| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
04/13/2011 - 04/14/2011 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 46748 | Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ED LESSMANN
HQ OPS Officer: BILL HUFFMAN | Notification Date: 04/13/2011
Notification Time: 01:57 [ET]
Event Date: 04/12/2011
Event Time: 22:15 [CDT]
Last Update Date: 04/13/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
GEOFFREY MILLER (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Refueling | 0 | Refueling | Event Text ESF ACTUATION FOLLOWING LOSS OF A SAFEGUARD BUS DURING EDG TESTING
The following event occurred with the unit in a "No Mode" defueled condition.
"On the 12th of April at 2215 CDT Comanche Peak Nuclear Power Plant Unit 2 had a Train B ESF Actuation (Black Out) reportable per 10CFR50.72(b)(3)(iv) for [the 6.9KV Train B] Emergency AC Electrical power systems including Emergency Diesel Generator (EDG).
"At the time of the event, Unit 2 was in 'No Mode' - the core was off loaded and post maintenance testing was being performed on the 2-02 Emergency Diesel Generator. The scope of the EDG testing was to verify proper operation of the EDG when it was the sole supply to the Unit 2 Train B 6.9KV safeguards buses. Unit 2 Train B 6.9 KV buses have 3 AC sources - XST1 (138KV) preferred source, XST2 (345KV) alternate source and the 2-02 Emergency Diesel Generator.
"The 2-02 EDG was started normally and was operating in parallel with XST1 (preferred AC source) just before the event. The event was triggered when the preferred AC supply breaker to the Train B 6.9KV Safeguard bus was opened per plan. The opening of the preferred feeder breaker resulted in the 2-02 EDG being the sole AC source to the Train B 6.9KV bus. Immediately following this breaker operation, the EDG tripped on an Auto Voltage Regulator failure. This caused the Train B 6.9KV safeguard bus to de-energize which resulted in the automatic closure of the alternate AC (XST2) feeder breaker. This in turn triggered the Train B Solid State Sequencer to sequence on Train B Black Out loads - as designed.
"The Train B Black Out Solid State Sequencer operated as designed. No abnormalities were noted. All available equipment operated as designed.
"The 2-02 EDG is currently tagged out and the problem associated with the [Auto Voltage Regulator] failure is being investigated.
"[The] NRC Resident Inspector has been informed and is currently located on site."
No fuel movement was in progress during this event. Train A safeguard power was unaffected and available throughout. Non-safety related power was also not affected. The only operational impact was the loss of a Train B spent fuel pool cooling pump for approximately 10 minutes. The spent fuel pool temperature increased approximately 1/2 degree during before cooling was restored. |
| Fuel Cycle Facility | Event Number: 46749 | Facility: GLOBAL NUCLEAR FUEL - AMERICAS
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
LEU FABRICATION
LWR COMMERICAL FUEL
Region: 2
City: WILMINGTON State: NC
County: NEW HANOVER
License #: SNM-1097
Agreement: Y
Docket: 07001113
NRC Notified By: PHILLIP OLLIS
HQ OPS Officer: BILL HUFFMAN | Notification Date: 04/13/2011
Notification Time: 09:29 [ET]
Event Date: 04/13/2011
Event Time: 08:30 [EDT]
Last Update Date: 04/13/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(3) - ACUTE CHEMICAL EXPOSURE
| Person (Organization):
KATHLEEN O'DONOHUE (R2DO)
KING STABLEIN (NMSS)
| Event Text ACUTE CHEMICAL EXPOSURE FROM HYDROGEN FLUORIDE TO A MAINTENANCE WORKER
"A maintenance employee was involved in a pipe replacement project in the Hydrogen Fluoride (HF) Building. The employee was leaning on a pipe and received a HF exposure through his PPE [personal protective equipment and clothing] onto his abdomen. The employee was immediately placed under a safety shower and an on-site emergency response was initiated. EMT's applied calcium gluconate and the employee was transported to on-site medical clinic. The employee was not contaminated with any radioactive material. The employee was later transferred to off-site medical. The employee's abdomen was reddened and had some blistering, but exposure is not considered life threatening.
"AII work in the HF building has been stopped pending the completion of an investigation."
The licensee stated that the pipe had been flushed with water and steam prior to starting the maintenance evolution. The amount of fluid in the pipe was described as residual. There was no ongoing release of HF and no other employees were involved. The licensee is providing this as a notification under 10CFR70 App A (a) and 10CFR70.61(b)(4).
The licensee plans to notify the NRC Regional Staff (Thomas).
* * * UPDATE FROM PHILLIP OLIIS VIA FAX TO JOHN KNOKE AT 1226 EST ON 4/13/11 * * *
"The employee was released from the hospital with no restrictions. As such, the event classification is being amended to 10 CFR 70.61(c)(4)."
Notified NMSS (King Stablein), R2DO (Kathleen O'Donohue) |
| Power Reactor | Event Number: 46751 | Facility: NORTH ANNA
Region: 2 State: VA
Unit: [1] [2] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DON TAYLOR
HQ OPS Officer: JOHN KNOKE | Notification Date: 04/13/2011
Notification Time: 16:15 [ET]
Event Date: 04/14/2011
Event Time: 04:00 [EDT]
Last Update Date: 04/13/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
KATHLEEN O'DONOHUE (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 | 100 | Power Operation | 100 | Power Operation | Event Text TECHNICAL SUPPORT CENTER VENTILATION SYSTEM OUT OF SERVICE FOR MAINTENANCE
"This is a voluntary notification for planned maintenance that affects the TSC ventilation system.
"At approximately 0400 EDT an April 14, 2011 the North Anna TSC [Technical Support Center] air conditioning and filtration systems will be rendered non-functional to perform preventive maintenance on electrical buses supplying power. This condition has the potential to render the TSC unavailable due to the inability of the ventilation and filtration system to maintain a habitable atmosphere. Temporary ventilation is being established for the TSC computer room. The maintenance is expected to last less than 24 hours. Compensatory measures exist to relocate the TSC to alternate locations, if needed.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 46752 | Facility: VOGTLE
Region: 2 State: GA
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MATTHEW NORRIS
HQ OPS Officer: JOE O'HARA | Notification Date: 04/13/2011
Notification Time: 17:10 [ET]
Event Date: 04/13/2011
Event Time: 09:32 [EDT]
Last Update Date: 04/13/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
KATHLEEN O'DONOHUE (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 | 100 | Power Operation | 100 | Power Operation | Event Text FITNESS FOR DUTY REPORT INVOLVING A NON-LICENSED EMPLOYEE
A non-licensed employee had a confirmed positive for alcohol during a for-cause fitness-for-duty test. The employee's unescorted access has been terminated. Contact the Headquarters Operations Officer for additional details.
The licensee will notify the NRC Resident Inspector. | |