Event Notification Report for January 19, 2002
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/18/2002 - 01/19/2002
EVENT NUMBERS
38640
Power Reactor
Event Number: 38640
Facility: COOK
Region: 3 State: MI
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: S. KOSHAY
HQ OPS Officer: JOHN MacKINNON
Region: 3 State: MI
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: S. KOSHAY
HQ OPS Officer: JOHN MacKINNON
Notification Date: 01/19/2002
Notification Time: 07:56 [ET]
Event Date: 01/19/2002
Event Time: 00:05 [EST]
Last Update Date: 01/19/2002
Notification Time: 07:56 [ET]
Event Date: 01/19/2002
Event Time: 00:05 [EST]
Last Update Date: 01/19/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ANTON VEGEL (R3)
ANTON VEGEL (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Hot Standby | 0 | Hot Standby |
UNEXPECTED AUTOMATIC START OF TURBINE DRIVEN AUXILIARY FEEDWATER PUMP (TDAFW) AFTER PLANT SHUTDOWN.
After the scheduled reactor trip from 20% power in preparation for a refueling outage the steam generator water level lowered to approximately 17%. This was lower than anticipated on the trip resulting in the Turbine Driven Auxiliary Feedwater Pump autostarting as a function of the steam generator's water level. Both Motor Driven Auxiliary Feedwater (MDAFW) pumps had already been started. Steam generator water levels rapidly recovered and the reactor coolant system cooled below 547 degrees F, which is the normal no load temperature, to 540 degrees F. The 7 degree cooldown below the Tave No Load Condition resulted in Pressurizer Water Level shrink and a letdown isolation. The operators secured the TDAFW pump and throttled the flows from the MDAFW pumps and restored reactor coolant system temperature and pressurizer inventory. The reactor coolant system cooldown and depressurization proceeded normally from that point on.
The NRC Resident Inspector was notified of this event by the licensee.
After the scheduled reactor trip from 20% power in preparation for a refueling outage the steam generator water level lowered to approximately 17%. This was lower than anticipated on the trip resulting in the Turbine Driven Auxiliary Feedwater Pump autostarting as a function of the steam generator's water level. Both Motor Driven Auxiliary Feedwater (MDAFW) pumps had already been started. Steam generator water levels rapidly recovered and the reactor coolant system cooled below 547 degrees F, which is the normal no load temperature, to 540 degrees F. The 7 degree cooldown below the Tave No Load Condition resulted in Pressurizer Water Level shrink and a letdown isolation. The operators secured the TDAFW pump and throttled the flows from the MDAFW pumps and restored reactor coolant system temperature and pressurizer inventory. The reactor coolant system cooldown and depressurization proceeded normally from that point on.
The NRC Resident Inspector was notified of this event by the licensee.