Event Notification Report for April 20, 2008
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/19/2008 - 04/20/2008
EVENT NUMBERS
44152
Power Reactor
Event Number: 44152
Facility: SURRY
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: HUNTER SCHILL
HQ OPS Officer: JOHN KNOKE
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: HUNTER SCHILL
HQ OPS Officer: JOHN KNOKE
Notification Date: 04/21/2008
Notification Time: 00:37 [ET]
Event Date: 04/20/2008
Event Time: 22:16 [EDT]
Last Update Date: 04/21/2008
Notification Time: 00:37 [ET]
Event Date: 04/20/2008
Event Time: 22:16 [EDT]
Last Update Date: 04/21/2008
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 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)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
KATHLEEN O'DONOHUE (R2)
KATHLEEN O'DONOHUE (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 37 | Power Operation | 0 | Hot Shutdown |
UNIT 1 MANUAL REACTOR TRIP DUE TO MAIN TURBINE VIBRATIONS
"While ramping the Unit 1 Turbine following a forced unit outage, vibrations on the number 4 bearing increased to 13.9 mils. The ramp was stopped and a rapid load reduction was initiated. Due to sustained vibrations (>14.1 mils) after ramping the turbine down, the Unit 1 reactor was manually tripped. Unit 1 has been stabilized at Hot Shutdown.
"All three auxiliary feedwater pumps automatically initiated as designed on low-low steam generator level following the trip. Currently RCS temperature is being maintained stable at 547 degrees. All systems functioned as required following the reactor trip. There were no radiation releases due to this event, nor were there any personnel injuries or contamination events. This event is being reported in accordance with 10 CFR 50.72 (b)(2)(iv) and 10 CFR 50.72 (b)(3)(iv)."
Upon exiting the refueling outage in 11/07 the main turbine had a vibration issue of about 11 or 12 mils. Decay heat is being removed via the steam dumps to the condenser. Unit 2 was not affected during this event. Offsite power was lined up normally.
The licensee notified the NRC Resident Inspector.
"While ramping the Unit 1 Turbine following a forced unit outage, vibrations on the number 4 bearing increased to 13.9 mils. The ramp was stopped and a rapid load reduction was initiated. Due to sustained vibrations (>14.1 mils) after ramping the turbine down, the Unit 1 reactor was manually tripped. Unit 1 has been stabilized at Hot Shutdown.
"All three auxiliary feedwater pumps automatically initiated as designed on low-low steam generator level following the trip. Currently RCS temperature is being maintained stable at 547 degrees. All systems functioned as required following the reactor trip. There were no radiation releases due to this event, nor were there any personnel injuries or contamination events. This event is being reported in accordance with 10 CFR 50.72 (b)(2)(iv) and 10 CFR 50.72 (b)(3)(iv)."
Upon exiting the refueling outage in 11/07 the main turbine had a vibration issue of about 11 or 12 mils. Decay heat is being removed via the steam dumps to the condenser. Unit 2 was not affected during this event. Offsite power was lined up normally.
The licensee notified the NRC Resident Inspector.