Event Notification Report for February 04, 2001
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/03/2001 - 02/04/2001
Power Reactor
Event Number: 37714
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: MATT BAKER
HQ OPS Officer: BOB STRANSKY
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: MATT BAKER
HQ OPS Officer: BOB STRANSKY
Notification Date: 02/04/2001
Notification Time: 04:25 [ET]
Event Date: 02/04/2001
Event Time: 01:18 [CST]
Last Update Date: 02/04/2001
Notification Time: 04:25 [ET]
Event Date: 02/04/2001
Event Time: 01:18 [CST]
Last Update Date: 02/04/2001
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):
DAVID HILLS (R3)
DAVID HILLS (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 TURBINE TRIP/REACTOR SCRAM DURING TESTING
During performance or routine turbine valve testing, an automatic turbine trip and subsequent reactor scram occurred due to low turbine emergency trip system pressure. The unit is currently stable in Condition 3 (Hot Shutdown) with reactor vessel water level being maintained by the motor driven feedwater pump and reactor pressure being controlled via the steam bypass valves to the main condenser. All systems functioned as expected.
The NRC resident inspector has been informed of this event by the licensee.
During performance or routine turbine valve testing, an automatic turbine trip and subsequent reactor scram occurred due to low turbine emergency trip system pressure. The unit is currently stable in Condition 3 (Hot Shutdown) with reactor vessel water level being maintained by the motor driven feedwater pump and reactor pressure being controlled via the steam bypass valves to the main condenser. All systems functioned as expected.
The NRC resident inspector has been informed of this event by the licensee.
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
!!!!! THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor
Event Number: 37715
Facility: POINT BEACH
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: MIKE MEYER
HQ OPS Officer: FANGIE JONES
Region: 3 State: WI
Unit: [1] [] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: MIKE MEYER
HQ OPS Officer: FANGIE JONES
Notification Date: 02/04/2001
Notification Time: 14:52 [ET]
Event Date: 02/04/2001
Event Time: 12:45 [CST]
Last Update Date: 02/09/2001
Notification Time: 14:52 [ET]
Event Date: 02/04/2001
Event Time: 12:45 [CST]
Last Update Date: 02/09/2001
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVID HILLS (R3)
DAVID HILLS (R3)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 80 | Power Operation | 80 | Power Operation |
DISCOVERY OF VALVE CLOSED THAT COULD AFFECT ACCIDENT MITIGATION
"While performing troubleshooting operation on the Unit 1 Crossover Steam Dump System an Instrument Air Valve was discovered to be closed, when it should have been open. This closed valve (IA-1553) isolates Instrument Air to the Crossover Steam Dump Valves rendering the system inoperable. This system is required to be operable by the FSAR Appendix T and Power must be <437 MWe if the system is inop. At the time of discovery power was <437 MWe, however initial investigation leads to the conclusion that this valve has probably been closed since October, 2000. Since Crossover Steam Dumps provide protection for a Turbine Overspeed Accident and is part of the PBNP Design Basis it was conservatively decided to make this 8-hour report. Unit 1 will remain < 437 MWe until the system is fully restored and tested. An investigation is continuing."
The licensee notified the NRC Resident Inspector.
* * * UPDATE ON 2/9/01 @ 1630 BY ADAMS TO GOULD * * * RETRACTION
This event reported that the cross over steam dump system was discovered to be inoperable because of a mis-positioned instrument air valve. This was reported as a condition that could have prevented fulfillment of a safety function for a SSC [structure, system, and component] needed to mitigate the consequences of an accident. Upon closer evaluation of the condition and examination of the applicable licensing bases, they have determined that this condition is not reportable for the following reasons:
1. The cross over steam dump system is not a TS controlled system. The turbine overspeed protection system TS LCOs and surveillances were removed from the TS by License Amendments 176 and 180 on August 6,1997.
2. NUREG 1022, Rev 2, Page 54, clarifies that the systems included in the scope of criteria for 50.73(a)(2)(v) are those systems, required by the TS to be operable to perform one of the four functions specified in the rule. As noted in item 1, the cross over steam dump system is not in the TS.
3. A review of the accident analysis in FSAR Section 14.1.12 established that there is no mention of the cross over steam dump system for mitigation of this accident.
Therefore, the Licensee is retracting this event.
The NRC Resident Inspector was notified.
The Reg 3 RDO(Clayton was notified)
"While performing troubleshooting operation on the Unit 1 Crossover Steam Dump System an Instrument Air Valve was discovered to be closed, when it should have been open. This closed valve (IA-1553) isolates Instrument Air to the Crossover Steam Dump Valves rendering the system inoperable. This system is required to be operable by the FSAR Appendix T and Power must be <437 MWe if the system is inop. At the time of discovery power was <437 MWe, however initial investigation leads to the conclusion that this valve has probably been closed since October, 2000. Since Crossover Steam Dumps provide protection for a Turbine Overspeed Accident and is part of the PBNP Design Basis it was conservatively decided to make this 8-hour report. Unit 1 will remain < 437 MWe until the system is fully restored and tested. An investigation is continuing."
The licensee notified the NRC Resident Inspector.
* * * UPDATE ON 2/9/01 @ 1630 BY ADAMS TO GOULD * * * RETRACTION
This event reported that the cross over steam dump system was discovered to be inoperable because of a mis-positioned instrument air valve. This was reported as a condition that could have prevented fulfillment of a safety function for a SSC [structure, system, and component] needed to mitigate the consequences of an accident. Upon closer evaluation of the condition and examination of the applicable licensing bases, they have determined that this condition is not reportable for the following reasons:
1. The cross over steam dump system is not a TS controlled system. The turbine overspeed protection system TS LCOs and surveillances were removed from the TS by License Amendments 176 and 180 on August 6,1997.
2. NUREG 1022, Rev 2, Page 54, clarifies that the systems included in the scope of criteria for 50.73(a)(2)(v) are those systems, required by the TS to be operable to perform one of the four functions specified in the rule. As noted in item 1, the cross over steam dump system is not in the TS.
3. A review of the accident analysis in FSAR Section 14.1.12 established that there is no mention of the cross over steam dump system for mitigation of this accident.
Therefore, the Licensee is retracting this event.
The NRC Resident Inspector was notified.
The Reg 3 RDO(Clayton was notified)