05000354/LER-2013-011

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LER-2013-001, Filtration, Recirculation, and Ventilation System Exceeded Technical Specification Allowed Outage Time
Hope Creek Generating Station
Event date: 06-10-2013
Report date: 03-25-2015
Reporting criterion: 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications

10 CFR 50.73(a)(2)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident

10 CFR 50.73(a)(2)(v)(C), Loss of Safety Function - Release of Radioactive Material
3542013001R00 - NRC Website

PLANT AND SYSTEM IDENTIFICATION

General Electric — Boiling Water Reactor (BWR/4) Filtration, Recirculation and Ventilation System {BH/FIC}* *Energy Industry Identification System {EllS} codes and component function identifier codes appear as {SS/CCC}

IDENTIFICATION OF OCCURRENCE

Event Date: 6/10/13 Discovery Date: 2/13/15

CONDITIONS PRIOR TO OCCURRENCE

Hope Creek was in Operational Condition 1 at 100 percent rated thermal power (RTP).

DESCRIPTION OF OCCURRRENCE

On 6/24/13, at 11:34 EDT, the B Filtration, Recirculation and Ventilation System (FRVS) recirculation unit was declared inoperable when the associated fan tripped on low flow following a manual start signal. The system was being placed in service for scheduled surveillance testing. Maintenance technicians subsequently identified and repaired a loose electrical connection in the fan flow controller. The B FRVS recirculation unit was restored to an OPERABLE condition on 6/24/13, at 16:30. The flow controller is a Westinghouse Veritrak Model 751C.

The B FRVS recirculation unit surveillance test was completed satisfactorily on 6/2/13. Maintenance was performed on the fan flow controller on 6/3/13 to repair a faulty indication. Following the repair, a post maintenance test (PMT) was performed to verify electrical connectivity of the flow control circuit. However, the fan was not placed in service as part of the PMT to verify unit operation. The fan was not operated again until 6/24/13, when it tripped upon a manual start.

Plant Technical Specifications require that with one or two FRVS recirculation units inoperable, the units shall be returned to OPERABLE within 7 days, or the plant shall be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Contrary to this requirement, the FRVS recirculation unit was inoperable from 6/3/13 at 15:38, until 6/24/13 at 16:30, a period of 21 days, 52 minutes. During this period, the plant was shut down for an unplanned outage and was in Operational Condition 4, COLD SHUTDOWN, from 6/13/13 at 16:00, until 6/17/13 at 10:02, when a plant startup was commenced. During this time the LCO for the B FRVS recirculation unit was not applicable.

There were two periods of Technical Specification non-compliance due to the B FRVS recirculation unit inoperability.

The first was from 6/10/13 at 15:38, when the 7-day allowed outage time was exceeded. This lasted until 6/13/13 at 16:00, when the plant was placed in HOT SHUTDOWN, a period of 3 days, 22 minutes. The second non-compliance occurred on 6/17/13 at 10:02 when a mode change was made into Operational Condition 2, STARTUP, with the B FRVS recirculation unit inoperable, contrary to the requirements of Technical Specification 3.0.4. The plant operated for 7 days, 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, 28 minutes, with the B FRVS recirculation unit inoperable, until 6/24/13 at 16:30, when the B FRVS recirculation fan was restored to OPERABLE.

In addition, the A Emergency Diesel Generator (EDG) was inoperable for barring on 6/18/13, from 19:41 until 19:52, a period of 11 minutes. With the A EDG inoperable, the A and E FRVS recirculation units did not have a backup emergency power supply. As a result, three FRVS recirculation units were inoperable for a period of 11 minutes. Per the Hope Creek UFSAR, a minimum of four FRVS recirculation units are required for the first 10 minutes following a design basis accident to provide cooling to the Reactor Building air, and to reduce the offsite dose.

the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person Is not required to respond to, the information collection.

This LER is being submitted outside the 60-day reporting requirement. A recent re-evaluation of the details of the events between 6/3/13 and 6/24/13 determined that the operability of the B FRVS recirculation unit could not be assured, and therefore the condition is reportable.

CAUSE OF EVENT

The event was caused by a loose electrical pin connector that was not fully seated and locked into the connector, and was not identified by the post maintenance test performed. This pin provides the signal to operate the recirculation fan inlet damper. With the loss of this connection the damper could not operate, resulting in a low flow condition and a subsequent fan trip.

SAFETY CONSEQUENCES AND IMPLICATIONS

The FRVS recirculation system is an engineered safety feature (ESF) system, which operates during accident conditions to filter, recirculate and cool the secondary containment. There are a total of six FRVS recirculation units, of which four are required to operate following design basis accident conditions.

During the period from 6/3/13, 15:38, until 6/24/13, 16:30, there were at least four OPERABLE FRVS recirculation units, with one exception. On 6/18/13, the A EDG was inoperable for 11 minutes for barring-over. During this time, the A and E FRVS recirculation units were inoperable along with the B FRVS recirculation unit. The A EDG was available for manual starting during this period. Therefore, there was no significant impact on nuclear safety.

SAFETY SYSTEM FUNCTIONAL FAILURE

A review of this event determined that a Safety System Functional Failure (SSFF) did not occur as defined in Nuclear Energy Institute (NEI) 99-02, "Regulatory Assessment Performance Indicator Guideline.

PREVIOUS EVENTS

A review of events at Hope Creek involving the FRVS system was performed for a three year period prior to the event through 3/11/15. No similar events were identified.

CORRECTIVE ACTIONS

The FRVS fan flow controller was repaired and the system was returned to service.

Other corrective actions are documented in the licensee's corrective action program.

COMMITMENTS

This LER contains no regulatory commitments.