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Event Notification Report for October 07, 2007

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
10/06/2007 - 10/07/2007

EVENT NUMBERS
4369843699

Power Reactor
Event Number: 43698
Facility: HATCH
Region: 2     State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BILL DUVALL
HQ OPS Officer: JEFF ROTTON
Notification Date: 10/07/2007
Notification Time: 01:55 [ET]
Event Date: 10/07/2007
Event Time: 01:15 [EDT]
Last Update Date: 10/07/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
CAROLYN EVANS (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
2 N Y 100 Power Operation 100 Power Operation
Event Text
LOSS OF PROMPT NOTIFICATION MESSAGE SYSTEM

"Jacksonville National Weather Service does not have the capability to broadcast prompt notification messages due to phone lines or system problem at this time. Plant Hatch security notified the Operations Shift Manager at 0115 hour to notify NRC. Also, site Emergency Preparedness on call person has been contacted and security has notified the state and local agencies. Information Technology (IT) has been notified of problem."

Compensatory measures performed by the local emergency response agencies will be used if needed.

The licensee will notify the NRC Resident Inspector.

* * * UPDATE PROVIDED BY BILL DUVALL TO JEFF ROTTON AT 0345 EDT ON 10/07/07 * * *

The Jacksonville National Weather Service has restored the capability to broadcast prompt notification messages effective 0344 EDT on 10/07/07.

The licensee notified the NRC Resident Inspector and the state and local emergency response agencies. Notified R2DO (Evans).


Power Reactor
Event Number: 43699
Facility: FERMI
Region: 3     State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: MIKE HIMEBAUCH
HQ OPS Officer: JOE O'HARA
Notification Date: 10/07/2007
Notification Time: 05:56 [ET]
Event Date: 10/07/2007
Event Time: 01:14 [EDT]
Last Update Date: 10/07/2007
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
LAURA KOZAK (R3)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Refueling 0 Refueling
Event Text
PRIMARY CONTAINMENT LEAK RATE EXCEEDED

"At 0114 EDT on 10/7/07, Fermi 2 feed water line check valves, B2100-F010B and B2100-F076B, failed their local leak rate tests. The leakage rate of the inboard check valve (B2100-F010B) was 297.3 SCFH and the leakage rate of the outboard check valve (B2100-F076B) was indeterminate due to leakage exceeding the capability of the leak rate monitor. Thus, the minimum path leakage through penetration X-9B is 297.3 SCFH. This leak rate exceeds the Primary Containment allowable leakage rate (1.0 La) of 296.3 SCFH per Tech. Spec. 5.5.12. The NRC Resident Inspector has been notified of this event."

The licensee is reporting a degraded safety function associated with the primary containment barrier. The licensee intends to repair the leaking valve and retest it prior to any mode change. There is no LCO associated with this condition because the licensee is in mode 5.