LER-1980-042, /01T-0:on 800707,w/Mayflower 500 Kv Transmission Line Out of Svc,Mabelvale 500 Kv Tripped on Ground Fault. Caused by Ground Fault & Resulting Overload |
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8 60 61 DoCEET Nuuttp in8 WJ EvtNT DATg la 7b NF,oHT DATE 80 EVENT DESCRIPTION AND PROS ABLE CONSEOUENCES h l o 121 I With the Mavflower 500KV transmission line out of service & the unit 00-1 1 o 131 I eratino at 91% cower: the 500KV Mabelvale line trioned on a ground faults t o i. i i the 500KV Fort Smith line opened on the Fort Smith end, isolating all but in isi i the two 161 KV transmission lines from the AUO switchyard.
The Morrilton 1o1611 East 161 KV line triooed due the resultant overload. leaving one soc.rce I lo til I of offsite power - Russellville East 161KV ine supplying SU transformer l
- 2, which remained operable throughout the transient.
No similar occur-ionii rences.
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40 en 42 43 CAUSF DESCRFTION AND CORRECflVE ACTIONS Laloti Transmission lines tripped due to around fault and resulting overload.
i i, ii 1 l The Reactor & Turbine-Generator subs _eauently triooed.
The Emergency Dies sii2i i sel Generators started and loaded per design and remained in service un-I m i til Lock-out relays were reset and 500KV bus re-energized when unit loada i s i. i i were transferred manually to startup tr.ansformers.
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- - l-Reportable Occurrence Report No.
50-368/80-042/01T
- 2.. Report Date:
7/7/80 3.
Occurrence Date:
6/24/80
- 4 Facility:
Arkansas Nuclear-0ne - Unit Two Russellville, Arkansas 5.
Identification of Occurrence:
' Conditions arising from natural events, that as a resalt of the event (partial loss of offsite power due to transmission l'ne failure) require a unit shutdown & operation of safety systems or oth :r protective measures (ES bus voltage restored by automatic action of Dnergency Diesel Genera-tors). Reportable per T.S.3.8.1 and T.S.6.9.1.8.g.
6.
Conditions Prior to Occurrence:
Steady-State Power X
Reactor Power __2360 MWth Hot Standby Net Output
___ 840 Mwe Cold Shutdown Perecnt of Full ower 91% %
Refueling Shutdow'n Load Changes During Routine Routine Startup Operation Routine Shutdown Operation Other ('specify)
Steady state power operation with the Mayflower 500KV line (one of three 500KV lines) out of service.
7.
Description of Occurrence:
At 1540 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.8597e-4 months <br />, switchyard circuit breakers _ tripped apparently due to a ground fault ' isolating' the Mabelvale 500KV line. The unit's generation, along with Unit I's generation, was' transferred to the Fort Smith 500KV
- - line which tripped open at the Fort Smith end, as a result of feeder overl oad. The Mabelvsle line became available again, but did not close into the ANO switchyard '500KV ring bus because of-inability -to sync-
. check.
Unit II tripped from CPC generated DIER trips based on decreasing RC Pump. speed, 'apparently ~ induced from -frequency and voltage upsets 'oc-curringLon the: system grid.. The Morrilton East ^161KV line tripped on overload leaving _ only the 500KV bus segment-(Unit I generator output)
' feeding the autotransformer and the Russ.lv'lle _ East line carrying power, generation.
Startup transformer y renained energized from the
. autotransformer, and ~ startup transformer #2' remained tied to the 161KV.
_ bus. The ' unit's-4160 volt auxiliaries were transferred to startup ec
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'f Reportable Occurrence No. 50-368/80-042/01T Description of Occurrence (Cont.):
~
- - transformer #3, while the 6900 volt buses were switched to SU#3 prior-
- - to the~ occurrence. Under voltage rel_ays on the 6900 volt buses -oper-ated, shedding the Reactor Coolant Pumps and Circulating Water Pump loads. The 4160 volt auxiliary circuit indicated low voltage, strip--
ping the buses 'from startup transformer #3.
Subsequently, the auto-transformer bank received lockout relay _ operation from an apparently
~
faulted relay, resulting in lockout relay operation of startup trans-former #3 (and Unit I's startup transformer #1), placing both units r
witho_ut auxiliary bus voltage. At.this point, the switchyard buses
. were deenergized except for the Russellville East' tie to startup transformer.#2 (one source of offsite power), which remained energized.
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t D-9 Reportable Occurrence Report No.
50-368/80-042/01T 8.
Designation of Apparent Cause of Occurrence:
Design Pro'cedure Manufacture Unusual Service Condition X
Including Environmental Installation /
Construction Component Failure X
(See Failure Data)
Operator Other (specify)
Occurrence was. caused by a loss of offsite transmission and aggravated by the resultant grid degradation.
9.
Analysis or Occurrence:
Coincident with the shedding of the 6900 volt and 4160 volt buses from startup transformer #3, Emergency Diesel Generators, 2DG-1 & 2DG-2, auto-started on 2A3 and 2A4 bus under voltage.
The Unit's ES buses were
- - reenergized and normal' loads were sequenced on.
Approximately four min-utes later the 2A1 and 2H1 buses were energized from startup transformer
- 2. At about 55 minutes later,'all house loads were transferred back to startup transformer #3 and both Emergency Diesel Generators were secured.
The Reactor Coolant. Pumps were: sequenced on. The reactor was fed by natural circulation for a total of approximately 66 minutes.
The unit was taken to Cold Shutdown conditions for Reactor Coolant Pump Seal re-placement.
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Reportable Occurrence Report No.
50-368/80-042/01T f
10.
Corrective Action
i AP&L Transmission line fault was cleared.
No plant site corrective action required as all plar:t s vstems operated per design.
11.
Failure Data:
Not applicable.
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| 05000368/LER-1980-001-03, /03L-0:on 800107,during Mode 1 Operation, Containment Isolation Valve 25V-5876-2 Failed to Close After Taking Samples from Safety Injection Tanks for Boron Analysis.Caused by Faulty Valve Position Indication | /03L-0:on 800107,during Mode 1 Operation, Containment Isolation Valve 25V-5876-2 Failed to Close After Taking Samples from Safety Injection Tanks for Boron Analysis.Caused by Faulty Valve Position Indication | | | 05000313/LER-1980-001-03, /03L-0:on 800114,while Performing Surveillance Test,Hydrogen Purge Supply Isolation Valve CV-7444 Failed to Close.Caused by Oxidation on Torque Switch Contacts, Resulting in High Resistance to Closure.Contacts Cleaned | /03L-0:on 800114,while Performing Surveillance Test,Hydrogen Purge Supply Isolation Valve CV-7444 Failed to Close.Caused by Oxidation on Torque Switch Contacts, Resulting in High Resistance to Closure.Contacts Cleaned | | | 05000368/LER-1980-002-03, /03L-0:on 800110,during Mode 1 Operation,Core Protection Calculator C Failed,Resulting in DNBR & Linear Power Density Trips in Channel C Primary Power Sys.Cause Undetermined.Sys Restarted During Failure Analysis | /03L-0:on 800110,during Mode 1 Operation,Core Protection Calculator C Failed,Resulting in DNBR & Linear Power Density Trips in Channel C Primary Power Sys.Cause Undetermined.Sys Restarted During Failure Analysis | | | 05000313/LER-1980-002-03, /03L-0:on 800114,while Performing Surveillance Test,Hydrogen Purge Supply Isolation Valve CV-7448 Failed to Close.Caused by Oxidation on Torque Switch Contacts.Contacts Cleaned | /03L-0:on 800114,while Performing Surveillance Test,Hydrogen Purge Supply Isolation Valve CV-7448 Failed to Close.Caused by Oxidation on Torque Switch Contacts.Contacts Cleaned | | | 05000313/LER-1980-003-01, /01T-0:on 800121,while at Cold Shutdown,Boron Buildups Identified on Loop B of Reactor Bldg Spray & Piping.Buildups Verified to Be Cracks in heat-affected Zone of Schedule 10 Pipe to Fitting Welds | /01T-0:on 800121,while at Cold Shutdown,Boron Buildups Identified on Loop B of Reactor Bldg Spray & Piping.Buildups Verified to Be Cracks in heat-affected Zone of Schedule 10 Pipe to Fitting Welds | | | 05000313/LER-1980-003, Forwards LER 80-003/01T-0 | Forwards LER 80-003/01T-0 | | | 05000368/LER-1980-003-03, /03L-0:on 800120,during Mode 3 Operation, Emergency Feedwater Flow Control Valve Failed to Close on Demand.Caused by Lack of Hydraulic Pressure | /03L-0:on 800120,during Mode 3 Operation, Emergency Feedwater Flow Control Valve Failed to Close on Demand.Caused by Lack of Hydraulic Pressure | | | 05000368/LER-1980-004-03, /03L-0:on 800107,during Mode 1 Operation,Core Protection Calculator B Failed.Channel B DNBR & Linear Power Density Trips Were Bypassed Placing Reactor Trip Logic in two-out-of-three Trip Sequence.Cause Unknown | /03L-0:on 800107,during Mode 1 Operation,Core Protection Calculator B Failed.Channel B DNBR & Linear Power Density Trips Were Bypassed Placing Reactor Trip Logic in two-out-of-three Trip Sequence.Cause Unknown | | | 05000313/LER-1980-004-03, /03L-0:on 800205,during Operational Test for Leak Rates,Reactor Bldg Ventilation Penetrations V1 & V2 Found Leaking in Excess of Tech Specs.Caused by Maladjusted Valve Seats.Valves Readjusted & Retested | /03L-0:on 800205,during Operational Test for Leak Rates,Reactor Bldg Ventilation Penetrations V1 & V2 Found Leaking in Excess of Tech Specs.Caused by Maladjusted Valve Seats.Valves Readjusted & Retested | | | 05000313/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000368/LER-1980-005, Forwards Revised LER 80-005/03X-1 | Forwards Revised LER 80-005/03X-1 | | | 05000368/LER-1980-005-03, /03L-0:on 800123,during Steady State Mode 1 Operation,Reactor Coolant Leakage Calculation Indicated Approx 3.6 Gpm Unidentified Leakage.Caused by Packing on Pressurized Spray Valves Leaking Excessively | /03L-0:on 800123,during Steady State Mode 1 Operation,Reactor Coolant Leakage Calculation Indicated Approx 3.6 Gpm Unidentified Leakage.Caused by Packing on Pressurized Spray Valves Leaking Excessively | | | 05000313/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000313/LER-1980-005-03, /03L-0:on 800306,during Scheduled Surveillance Test of P7-A,CV-2617 Valve Failed to Close Remote Electrically.Caused by Valve Binding in Closed Position. Valve Stem Repacked & Proper Operation Verified | /03L-0:on 800306,during Scheduled Surveillance Test of P7-A,CV-2617 Valve Failed to Close Remote Electrically.Caused by Valve Binding in Closed Position. Valve Stem Repacked & Proper Operation Verified | | | 05000313/LER-1980-006, Forwards LER 80-006/04L-0 | Forwards LER 80-006/04L-0 | | | 05000368/LER-1980-006-03, /03L-0:on 800123,during Mode 1 Operation,Core Protection Calculator B Failed,Generating DNBR & Linear Power Density Trips in Primary Power Sys.Cause Undetermined. Channel Restarted & Declared Operable | /03L-0:on 800123,during Mode 1 Operation,Core Protection Calculator B Failed,Generating DNBR & Linear Power Density Trips in Primary Power Sys.Cause Undetermined. Channel Restarted & Declared Operable | | | 05000313/LER-1980-006-04, /04L-0:on 800318,average Gross Release Rate for Jan-Mar 1980 Found to Be 4.3% of Max Permissible Concentration,Exceeding Tech Specs.Major Portion Caused by Reactor Bldg Purge in Jan | /04L-0:on 800318,average Gross Release Rate for Jan-Mar 1980 Found to Be 4.3% of Max Permissible Concentration,Exceeding Tech Specs.Major Portion Caused by Reactor Bldg Purge in Jan | | | 05000313/LER-1980-007, Forwards LER 80-007/01T-0 | Forwards LER 80-007/01T-0 | | | 05000313/LER-1980-007-99, Vendor Notified of Discrepancy Between Decay Heat Pump Specs & Parts Supplied. Potential Failure Feared.Tests & Performance History Indicate No Reliability Problems | Vendor Notified of Discrepancy Between Decay Heat Pump Specs & Parts Supplied. Potential Failure Feared.Tests & Performance History Indicate No Reliability Problems | | | 05000313/LER-1980-007-01, /01T-0:on 800314,B&W Advised That Mating Wear Rings on Double Suction Pump Could Cause Pump Failure During Accident Conditions.Caused by Failure to Document Design Revision on Pump Design Drawings | /01T-0:on 800314,B&W Advised That Mating Wear Rings on Double Suction Pump Could Cause Pump Failure During Accident Conditions.Caused by Failure to Document Design Revision on Pump Design Drawings | | | 05000368/LER-1980-007-03, /03L-0:on 800124,during Mode 1 Operation,Sodium Hydroxide Tank Level Found to Be 93% of Indicated Level. Following Calibr,Level Found to Be Below Tech Spec Limits. Cause Not Stated.Tank Levels Returned to Operable Limits | /03L-0:on 800124,during Mode 1 Operation,Sodium Hydroxide Tank Level Found to Be 93% of Indicated Level. Following Calibr,Level Found to Be Below Tech Spec Limits. Cause Not Stated.Tank Levels Returned to Operable Limits | | | 05000313/LER-1980-008-03, /03L-0:on 800324,while Performing Surveillance Test,Bypass Flow Was Observed to Be Zero Due to Failure of CV-2126 in Closed Position.Caused by Blown Control Fuse.Fuse Replaced & Valve Proved Operable | /03L-0:on 800324,while Performing Surveillance Test,Bypass Flow Was Observed to Be Zero Due to Failure of CV-2126 in Closed Position.Caused by Blown Control Fuse.Fuse Replaced & Valve Proved Operable | | | 05000368/LER-1980-008-03, /03L-0:on 800128,during Mode 1 Operation,Core Protection Calculator B Failed.Cause Not Determined.Core Protection Calculator B Restored & Functionally Tested | /03L-0:on 800128,during Mode 1 Operation,Core Protection Calculator B Failed.Cause Not Determined.Core Protection Calculator B Restored & Functionally Tested | | | 05000313/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000313/LER-1980-009-03, /03L-0:on 800328,while Performing Surveillance Test,Lead Hydrogen Purge Supply fan,VSF-30A Tripped on Overload.Caused by Check Valve HPA-5 Being Stuck,Due to Corrosion from Seal Water Leaking Onto Valve | /03L-0:on 800328,while Performing Surveillance Test,Lead Hydrogen Purge Supply fan,VSF-30A Tripped on Overload.Caused by Check Valve HPA-5 Being Stuck,Due to Corrosion from Seal Water Leaking Onto Valve | | | 05000313/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000368/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000368/LER-1980-009-03, /03L-0:on 800129,during Mode 3 Operation Following Reactor Trip from 100% power,I-131 Value of 1.67 Uci Was Observed.Caused by Expected Spike Following Reactor Trip.No Corrective Actions Necessary | /03L-0:on 800129,during Mode 3 Operation Following Reactor Trip from 100% power,I-131 Value of 1.67 Uci Was Observed.Caused by Expected Spike Following Reactor Trip.No Corrective Actions Necessary | | | 05000368/LER-1980-010-03, /03L-0:on 800212,during Mode 5 Operation, Discovered That Tech Spec 24-month Local Leak Rate Surveillance Requirements Had Not Been Performed.Caused by Confusion Over 24-month Surveillance Interval | /03L-0:on 800212,during Mode 5 Operation, Discovered That Tech Spec 24-month Local Leak Rate Surveillance Requirements Had Not Been Performed.Caused by Confusion Over 24-month Surveillance Interval | | | 05000313/LER-1980-010-03, /03L-0:on 800307,sys Reviews Per IE Bulletin 79-14 Found Hangers Inoperable.Cause Not Stated.Hangers Repaired & Mods Made by Revision to DCP 80-D-1207.List of Hangers Encl | /03L-0:on 800307,sys Reviews Per IE Bulletin 79-14 Found Hangers Inoperable.Cause Not Stated.Hangers Repaired & Mods Made by Revision to DCP 80-D-1207.List of Hangers Encl | | | 05000313/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000313/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000313/LER-1980-011-03, /03L-0:on 800401,based on Sys Review Per IE Bulletin 79-14,certain Hangers Declared Inoperable.Cause Not Stated.Hangers Repaired or Modified within Required Time Limit on Affected Svc Water & Main Steam Sys | /03L-0:on 800401,based on Sys Review Per IE Bulletin 79-14,certain Hangers Declared Inoperable.Cause Not Stated.Hangers Repaired or Modified within Required Time Limit on Affected Svc Water & Main Steam Sys | | | 05000368/LER-1980-011-03, /03L-0:on 800214,during Mode 5 Operation,While Performing Local Leak Rate Test,Five Containment Penetration Leak Rates Exceeded Tech Specs.Caused by Corrosion Buildup on Seating Surface or Valves Needing Adjustment | /03L-0:on 800214,during Mode 5 Operation,While Performing Local Leak Rate Test,Five Containment Penetration Leak Rates Exceeded Tech Specs.Caused by Corrosion Buildup on Seating Surface or Valves Needing Adjustment | | | 05000368/LER-1980-012, Forwards Updated LER 80-012/03X-2 | Forwards Updated LER 80-012/03X-2 | | | 05000313/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000313/LER-1980-012-03, /03L:on 800406,while Performing Monthly Inservice Valve Stroke Test,Emergency Feedwater Supply valves,CV2667 & CV2617,failed to Fully Open.Caused by Binding Due to Loose Bolts Securing Actuator | /03L:on 800406,while Performing Monthly Inservice Valve Stroke Test,Emergency Feedwater Supply valves,CV2667 & CV2617,failed to Fully Open.Caused by Binding Due to Loose Bolts Securing Actuator | | | 05000368/LER-1980-012-03, /03L-0:on 800222,during Mode 5 Operation,While Performing Surveillance Tests on Diesel Generator 1,unit Became Inoperable.Caused by Broken Generator Rotor Shaft in Area of Motor End Bearing Housing.Analyzing Exact Cause | /03L-0:on 800222,during Mode 5 Operation,While Performing Surveillance Tests on Diesel Generator 1,unit Became Inoperable.Caused by Broken Generator Rotor Shaft in Area of Motor End Bearing Housing.Analyzing Exact Cause | | | 05000313/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000368/LER-1980-013-03, /03L-0:on 800229,during Mode 5 Operation,Reactor Cooling Sys Chloride Concentration Found to Be Approx 0.5 Ppm,Violating Tech Specs.Probably Caused by Batch Contaminated During Maint on Safety Injection Check Valve | /03L-0:on 800229,during Mode 5 Operation,Reactor Cooling Sys Chloride Concentration Found to Be Approx 0.5 Ppm,Violating Tech Specs.Probably Caused by Batch Contaminated During Maint on Safety Injection Check Valve | | | 05000368/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000313/LER-1980-013-03, /03L-0:on 800407,during Reactor Trip of Offsite Power,High Pressure Injection Was Manually Initiated & CV-1227 High Pressure Injection Valve,Loop B Failed to Open on Demand.Caused by Stuck Engaging Lever | /03L-0:on 800407,during Reactor Trip of Offsite Power,High Pressure Injection Was Manually Initiated & CV-1227 High Pressure Injection Valve,Loop B Failed to Open on Demand.Caused by Stuck Engaging Lever | | | 05000368/LER-1980-014-03, /03L-0:on 800313,during Mode 5 Operation,Local Leak Rate Testing at Containment Penetration 2V2 Revealed Excessive Leak Rate Between Valve Actuation & Heatup Processes.Caused by Partially Open Inside Isolation Valve | /03L-0:on 800313,during Mode 5 Operation,Local Leak Rate Testing at Containment Penetration 2V2 Revealed Excessive Leak Rate Between Valve Actuation & Heatup Processes.Caused by Partially Open Inside Isolation Valve | | | 05000368/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000313/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000313/LER-1980-014-03, /03X-1:on 800415,fire & Smoke Detector Testing Not Completed within Surveillance Interval Due to High Radiation Level.Detectors Tested at Cold Shutdown.Tech Spec 4.19 Revised | /03X-1:on 800415,fire & Smoke Detector Testing Not Completed within Surveillance Interval Due to High Radiation Level.Detectors Tested at Cold Shutdown.Tech Spec 4.19 Revised | | | 05000368/LER-1980-015, Forward LER 80-015/99X-0 | Forward LER 80-015/99X-0 | | | 05000368/LER-1980-015-99, /99X-0:on 800129,during Recovery from Planned Transient,Rcs Depressurized to Min of 1,350 Psia.Caused by Pressurizer Spray Valve 2CV-4651 & Steam Dump & Bypass Valve 2CV-0301 Not Fully Closing on Demand.Valves Modified | /99X-0:on 800129,during Recovery from Planned Transient,Rcs Depressurized to Min of 1,350 Psia.Caused by Pressurizer Spray Valve 2CV-4651 & Steam Dump & Bypass Valve 2CV-0301 Not Fully Closing on Demand.Valves Modified | | | 05000313/LER-1980-015, Forwards LER 80-015/01T-0 | Forwards LER 80-015/01T-0 | | | 05000313/LER-1980-015-01, /01T-0:on 800510,changes in Seal Pressure & Makeup Tank Level Occurred During Steady State Power Operation. Caused by Rx Coolant Pump Seal C.Seal Cartridge Rebuilt & Seal Failure Being Investigated | /01T-0:on 800510,changes in Seal Pressure & Makeup Tank Level Occurred During Steady State Power Operation. Caused by Rx Coolant Pump Seal C.Seal Cartridge Rebuilt & Seal Failure Being Investigated | |
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