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Event Notification Report for January 27, 2004

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
01/26/2004 - 01/27/2004

EVENT NUMBERS
404824048340484

Power Reactor
Event Number: 40482
Facility: SAINT LUCIE
Region: 2     State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: A. T. HALL
HQ OPS Officer: DICK JOLLIFFE
Notification Date: 01/27/2004
Notification Time: 11:16 [ET]
Event Date: 01/27/2004
Event Time: 08:05 [EST]
Last Update Date: 01/27/2004
Emergency Class:
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CAUDLE JULIAN (R2)
Power Reactor Unit Info
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
OFFSITE NOTIFICATION OF LOSS OF COMMUNICATIONS

"On January 27, 2004, at 0805 hours, the Unit 1 Control Room Bell (Commercial) telephones, Unit 1 State Warning Point / Hot Ringdown phone, the Unit 1 NRC Emergency Notification System phone, and the Unit 1 ESATCOM phone communications capabilities were lost, due to inadvertent severing of cables. The Technical Support Center (adjacent to Unit 1 Control Room), and Unit 2, communications telephones, including the Bell (Commercial) phones, State Warning Point / Hot Ringdown phones, NRC Emergency Notification System phones, and ESATCOM phones, were verified operational and satisfactory. The Unit 1 Cellular Telephone and the Portable (Wireless) Telephone continued to remain operable. The licensee has restored all these temporarily disrupted communications capabilities as of 01/27/04 @ 1100 hours. State and Local Government Agencies, and the NRC Resident, have been notified.

"This non-emergency notification is being made pursuant to 10 CFR 50.72 (b)(1)(xi), due to the 'Other Government Notifications' (State & Local Government Agencies), NUREG-1022 Section 3.2.12, and 10 CFR 50.72(b)(3)(xiii), due to the 'Loss of Emergency Assessment, Offsite Response, or Communications Capability,' NUREG-1022 Section 3.2.13."

This event had no effect on Unit 2.


Power Reactor
Event Number: 40483
Facility: SUMMER
Region: 2     State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP
NRC Notified By: EDDIE BYARS
HQ OPS Officer: BILL GOTT
Notification Date: 01/27/2004
Notification Time: 13:33 [ET]
Event Date: 01/27/2004
Event Time: 12:00 [EST]
Last Update Date: 01/29/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
GEORGE KUZO (R2)
Power Reactor Unit Info
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
LOSS OF ENS TELEPHONE AND SIREN SYSTEM

The licensee reported intermittent problems with the ENS telephone and Early Warning Siren System (EWSS) capability. EWSS capability is less than 75% and is currently 58%. The ENS phone system is repaired. Ice storms are the cause of the communication problems.

The licensee notified the NRC Resident Inspector.

* * * UPDATE 1138 EST ON 1/29/04 FROM ROBERT SWEET TO S. SANDIN * * *

The licensee is updating this report to indicate that greater than 75% of the EWSS capability has been restored. The licensee informed the NRC Resident Inspector. Notified R2DO(Kuzo).


Power Reactor
Event Number: 40484
Facility: CALLAWAY
Region: 4     State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: EURMAN HENSON
HQ OPS Officer: BILL GOTT
Notification Date: 01/27/2004
Notification Time: 22:15 [ET]
Event Date: 01/27/2004
Event Time: 17:30 [CST]
Last Update Date: 01/28/2004
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
WILLIAM JOHNSON (R4)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Standby
Event Text
AUTOMATIC REACTOR TRIP

"At 1730, 1/27/04, Callaway Plant experienced a reactor trip. Auxiliary feedwater actuated as expected to stabilize steam generator levels. All other plant systems responded as expected. At present the cause of the reactor trip is undetermined. Initial indications are that there were no voltage or frequency perturbations on the electrical grid and that the trip signal originated from Callaway's switchyard breaker circuitry. Plant staff is currently engaged in a review of all indications that occurred at the time of the trip and systematically investigating potential problem areas in an effort to identify the cause of the trip."

The licensee also reported that all control rods inserted on the reactor trip, no primary or secondary system relief valves operated, and that reactor temperature is being maintained using steam dump to the condenser. Steam generator water levels are being maintained using auxiliary feedwater. The station electrical system is available and in a normal configuration.

The licensee notified the NRC Resident Inspector.

* * * UPDATE 0250 EST ON 1/28/04 FROM EURMAN HENSON TO S. SANDIN * * *

The licensee provided the following information as an update to their initial report:

"The cause of the reactor trip has been identified as a failed electrical relay in the main generator protection circuitry. The relay is designed to sense a fault in the main electrical generator and trip the generator output breakers. The failed relay was designated as a 321/G relay and provides phase fault backup protection to prevent exceeding thermal limits of the stator windings.

"After determining the cause of the reactor trip, preparations for a reactor startup are in progress."

The licensee will inform the NRC Resident Inspector. Notified R4DO(Johnson).