Event Notification Report for October 03, 2015
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/02/2015 - 10/03/2015
Power Reactor
Event Number: 51444
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN RASMUSSEN
HQ OPS Officer: MARK ABRAMOVITZ
Region: 4 State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN RASMUSSEN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 10/03/2015
Notification Time: 12:02 [ET]
Event Date: 10/03/2015
Event Time: 10:00 [CDT]
Last Update Date: 10/05/2015
Notification Time: 12:02 [ET]
Event Date: 10/03/2015
Event Time: 10:00 [CDT]
Last Update Date: 10/05/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
NICK TAYLOR (R4DO)
NICK TAYLOR (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 47 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DURING SHUTDOWN FOR A REFUELING OUTAGE
"During the scheduled Unit 2 down power to start 2RF15, Steam Generator 3 Feed Control Valve failed to control in Automatic or Manual resulting in excessive feedwater flow. Control Room Operators manually tripped the reactor and aligned Auxiliary Feedwater. No automatic RPS or ESF actuations occurred. Plant conditions are stable."
All control rods fully inserted on the trip and no safety or relief valves lifted. The plant is supplying water to the steam generators with auxiliary feedwater and removing decay heat through the main condenser. The unit is in its normal shutdown electrical lineup. There was no effect on unit-1.
The licensee informed the NRC Resident Inspector.
* * * UPDATE AT 1848 EDT ON 10/05/15 FROM JOHN RASMUSSEN TO JEFF HERRERA * * *
The licensee added 10 CFR 50.72(b)(3)(iv)(A) to the 10 CFR codes reporting section. No other text was modified.
Notified the R4DO (Taylor).
"During the scheduled Unit 2 down power to start 2RF15, Steam Generator 3 Feed Control Valve failed to control in Automatic or Manual resulting in excessive feedwater flow. Control Room Operators manually tripped the reactor and aligned Auxiliary Feedwater. No automatic RPS or ESF actuations occurred. Plant conditions are stable."
All control rods fully inserted on the trip and no safety or relief valves lifted. The plant is supplying water to the steam generators with auxiliary feedwater and removing decay heat through the main condenser. The unit is in its normal shutdown electrical lineup. There was no effect on unit-1.
The licensee informed the NRC Resident Inspector.
* * * UPDATE AT 1848 EDT ON 10/05/15 FROM JOHN RASMUSSEN TO JEFF HERRERA * * *
The licensee added 10 CFR 50.72(b)(3)(iv)(A) to the 10 CFR codes reporting section. No other text was modified.
Notified the R4DO (Taylor).
Power Reactor
Event Number: 51445
Facility: OYSTER CREEK
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: JOSH MCGUIRE
HQ OPS Officer: DANIEL MILLS
Region: 1 State: NJ
Unit: [1] [] []
RX Type: [1] GE-2
NRC Notified By: JOSH MCGUIRE
HQ OPS Officer: DANIEL MILLS
Notification Date: 10/03/2015
Notification Time: 14:46 [ET]
Event Date: 10/03/2015
Event Time: 10:25 [EDT]
Last Update Date: 10/03/2015
Notification Time: 14:46 [ET]
Event Date: 10/03/2015
Event Time: 10:25 [EDT]
Last Update Date: 10/03/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
FRED BOWER (R1DO)
FRED BOWER (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY - CONFIRMED POSITIVE FFD TEST
A non-licensed supervisory employee had a confirmed positive for alcohol during a for-cause fitness-for-duty test. The employee's access to the plant has been restricted.
The licensee notified the NRC Resident Inspector.
A non-licensed supervisory employee had a confirmed positive for alcohol during a for-cause fitness-for-duty test. The employee's access to the plant has been restricted.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 51447
Facility: WATERFORD
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: LEIA MILSTER
HQ OPS Officer: STEVE SANDIN
Region: 4 State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: LEIA MILSTER
HQ OPS Officer: STEVE SANDIN
Notification Date: 10/04/2015
Notification Time: 03:51 [ET]
Event Date: 10/03/2015
Event Time: 23:07 [CDT]
Last Update Date: 10/04/2015
Notification Time: 03:51 [ET]
Event Date: 10/03/2015
Event Time: 23:07 [CDT]
Last Update Date: 10/04/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
NICK TAYLOR (R4DO)
NICK TAYLOR (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP
"At 2307 CDT Waterford 3 experienced an automatic reactor trip and all Control Element Assemblies (CEAs) inserted into the core. The cause of the automatic reactor trip is currently under investigation.
"The plant is currently in Mode 3 [Hot Standby] and stable with Main Feedwater feeding and maintaining both Steam Generators. Main Feedwater Pump 'A' tripped subsequent to the reactor trip. Emergency Feedwater actuated following the plant trip as expected, but was not required to maintain Steam Generator level.
"The plant entered the Emergency Operating Procedure for an uncomplicated reactor trip and has now transitioned to the normal operating shutdown procedure."
Unit 3 is in a normal post trip electrical lineup. The Main Condenser is in-service removing decay heat..
The licensee informed the NRC Resident Inspector.
"At 2307 CDT Waterford 3 experienced an automatic reactor trip and all Control Element Assemblies (CEAs) inserted into the core. The cause of the automatic reactor trip is currently under investigation.
"The plant is currently in Mode 3 [Hot Standby] and stable with Main Feedwater feeding and maintaining both Steam Generators. Main Feedwater Pump 'A' tripped subsequent to the reactor trip. Emergency Feedwater actuated following the plant trip as expected, but was not required to maintain Steam Generator level.
"The plant entered the Emergency Operating Procedure for an uncomplicated reactor trip and has now transitioned to the normal operating shutdown procedure."
Unit 3 is in a normal post trip electrical lineup. The Main Condenser is in-service removing decay heat..
The licensee informed the NRC Resident Inspector.