in 10-h | | | 05000335/LER-1982-022-03, /03L-0:on 820609,subcooled Margin Monitor Failed to Operate.Caused by 1A2 Tc Input Transmitter Failure.Lead from Transmitter Lifted & Subcooled Monitor Returned to Svc on 820610 | /03L-0:on 820609,subcooled Margin Monitor Failed to Operate.Caused by 1A2 Tc Input Transmitter Failure.Lead from Transmitter Lifted & Subcooled Monitor Returned to Svc on 820610 | | | 05000335/LER-1982-022, Forwards LER 82-022/03L-0 | Forwards LER 82-022/03L-0 | | | 05000335/LER-1982-023-99, /99X-0:on 820614,fire Detection Instrument Channels 2.01.13,2.01.14 & 2.02.13 in Containment at 18-ft Level & Below Alarmed.Cause Not Determined.Instrument Repairs Will Be Done When Shutdown Allows Accesibility | /99X-0:on 820614,fire Detection Instrument Channels 2.01.13,2.01.14 & 2.02.13 in Containment at 18-ft Level & Below Alarmed.Cause Not Determined.Instrument Repairs Will Be Done When Shutdown Allows Accesibility | | | 05000335/LER-1982-023, Forwards LER 82-023/99X-0 | Forwards LER 82-023/99X-0 | | | 05000335/LER-1982-024, Forwards LER 82-024/03L-0 | Forwards LER 82-024/03L-0 | | | 05000335/LER-1982-024-03, /03L-0:on 820616,diesel Generator 1B Failed Due to Loss of Oil Pressure During Turbocharger Coastdown.Caused by Failed Turbocharger Unit.Turbocharger & Oil Pump Replaced | /03L-0:on 820616,diesel Generator 1B Failed Due to Loss of Oil Pressure During Turbocharger Coastdown.Caused by Failed Turbocharger Unit.Turbocharger & Oil Pump Replaced | | | 05000335/LER-1982-025-03, /03L-0:on 820616,routine Surveillance Revealed That Pressurizer Safety Valve V-1200 Acoustic Flow Position Indicator Inoperable.Cause Unknown.Indicator Will Be Repaired or Replaced During Next Outage | /03L-0:on 820616,routine Surveillance Revealed That Pressurizer Safety Valve V-1200 Acoustic Flow Position Indicator Inoperable.Cause Unknown.Indicator Will Be Repaired or Replaced During Next Outage | | | 05000335/LER-1982-025, Forwards LER 82-025/03L-0 | Forwards LER 82-025/03L-0 | | | 05000335/LER-1982-026-03, /03L-0:on 820622,one of Four Redundant 120-volt Ac Instrument Power Buses Was Lost When Output Breaker 1A Static Inverter Opened.Cause Unknown.Oscillator Circuit Board Replaced | /03L-0:on 820622,one of Four Redundant 120-volt Ac Instrument Power Buses Was Lost When Output Breaker 1A Static Inverter Opened.Cause Unknown.Oscillator Circuit Board Replaced | | | 05000335/LER-1982-026, Forwards LER 82-026/03L-0 | Forwards LER 82-026/03L-0 | | | 05000335/LER-1982-027-03, /03L-0:on 820715,dc Ground Isolated on Solenoid Valve V6554.Caused by Valve Failing to Properly Indicate Position Due to Shorted Terminal Lugs on Terminal Board of Valve.Lugs Reconnected & Valves Returned to Svc | /03L-0:on 820715,dc Ground Isolated on Solenoid Valve V6554.Caused by Valve Failing to Properly Indicate Position Due to Shorted Terminal Lugs on Terminal Board of Valve.Lugs Reconnected & Valves Returned to Svc | | | 05000335/LER-1982-027, Forwards LER 82-027/03L-0 | Forwards LER 82-027/03L-0 | | | 05000335/LER-1982-028, Forwards LER 82-028/03L-0 | Forwards LER 82-028/03L-0 | | | 05000335/LER-1982-028-03, /03L-0:on 820624,while Performing Periodic Control Element Assembly Exercise,Control Element Assembly 54 Dropped to Full Insertion.Cause Not Determined | /03L-0:on 820624,while Performing Periodic Control Element Assembly Exercise,Control Element Assembly 54 Dropped to Full Insertion.Cause Not Determined | | | 05000335/LER-1982-029, Forwards LER 82-029/03L-0 | Forwards LER 82-029/03L-0 | |
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