Event Notification Report for July 24, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/23/2003 - 07/24/2003
EVENT NUMBERS
40014
Power Reactor
Event Number: 40014
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CHRIS SKINNER
HQ OPS Officer: JOHN MacKINNON
Region: 1 State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CHRIS SKINNER
HQ OPS Officer: JOHN MacKINNON
Notification Date: 07/24/2003
Notification Time: 09:32 [ET]
Event Date: 07/24/2003
Event Time: 05:57 [EDT]
Last Update Date: 07/24/2003
Notification Time: 09:32 [ET]
Event Date: 07/24/2003
Event Time: 05:57 [EDT]
Last Update Date: 07/24/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
DANIEL HOLODY (R1)
DANIEL HOLODY (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 50 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM DUE TO POWER SUPPLY FAILURE
"A power supply failed for three of four main steam line flow instruments for the feedwater level control system. Feedwater level control system responded to the sensed reduction in main steam flow by reducing feedwater flow. The feedwater flow reduction resulted in the reactor recirculation system pumps downshifting to slow speed. At 0557, the reactor protection system automatically tripped on Oscillation Power Range Monitors due to a power/flow mismatch. The operators did not observe any power oscillations. The plant is currently stable with reactor pressure being controlled by the main steam bypass valves and reactor level is being maintained by the feedwater system. "
"The reason for the loss of the power supply failure is unknown at this time."
Reactor power was initially at 100% when the power failure occurred. After the reactor recirculation pumps downshifted to slow speed reactor power was at 50% when the automatic reactor scram initiated. All rods fully inserted into the core. All emergency core cooling systems and the emergency diesel generators are fully operable if needed.
The NRC Resident Inspector was notified of this event by the licensee.
"A power supply failed for three of four main steam line flow instruments for the feedwater level control system. Feedwater level control system responded to the sensed reduction in main steam flow by reducing feedwater flow. The feedwater flow reduction resulted in the reactor recirculation system pumps downshifting to slow speed. At 0557, the reactor protection system automatically tripped on Oscillation Power Range Monitors due to a power/flow mismatch. The operators did not observe any power oscillations. The plant is currently stable with reactor pressure being controlled by the main steam bypass valves and reactor level is being maintained by the feedwater system. "
"The reason for the loss of the power supply failure is unknown at this time."
Reactor power was initially at 100% when the power failure occurred. After the reactor recirculation pumps downshifted to slow speed reactor power was at 50% when the automatic reactor scram initiated. All rods fully inserted into the core. All emergency core cooling systems and the emergency diesel generators are fully operable if needed.
The NRC Resident Inspector was notified of this event by the licensee.