| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/18/2016 - 02/19/2016 ** EVENT NUMBERS ** |
 | Power Reactor | Event Number: 51717 | Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN RASMUSSEN
HQ OPS Officer: STEVEN VITTO | Notification Date: 02/09/2016
Notification Time: 09:54 [ET]
Event Date: 02/09/2016
Event Time: 08:12 [CST]
Last Update Date: 02/18/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
NEIL OKEEFE (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 | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text PLANNED MAINTENANCE OF THE PLANT COMPUTER SYSTEM
"Planned maintenance of the Plant Computer System (PCS) will cause a loss of emergency assessment capability.
"Beginning February 9, 2016, PCS data will not be available to the following Comanche Peak Nuclear Power Plant (CPNPP) facilities due to planned PCS software modifications:
-Emergency Operations Facility [EOF]
-Backup EOF
-Operations Support Center
"The Emergency Response Data System [ERDS] will also be unavailable.
"The planned maintenance of the PCS is being reported as a loss of assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii) because the duration is expected to be more than 72 hours and the data to the Backup EOF is also affected.
"CPNPP has compensatory measures in place to ensure timely emergency classification, protective action recommendation and emergency notification, as needed.
"The PCS modification is expected to be complete by February 18, 2016. A follow-up ENS [Emergency Notification System] communication will be made when the EOF assessment capability is restored."
The Licensee has notified the NRC Resident Inspector.
* * * UPDATE FROM RAUL MARTINEZ TO STEVEN VITTO ON 02/18/2016 AT 1541 EST * * *
"The planned maintenance of the Comanche Peak Plant Computer System (PCS) that began on February 9, 2016 is complete.
"Assessment capability in the following facilities was restored effective 1300 [CST] February 18, 2016:
-Emergency Operations Facility (EOF)
-Backup EOF
-Operations Support Center
"The Emergency Response Data System availability has also been restored."
The Licensee has notified the NRC Resident Inspector.
Notified the R4DO(Werner). |
| Agreement State | Event Number: 51726 | Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: KILGORE FLARES COMPANY, LLC
Region: 1
City: TOONE State: TN
County:
License #: GL 334
Agreement: Y
Docket:
NRC Notified By: ANDREW HOLCOMB
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/11/2016
Notification Time: 15:43 [ET]
Event Date: 02/04/2013
Event Time: [EST]
Last Update Date: 02/11/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY POWELL (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - MISSING NRD IONIZER DEVICE
The following historical information was received from the State of Tennessee via email:
"On March 26, 2013, Kilgore Flares Company and the Division of Radiological Health (DRH) discovered that one of Kilgore's NRD Ionizer devices, model P-2035; S/N A2GK795, was lost. The device contained 40 mCi of Po-210. The device was shipped 10/09/08 from NRD, LLC, located in Grand Island, NY. It was taken out of service in October 2009 when Kilgore renewed the lease for the device. Kilgore was under the impression that the ionizer had been sent back to NRD the previous year. Kilgore did not learn until after the inventory list was sent to DRH February 4, 2013, that NRD had not received them. The device was searched for but could not be located. The boxes that contained the devices sat in the shipping department for some time and this is believed to be where the device came up missing. Kilgore reported that they now keep all devices, being sent back, in the Maintenance Planners office until sealed up for shipping. Kilgore provided a report to DRH on 4/2/13."
State Event Report ID No.: TN-13-048
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: 51727 | Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: TOXCO MATERIAL MANAGEMENT CENTER (TMMC)
Region: 1
City: OAK RIDGE State: TN
County:
License #: R-01037-E16
Agreement: Y
Docket:
NRC Notified By: ANDREW HOLCOMB
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/11/2016
Notification Time: 15:43 [ET]
Event Date: 06/17/2013
Event Time: [EDT]
Last Update Date: 02/11/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY POWELL (R1DO)
ANGELA MCINTOSH (NMSS)
| Event Text AGREEMENT STATE REPORT - EXOTHERMIC REACTION IN SUPERCOMPACTOR ROOM INVOLVING LICENSED MATERIAL
The following historical information was received from the State of Tennessee via email:
"During a routine inspection, it was discovered through review of Toxco Radiological Occurrence Reports that Toxco had an event on June 17, 2013. In the Building A Supercompactor Room, a 55-gallon drum exploded due to an exothermic reaction. The cause was suspected to be the inadvertent packing of nitro-cellulous filters being placed in a waste drum of 3.7 mCi of I-125 contaminated personal protective equipment from Boston Heart Laboratory. The compactor was secured and no indication of radioactive material was discovered in the vicinity beyond the compaction cell. All personnel passed through a personnel contamination monitor without incident. The licensee performed a root-cause analysis determining that Boston Heart Laboratory had packed the nitro-cellulous filters into the waste containers. The licensee isolated two additional 55-gallon drums for return to Boston Heart Laboratory."
State Event ID No.: TN-13-195 |
| Agreement State | Event Number: 51728 | Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: CLARA MAASS MEDICAL CENTER
Region: 1
City: BELLEVILLE State: NJ
County:
License #: NJ PI ID # 42
Agreement: Y
Docket:
NRC Notified By: RICHARD PEROS
HQ OPS Officer: STEVE SANDIN | Notification Date: 02/11/2016
Notification Time: 15:38 [ET]
Event Date: 02/11/2016
Event Time: [EST]
Last Update Date: 02/11/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
RAY POWELL (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text AGREEMENT STATE REPORT - BRACHYTHERAPY DEVICE MALFUNCTION RESULTING IN UNDERDOSE
The following information was received from the State of New Jersey via fax:
"One of the hospital's authorized medical physicists reported that a patient was due to receive a therapeutic treatment from the center's HDR [High Dose Rate] unit. During administration of the fraction, there was a device malfunction. The source was safely returned to the shielded position, but the patient did not receive the prescribed dose for the fraction. There was an underdose. The patient and the patient's physician have been informed. The unit is a Nucletron MicroSelectron Model 106.990. Additional details will be forthcoming from the hospital."
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient. |
| Power Reactor | Event Number: 51742 | Facility: HATCH
Region: 2 State: GA
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: GUY GRIFFIS
HQ OPS Officer: STEVEN VITTO | Notification Date: 02/18/2016
Notification Time: 15:48 [ET]
Event Date: 02/16/2016
Event Time: 06:31 [EST]
Last Update Date: 02/18/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
SHANE SANDAL (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text WELD OVERLAY FLAW DID NOT MEET ACCEPTANCE CRITERIA
"As part of the upgrade to the full structural weld overlays (FSWOL) per NRC-approved ISI [In-service Inspection] Alternative HNP-ISI-ALT-15-01, the surface of the existing weld overlay for the 1E Recirculation weld (1B31-1RC-12BR-E-5) was ground to prepare the surface for receipt of a new Alloy 52M overlay. Upon performance of the subsequent liquid penetrant testing examination, it was discovered that the as-found condition of the flaw did not meet acceptance criteria. It was determined that the flaw constituted a defect in the primary coolant system that could not be found acceptable per ASME Section XI. Therefore, this event notification is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A).
"Evaluation of the flaw found in the weld overlay suggests that the non-satisfactory liquid penetrant surface examination is a result of the propagation of the original flaw that was found on the 1E Recirculation Loop Piping. The flaw is axial in nature and therefore there is no impact on structure integrity degradation. No leakage is currently present or was seen during the previous operating cycle from this flaw. There is also reasonable assurance that there was not a breach in the credited RCS [Reactor Coolant System] boundary during the previous operating cycle.
"As part of the corrective action to fix the flaw, the 1E Recirculation weld will be upgraded to full structural weld overlay per the NRC-approved ISI Alternative."
The Licensee notified the NRC Resident Inspector. |
| Part 21 | Event Number: 51743 | Rep Org: NUCLEAR LOGISTICS INC
Licensee: NUCLEAR LOGISTICS INC
Region: 4
City: FORT WORTH State: TX
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TRACY BOLT
HQ OPS Officer: STEVEN VITTO | Notification Date: 02/18/2016
Notification Time: 18:29 [ET]
Event Date: 02/18/2016
Event Time: [CST]
Last Update Date: 02/18/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
| Person (Organization):
GLENN DENTEL (R1DO)
SHANE SANDAL (R2DO)
ROBERT ORLIKOWSKI (R3DO)
GREG WERNER (R4DO)
PART 21/50.55 REACT (EMAI)
| Event Text PART 21 - CONTACTOR MAKING NOISE
The following was received via fax:
"Initial notification of a potential 10 CFR Part 21 condition.
"Pursuant to the rules of 10 CFR 21.21 this initial notification is being submitted to the NRC to identify a potential reportable condition that is currently under evaluation.
"FPL [Florida Power & Light] Turkey Point has identified a contactor that was making a considerable amount of noise that was not expected. The unit was continuing to functionally operate, however the source of the noise is cause for investigation.
"The contactors are a non-standard Size 3 and Size 4 Freedom Series Starter/Contactor. These units are currently under evaluation and review by NLI [Nuclear Logistics Inc.] to determine the root cause of the identified condition to determine if the contactor contains a defect.
"To date there have been no reported failures of this item to perform the intended safety function. These components were first supplied in September 2002 to Duke Oconee with no reported issues identified. The units reported by FPL Turkey point were supplied in May and December 2011. They have been installed into other facilities including the Duke Shearon Harris plant in December 2013. Although the increased noise is undesirable, it is not presenting a significant condition adverse to quality that could create a substantial safety hazard. Preliminary testing has confirmed that the safety related performance characteristics have not been degraded. However, due to the number of utilities which may have these components in service, this notification is being submitted to identify the condition to the industry.
"NLI plans to have the completed report submitted by 3/15/2016." | |