Event Notification Report for December 21, 1999
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/20/1999 - 12/21/1999
EVENT NUMBERS
36532
Power Reactor
Event Number: 36532
Facility: OCONEE
Region: 2 State: SC
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: NEIL CONSTANCE
HQ OPS Officer: DOUG WEAVER
Region: 2 State: SC
Unit: [] [2] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: NEIL CONSTANCE
HQ OPS Officer: DOUG WEAVER
Notification Date: 12/21/1999
Notification Time: 19:34 [ET]
Event Date: 12/21/1999
Event Time: 18:52 [EST]
Last Update Date: 12/21/1999
Notification Time: 19:34 [ET]
Event Date: 12/21/1999
Event Time: 18:52 [EST]
Last Update Date: 12/21/1999
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(ii) - RPS ACTUATION
10 CFR Section:
50.72(b)(2)(ii) - RPS ACTUATION
Person (Organization):
CHARLES OGLE (R2)
CHARLES OGLE (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 0 | Hot Standby |
REACTOR SCRAM ON HIGH REACTOR SYSTEM PRESSURE (Refer to event #36537 for a similar event that occurred on 12/24/99.)
"Unit 2 tripped on RCS high pressure at 1852. The Reactor Protection System (RPS) setpoint of 2345 psig was exceeded, resulting in an RPS actuation and tripping [of] all CRD breakers. RCS pressure peaked at 2378 psig. The initiating event was a transient on the secondary plant that affected heat removal capabilities. Post-trip response was normal. The plant is presently in mode 3 with a trip investigation in progress."
No primary Power-Operated Relief valves or code safety valves lifted. Secondary side code safeties lifted as expected on a trip. All valves shut, but two have minor leakage. The plant is stable in mode 3 with RCPs running and decay heat being removed via the Steam Generators to the main condenser.
The NRC resident inspector was notified.
"Unit 2 tripped on RCS high pressure at 1852. The Reactor Protection System (RPS) setpoint of 2345 psig was exceeded, resulting in an RPS actuation and tripping [of] all CRD breakers. RCS pressure peaked at 2378 psig. The initiating event was a transient on the secondary plant that affected heat removal capabilities. Post-trip response was normal. The plant is presently in mode 3 with a trip investigation in progress."
No primary Power-Operated Relief valves or code safety valves lifted. Secondary side code safeties lifted as expected on a trip. All valves shut, but two have minor leakage. The plant is stable in mode 3 with RCPs running and decay heat being removed via the Steam Generators to the main condenser.
The NRC resident inspector was notified.