On February 11, 2002 at 0314 with Columbia Generating Station (Columbia) operating at 100% power, planned online maintenance commenced on Emergency Diesel Generator ( EDG) 2. Maintenance was completed as scheduled. Surveillance testing to demonstrate operability of the EDG-2, and exit from the Limiting Condition of Operation (LCO), was started on February 13. Immediately after the EDG-2 output breaker was closed, the control room received an annunciator alarm. Investigation and evaluation revealed that the circuit breaker had closed but the Mechanism Operated Cell ( MOC) switch assembly had failed to change state as expected. Columbia was at 100% power, when it was decided to shutdown the plant within the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time of TS 3.8.1 Required Action B.4. On February 14, 2002 at 1257 the plant entered Mode 3 as required by TS 3.8.1.F.1. The failure of the MOC switches to not fully actuate was due to lack of preventive maintenance and a breaker replacement that produced less drive force to actuate the MOC assembly. The root cause was the failure to recognize the importance of MOC assembly maintenance. The corrective actions are to establish maintenance on all 4160 volt and 6900 volt cubicle switchgears, and to enhance an existing Circuit Breaker Program to provide guidance on breaker and cell maintenance.
968-26158 RI (9/01) |
Description of Event
On February 11, 2002 at 0314 Columbia Generating Station (Columbia) began planned online maintenance on Emergency Diesel Generator (EDG) 2. Maintenance was completed as scheduled. Surveillance testing to demonstrate operability of the EDG-2, and exit from the Limiting Condition of Operation (LCO), was started on February 13. Immediately after the EDG-2 output breaker was closed, the control room received an annunciator alarm. As this was not an expected alarm, the System Engineer and the Electrical Supervisor were contacted for evaluation. Further investigation revealed that the circuit breaker had closed but the Mechanism Operated Cell (MOC) switch assembly had failed to change state as expected. The circuit breaker is a Westinghouse model DHP-VR, which was installed during an upgrade process in June 2001. Columbia was at 100% power when the decision was made to shutdown the plant, due to the inability to restore EDG-2 to an Operable status within the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time of TS 3.8.1 Required Action B.4. OP February 14, 2002 at 1257 the plant entered Mode 3 as required by 7'S 3.8.1.F.1. On February 15, 2002 at 0242 the plant entered Mode 4 as required by TS 3.8.1.F.2 A four hour event notification telephone call was made to the NRC Operations Center at 0418 EST on February 14, 2002 pursuant to 10 CFR 50.72(b)(2)(i) after the plant shutdown was initiated (Event Number 38694).
Immediate Corrective Actions
All Safety Related circuit breakers of the DHP-VR design and associated breaker cubicle, and other 4160 and 6900 volt breakers and their cubicles, that have an active safety function, have had preventive maintenance performed in accordance with the guidance developed by Columbia, Westinghouse, and Cutler Hammer staff. The MOC assemblies for these breaker cubicles were completely disassembled, inspected for wear, cleaned, re-greased, and worn parts were replaced as needed. The Vendor also helped to establish acceptable operating limits for the breaker applied MOC operating pin force and the MOC linkage resistance force to be used to assess the degradation rate of the breaker's MOC switch interface.
Cause of the Event
The failure of the MOC switches to fully actuate was excessive resistance in the pantograph assembly due to a lack of preventive maintenance. The root cause was the failure to recognize the sensitivity of the new breakers to the importance of MOC assembly maintenance. During the last refueling outage that ended July 2, 2001, 22 obsolete magnetic air DHP type breakers were replaced with vacuum element DHP-VR type breakers. The original DHP breakers 968-26158 RI (9/01)
Assessment of Safety Consequences
An evaluation was performed of the period of time from when the DHP-VR breakers were installed until the plant was shutdown as a result of this event. There was no time at which any of the affected systems were called ,ipon where they were unable to perform their required safety functions; therefore there were no safety consequences. Actuation force analysis performed on the MOC switch assemblies subsequent to plant shutdown showed that the reduced breaker applied force would not have resulted in a loss of any safety function.
Actions to Prevent Recurrence Additional corrective actions include establishing the preventive maintenance frequency and scope of work for the MOC switches, MOC switch linkage, and pantograph channels of all the 4160 VAC and 6900 VAC cubicle switchgears. A plant procedure will be revised to include lubrication and maintenance instructions for the pantograph and MOC linkage assemblies. The Circuit Breaker Program will be enhanced to provide guidance on circuit breaker and cell maintenance.
Previous Similar Events
Three previous similar events have been identified. Two cases were intermittent, could not be repeated, and both occurred in the same cubicle. In the first instance the cause was degradation in the MOC switch linkages. Corrective actions were to inspect all cubicles with the 22 DHP-VR type breakers installed and change the procedural guidance to lubricate the MOC switches that are in the DHP type switchgears.
In the second case, looseness with side-to-side movement in the pantograph was the cause.
Generic MOC linkage maintenance was a concern and corrective action was initiated to evaluate the preventive maintenance program for 211 MOC linkages and pantograph assemblies.
However this action was not scheduled to be complete on all 22 breakers until Jul:, 1, 2002.
The third case that occurred on January 17, 2002, was an unexpected alarm in the control room of a breaker trip that immediately cleared. The breaker functioned correctly and did not trip. The system engineer was concerned and a work order was initiated to address the failure, but the February 13, 2002 failure occurred before the work order was worked.
50-397
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05000255/LER-2002-001 | NONCOMPLIANCE WITH TECHNICAL SPECIFICATION REQUIREMENTS FOR SAFETY INJECTION TANK T-82D | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000219/LER-2002-001 | | 10 CFR 50.73(a)(2)(i) | 05000305/LER-2002-001 | | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000313/LER-2002-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000331/LER-2002-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000346/LER-2002-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000348/LER-2002-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000368/LER-2002-001 | | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000247/LER-2002-001 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | 05000261/LER-2002-001 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000263/LER-2002-001 | Mechanical Pressure Regulator Failure Causes Reactor Scram | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000266/LER-2002-001 | | 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System | 05000277/LER-2002-001 | | | 05000289/LER-2002-001 | | | 05000301/LER-2002-001 | | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000353/LER-2002-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000400/LER-2002-001 | | 10 CFR 50.73(a)(2)(iv), System Actuation | 05000397/LER-2002-001 | | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000361/LER-2002-001 | | | 05000454/LER-2002-001 | Multiple Main Steam Safety Valve Relief Tests Exceeded Required Tolerance Due to Disk to Nozzle Metallic Bonding and Setpoint Drift | 10 CFR 50.73(a)(2)(i)(b) | 05000483/LER-2002-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(iv), System Actuation | 05000370/LER-2002-001 | | | 05000362/LER-2002-001 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000369/LER-2002-001 | | | 05000348/LER-2002-002 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000305/LER-2002-002 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i) | 05000368/LER-2002-002 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000440/LER-2002-002 | Failure of the High Pressure Core Spray Pump to Start | 10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident | 05000247/LER-2002-002 | | 10 CFR 50.73(a)(2)(i) | 05000346/LER-2002-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000331/LER-2002-002 | | 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000266/LER-2002-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000282/LER-2002-002 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000361/LER-2002-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000289/LER-2002-002 | | | 05000301/LER-2002-002 | | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000352/LER-2002-002 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000313/LER-2002-002 | | 10 CFR 50.73(a)(2)(iv)(A), System Actuation | 05000483/LER-2002-002 | | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000331/LER-2002-003 | | 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown | 05000346/LER-2002-003 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000305/LER-2002-003 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | 05000313/LER-2002-003 | | 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded | 05000400/LER-2002-003 | Reactor Trip Due to Momentary Grid Undervoltage | | 05000454/LER-2002-003 | Two Automatic Reactor Trips Due to Reactor Coolant Overtemperature Conditions Caused by Digital Electrohydraulic Control System Circuit Card Failure Causing the Turbine Governor Valves To Close | | 05000348/LER-2002-003 | | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000397/LER-2002-003 | | | 05000247/LER-2002-003 | | 10 CFR 50.73(a)(2)(iv), System Actuation | 05000483/LER-2002-003 | 1 OF 4 | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000270/LER-2002-003 | | |
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