Event Notification Report for June 20, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
06/19/2001 - 06/20/2001
Power Reactor
Event Number: 38080
Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: GEORGE RUITER
HQ OPS Officer: JOHN MacKINNON
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: GEORGE RUITER
HQ OPS Officer: JOHN MacKINNON
Notification Date: 06/20/2001
Notification Time: 04:07 [ET]
Event Date: 06/20/2001
Event Time: 00:11 [CDT]
Last Update Date: 06/20/2001
Notification Time: 04:07 [ET]
Event Date: 06/20/2001
Event Time: 00:11 [CDT]
Last Update Date: 06/20/2001
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):
MONTE PHILLIPS (R3)
MONTE PHILLIPS (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 96 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR TRIP DUE TO FEEDWATER REGULATING VALVE FAILING SHUT.
At 0011 CDT feedwater regulating valve to steam generator "B" failed to the closed position and manual control was not effective. The reactor/turbine tripped on steam flow greater than feed flow coincident with low steam generator water level. Following the trip, the rod bottom light for rod D4 (interior rod) was off and valve LD-2 indicated mid-position (letdown isolated on low pressurizer water level). Individual Rod Position Indication for rod D4 indicates zero, however, emergency boration was used to inject the required amount of boric acid for one stuck rod. Excess letdown was established at 0028 CDT hours, since normal letdown was not available due to the failure of valve LD-2. All emergency core cooling systems, emergency diesel generators are fully operable if needed and the electrical grid is stable.
Both Motor Driven and the Turbine Driven Auxiliary Feedwater Pumps automatically started. The Turbine Driven Auxiliary Feedwater pump was secured per procedure and steam generator water is being maintained by the Motor Driven Auxiliary Feedwater Pumps.
At this time the licensee thinks that rod bottom light for rod D4 is burned out. The licensee is also investigating why letdown isolation valve, LD-2, indicates mid-position and the unexpected closure of feedwater regulating valve for steam generator "B". The steam dump bypass control system is operating properly.
The NRC Resident Inspector was notified of this event by the licensee.
At 0011 CDT feedwater regulating valve to steam generator "B" failed to the closed position and manual control was not effective. The reactor/turbine tripped on steam flow greater than feed flow coincident with low steam generator water level. Following the trip, the rod bottom light for rod D4 (interior rod) was off and valve LD-2 indicated mid-position (letdown isolated on low pressurizer water level). Individual Rod Position Indication for rod D4 indicates zero, however, emergency boration was used to inject the required amount of boric acid for one stuck rod. Excess letdown was established at 0028 CDT hours, since normal letdown was not available due to the failure of valve LD-2. All emergency core cooling systems, emergency diesel generators are fully operable if needed and the electrical grid is stable.
Both Motor Driven and the Turbine Driven Auxiliary Feedwater Pumps automatically started. The Turbine Driven Auxiliary Feedwater pump was secured per procedure and steam generator water is being maintained by the Motor Driven Auxiliary Feedwater Pumps.
At this time the licensee thinks that rod bottom light for rod D4 is burned out. The licensee is also investigating why letdown isolation valve, LD-2, indicates mid-position and the unexpected closure of feedwater regulating valve for steam generator "B". The steam dump bypass control system is operating properly.
The NRC Resident Inspector was notified of this event by the licensee.
Power Reactor
Event Number: 38081
Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: MORIARTY
HQ OPS Officer: CHAUNCEY GOULD
Region: 1 State: VT
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: MORIARTY
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 06/20/2001
Notification Time: 11:56 [ET]
Event Date: 06/20/2001
Event Time: 11:15 [EDT]
Last Update Date: 06/20/2001
Notification Time: 11:56 [ET]
Event Date: 06/20/2001
Event Time: 11:15 [EDT]
Last Update Date: 06/20/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
10 CFR Section:
73.71(b)(1) - SAFEGUARDS REPORTS
Person (Organization):
JAMES TRAPP (R1)
JAMES TRAPP (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNESCORTED ACCESS GRANTED INAPPROPRIATELY.
COMPENSATORY MEASURES TAKEN UPON DISCOVERY
THE RESIDENT INSPECTOR WAS NOTIFIED
CONTACT THE HOO FOR ADDITIONAL INFORMATION
COMPENSATORY MEASURES TAKEN UPON DISCOVERY
THE RESIDENT INSPECTOR WAS NOTIFIED
CONTACT THE HOO FOR ADDITIONAL INFORMATION