Event Notification Report for March 02, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/01/2014 - 03/02/2014
Power Reactor
Event Number: 49865
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: ANDREW DOBY
HQ OPS Officer: HOWIE CROUCH
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: ANDREW DOBY
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/02/2014
Notification Time: 00:45 [ET]
Event Date: 03/02/2014
Event Time: 00:13 [EST]
Last Update Date: 03/02/2014
Notification Time: 00:45 [ET]
Event Date: 03/02/2014
Event Time: 00:13 [EST]
Last Update Date: 03/02/2014
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
ANNE DeFRANCISCO (R1DO)
HO NIEH (NRR)
JENNIFER UHLE (NRR)
WILLIAM DEAN (R1RA)
JEFFERY GRANT (IRD)
ANNE DeFRANCISCO (R1DO)
HO NIEH (NRR)
JENNIFER UHLE (NRR)
WILLIAM DEAN (R1RA)
JEFFERY GRANT (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNUSUAL EVENT DECLARED DUE A FIRE ALARM IN THE CONTAINMENT BUILDING
"An Unusual Event (NOUE) was declared at 0013 EST on 3/2/2014 due to a possible fire in the protected area inside containment which could not be verified within 15 minutes (EAL HU4). A containment building smoke alarm was received at 2120 on 3/1/14 after indications that a relief valve lifted during a safety injection accumulator fill evolution. Diverse containment instrumentation was checked and showed that containment dew point was elevated while containment temperature and pressure remained steady. The fire alarm was reset and did not reflash. A containment entry will be made to investigate the alarm. There are no requests for the local fire department to respond and there are no indications of a radiological release to the environment.
"The NRC Resident Inspector has been notified."
The licensee notified the Commonwealth of Pennsylvania Emergency Management Agency, Beaver County in Pennsylvania, the State of Ohio, Columbiana County in Ohio, the State of West Virginia and Hancock County in West Virginia.
Notified DHS SWO, FEMA, NICC and Nuclear SSA (via email).
* * * UPDATE FROM BRIAN STROBEL TO HOWIE CROUCH AT 0211 EST ON 3/2/14 * * *
The licensee terminated the NOUE at 0205 EST after a containment entry determined no fire or indications of fire existed.
Notified R1DO (DeFrancisco) IRD (Grant), NRR EO (Nieh), DHS SWO, FEMA, DHS NICC, and Nuclear SSA (via email).
"An Unusual Event (NOUE) was declared at 0013 EST on 3/2/2014 due to a possible fire in the protected area inside containment which could not be verified within 15 minutes (EAL HU4). A containment building smoke alarm was received at 2120 on 3/1/14 after indications that a relief valve lifted during a safety injection accumulator fill evolution. Diverse containment instrumentation was checked and showed that containment dew point was elevated while containment temperature and pressure remained steady. The fire alarm was reset and did not reflash. A containment entry will be made to investigate the alarm. There are no requests for the local fire department to respond and there are no indications of a radiological release to the environment.
"The NRC Resident Inspector has been notified."
The licensee notified the Commonwealth of Pennsylvania Emergency Management Agency, Beaver County in Pennsylvania, the State of Ohio, Columbiana County in Ohio, the State of West Virginia and Hancock County in West Virginia.
Notified DHS SWO, FEMA, NICC and Nuclear SSA (via email).
* * * UPDATE FROM BRIAN STROBEL TO HOWIE CROUCH AT 0211 EST ON 3/2/14 * * *
The licensee terminated the NOUE at 0205 EST after a containment entry determined no fire or indications of fire existed.
Notified R1DO (DeFrancisco) IRD (Grant), NRR EO (Nieh), DHS SWO, FEMA, DHS NICC, and Nuclear SSA (via email).
Power Reactor
Event Number: 49866
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: NEEL SHUKLA
HQ OPS Officer: JOHN SHOEMAKER
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: NEEL SHUKLA
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 03/02/2014
Notification Time: 22:10 [ET]
Event Date: 03/02/2014
Event Time: 16:30 [CST]
Last Update Date: 03/02/2014
Notification Time: 22:10 [ET]
Event Date: 03/02/2014
Event Time: 16:30 [CST]
Last Update Date: 03/02/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
DANIEL RICH (R2DO)
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 |
DISCOVERED A POSTULATED HOT SHORT OF A CABLE DURING EXTENT OF CONDITION REVIEW
"On March 2, 2014, during an extent of condition review for a separate problem evaluation report (PER) for the Browns Ferry Nuclear Plant (BFN), it was discovered that a postulated worst case failure hot short of cable PP679-IA associated with 4kV Shutdown Board 'A' cross-tie breaker 1824 may cause spurious opening of breaker 1824.
"4KV Shutdown Board 'A' breaker 1824 is required to be closed during an Appendix R safe shutdown event in fire area 2-3. The action taken by 0-SSI-2-3 is to assure breaker 1824 is closed after placing '43 switch' (Breaker Control Transfer switch) and '43AR switch' (Appendix R Isolation switch) in the emergency position. Cable PP679-IA is routed in fire area 2-3 and fire damage resulting in a hot short could prevent closing breaker 1824 upon demand.
"Therefore, this condition could result in a loss of power to credited safe shutdown equipment used for Unit 1 that would challenge the ability to provide adequate core cooling during performance of BFN Safe Shutdown Instructions.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(B), 'Any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.'. This is also reportable as a 60-day written report in accordance with 10 CFR 50.73(a)(2)(ii)(B). This item has been entered into the Corrective Action Program as PER# 853503.
"The NRC Resident Inspector has been notified of this event."
The licensee has established compensatory actions to ensure breaker 1824 remains closed.
"On March 2, 2014, during an extent of condition review for a separate problem evaluation report (PER) for the Browns Ferry Nuclear Plant (BFN), it was discovered that a postulated worst case failure hot short of cable PP679-IA associated with 4kV Shutdown Board 'A' cross-tie breaker 1824 may cause spurious opening of breaker 1824.
"4KV Shutdown Board 'A' breaker 1824 is required to be closed during an Appendix R safe shutdown event in fire area 2-3. The action taken by 0-SSI-2-3 is to assure breaker 1824 is closed after placing '43 switch' (Breaker Control Transfer switch) and '43AR switch' (Appendix R Isolation switch) in the emergency position. Cable PP679-IA is routed in fire area 2-3 and fire damage resulting in a hot short could prevent closing breaker 1824 upon demand.
"Therefore, this condition could result in a loss of power to credited safe shutdown equipment used for Unit 1 that would challenge the ability to provide adequate core cooling during performance of BFN Safe Shutdown Instructions.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(B), 'Any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.'. This is also reportable as a 60-day written report in accordance with 10 CFR 50.73(a)(2)(ii)(B). This item has been entered into the Corrective Action Program as PER# 853503.
"The NRC Resident Inspector has been notified of this event."
The licensee has established compensatory actions to ensure breaker 1824 remains closed.