Event Notification Report for July 11, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/10/2003 - 07/11/2003
EVENT NUMBERS
39993
Power Reactor
Event Number: 39993
Facility: POINT BEACH
Region: 3 State: WI
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: RICK ROBBINS
HQ OPS Officer: ARLON COSTA
Region: 3 State: WI
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: RICK ROBBINS
HQ OPS Officer: ARLON COSTA
Notification Date: 07/11/2003
Notification Time: 23:57 [ET]
Event Date: 07/11/2003
Event Time: 20:09 [CDT]
Last Update Date: 07/11/2003
Notification Time: 23:57 [ET]
Event Date: 07/11/2003
Event Time: 20:09 [CDT]
Last Update Date: 07/11/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION
10 CFR Section:
50.72(b)(2)(iv)(A) - ECCS INJECTION
Person (Organization):
MARK RING (R3)
TAD MARSH (NRR)
MARK RING (R3)
TAD MARSH (NRR)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Hot Standby | 0 | Hot Standby |
MANUAL SAFETY INJECTION DUE TO PRESSURIZER LOW LEVEL
Unit 2 was in mode 3 with the main feedwater regulating valve controllers in automatic. Upon closure of the reactor trip breakers in preparation for critical approach, the main feed regulating valves opened causing a cooldown of the reactor coolant system (RCS) and pressurizer low level. The operator response sequence included a manual reactor trip and manual safety injection. There was no actual safety injection and the charging pumps made up for the RCS shrinkage due to the cooldown. Steam generator levels remained within their normal band range. A shutdown margin calculations was performed and verified satisfactorily. All plant systems functioned as required and the unit is currently stable in mode 3. The NRC Resident Inspector was in the Control Room during this incident.
Unit 2 was in mode 3 with the main feedwater regulating valve controllers in automatic. Upon closure of the reactor trip breakers in preparation for critical approach, the main feed regulating valves opened causing a cooldown of the reactor coolant system (RCS) and pressurizer low level. The operator response sequence included a manual reactor trip and manual safety injection. There was no actual safety injection and the charging pumps made up for the RCS shrinkage due to the cooldown. Steam generator levels remained within their normal band range. A shutdown margin calculations was performed and verified satisfactorily. All plant systems functioned as required and the unit is currently stable in mode 3. The NRC Resident Inspector was in the Control Room during this incident.