Event Notification Report for February 09, 2011
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
02/08/2011 - 02/09/2011
Power Reactor
Event Number: 46605
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: JOHN VAN FLEET
HQ OPS Officer: MARK ABRAMOVITZ
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: JOHN VAN FLEET
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 02/09/2011
Notification Time: 19:59 [ET]
Event Date: 02/09/2011
Event Time: 18:04 [CST]
Last Update Date: 02/09/2011
Notification Time: 19:59 [ET]
Event Date: 02/09/2011
Event Time: 18:04 [CST]
Last Update Date: 02/09/2011
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS 50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
ERIC DUNCAN (R3DO)
PATRICK HILAND (NRR)
JEFFERY GRANT (IRD)
ERIC DUNCAN (R3DO)
PATRICK HILAND (NRR)
JEFFERY GRANT (IRD)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 6 | Startup | 0 | Hot Shutdown |
PRESSURE BOUNDARY LEAKAGE
"At 1830 CST on 02/09/11, LaSalle Unit 1 commenced a Technical Specification required plant shutdown, due to identification of pressure boundary leakage. At 1804 CST on 02/09/11, it was identified that 1E51-F076, Reactor Core Isolation Cooling System Steam Supply Inboard Isolation Bypass Warmup Valve, had a one inch crack in a weld on the pressure seal joint. This qualifies as pressure boundary leakage, which requires entry into Tech Spec 3.4.5, RCS Operational Leakage, Required Action C, to be in Mode 3, Hot Shutdown, by 0604 on 02/10/11, and Mode 4, Cold Shutdown, by 0604 on 02/11/11 . At the time of discovery, Unit 1 was in startup mode following a forced outage. A repair plan is being prepared at this time and the Unit will remain in cold shutdown until repairs are complete."
This is an unisolable leak. Reactor pressure is 913 psig.
The licensee notified the NRC Resident Inspector.
"At 1830 CST on 02/09/11, LaSalle Unit 1 commenced a Technical Specification required plant shutdown, due to identification of pressure boundary leakage. At 1804 CST on 02/09/11, it was identified that 1E51-F076, Reactor Core Isolation Cooling System Steam Supply Inboard Isolation Bypass Warmup Valve, had a one inch crack in a weld on the pressure seal joint. This qualifies as pressure boundary leakage, which requires entry into Tech Spec 3.4.5, RCS Operational Leakage, Required Action C, to be in Mode 3, Hot Shutdown, by 0604 on 02/10/11, and Mode 4, Cold Shutdown, by 0604 on 02/11/11 . At the time of discovery, Unit 1 was in startup mode following a forced outage. A repair plan is being prepared at this time and the Unit will remain in cold shutdown until repairs are complete."
This is an unisolable leak. Reactor pressure is 913 psig.
The licensee notified the NRC Resident Inspector.
Agreement State
Event Number: 49254
Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: FLAKEBOARD AMERICA, LLC
Region: 4
City: MALVERN State: AR
County:
License #: ARK-0664-0312
Agreement: Y
Docket:
NRC Notified By: TAMMY KRIESEL
HQ OPS Officer: BILL HUFFMAN
Licensee: FLAKEBOARD AMERICA, LLC
Region: 4
City: MALVERN State: AR
County:
License #: ARK-0664-0312
Agreement: Y
Docket:
NRC Notified By: TAMMY KRIESEL
HQ OPS Officer: BILL HUFFMAN
Notification Date: 08/09/2013
Notification Time: 10:26 [ET]
Event Date: 02/09/2011
Event Time: 00:00 [CDT]
Last Update Date: 08/09/2013
Notification Time: 10:26 [ET]
Event Date: 02/09/2011
Event Time: 00:00 [CDT]
Last Update Date: 08/09/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
10 CFR Section:
Person (Organization):
MICHAEL VASQUEZ (R4DO)
FSME EVENT RESOURCE (E-MA)
MICHAEL VASQUEZ (R4DO)
FSME EVENT RESOURCE (E-MA)
AGREEMENT STATE REPORT - SHUTTER PROBLEM ON A GAMMA GAUGE
The following report was received via e-mail from the State of Arkansas Radiation Control Program:
"During an on-site inspection on August 8, 2013, the licensee stated that a VEGA Americas Corporation model A-2102 gamma gauge shutter was vibrating shut. The source rotor and top plate was replaced on February 9, 2011. The gauge is serial number 6757GK and contains 10 mCi of Cesium-137.
"The licensee indicated the gauge was locked out and unused until it was repaired.
"In accordance with RH-1502.f.2. (10 CFR 30.50(b)(2)) the stuck shutter should have been reported to the State of Arkansas within 24 hours.
"The State of Arkansas is awaiting a written report from the licensee. "
Arkansas Report: ARK-2013-005.
The following report was received via e-mail from the State of Arkansas Radiation Control Program:
"During an on-site inspection on August 8, 2013, the licensee stated that a VEGA Americas Corporation model A-2102 gamma gauge shutter was vibrating shut. The source rotor and top plate was replaced on February 9, 2011. The gauge is serial number 6757GK and contains 10 mCi of Cesium-137.
"The licensee indicated the gauge was locked out and unused until it was repaired.
"In accordance with RH-1502.f.2. (10 CFR 30.50(b)(2)) the stuck shutter should have been reported to the State of Arkansas within 24 hours.
"The State of Arkansas is awaiting a written report from the licensee. "
Arkansas Report: ARK-2013-005.