| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/07/2011 - 02/08/2011 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 46586 | Rep Org: ARIZONA RADIATION REGULATORY AGENCY
Licensee: YUMA CARDIOLOGIST ASSOCIATES
Region: 4
City: YUMA State: AZ
County:
License #: 14-029
Agreement: Y
Docket:
NRC Notified By: AUBREY V. GOODWIN
HQ OPS Officer: JOHN KNOKE | Notification Date: 02/02/2011
Notification Time: 15:47 [ET]
Event Date: 12/23/2010
Event Time: [MST]
Last Update Date: 02/04/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
LINDA HOWELL (R4DO)
JACK FOSTER (FSME)
| Event Text AGREEMENT STATE REPORT INVOLVING AN UNPLANNED FETAL EXPOSURE
This information was provided by the state via email:
"On 12/23/10, the patient was administered the radiopharmaceutical for a nuclear stress test. Notices were posted in English and Spanish to [advise the patient to] inform the staff if you [the patient] think you are or could be pregnant. The patient was scheduled to return for the resting portion of the study on 12/28/2010. At this time, the patient and the husband raised the possibility of the patient being pregnant. The resting test was canceled and a pregnancy test performed which was positive.
"The Agency continues to investigate the actions of the licensee and timeliness of reporting of this event. The U.S. NRC and the Arizona Governor's office have been notified of this event. Press coverage is not anticipated.
"Source: Tc99m; Activity: 30 milliCuries"
Arizona First Notice: 11-001
* * UPDATE FROM AUBREY GODWIN TO DONG PARK AT 1046 EST ON 2/4/11 * * *
This information was provided by the State via email:
"Doses: The licensee estimates the fetus exposure is 1,300 mRem.
"Corrective Actions: The licensee now requires a signed statement on pregnancy."
Notified FSME EO (Villamar) and R4DO (Howell). |
| Agreement State | Event Number: 46587 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: CHEVRON PHILLIPS CHEMICAL COMPANY LP
Region: 4
City: ORANGE State: TX
County:
License #: 00031
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: JOHN KNOKE | Notification Date: 02/02/2011
Notification Time: 16:07 [ET]
Event Date: 02/01/2011
Event Time: [CST]
Last Update Date: 02/02/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
LINDA HOWELL (R4DO)
JACK FOSTER (FSME)
| Event Text AGREEMENT STATE REPORT - STUCK SHUTTER ON GAUGE
This information was provided by the state via email:
"On February 2, 2011, the Agency [State of Texas] was notified by the licensee that the shutter on a Ronan model SA1-F37 nuclear gauge was stuck in the open position. The gauge contained an original activity of 100 milliCuries of Cesium (Cs) - 137. The gauge is mounted on a vessel 100 feet above the ground and does not pose an exposure risk.
"The licensee has contacted the manufacturer and expects the gauge to be repaired in the next few days. Additional information will be supplied in accordance with SA-300."
Texas Incident Number: I-8817 |
| Non-Agreement State | Event Number: 46596 | Rep Org: LUZENAC AMERICA INC
Licensee: LUZENAC AMERICA INC
Region: 4
City: THREE FORKS State: MT
County:
License #: GL 1424-1611
Agreement: N
Docket:
NRC Notified By: RON HYATTE
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/07/2011
Notification Time: 13:00 [ET]
Event Date: 02/07/2011
Event Time: 10:45 [MST]
Last Update Date: 02/07/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
JEFF CLARK (R4DO)
GLENDA VILLAMAR (FSME)
CANADA VIA EMAIL ()
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text SEVEN TRITIUM EXIT SIGNS LOST
Luzenac America Inc. purchased their property from Cypress Minerals Corporation in February 1988. Seven Tritium exit signs were included in the transfer. However, these exit signs were not inventoried nor were their locations documented. These signs cannot be located and have been declared missing.
Sign Manufacturer: Self Powered Lighting
Model: 710
Activity: 25 Ci each at the time of manufacture
THIS MATERIAL EVENT CONTAINS A "LESS THAN CAT 3" LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
This source is not amongst those sources or devices identified by the IAEA Code of Conduct for the Safety & Security of Radioactive Sources to be of concern from a radiological standpoint. Therefore is it being categorized as a less than Category 3 source |
| Power Reactor | Event Number: 46597 | Facility: CALLAWAY
Region: 4 State: MO
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: KIETH DUNCAN
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/07/2011
Notification Time: 17:18 [ET]
Event Date: 02/07/2011
Event Time: 09:18 [CST]
Last Update Date: 02/07/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
| Person (Organization):
JEFF CLARK (R4DO)
|
| 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 HIGH ENERGY LINE BREAK ANALYSIS FOR AUX STEAM TO THE AUXILIARY BUILDING
"On December 15, 2009, Callaway Plant reported a condition in which valve FBV0146, an isolation valve on an auxiliary steam line in the Auxiliary Building, was found to be kept normally open. With FBV0146 open, the auxiliary steam line downstream of FBV0146 must be considered a high energy line. This configuration was not consistent with the analysis of record for High Energy Line Break (HELB) events. Valve FBV0146 was closed upon discovery of the condition.
"This condition was reported under EN # 45571 as an unanalyzed condition that significantly degrades plant safety. EN #45571 was then retracted on January 21, 2010 when analysis showed that no safety-related components would be rendered inoperable in a postulated HELB event due to the condition. Based on this analysis, FBV0146 was reopened.
"Subsequent review of this condition now shows that, with FCV0146 open, a harsh environment from a postulated HELB downstream of FBV0146 could be transmitted to other areas of the Auxiliary Building. This would occur via a flow path through door gaps and an Auxiliary Building elevator shaft. This flow path had not been considered by the previous analysis.
"The areas that could be affected by a postulated line break contain safe shutdown equipment (such as equipment for the Component Cooling Water system) that is not assumed to experience harsh conditions. Because of the potential impact on this equipment, this condition is considered to have met the criteria for reporting under 10 CFR 50.72(b)(3)(ii)(B).
"FBV0146 is now closed.
"This review was performed as part of the ongoing evaluation of HELB Program deficiencies described in Callaway Plant License Event Report (LER) 2010-009-00.
"The NRC Resident Inspector has been notified."
The auxiliary steam line in the Auxiliary Building feeds non-safety related components. |
| Part 21 | Event Number: 46598 | Rep Org: FAIRBANKS MORSE
Licensee: FAIRBANKS MORSE
Region: 3
City: BELOIT State: WI
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DOMINIC DEDOLPH
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/07/2011
Notification Time: 17:50 [ET]
Event Date: 02/07/2011
Event Time: [CST]
Last Update Date: 02/07/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21 - UNSPECIFIED PARAGRAPH
| Person (Organization):
ERIC DUNCAN (R3DO)
RONALD BELLAMY (R1DO)
PART 21 GROUP ()
| Event Text POTENTIAL EMERGENCY DIESEL GENERATOR BEARING FAILURES
The following information was received via e-mail:
"Linear indications (hot tears) were observed on one main bearing by the FM [Fairbanks Morse] production inspector. The indications were only on one edge of the bearing. The indications went across the entire edge and extended about 1 inch deep into the bearing, being visible on the outside diameter and the inside diameter for about 1 inch. Subsequent 100% liquid penetrant inspection (PT) of all finished bearings in stock has found linear indications on 13 of 454 bearings (3% reject rate) made from permanent mold castings.
"No bearing failures in engines have been linked to linear indications. The root cause of the problem occurs during the casting of the aluminum material in the permanent mold. The linear indications occur only on one edge of the casting, which has been identified as the bottom of the casting. During the cooling and solidification of the molten material poured into the permanent mold tool, the material shrinks and must be continuously replenished with molten material from the top of the casting. If the top of the casting solidifies before the bottom, there is no additional molten material available from the top to feed the bottom as it cools and shrinks, resulting in tears (hot tears) to the material on the bottom of the casting. It is suspected these hot tears are occurring due to improper cooling of the mold tool core. Because there are no cooling passages within the solid mold tool core, the core becomes progressively hotter throughout the production run until the core reaches a temperature hot enough to cause the hot tears."
Affected plants are: Limerick, Peach Bottom and Prairie Island. |
| Power Reactor | Event Number: 46599 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [2] [ ]
RX Type: [1] CE,[2] CE
NRC Notified By: LOURDES PORRO
HQ OPS Officer: DONALD NORWOOD | Notification Date: 02/07/2011
Notification Time: 22:35 [ET]
Event Date: 02/07/2011
Event Time: 22:25 [EST]
Last Update Date: 02/08/2011 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
GEORGE HOPPER (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 | N | 0 | Refueling | 0 | Refueling | Event Text CONTROL ROOM EMERGENCY VENTILATION SYSTEM OUT OF SERVICE DUE TO PLANNED MAINTENANCE
"On February 07, 2011 at 2225 EST, the Control Room Emergency Ventilation system on St. Lucie Unit 1 was declared out of service due to pre-planned maintenance to upgrade the Emergency Response Data Acquisition and Display System. This maintenance renders the control room envelope out of service for a portion of the maintenance. The Technical Support Center (TSC) ventilation system is part of the Unit 1 Control Room Emergency Ventilation system, therefore, the TSC ventilation system has been rendered non-functional during the course of work activities. The TSC ventilation is expected to be returned to service in 4 hours.
"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures. Should the TSC become uninhabitable, the TSC staff will relocate to an alternate TSC location in accordance with applicable site procedures.
"This notification is being made in accordance with 10CFR50.72(b)(3)(xiii) due to the potential loss of an Emergency Response Facility (ERF). An update will be provided once the TSC ventilation system has been restored to normal operation. The NRC Resident Inspector has been notified."
* * * UPDATE FROM LOURDES PORRO TO DONG PARK AT 0040 EST ON 2/7/11* * *
"[As of 0013 EST, the] Control Room and TSC ventilation system has been restored to normal operation."
The licensee will notify the NRC Resident Inspector. | |