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Event Notification Report for October 15, 2004

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/14/2004 - 10/15/2004

** EVENT NUMBERS **


41119 41120 41121

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Power Reactor Event Number: 41119
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: RONALD TIMOTHY GREEN
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/14/2004
Notification Time: 14:40 [ET]
Event Date: 09/10/2004
Event Time: 17:30 [EDT]
Last Update Date: 10/14/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
BRIAN MCDERMOTT (R1)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation

Event Text

INVALID ACTUATION OF STEAM DRIVEN AUXILIARY FEEDWATER PUMP

"On September 10, 2004 at 1730 hours, one steam supply isolation valve (TV-1MS-105B) to the steam-driven Auxiliary Feedwater System Pump (FW-P-2) unexpectedly opened at Beaver Valley Power Station Unit No. 1, causing this pump to commence feeding all three steam generators. FW-P-2 functioned as designed with steam being supplied to the pump's steam-drive turbine. Neither of the other two Auxiliary Feedwater System motor-driven pumps were actuated at Beaver Valley Power Station Unit No. 1. This initially caused Steam Generator Water Level Deviations alarms on all three steam generators. The steam generator levels returned to their normal operating levels via the automatic level control system. After determining that there was no demand for this Auxiliary Feedwater System pump to be operating, the control room crew attempted to close TV-1MS-105B from the control room, without success. The upstream motor-operated isolation valve (MOV-1MS-105) to TV-1MS-105B was then closed to stop steam flow to FW-P-2, terminating the auxiliary feedwater flow to the steam generators.

"No maintenance or tests were ongoing with the Auxiliary Feedwater System at the time. Subsequent investigation determined that this event occurred due to a failure of an instrument card within the Solid State Protection System which caused TV-1MS-105B to inappropriately open. Therefore this actuation was not initiated by a valid actuation signal.

"This event is reportable pursuant to 10 CFR 50.73(a)(2)(iv)(A) since it involved an actuation of a PWR auxiliary feedwater water system train as per 10 CFR 50.73(a)(2)(iv)(B)(6). This pump start was not part of a pre-planned sequence and did not occur with this system properly removed from service.

"However, pursuant to 10 CFR 50.73(a)(1), this event is being reported via this telephone notification instead of submitting a written Licensee Event Report since the automatic actuation of the Auxiliary Feedwater System pump was not generated by a valid actuation."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 41120
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: DAVID KARST
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/14/2004
Notification Time: 15:52 [ET]
Event Date: 10/14/2004
Event Time: 13:44 [CDT]
Last Update Date: 10/14/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xii) - OFFSITE MEDICAL
Person (Organization):
BRENT CLAYTON (R3)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling Shutdown 0 Refueling Shutdown

Event Text

OFFSITE MEDICAL

At 1330 EDT on 10/14/04, the control room was notified that a worker in the Containment Building had a potential neck injury. An ambulance was requested to transport the worker. The individual was taken directly from the Containment building to the ambulance and a HP Technician with a radiation detector accompanied the individual to the hospital. A contamination survey was not completed on site. At 1344, the HP Tech and worker left the site for the hospital. The Shift Manager contacted the hospital to alert them of the potential for contamination on the injured person. At 1430, HP Technician confirmed that there was no contamination present.

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 41121
Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: SEAN DAVISON
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/14/2004
Notification Time: 18:48 [ET]
Event Date: 10/14/2004
Event Time: 16:10 [EDT]
Last Update Date: 10/14/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
DAVID AYRES (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

OFFSITE NOTIFICATION FOR EXCEEDING STATE PERMIT LIMITS

"At 1610 EDT on 10/14/04, Florida Power and Light Company notified the Florida Department of Environmental Protection (FDEP) that St. Lucie Station exceeded a permit allowance limitation for operating time on one of the station's administrative office building emergency diesel generators. FDEP notification was required per the general conditions of the permit. The permit allows 200 hours of run time per year. This particular generator logged 222.9 hours of run time in September 2004. The additional usage was directly related to Hurricane Frances and Jeanne. This particular generator was used to supply the South Service Building with electricity during the two hurricanes. The South Service Building housed plant support staff during the hurricanes.

"This non-emergency notification is being made pursuant to 10CFR50.72(b)(2)(xi) due to FDEP notification."

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Friday, March 30, 2012
Friday, March 30, 2012