Event Notification Report for May 20, 2014
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
05/19/2014 - 05/20/2014
Power Reactor
Event Number: 50124
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MICHAEL STERANKO
HQ OPS Officer: MARK ABRAMOVITZ
Region: 1 State: PA
Unit: [] [2] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: MICHAEL STERANKO
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 05/20/2014
Notification Time: 10:52 [ET]
Event Date: 05/20/2014
Event Time: 08:35 [EDT]
Last Update Date: 05/20/2014
Notification Time: 10:52 [ET]
Event Date: 05/20/2014
Event Time: 08:35 [EDT]
Last Update Date: 05/20/2014
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):
HAROLD GRAY (R1DO)
HAROLD GRAY (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 17 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP DURING REACTOR STARTUP
"On May 20, 2014, at 0835 hours during plant startup, Beaver Valley Power Station Unit 2 Operations personnel manually tripped the reactor due to meeting the pre-briefed trip criteria of 85% narrow range level on the 'A' Steam Generator. This manual trip criterion was reached after the steam generator water level began to oscillate following the start of the 'A' Condensate pump. A manual main steam line isolation was performed in order to limit reactor coolant system cool down. Plant trip response was as expected without complications, and all control rods fully inserted in the core. The plant is currently stable in Mode 3.
"This event is reportable pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A).
"Beaver Valley Power Station Unit 1 was not affected by this event.
"The NRC Resident Inspector has been notified."
No relief or safety valves lifted during this event. The unit is maintaining primary temperature using the atmospheric steam dumps and main feedwater pumps. There is no primary to secondary leakage. The plant is in its normal shutdown electrical lineup.
"On May 20, 2014, at 0835 hours during plant startup, Beaver Valley Power Station Unit 2 Operations personnel manually tripped the reactor due to meeting the pre-briefed trip criteria of 85% narrow range level on the 'A' Steam Generator. This manual trip criterion was reached after the steam generator water level began to oscillate following the start of the 'A' Condensate pump. A manual main steam line isolation was performed in order to limit reactor coolant system cool down. Plant trip response was as expected without complications, and all control rods fully inserted in the core. The plant is currently stable in Mode 3.
"This event is reportable pursuant to 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A).
"Beaver Valley Power Station Unit 1 was not affected by this event.
"The NRC Resident Inspector has been notified."
No relief or safety valves lifted during this event. The unit is maintaining primary temperature using the atmospheric steam dumps and main feedwater pumps. There is no primary to secondary leakage. The plant is in its normal shutdown electrical lineup.
Power Reactor
Event Number: 50125
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: VINCE WESSLING
HQ OPS Officer: STEVE SANDIN
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: VINCE WESSLING
HQ OPS Officer: STEVE SANDIN
Notification Date: 05/20/2014
Notification Time: 14:30 [ET]
Event Date: 05/20/2014
Event Time: 08:53 [EDT]
Last Update Date: 05/20/2014
Notification Time: 14:30 [ET]
Event Date: 05/20/2014
Event Time: 08:53 [EDT]
Last Update Date: 05/20/2014
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):
HAROLD GRAY (R1DO)
HAROLD GRAY (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
LOSS OF ASSESSMENT CAPABILITY DUE TO PRE-PLANNED MAINTENANCE ON STACK RADIATION MONITOR
At 0853 EDT, Millstone Station Unit 2 removed the Stack Radiation Monitor RM-8169 from service for planned maintenance. Maintenance and testing were completed and the Stack Radiation Monitor returned to service at 1100 EDT.
The licensee informed both State and local agencies and the NRC Resident Inspector.
At 0853 EDT, Millstone Station Unit 2 removed the Stack Radiation Monitor RM-8169 from service for planned maintenance. Maintenance and testing were completed and the Stack Radiation Monitor returned to service at 1100 EDT.
The licensee informed both State and local agencies and the NRC Resident Inspector.