LER-1979-015, Forwards LER 79-015/03X-1 |
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f9 COOPER NUCLEAR STATION P.O. Bo X 98, BRoWNVILLE, NEBR ASKA 68321 y
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Nebraska Publ.ic Power D. tr. t is ic TeLemo~c m.2s-3.u CNSS79G400 August 1, 1979 Mr. K. V. Seyfrit U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region IV 611 Ryan Plaza Suite 1000 Arlington, Texas 76011
Dear Sir:
This report is submitted in accordance with Section 6.7.2.B.2 of the Technical Specifications for Cooper Nuclear Station and discusses a reportable occurrence that was discovered on >by 25, 1979. A licensee event report form is also enclosed. This revised report indicates changes in designation of apparent cause of occurrence and corrective action for breaker 1FA.
Report No.:
50-298-79-15-1 Report Date:
August 1, 1979 Occurrence Date: May 25, 1979 Facility:
Cooper Nuclear Station Brownville, Nebraska 68321 Identification of Occurrence:
A condition which lead to operation in a degraded mode permitted by a limiting condition for operation established in paragraph 3.9.A.1 of the Technical Specifications.
Conditions Prior to Occurrence:
Steady state power operation at 290 MWe.
Event occurred immed-iately after the reactor scrammed.
Description of Occurrence:
When the reactor scra==ed, breaker lAS failed to close automat-ically.
Breaker lAS is the feeder breaker from the startup trans-former.
Secondly, breaker 1FA failed to trip automatically when bus IF was energized from the emergency transfor=cr.
Breaker 1FA is one of two breakers in series connecting the 4160V bus IF to the 4160V bus lA.
Breaker 1FA also failed to trip from the control room when the control switch was operated to TRIP.
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Mr. K. V. Seyfrit August 1, 1979 Page 2.
Designation of Apparent Cause of Occurrence:
It is believed that breaker lAS failed to close automatically because the auxiliary switch 52, located in breaker lAN, failed to close its contact when lAN opened due to the main generator trip.
When breaker lAN trips, its auxiliary switch 52 is returned to its nor=al position by a spring.
This spring, a part of the auxiliary switch, apparently failed to close the switch contacts.
On July 28, 1979, breaker 1FA was removed, inspected and tested under supervision of the manufacturer's engineers. A series of bench tests revealed that breaker 1FA failure to trip was caused by misalignment of the trip coil rather than by the contact of the position switch 52H not being closed as reported on June 23, 1979.
The problem did not become evident when breaker 1FA was operated in the test position.
Breakers lAS and 1FA are GE Magna Blast Type AMH 4.76-250.
Analysis of Occurrence:
During normal operation when the generator is connected to the 345 KV system, the 4160V bus LA is energized from the normal trans-former via breaker lAN. When the generator trips breaker lAN trips, and breaker LAS closes automatically and energizes the 4160V bus lA from the startup transformer.
Since breaker LAS failed to close, the 4160V bus IF was automatically energized from the emergency transformer.
Breaker lAS was then closed by the manual control switch.
Diesel Generator #1, the third source of power to the 4160V bus IF, started automatically and was operable. However, the diesel gen-erator did not energize bus IF due to the bus being energized by the emergency transformer.
Breaker IFA is in series with the breaker lAF.
Both breakers open on loss of voltage to bus IF.
Either breaker then isolates the emergency bus IF from bus lA.
Failure of breaker 1FA to trip did not affect operation of the emergency bus IF because lAF opened.
This occurrence presented no adverse consequences from the stand-point of public health and safety.
2035 289
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Mr. K. V. Seyfrit August 1, 1979 Page 3.
Corrective Action; The breaker manufacturer (GE) has been contactec in regards to the evaluation of the problem with breaker lAS.
The 3xisting auxiliary switch 52 was cycled, cleaned and tested satisfactc-ily. Further action will depend on the manufacturer's recommendaticas.
The trip coil support for breaker 1FA was readjusted to obtain the recommended trip armature travel as specified by the manufacturer.
The trip coil and the trip armature were aligned. Breaker 1FA was given a series of closing and tripping tests and correct operation verified.
The failure to trip which occurred on breaker 1FA has never been experienced on the remaining 51 similar breakers. Tripping of breaker 1FA will be verified again in about 8 weeks.
If satis-factory, no other further cecrective action is planned.
Sincerely, L. C. Lessor Station Superintendent Cooper Nuclear Station [Ohj [9O LCL:cg Attach.
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| 05000298/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000298/LER-1979-001-03, /03L-0 on 790103:during Operation,Drywell Atmospheric Radiation Monitor Gas Channel (RMV-RM-4C) Failed Downscale.Caused by Detector Failure Caused by Moisture in Detector Chamber.Detector Replaced;Chamber & Lines Dried | /03L-0 on 790103:during Operation,Drywell Atmospheric Radiation Monitor Gas Channel (RMV-RM-4C) Failed Downscale.Caused by Detector Failure Caused by Moisture in Detector Chamber.Detector Replaced;Chamber & Lines Dried | | | 05000298/LER-1979-005-03, /03X-1 on 790216:reactor Recirculation Motor Generator Set a Tripped During Normal Operation.Caused by Failure of Level Switch NBI-LIS-58A Due to Corrosion. Corrosion Cleaned from Inside Switch Case & Switch Replaced | /03X-1 on 790216:reactor Recirculation Motor Generator Set a Tripped During Normal Operation.Caused by Failure of Level Switch NBI-LIS-58A Due to Corrosion. Corrosion Cleaned from Inside Switch Case & Switch Replaced | | | 05000298/LER-1979-005, Forwards LER 79-005/03X-1 | Forwards LER 79-005/03X-1 | | | 05000298/LER-1979-008-03, /03L-0 on 790420:breaker 1FA Failed to Trip When Control Switch Operated to Trip.Caused by Failure of Auxiliary Switch Contact Mounted Inside Breaker 1FA to Make Proper Electrical Contact.Breaker Inspected & Cleaned | /03L-0 on 790420:breaker 1FA Failed to Trip When Control Switch Operated to Trip.Caused by Failure of Auxiliary Switch Contact Mounted Inside Breaker 1FA to Make Proper Electrical Contact.Breaker Inspected & Cleaned | | | 05000298/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000298/LER-1979-009-03, /03L-0 on 790430:four Penetrations Found Leaking Excessively During Local Leak Rate Test.Caused by Defects in Limitorque Operator Torque Switch,Seal Rings & Check Valves. All Defects Repaired | /03L-0 on 790430:four Penetrations Found Leaking Excessively During Local Leak Rate Test.Caused by Defects in Limitorque Operator Torque Switch,Seal Rings & Check Valves. All Defects Repaired | | | 05000298/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000298/LER-1979-010, Forwards LER 79-010/03L-0 | Forwards LER 79-010/03L-0 | | | 05000298/LER-1979-010-03, /03L-0 on 790424:surface Linear Indication Found in Weld RA5-CF-13,main Steam to a & B RHR Heat Exchangers & HPCI Turbine.Caused by Welding Error.Defect Removed | /03L-0 on 790424:surface Linear Indication Found in Weld RA5-CF-13,main Steam to a & B RHR Heat Exchangers & HPCI Turbine.Caused by Welding Error.Defect Removed | | | 05000298/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000298/LER-1979-011-03, /03L-0 on 790424:reactor Water Cleanup MO-18 Contactor Failed to Close Manually During Cold Shutdown. Caused by Failure of Auxiliary Contact Mechanism.Repairs Completed Per IE Bulletin 78-05 | /03L-0 on 790424:reactor Water Cleanup MO-18 Contactor Failed to Close Manually During Cold Shutdown. Caused by Failure of Auxiliary Contact Mechanism.Repairs Completed Per IE Bulletin 78-05 | | | 05000298/LER-1979-012-03, /03L-0 on 790503:vessel Water Temp Increased to 220 F W/Primary Containment Integrity Not Established.Caused by Omission in Operating Procedures.Setpoint of Interlock Verified & Procedures Revised | /03L-0 on 790503:vessel Water Temp Increased to 220 F W/Primary Containment Integrity Not Established.Caused by Omission in Operating Procedures.Setpoint of Interlock Verified & Procedures Revised | | | 05000298/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000298/LER-1979-013-03, /03L-0 on 790508:correct Drywell to Suppression Chamber Reading Not Established.Caused by Leaking Inlet Purge Valve.Valve Repaired & Leak Tested | /03L-0 on 790508:correct Drywell to Suppression Chamber Reading Not Established.Caused by Leaking Inlet Purge Valve.Valve Repaired & Leak Tested | | | 05000298/LER-1979-013, Forwards LER 79-013/03L-0 | Forwards LER 79-013/03L-0 | | | 05000298/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000298/LER-1979-014-03, /03L-0 on 790509:chamber Vent Valve for Torus Level Transmitter Was Left Closed.Caused by Technician Error.Vent Valve Opened & PC-LT-12 Placed Back Into Svc | /03L-0 on 790509:chamber Vent Valve for Torus Level Transmitter Was Left Closed.Caused by Technician Error.Vent Valve Opened & PC-LT-12 Placed Back Into Svc | | | 05000298/LER-1979-015-03, /03X-1 on 790525:breaker 1AS Failed to Close Automatically After Reactor Scrammed.Caused by Improper Operations of Switch 52 in Breaker 1AN.Breaker 1FA Failed to Trip.Caused by Misaligned Trip Coil & Armature | /03X-1 on 790525:breaker 1AS Failed to Close Automatically After Reactor Scrammed.Caused by Improper Operations of Switch 52 in Breaker 1AN.Breaker 1FA Failed to Trip.Caused by Misaligned Trip Coil & Armature | | | 05000298/LER-1979-015, Forwards LER 79-015/03X-1 | Forwards LER 79-015/03X-1 | | | 05000298/LER-1979-016-03, /03L-0 on 790531:RHR Pump 1A Tripped During Start on Overcurrent in Phase C.Caused by Failure of GE Model 121AC66K8A Overcurrent Relay Operating Disc to Return to Normal Position.Relay Cleaned,Recalibr & Retested | /03L-0 on 790531:RHR Pump 1A Tripped During Start on Overcurrent in Phase C.Caused by Failure of GE Model 121AC66K8A Overcurrent Relay Operating Disc to Return to Normal Position.Relay Cleaned,Recalibr & Retested | | | 05000298/LER-1979-016, Forwards LER 79-016/03L-0 | Forwards LER 79-016/03L-0 | | | 05000298/LER-1979-017, Forwards LER 79-017/03L-0 | Forwards LER 79-017/03L-0 | | | 05000298/LER-1979-017-03, /03L-0 on 790620:during Review,Observed That Surveillance Procedure 6.2.4.1 Did Not Include Daily Check of Undervoltage Relays or Monthly Functional Testing. Cause Unstated.Procedures Revised | /03L-0 on 790620:during Review,Observed That Surveillance Procedure 6.2.4.1 Did Not Include Daily Check of Undervoltage Relays or Monthly Functional Testing. Cause Unstated.Procedures Revised | | | 05000298/LER-1979-018-03, /03L-0 on 790706:during Routine Testing,Reactor Vessel Level Indicating Switch NBI-LIS-58A Was Found W/Trip Point Less than Allowed.Caused by Sediments of Dust & Moisture in Auxiliary Switch | /03L-0 on 790706:during Routine Testing,Reactor Vessel Level Indicating Switch NBI-LIS-58A Was Found W/Trip Point Less than Allowed.Caused by Sediments of Dust & Moisture in Auxiliary Switch | | | 05000298/LER-1979-018, Forwards LER 79-018/03L-0 | Forwards LER 79-018/03L-0 | | | 05000298/LER-1979-019-01, /01T-0:on 790809,upon Auto Start Signal,High Pressure Coolant Injection Pump Did Not Initially Start. Caused by Deterioration of Piston Rings in Valve Actuator. Rings Replaced & Test Completed Satisfactorily | /01T-0:on 790809,upon Auto Start Signal,High Pressure Coolant Injection Pump Did Not Initially Start. Caused by Deterioration of Piston Rings in Valve Actuator. Rings Replaced & Test Completed Satisfactorily | | | 05000298/LER-1979-019, Forwards LER 79-019/01T-0 | Forwards LER 79-019/01T-0 | | | 05000298/LER-1979-020-03, /03L-0:on 790809,while Performing Surveillance Procedure on Relief Valve Bellows Monitoring Sys,Pressure Switch MS-PS-71G Failed to Actuate.Caused by Improper Assembly.Switch Was Replaced | /03L-0:on 790809,while Performing Surveillance Procedure on Relief Valve Bellows Monitoring Sys,Pressure Switch MS-PS-71G Failed to Actuate.Caused by Improper Assembly.Switch Was Replaced | | | 05000298/LER-1979-020, Forwards LER 79-020/03L-0 | Forwards LER 79-020/03L-0 | | | 05000298/LER-1979-021-03, /03L-0:on 790811,carbon Absorber in Standby Gas Treatment Sys B Was Wetted W/Water When Control Room Received Actuation Alarm for Deluge Sys.Caused by Improper Installation of Baseplate of Fire Detection Unit | /03L-0:on 790811,carbon Absorber in Standby Gas Treatment Sys B Was Wetted W/Water When Control Room Received Actuation Alarm for Deluge Sys.Caused by Improper Installation of Baseplate of Fire Detection Unit | | | 05000298/LER-1979-021, Forwards LER 79-021/03L-0 | Forwards LER 79-021/03L-0 | | | 05000298/LER-1979-022-03, /03L-0:on 790812,water from Carbon Absorber Housing of Standby Gas Treatment Sys a Sprayed Carbon Absorber Trays,Rendering Trays Inoperable.Caused by Inadequate Seating Area Between Valve Clapper & Latch | /03L-0:on 790812,water from Carbon Absorber Housing of Standby Gas Treatment Sys a Sprayed Carbon Absorber Trays,Rendering Trays Inoperable.Caused by Inadequate Seating Area Between Valve Clapper & Latch | | | 05000298/LER-1979-022, Forwards LER 79-022/03L-0 | Forwards LER 79-022/03L-0 | | | 05000298/LER-1979-023, Forwards LER 79-023/03L-0 | Forwards LER 79-023/03L-0 | | | 05000298/LER-1979-023-03, /03L-0:on 790809,Barton Model 288 Differential Pressure Indicating Switch MS-DPIS-119B Was Found in Excess of Tech Specs Table 3.2.A.Caused by Faulty Switch. Microswitch Assembly Was Replaced | /03L-0:on 790809,Barton Model 288 Differential Pressure Indicating Switch MS-DPIS-119B Was Found in Excess of Tech Specs Table 3.2.A.Caused by Faulty Switch. Microswitch Assembly Was Replaced | | | 05000298/LER-1979-024, Forwards LER 79-024/03L-0 | Forwards LER 79-024/03L-0 | | | 05000298/LER-1979-024-03, /03L-0:on 790831,surveillance Testing Pressure Switch NBI-PS-55D Found W/Trip Point Below Tech Specs.Cause Not Stated.Switch Readjusted to Proper Setpoint & Then Replaced After Unsatisfactory Performance | /03L-0:on 790831,surveillance Testing Pressure Switch NBI-PS-55D Found W/Trip Point Below Tech Specs.Cause Not Stated.Switch Readjusted to Proper Setpoint & Then Replaced After Unsatisfactory Performance | | | 05000298/LER-1979-025, Forwards LER 79-025/03L-0 | Forwards LER 79-025/03L-0 | | | 05000298/LER-1979-025-03, /03L-0:on 790912,HPCI Turbine Stop Valve Separated from Actuator at Split Coupling.Caused by Improperly Mfg Split Coupling.Split Coupling Replaced & Installation Procedures Revised | /03L-0:on 790912,HPCI Turbine Stop Valve Separated from Actuator at Split Coupling.Caused by Improperly Mfg Split Coupling.Split Coupling Replaced & Installation Procedures Revised | | | 05000298/LER-1979-026, Forwards LER 79-026/03L-0 | Forwards LER 79-026/03L-0 | | | 05000298/LER-1979-026-03, /03L-0:on 790912,investigation Found Unidentified Drywell Leak on Reactor Recirculation Pump B.Caused by Failure of Pump Seal at Natural End of Life.Seal Replaced.No Further Action Planned | /03L-0:on 790912,investigation Found Unidentified Drywell Leak on Reactor Recirculation Pump B.Caused by Failure of Pump Seal at Natural End of Life.Seal Replaced.No Further Action Planned | | | 05000298/LER-1979-027, Forwards LER 79-027/03L-0 | Forwards LER 79-027/03L-0 | | | 05000298/LER-1979-027-03, /03L-0:on 791001,during Routine Surveillance Procedure MS-DPIS-119B,switch Was Found W/Setpoints in Excess of Tech Specs.Caused by Setpoint Drift.Instrument Recalibr | /03L-0:on 791001,during Routine Surveillance Procedure MS-DPIS-119B,switch Was Found W/Setpoints in Excess of Tech Specs.Caused by Setpoint Drift.Instrument Recalibr | | | 05000298/LER-1979-028, Forwards LER 79-028/03L-0 | Forwards LER 79-028/03L-0 | | | 05000298/LER-1979-028-03, /03L-0:on 791008,during Insp of Cable Spreading Room,One 4-inch Pipe Sleeve Not Sealed.Caused by Inadequate Control of Fire Seals Installation During Microwave Communications Sys Installation.Sleeve Was Sealed | /03L-0:on 791008,during Insp of Cable Spreading Room,One 4-inch Pipe Sleeve Not Sealed.Caused by Inadequate Control of Fire Seals Installation During Microwave Communications Sys Installation.Sleeve Was Sealed | | | 05000298/LER-1979-029-03, /03L-0:on 791012,during Routine Plant Tour,Pinhole Leak Detected in Upstream Weld of Supply Isolation Valve. Cause Unknown.Weld Will Be Repaired During Next Shutdown | /03L-0:on 791012,during Routine Plant Tour,Pinhole Leak Detected in Upstream Weld of Supply Isolation Valve. Cause Unknown.Weld Will Be Repaired During Next Shutdown | | | 05000298/LER-1979-029, Forwards LER 79-029/03L-0 | Forwards LER 79-029/03L-0 | | | 05000298/LER-1979-030-03, /03L-0:on 791021,while Pumping Water from Torus to radwaste,drywell-to-torus Differential Pressure Dropped Below Tech Specs.Caused by Nitrogen Pressure Forcing Water from Downcomers to Flow to Torus | /03L-0:on 791021,while Pumping Water from Torus to radwaste,drywell-to-torus Differential Pressure Dropped Below Tech Specs.Caused by Nitrogen Pressure Forcing Water from Downcomers to Flow to Torus | | | 05000298/LER-1979-030, Forwards LER 79-030/03L-0 | Forwards LER 79-030/03L-0 | |
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