Event Notification Report for September 21, 2010
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/20/2010 - 09/21/2010
General Information or Other
Event Number: 46267
Rep Org: IOWA DEPARTMENT OF PUBLIC HEALTH
Licensee: MID-AMERICA LOUISA GEN STATION
Region: 3
City: MUSCATINE State: IA
County:
License #: 0040-1-70-FG
Agreement: Y
Docket:
NRC Notified By: MELANIE RASMUSSEN
HQ OPS Officer: DONALD NORWOOD
Licensee: MID-AMERICA LOUISA GEN STATION
Region: 3
City: MUSCATINE State: IA
County:
License #: 0040-1-70-FG
Agreement: Y
Docket:
NRC Notified By: MELANIE RASMUSSEN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 09/22/2010
Notification Time: 13:26 [ET]
Event Date: 09/21/2010
Event Time: 17:30 [CDT]
Last Update Date: 09/22/2010
Notification Time: 13:26 [ET]
Event Date: 09/21/2010
Event Time: 17:30 [CDT]
Last Update Date: 09/22/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
RICHARD SKOKOWSKI (R3DO)
ANGELA MCINTOSH (FSME)
RICHARD SKOKOWSKI (R3DO)
ANGELA MCINTOSH (FSME)
AGREEMENT STATE REPORT - DAMAGED FIXED GAUGE
The State of Iowa was notified by Louisa Generating Station, a coal-fired electrical generating plant, that a fixed gauge source had been damaged.
"The facility has two 50 mCi Cs-137 sources attached to coal crushers. The gauges are used as low level alarm detection devices and detect whether or not coal is in the hopper at any given time. At approximately 5:30 p.m. on 9.21.10 there was a machine failure. [The licensee] suspects that as a result of the failure there was vibrational damage to one of the gauges (manufactured by Texas Nuclear, housing model 5192, serial number B2724). The gauge was visibly damaged but has not resulted in elevated rad levels. No employees were exposed as a result of this event. The gauges are mounted 15 ft from the floor in a building that is not occupied by staff. The machine (coal crusher) remains out of service since the time of failure on 9.21.10.
"Again, [the licensee] reports no source damage. Their calibrated instrument reads 0.5-1.0 mrem 1 ft from the source, 0.2-0.3 mrem at 2 ft and 0.1 mrem at 3 ft from the source.
"A technician out of Illinois is scheduled to arrive at the facility on Tuesday, September 28th for further testing and possible repair."
The gauge is located in a contained building. The shutter is normally open and the suspected vibration damage resulted in being unable to close the shutter.
The State of Iowa was notified by Louisa Generating Station, a coal-fired electrical generating plant, that a fixed gauge source had been damaged.
"The facility has two 50 mCi Cs-137 sources attached to coal crushers. The gauges are used as low level alarm detection devices and detect whether or not coal is in the hopper at any given time. At approximately 5:30 p.m. on 9.21.10 there was a machine failure. [The licensee] suspects that as a result of the failure there was vibrational damage to one of the gauges (manufactured by Texas Nuclear, housing model 5192, serial number B2724). The gauge was visibly damaged but has not resulted in elevated rad levels. No employees were exposed as a result of this event. The gauges are mounted 15 ft from the floor in a building that is not occupied by staff. The machine (coal crusher) remains out of service since the time of failure on 9.21.10.
"Again, [the licensee] reports no source damage. Their calibrated instrument reads 0.5-1.0 mrem 1 ft from the source, 0.2-0.3 mrem at 2 ft and 0.1 mrem at 3 ft from the source.
"A technician out of Illinois is scheduled to arrive at the facility on Tuesday, September 28th for further testing and possible repair."
The gauge is located in a contained building. The shutter is normally open and the suspected vibration damage resulted in being unable to close the shutter.
Power Reactor
Event Number: 46265
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: ROGER MONTGOMERY
HQ OPS Officer: VINCE KLCO
Region: 2 State: FL
Unit: [] [4] []
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: ROGER MONTGOMERY
HQ OPS Officer: VINCE KLCO
Notification Date: 09/21/2010
Notification Time: 22:28 [ET]
Event Date: 09/21/2010
Event Time: 20:17 [EDT]
Last Update Date: 09/21/2010
Notification Time: 22:28 [ET]
Event Date: 09/21/2010
Event Time: 20:17 [EDT]
Last Update Date: 09/21/2010
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
GEORGE HOPPER (R2DO)
GEORGE HOPPER (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 4 | A/R | Y | 100 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP
"At 2017 [EDT] on 9/21/10, Turkey Point Unit 4 spuriously tripped. The cause of the reactor trip is currently under investigation.
"At the time of the trip, reactor power was 100%. Auxiliary feedwater [AFW] was automatically initiated when steam generator levels lowered below the actuation setpoint. Steam generator levels are now stable at their normal Mode 3 band and auxiliary feedwater is secured.
"Unit 4 has been stabilized in Mode 3 on normal off-site power.
"This event is reportable per 10 CFR 50.72(b)(2)(iv)(B) - actuation of the reactor protection system with the reactor critical and 10 CFR 50.72(b)(3)(iv)(A) - valid actuation of an ESF system (AFW)."
All control rods inserted into the core. Decay heat is being removed through the steam dumps to atmosphere. There was no activation of PORVs or SRVs. The reactor is at shutdown NOP and NOT. The reactor trip response was uncomplicated and there was no impact on Unit 3.
The licensee notified the NRC Resident Inspector.
"At 2017 [EDT] on 9/21/10, Turkey Point Unit 4 spuriously tripped. The cause of the reactor trip is currently under investigation.
"At the time of the trip, reactor power was 100%. Auxiliary feedwater [AFW] was automatically initiated when steam generator levels lowered below the actuation setpoint. Steam generator levels are now stable at their normal Mode 3 band and auxiliary feedwater is secured.
"Unit 4 has been stabilized in Mode 3 on normal off-site power.
"This event is reportable per 10 CFR 50.72(b)(2)(iv)(B) - actuation of the reactor protection system with the reactor critical and 10 CFR 50.72(b)(3)(iv)(A) - valid actuation of an ESF system (AFW)."
All control rods inserted into the core. Decay heat is being removed through the steam dumps to atmosphere. There was no activation of PORVs or SRVs. The reactor is at shutdown NOP and NOT. The reactor trip response was uncomplicated and there was no impact on Unit 3.
The licensee notified the NRC Resident Inspector.