Event Notification Report for February 09, 2016
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/08/2016 - 02/09/2016
Power Reactor
Event Number: 51720
Facility: SEQUOYAH
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRUCE BUCH
HQ OPS Officer: JEFF ROTTON
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRUCE BUCH
HQ OPS Officer: JEFF ROTTON
Notification Date: 02/09/2016
Notification Time: 17:25 [ET]
Event Date: 02/09/2016
Event Time: 14:15 [EST]
Last Update Date: 02/09/2016
Notification Time: 17:25 [ET]
Event Date: 02/09/2016
Event Time: 14:15 [EST]
Last Update Date: 02/09/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ALAN BLAMEY (R2DO)
ALAN BLAMEY (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Standby | 0 | Hot Standby |
ECCS DISCHARGE TO RCS VIA CHARGING SYSTEM
"At 1415 EST on 02/09/2016, Sequoyah Unit 1 was at 0 percent power (mode 3, 526F, 2235 psig) when a low steam line pressure Safety Injection actuated from Loop 2 Steam Generator. Prior to this event, the Loop 2 Main Steam Isolation Valve bypass was opened at 1413 EST for main steam line warm up in preparation for unit startup. Loop 2 Main Steam Isolation Valve bypass closed automatically following low steam line pressure Safety Injection.
"Following the Safety Injection, all safety-related equipment operated as designed.
"Current Reactor Coolant System temperature and pressure - Unit 1 is currently being maintained in Mode 3 at approximately 517 F and 2235 psig, with auxiliary feedwater supplying the steam generators and decay heat removal via steam generator atmospheric relief valves. There is no indication of any primary to secondary leakage. The electrical alignment is normal with shutdown power supplied from off-site power.
"There is no operational impact to Unit 2.
"The cause of the Safety Injection actuation is under investigation.
"This event had no impact on the health and/or safety of the public. The NRC Resident Inspector has been notified."
Due to RCS pressure, the only system that injected into the RCS was the charging system. The AFW system initiated to feed the steam generators and the Emergency Diesel Generators started but did not load.
"At 1415 EST on 02/09/2016, Sequoyah Unit 1 was at 0 percent power (mode 3, 526F, 2235 psig) when a low steam line pressure Safety Injection actuated from Loop 2 Steam Generator. Prior to this event, the Loop 2 Main Steam Isolation Valve bypass was opened at 1413 EST for main steam line warm up in preparation for unit startup. Loop 2 Main Steam Isolation Valve bypass closed automatically following low steam line pressure Safety Injection.
"Following the Safety Injection, all safety-related equipment operated as designed.
"Current Reactor Coolant System temperature and pressure - Unit 1 is currently being maintained in Mode 3 at approximately 517 F and 2235 psig, with auxiliary feedwater supplying the steam generators and decay heat removal via steam generator atmospheric relief valves. There is no indication of any primary to secondary leakage. The electrical alignment is normal with shutdown power supplied from off-site power.
"There is no operational impact to Unit 2.
"The cause of the Safety Injection actuation is under investigation.
"This event had no impact on the health and/or safety of the public. The NRC Resident Inspector has been notified."
Due to RCS pressure, the only system that injected into the RCS was the charging system. The AFW system initiated to feed the steam generators and the Emergency Diesel Generators started but did not load.
Power Reactor
Event Number: 51721
Facility: DRESDEN
Region: 3 State: IL
Unit: [] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: EDWARD BURNS
HQ OPS Officer: HOWIE CROUCH
Region: 3 State: IL
Unit: [] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: EDWARD BURNS
HQ OPS Officer: HOWIE CROUCH
Notification Date: 02/10/2016
Notification Time: 02:17 [ET]
Event Date: 02/09/2016
Event Time: 21:42 [CST]
Last Update Date: 02/10/2016
Notification Time: 02:17 [ET]
Event Date: 02/09/2016
Event Time: 21:42 [CST]
Last Update Date: 02/10/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
DAVID HILLS (R3DO)
DAVID HILLS (R3DO)
| 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 |
SECONDARY CONTAINMENT INOPERABLE
"At 2142 [CST] on February 9, 2016, Reactor Building differential pressure did not meet the required 0.25 inches of vacuum water gauge due to failure of the control system. At 2205, the Unit 3 Reactor Building Ventilation System was secured and manually isolated. The Reactor Building differential pressure returned to [greater than or equal to] 0.25 inches of vacuum water gauge at 2207.
"This condition represents a failure to meet Surveillance Requirement 3.6.4.1.1. As a result, entry into Technical Specifications 3.6.4.1 condition A was made due to Secondary Containment being inoperable. This event is being reported in accordance with 10 CFR 50.72(b)(3)(v)(C) as a condition that could have prevented the fulfillment of a safety function.
"The NRC Resident Inspector has been notified."
"At 2142 [CST] on February 9, 2016, Reactor Building differential pressure did not meet the required 0.25 inches of vacuum water gauge due to failure of the control system. At 2205, the Unit 3 Reactor Building Ventilation System was secured and manually isolated. The Reactor Building differential pressure returned to [greater than or equal to] 0.25 inches of vacuum water gauge at 2207.
"This condition represents a failure to meet Surveillance Requirement 3.6.4.1.1. As a result, entry into Technical Specifications 3.6.4.1 condition A was made due to Secondary Containment being inoperable. This event is being reported in accordance with 10 CFR 50.72(b)(3)(v)(C) as a condition that could have prevented the fulfillment of a safety function.
"The NRC Resident Inspector has been notified."
Power Reactor
Event Number: 51717
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN RASMUSSEN
HQ OPS Officer: STEVEN VITTO
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN RASMUSSEN
HQ OPS Officer: STEVEN VITTO
Notification Date: 02/09/2016
Notification Time: 09:54 [ET]
Event Date: 02/09/2016
Event Time: 08:12 [CST]
Last Update Date: 02/18/2016
Notification Time: 09:54 [ET]
Event Date: 02/09/2016
Event Time: 08:12 [CST]
Last Update Date: 02/18/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
NEIL OKEEFE (R4DO)
NEIL OKEEFE (R4DO)
| 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 |
PLANNED MAINTENANCE OF THE PLANT COMPUTER SYSTEM
"Planned maintenance of the Plant Computer System (PCS) will cause a loss of emergency assessment capability.
"Beginning February 9, 2016, PCS data will not be available to the following Comanche Peak Nuclear Power Plant (CPNPP) facilities due to planned PCS software modifications:
-Emergency Operations Facility [EOF]
-Backup EOF
-Operations Support Center
"The Emergency Response Data System [ERDS] will also be unavailable.
"The planned maintenance of the PCS is being reported as a loss of assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii) because the duration is expected to be more than 72 hours and the data to the Backup EOF is also affected.
"CPNPP has compensatory measures in place to ensure timely emergency classification, protective action recommendation and emergency notification, as needed.
"The PCS modification is expected to be complete by February 18, 2016. A follow-up ENS [Emergency Notification System] communication will be made when the EOF assessment capability is restored."
The Licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM RAUL MARTINEZ TO STEVEN VITTO ON 02/18/2016 AT 1541 EST * * *
"The planned maintenance of the Comanche Peak Plant Computer System (PCS) that began on February 9, 2016 is complete.
"Assessment capability in the following facilities was restored effective 1300 [CST] February 18, 2016:
-Emergency Operations Facility (EOF)
-Backup EOF
-Operations Support Center
"The Emergency Response Data System availability has also been restored."
The Licensee has notified the NRC Resident Inspector.
Notified the R4DO(Werner).
"Planned maintenance of the Plant Computer System (PCS) will cause a loss of emergency assessment capability.
"Beginning February 9, 2016, PCS data will not be available to the following Comanche Peak Nuclear Power Plant (CPNPP) facilities due to planned PCS software modifications:
-Emergency Operations Facility [EOF]
-Backup EOF
-Operations Support Center
"The Emergency Response Data System [ERDS] will also be unavailable.
"The planned maintenance of the PCS is being reported as a loss of assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii) because the duration is expected to be more than 72 hours and the data to the Backup EOF is also affected.
"CPNPP has compensatory measures in place to ensure timely emergency classification, protective action recommendation and emergency notification, as needed.
"The PCS modification is expected to be complete by February 18, 2016. A follow-up ENS [Emergency Notification System] communication will be made when the EOF assessment capability is restored."
The Licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM RAUL MARTINEZ TO STEVEN VITTO ON 02/18/2016 AT 1541 EST * * *
"The planned maintenance of the Comanche Peak Plant Computer System (PCS) that began on February 9, 2016 is complete.
"Assessment capability in the following facilities was restored effective 1300 [CST] February 18, 2016:
-Emergency Operations Facility (EOF)
-Backup EOF
-Operations Support Center
"The Emergency Response Data System availability has also been restored."
The Licensee has notified the NRC Resident Inspector.
Notified the R4DO(Werner).