| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/20/2007 - 06/21/2007 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 43427 | Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: NODARSE AND ASSOCIATES
Region: 1
City: WEST PALM BEACH State: FL
County:
License #: 2429-1
Agreement: Y
Docket:
NRC Notified By: STEVE L FURNACE
HQ OPS Officer: STEVE SANDIN | Notification Date: 06/18/2007
Notification Time: 12:17 [ET]
Event Date: 02/18/2007
Event Time: 12:00 [EDT]
Last Update Date: 06/18/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
WILLIAM COOK (R1)
GREG MORELL (FSME)
| Event Text AN AGREEMENT STATE REPORT FROM THE STATE OF FLORIDA - DAMAGED TROXLER GAUGE
This event was called in by the State of Florida Bureau of Radiation Control:
"Troxler Gauge damaged on site February 22, 2007. Company RSO notified this office on June 18, 2007. Back loader drove over gauge and damaged it. Gauge leak tested by Atlantic Drilling and found to be satisfactory."
Incident Location: Fort Lauderdale, Davie Blvd between 31st and 32 streets.
Isotope(s)/Activities: Cs-137 (10 mCi) and Am-241/Be (40 mCi)
State of Florida Incident Number: FL07-100 |
| Power Reactor | Event Number: 43433 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: JIM PETERSON
HQ OPS Officer: JOHN MacKINNON | Notification Date: 06/20/2007
Notification Time: 16:35 [ET]
Event Date: 06/20/2007
Event Time: 13:55 [CDT]
Last Update Date: 06/20/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JAMNES CAMERON (R3)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 1 | Startup | 1 | Startup | Event Text MAJOR LOSS OF EMERGENCY ASSESSMENT CAPABILITY - 13 OF 44 EMERGENCY SIRENS OUT OF SERVICE
"On June 20, 2007, a disturbance on the transmission system was experienced causing a loss of 13 of 44 emergency sirens (approximately 30 percent) for Clinton Power Station. At 1355 hours (CDT), since power was not restored to these sirens within one hour, this event was determined to be a major loss of emergency assessment capability. At 1512 hours, only 6 sirens (14 percent) remain out of service. At this time, an estimated return to service has not been provided for the remaining sirens."
"DeWitt County, Illinois Emergency Management Agency, and the NRC Resident have been informed of this information. " |
| Power Reactor | Event Number: 43435 | Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [ ]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: JOEL BARNETT
HQ OPS Officer: PETE SNYDER | Notification Date: 06/21/2007
Notification Time: 03:24 [ET]
Event Date: 06/20/2007
Event Time: 22:50 [PDT]
Last Update Date: 06/21/2007 | 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
| Person (Organization):
BLAIR SPITZBERG (R4)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 96 | Power Operation | 0 | Hot Standby | Event Text FAILED INSTRUMENT AIR HEADER LEADS TO MANUAL REACTOR TRIP
At 2250 on 6/20/07, "Instrument Air header pressure failed at a brazed joint. The loss of Instrument Air pressure caused the Steam Generator (S/G) Feedwater Regulating Valves to stop controlling and S/G level, E-088, to rise uncontrolled. Control Room Operators tripped the reactor manually. Main Feedwater Pumps were manually tripped to stop excess feedwater to the S/Gs. Loss of Instrument Air failed the normal cooling to Containment. Containment Emergency Cooling units were manually started to provide containment cooling. The standard post trip actions were carried out with all safety functions satisfied." The site is proceeding with post trip recovery. The Instrument Air leak was isolated at 2321 PDT.
All control rods fully inserted on the manual trip. RCPs are in operation transferring decay heat to the S/Gs. Emergency feedwater is feeding the S/Gs with steam being discharged to the condenser via the steam dumps. Atmospheric relief valves were used to discharge steam to the atmosphere initially for approximately 20 minutes following the trip. There are no primary to secondary tube leaks. Containment isolation failed closed as expected following the loss of instrument air pressure to the containment.
Normal offsite power is available and the emergency diesel generators are available if needed.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 43436 | Facility: LIMERICK
Region: 1 State: PA
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: NED DENNIN
HQ OPS Officer: JOE O'HARA | Notification Date: 06/21/2007
Notification Time: 04:05 [ET]
Event Date: 06/21/2007
Event Time: 03:15 [EDT]
Last Update Date: 06/21/2007 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
WILLIAM COOK (R1)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text HPCI INOPERABLE DUE TO QUARTERLY VALVE STROKE TEST FAILURE
"During performance of the quarterly HPCI valve stroke test the HV-55-2F006, HPCI pump discharge isolation valve to Core Spray failed to open within the maximum allowed time. The HV-55-2F006 valve is a motor operated valve and the maximum allowed opening time is 17.25 seconds. The valve was given an open signal via the handswitch as required by the test but did not initially respond. Several minutes later the valve went full open. HPCI was declared inoperable at 0315 on 6/21/2007. Cause for valve stroke time failure is not known at this time."
As a result, the licensee is in a 14 day shutdown LCO.
The licensee notified the NRC Resident Inspector. | |