05000324/LER-2004-002

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LER-2004-002, Reactor Shutdown Required by Technical Specifications Due to Containment Vacuum Breaker Not Closed
Brunswick Steam Electric Plant (Bsep)
Event date: 07-29-2004
Report date: 09-27-2004
Reporting criterion: 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown

10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material
3242004002R00 - NRC Website

Energy Industry Identification System (MS) codes are identified in the text as [XX].

INTRODUCTION

On July 29, 2004, at approximately 0942 hours0.0109 days <br />0.262 hours <br />0.00156 weeks <br />3.58431e-4 months <br />, the Unit 2 control room operators commenced a reactor shutdown from 88 percent of rated thermal power (RTP) required by Technical Specification (TS) Limiting Condition for Operation (LCO) 3.6.1.6, "Suppression Chamber-to-Drywell Vacuum Breakers," due to an open vacuum breaker [VACB]. At 1214 hours0.0141 days <br />0.337 hours <br />0.00201 weeks <br />4.61927e-4 months <br />, notification was made to the NRC (i.e., Event Number 40905) in accordance with 10 CFR 50.72(b)(2)(i) for the initiation of a nuclear plant shutdown required by the plant's TS. At 1517 hours0.0176 days <br />0.421 hours <br />0.00251 weeks <br />5.772185e-4 months <br />, a manual Reactor Protection System (RPS) [JC] trip was inserted to shut down the reactor from approximately 23 percent of RTP. A follow-up notification was made to the NRC Operations Center at 1654 hours0.0191 days <br />0.459 hours <br />0.00273 weeks <br />6.29347e-4 months <br /> to confirm the completed successful shutdown. During this event, all emergency core cooling systems (ECCS), emergency diesel generators, and the reactor core isolation cooling (RCIC) system were operable. This event is being reported in accordance with 10 CFR 50.73(a)(2)(i)(A) as the completion of a nuclear plant shutdown required by the plant's TS and 10 CFR 50.73(a)(2)(v)(C) and (D) as a condition that could have prevented the fulfillment of the safety function of structures or systems needed to control the release of radioactive material and mitigate the consequences of an accident.

EVENT DESCRIPTION

On July 29, 2004, at approximately 0351 hours0.00406 days <br />0.0975 hours <br />5.803571e-4 weeks <br />1.335555e-4 months <br />, control room operators authorized testing of suppression chamber-to-drywell [BF] vacuum breakers in accordance with periodic test (OPT-02.3.1) "Suppression Chamber-to-Drywell Vacuum Breakers Operability Test". This test verifies the operability of the ten suppression chamber-to-drywell vacuum breakers in accordance with TS Surveillance Requirement (SR) 3.6.1.6.2, which requires performing a functional test of each required vacuum breaker every 31 days and within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after any discharge of steam to the suppression chamber from any source. At 0357 hours0.00413 days <br />0.0992 hours <br />5.902778e-4 weeks <br />1.358385e-4 months <br />, the plant entered TS LCO 3.6.1.6 Condition B (i.e., one suppression chamber-to-drywell vacuum breaker not closed) when vacuum breaker 2-CAC-X18D (Manufacturer: GPE Controls, Model No.: LD-240-192) continued to indicate "open" after testing. TS LCO 3.6.1.6 Required Action B.1 states to close the open vacuum breaker within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Operators attempted to cycle 2-CAC-X18D, under Senior Reactor Operator direction, and attempted performance of OPT-02.3.1a, "Suppression Pool to Drywell Vacuum Breaker Position Check (Alternate Method)," which involves the observation of differential pressures between the drywell and suppression pool to verify proper vacuum breaker position, but the vacuum breaker continued to indicate "open." Additional attempts by operators and Instrumentation and Control (I&C) technicians to verify the vacuum breaker position were unsuccessful, and, at 0757 hours0.00876 days <br />0.21 hours <br />0.00125 weeks <br />2.880385e-4 months <br />, the plant entered TS LCO 3.6.1.6 Condition C. TS LCO Required Actions C.1 and C.2 require the plant to be in Mode 3 (i.e., Hot Shutdown) within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to be in Mode 4 (i.e., Cold Shutdown) within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

On July 29, 2004, at 0921 hours0.0107 days <br />0.256 hours <br />0.00152 weeks <br />3.504405e-4 months <br />, operators secured from OPT-02.3.1a, and at 0942 hours0.0109 days <br />0.262 hours <br />0.00156 weeks <br />3.58431e-4 months <br />, commenced a reactor shutdown from approximately 88 percent RTP. At approximately 1211 hours0.014 days <br />0.336 hours <br />0.002 weeks <br />4.607855e-4 months <br />, I&C technicians attempted to agitate the test solenoid for vacuum breaker 2-CAC-X18D by varying the voltage and EVENT DESCRIPTION (continued) frequency of the electrical power to the solenoid. The attempt was unsuccessful at closing the vacuum breaker. Operators continued to reduce reactor power and, at 1517 hours0.0176 days <br />0.421 hours <br />0.00251 weeks <br />5.772185e-4 months <br />, operators inserted a manual RPS trip to shut down the reactor from approximately 23 percent RTP.

All control rods fully inserted into the core and no ECCS/RCIC actuations or safety relief valve lifts occurred. Following the scram, an expected reactor vessel coolant level shrink occurred, causing coolant level to decrease below the Low Level 1 setpoint. This coolant level decrease resulted in a Primary Containment Isolation System (PCIS) isolation signal to Group 2 (i.e., Drywell Equipment and Floor Drain, Traversing In-core Probe, Residual Heat Removal (RHR) Discharge to Radwaste, and RHR Process Sample) primary containment isolation valves (PCIVs), Group 6 (i.e., Containment Atmosphere Control/Dilution, Containment Atmosphere Monitoring, and Post Accident Sampling System) PCIVs, and Group 8 (i.e., RHR Shutdown Cooling Suction and RHR Inboard Injection) PCIVs. The isolation signal closed all of the PCIVs that were open at the time of the expected actuation. On July 30, 2004, at approximately 0025 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />, the plant entered Mode 4.

EVENT CAUSE

The cause of the event is attributed to mechanical interference between a portion of the hinge assembly, which actuates an "open" position indicating limit switch, and the fit-up bushing (i.e., listed in the vendor manual as a retaining ring) that houses the limit switch. A contributing cause was the sticking of the test actuator for 2-CAC-X18D in the "open" position.

After the plant was shut down, the suppression chamber was accessed and vacuum breaker 2-CAC-X18D was inspected. Engineering and maintenance personnel found 2-CAC-X18D fully open with the pneumatic test actuator in the extended (i.e., open) position. When operations attempted to cycle 2-CAC-X18D with the investigators present, the actuator, which utilizes pressurized nitrogen to extend and spring to retract, moved only approximately one eighth of an inch, and the vacuum breaker remained open. Actions to ensure that the test actuator was being properly vented, when the vacuum breaker test switch was taken to the "closed" position, did not result in the vacuum breaker closing. Investigating personnel then reached inside the vacuum breaker and attempted to move the pallet side-to-side in an effort to determine if the hinge assembly was bound. Although the pallet could not be moved in the side-to-side direction, when it was released, the pallet and actuator arm swung closed as the test actuator returned to the retracted position.

Additional testing of the vacuum breaker demonstrated that the sticking open condition was repeatable but not consistent. Further evaluation also demonstrated that the pallet would stick open without the additional support of the test actuator (i.e., with the test actuator retracted). Visual inspection from inside the vacuum breaker identified mechanical interference between the "open" limit switch fit-up bushing and the portion of the hinge assembly, which actuates the limit switch. The mechanical interference occurred when the vacuum breaker was at or near the full "open" position and would cause the vacuum breaker to stick open.

Inspection of the disassembled test actuator indicated uncharacteristic wear corresponding to the area where the actuator was found sticking. This wear came from side loading on the actuator piston caused by binding EVENT CAUSE (continued) of the pallet assembly in the last few degrees of stroke to the "open" position (i.e., the binding of the pallet assembly hinge caused the abnormal loading and wear on the actuator).

The root cause of the condition is attributed to insufficient procedural detail and guidance. None of the maintenance or test procedures applicable to the vacuum breakers contained adequate guidance to address potential binding when adjusting the vacuum breaker hinges or the "open" limit switches. No cautions pertaining to potential interference were provided in the procedures or vendor manual and no checks were provided after adjustment of the components. Vacuum breaker 2-CAC-X18D was disassembled, inspected, and reassembled, along with four other vacuum breakers during the spring 2003, refueling outage. This was most likely the time that the interference condition was introduced.

A contributing cause identified during the investigation was that the suppression chamber-to-drywell vacuum breaker test actuators did not have any preventive maintenance tasks established for the periodic maintenance of the components.

CORRECTIVE ACTIONS

For vacuum breaker 2-CAC-X18D, the "open" limit switch, whose fit-up bushing was causing interference, was replaced and the fit-up bushing was properly adjusted to preclude any further interference with the hinge. Additionally, the test actuator was replaced, and 2-CAC-X18D was retested satisfactorily in accordance with plant procedures. The remaining nine suppression chamber-to-drywell vacuum breakers were inspected and no other conditions of interference between the "open" limit switch fit-up bushings and the vacuum breaker hinge assemblies were identified.

Although the remaining nine vacuum breakers were stroke tested and had acceptable results, two additional conditions were identified with test actuators. For vacuum breaker 2-CAC-X18F, the test actuator was found to have an approximate ten second retraction time as compared to the two to three second stroke time observed for the other actuators. The governor/control valve was replaced and a normal stroke time was restored. For vacuum breaker 2-CAC-X18H, the test actuator cylinder was observed leaking through a crack in the cylinder wall. The test actuator was replaced. Both vacuum breakers were retested satisfactorily in accordance with plant procedures. Neither of these as-found conditions adversely affected vacuum breaker operability.

Due to the interference condition found on the Unit 2 vacuum breaker, consideration was given to the possibility of the same condition existing on Unit 1 suppression chamber-to-drywell vacuum breakers.

OPT-02.3.1 was revised to include provisions for recording "open" and "closed" stroke time data to trend actuator/vacuum breaker performance. The ten Unit 1 suppression chamber-to-drywell vacuum breakers were tested in accordance with OPT-02.3.1 and were found to be performing satisfactorily. On August 15, 2004, with Unit 1 shutdown due to Hurricane Charley, engineering and maintenance personnel entered the suppression chamber to inspect and test the vacuum breakers. Visual inspection of the internals of the ten vacuum breakers found no conditions of interference between "open" limit switch fit-up bushings and the vacuum breaker hinge assemblies. Each vacuum breaker was stroked from the control room while being CORRECTIVE ACTIONS (continued) observed locally. All ten vacuum breakers stroked satisfactorily and smoothly; although vacuum breaker 1CAC-X18C had one non-repeatable "open" stroke time of 6.74 seconds. As a precautionary measure, the governor/control valve was replaced, and the vacuum breaker was retested satisfactorily.

Appropriate preventive maintenance activities for the suppression chamber-to-drywell vacuum breaker test actuators are being developed. Implementation of the activities will begin during the next refueling outage for each unit.

To prevent recurrence of this event, Preventive Maintenance procedure (OPM-VBR500), "GPE/Singer Vacuum Breakers, Models LD-240-192 and 193 Inspection," is being revised to include provisions to:

1. Check for hinge/fit-up bushing binding whenever a disassembly inspection is performed.

2. Perform a more thorough post-test examination of the vacuum breakers and test actuators to detect and address erratic stroking, binding, and cylinder leaks.

3. Rebuild the test actuators at a set frequency.

4. Adjust "open" limit switches and caution personnel relative to possible interference problems if an adjustment is performed.

The revision to OPM-VBR500 will be effective by December 1, 2004.

SAFETY ASSESSMENT

The safety significance of this occurrence is considered minimal. The function of the suppression chamber­ to-drywell vacuum breakers is to relieve vacuum in the drywell. There are 10 internal vacuum breakers located on the vent header between the drywell and the suppression chamber, which allow flow from the suppression chamber atmosphere to the drywell when the drywell is at a negative pressure with respect to the suppression chamber. Each vacuum breaker is self actuating, similar to a check valve, and can be remotely operated for testing purposes. The safety analyses assume that these vacuum breakers are closed initially. With one vacuum breaker not closed, communication between the drywell and suppression chamber airspace could occur, and as a result, there is the potential for primary containment over pressurization due to this bypass leakage if a loss of coolant accident (LOCA) were to occur. A short time is allowed to close the vacuum breaker due to the low probability of an event that would pressurize primary containment.

The vacuum breaker 2-CAC-X18D was open in Mode 1 for approximately 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> and 40 minutes, and in Mode 3 for approximately 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> and 8 minutes. For these periods of time for which the vacuum breaker is required to be closed, it is conservatively assumed that the safety function of containment was lost. This assumption is considered to be conservative because only minimal mechanical agitation was applied to allow the pallet to swing closed. Accident conditions would likely result in mechanical agitation greater than that required to free the pallet. During the times that the vacuum breaker was open and required to be closed, operators were aware of the condition and were in compliance with the TS LCO 3.6.1.6 Required Actions to attempt to close the vacuum breaker and shut down the plant.

SAFETY ASSESSMENT (continued) The condition that led to the vacuum breaker being stuck in the open position was most likely introduced during the spring 2003, refueling outage, when preventive maintenance was performed, which included disassembly of the pallet/hinge and replacement of the eccentric hinge bushings. Analyses postulating 2-CAC-X18D being initially closed and sticking open during either a large-break or small-break LOCA conclude that the safety function of primary containment would be maintained.

PREVIOUS SIMILAR EVENTS

A review of events occurring within the past three years has not identified any previous similar occurrences.

COMMITMENTS

Those actions committed to by Progress Energy Carolinas, Inc. (PEC) in this document are identified below.

Any other actions discussed in this submittal represent intended or planned actions by PEC. They are described for the NRC's information and are not regulatory commitments. Please notify the Manager - Support Services at BSEP of any questions regarding this document or any associated regulatory commitments.

To prevent recurrence of this event, OPM-VBR500 is being revised to include provisions to:

1. Check for hinge/fit-up bushing binding whenever a disassembly inspection is performed.

2. Perform a more thorough post-test examination of the vacuum breakers and test actuators to detect and address erratic stroking, binding, and cylinder leaks.

3. Rebuild the test actuators at a set frequency.

4. Adjust "open" limit switches and caution personnel relative to possible interference problems if an adjustment is performed.

The revision to OPM-VBR500 will be effective by December 1, 2004.