Event Notification Report for November 17, 2012
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/16/2012 - 11/17/2012
Power Reactor
Event Number: 48517
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: JOE McKEE
HQ OPS Officer: PETE SNYDER
Region: 2 State: FL
Unit: [3] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: JOE McKEE
HQ OPS Officer: PETE SNYDER
Notification Date: 11/17/2012
Notification Time: 22:16 [ET]
Event Date: 11/17/2012
Event Time: 20:00 [EST]
Last Update Date: 11/17/2012
Notification Time: 22:16 [ET]
Event Date: 11/17/2012
Event Time: 20:00 [EST]
Last Update Date: 11/17/2012
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):
MALCOLM WIDMANN (R2DO)
MALCOLM WIDMANN (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 |
| 4 | N | N | 0 | Refueling | 0 | Refueling |
AUTO-INITIATION FEATURE OF TECHNICAL SUPPORT CENTER VENTILATION IMPROPERLY INHIBITED
"In anticipation of core offload, the control room emergency ventilation system was placed in recirculation mode. As a result of a deficient procedure, an automatic initiation feature to the Technical Support Center (TSC) ventilation system was inhibited from 11/16/12 at 2325 [EST] to 11/17/12 at 1419 [EST].
"The Turkey Point TSC habitability design basis assumes that upon discovery of an accident condition, an initiation signal will automatically place both control room and TSC ventilation systems in recirculation.
"Contrary to the design basis, it was discovered on 11/17/12 at 2000 [EST] that when the TSC ventilation system was placed in the 'inhibited mode,' the automatic initiation feature to the TSC ventilation system recirculation mode was defeated. The TSC ventilation system otherwise remained functional and available.
"Upon discovery of this condition, the TSC inhibit switch was returned to enable which would allow the TSC to automatically go on recirculation from an automatic start signal. No accident conditions occurred that warranted a need to activate any emergency operations facilities.
"This notice is made in accordance with 10 CFR 50.72(b)(3)(xiii)."
The licensee notified the NRC Resident Inspector.
"In anticipation of core offload, the control room emergency ventilation system was placed in recirculation mode. As a result of a deficient procedure, an automatic initiation feature to the Technical Support Center (TSC) ventilation system was inhibited from 11/16/12 at 2325 [EST] to 11/17/12 at 1419 [EST].
"The Turkey Point TSC habitability design basis assumes that upon discovery of an accident condition, an initiation signal will automatically place both control room and TSC ventilation systems in recirculation.
"Contrary to the design basis, it was discovered on 11/17/12 at 2000 [EST] that when the TSC ventilation system was placed in the 'inhibited mode,' the automatic initiation feature to the TSC ventilation system recirculation mode was defeated. The TSC ventilation system otherwise remained functional and available.
"Upon discovery of this condition, the TSC inhibit switch was returned to enable which would allow the TSC to automatically go on recirculation from an automatic start signal. No accident conditions occurred that warranted a need to activate any emergency operations facilities.
"This notice is made in accordance with 10 CFR 50.72(b)(3)(xiii)."
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 48514
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DON CERNY
HQ OPS Officer: BILL HUFFMAN
Region: 4 State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DON CERNY
HQ OPS Officer: BILL HUFFMAN
Notification Date: 11/17/2012
Notification Time: 12:30 [ET]
Event Date: 11/17/2012
Event Time: 10:23 [CST]
Last Update Date: 11/17/2012
Notification Time: 12:30 [ET]
Event Date: 11/17/2012
Event Time: 10:23 [CST]
Last Update Date: 11/17/2012
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):
JAMES DRAKE (R4DO)
JAMES DRAKE (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP ON LOW STEAM GENERATOR WATER LEVEL
"At 1023 CDT Comanche Peak Unit 2 automatically tripped due to steam generator low level. The trip was uncomplicated. All control and shutdown rods fully inserted. Neither emergency diesel generator started. All safety systems functioned as designed. Both motor driven and the turbine driven AFW pumps started as required to restore steam generator level as a result of the trip. The turbine driven AFW pump was returned to auto-start status. The turbine driven AFW pump has been placed in pull-out as per procedure after verifying normal motor driven AFW pump operation.
"Currently Unit 2 is in Mode 3, (no-load Tave 557 - degrees Fahrenheit) with temperature being maintained with the AFW and steam dumps to the main condenser. Recovery actions will be planned. All electrical busses are powered from offsite power and grid conditions are stable.
"The initiating event appears to be a sheared instrument air tubing line that feeds the common heater drain pump discharge valve which will fail close resulting in loss of all heater drain flow."
The licensee has notified the NRC Resident Inspector.
"At 1023 CDT Comanche Peak Unit 2 automatically tripped due to steam generator low level. The trip was uncomplicated. All control and shutdown rods fully inserted. Neither emergency diesel generator started. All safety systems functioned as designed. Both motor driven and the turbine driven AFW pumps started as required to restore steam generator level as a result of the trip. The turbine driven AFW pump was returned to auto-start status. The turbine driven AFW pump has been placed in pull-out as per procedure after verifying normal motor driven AFW pump operation.
"Currently Unit 2 is in Mode 3, (no-load Tave 557 - degrees Fahrenheit) with temperature being maintained with the AFW and steam dumps to the main condenser. Recovery actions will be planned. All electrical busses are powered from offsite power and grid conditions are stable.
"The initiating event appears to be a sheared instrument air tubing line that feeds the common heater drain pump discharge valve which will fail close resulting in loss of all heater drain flow."
The licensee has notified the NRC Resident Inspector.