| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/11/2011 - 05/12/2011 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 46826 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: SHELL OIL
Region: 4
City: HOUSTON State: TX
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BOB FREE
HQ OPS Officer: PETE SNYDER | Notification Date: 05/06/2011
Notification Time: 13:05 [ET]
Event Date: 06/15/2010
Event Time: [CDT]
Last Update Date: 05/06/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID PROULX (R4DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - STUCK LEVEL GAUGE SHUTTER
In June 2010, Shell identified a stuck level gauge shutter during scheduled maintenance testing. The licensee removed the gauge from service.
"The licensee intends to leave the gauge secured in storage until an undetermined future date when it is needed. This facility is a research facility and uses the gauge in its research and testing operations."
The gauge was a Berthold Model LB-440 with a 50 milliCurie Cs-137 source.
Texas Report Number: I-8842 |
| Power Reactor | Event Number: 46839 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL SPRINKLE
HQ OPS Officer: JOE O'HARA | Notification Date: 05/11/2011
Notification Time: 01:21 [ET]
Event Date: 05/09/2011
Event Time: 15:18 [EDT]
Last Update Date: 05/11/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
EUGENE GUTHRIE (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text POTENTIAL VALVE MISPOSITIONING LED TO A CONDITION PROHIBITED BY TECHNICAL SPECIFICATIONS
"On May 9, 2011, at 1518 Eastern Daylight Saving Time (EDT), WBN [Watts Bar Nuclear] started a Safety Injection Pump and began to inject into the Reactor Coolant System contrary to Technical Specification Limiting Condition for Operation 3.4.12, which requires in part for Mode 5 that a Cold Overpressure Mitigation System (COMS) shall be OPERABLE with a maximum of one charging pump and no safety injection pump capable of injecting into the RCS and the accumulators isolated.
"The RCS pressure rise was recognized immediately, and the pump was secured within 27 seconds. The pressure reached a maximum of 328 psig. which is below the relief valve setpoint, so no structure, system, or component pressure limit was exceeded at any time. LCO 3.4.12 Condition A was entered immediately. At 1521, the pump breaker was directed to be racked out, and the breaker was reported racked out and verified by 1600, at which time LCO 3.4.12 was exited.
"This event was determined to be reportable as a condition prohibited by Technical Specifications in accordance with 10 CFR 50.73(a) (2)(i)(b). This notification is made in accordance with Watts Bar License condition 2.G.
"The NRC Resident Inspector has been notified of this event and event notification."
The licensee is investigating the likelihood of a valve mispositioning. |
| Power Reactor | Event Number: 46840 | Facility: CATAWBA
Region: 2 State: SC
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: STAN SINCLAIR
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/11/2011
Notification Time: 07:30 [ET]
Event Date: 05/11/2011
Event Time: 02:01 [EDT]
Last Update Date: 05/11/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
EUGENE GUTHRIE (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF >25% OF EMERGENCY NOTIFICATION SYSTEM SIRENS DUE TO ADVERSE WEATHER
"Greater than 25% of the Catawba offsite Alert and Notification Sirens are unavailable due to severe thunderstorm related power outages in the area. As of approximately 0200 EDT, 40 of 89 sirens were unavailable. Power restoration efforts in the area are underway."
As of 0730 EDT, 27 of the 89 sirens remain out of service.
The licensee notified the State of North Carolina including Mecklenburg and Gaston Counties, and the State of South Carolina including York County. They also will be notifying the NRC Resident Inspector. |
| Power Reactor | Event Number: 46841 | Facility: HATCH
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: KENNY HUNTER
HQ OPS Officer: VINCE KLCO | Notification Date: 05/11/2011
Notification Time: 15:50 [ET]
Event Date: 05/11/2011
Event Time: 09:00 [EDT]
Last Update Date: 05/11/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
EUGENE GUTHRIE (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | | 2 | N | Y | 55 | Power Operation | 55 | Power Operation | Event Text TECHNICAL SUPPORT CENTER OUT OF SERVICE DUE TO VENTILATION ROLL FILTER MAINTENANCE
"During an Emergency Preparedness drill on May 11, 2011 the Hatch Nuclear Plant's Technical Support Center (TSC) HVAC [Heating, Ventilation and Air-Conditioning] system's Roll Filter Indicating Light on the 1X75B001 TSC Air Handling Unit was illuminated. The ARP [Alarm Response Procedure] response actions in the 73EP-EIP-016-0 indicated that the roll filter needed to be replaced. Reference [Hatch] Condition Report 2011106603.
"The TSC HVAC is being considered non-functional during the performance of this corrective work activity. If an emergency condition occurs during the time these work activities are being performed, which requires activation of the TSC, the contingency plan calls for utilization of the TSC, as long as radiological conditions allow for habitability of the facility. Procedure 73EP-EIP-063-0, Technical Support Center Activation, provides instructions to direct TSC management to the Control Room and TSC support personnel to the Simulator Building to continue TSC activities if it is necessary to relocate from the primary TSC so that TSC functions can be continued.
"This event is reportable per 10CFR50.72 (b)(3)(xiii) as described In NUREG-1022, Rev. 1 since this activity affects the functionality of the TSC emergency response facility for the duration of the evolution."
The licensee notified the NRC Resident Inspector. | |