Event Notification Report for June 15, 2015
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/14/2015 - 06/15/2015
Power Reactor
Event Number: 51154
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BLAKE BAXTER
HQ OPS Officer: DANIEL MILLS
Region: 3 State: IL
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BLAKE BAXTER
HQ OPS Officer: DANIEL MILLS
Notification Date: 06/15/2015
Notification Time: 17:42 [ET]
Event Date: 06/15/2015
Event Time: 07:00 [CDT]
Last Update Date: 06/18/2015
Notification Time: 17:42 [ET]
Event Date: 06/15/2015
Event Time: 07:00 [CDT]
Last Update Date: 06/18/2015
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):
PATTY PELKE (R3DO)
PATTY PELKE (R3DO)
| 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 |
TSC VENTILATION TO BE REMOVED FROM SERVICE FOR PLANNED MAINTENANCE
"On 6/16/2015, planned preventive maintenance activities [will be] performed on the Braidwood Generating Station Technical Support Center (TSC), Ventilation System. The work will be completed within approximately 48 hours. This activity includes preventative maintenance that requires the TSC ventilation system to be out of service which will render the TSC ventilation system non-functional.
"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff as necessary.
"This event is reportable per 10 CFR 50.72(b)(3)(xiii) for 'any event that results in a major loss of emergency assessment capability.' The planned maintenance will not be able to restore the TSC condensing unit or ventilation system to service within the facility activation time specified in the emergency plan (1 hour) in the event of an accident. The Emergency Response Organization team has been notified of the maintenance and the possible need to relocate during an emergency.
"The licensee has notified the NRC Resident Inspector."
* * * UPDATE AT 1102 EDT ON 6/18/15 FROM DAVID KORTGE TO JEFF HERRERA * * *
"Braidwood Generating Station TSC ventilation was restored to available status at 0700 CDT on June 18, 2015.
"The previously reported system preventative maintenance has been completed."
The licensee notified the NRC Resident Inspector.
Notified the R3DO (Pelke).
"On 6/16/2015, planned preventive maintenance activities [will be] performed on the Braidwood Generating Station Technical Support Center (TSC), Ventilation System. The work will be completed within approximately 48 hours. This activity includes preventative maintenance that requires the TSC ventilation system to be out of service which will render the TSC ventilation system non-functional.
"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff as necessary.
"This event is reportable per 10 CFR 50.72(b)(3)(xiii) for 'any event that results in a major loss of emergency assessment capability.' The planned maintenance will not be able to restore the TSC condensing unit or ventilation system to service within the facility activation time specified in the emergency plan (1 hour) in the event of an accident. The Emergency Response Organization team has been notified of the maintenance and the possible need to relocate during an emergency.
"The licensee has notified the NRC Resident Inspector."
* * * UPDATE AT 1102 EDT ON 6/18/15 FROM DAVID KORTGE TO JEFF HERRERA * * *
"Braidwood Generating Station TSC ventilation was restored to available status at 0700 CDT on June 18, 2015.
"The previously reported system preventative maintenance has been completed."
The licensee notified the NRC Resident Inspector.
Notified the R3DO (Pelke).
Power Reactor
Event Number: 51156
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: LUKE HEDGES
HQ OPS Officer: DONALD NORWOOD
Region: 1 State: NY
Unit: [] [3] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: LUKE HEDGES
HQ OPS Officer: DONALD NORWOOD
Notification Date: 06/15/2015
Notification Time: 20:15 [ET]
Event Date: 06/15/2015
Event Time: 19:20 [EDT]
Last Update Date: 06/16/2015
Notification Time: 20:15 [ET]
Event Date: 06/15/2015
Event Time: 19:20 [EDT]
Last Update Date: 06/16/2015
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):
BRICE BICKETT (R1DO)
BRICE BICKETT (R1DO)
| 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 |
REACTOR TRIP DUE TO TURBINE TRIP
"On June 15, 2015 at 1920 EDT, Indian Point Unit 3 received a Turbine trip which directly led to a Reactor trip. Operators entered [plant procedure] E-0, Reactor Trip or Safety Injection. All control rods fully inserted. All safety systems responded as expected. The Auxiliary Feedwater (AFW) system actuated as expected. Offsite power and electrical lineups are normal. No primary or secondary code safety valves lifted. All MSIVs are open and the Main Condensers are being used as the heat sink. The Reactor is in Mode 3 and stable. Unit 2 was unaffected and remains at 100% power. Preliminary investigation determined that Breaker Number 1 in the Ring Bus was intentionally opened [by plant personnel on switching orders from the district operator] due to a problem on W93 [output feeder from Ring Bus]. Subsequently Breaker #3 went open and caused a Turbine/Reactor trip of the Unit."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM BOB WALPOLE TO DANIEL MILLS ON 6/16/15 AT 1320 EDT * * *
The licensee previously identified "a problem on W93" which was a mistake and should have been stated as "a problem on W97". All other information was stated correctly.
The NRC Resident Inspector has been notified.
Notified R1DO (Bickett).
"On June 15, 2015 at 1920 EDT, Indian Point Unit 3 received a Turbine trip which directly led to a Reactor trip. Operators entered [plant procedure] E-0, Reactor Trip or Safety Injection. All control rods fully inserted. All safety systems responded as expected. The Auxiliary Feedwater (AFW) system actuated as expected. Offsite power and electrical lineups are normal. No primary or secondary code safety valves lifted. All MSIVs are open and the Main Condensers are being used as the heat sink. The Reactor is in Mode 3 and stable. Unit 2 was unaffected and remains at 100% power. Preliminary investigation determined that Breaker Number 1 in the Ring Bus was intentionally opened [by plant personnel on switching orders from the district operator] due to a problem on W93 [output feeder from Ring Bus]. Subsequently Breaker #3 went open and caused a Turbine/Reactor trip of the Unit."
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM BOB WALPOLE TO DANIEL MILLS ON 6/16/15 AT 1320 EDT * * *
The licensee previously identified "a problem on W93" which was a mistake and should have been stated as "a problem on W97". All other information was stated correctly.
The NRC Resident Inspector has been notified.
Notified R1DO (Bickett).