Alert

Due to a lapse in appropriations, the NRC has ceased normal operations. However, excepted and exempted activities necessary to maintain critical health and safety functions—as well as essential progress on designated critical activities, including those specified in Executive Order 14300—will continue, consistent with the OMB-Approved NRC Lapse Plan.

Event Notification Report for October 19, 2012

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
10/18/2012 - 10/19/2012

** EVENT NUMBERS **

48419

48421

Power Reactor	Event Number: 48419
Facility: BROWNS FERRY Region: 2 State: AL Unit: [1] [2] [3] RX Type: [1] GE-4,[2] GE-4,[3] GE-4 NRC Notified By: ERIC STEELE HQ OPS Officer: MARK ABRAMOVITZ	Notification Date: 10/18/2012 Notification Time: 13:34 [ET] Event Date: 10/17/2012 Event Time: 14:50 [CDT] Last Update Date: 10/18/2012
Emergency Class: NON EMERGENCY 10 CFR Section: 26.719 - FITNESS FOR DUTY	Person (Organization): DANIEL RICH (R2DO)

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
3	N	Y	100	Power Operation	100	Power Operation

Event Text

CONFIRMED POSITIVE FITNESS FOR DUTY TEST

A non-licensed contract supervisor had a confirmed positive for alcohol during a for-cause fitness-for-duty test. The contractor's access to the plant has been suspended. Contact the Headquarters Operations Officer for additional details.

The NRC Resident Inspector has been notified.

Power Reactor	Event Number: 48421
Facility: BROWNS FERRY Region: 2 State: AL Unit: [ ] [2] [3] RX Type: [1] GE-4,[2] GE-4,[3] GE-4 NRC Notified By: ERIC STEELE HQ OPS Officer: VINCE KLCO	Notification Date: 10/18/2012 Notification Time: 18:57 [ET] Event Date: 10/18/2012 Event Time: 13:14 [CDT] Last Update Date: 10/18/2012
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(ii)(B) - UNANALYZED CONDITION 50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD	Person (Organization): DANIEL RICH (R2DO)

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

Event Text

FIRE PROTECTION REVIEW IDENTIFIES A POTENTIAL UNANALYZED CONDITION

"During BFNP [Browns Ferry Nuclear Plant] NFPA [National Fire Protection Association] 805 transition review, it was determined in the event of an Appendix-R fire, fire induced circuit damage could potentially result in the Residual Heat Removal System Division II inboard isolation valve being prevented from opening or cause the valve to spuriously close on units 2 and 3. The current Appendix R safe shutdown analysis credits opening of these valves. Failure to open these valves results in loss of ability to provide long term cooling to the core.

"Compensatory actions in the form of fire watches to mitigate this condition are in place in accordance with the BFNP Fire Protection Report.

"This condition is being reported pursuant to 10CFR50.72(b)(3)(ii)(B) and 10CFR50.72(b)(3)(v).

"The NRC Resident Inspector has been notified."

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