| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
01/29/2014 - 01/30/2014 ** EVENT NUMBERS ** |
 | Part 21 | Event Number: 49628 | Rep Org: TRIVIS INC.
Licensee: TRIVIS INC.
Region: 1
City: BIRMINGHAM State: AL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DAVID BLAND
HQ OPS Officer: HOWIE CROUCH | Notification Date: 12/13/2013
Notification Time: 14:37 [ET]
Event Date: 12/13/2013
Event Time: [CST]
Last Update Date: 01/29/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
| Person (Organization):
RICHARD SKOKOWSKI (R3DO)
PART 21 GROUPS (EMAI)
| Event Text PART 21 REPORT - NON-DESTRUCTIVE TESTING DID NOT MEET PROCEDURAL REQUIREMENTS
The following information was summarized from the report submitted by TriVis via facsimile:
David Bland, President of TriVis Inc. reported that two contract Non-Destructive Evaluation (NDE) Level II examiners, employed by TriVis, failed to meet NDE procedural requirements for weld testing on the Outer Top Cover Plate (OTCP) on six Transnuclear Model NUHOMS-61BTH Dry Shield Canisters (DSC) at the Monticello Nuclear Generating Plant.
An NRC inspector observed part of this activity and questioned whether the dwell times for the penetrant and developer used by a NDE Level II employee of TriVis were sufficient to meet procedural requirements. Upon evaluating recorded video of the work location, it was determined that the dwell times for both the penetrant and the developer of the OTCP weld on DSC #16 were not in compliance with the TriVis NDE LPT [Liquid Penetrant Test] Procedure. An extent of condition review of previous LPT exams conducted on DSCs 11 through 16 revealed additional examinations that were not in compliance with the dwell times specified by the procedure as well as other procedural discrepancies.
All six DSCs were declared inoperable at the time of discovery. All work activities associated with dry fuel storage at Monticello were stopped. A timeline and corrective actions are being developed by TriVis and the licensee.
The two NDE Level II examiners were not previously employed by TriVis and did not perform any other NDE activities at Monticello.
Evaluations will be completed by January 31, 2014 or a follow-up interim report will be submitted.
The licensee notified the NRC Resident Inspector.
* * * UPDATE FROM MIKE SOUTH TO DANIEL MILLS ON 1/29/14 AT 0945 EDT * * *
The following information was selected from the report submitted by TriVis via facsimile:
"TriVis has completed its evaluation of the activity and determined that it is limited to procedural non-compliance on DSCs 11 through 16 at [Monticello] only. Based on the results of the evaluation, TriVis believes the procedural non-compliance did not adversely affect the health and safety of the public and does not constitute a substantial safety hazard."
Notified R3DO (Sheldon), and NRR Part 21 Group (via email). |
| Agreement State | Event Number: 49752 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: THE QUAKER OATS COMPANY
Region: 4
City: DALLAS State: TX
County:
License #: 01878
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: CHARLES TEAL | Notification Date: 01/21/2014
Notification Time: 15:24 [ET]
Event Date: 01/21/2014
Event Time: [CST]
Last Update Date: 01/21/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BLAIR SPITZBERG (R4DO)
FSME EVENT RESOURCE (EMAI)
MEXICO (FAX)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST PROCESS GAUGE
"On January 21, 2014, the Agency [State of Texas] was notified by the licensee that while conducting a routine source inventory, it could not find a beverage fill device containing a 100 millicurie americium-241 source. The licensee stated the unit was removed from the production line several years ago and placed in storage. The licensee stated the source shutter on the device was locked in the closed position when it was placed in storage. The licensee stated the unit has the appropriate labels on it. The licensee does not believe the lost source presents a risk of exposure to any individual as long as the device is not altered.
"The licensee is interviewing employees and contractor personnel in an attempt to locate the source. The licensee stated the source was inventoried in 2013, but could not provide a specific date. Additional information will be provided as it is received in accordance with SA-300."
Texas Incident Number: I-9147
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: 49755 | Rep Org: VIRGINIA RAD MATERIALS PROGRAM
Licensee: UNKNOWN
Region: 1
City: ASHLAND State: VA
County: HANOVER
License #:
Agreement: Y
Docket:
NRC Notified By: MIKE WELLING
HQ OPS Officer: VINCE KLCO | Notification Date: 01/22/2014
Notification Time: 15:58 [ET]
Event Date: 01/20/2014
Event Time: [EST]
Last Update Date: 01/28/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
HAROLD GRAY (R1DO)
FSME EVENT RESOURCES (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST GENERAL LICENSED DEVICE
The following information was received from the Commonwealth of Virginia by email:
"Event description: On January 20th the Radioactive Materials Program (RMP) received a call from Simms Metal Recycling in Petersburg, that a load of scrap metal being received set off the radiation monitoring detector. A DOT exemption form was completed and the scrap load returned C&C Cullet, Inc. in Ashland, where it originated from. They dumped the scrap load and found the item using a survey meter, which indicated 87 microrem/hr. Pictures were sent to the RMP and upon review concluded that the device was a liquid scintillation analyzer. The RMP contacted the manufacturer, Perkin Elmer, and began a conversation regarding the analyzer. The analyzer is secured at C&C Cullet, Inc. as an investigation is ongoing to determine the serial number and owner of the analyzer. It is believed to contain an 18 mCi source of either Ba-133 or Ni-63. There are no health or safety impacts as the source is secured in the analyzer."
Virginia Event: VA-14-01
* * * UPDATE FROM MIKE WELLING TO CHARLES TEAL ON 1/28/14 AT 1541 EST * * *
The following was received from the Commonwealth of Virginia via email:
"On Tuesday January 28th, the source was removed by the manufacturer for disposal. The company will try to ascertain a serial number from the source to determine the General Licensee whom the device was provided to."
Notified R1DO (Burritt) and FSME Event Resource via email.
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: 49756 | Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: ELEMENT MATERIALS TECHNOLOGY HOUSTON, INC.
Region: 4
City: HOUSTON State: TX
County:
License #: 06451
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: HOWIE CROUCH | Notification Date: 01/22/2014
Notification Time: 17:13 [ET]
Event Date: 01/22/2014
Event Time: [CST]
Last Update Date: 01/22/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BLAIR SPITZBERG (R4DO)
FSME EVENTS RESOURCE (EMAI)
| Event Text TEXAS AGREEMENT STATE REPORT - POTENTIAL OVEREXPOSURE TO RADIOLOGICAL WORKER
The following information was obtained from the State of Texas via email:
"On January 22, 2014, the Agency [Texas Department of Health] was notified by the licensee's Radiation Safety Officer that they had received a report from their dosimetry processor indicating one of their employees had received 11.27 rem DDE [Deep-Dose Equivalent] on their OSL [optically stimulated luminescence] dosimeter for the exposure period of December 1, 2013 to December 31, 2013. This brought the individuals exposure for the year 2013 to 14.250 rem DDE. The RSO stated they had interviewed the employee, who is a radiography trainee, and was not able to discredit the exposure. The radiographer trainer the trainee worked with was also interviewed and did not have an explanation for the exposure. The trainee has been removed from all duties requiring exposure to radiation. The RSO stated they will contact the Radiation Emergency Assistance Center/Training Site, (REAC/TS) the morning of January 23, 2014, to have a cytogenetic blood testing performed of the individual.
"The RSO stated the trainee's exposure total for the same exposure period, as measured by their self-reading dosimeter, was 165 millirem. The RSO stated the trainee had not been involved in any reported source recoveries or misconnects. The RSO stated they had not observed any medical conditions that would support the reported exposure. The RSO does not believe the exposure is real, but since he has not identified another explanation for the reading he will treat it as real until proven otherwise. Additional information will be provided as it is receive in accordance with SA-300."
Texas Incident #: I-9149 |
| Power Reactor | Event Number: 49767 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: CHARLIE ACUNA
HQ OPS Officer: JEFF ROTTON | Notification Date: 01/27/2014
Notification Time: 11:02 [ET]
Event Date: 01/27/2014
Event Time: 09:37 [EST]
Last Update Date: 01/29/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
ART BURRITT (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text RADIATION MONITOR REMOVED FROM SERVICE FOR PLANNED MAINTENANCE
Supplementary Leakage Collection and Release system (SLCRS) Radiation monitor, 3HUR-RE10A/B, is being removed from service for planned maintenance. Radiation monitor is scheduled to be returned to service on February 2, 2014.
The Licensee notified the NRC Resident Inspector, the State Department of Environmental Protection, and the town of Waterford.
* * * UPDATE FROM TOM CLEARY TO CHARLES TEAL AT 1241 EST ON 1/29/14 * * *
The licensee called to correct the identification number of the SLCRS radiation monitor. The SLCRS radiation monitor identification number should be 3HVR 19A/B.
Notified R1DO (Burritt). |
| Power Reactor | Event Number: 49773 | Facility: PALISADES
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: BARBARA DOTSON
HQ OPS Officer: VINCE KLCO | Notification Date: 01/29/2014
Notification Time: 11:06 [ET]
Event Date: 01/29/2014
Event Time: 09:00 [EST]
Last Update Date: 01/29/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
STUART SHELDON (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text INDICATIONS IDENTIFIED ON CONTROL ROD DRIVE MECHANISM HOUSINGS
"On January 29, 2014, during planned inspections of control rod drive mechanism (CRDM) upper housings, it was determined that the inspection results for some housings did not meet the applicable acceptance criteria. That is, evaluations of the housing indications are being performed under ASME Code, Section XI, IWB-3600, 'Analytical Evaluation of Flaws,' and indications were identified that exceed acceptance criteria specified in the Code. None of the indications were through-wall and there was no evidence of leakage.
"The housing indications, varying in depth and length characteristics, were identified in 17 of the 45 CRDM housings inspected. All 45 CRDM housings were inspected, which constituted 100% extent of condition inspection.
"The plant was in cold shutdown at 0% power for a planned refueling outage at the time of discovery. Replacement or repair actions are in progress and will be completed prior to plant startup from the outage.
"This condition has no impact to the health and safety of the public.
"This report is being made in accordance with 10CFR 50.72(b)(3)(ii)(A), since indications were found that did not meet acceptance criteria referenced in ASME Code, Section XI.
"The licensee notified the NRC Senior Resident Inspector." |
| Power Reactor | Event Number: 49774 | Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: ADAM McGUIRE
HQ OPS Officer: CHARLES TEAL | Notification Date: 01/29/2014
Notification Time: 14:58 [ET]
Event Date: 01/29/2014
Event Time: 11:15 [EST]
Last Update Date: 01/29/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ART BURRITT (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text SECONDARY CONTAINMENT BOUNDARY WAS TEMPORARILY BLOCKED OPEN
"Title: Door Opened Under Administrative Control Could Have Prevented Fulfillment of Safety Functions to Control the Release of Radioactive Material and Mitigate the Consequences of an Accident
"On January 29, 2014, it was determined a door credited as a Secondary Containment Boundary was temporarily blocked opened multiple times since January 25, 2014 under administrative control. Technical Specification 3.6.6.2 'Secondary Containment' is applicable and requires the system to be restored to operable status within 24 hours. In each instance where the door was blocked open, the requirements of Technical Specification 3.6.6.2 were entered and complied with.
"NUREG 1022 Revision 3 states inoperability of a single train system is reportable even though the plant's Technical Specifications may allow the condition to exist for a limited time. Although the plant was operated within the licensing basis, since Secondary Containment 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 and mitigate the consequences of an accident.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(v)(C) and 10 CFR 50.72(b)(3)(v)(D).
"The NRC Senior Resident Inspector has been notified. |
| Power Reactor | Event Number: 49776 | Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: JASON DEPRIEST
HQ OPS Officer: DANIEL MILLS | Notification Date: 01/29/2014
Notification Time: 18:33 [ET]
Event Date: 01/29/2014
Event Time: 09:53 [CST]
Last Update Date: 01/29/2014 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
STUART SHELDON (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 97 | Power Operation | 97 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text LOSS OF TECHNICAL SUPPORT CENTER VENTILATION FAN
"This telephone notification is provided in accordance with Exelon Reportability manual SAF 1.10, 'Major Loss of Emergency Preparedness Capabilities', and 10 CFR 50.72(b)(3)(xiii).
"On January 29th at 09:53 CST, it was determined that the onsite Technical Support Center (TSC) Ventilation System Supply Fan had failed (due to failed fan belts as a result of degraded alignment), resulting in loss of ventilation for the TSC. Repairs have been initiated, however repairs will not have been completed within the time required to staff the TSC. There is currently no emergency event in progress requiring TSC staffing. The Main Control Room remains available as an Emergency Response Facility (ERF), should an event occur requiring Emergency Response Facilities to be staffed.
"The licensee has notified the Senior Resident Inspector of the issue." | |