Event Notification Report for November 28, 2003
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
11/27/2003 - 11/28/2003
Power Reactor
Event Number: 40361
Facility: MILLSTONE
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: JEFF YOUNG
HQ OPS Officer: BILL GOTT
Region: 1 State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: JEFF YOUNG
HQ OPS Officer: BILL GOTT
Notification Date: 11/28/2003
Notification Time: 22:57 [ET]
Event Date: 11/28/2003
Event Time: 22:05 [EST]
Last Update Date: 11/28/2003
Notification Time: 22:57 [ET]
Event Date: 11/28/2003
Event Time: 22:05 [EST]
Last Update Date: 11/28/2003
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):
ANTHONY DIMITRIADIS (R1)
ANTHONY DIMITRIADIS (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | M/R | Y | 11 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP FROM 11% POWER DUE TO TURBINE VIBRATION
At 2205 EST on 11/28/03 while at 11% power, Millstone Unit 2 performed a required manual reactor trip when main turbine vibration reached a turbine trip set point of 12 MILS. The turbine vibration did not reduce when the turbine was tripped which required breaking condenser vacuum and ultimately a manual reactor trip. The main turbine vibrations were anticipated during power ascension due to a newly installed low pressure "Mono-Block" rotor. All control rods fully inserted during the reactor trip and no ECCS injection occurred or primary relief valves lifted.
The licensee informed the NRC Resident Inspector.
At 2205 EST on 11/28/03 while at 11% power, Millstone Unit 2 performed a required manual reactor trip when main turbine vibration reached a turbine trip set point of 12 MILS. The turbine vibration did not reduce when the turbine was tripped which required breaking condenser vacuum and ultimately a manual reactor trip. The main turbine vibrations were anticipated during power ascension due to a newly installed low pressure "Mono-Block" rotor. All control rods fully inserted during the reactor trip and no ECCS injection occurred or primary relief valves lifted.
The licensee informed the NRC Resident Inspector.
Power Reactor
Event Number: 40362
Facility: COOPER
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JOHN MYERS
HQ OPS Officer: MIKE RIPLEY
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JOHN MYERS
HQ OPS Officer: MIKE RIPLEY
Notification Date: 11/29/2003
Notification Time: 02:47 [ET]
Event Date: 11/28/2003
Event Time: 22:02 [CST]
Last Update Date: 11/29/2003
Notification Time: 02:47 [ET]
Event Date: 11/28/2003
Event Time: 22:02 [CST]
Last Update Date: 11/29/2003
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(2)(iv)(A) - ECCS INJECTION 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)(2)(iv)(A) - ECCS INJECTION 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
BLAIR SPITZBERG (R4)
BLAIR SPITZBERG (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC SCRAM DUE TO LOW REACTOR WATER LEVEL
"At 2202 CST, a low Reactor Water Level Scram (Level 3) occurred due to lowering feedwater flow. All control rods inserted on the Scram. The Scram resulted in actuation of HPCI and RCIC on low Reactor Water level (Level 2), and the low level ATWS Recirculation Pump Trip (RPT). HPCI and RCIC initiated and both Reactor Recirculation pumps tripped. It is estimated that RCIC injected approximately 500 to 600 gallons, and HPCI injected less than 100 gallons. HPCI was secured early in the transient, and RCIC operated for approximately 2 minutes. Reactor Water level was recovered and maintained with the operating feedwater pump.
"The Reactor Water low level (Level 3) also resulted in Group 2 (Primary Containment), Group 3 (Reactor Water Cleanup), and Group 6 isolations (Secondary Containment Isolation and Control Room Ventilation system start). All isolations functioned as designed.
"Initial indications are that Feedwater Pump B speed lowered unexpectedly, causing Reactor Water level to lower. Reactor Water level reached -44 inches (wide range instruments) [120 inches above top of active fuel]. The setpoints for HPCI, RCIC, and ATWS-RPT are -33 inches.
"Plans are to take the unit to Mode 4."
The licensee notified the NRC Resident Inspector.
"At 2202 CST, a low Reactor Water Level Scram (Level 3) occurred due to lowering feedwater flow. All control rods inserted on the Scram. The Scram resulted in actuation of HPCI and RCIC on low Reactor Water level (Level 2), and the low level ATWS Recirculation Pump Trip (RPT). HPCI and RCIC initiated and both Reactor Recirculation pumps tripped. It is estimated that RCIC injected approximately 500 to 600 gallons, and HPCI injected less than 100 gallons. HPCI was secured early in the transient, and RCIC operated for approximately 2 minutes. Reactor Water level was recovered and maintained with the operating feedwater pump.
"The Reactor Water low level (Level 3) also resulted in Group 2 (Primary Containment), Group 3 (Reactor Water Cleanup), and Group 6 isolations (Secondary Containment Isolation and Control Room Ventilation system start). All isolations functioned as designed.
"Initial indications are that Feedwater Pump B speed lowered unexpectedly, causing Reactor Water level to lower. Reactor Water level reached -44 inches (wide range instruments) [120 inches above top of active fuel]. The setpoints for HPCI, RCIC, and ATWS-RPT are -33 inches.
"Plans are to take the unit to Mode 4."
The licensee notified the NRC Resident Inspector.