Event Notification Report for March 02, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
03/01/2000 - 03/02/2000
Power Reactor
Event Number: 36748
Facility: MCGUIRE
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: HUSSEY
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: HUSSEY
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/02/2000
Notification Time: 18:18 [ET]
Event Date: 03/02/2000
Event Time: 18:00 [EST]
Last Update Date: 03/02/2000
Notification Time: 18:18 [ET]
Event Date: 03/02/2000
Event Time: 18:00 [EST]
Last Update Date: 03/02/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
10 CFR Section:
50.72(b)(1)(ii)(B) - OUTSIDE DESIGN BASIS
Person (Organization):
LEN WERT (R2)
LEN WERT (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
THE LICENSEE DISCOVERED NON-CONSERVATISM IN CRITICALITY CALCULATIONS FOR FUEL POOL STORAGE REQUIREMENTS.
It was determined that certain assumptions may result in a K-effective (K-eff) in excess of 0.95 at 0 ppm boron concentration in the spent fuel pool. The Design Basis of the plant is that the fuel stored in the fuel pool will remain less than or equal to 0.95 K-eff when fully flooded with unborated water. As such the Licensee is reporting this as a condition outside the design basis of the plant in accordance with 10CFR50.72(b)(1)(ii)(B).
Currently each spent fuel pool has boron concentrations in excess of 2675 ppm as required by Technical Specifications. Under these conditions, with routine monitoring of boron concentration as required by Technical Specifications, the plant will not require any compensatory measures to remain operable in the fuel pool. Duke will continue to evaluate the models to further evaluate this condition.
The NRC Resident Inspector was informed.
It was determined that certain assumptions may result in a K-effective (K-eff) in excess of 0.95 at 0 ppm boron concentration in the spent fuel pool. The Design Basis of the plant is that the fuel stored in the fuel pool will remain less than or equal to 0.95 K-eff when fully flooded with unborated water. As such the Licensee is reporting this as a condition outside the design basis of the plant in accordance with 10CFR50.72(b)(1)(ii)(B).
Currently each spent fuel pool has boron concentrations in excess of 2675 ppm as required by Technical Specifications. Under these conditions, with routine monitoring of boron concentration as required by Technical Specifications, the plant will not require any compensatory measures to remain operable in the fuel pool. Duke will continue to evaluate the models to further evaluate this condition.
The NRC Resident Inspector was informed.
Power Reactor
Event Number: 36749
Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MORRIS
HQ OPS Officer: CHAUNCEY GOULD
Region: 4 State: TX
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MORRIS
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 03/02/2000
Notification Time: 19:25 [ET]
Event Date: 03/02/2000
Event Time: 16:30 [CST]
Last Update Date: 03/02/2000
Notification Time: 19:25 [ET]
Event Date: 03/02/2000
Event Time: 16:30 [CST]
Last Update Date: 03/02/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
CHARLES CAIN (R4)
CHARLES CAIN (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
LICENSEE DID NOT COMPLY WITH LCO ACTION STATEMENTS
On March 1, 2000 at 1008 hours, 125 VDC Battery System E1A11 was declared inoperable. Subsequently, in accordance with Technical Specifications 3.8.2.2, "D. C. Sources," and 3.8.3.2, "Onsite Power Distribution - Shutdown," Nuclear Instrumentation Source Range Detector 31 should have been declared inoperable or actions should have been initiated to suspend operations involving positive reactivity changes. Contrary to these requirements, Source Range Detector 31 was not declared inoperable, and at 0027 hours on March 2, 2000, control rods were moved as part of rapid refueling rod holdout operations. The rods were cycled 18 steps 3 times between the hours 0027 and 0400 @ 3/2/00. No movements have taken place since then. Detector 31 has been declared inoperable and is still inoperable.
The NRC Resident Inspector has been notified.
This notification is being made pursuant to Operating License NPF-76 Condition 2.G for operation or condition prohibited by Technical Specifications.
On March 1, 2000 at 1008 hours, 125 VDC Battery System E1A11 was declared inoperable. Subsequently, in accordance with Technical Specifications 3.8.2.2, "D. C. Sources," and 3.8.3.2, "Onsite Power Distribution - Shutdown," Nuclear Instrumentation Source Range Detector 31 should have been declared inoperable or actions should have been initiated to suspend operations involving positive reactivity changes. Contrary to these requirements, Source Range Detector 31 was not declared inoperable, and at 0027 hours on March 2, 2000, control rods were moved as part of rapid refueling rod holdout operations. The rods were cycled 18 steps 3 times between the hours 0027 and 0400 @ 3/2/00. No movements have taken place since then. Detector 31 has been declared inoperable and is still inoperable.
The NRC Resident Inspector has been notified.
This notification is being made pursuant to Operating License NPF-76 Condition 2.G for operation or condition prohibited by Technical Specifications.