Event Notification Report for August 21, 2002
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
08/20/2002 - 08/21/2002
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 39142
Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: EURMAN HENSON
HQ OPS Officer: MIKE NORRIS
Region: 4 State: MO
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: EURMAN HENSON
HQ OPS Officer: MIKE NORRIS
Notification Date: 08/21/2002
Notification Time: 21:03 [ET]
Event Date: 08/21/2002
Event Time: 14:00 [CDT]
Last Update Date: 09/13/2002
Notification Time: 21:03 [ET]
Event Date: 08/21/2002
Event Time: 14:00 [CDT]
Last Update Date: 09/13/2002
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
WILLIAM JOHNSON (R4)
WILLIAM JOHNSON (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNANALYZED CONDITION REGARDING RCS BORATION REQUIREMENTS
"On August 21, 2002, with Callaway Plant in Mode 1 at 100 % power, it was determined that a potential unanalyzed condition had existed regarding Reactor Coolant System (RCS) boration requirements when in Mode 3 below the P-11 setpoint of 1970 psig RCS pressure. During an extent of condition review, a concern had been identified regarding the Westinghouse analysis of Steam Line Breaks in Mode 3 below P-11. In order to conclude that acceptable core performance results would be obtained for a lower Mode 3 Steam Line Break, the Westinghouse analyses assumes that the plant is borated to cold shutdown conditions prior to blocking P-11. Discussions with Westinghouse confirmed this requirement was applicable to Callaway. Callaway Plant procedures did not specifically require that the plant be maintained at Cold Shutdown boron concentrations with P-11 blocked. A historical review documented that the Callaway Plant shutdown twice within the last three years. During these shutdowns, the plant maneuvered through Mode 3 below P-11 once during each plant shutdown and once during each plant startup.
"A review of historical data is being conducted for those periods to establish actual boron concentrations versus calculated requirements for past conditions. Preliminary reviews for three of those periods have been completed and document actual boron concentrations of 1397 ppm or greater.
"This condition is being reported as an unanalyzed condition until historical reviews determine otherwise. Compensatory actions taken included determining a boron concentration that would satisfy accident analysis requirements for present plant conditions and revising Callaway Plant procedures to require boration to specified boron concentrations for Mode 3 operation with P-11 blocked."
P-11(Pressurizer SI Block Permissive) enables BLOCK switches to allow the operator to block low Pressurizer pressure SI.
The NRC Resident Inspector has been notified. The Licensee has discussed this condition with Wolf Creek.
****RETRACTION ON 09/13/02 AT 1527ET BY E. HENSON TAKEN BY MACKINNON****
Upon completion of a review of historical data encompassing the previous three years of plant operation, it was determined that sufficient boron concentrations were maintained to ensure compliance with accident analysis requirements when in Mode 3 below P-11. Based upon this information, no unanalyzed condition existed and Event Notification # 39142 is being retracted. R4DO (Jack Whitten) notified.
The NRC Resident Inspector was notified of this event retraction.
"On August 21, 2002, with Callaway Plant in Mode 1 at 100 % power, it was determined that a potential unanalyzed condition had existed regarding Reactor Coolant System (RCS) boration requirements when in Mode 3 below the P-11 setpoint of 1970 psig RCS pressure. During an extent of condition review, a concern had been identified regarding the Westinghouse analysis of Steam Line Breaks in Mode 3 below P-11. In order to conclude that acceptable core performance results would be obtained for a lower Mode 3 Steam Line Break, the Westinghouse analyses assumes that the plant is borated to cold shutdown conditions prior to blocking P-11. Discussions with Westinghouse confirmed this requirement was applicable to Callaway. Callaway Plant procedures did not specifically require that the plant be maintained at Cold Shutdown boron concentrations with P-11 blocked. A historical review documented that the Callaway Plant shutdown twice within the last three years. During these shutdowns, the plant maneuvered through Mode 3 below P-11 once during each plant shutdown and once during each plant startup.
"A review of historical data is being conducted for those periods to establish actual boron concentrations versus calculated requirements for past conditions. Preliminary reviews for three of those periods have been completed and document actual boron concentrations of 1397 ppm or greater.
"This condition is being reported as an unanalyzed condition until historical reviews determine otherwise. Compensatory actions taken included determining a boron concentration that would satisfy accident analysis requirements for present plant conditions and revising Callaway Plant procedures to require boration to specified boron concentrations for Mode 3 operation with P-11 blocked."
P-11(Pressurizer SI Block Permissive) enables BLOCK switches to allow the operator to block low Pressurizer pressure SI.
The NRC Resident Inspector has been notified. The Licensee has discussed this condition with Wolf Creek.
****RETRACTION ON 09/13/02 AT 1527ET BY E. HENSON TAKEN BY MACKINNON****
Upon completion of a review of historical data encompassing the previous three years of plant operation, it was determined that sufficient boron concentrations were maintained to ensure compliance with accident analysis requirements when in Mode 3 below P-11. Based upon this information, no unanalyzed condition existed and Event Notification # 39142 is being retracted. R4DO (Jack Whitten) notified.
The NRC Resident Inspector was notified of this event retraction.
Power Reactor
Event Number: 39140
Facility: FARLEY
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: PETE WEBB
HQ OPS Officer: JOHN MacKINNON
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: PETE WEBB
HQ OPS Officer: JOHN MacKINNON
Notification Date: 08/21/2002
Notification Time: 08:59 [ET]
Event Date: 08/21/2002
Event Time: 07:30 [CDT]
Last Update Date: 08/21/2002
Notification Time: 08:59 [ET]
Event Date: 08/21/2002
Event Time: 07:30 [CDT]
Last Update Date: 08/21/2002
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
KEN BARR (R2)
JOSEPH HOLONICH (IRO)
TERRY REIS (NRR)
KEN CIBOCH (FEMA)
KEN BARR (R2)
JOSEPH HOLONICH (IRO)
TERRY REIS (NRR)
KEN CIBOCH (FEMA)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
UNUSUAL EVENT DECLARED DUE TO FIRE AFFECTING EMERGENCY CORE COOLING SYSTEM
Loss of "A" Train Service Water as a result of a fire on the "1C" Service Water pump. The "1C" pump tripped and the "1A" Service Water was out of service for maintenance. Fire was out at 0724 CDT. Actions being taken to restore the "A" Train Service Water. The "1B" Service Water pump remained running during the entire event. System pressure remained at required value.
The Fire Protection System for the "1C" Service Water pump actuated and extinguished the fire. When the fire brigade arrived the fire was already out. The licensee did not need offsite help for the fire. "B" Train Service Water is operating.
The licensee notified State and local officials of the declaration of an Unusual Event.
The NRC Resident Inspector was notified of this event by the licensee.
****UPDATE AT 0931 ET ON 08/21/02 BY BOB VANDERBYE TAKEN BY MACKINNON****
Unusual event has been terminated at 0814 CT as a result that there was no fire and the plant is stable. No fire was seen but a large arc was seen when the "1C" Service Water pump tripped. State and Local officials will be notified by the licensee that the Unusual event was terminated at 0814 CT. R2DO (Ken Barr), NRR EO (Terry Reis), & FEMA (Ken Ciboch) notified.
The NRC Resident Inspector will be notified by the licensee.
Loss of "A" Train Service Water as a result of a fire on the "1C" Service Water pump. The "1C" pump tripped and the "1A" Service Water was out of service for maintenance. Fire was out at 0724 CDT. Actions being taken to restore the "A" Train Service Water. The "1B" Service Water pump remained running during the entire event. System pressure remained at required value.
The Fire Protection System for the "1C" Service Water pump actuated and extinguished the fire. When the fire brigade arrived the fire was already out. The licensee did not need offsite help for the fire. "B" Train Service Water is operating.
The licensee notified State and local officials of the declaration of an Unusual Event.
The NRC Resident Inspector was notified of this event by the licensee.
****UPDATE AT 0931 ET ON 08/21/02 BY BOB VANDERBYE TAKEN BY MACKINNON****
Unusual event has been terminated at 0814 CT as a result that there was no fire and the plant is stable. No fire was seen but a large arc was seen when the "1C" Service Water pump tripped. State and Local officials will be notified by the licensee that the Unusual event was terminated at 0814 CT. R2DO (Ken Barr), NRR EO (Terry Reis), & FEMA (Ken Ciboch) notified.
The NRC Resident Inspector will be notified by the licensee.