| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/13/2009 - 02/17/2009 ** EVENT NUMBERS ** |
 | General Information or Other | Event Number: 44847 | Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: NUCOR STEEL COMPANY
Region: 4
City: ARMOREL State: AR
County:
License #: ARK-078603120
Agreement: Y
Docket:
NRC Notified By: KATIA GRAY
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/12/2009
Notification Time: 11:41 [ET]
Event Date: 01/20/2009
Event Time: [CST]
Last Update Date: 02/12/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GEOFFREY MILLER (R4)
ANGELA McINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - SOURCE SHUTTER STUCK OPEN
The following report was received from the state via e-mail:
"Nucor Steel Company informed the [Arkansas] Department [of Health] that they had a stuck shutter on one of their caster sources. The licensee utilized a lifting mechanism that allowed the technicians to lift and move the source without being near the source. The source and source holder were placed in an appropriate container and surveys were performed. The highest reading on the storage container with the shutter open at contact was 120 MicroR/hour.
"The storage container was relocated to a remote area on the casting deck and surveys were performed. A source service provider was contacted and arrived on site the next day to evaluate the problem.
"Source: Berthold Model LB 300 MLT, Serial number 730-4-97, 36 mCi of Co-60 used for mold level control.
"On 02/12/2009, at 10:01 AM the licensee provided the Department with a more detailed description of the steps taken by the technicians during the event, storage of the source, exposure reading at the source, and security of the source at this time. The licensee is currently awaiting feedback from the gauge service provider.
"The Department will leave this report open pending receipt of a final written report from the licensee, due in 30 days."
Arkansas Report: 09-02-01 |
| Power Reactor | Event Number: 44851 | Facility: FT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: SHANNON SHEA
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/13/2009
Notification Time: 17:00 [ET]
Event Date: 02/13/2009
Event Time: 15:26 [CST]
Last Update Date: 02/13/2009 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
GEOFFREY MILLER (R4)
ELMO COLLINS (R4)
ERIC LEEDS (NRR)
TONY McMURTRAY (IRD)
MARYANNE DOYLE (DHS)
DENNIS VIA (FEMA)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text UNUSUAL EVENT - ENGINEERING ANALYSIS REQUIRES TECHNICAL SPECIFICATION SHUTDOWN
"On February 13, 2009 at 1526 CST, Fort Calhoun Station declared a Notification of Unusual Event [NOUE] based upon EAL 4.2 - Both Diesel Generators NOT Operable. The station has entered Technical Specification 2.0.1(1) requiring the Unit to be placed in at least HOT SHUTDOWN within 6 hours.
"The cause of the NOUE is a potential common mode failure of the diesel generators. Design Engineering has identified an unanalyzed condition in which a High Energy Line Break in Room 81, Main Steam Lines Containment Penetration Room, or an auxiliary steam leak in Room 82, Turbine Building Ventilation Room, can potentially result in water entering both diesel generator rooms through the floor of Room 82 located directly above the diesel rooms, Rooms 63 and 64. This condition presents a potential common mode failure of the diesel generators due to loss of diesel generator auxiliaries from a single failure. The possibility of water leaking into Rooms 63, 64 and the Switchgear rooms prompted this declaration."
Compensatory measures to exit the NOUE will be to remove auxiliary steam from room 82 and blockading shut the door between rooms 81 and 82. These actions are expected to be completed within one to three hours.
The licensee notified the NRC Resident Inspector.
* * * UPDATE AT 1928 ON 2/13/2009 FROM SCOTT EIDEM TO MARK ABRAMOVITZ * * *
At 1828 CST, Fort Calhoun Station exited the Notification of Unusual Event. Both Diesel Generators were declared operable based upon establishing compensatory measures. Diesel 2 was confirmed operable by running in accordance with approved procedures. Diesel 1 was successfully run on February 11, 2009 per a monthly surveillance tests. No additional water intrusion had occurred into the diesel 1 room since completion of the surveillance test. Compensatory measures to prevent water intrusion into Room 82 include isolating auxiliary steam to room 82 to eliminate a source of water to room 82, installing a temporary barrier at the door between rooms 81 and 82 to prevent water from flowing from room 81 to room 82, should an HELB occur in room 81, and to open the door between room 81 and the turbine building to allow water to flow out of room 81 so as not to flow into room 82. Technical Specification 2.0.1 has been exited as of time 1828 CST."
The licensee will notify the NRC Resident Inspector.
Notified the R4DO (Miller), IRD (McDermott, McMurtray), DHS (Doyle), and FEMA (Via). |
| Power Reactor | Event Number: 44852 | Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] B&W-L-LP
NRC Notified By: RICKY RAWLS
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/13/2009
Notification Time: 18:26 [ET]
Event Date: 02/13/2009
Event Time: 12:02 [EST]
Last Update Date: 02/13/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
JONATHAN BARTLEY (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text FITNESS FOR DUTY
A non-licensed employee supervisor had a confirmed positive for illegal drugs during a follow-up fitness-for-duty test. The employee's access to the plant has been terminated. Contact the Headquarters Operations Officer for additional details. |
| Power Reactor | Event Number: 44854 | Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: JOE BENNETT
HQ OPS Officer: JASON KOZAL | Notification Date: 02/16/2009
Notification Time: 09:45 [ET]
Event Date: 02/16/2009
Event Time: 05:13 [CST]
Last Update Date: 02/16/2009 | 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):
JONATHAN BARTLEY (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM DUE TO LOSS OF STATOR COOLING WATER
"At 0513 on 2/16/09, the Unit 2 reactor was manually scrammed in accordance with alarm response procedure 2-ARP-9-8A 'TURBINE TRIP TIMER INITIATED'. Other associated alarms and indications both locally and in the Main Control Room indicated a failure of the stator cooling water system. The exact cause of the failure is still being investigated.
"All systems responded as expected to the insertion of the manual scram. No ECCS injection was initiated or required, and all expected containment isolation and initiation signals were received.
"This event is reportable within 4 hours per 10CFR 50.72(b)(2)(iv)(B) 'any event or condition that results in actuation of the reactor protection system (RPS) when the reactor is critical except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation'. It is also reportable within 8 hours per 10CFR 50.72(b)(3)(iv)(A) and requires an LER within 60 days per 10CFR 50.73(a)(2)(iv)(A)."
All rods inserted fully into the reactor. The electrical power system is in a normal shut down configuration. Decay heat removal is through the main condenser via the turbine bypass valves. There is no impact on Units 1 and 3.
The NRC resident inspector has been notified. |
| Power Reactor | Event Number: 44855 | Facility: FARLEY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: BILL ARENS
HQ OPS Officer: PETE SNYDER | Notification Date: 02/16/2009
Notification Time: 22:09 [ET]
Event Date: 02/16/2009
Event Time: 16:55 [CST]
Last Update Date: 02/16/2009 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
JONATHAN BARTLEY (R2)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text INADVERTENT RELAY ACTUATION RESULTS IN AUTO START OF 1C EMERGENCY DIESEL GENERATOR
"No release of radiation has occurred as a result of this event."
"At 1655 CST, the Unit One 'H' 4160V bus phase two differential relay actuated when the relay panel was inadvertently bumped. This resulted in the de-energization and lockout of the 1H 4160V bus and the auto start of the 1C Emergency Diesel Generator [EDG]. Recovery actions have been successful in restoring power to the affected switchgear. All equipment functioned as expected. Normal equipment lineup has been restored. Unit One remained at full power during this event."
The 1C EDG never picked up any loads because of the lockout on the 1H bus. Some loads were lost including an air compressor and some oil pumps but this equipment was either re-started or backups were started within about two hours.
The licensee notified the NRC Resident Inspector. | |