| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
06/26/2017 - 06/27/2017 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 52809 | Rep Org: KENTUCKY DEPT OF RADIATION CONTROL
Licensee: KENVIRONS, INC.
Region: 1
City: FRANKFORT State: KY
County:
License #: 401-079-20
Agreement: Y
Docket:
NRC Notified By: CURT PENDERGRASS
HQ OPS Officer: BETHANY CECERE | Notification Date: 06/16/2017
Notification Time: 09:01 [ET]
Event Date: 06/14/2017
Event Time: [CDT]
Last Update Date: 06/16/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MEL GRAY (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOSS OF CONTROL OF LICENSED MATERIAL
The following was received from the Commonwealth of Kentucky:
"Sometime in February 2009 during the decommissioning of the licensee's laboratory, the electron capture detector (ECD) contained in a Varian model 3700 gas chromatograph went missing. The ECD was an Amersham model NBC containing 8 mCi of Ni-63, S/N A404, assay date 2/14/1992. The licensee discovered the device was missing during a routine inspection by the KY Radiation Health Branch. This event is actively being investigated by the licensee."
KY Event Report ID No: KY170005
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 |
| Fuel Cycle Facility | Event Number: 52811 | Facility: GLOBAL NUCLEAR FUEL - AMERICAS
RX Type: URANIUM FUEL FABRICATION
Comments: LEU CONVERSION (UF6 TO UO2)
LEU FABRICATION
LWR COMMERICAL FUEL
Region: 2
City: WILMINGTON State: NC
County: NEW HANOVER
License #: SNM-1097
Agreement: Y
Docket: 07001113
NRC Notified By: PHILLIP OLLIS
HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/16/2017
Notification Time: 18:20 [ET]
Event Date: 06/16/2017
Event Time: 17:00 [EDT]
Last Update Date: 06/16/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (b)(1) - UNANALYZED CONDITION
| Person (Organization):
OMAR LOPEZ (R2DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text UNANALYZED CONDITION IDENTIFIED
"At 1700 EDT on June 16, 2017 it was determined that an unanalyzed condition was identified that failed to meet performance criteria. This report is conservatively being made in accordance with 10CFR70 Appendix A (b)(1).
"In the powder process, a non-radioactive additive is added to a can of uranium in a hood. A previous process hazard analysis (PHA) determined that a criticality in the associated HEPA filters was not credible during this step. A recent update to a criticality analysis identified a potential condition where small amounts of uranium could build up in the HEPA filter over decades. The ISA [Integrated Safety Analysis] team met and decided that current safety controls will need to be implemented as IROFS [items relied on for safety] to assure that performance criteria are met. The operation is currently shut down and no unsafe condition existed.
"Safety Significance of Events: At no time was an unsafe condition present.
"Safety Equipment Status: The operation was shutdown.
"Status of Corrective Actions: Additional corrective actions, extent of condition, and extent of cause are being investigated." |
| Part 21 | Event Number: 52828 | Rep Org: ITT ENIDINE INC.
Licensee: ITT ENIDINE INC.
Region: 1
City: WESTMINSTER State: SC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JEFF GOTTHELF
HQ OPS Officer: STEVE SANDIN | Notification Date: 06/26/2017
Notification Time: 14:42 [ET]
Event Date: 06/26/2017
Event Time: [EDT]
Last Update Date: 06/26/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
RAY POWELL (R1DO)
REINALDO RODRIGUEZ (R2DO)
ERIC DUNCAN (R3DO)
MICHAEL VASQUEZ (R4DO)
PART 21/50.55 REACTO (EMAI)
| Event Text PART 21 - POTENTIAL TRANSDUCER COMPONENT DEFECT
The following information was received via fax:
"This letter is a Part 21 notification to the US Nuclear Regulatory Commission of a potential component defect.
"The ITT Conoflow models GT25CA1826 and GT25CD1826 current to pressure (l/P) transducers produce a calibrated 3.0 to 15.0 psi output pressure from a 4.0 to 20.0 mA DC (input) signal.
"On May 5, 2017 a non-safety related GT25CA1826 was received for evaluation. This transducer would not respond to the 4 to 20 mA operating signal. The failure was caused by a defective solder joint at a coil lead terminal on the printed circuit board. The circuit board was replaced and the unit worked correctly.
"An immediate inspection of all stock revealed additional parts with defective solder joints. Based on our [Enidine] investigation, circuit boards with defective solder joints are limited to two lots, received on April 29, 2016 and May 27, 2016. Preventive measures have been implemented to prevent recurrence.
"We [Enidine] have produced and shipped the following safety related products that have used parts from these two lots of circuit boards:
Enertech Purchase Order No.: 638764
Utility/Station P.O. No.: 15018770
Qty: 2
Part Number: GT25CD1826
Serial Numbers: 628974 and 628975
Customer/Station: Enertech\Gefran [Benelux NV]
Enertech Purchase Order No.: 638942-1
Utility/Station P.O. No. 500603219
Qty: 1
Part Number: GT25CA1826
Serial Numbers: 629276
Customer/Station: Enertech\Arizona Power [Palo Verde]
Enertech Purchase Order No.: 639238
Utility/Station P.O. No.: 343472
Qty: 2
Part Number: GT25CD1826
Serial Numbers: 629454 and 629455
Customer/Station: Enertech\CCI [Control Components Inc.]
"Facilities which have procured suspect product will be notified and advised how to examine their stock for the potential defect. ITT will provide verified replacements for any defective or suspect circuit boards."
Enidine
105 Commerce Way
Westminster, SC 29691
Phone: (864)-647-9521
Fax: (864}-647-9574
Jeff Gotthelf
Engineering Manager |
| Power Reactor | Event Number: 52829 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [ ] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: MICHAEL MCCARTHY
HQ OPS Officer: VINCE KLCO | Notification Date: 06/26/2017
Notification Time: 18:39 [ET]
Event Date: 06/26/2017
Event Time: [EDT]
Last Update Date: 06/26/2017 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
RAY POWELL (R1DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 93 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO LOSS OF MAIN FEEDPUMP
"On June 26, 2017, at 1531 [EDT], Indian Point Unit 2 inserted a manual reactor trip prior to Steam Generator levels reaching the automatic reactor trip setpoint. Steam Generator water level perturbation resulted from a loss of 22 Main Boiler Feed Pump. All Control Rods verified inserted. The Auxiliary Feedwater System started as designed and supplied feedwater to the Steam Generators. Heat removal is via the Main Condenser through the High Pressure Steam Dumps. Offsite power is being supplied through the normal 138kV feeder 95332. The cause of the 22 Main Boiler Feed Pump loss is currently under investigation. Entergy is issuing a press release/news release on this issue."
Unit 2 is stable and in Mode 3. There was no impact on Unit 3.
The licensee notified the State of New York and the NRC Resident Inspector. |
| Power Reactor | Event Number: 52830 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: SID MORRISON
HQ OPS Officer: HOWIE CROUCH | Notification Date: 06/27/2017
Notification Time: 01:05 [ET]
Event Date: 06/26/2017
Event Time: 17:56 [PDT]
Last Update Date: 06/27/2017 | 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):
MICHAEL VASQUEZ (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 98 | Power Operation | 98 | Power Operation | Event Text SECONDARY CONTAINMENT DECLARED INOPERABLE
"On June 26, 2017 at 1756 PDT, Reactor Building (Secondary Containment) pressure rose above the Technical Specification (TS) requirement multiple times from 1756 to 1800.
"Secondary Containment was declared inoperable and entry into Technical Specification Action Statement 3.6.4.1.A was made. There was a significant change in average wind speed and barometric pressure occurring at that time.
"At 1800 PDT, Secondary Containment pressure was restored to within limits and TS 3.6.4.1.A was exited. Environmental conditions have stabilized. The Reactor Building Differential Pressure controllers are working as designed.
"This condition is being reported under 10 CFR 50.72(b)(3)(v)(C) and 10 CFR 50.72(b)(3)(v)(D) for an event or condition that could have prevented fulfillment of a safety function needed to control the release of radioactive material and accident mitigation.
"The licensee has notified the NRC Resident Inspector." | |