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Event Notification Report for March 3, 2005

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
03/02/2005 - 03/03/2005

** EVENT NUMBERS **


41455 41456 41457

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Fuel Cycle Facility Event Number: 41455
Facility: FRAMATOME ANP RICHLAND
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION
                   FABRICATION & SCRAP RECOVERY
                   COMMERCIAL LWR FUEL
Region: 2
City: RICHLAND State: WA
County: BENTON
License #: SNM-1227
Agreement: Y
Docket: 07001257
NRC Notified By: JERALD HOLM (VIA FAX)
HQ OPS Officer: JEFF ROTTON
Notification Date: 03/02/2005
Notification Time: 12:27 [ET]
Event Date: 01/27/2005
Event Time: [PST]
Last Update Date: 03/02/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
Person (Organization):
CAROLYN EVANS (R2)
CHUCK CAIN (R4)
THOMAS KOZAK (R3)

Event Text

PART 21 REPORT CONCERNING MCPR LIMITS AND MCPR MONITORING


On 01/27/05, Framatome ANP determined that a deviation exists in the interpolation scheme for the minimum critical power ratio (MCPR) within a range of fuel bundle flows for several operating plants. The condition could be experienced during startup, shutdown, or for other generally very infrequent reasons with core flows in the 30-45% range. The error has no impact on reactor operation above 45% flow. The defect involves the MCPR operating limit and the monitoring of that limit.

The plants where the MCPR operating limit was affected are Browns Ferry Unit 3 and Grand Gulf. The plants where the steady state MCPR predicted by the monitoring system was affected are Browns Ferry Unit 3, Columbia Generating Station, Grand Gulf, LaSalle Unit 2, and River Bend. All affected plants have been notified. Recommendations for compensatory actions have been provided to those plants (Grand Gulf and River Bend) where the impact of the error is evident for current and future cycle exposures. Compensatory measures have been provided to the affected plants for use until the incore monitoring code can be updated at each plant.

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Power Reactor Event Number: 41456
Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MICHAEL WHALEN
HQ OPS Officer: JEFF ROTTON
Notification Date: 03/02/2005
Notification Time: 17:49 [ET]
Event Date: 03/02/2005
Event Time: 12:39 [EST]
Last Update Date: 03/02/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CAROLYN EVANS (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

LOSS OF EMERGENCY SIRENS

The following information was provided by the licensee via facsimile (licensee text in quotes):

"On March 2, 2005, at approximately 1239 hours [EST], the transmitter antenna that provides the signal that activates the emergency sirens was determined to be inoperable during testing activities. This affected the system's ability to automatically activate the emergency sirens. The antenna system was restored to service at 1249 hours on March 2, 2005. All sirens re-tested satisfactorily. This event is a loss of the Emergency Notification System and is reportable under 10 CFR 50.72(b)(3)(xiii)."

The equipment was repaired by replacing faulty components. Troubleshooting the failure is in progress. Sirens were last tested satisfactorily on 02/23/05.

The licensee will notify the NRC Resident Inspector.

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Power Reactor Event Number: 41457
Facility: MCGUIRE
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GARY MILLS
HQ OPS Officer: JEFF ROTTON
Notification Date: 03/02/2005
Notification Time: 20:15 [ET]
Event Date: 03/02/2005
Event Time: 16:29 [EST]
Last Update Date: 03/02/2005
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
CAROLYN EVANS (R2)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Hot Standby 0 Hot Standby

Event Text

AUTOMATIC ACTUATION OF MOTOR DRIVEN AFW PUMPS DURING OUTAGE

The following information was provided by the licensee via facsimile (licensee text in quotes):

"At 1629 [EST] on March 2, 2005, McGuire Nuclear Station Unit 2 experienced an automatic actuation of the 2A and 2B Motor Driven Auxiliary Feedwater (MDCA) Pumps. At the time of these actuations, Unit 2 was in MODE 3 in a refueling outage, the 2A Main Feedwater (CF) Pump was in service and, as per procedure, the 2B CF Pump was in a tripped condition and out of service.

"While performing system evolutions, Unit 2 CF system pressure unexpectedly dropped to a level that caused initiation of a low CF pump suction pressure signal which tripped the 2A CF Pump. Since the 2B CF Pump had previously been placed in a tripped condition, the logic for automatic start of the 2A and 2B MDCA Pumps was satisfied and these pumps started as designed. Since the 2A and 2B MDCA Pumps started in response to actual plant conditions or parameters satisfying the requirements for initiation of the Auxiliary Feedwater (CA) System safety function, this represented a valid actuation of the CA system reportable under the requirements of 10 CFR 50.72(b)(3)(iv)(A) .

"Note that the 2A and 2B MDCA Pumps started and operated normally and Unit 2 remained in a stable condition during this event. Unit 2 CF system parameters and alignments have been returned to normal for the current plant MODE and conditions. The 2A and 2B CA Pumps are now off."

The licensee notified the NRC Resident Inspector.

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Friday, March 30, 2012