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Event Notification Report for January 17, 2008

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/16/2008 - 01/17/2008

** EVENT NUMBERS **


43907 43909

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Power Reactor Event Number: 43907
Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: TOM JESSESSKY
HQ OPS Officer: JEFF ROTTON
Notification Date: 01/15/2008
Notification Time: 16:14 [ET]
Event Date: 01/15/2008
Event Time: 14:15 [CST]
Last Update Date: 01/16/2008
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
ANNE MARIE STONE (R3)
THOMAS BLOUNT (IRD)
MARY JANE ROSS-LEE (NRR)
JIM DYER (NRR)
JAMES CALDWELL (R3)
VICENTE GOMEZ (DHS)
MIKE EACHES (FEMA)

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

UNUSUAL EVENT - LOSS OF OFFSITE POWER

"At 1404 1/15/2008, Central time, Point Beach experienced a loss of Unit 1X-04, Low Voltage Station Auxiliary Transformer. This loss has caused Point Beach to declare an Unusual Event (SU 1.1, Loss of all Offsite Power to essential busses for greater than 15 minutes.)

"The loss of Unit 1X-04 transformer is under investigation.

"All equipment operated properly with the exception of 1B-04, 'B' train 480 VAC Safeguards Bus, supply breaker opened for unknown reasons.

"The licensee notified the NRC Resident Inspector.

"Preparations are underway for a Unit 1 shutdown."

Both Unit 1 EDGs are running and supplying Unit 1 safeguard buses. Non-safety buses are powered from an auto transfer that occurred after the loss of 1X-04. No impact on Unit 2 due to the Unit 1 electrical transient. Licensee notified state and local emergency management agencies.

* * * UPDATE FROM DENNY SMITH TO JEFF ROTTON AT 2300 ON 1/15/08 * * *

"On 1/15/08 at 1941 central time, FPL Energy Point Beach, LLC issued a press release concerning the Unusual Event at Point Beach that was declared on 1/15/08 at 1415 central time. The Unusual Event was reported under EN# 43907 and occurred due to the loss of all offsite power to essential busses for greater than 15 minutes from the failure of the Unit 1 X-04, Low Voltage Station Auxiliary Transformer.

"The NRC Resident Inspector has been informed of the press release and this subsequent notification."

* * * UPDATE FROM RICK ROBBINS TO JOE O'HARA AT 1816 EST ON 1/16/08 * * *

"At 1404 on 1/15/08 central time, Point Beach experienced a loss of Unit 1 X-04, Low Voltage Station Auxiliary Transformer. This loss caused Point Beach to declare an Unusual Event and that was reported under EN# 43907. Technical Specification 3.8.1.B, Associated unit's 13.8/4.16 kv (X04) transformer inoperable, was not met as of 1404 on 1/15/08 and this LCO has a Required Action to restore the (X04) transformer to Operable status with a Completion time of 24 hours.

"At 1404 1/16/08 the LCO was still not met and Unit 1 entered Technical Specification 3.8.1.H Required Action and associated Completion Time Not met, with a required action to be in Mode 3 in 6 hours and Mode 5 in 36 hours.

"This Event Notification Worksheet is for the initiation of the Technical Specification Required reactor shutdown that commenced at 1549 on 1/16/08, per 10 CFR 50.72(b)(2)(i)."

The licensee notified the NRC Resident Inspector.

Notified R3DO(Stone), NRR EO(Evans), and IRD(Blount).

* * * UPDATE FROM RICK ROBBINS TO JOE O'HARA AT 2222 EST ON 1/16/08 * * *

"Update: At 1947 CST on 01/16/08, the Unit 1 reactor reached MODE 3, completing the required Technical Specification Shutdown. Offsite power has been restored to the essential busses by paralleling from Unit 2 4160 V buses and the Emergency Diesel Generators G-01 and G-03 have been placed back to a normal standby alignment. The unit is being taken to MODE 5 in accordance with plant TS requirements.

"This update to EN #43907 also reports the termination of the Unusual Event [AT 2035 CST] SU1.1, Loss of all offsite power to essential buses for greater than 15 minutes initially reported via EN #43907. The State of Wisconsin and the counties of Kewaunee and Manitowoc were notified of the termination via the Nuclear Accident Reporting System (NARS) at 2041 on 1/16/08."

The licensee notified the NRC Resident Inspector.

Notified R3DO(Stone), NRR EO(Evans), NRR ET(Dyer), DHS(Gray), FEMA(Dunker), and IRD(Blount).

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Power Reactor Event Number: 43909
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CHRIS REEVES
HQ OPS Officer: JEFF ROTTON
Notification Date: 01/16/2008
Notification Time: 21:15 [ET]
Event Date: 01/16/2008
Event Time: 19:25 [EST]
Last Update Date: 01/16/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
JAMES MOORMAN (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 100 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO LOWERING STEAM GENERATOR LEVEL

During a surveillance test on the Loop 3 Steam Generator pressure channel, the loop 3 Steam Generator main feedwater regulating valve went closed. The unit was manually tripped on lowering steam generator level. All control rods fully inserted on the reactor trip. Both motor driven and the turbine driven AFW pumps started successfully. The turbine driven AFW pump was secured and the motor driven AFW pumps are providing feedwater to the steam generators. Decay heat is being removed to the main condenser via the turbine steam dump valves. No PORV, safety relief valves, or atmospheric dump valves opened on the reactor trip. Unit 1 is in a normal shutdown electrical lineup. There was no effect on Unit 2 during this event. The licensee is investigating the unexpected closure of the Loop 3 Steam Generator main feedwater regulating valve.

The licensee notified the NRC Resident Inspector.

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