Event Notification Report for December 22, 2000
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
12/21/2000 - 12/22/2000
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 37630
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: RICK HUBBARD
HQ OPS Officer: DOUG WEAVER
Region: 4 State: KS
Unit: [1] [] []
RX Type: [1] W-4-LP
NRC Notified By: RICK HUBBARD
HQ OPS Officer: DOUG WEAVER
Notification Date: 12/22/2000
Notification Time: 11:29 [ET]
Event Date: 12/22/2000
Event Time: 09:45 [CST]
Last Update Date: 02/19/2001
Notification Time: 11:29 [ET]
Event Date: 12/22/2000
Event Time: 09:45 [CST]
Last Update Date: 02/19/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(1)(v) - OTHER ASMT/COMM INOP
10 CFR Section:
50.72(b)(1)(v) - OTHER ASMT/COMM INOP
Person (Organization):
BILL JONES (R4)
BILL JONES (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 |
LOSS OF POWER TO THE TECHNICAL SUPPORT CENTER (TSC)
Breaker 13-40 tripped with the ground flag dropped. This breaker supplies primary power to the TSC. There is a backup diesel generator available to supply power to the TSC but will not be energized until it is determined that there is no ground at the TSC. Once the TSC D/G is energized the facility will once again be available.
The licensee notified the NRC resident inspector.
* * * Update at 1150 on 12/22/00 by Hubbard received by Weaver * * *
The diesel generator is now supplying the TSC with electrical power (as of 1041 CST). Investigation continues into why breaker 13-40 tripped.
Notified the R4DO(Jones).
* * * RETRACTED AT 1309 EST ON 2/19/01 BY CHRIS REEKIE TO FANGIE JONES * * *
The licensee is retracting this event. Upon review of the potential loss of emergency communications and assessment capability they have determined that no such loss would have happened with the initial problem.
The licensee notified the NRC Resident Inspector. The R4DO (Greg Pick) has been notified.
Breaker 13-40 tripped with the ground flag dropped. This breaker supplies primary power to the TSC. There is a backup diesel generator available to supply power to the TSC but will not be energized until it is determined that there is no ground at the TSC. Once the TSC D/G is energized the facility will once again be available.
The licensee notified the NRC resident inspector.
* * * Update at 1150 on 12/22/00 by Hubbard received by Weaver * * *
The diesel generator is now supplying the TSC with electrical power (as of 1041 CST). Investigation continues into why breaker 13-40 tripped.
Notified the R4DO(Jones).
* * * RETRACTED AT 1309 EST ON 2/19/01 BY CHRIS REEKIE TO FANGIE JONES * * *
The licensee is retracting this event. Upon review of the potential loss of emergency communications and assessment capability they have determined that no such loss would have happened with the initial problem.
The licensee notified the NRC Resident Inspector. The R4DO (Greg Pick) has been notified.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 37631
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: NACOSTE
HQ OPS Officer: CHAUNCEY GOULD
Region: 2 State: AL
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: NACOSTE
HQ OPS Officer: CHAUNCEY GOULD
Notification Date: 12/22/2000
Notification Time: 16:54 [ET]
Event Date: 12/22/2000
Event Time: 12:25 [CST]
Last Update Date: 12/23/2000
Notification Time: 16:54 [ET]
Event Date: 12/22/2000
Event Time: 12:25 [CST]
Last Update Date: 12/23/2000
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iii)(A) - POT UNABLE TO SAFE SD
10 CFR Section:
50.72(b)(2)(iii)(A) - POT UNABLE TO SAFE SD
Person (Organization):
MIKE ERNSTES (R2)
MIKE ERNSTES (R2)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
PLANT ENTERED 14 DAY LCO DUE TO HIGH PRESSURE COOLANT INJECTION BEING INOPERABLE
HPCI was declared inoperable after failing testing. During the performance of 2-SI-3.5.1.7 HPCI MAIN AND BOOSTER PUMP SET DEVELOPED HEAD AND FLOW RATE TEST AT RATED REACTOR PRESSURE, the HPCI system could not be verified to be vented.
The probable reason for not being able to make this verification is due to a faulty flow gauge in the HPCI piping system.
The NRC Resident Inspector will be notified.
* * * RETRACTED AT 0240 EST 0N 12/23/00 BY MICKEY HUNTER TO FANGIE JONES * * *
"The 4 hour report made in accordance with 10CFR50.72.b.2.iii at 1630 on 12/22/2000 is being retracted for the following reasons: During the performance of 2-SR-3.5.1.7 HPCI MAIN AND BOOSTER PUMP SET DEVELOPED HEAD AND FLOW RATE TEST AT RATED REACTOR PRESSURE, there were indications of flow through the vent line during initial Surveillance testing however; the test methodology used in the Surveillance could not verify that flow. We revised the Surveillance methodology to prescribe an alternate process of determining flow. The Surveillance test was reperformed satisfactorily and verified indications of flow that was observed in the previous performance of the Surveillance test. Thus this proved operability of HPCI during previous performance of Surveillance test."
The licensee notified the NRC Resident Inspector. The R2DO (Mike Ernstses) was notified.
HPCI was declared inoperable after failing testing. During the performance of 2-SI-3.5.1.7 HPCI MAIN AND BOOSTER PUMP SET DEVELOPED HEAD AND FLOW RATE TEST AT RATED REACTOR PRESSURE, the HPCI system could not be verified to be vented.
The probable reason for not being able to make this verification is due to a faulty flow gauge in the HPCI piping system.
The NRC Resident Inspector will be notified.
* * * RETRACTED AT 0240 EST 0N 12/23/00 BY MICKEY HUNTER TO FANGIE JONES * * *
"The 4 hour report made in accordance with 10CFR50.72.b.2.iii at 1630 on 12/22/2000 is being retracted for the following reasons: During the performance of 2-SR-3.5.1.7 HPCI MAIN AND BOOSTER PUMP SET DEVELOPED HEAD AND FLOW RATE TEST AT RATED REACTOR PRESSURE, there were indications of flow through the vent line during initial Surveillance testing however; the test methodology used in the Surveillance could not verify that flow. We revised the Surveillance methodology to prescribe an alternate process of determining flow. The Surveillance test was reperformed satisfactorily and verified indications of flow that was observed in the previous performance of the Surveillance test. Thus this proved operability of HPCI during previous performance of Surveillance test."
The licensee notified the NRC Resident Inspector. The R2DO (Mike Ernstses) was notified.