| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
05/15/2013 - 05/16/2013 ** EVENT NUMBERS ** |
 | Non-Agreement State | Event Number: 49000 | Rep Org: VALLEY QUARRIES, INC.
Licensee: VALLEY QUARRIES, INC.
Region: 1
City: CHAMBERSBURG State: PA
County:
License #: PA-1222
Agreement: Y
Docket:
NRC Notified By: JOHN ENGLERTH
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/03/2013
Notification Time: 17:03 [ET]
Event Date: 05/03/2013
Event Time: [EDT]
Last Update Date: 05/15/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
| Person (Organization):
GORDON HUNEGS (R1DO)
FSME EVENTS RESOURCE (EMAI)
ILTAB (EMAI)
|
| This material event contains a "Less than Cat 3" level of radioactive material. | Event Text LOST TROXLER MOISTURE DENSITY GAUGE
The licensee from Chambersburg, PA, was doing work in West Virginia under a reciprocity agreement. The authorized user was conducting a reading when he was asked by his supervisor to pick-up a fellow employee at the construction yard approximately 1.5 miles from the reading site. After the reading was done, the user placed the gauge in the back of his pickup truck and proceeded to the construction yard. Once he arrived at the yard, he saw that his truck tailgate was down and the gauge was missing. The gauge was not in its shipping container. The user and his co-worker doubled back in search of the gauge but did not find it. When the RSO arrived, another employee told him that he saw someone stopping along the highway to pick up what appeared to be the gauge and then driving off. At that time, the employee was unaware a gauge was missing so he didn't pay much attention to the vehicle.
The gauge is identified as a Troxler Electronics Laboratories Model # 3430, Serial # 32506. It contains 8 mCi of Cs-137 and 40 mCi of Am-241.
The RSO notified the West Virginia State Police, the local newspaper and the regional television station. The licensee is considering offering a reward for the return of the gauge.
* * * UPDATE AT 2244 EDT ON 5/15/13 FROM THE PENNSYLVANIA DEPARTMENT OF ENVIRONMENTAL PROTECTION TO SNYDER * * *
The gauge has been recovered and is now in the possession of the licensee. Notified R1DO (Schroeder), ILTAB (Hahn), and FSME Events Resource (E-Mail).
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 |
| Agreement State | Event Number: 49009 | Rep Org: MISSISSIPPI DIV OF RAD HEALTH
Licensee: MISTRAS GROUP, INC.
Region: 4
City: PASCAGOULA State: MS
County:
License #: MS-995-01
Agreement: Y
Docket:
NRC Notified By: JAYSON MOAK
HQ OPS Officer: DONALD NORWOOD | Notification Date: 05/07/2013
Notification Time: 15:05 [ET]
Event Date: 05/06/2013
Event Time: [CDT]
Last Update Date: 05/07/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MICHAEL VASQUEZ (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text AGREEMENT STATE REPORT - STUCK RADIOGRAPHY SOURCE
The following information was received via E-mail:
"Licensee reported a stuck radiography source that occurred at approximately 2315 CDT on May 6, 2013. Licensee's RSO responded to incident site, increased barricades, maintained perimeter, and notified Chevron RSO. Licensee's source was fully retracted into the shielded position at 0100 CDT [on May 7, 2013]. The Licensee's RSO received 20 mR conducting the source retrieval."
The incident occurred while performing work at the Chevron Pascagoula Refinery. |
| Agreement State | Event Number: 49011 | Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: QSA GLOBAL
Region: 1
City: BURLINGTON State: MA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BRUCE PACKARD
HQ OPS Officer: DONALD NORWOOD | Notification Date: 05/08/2013
Notification Time: 17:03 [ET]
Event Date: 05/08/2013
Event Time: 10:00 [EDT]
Last Update Date: 05/09/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
JAMES DWYER (R1DO)
BRIAN MCDERMOTT ()
JANE MARSHALL (IRD)
JIM WHITNEY (ILTA)
DAVID AYRES (R2DO)
HIRONORI PETERSON (R3DO)
MICHAEL VASQUEZ (R4DO)
FSME EVENTS RESOURCE (EMAI)
|
| This material event contains a "Category 2" level of radioactive material. | Event Text AGREEMENT STATE REPORT - POTENTIALLY LOST RADIOACTIVE SOURCE SHIPMENT
Two, Category 2, IR-192 industrial radiography sources, loaded in a QSA Global model 650L source changer, left Wilmington, MA at 1416 EDT, 5/6/13 headed for Norfolk Naval Shipyard, Norfolk, VA. The source changer was expected to be delivered early the morning of 5/8/13. Norfolk Naval Shipyards notified QSA Global when the source changer did not arrive as scheduled. The transportation company was then notified. The transportation company began searches of its facilities in Newark, NJ and Boston, MA for the source changer. The last known shipping scan of the source changer was at 2342 EDT, 5/6/13 in Newark, NJ.
The source changer is a metal container measuring 8 1/4 inches x 10 inches x 13 inches that weighs approximately weighs 90 lbs. The transportation company is continuing to search for the source changer.
* * * UPDATE FROM CHARLES ELLARS (QSA Global) TO CHARLES TEAL ON 5/9/13 AT 0902 EDT * * *
The sources were found in the Newark, NJ facility and the shipment is expected to arrive at Norfolk Naval Shipyard on 5/10/13.
Notified R1DO (Dwyer), R2DO (Ayers), R3DO (Peterson), R4DO (Vasquez), IRD (Marshall), ILTAB (Whitney), FSME (McDermott), FSME Event Resources via email, DHS SWO, DOE, FEMA, HHS, NICC, USDA, EPA and Nuclear SSA via email.
* * * UPDATE FROM KENATH TRAEGDE (MA STATE) TO JOHN SHOEMAKER ON 5/9/13 AT 1444 EDT * * *
The state was notified, by QSA Global, at 0825 EDT on 5/9/13 that the source was found at 0450 EDT on 5/9/13. The state will submit a follow-up report.
THIS MATERIAL EVENT CONTAINS A "CATEGORY 2" LEVEL OF RADIOACTIVE MATERIAL
Category 2 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for a short time (minutes to hours). It could possibly be fatal to be close to this amount of unshielded radioactive material for a period of hours to days. These sources are typically used in practices such as industrial gamma radiography, high dose rate brachytherapy and medium dose rate brachytherapy. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf |
| Power Reactor | Event Number: 49031 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: RICK GARCIA
HQ OPS Officer: PETE SNYDER | Notification Date: 05/14/2013
Notification Time: 18:37 [ET]
Event Date: 05/14/2013
Event Time: 15:02 [PDT]
Last Update Date: 05/15/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MICHAEL HAY (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 PLANNED POWER OUTAGE AT TSC AND OSC
"During Refueling Outage 21, at 1502 PDT on 5/14/13, power to the Technical Support Center (TSC) and Operations Support Center (OSC) was removed as part of transferring the facility to temporary power during a bus outage impacting the normal facility power supply. The TSC and OSC will be unavailable for use for several hours until temporary power has been established.
"Established compensatory measures direct ERO members normally responding to either of the two impacted centers to respond to alternate locations. No other emergency response facilities are impacted by the bus outage.
"This event is being reported as a loss of emergency preparedness capabilities in accordance with 10 CFR 50.72(b)(3)(xiii). The resident inspector has been notified. A follow up notification will be made when temporary power has been established and the facility is available for use."
The licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM SANDRA CHRISTIANSON TO PETE SNYDER AT 1637 EDT ON 5/15/13 * * *
"This is a follow-up courtesy notification to EN# 49031. Temporary power has been established to the TSC and OSC, and both are available for emergency response. Normal power to TSC and OSC is expected to be restored on or about June 2, 2013 at 0600 PDT and will require a similar removal of power to the facility. A separate notification will be made when swapping off of temporary power."
The licensee has notified the NRC Resident Inspector. Notified R4DO (Hay). |
| Power Reactor | Event Number: 49032 | Facility: CATAWBA
Region: 2 State: SC
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: WALTER HUNNICUTT
HQ OPS Officer: DONALD NORWOOD | Notification Date: 05/15/2013
Notification Time: 02:52 [ET]
Event Date: 05/14/2013
Event Time: 23:23 [EDT]
Last Update Date: 05/15/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
JONATHAN BARTLEY (R2DO)
|
| 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 OFFSITE NOTIFICATION DUE TO LEAK FROM TURBINE BUILDING SUMP CONTAINING TRITIUM
"Sample exceeding the industry groundwater protection initiative related to radioactivity in groundwater for which a news release is planned and notification to other government agencies will be made."
"A leak greater than 100 gallons containing tritium has the potential to reach groundwater. The source has been identified. Actions to isolate this source are being initiated."
The licensee has identified a leak in a fiberglass discharge pipe from the turbine building sump. The licensee estimates that greater than 100 gallons of water has been discharged through the leak at the present time. The licensee is in the process of installing a temporary sump pump in the turbine building sump in order to isolate the discharge path. Samples indicate a tritium concentration of 8.964 E-6 uCi/mL.
The licensee will notify state and local government agencies. A press release is planned. The licensee will notify the NRC Resident Inspector. |
| Research Reactor | Event Number: 49033 | Facility: TEXAS A&M UNIVERSITY
RX Type: 1000 KW TRIGA (CONVERSION)
Comments:
Region: 4
City: COLLEGE STATION State: TX
County: BRAZOS
License #: R-83
Agreement: Y
Docket: 05000128
NRC Notified By: ESTEBAN BOTELLO
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/15/2013
Notification Time: 11:03 [ET]
Event Date: 05/14/2013
Event Time: 22:09 [CDT]
Last Update Date: 05/15/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
NON-POWER REACTOR EVENT
| Person (Organization):
MICHAEL HAY-email (R4DO)
DUANE HARDESTY (NRR)
JESSE QUICHOCHO (NRR)
| Event Text RESEARCH REACTOR REPORTABLE EVENT - CONTROL ROD DRIVE MECHANISM JAM
"This preliminary event report is in compliance with Technical Specification 6.6.2 Special Reports confirming in writing the initial report made by telephone to the USNRC Operations Center.
"During reactor shutdown after normal steady state operation on May 14, 2013 at 2209 CDT, shim safety 1 jammed at 30% withdrawn (70% inserted). Operators lowered the remaining rods with no other issues and after determining the reactor was shut down at 2250 CDT, operators began investigating the cause of the jam. The shutdown margin in this configuration was determined to be $2.91 [negative reactivity] with shim safety 1 jammed at 30%. The Technical Specification requirement for shutdown margin is $0.25 [negative reactivity] which meant the reactor was well within acceptable limits for shutdown.
"The reactor was determined to be in a safe shutdown state. During inspection a rope that was attached to an experiment was found to be caught inside the Control Rod Drive Mechanism (CRDM) for shim safety 1 about 10 feet from the surface of the pool. This caused a jam in the drive mechanism not allowing the rod to go below 29% and above 32%.
"A fuel handling team was assembled at 0945 CDT on 5/15/13 in order to remove the control rod assembly for shim safety 1. The rope connecting the experiment to the CRDM was cut in order to allow proper removal of the CRDM. The CRDM was successfully removed and the piece of rope caught inside the drive was removed. After further inspection of the CRDM no other issues were found and it was reinstalled into its normal position.
"Operability and scram time tests were performed and completed satisfactory at 1130 CDT. The fuel handling team was disbanded at 1137 CDT and the reactor was determined to be operational. At no point during this event was there any danger to the general public or Nuclear Science Center personnel." |
| Power Reactor | Event Number: 49034 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: GERALD BAKER
HQ OPS Officer: PETE SNYDER | Notification Date: 05/15/2013
Notification Time: 11:55 [ET]
Event Date: 05/15/2013
Event Time: 04:00 [EDT]
Last Update Date: 05/15/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
DAN SCHROEDER (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Hot Shutdown | 0 | Hot Standby | Event Text LEAKING CONTAINMENT AIR LOCK EQUALIZING VALVE
"On May 15, 2013, at 0400 EDT, it was discovered that an equalizing valve for the outer containment air lock was leaking by its seat rendering the outer containment air lock inoperable. This condition was discovered by maintenance personnel as they were exiting containment through the inner containment air lock.
"The containment inner door was open for transit, which resulted in the Loss of Containment Integrity.
"With both containment air lock doors open at the time of discovery of the leaking equalizing valve, this condition is reportable pursuant to 10 CFR 50.72(b)(3)(v). The inner air lock door was immediately closed and has remained closed since.
"Technical Specification 3.6.1.1 Primary Containment Integrity is applicable in Modes 1,2,3, and 4. Since Primary Containment Integrity was rendered inoperable, Dominion is reporting that this condition could have prevented the fulfillment of the safety function to control the release of radioactive material.
"The NRC Senior Resident Inspector has been notified." |
| Power Reactor | Event Number: 49038 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: ARTHUR PAN
HQ OPS Officer: PETE SNYDER | Notification Date: 05/15/2013
Notification Time: 19:55 [ET]
Event Date: 05/15/2013
Event Time: 06:49 [EDT]
Last Update Date: 05/15/2013 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
JONATHAN BARTLEY (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 | Event Text TECHNICAL SPECIFICATION REQUIRED SHUTDOWN DUE TO DISCOVERY OF AN UNACCEPTABLE FLAW DURING DATA REVIEW
"On May 13, 2013, during a secondary review of ultrasonic data of the reactor vessel head penetrations performed during Harris Nuclear Plant spring 2012 refueling outage, it was determined that the results for one of the penetrations appeared to not meet the applicable acceptance criteria. Further evaluation completed on May 15, 2013, characterized the flaw as a 0.26 inch flaw an nozzle 49 that overlaps the J-grove weld and exhibits characteristics of primary water stress corrosion cracking. The original examinations were performed per NRC requirements.
"Initial evaluation indicates that the flaw is not through wall and there is no evidence of leakage based on inspections performed on the top of the reactor vessel head during the spring 2012 refueling outage. Operators are shutting down the unit to make the necessary repairs. There is no impact to the health and safety of employees or the public.
"The NRC resident inspector has been informed.
"This report is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A), discovery of a degraded condition, 10 CFR 50.72(b)(2)(i), plant shutdown required by technical specifications, and 10 CFR 50.72(b)(3)(v)(C), a condition which could have prevented the fulfillment of a safety function to control the release of radioactive material." | |