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LER-1978-010, /01T-0:on 780318,during Emergency Sequence & Power Transfer test,1A & 1C Makeup Pumps Tripped When Transferring to Onsite Source Due to Malfunctioning Time Delay Relay & Diesel Generators Failed to Start Due to Pressure Switches |
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| 2891978010R01 - NRC Website |
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o l The apparent cause for the MU Pump failure was a malfunctioning time delay relay in llow lube Oil trip circuit. The timers vill be replaced.
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Narrative
for Licensee Event Recort 78-lO/lT During the Emerger y Sequence and Power Transfer Test, Makeup Pu=ps 2A and 1C tripped on separate occasions. Tne test procedure requires simulating the undervoltage condition, which trips the ES hus feeder breakers causing actual loss of ES bus voltage. When the ES bus is tripped on the under-voltage condition, the =akeup pu=ps lose power and pu=p lube oil pressure.
During pu=p startup, there is a six second delay Defore the timer relay picks up.
This is to alls nor=al pu=p lube oil pressure to develop, which opens the lube oil pressure switch.
One of the pu=p trips occurred as a result of a failure of the timing relay to latch after being de-energined. Upon energining the bus, the timing relay picked up before the pu=p lube oil pressure switch opened. Tne other =akeup punp trip occurred as a result of a failure of the ti=ing relay to drop out after being de-energined in conjunction with loss of pu=p lube oil pressure.
.The d eup e ens would have operated satisfactorily on off-site power had an ES occurze However, operator intervention would have been required to restart the =ueup pu=ps if loss of off-site power occurred after an ES, as in the test sequence.
The ti=er relays will be replaced during the 1978 refueling outage.
The diesel start failure was previously identified by LER 7h-13 and LER 78-03 The OPLS pressure switch failed to operate before the cranking timers timed o t.
The pressure switches will be replaced during the 1978 Refueling outage, and the tests will be rerun.
M.U. Pu=p Ti=er GTE Sylvania, Clark Control Inc., AC pneu=atic ti=ing relay, Cat. No.17713UPE-76, 120 V AC coil, time delay:
0.2 seconds to 3 =inutes.
D.G. Pressure Switch Consolidated Control Corp., pressure range: 1 to 25 psi differential:
0.2 to 10 psi, 3ellows - phospher bronne Cat. No. 21A W 253-3.
.%ilure of the 1A diesel generator breaker to close was also noted in the pro =pt notification. Tnis failure resulted from the test method in that the switch handle =ust be released pro:M27 when it is removed from PULL-TO-LOCK or a trip signal occurs. Since the switch is not in FULL-TO-LOCK when the diesel is in standby, this problem is considered test related and is, therefore, not reportabl:
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| 05000320/LER-1978-001-03, /03L-0 on 780208:reactor Bldg Purge Supply Fans & Associated Purge Recirculation Damper Sys Were Inoperable. Caused by Incomplete Const | /03L-0 on 780208:reactor Bldg Purge Supply Fans & Associated Purge Recirculation Damper Sys Were Inoperable. Caused by Incomplete Const | | | 05000320/LER-1978-001, Forwards LER 78-001/03L-0 | Forwards LER 78-001/03L-0 | | | 05000312/LER-1978-001-01, /01T-0:on 780320,non-nuclear Instrumentation Dc Power Short Resulted in Reactor Trip & RCS Cooldown in Excess of Tech Spec Figure 3.1.2-2 Limits.Caused by Operator Changing Lightbulb.Conditions Imposed for Return to Power | /01T-0:on 780320,non-nuclear Instrumentation Dc Power Short Resulted in Reactor Trip & RCS Cooldown in Excess of Tech Spec Figure 3.1.2-2 Limits.Caused by Operator Changing Lightbulb.Conditions Imposed for Return to Power | | | 05000289/LER-1978-001-01, /01T-0:on 780106,B&W Informed Util That During Certain Plant Transients,Difference Between Reactor Power as Indicated by out-of-core Instrumentation & as Calculated by Heat Balance May Exceed 4% of Full Power | /01T-0:on 780106,B&W Informed Util That During Certain Plant Transients,Difference Between Reactor Power as Indicated by out-of-core Instrumentation & as Calculated by Heat Balance May Exceed 4% of Full Power | | | 05000289/LER-1978-001, Forwards LER 78-001/01T-0 | Forwards LER 78-001/01T-0 | | | 05000320/LER-1978-002, Forwards LER 78-002/03L-0 | Forwards LER 78-002/03L-0 | | | 05000320/LER-1978-002-03, /03L-0 on 780208:prior to Initial Refueling,Defect Found in Plate 6 of Seismic Instrumentation Triaxial Response Spectrum Recorder 714.Caused by Mfg Error | /03L-0 on 780208:prior to Initial Refueling,Defect Found in Plate 6 of Seismic Instrumentation Triaxial Response Spectrum Recorder 714.Caused by Mfg Error | | | 05000289/LER-1978-002-01, /01T-0:on 780112,valve FS-V156 Closed to Modify Sprinkler Sys Piping to B Emergency Diesel Radiator Room & Continuous Fire Watch Not Established for 24-h.Caused by Personnel Error.Fire Protection Tech Specs to Be Reviewed | /01T-0:on 780112,valve FS-V156 Closed to Modify Sprinkler Sys Piping to B Emergency Diesel Radiator Room & Continuous Fire Watch Not Established for 24-h.Caused by Personnel Error.Fire Protection Tech Specs to Be Reviewed | | | 05000289/LER-1978-002, Forwards LER 78-002/01T-0 | Forwards LER 78-002/01T-0 | | | 05000320/LER-1978-003, Forwards LER 78-003/01T-0 | Forwards LER 78-003/01T-0 | | | 05000320/LER-1978-003-01, /01T-0 on 780213:while in Mode 6,continuous Fire Watch Not Established When Cable Room Halon Sys Automatic Actuation Sys Was Inoperable.Caused by Misunderstanding | /01T-0 on 780213:while in Mode 6,continuous Fire Watch Not Established When Cable Room Halon Sys Automatic Actuation Sys Was Inoperable.Caused by Misunderstanding | | | 05000289/LER-1978-003, Forwards LER 78-003/03L-0 | Forwards LER 78-003/03L-0 | | | 05000289/LER-1978-003-03, /03L-0:on 780112,emergency Diesel Generator 1B Failed to Start on Simulated Test Signal During Procedure SP1305-5.2.Caused by Drifting Oil Pressure Limit Switch. Setting Adjusted,New Limit Switch Ordered | /03L-0:on 780112,emergency Diesel Generator 1B Failed to Start on Simulated Test Signal During Procedure SP1305-5.2.Caused by Drifting Oil Pressure Limit Switch. Setting Adjusted,New Limit Switch Ordered | | | 05000320/LER-1978-004, Forwards LER 78-004/01T-0 | Forwards LER 78-004/01T-0 | | | 05000320/LER-1978-004-01, /01T-0:on 780214,after Initial Fueling,Two Fuel Assemblies Were Loaded Into Reactor Vessel W/O Having Source Range Audible Counts in Containment Bldg | /01T-0:on 780214,after Initial Fueling,Two Fuel Assemblies Were Loaded Into Reactor Vessel W/O Having Source Range Audible Counts in Containment Bldg | | | 05000289/LER-1978-004-03, /03L-0:on 780117,while Closing Valve MU-V74A,22 Gallon Per Minute Packing Gland Leak Developed.Caused by Worn Packing in Valve.Valve Placed on Backseat.Packing Replaced 780118 | /03L-0:on 780117,while Closing Valve MU-V74A,22 Gallon Per Minute Packing Gland Leak Developed.Caused by Worn Packing in Valve.Valve Placed on Backseat.Packing Replaced 780118 | | | 05000289/LER-1978-004, Forwards LER 78-004/03L-0 | Forwards LER 78-004/03L-0 | | | 05000320/LER-1978-005-99, /99T-0 on 780208:during Surveillance of Dike,Noted That Area of Rock rip-rap Had Slid 15 Feet Down Slope.Caused by Ratio of incline.Rip-rap Repositioned | /99T-0 on 780208:during Surveillance of Dike,Noted That Area of Rock rip-rap Had Slid 15 Feet Down Slope.Caused by Ratio of incline.Rip-rap Repositioned | | | 05000320/LER-1978-005, Forwards LER 78-05l/01T | Forwards LER 78-05l/01T | | | 05000289/LER-1978-005-01, /01T-0:on 780119,Plant Operation Review Committee Found Containment Integrity Violated by Opening Valves BS-V47A & B During Pump Operability Test.Caused by Error in Operating Procedure OP 1104-5.Procedure to Be Revised | /01T-0:on 780119,Plant Operation Review Committee Found Containment Integrity Violated by Opening Valves BS-V47A & B During Pump Operability Test.Caused by Error in Operating Procedure OP 1104-5.Procedure to Be Revised | | | 05000289/LER-1978-005, Forwards LER 78-005/01T-0 | Forwards LER 78-005/01T-0 | | | 05000320/LER-1978-006-01, /01T-0 on 780217:core Alterations Made When Containment Integrity Had Been Broken & During Break in Communications W/Control Room | /01T-0 on 780217:core Alterations Made When Containment Integrity Had Been Broken & During Break in Communications W/Control Room | | | 05000320/LER-1978-006, Forwards LER 78-006/01T-0 | Forwards LER 78-006/01T-0 | | | 05000289/LER-1978-006-03, /03L-0:on 780124,during Normal Operation,Reactor Coolant Sample Isolation Valve CA-V13 Failed to Close When Actuated by Remote Signal.Caused by Valve Stem Thread Wear. Containment Isolation Valve CA-V2 Closed | /03L-0:on 780124,during Normal Operation,Reactor Coolant Sample Isolation Valve CA-V13 Failed to Close When Actuated by Remote Signal.Caused by Valve Stem Thread Wear. Containment Isolation Valve CA-V2 Closed | | | 05000289/LER-1978-006, Forwards LER 78-006/03L-0 | Forwards LER 78-006/03L-0 | | | 05000320/LER-1978-007, Forwards LER 78-007/03L-0 | Forwards LER 78-007/03L-0 | | | 05000320/LER-1978-007-03, /03L-0 on 780216:diesel Generator DF-X-1B Tripped. Caused by Spurious Actuation of Reverse Power Relay.Relay Reset & Surveillance Test on Diesel Generator Rerun | /03L-0 on 780216:diesel Generator DF-X-1B Tripped. Caused by Spurious Actuation of Reverse Power Relay.Relay Reset & Surveillance Test on Diesel Generator Rerun | | | 05000289/LER-1978-007, Forwards LER 78-007/03L-0 | Forwards LER 78-007/03L-0 | | | 05000289/LER-1978-007-03, /03L-0:on 780128,while at 50% of Full Power,Incore Quadrant Power Tilt Limit Exceeded.Transient Caused by Transient Power Operations & Maneuvering to all-rods-out Configuration.Xenon Burned Out & Tilt Returned to Limits | /03L-0:on 780128,while at 50% of Full Power,Incore Quadrant Power Tilt Limit Exceeded.Transient Caused by Transient Power Operations & Maneuvering to all-rods-out Configuration.Xenon Burned Out & Tilt Returned to Limits | | | 05000289/LER-1978-008, Forwards LER 78-008/01T-0 | Forwards LER 78-008/01T-0 | | | 05000289/LER-1978-008-01, /01T-0:on 780202,once-through Steam Generator Feedwater Nozzles Flooded During Operation Below 5% Full Power.Caused by Incorrect Procedure Due to Operating Inexperience.Shutdown & Cooldown Procedures Revised | /01T-0:on 780202,once-through Steam Generator Feedwater Nozzles Flooded During Operation Below 5% Full Power.Caused by Incorrect Procedure Due to Operating Inexperience.Shutdown & Cooldown Procedures Revised | | | 05000320/LER-1978-008-03, /03L-0 on 780224:during Final Turnover Insp Three Fire Penetration Seals Found Not Functional.Caused by Seals Being Breached During Const.Fire Watch Was Posted | /03L-0 on 780224:during Final Turnover Insp Three Fire Penetration Seals Found Not Functional.Caused by Seals Being Breached During Const.Fire Watch Was Posted | | | 05000320/LER-1978-008, Forwards LER 78-008/03L-0 | Forwards LER 78-008/03L-0 | | | 05000289/LER-1978-009-03, /03L-0 on 780315:dc Breaker CB3 Failed to Trip on One of Several Tests.Caused by Apparent Binding of Breaker Operating Linkage.Binding May Have Been Due to Insufficient Exercise of Breaker &/Or Lack of Maint | /03L-0 on 780315:dc Breaker CB3 Failed to Trip on One of Several Tests.Caused by Apparent Binding of Breaker Operating Linkage.Binding May Have Been Due to Insufficient Exercise of Breaker &/Or Lack of Maint | | | 05000320/LER-1978-009-03, /03L-0 on 780302:surveillance Requirements Re Control Rod Drive Mechanism Not Met.Failed to Realize Specific Submode Had Been Entered | /03L-0 on 780302:surveillance Requirements Re Control Rod Drive Mechanism Not Met.Failed to Realize Specific Submode Had Been Entered | | | 05000320/LER-1978-009, Forwards LER 78-009/03L-0 | Forwards LER 78-009/03L-0 | | | 05000289/LER-1978-009, Forwards LER 78-009/03L-0 | Forwards LER 78-009/03L-0 | | | 05000320/LER-1978-010-03, /03L-0 on 780307:river Water Pump Outlet & Prelube Valves & Redundant RCP Seal Injection Valves Not Functionally Tested Before Being Placed in Svc | /03L-0 on 780307:river Water Pump Outlet & Prelube Valves & Redundant RCP Seal Injection Valves Not Functionally Tested Before Being Placed in Svc | | | 05000320/LER-1978-010, Forwards LER 78-010/03L-0 | Forwards LER 78-010/03L-0 | | | 05000289/LER-1978-010, Forwards LER 78-010/01T-0 | Forwards LER 78-010/01T-0 | | | 05000289/LER-1978-010-01, /01T-0:on 780318,during Emergency Sequence & Power Transfer test,1A & 1C Makeup Pumps Tripped When Transferring to Onsite Source Due to Malfunctioning Time Delay Relay & Diesel Generators Failed to Start Due to Pressure Swit | /01T-0:on 780318,during Emergency Sequence & Power Transfer test,1A & 1C Makeup Pumps Tripped When Transferring to Onsite Source Due to Malfunctioning Time Delay Relay & Diesel Generators Failed to Start Due to Pressure Switches | | | 05000289/LER-1978-011-03, /03L-0:on 780318,snubber MS-201 Found W/No Fluid in Reservoir.Caused by Pinched Rod Wiper Seal | /03L-0:on 780318,snubber MS-201 Found W/No Fluid in Reservoir.Caused by Pinched Rod Wiper Seal | | | 05000320/LER-1978-011-03, /03L-0 on 780311:entered Mode 4 W/O Establishing Containment Integrity & Surveillance on Bldg Door Not Performed.Door Failure Caused by Damaged O Ring Seals | /03L-0 on 780311:entered Mode 4 W/O Establishing Containment Integrity & Surveillance on Bldg Door Not Performed.Door Failure Caused by Damaged O Ring Seals | | | 05000320/LER-1978-011, Forwards LER 78-011/03L-0 | Forwards LER 78-011/03L-0 | | | 05000289/LER-1978-011, Forwards LER 78-011/03L-0 | Forwards LER 78-011/03L-0 | | | 05000320/LER-1978-012, Forwards LER 78-012/03L-0 | Forwards LER 78-012/03L-0 | | | 05000289/LER-1978-012-03, /03L-0:on 780406,during Functional Tests,One Snubber DHH-187 Would Not Lock Up Upon Compression.Cause Undetermined.Valve Block Replaced & Satisfactory Test Made | /03L-0:on 780406,during Functional Tests,One Snubber DHH-187 Would Not Lock Up Upon Compression.Cause Undetermined.Valve Block Replaced & Satisfactory Test Made | | | 05000289/LER-1978-012, Forwards LER 78-012/03L-0 | Forwards LER 78-012/03L-0 | | | 05000320/LER-1978-012-03, /03L-0:on 780314,Unit 2 Entered Mode 4 with Only One Operable Bldg Spray Sys.Caused by Clerical Error | /03L-0:on 780314,Unit 2 Entered Mode 4 with Only One Operable Bldg Spray Sys.Caused by Clerical Error | | | 05000289/LER-1978-013-01, /01T-0:on 780413,B&W Informed Util That Small Break on Reactor Coolant Pump Discharge Had Not Been Analyzed in Fsar.Procedures to Be Revised & Operators to Be Trained in Response to Small Break LOCA | /01T-0:on 780413,B&W Informed Util That Small Break on Reactor Coolant Pump Discharge Had Not Been Analyzed in Fsar.Procedures to Be Revised & Operators to Be Trained in Response to Small Break LOCA | |
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