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U.S. Nuclear Regulatory Commission
Operations Center
Event Reports For
02/21/2007 - 02/22/2007
** EVENT NUMBERS **
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| General Information or Other |
Event Number: 43170 |
Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: MATERIALS TESTING OF ARKANSAS
Region: 4
City: LITTLE ROCK State: AR
County:
License #: ARK-859
Agreement: Y
Docket:
NRC Notified By: BERNIE BEVILL
HQ OPS Officer: JOE O'HARA |
Notification Date: 02/19/2007
Notification Time: 08:56 [ET]
Event Date: 02/19/2007
Event Time: [CST]
Last Update Date: 02/19/2007 |
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE |
Person (Organization):
ANTHONY GODY (R4)
SCOTT MOORE (FSME)
R. WARREN ILTAB () |
| This material event contains a "Less than Cat 3" level of radioactive material. |
Event Text
AGREEMENT STATE REPORT INVOLVING STOLEN TROXLER MOISTURE DENSITY GAUGE MODEL 3440
The Arkansas Department of Health reported that one of their licensees, Materials Testing of Arkansas, had a Troxler moisture density gauge stolen from a pickup truck in front of a Wal-Mart in Little Rock, Arkansas between 6:00 a.m. and 6:30 a.m. CST. When the licensee returned to the vehicle, he found that the chain securing the gauge had been cut, and the Troxler and some other personal equipment had been stolen from the back of the vehicle. The Troxler is a Model 3440 S/N 19914 and contains 9 milli Curies of Cs-137 and 44 milli Curies of Am-241. The Little Rock Police Department is investigating the theft under case number 07-18990.
The Arkansas Department of Health is preparing a press release on this event.
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.
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: 43172 |
Facility: DUANE ARNOLD
Region: 3 State: IA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: ELLIS VANN
HQ OPS Officer: JEFF ROTTON |
Notification Date: 02/19/2007
Notification Time: 15:34 [ET]
Event Date: 02/19/2007
Event Time: [CST]
Last Update Date: 02/21/2007 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION |
Person (Organization):
MARK RING (R3) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 1 |
N |
N |
0 |
Refueling |
0 |
Refueling |
Event Text
DEGRADED CONDITION - 30% THROUGH WALL INDICATION ON REACTOR RECIRC NOZZLE
"Information from a Phased Array UT examination of RRF-F002 (Reactor Recirc 'F' Nozzle to Safe-end weld) indicates that a linear indication approximately 7" long (centered at the bottom of the weld) and approximately 30% through wall extent (ID connected) exists. The Phased Array UT examination of RRF-F002 (Reactor Recirc 'F' Nozzle to Safe-end weld) was performed as part of scheduled outage activities.
"TRM LCO 3.7.3 for Structural Integrity, Condition B has been entered for the Recirc nozzle/piping.
"This event is reportable under § 50.72(b)(3)(ii), 'Any event or condition that results in: (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded', when there are welding or material defects in the primary coolant system which cannot be found acceptable under ASME Section XI, IWB-3600, 'Analytical Evaluation of Flaws' or ASME Section XI, Table IWB-3410-1, 'Acceptance Standards.'"
The licensee informed the NRC Resident Inspector.
* * * UPDATE PROVIDED BY HANS OLSON TO JEFF ROTTON AT 2315 EST ON 02/21/07 * * *
"Information from a Phased Array UT examination of RRC-F002 (Reactor Recirc 'C' Nozzle to Safe-end weld) indicates that a linear indication approximately 10" long and approximately 82% through wall extent (Inner Diameter connected) exists. The Phased Array UT examination of RRC-F002 (Reactor Recirc 'C' Nozzle to Safe-end weld) was performed as part of a follow-up activity for an extent of condition evaluation on RRF-F002 (Reactor Recirc 'F' Nozzle to Safe-end weld).
"TRM LCO 3.7.3 for Structural Integrity, Condition B has been entered for the Recirc nozzle/piping."
Corrected error in original report due to event entry error that identified the affected nozzle as RRF-17002 vice the correct identification of RRF-F002
The licensee notified the NRC Resident Inspector. Notified R3DO (Burgess) |
| Other Nuclear Material |
Event Number: 43176 |
Rep Org: ENVIRONMENTAL PROTECTION AGENCY
Licensee: ENVIRONMENTAL PROTECTION AGENCY
Region: 1
City: EDISON State: NJ
County:
License #:
Agreement: N
Docket:
NRC Notified By: RODNEY DORWIN
HQ OPS Officer: STEVE SANDIN |
Notification Date: 02/20/2007
Notification Time: 17:30 [ET]
Event Date: 12/18/2006
Event Time: [EST]
Last Update Date: 02/21/2007 |
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X |
Person (Organization):
TODD JACKSON (R1)
SCOTT MOORE (FSME) |
| This material event contains a "Less than Cat 3" level of radioactive material. |
Event Text
DEVICE CONTAINING RADIOACTIVE SOURCES INADVERTENTLY SENT TO RECYCLING FACILITY
"The U.S. Environmental Protection Agency's Region 2 is reporting that an X-ray fluorescence analyzer (model X-Met 880) bought by an EPA contractor in 1990 intended for handing over to EPA REAC/ERT, a headquarters facility in 1995, was inadvertently picked up on December 18, 2006 from the EPA Region 2 facility in Edison, NJ. EPA Region 2 health & safety personnel were notified on Friday afternoon, February 16, 2007, that the analyzer sent with other equipment to a Canadian recycling facility was screened, found to contain a radioactive component, and set aside under lock and key. This was inconsistent with information that sources were removed from any equipment sent. Contact was successfully made with the recycling facility on Tuesday after President's Day, February 20, 2007, confirming that the facility had detected the sources in the analyzer. Region 2 staff has also endeavored to contact EPA headquarters personnel thought to have responsibility for this analyzer, but as of this writing have not received a response.
"The analyzer, containing 100 mCi of Cm-244 and 30 mCi of Am-241 is intact, in its original case and is secured by the company awaiting return to EPA. If Region 2 EPA is the party that must take this back then it plans to have the unit wipe tested before return."
* * * UPDATE 1420 EST ON 2/21/07 FROM QWONG CHO TO S. SANDIN * * *
The device was purchased by Roy F. Weston Corp. while under contract to the U.S. EPA and was stored in a locked warehouse in Edison, NJ since approximately 1995. The Model X-Met 880 S/N is 144216 and the two sealed source S/N's are 2765LX (Am-241) and 1951LM (Cm-244). The device is currently in the custody of Maser Canada, Inc. located in Barrie, Ontario pending arrangements for its return. The Canadian Nuclear Safety Commission is aware of this incident.
Notified R1DO (Jackson) and FSME (Morell).
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.
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: 43178 |
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: JEFF GROFF
HQ OPS Officer: JEFF ROTTON |
Notification Date: 02/21/2007
Notification Time: 20:37 [ET]
Event Date: 02/21/2007
Event Time: 13:30 [EST]
Last Update Date: 02/21/2007 |
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE |
Person (Organization):
BRUCE BURGESS (R3) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 2 |
N |
Y |
100 |
Power Operation |
100 |
Power Operation |
Event Text
ALTERNATE EOF UNAVAILABLE
"While the normal Emergency Operations Facility (EOF) was unavailable due to modification, the space that is utilized for the Alternate EOF was in a locked condition and it is normally not locked. This condition was discovered during the dayshift and was readily corrected. However, had the facility been required during off hours it would have delayed activation of the Alternate EOF.
"Additionally, activation of the Alternate EOF would have been hampered by key availability to the facility storage room and supply cabinet.
"Access to Alternate EOF and equipment has been restored."
The licensee notified the NRC Resident Inspector. |
| Power Reactor |
Event Number: 43179 |
Facility: CRYSTAL RIVER
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] B&W-L-LP
NRC Notified By: RICKY E. RAWLS
HQ OPS Officer: STEVE SANDIN |
Notification Date: 02/21/2007
Notification Time: 22:11 [ET]
Event Date: 02/21/2007
Event Time: 19:15 [EST]
Last Update Date: 02/21/2007 |
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):
EUGENE GUTHRIE (R2) |
| Unit |
SCRAM Code |
RX CRIT |
Initial PWR |
Initial RX Mode |
Current PWR |
Current RX Mode |
| 3 |
A/R |
Y |
71 |
Power Operation |
0 |
Hot Standby |
Event Text
AUTOMATIC REACTOR TRIP ON HIGH RCS PRESSURE FOLLOWING A FEEDWATER TRANSIENT
"At 1915 on February 21, 2007, Crystal River Unit 3 was at reduced power (71%) for planned maintenance on one of four condenser waterboxes when the Integrated Control System (ICS) for Main Feedwater became erratic causing a feedwater transient that underfed the once thru steam generators. The reactor protection system (RPS) actuated on high Reactor Coolant System pressure causing a reactor trip. CR3 also received an Emergency Feedwater Actuation (EFIC) on low steam generator levels. This event is reportable as a 4-Hour Non-Emergency Notification per 10CFR50.72 (b)(2)(iv)(B) for Reactor Protection System Actuation and as an 8-Hour Non-Emergency Notification per 10CFR50.72 (b)(3)(iv)(A) for Emergency Feedwater Actuation and for Reactor Protection System actuation. All systems responded as designed and the plant remains stable with Emergency Feedwater in MODE 3."
The licensee informed the NRC Resident Inspector. |
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