Event Notification Report for May 12, 2015
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/11/2015 - 05/12/2015
Power Reactor
Event Number: 51065
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: SEAN BLOOM
HQ OPS Officer: DONG HWA PARK
Region: 2 State: FL
Unit: [] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: SEAN BLOOM
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/12/2015
Notification Time: 05:48 [ET]
Event Date: 05/12/2015
Event Time: 04:30 [EDT]
Last Update Date: 05/12/2015
Notification Time: 05:48 [ET]
Event Date: 05/12/2015
Event Time: 04:30 [EDT]
Last Update Date: 05/12/2015
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):
BRIAN BONSER (R2DO)
BRIAN BONSER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 4 | A/R | Y | 81 | Power Operation | 0 | Hot Standby |
REACTOR TRIP DUE TO MAIN GENERATOR DIFFERENTIAL TRIP
"This is an non-emergency notification to the NRC [Headquarters] Operations Center in accordance with 10 CFR 50.72(b)(2)(iv)(B) for a valid actuation of the reactor protection system (RPS) (four hour notification) and 10 CFR 50.72(b)(3)(iv)(A) for a valid Engineered Safeguards (ESF) actuation (eight hour notification) due to auxiliary feedwater (AFW) initiation.
"On 5/12/15 at 0430 EDT, Unit 4 experienced an automatic reactor trip due to Generator Differential Trip. Investigation is underway to determine the cause. Auxiliary feedwater automatically initiated as expected. All systems operated correctly in response to the reactor trip. Unit 4 is currently in Mode 3 and stable."
All control rods fully inserted. Normal offsite power is available with decay heat is being removed by the atmospheric steam dumps. There is no known primary to secondary reactor coolant system leakage.
The licensee has notified the NRC Resident Inspector.
"This is an non-emergency notification to the NRC [Headquarters] Operations Center in accordance with 10 CFR 50.72(b)(2)(iv)(B) for a valid actuation of the reactor protection system (RPS) (four hour notification) and 10 CFR 50.72(b)(3)(iv)(A) for a valid Engineered Safeguards (ESF) actuation (eight hour notification) due to auxiliary feedwater (AFW) initiation.
"On 5/12/15 at 0430 EDT, Unit 4 experienced an automatic reactor trip due to Generator Differential Trip. Investigation is underway to determine the cause. Auxiliary feedwater automatically initiated as expected. All systems operated correctly in response to the reactor trip. Unit 4 is currently in Mode 3 and stable."
All control rods fully inserted. Normal offsite power is available with decay heat is being removed by the atmospheric steam dumps. There is no known primary to secondary reactor coolant system leakage.
The licensee has notified the NRC Resident Inspector.
Power Reactor
Event Number: 51066
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [] [] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: ANDREW MITCHELL
HQ OPS Officer: DONG HWA PARK
Region: 2 State: AL
Unit: [] [] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: ANDREW MITCHELL
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/12/2015
Notification Time: 09:08 [ET]
Event Date: 05/12/2015
Event Time: 01:04 [CDT]
Last Update Date: 05/12/2015
Notification Time: 09:08 [ET]
Event Date: 05/12/2015
Event Time: 01:04 [CDT]
Last Update Date: 05/12/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BRIAN BONSER (R2DO)
BRIAN BONSER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 3 | N | Y | 100 | Power Operation | 100 | Power Operation |
HIGH PRESSURE COOLANT INJECTION DECLARED INOPERABLE
"On May 12, 2015, at 0104 CDT, during performance of 3-SR-3.3.6.1.2(3B), High Pressure Coolant Injection (HPCI) System Steam Supply Pressure Low Functional Test, an inadvertent PCIS Group 4 (HPCI) isolation occurred. All automatic actions occurred as designed. HPCI was declared inoperable and Technical Specification LCO 3.5.1.C was entered with required action to verify immediately that RCIC is operable administratively and to restore HPCI to operable within 14 days. HPCI was returned to service at 0125 CDT, declared operable and TS LCO 3.5.1.C was exited. The cause of the isolation is unknown with an investigation in progress.
"This condition is reportable as an 8-hour ENS notification under 10CFR 50.72(b)(3)(v)(D) due to the failure of a single train system affecting accident mitigation.
"This condition also requires a 60 day written report.
"The NRC Resident Inspector has been notified."
"On May 12, 2015, at 0104 CDT, during performance of 3-SR-3.3.6.1.2(3B), High Pressure Coolant Injection (HPCI) System Steam Supply Pressure Low Functional Test, an inadvertent PCIS Group 4 (HPCI) isolation occurred. All automatic actions occurred as designed. HPCI was declared inoperable and Technical Specification LCO 3.5.1.C was entered with required action to verify immediately that RCIC is operable administratively and to restore HPCI to operable within 14 days. HPCI was returned to service at 0125 CDT, declared operable and TS LCO 3.5.1.C was exited. The cause of the isolation is unknown with an investigation in progress.
"This condition is reportable as an 8-hour ENS notification under 10CFR 50.72(b)(3)(v)(D) due to the failure of a single train system affecting accident mitigation.
"This condition also requires a 60 day written report.
"The NRC Resident Inspector has been notified."