Event Notification Report for November 23, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/22/2003 - 11/23/2003
EVENT NUMBERS
40350
Power Reactor
Event Number: 40350
Facility: SALEM
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN KONOVALCHICK
HQ OPS Officer: GERRY WAIG
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN KONOVALCHICK
HQ OPS Officer: GERRY WAIG
Notification Date: 11/23/2003
Notification Time: 06:48 [ET]
Event Date: 11/23/2003
Event Time: 05:19 [EST]
Last Update Date: 11/23/2003
Notification Time: 06:48 [ET]
Event Date: 11/23/2003
Event Time: 05:19 [EST]
Last Update Date: 11/23/2003
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):
JOHN ROGGE (R1)
JOHN ROGGE (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 0 | Startup | 0 | Hot Standby |
REACTOR WAS MANUALLY TRIPPED AFTER A CONTROL ROD DROPPED DURING LOW POWER PHYSICS
"During performance of low power physics testing for dynamic rod worth measurements, control rod bank D was being withdrawn. At control bank D position of 209 steps, control rod 1D4 dropped into the reactor core. The control room crew entered the abnormal operating procedure for a dropped [control] rod at 0507. Based upon the dropped control rod causing the reactor to go subcritical, the abnormal operating procedure directs that all [control] rods to be inserted. Based upon the control bank D not being fully withdrawn and not in the proper bank overlap due to low power physics testing, the Control Room Supervisor directed the reactor to be [manually] tripped. The crew entered the emergency operating procedure at 0519. All equipment functioned as designed and all major equipment is available. [The crew] exited the emergency operating procedures at 0538. The plant is currently stable in mode 3 at normal operating temperature and pressure.
"The cause of the drop rod is reported to be a blown fuse on the stationary coil. All reactor coolant pumps are in service and decay heat removal is through the steam dumps to the condenser."
All control rods fully inserted when the reactor was manually tripped. Feedwater to the steam generators is being supplied by the auxiliary feedwater system.
The licensee has notified the NRC Resident Inspector and will be notifying the LAC (Lower Alloways Creek) Township.
"During performance of low power physics testing for dynamic rod worth measurements, control rod bank D was being withdrawn. At control bank D position of 209 steps, control rod 1D4 dropped into the reactor core. The control room crew entered the abnormal operating procedure for a dropped [control] rod at 0507. Based upon the dropped control rod causing the reactor to go subcritical, the abnormal operating procedure directs that all [control] rods to be inserted. Based upon the control bank D not being fully withdrawn and not in the proper bank overlap due to low power physics testing, the Control Room Supervisor directed the reactor to be [manually] tripped. The crew entered the emergency operating procedure at 0519. All equipment functioned as designed and all major equipment is available. [The crew] exited the emergency operating procedures at 0538. The plant is currently stable in mode 3 at normal operating temperature and pressure.
"The cause of the drop rod is reported to be a blown fuse on the stationary coil. All reactor coolant pumps are in service and decay heat removal is through the steam dumps to the condenser."
All control rods fully inserted when the reactor was manually tripped. Feedwater to the steam generators is being supplied by the auxiliary feedwater system.
The licensee has notified the NRC Resident Inspector and will be notifying the LAC (Lower Alloways Creek) Township.