| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/28/2012 - 02/29/2012 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 47691 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: EQUISTAR CHEMICALS LP
Region: 4
City: PASADENA State: TX
County:
License #: 01854
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: DONALD NORWOOD | Notification Date: 02/23/2012
Notification Time: 08:21 [ET]
Event Date: 02/22/2012
Event Time: [CST]
Last Update Date: 02/23/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RICK DEESE (R4DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - STUCK GAUGE SHUTTER
The following information was received via facsimile:
"On February 22, 2012, the State of Texas was notified by the licensee that the shutter on an Ohmart SH-F1A nuclear gauge containing 50 millicuries of cesium 137 was found stuck in the open position. The gauge shutter was being closed to reduce dose rates in an area where calibration of equipment was to be done. Open is the normal position for the gauge and the gauge does not create any additional exposure risk to any individual. The licensee is making arrangements with the manufacturer for repairs to the gauge. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident #: I-8936 |
| Agreement State | Event Number: 47692 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: QSA GLOBAL
Region: 1
City: BURLINGTON State: MA
County:
License #: 12-8361
Agreement: Y
Docket:
NRC Notified By: JOHN SUMARES
HQ OPS Officer: CHARLES TEAL | Notification Date: 02/23/2012
Notification Time: 08:28 [ET]
Event Date: 01/31/2012
Event Time: [EST]
Last Update Date: 02/23/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MEL GRAY (R1DO)
ANGELA MCINTOSH (FSME)
| Event Text AGREEMENT STATE REPORT - CONTAMINATION LEVELS EXCEED ACTION LEVELS
The following was received from the Commonwealth of Massachusetts via facsimile:
"On Tuesday, 1/31/12, routine contamination surveys discovered approximately 0.5 nCi of Ir-192 outside of the restricted area on the first floor. The calculated dose for an 8-hour exposure to this RAM is 0.7 mrem. The contamination survey results prompted QSA to perform additional surveys to determine the source of contamination. Survey wipes yielded 10,000 to 30,000 dpm over large areas (approximately 2 feet x 2 feet) at different locations.
"Upon investigation, QSA discovered that the exhaust fan on the Ir-192 source production hot cell had been turned 'off.' The exhaust fan was immediately turned back 'on.' About one week earlier, Ir-192 from a supplier was transferred into the hot cell. This operation requires the hot cell exhaust fan to be turned 'off' temporarily. QSA realized that the exhaust fan had not been turned back 'on.'
"Radiation workers who performed hot cell production operations during the time the exhaust fan was 'off' were subjected to whole body counts performed at MIT. The whole body counts indicated workers ingested 12 to 20 nCi of Ir-192 and based on the MIT results, the RSO calculated the committed dose to be less than 2 mrem.
"Since the contamination discovery, QSA has performed cleaning operations on the first and second floors, daily survey monitoring of the first and second floors, and radiation workers performing production operations using the Ir-192 hot cell have worn full protective clothing suits. QSA reports daily surveys results indicate contamination levels have steadily decreased."
Docket No: 14-0067 |
| Fuel Cycle Facility | Event Number: 47705 | 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: SCOTT MURRAY
HQ OPS Officer: CHARLES TEAL | Notification Date: 02/28/2012
Notification Time: 14:19 [ET]
Event Date: 02/27/2012
Event Time: 14:30 [EST]
Last Update Date: 02/28/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(1) - UNANALYZED CONDITION
| Person (Organization):
MARK FRANKE (R2DO)
JAMES RUBENSTONE (NMSS)
| Event Text UNANALYZED PIPING CONFIGURATION DISCOVERED
"During a GNF-A ongoing review of the Fuel Manufacturing Operation (FMO) Integrated Safety Analysis (ISA), facility walk-downs of the process gas piping were performed that identified a configuration that was different than previously analyzed. Based on a review of this as-found condition, it was discovered at 1430 EST February 27, 2012 that the system was different than analyzed in the ISA.
"Production operations in the affected area have been suspended pending an administrative update of the ISA to reflect current conditions. Additional corrective actions and extent of condition are being evaluated. At no time did an unsafe condition exist.
"While this discovery did not result in an unsafe condition, it is being reported pursuant to the reporting requirements of 10CFR70 Appendix A(b)(1) within 24 hours."
The licensee notified the NC Division of Radiation Protection and New Hanover County. |
| Part 21 | Event Number: 47706 | Rep Org: FISHER CONTROLS INTERNATIONAL
Licensee: FISHER CONTROLS INTERNATIONAL
Region: 3
City: MARSHALLTOWN State: IA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BILL FITZGERALD
HQ OPS Officer: CHARLES TEAL | Notification Date: 02/28/2012
Notification Time: 15:21 [ET]
Event Date: 02/24/2012
Event Time: [CST]
Last Update Date: 02/28/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
ANN MARIE STONE (R3DO)
MARK FRANKE (R2DO)
PART 21 GROUP (EMAI)
| Event Text PART 21 REPORT - POTENTIAL MINIMUM WALL VIOLATION ON SEISMIC PLATE VALVE BODIES
"While reviewing Valve Body drawing 16B2201, it was discovered that an area in the packing bore has the possibility to not meet the minimum wall requirements of ASME B16.34 for a Class 150 valve at the minimum material condition due to a potential stack up of tolerances.
"Upon discovery of this possible failure to comply, an investigation was performed on all NPS 3-12 Type A11 Class 150 Seismic Plate Valve Bodies and it was determined that this issue was isolated to the NPS 8 Type A11 Class 150 Seismic Plate Valve Body per drawing 16B2201.
"It is the opinion of Fisher that there is no inherent safety risk associated with this situation. Fisher will be working with the individual plants [Clinton Power Station and Watts Bar] in question to measure the actual dimensions of the bodies to determine if a problem exists and will take appropriate corrective action."
Fisher Information Notice: FIN 2012-01 |
| Power Reactor | Event Number: 47707 | Facility: KEWAUNEE
Region: 3 State: WI
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP
NRC Notified By: JOSEPH STODOLA
HQ OPS Officer: VINCE KLCO | Notification Date: 02/28/2012
Notification Time: 17:59 [ET]
Event Date: 02/28/2012
Event Time: 15:44 [CST]
Last Update Date: 02/28/2012 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
ANN MARIE STONE (R3DO)
|
| 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 UNANALYZED CONDITION RELATED TO CERTAIN POSTULATED FIRE CONDITIONS
"At 1544 CST on February 28. 2012, it was identified that under certain fire conditions, the ability to meet the performance criteria of the approved Fire Protection Program may be challenged. Specifically the cabling within the Dedicated Fire Zone may be affected under certain fire conditions resulting in fire induced spurious operation of valves RC-46 (pressurizer/reactor head vent), PR-33A (pressurizer head vent) and RC-45A (reactor head vent). The ability to maintain pressurizer level within the indicated range may be challenged due to these spurious valve openings during these postulated conditions.
"Contingency actions per the Fire Protection Program to address the fire in the area of concern have been established (hourly fire watch). This condition is reported pursuant to 10CFR50.72 (b)(3)(ii)(B).
"Similar conditions have been previously reported by the licensee in EN #44482 and EN #47686. The compensatory measures that had been put in place for those earlier conditions remain applicable to this current condition."
The licensee notified the NRC Resident Inspector |
| Power Reactor | Event Number: 47708 | Facility: BYRON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CHRIS COTE
HQ OPS Officer: CHARLES TEAL | Notification Date: 02/28/2012
Notification Time: 19:03 [ET]
Event Date: 02/28/2012
Event Time: 17:31 [CST]
Last Update Date: 02/28/2012 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ANN MARIE STONE (R3DO)
SAMSON LEE (NRR)
CYNTHIA PEDERSON (R3RA)
BRUCE BOGER (NRR)
SCOTT MORRIS (IRD)
KEVIN BISCOE (FEMA)
DAN GATES (DHS)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 99 | Power Operation | Event Text UNUSUAL EVENT DUE TO LOSS OF OFFSITE POWER
Byron Unit 1 declared an Unusual Event due to a loss of offsite power for greater than 15 minutes (EAL MU-1). The 1A and 1B emergency diesel generators auto-started and automatically restored power to ESF (Engineered Safety Feature) Busses 141 and 142. The 1A Auxiliary Feedwater pump auto-started due to an undervoltage signal to ESF bus 141. The 6.9 KV Busses (Non-ESF) and 4.16 KV Busses (Non-ESF) auto transferred to the Unit Auxiliary Transformers and Unit 1 remained online. The ESF reserve feed breakers are available and in the process of transferring ESF loads over to Unit 2 via the ESF cross-ties. This will allow shutdown of the 1A and 1B diesel-generators and allow alignment to standby status. Switchyard repairs are being initiated.
The licensee notified the State of Illinois, Ogle County, Oregon and Byron municipalities and the NRC Resident Inspector. The licensee plans on issuing a news release. Unit 2 remained online and was unaffected throughout the event.
Notified Nuclear SSA and NICC vie email. | |