PNO-III-16-001, A, Perry Nuclear Plant, Unplanned Shutdown Greater than 72 Hours Due to Reactor Coolant System Leakage Exceeding Technical Specification Limits and Subsequent Plant Restart

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PNO-III-16-001A, Perry Nuclear Plant, Unplanned Shutdown Greater than 72 Hours Due to Reactor Coolant System Leakage Exceeding Technical Specification Limits and Subsequent Plant Restart
ML16036A186
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 02/05/2016
From:
NRC/RGN-III
To:
References
PNO-III-16-001A
Download: ML16036A186 (1)


PRELIMINARY NOTIFICATION February 5, 2016 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE - PNO-III-16-001A This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. Some of the information may not yet be fully verified or evaluated and is basically all that is known by the Region III staff on this date.

Facility Licensee Emergency Classification Perry Nuclear Power Plant Notification of Unusual Event FirstEnergy Nuclear Operating Company Alert Perry, OH Site Area Emergency Docket No. 05000440 General Emergency License No. NPF-58 X Not Applicable

SUBJECT:

UNPLANNED SHUTDOWN GREATER THAN 72 HOURS DUE TO REACTOR COOLANT SYSTEM LEAKAGE EXCEEDING TECHNICAL SPECIFICATION LIMITS AND SUBSEQUENT PLANT RESTART On January 23, 2016, at 2100 EST, the Perry Nuclear Power Plant commenced a controlled plant shutdown due to an increasing trend in reactor coolant system leakage in the drywell. At 2122 EST, leakage exceeded Technical Specification limits. On January 24, 2016, at 1007 EST with the plant at approximately 8 percent power, plant operators manipulated plant equipment to place the motor feed pump in service. During this operation, the reactor water level rose to the reactor trip set points. The reactor protection system auto-initiated, as designed, scramming the reactor. The licensee continues to investigate the cause for the feedwater transient and reactor water level rise.

Following the plant shutdown, licensee personnel entered the drywell and identified the leak on recirculation loop A pump discharge valve vent line, which is part of the reactor coolant system pressure boundary. As required by Technical Specifications, on January 24, 2016, at 2059 EST, the plant was cooled down to Mode 4 to conduct repairs. The licensee replaced the leaking portion of the vent line and made other repairs to the system. Following the repair activities, licensee personnel restarted the reactor on January 31, 2016. The leakage was contained in the plant. There was no impact on public health.

The State of Ohio has been notified.

This preliminary notification is issued for information only.

The resident inspector responded to the control room to monitor plant parameters and licensee actions. The NRC resident staff, assisted by inspectors from the NRC Region 3 Office, monitored licensee actions to identify the leak and the repair activities.

The information presented herein has been discussed with the licensee, and is current as of 1047 EST on February 5, 2016.

ADAMS Accession Number ML16036A186

Contact:

B. Dickson (630) 829-9827 Billy.Dickson@nrc.gov

PRELIMINARY NOTIFICATION February 5, 2016 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE - PNO-III-16-001A This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. Some of the information may not yet be fully verified or evaluated and is basically all that is known by the Region III staff on this date.

Facility Licensee Emergency Classification Perry Nuclear Power Plant Notification of Unusual Event FirstEnergy Nuclear Operating Company Alert Perry, OH Site Area Emergency Docket No. 05000440 General Emergency License No. NPF-58 X Not Applicable

SUBJECT:

UNPLANNED SHUTDOWN GREATER THAN 72 HOURS DUE TO REACTOR COOLANT SYSTEM LEAKAGE EXCEEDING TECHNICAL SPECIFICATION LIMITS AND SUBSEQUENT PLANT RESTART On January 23, 2016, at 2100 EST, the Perry Nuclear Power Plant commenced a controlled plant shutdown due to an increasing trend in reactor coolant system leakage in the drywell. At 2122 EST, leakage exceeded Technical Specification limits. On January 24, 2016, at 1007 EST with the plant at approximately 8 percent power, plant operators manipulated plant equipment to place the motor feed pump in service. During this operation, the reactor water level rose to the reactor trip set points. The reactor protection system auto-initiated, as designed, scramming the reactor. The licensee continues to investigate the cause for the feedwater transient and reactor water level rise.

Following the plant shutdown, licensee personnel entered the drywell and identified the leak on recirculation loop A pump discharge valve vent line, which is part of the reactor coolant system pressure boundary. As required by Technical Specifications, on January 24, 2016, at 2059 EST, the plant was cooled down to Mode 4 to conduct repairs. The licensee replaced the leaking portion of the vent line and made other repairs to the system. Following the repair activities, licensee personnel restarted the reactor on January 31, 2016. The leakage was contained in the plant. There was no impact on public health.

The State of Ohio has been notified.

This preliminary notification is issued for information only.

The resident inspector responded to the control room to monitor plant parameters and licensee actions. The NRC resident staff, assisted by inspectors from the NRC Region 3 Office, monitored licensee actions to identify the leak and the repair activities.

The information presented herein has been discussed with the licensee, and is current as of 1047 EST on February 5, 2016.

ADAMS Accession Number ML16036A186

Contact:

B. Dickson (630) 829-9827 Billy.Dickson@nrc.gov