View source for PNO-III-04-003, Shutdown of the Davis-Besse Nuclear Power Station Plant for Greater than 72 Hours

{{Adams
| number = ML040770652
| issue date = 03/17/2004
| title = PNO-III-04-003: Shutdown of the Davis-Besse Nuclear Power Station Plant for Greater than 72 Hours
| author name = Lipa C, Thomas S
| author affiliation = NRC/RGN-III/DRP
| addressee name = 
| addressee affiliation = 
| docket = 05000346
| license number = NPF-003
| contact person = 
| document report number = PNO-III-04-003
| document type = NRC Preliminary Notification of Event/Occurrence
| page count = 1
}}
{{#Wiki_filter:March 17, 2004 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE -- PNO-III-04-003 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without verification or evaluation, and is basically all that is known by the Region III staff on this date.
Facility                                             Licensee Emergency Classification Facility Name: Davis-Besse                           ___Notification of Unusual Event Licensee: FirstEnergy Nuclear Operating Co.              Alert City, State: Oak Harbor, Ohio                            Site Area Emergency Docket: [050-346]                                        General Emergency License: NPF-3                                        X Not Applicable

==SUBJECT:==
Shutdown of the Davis-Besse Nuclear Power Station Plant for Greater Than 72 Hours DESCRIPTION: On March 16, 2004, the Davis-Besse Nuclear Power Station informed the resident inspectors that a plant shut down and cooldown would be conducted due to the equipment issue summarized below.
During re-alignment of the main feedwater control system supplying steam generator 1-1, operators did not observe expected feedwater flow when placing the system in automatic operation. The system was returned to the startup feedwater control mode, and subsequent investigation indicated that the valve stem had separated from the valve disc inside the feedwater block isolation valve for the flowpath to steam generator 1-1. To establish necessary isolation conditions for replacing the valve, the licensee is conducting a plant shutdown and cooldown to Mode 4 (200oF < reactor coolant temperature
< 280oF). The plant entered Mode 2 (0 percent # reactor power # 5 percent) at 11:30 a.m. on March 17, 2004. The duration of this outage is expected to exceed 72 hours. Following repairs and testing, the licensee will commence a plant heatup and reactor startup. The NRC will continue its round the clock inspection coverage of plant activities, including monitoring the plant shutdown, equipment repairs, transition to Modes 3, 2, and 1, and power ascension.
The State of Ohio has been notified of this issue. This PN was discussed with the licensee to confirm the technical accuracy prior to issuance. This information is current as of 11:30 am EST.
CONTACTS: Christine Lipa CAL, (630) 829-9619 Scott Thomas CST1, (419) 244-4494}}

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