LER-1979-029, /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 |
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U. S. NUCLE AR REGUL AToRY CoMMISSloN NRC FOAM 366 (7 77)
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60 61 DOCK ET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h puring normal operation, a routine tour of the plant indicated a through-wall crack l O
2 pf a weld in the REC supply to the south critical loop, upstream of the supply o
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P COOPER NUCLEAR STATION P.O. Box 98, BRoWNvlLLE, NEBR A5KA 68321 Nebraska Public Power Distr =ct i
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CNSS790554 November 5, 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 October 8, 1979. A li-censee event report form is also enclosed.
Report No.:
50-298-79-28 Report Date:
November 5, 1979 Occurrence Date: October 8, 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 Section 3.19.B of the Technical Specifications.
Conditions Prior to Occurrence:
The reactor was at a steady state power level of approximately 9}%
of rated thermal power.
Description 'f Occurrence:
Unile laspecting the cable spreading room it was noted that a four inch diameter pipe sleeve in the fire wall between the cable spreading room and the cable expansion room was not properly sealed.
Designation of Apparent Cause of Occurrence:
Inadequate control of installe. tion of fire seals during a microwave communications system installation in December 1978.
1398 185
Mr. K. V. Seyfrit November 5, 1979 Page 2.
Analysis of Occurrence:
The four inch sleeve, located in the wall between the cable spread-ing room and the cable expansion room, carries two 1 inch conduits through it.
One conduit contains control cable for reactor re-circulation motor generator set ventilation flow indication. The other conduit contains cable for microwave communication. The space inside the four inch sleeve and outside of the two one inch conduits was not adequately sealed. The possibility of a fire starting in this area is minimal because no combustible material was present. The cable spreading room is equipped with an auto-matic sprinkler system which could extinguish a fire if one started.
The possibility of a fire spreading through the unsealed sleeve was remote because the sleeve contained no combustible material. This occurrence presented no adverse effect to public health and safety.
Corrective Action
The four inch sleeve was immediately sealed and an adequate fire barrier established. All remaining sleeves in this area were inspected and verified to be properly sealed. The Technical Spec-ifications also require that the penetrations in the cable spread-ing room be inspected every 18 months. This event was discussed with the appropriate personnel.
Sincerely, L. C. Lessor Station Superintendent Cooper Nuclear Station LCL:cg irtach.
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(7 77)
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60 61 DOCKET NUMB ER 68 59 EVENT DATE 74 7b REPORT OATE 80 EVENT DESCRIPTICN AND PROB ABLE CONSEQUENCES h 4 inch pipn sleevo I O
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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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