United States Nuclear Regulatory Commission - Protecting People and the Environment

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

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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.

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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."

Page Last Reviewed/Updated Friday, October 19, 2012
Friday, October 19, 2012