Event Notification Report for November 02, 2009
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/01/2009 - 11/02/2009
Power Reactor
Event Number: 45474
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: DAN LYON
HQ OPS Officer: BILL HUFFMAN
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: DAN LYON
HQ OPS Officer: BILL HUFFMAN
Notification Date: 11/02/2009
Notification Time: 23:55 [ET]
Event Date: 11/02/2009
Event Time: 22:41 [EDT]
Last Update Date: 11/03/2009
Notification Time: 23:55 [ET]
Event Date: 11/02/2009
Event Time: 22:41 [EDT]
Last Update Date: 11/03/2009
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):
RICHARD BARKLEY (R1DO)
RICHARD BARKLEY (R1DO)
| 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 |
REACTOR TRIP DUE TO TURBINE TRIP CAUSED BY A GENERATOR LOCK-OUT RELAY ACTUATION
"At 2242 on November 2, 2009 Indian Point Unit 2 reactor tripped from 100% due to a turbine trip. The turbine tripped due to a generator lockout relay actuation. The investigation into the relay actuation is ongoing. All systems responded as expected. Auxiliary feed water is providing steam generator feed and levels are being maintained. No steam safeties opened and no coolant system relief or safety valves actuated. The reactor plant is in mode 3 and stable. Unit 3 was unaffected and remains at 100%."
The trip was characterized as uncomplicated. All rods fully inserted and stabilized at the normal mode 3 no-load Tave and pressure. The shutdown electrical lineup is normal and the unit was not in any significant LCOs at the time of the trip. The licensee stated that they were not performing any maintenance or surveillances at the time of the trip. Initial investigation has not revealed any obvious generator electrical system issues but a detailed investigation is ongoing.
The licensee has notified State and local authorities and the NRC Resident Inspector.
"At 2242 on November 2, 2009 Indian Point Unit 2 reactor tripped from 100% due to a turbine trip. The turbine tripped due to a generator lockout relay actuation. The investigation into the relay actuation is ongoing. All systems responded as expected. Auxiliary feed water is providing steam generator feed and levels are being maintained. No steam safeties opened and no coolant system relief or safety valves actuated. The reactor plant is in mode 3 and stable. Unit 3 was unaffected and remains at 100%."
The trip was characterized as uncomplicated. All rods fully inserted and stabilized at the normal mode 3 no-load Tave and pressure. The shutdown electrical lineup is normal and the unit was not in any significant LCOs at the time of the trip. The licensee stated that they were not performing any maintenance or surveillances at the time of the trip. Initial investigation has not revealed any obvious generator electrical system issues but a detailed investigation is ongoing.
The licensee has notified State and local authorities and the NRC Resident Inspector.
Power Reactor
Event Number: 45472
Facility: DRESDEN
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: CHRIS KENT
HQ OPS Officer: VINCE KLCO
Region: 3 State: IL
Unit: [] [2] []
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: CHRIS KENT
HQ OPS Officer: VINCE KLCO
Notification Date: 11/02/2009
Notification Time: 14:23 [ET]
Event Date: 11/02/2009
Event Time: 07:12 [CDT]
Last Update Date: 11/02/2009
Notification Time: 14:23 [ET]
Event Date: 11/02/2009
Event Time: 07:12 [CDT]
Last Update Date: 11/02/2009
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
RICHARD SKOKOWSKI (R3DO)
RICHARD SKOKOWSKI (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown |
LOSS OF SHUTDOWN COOLING
"On 11/2/09 at 0712 shutdown cooling (SDC) was lost on Dresden Unit 2 when a recirculation loop temperature element (2-0260-13B) failed upscale. Unit 2 was in the process of initial cooldown for entry into a refueling outage. Recirculation loop temperature was approximately 224 degrees F based on alternate indications. The circuitry was jumpered out and SDC was restarted at 0748. The Recirculation loop temperature was at 260 degrees F upon restart. At 0835, the reactor entered Mode 4 (i.e., Recirculation loop temperature less than or equal to 212 degrees F and Mode Switch in Shutdown). This event is reportable under 10CFR 50.72(b)(3)(v)(B). This event is being reported based on lessons learned from industry experience and is undergoing further review.
"The licensee notified NRC Resident Inspector."
"On 11/2/09 at 0712 shutdown cooling (SDC) was lost on Dresden Unit 2 when a recirculation loop temperature element (2-0260-13B) failed upscale. Unit 2 was in the process of initial cooldown for entry into a refueling outage. Recirculation loop temperature was approximately 224 degrees F based on alternate indications. The circuitry was jumpered out and SDC was restarted at 0748. The Recirculation loop temperature was at 260 degrees F upon restart. At 0835, the reactor entered Mode 4 (i.e., Recirculation loop temperature less than or equal to 212 degrees F and Mode Switch in Shutdown). This event is reportable under 10CFR 50.72(b)(3)(v)(B). This event is being reported based on lessons learned from industry experience and is undergoing further review.
"The licensee notified NRC Resident Inspector."