PNO-III-13-001, Unplanned Shutdown Greater than 72 Hours Due to an Automatic Reactor Protection System Actuation

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PNO-III-13-001, Unplanned Shutdown Greater than 72 Hours Due to an Automatic Reactor Protection System Actuation
ML13029A646
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 01/29/2013
From: Michael Kunowski
NRC/RGN-III/DRP/B5
To:
References
PNO-III-13-001
Download: ML13029A646 (2)


PRELIMINARY NOTIFICATION January 29, 2013 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE - PNO-III-13-001 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 AN AUTOMATIC REACTOR PROTECTION SYSTEM ACTUATION On Saturday, January 26, 2013, at 12:34 p.m. EST, the Perry operators restarted the reactor following repairs to the Volt AC electrical system that had caused a transient in the feedwater system resulting in an unplanned shutdown. The unit synchronized to the grid at 3:43 p.m. EST on January 27, 2013.

Previously, on January 22, 2013, at approximately 3:32 a.m. EST, an automatic Reactor Protection System (RPS) actuation occurred at the Perry Nuclear Power Plant, Unit 1. At the time of the event, the plant was in Mode 1 at 100 percent power. All control rods inserted into the reactor core and the plant reached cold shutdown at approximately 8:36 p.m. on January 23.

The RPS actuation was initiated by a low reactor water level (Level 3 - 178") signal. In response to the RPS actuation and subsequent reactor Level 2 (130") signal, the High Pressure Core Spray (HPCS) system and Reactor Core Isolation Cooling (RCIC) system both actuated and injected to maintain reactor coolant level. The reactor level was maintained in its normal band by the feedwater system and decay heat was removed by turbine bypass valves to the condenser (both HPCS and RCIC had been returned to standby). The plant was in the normal electrical line-up with all three Emergency Diesel Generators operable and available, if needed.

The NRC resident inspectors responded to the site when the event occurred and closely monitored the licensee's activities, including plant startup.

This preliminary notification is issued for information only.

The State of Ohio has been informed.

Region III received initial notification of this occurrence by a telephone call from Perry to the senior resident inspector (SRI) at approximately 3:32 a.m. EST on January 22, 2013 (refer to Event Notification 48688).

The information herein has been discussed with the licensee, and is current as of 10:19 a.m.

EST on January 29, 2013.

ADAMS Accession Number: ML13029A646

Contact:

M. Kunowski (630) 829-9618 Michael.Kunowski@nrc.gov