LER-1982-019, /03L-0:on 821024,MSIVs HCV-1041A & HCV-1042A Stopped Three to Four Degrees Off Seat When Signaled to Close.Caused by Binding Between Valve Packing & Shaft. Packings Sprayed W/Penetrant Oil |
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60 61 DOCKET NUMSER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o l2l l On October 24, 1982, at approximately 1624, while the plant was in a cold shutdown l
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LER No.82-019 Omaha Public Power District Fort Calhoun Station Unit No. 1 Docket No. 05000285 ATTACHMENT NO. 1
Safety Analysis
The purpose of the main steam isolation valves is to limit the uncontrolled cooldown of the reactor coolant system in the case of a main steam line break between the turbine and-one of the isolation valves.
If a break occurs between one steam generator and its asso-ciated main steam isolation valve, valve closure' limits the blowdown of the affected steam generator (s).
During this incident, the plant was in a cold shutdown condition to repair leakage from hand hole gaskets on the steam generators. The main steam isolation valves were cycled closed to prevent venting of contain-ment atmosphere through the steam lines during repairs to the' hand holes. During this cycling, the valves stopped closing three to four degrees off the seat. Under power operating conditions, if the main steam isolation valves had been signaled to close, the flow of steam in the lines would have forced the swing disc to seal against the valve seat, thus ensuring full closure.
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LER No.82-019 Omaha Public Power District Fort Calhoun Station Unit No. 1 Docket No. 05000285 ATTACHMENT.NO. 2
Corrective Action
When it was discovered that the valves did not seat, two Mainte-nance Orders were written to correct the problem. The valve packings were sprayed with a penetrant oil and were then cycled satisfactorily.
Surveillance Test ST-ISI-MS-1 (F.2) was performed to verify and document proper operability of both valves.
No further corrective action is considered necessary as this particular malfunction involving excessive friction between the packing and the valve shaft has not been a recurring problem. The valves are stroked each refueling outage and verified operable per the applicable Surveillance Test.
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LER No.82-019 Omaha Public Power District Fort Calhoun Station Unit No. 1 Docket No. 05000285 ATTACHMENT NO. 3 Failure Data This was the third occurrence of main steam isolation valve HCV-1042A failing to close within the four second time limit delineated by Technical Specification 2.5.
This was the second occurrence for isola-tion valve HCV-1041A.
Other events involving these valves were reported as:
1.
Abnormal Occurrence 73-8: Failure of Main Steam isolation Valve llCV-1041A to close in four seconds under no flow conditions.
2.
Abnormal Occurrence 74A-2: Failure of Main Steam Isolation Valve llCV-1042A in the open position.
3.
Abnormal Occurrence 74-16: Failure of Main Steam Isolation Valve llCV-1042A to close in less than four seconds under no flow conditions.
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| 05000285/LER-1982-001-03, /03L-0:on 820111,during Normal Operation,Two Fire Barrier Penetrations Found Nonfunctional.Shift Supervisor Immediately Notified;However,Fire Watch Not Posted.Insp & Supervisor Personnel Instructed on Proper Actions | /03L-0:on 820111,during Normal Operation,Two Fire Barrier Penetrations Found Nonfunctional.Shift Supervisor Immediately Notified;However,Fire Watch Not Posted.Insp & Supervisor Personnel Instructed on Proper Actions | | | 05000285/LER-1982-001, Forwards LER 82-001/03L-0 | Forwards LER 82-001/03L-0 | | | 05000285/LER-1982-002, Forwards LER 82-002/03L-1 | Forwards LER 82-002/03L-1 | | | 05000285/LER-1982-002-03, /03L-1:on 820114,stack Particulate Process Radiation Monitor RM-061 Tripped Causing Containment Radiation High Signal Actuation Due to Failure of Lockout Relay 86B1 to Trip.Caused by Burnt Coil.Coil Replaced | /03L-1:on 820114,stack Particulate Process Radiation Monitor RM-061 Tripped Causing Containment Radiation High Signal Actuation Due to Failure of Lockout Relay 86B1 to Trip.Caused by Burnt Coil.Coil Replaced | | | 05000285/LER-1982-003, Forwards LER 82-003/03L-1 | Forwards LER 82-003/03L-1 | | | 05000285/LER-1982-004-03, /03L-0:on 820203,small Quantity of Radioactive Gas/Particulate Released to Auxiliary Bldg During Routine Operation.Caused by Failure of Stack Gas Monitor RM-062 to Alarm at Appropriate Setpoint Due to Faulty Alarm Module | /03L-0:on 820203,small Quantity of Radioactive Gas/Particulate Released to Auxiliary Bldg During Routine Operation.Caused by Failure of Stack Gas Monitor RM-062 to Alarm at Appropriate Setpoint Due to Faulty Alarm Module | | | 05000285/LER-1982-005-03, /03L-0:on 820210,at 98% Power,Control Element 24 Inserted Into Core.Emergency Procedure EP-13,CEDM Malfunctions,Implemented & Power Stabilized at 88%.Caused by Erroneous Operating Instruction.Instruction Changed | /03L-0:on 820210,at 98% Power,Control Element 24 Inserted Into Core.Emergency Procedure EP-13,CEDM Malfunctions,Implemented & Power Stabilized at 88%.Caused by Erroneous Operating Instruction.Instruction Changed | | | 05000285/LER-1982-005, Forwards LER 82-005/03L-0 | Forwards LER 82-005/03L-0 | | | 05000285/LER-1982-006, Forwards LER 82-006/03L-0 | Forwards LER 82-006/03L-0 | | | 05000285/LER-1982-006-03, /03L-0:on 820323,during Surveillance Test ST-ISI- WD-1,F.1,valve HCV-506A Failed to Close Via Control Room Switch.Caused by Solenoid Valve Malfunction.Solenoid Valve Disassembled,Cleaned & Reassembled | /03L-0:on 820323,during Surveillance Test ST-ISI- WD-1,F.1,valve HCV-506A Failed to Close Via Control Room Switch.Caused by Solenoid Valve Malfunction.Solenoid Valve Disassembled,Cleaned & Reassembled | | | 05000285/LER-1982-007, Forwards LER 82-007/03L-0 | Forwards LER 82-007/03L-0 | | | 05000285/LER-1982-007-03, /03L-0:on 820324,leak Discovered in Copper Tubing Vent Line from Thermal Mixing Valve to Coolant Expansion Tank in Diesel Generator 2.Caused by Crack in Vent Line. Defective Tubing Replaced | /03L-0:on 820324,leak Discovered in Copper Tubing Vent Line from Thermal Mixing Valve to Coolant Expansion Tank in Diesel Generator 2.Caused by Crack in Vent Line. Defective Tubing Replaced | | | 05000285/LER-1982-008-03, /03L-0:on 820330,during Performance of ST-FW-1, F.2(b)(6)per Tech Spec 3.9,steam Driven Auxiliary Feedwater Pump Failed to Start.Caused by Back Pressure Trip Lever in Tripped Position.Lever Reset | /03L-0:on 820330,during Performance of ST-FW-1, F.2(b)(6)per Tech Spec 3.9,steam Driven Auxiliary Feedwater Pump Failed to Start.Caused by Back Pressure Trip Lever in Tripped Position.Lever Reset | | | 05000285/LER-1982-008, Forwards LER 82-008/03L-0 | Forwards LER 82-008/03L-0 | | | 05000285/LER-1982-009-03, /03L-0:on 820411,while Exchanging Component Cooling Water Heat Exchangers,Associated Outlet Valves HCV-490B,HCV-491B & HCV-492B Failed to Open.Cause Not stated.HCV-491B Reassembled & Tested | /03L-0:on 820411,while Exchanging Component Cooling Water Heat Exchangers,Associated Outlet Valves HCV-490B,HCV-491B & HCV-492B Failed to Open.Cause Not stated.HCV-491B Reassembled & Tested | | | 05000285/LER-1982-009, Forwards LER 82-009/03L-0 | Forwards LER 82-009/03L-0 | | | 05000285/LER-1982-010, Forwards LER 82-010/03L-0 | Forwards LER 82-010/03L-0 | | | 05000285/LER-1982-010-03, /03L-0:on 820430,during Routine Operations,Reactor Protection Sys a Channel Trip Unit 3 (Reactor Coolant Flow) Setpoints Drifted Out of Spec in Nonconservative Direction. Caused by Faulty Negative 15-volt Power Supply | /03L-0:on 820430,during Routine Operations,Reactor Protection Sys a Channel Trip Unit 3 (Reactor Coolant Flow) Setpoints Drifted Out of Spec in Nonconservative Direction. Caused by Faulty Negative 15-volt Power Supply | | | 05000285/LER-1982-011, Forwards LER 82-011/01T-0 | Forwards LER 82-011/01T-0 | | | 05000285/LER-1982-011-01, /01T-0:on 820521,blowdown Sampling Line for Steam Generator B Inboard Containment Isolation Valve HCV-2507A Found Closed Resulting in Failure to Monitor for Radioactivity.Caused by Inadvertent Closing of Valve | /01T-0:on 820521,blowdown Sampling Line for Steam Generator B Inboard Containment Isolation Valve HCV-2507A Found Closed Resulting in Failure to Monitor for Radioactivity.Caused by Inadvertent Closing of Valve | | | 05000285/LER-1982-012, Forwards LER 82-012/01T-0 | Forwards LER 82-012/01T-0 | | | 05000285/LER-1982-012-01, /01T-0:on 820519,auxiliary Feedwater Sys Design & Configuration Found Inadequate to Withstand Loss of Onsite Power W/Subsequent Steam Supply Line to Feedwater Pump FW-10 Failure.Pump FW-6 Not Designed for Harsh Environ | /01T-0:on 820519,auxiliary Feedwater Sys Design & Configuration Found Inadequate to Withstand Loss of Onsite Power W/Subsequent Steam Supply Line to Feedwater Pump FW-10 Failure.Pump FW-6 Not Designed for Harsh Environ | | | 05000285/LER-1982-014-03, /03L-0:on 820618,during Process of Switching Component Cooling Water Heat Exchangers,Associated Inlet Valves HCV-498A,HCV-490A & HCV-492A Did Not Open.Cause unknown.HCV-492A Manually Opened.All Valves Operable | /03L-0:on 820618,during Process of Switching Component Cooling Water Heat Exchangers,Associated Inlet Valves HCV-498A,HCV-490A & HCV-492A Did Not Open.Cause unknown.HCV-492A Manually Opened.All Valves Operable | | | 05000285/LER-1982-014, Forwards LER 82-014/03L-0 | Forwards LER 82-014/03L-0 | | | 05000285/LER-1982-015, Forwards LER 82-015/03L-0 | Forwards LER 82-015/03L-0 | | | 05000285/LER-1982-015-03, /03L-0:on 820622,gas Vent Header Containment Isolation Valve HCV-507A Failed to Close Via Control Room Switch.Caused by Stuck Solenoid Valve.Valve Changed | /03L-0:on 820622,gas Vent Header Containment Isolation Valve HCV-507A Failed to Close Via Control Room Switch.Caused by Stuck Solenoid Valve.Valve Changed | | | 05000285/LER-1982-016, Forwards LER 82-016/03L-0 | Forwards LER 82-016/03L-0 | | | 05000285/LER-1982-016-03, /03L-0:on 820714,Channel B of Reactor Protective Sys Axial Power Distribution Unit Had Negative Axial Shape Index Setpoint Out of Tolerance.Caused by Setpoint Drift Due to Dirty Contact in Flow Dependent Setpoint Selector Sw | /03L-0:on 820714,Channel B of Reactor Protective Sys Axial Power Distribution Unit Had Negative Axial Shape Index Setpoint Out of Tolerance.Caused by Setpoint Drift Due to Dirty Contact in Flow Dependent Setpoint Selector Switch | | | 05000285/LER-1982-018-01, /01T-0:on 820917,review of electro-pneumatic (E/P) Valve Positioners Revealed Absence of Analysis or Test Qualification Data for Honeywell Model 67400-023 Positioners.Control Circuit,Solenoid Valves to Be Modified | /01T-0:on 820917,review of electro-pneumatic (E/P) Valve Positioners Revealed Absence of Analysis or Test Qualification Data for Honeywell Model 67400-023 Positioners.Control Circuit,Solenoid Valves to Be Modified | | | 05000285/LER-1982-018, Forwards LER 82-018/01T-0 | Forwards LER 82-018/01T-0 | | | 05000285/LER-1982-019, Forwards LER 82-019/03L-0 | Forwards LER 82-019/03L-0 | | | 05000285/LER-1982-019-03, /03L-0:on 821024,MSIVs HCV-1041A & HCV-1042A Stopped Three to Four Degrees Off Seat When Signaled to Close.Caused by Binding Between Valve Packing & Shaft. Packings Sprayed W/Penetrant Oil | /03L-0:on 821024,MSIVs HCV-1041A & HCV-1042A Stopped Three to Four Degrees Off Seat When Signaled to Close.Caused by Binding Between Valve Packing & Shaft. Packings Sprayed W/Penetrant Oil | | | 05000285/LER-1982-020-03, /03L-0:on 821207,during Main Steam Safety Valve Test,Four Main Steam Safety Valves Had Lift Setpoints Out of Tolerance.Caused by Normal Drift of Valves Over Operating Cycle.Valves Readjusted | /03L-0:on 821207,during Main Steam Safety Valve Test,Four Main Steam Safety Valves Had Lift Setpoints Out of Tolerance.Caused by Normal Drift of Valves Over Operating Cycle.Valves Readjusted | | | 05000285/LER-1982-020, Forwards LER 82-020/03L-0 | Forwards LER 82-020/03L-0 | | | 05000285/LER-1982-021, Forwards LER 82-021/03L-0 | Forwards LER 82-021/03L-0 | | | 05000285/LER-1982-021-03, /03L-0:on 821211,during ST-ESF-3,F.2 Refueling Surveillance test,A/PC-742-1 Pressure Switch Found to Initiate Above Tech Spec.Caused by Instrument Drift.Switch Calibr & Will Be Changed When Replacement Is Available | /03L-0:on 821211,during ST-ESF-3,F.2 Refueling Surveillance test,A/PC-742-1 Pressure Switch Found to Initiate Above Tech Spec.Caused by Instrument Drift.Switch Calibr & Will Be Changed When Replacement Is Available | |
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