| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
08/26/2016 - 08/29/2016 ** EVENT NUMBERS ** |
 | Part 21 | Event Number: 51030 | Rep Org: AZZ/NLI NUCLEAR LOGISTICS, INC
Licensee: ALLEN BRADLEY
Region: 4
City: FORT WORTH State: TX
County:
License #:
Agreement: Y
Docket:
NRC Notified By: TRACY BOLT
HQ OPS Officer: DANIEL MILLS | Notification Date: 05/01/2015
Notification Time: 13:32 [ET]
Event Date: 04/30/2015
Event Time: [CDT]
Last Update Date: 08/26/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
MEL GRAY (R1DO)
FRANK EHRHARDT (R2DO)
ROBERT ORLIKOWSKI (R3DO)
GEOFFREY MILLER (R4DO)
PART 21/50.55 REACT (EMAI)
| Event Text POTENTIALLY UNQUALIFIED COMPONENT IN CERTAIN ALLEN BRADLEY TIMING RELAYS
The following is an excerpt from a document received from the licensee via email:
"Report of potential 10 CFR Part 21, Allen Bradley Timing Relay Model 700RTC
"Pursuant to 10 CFR 21.21(d)(3)(ii), AZZ/NLI is providing written notification of the identification of a potential failure to comply.
"On the basis of our evaluation, it is determined that AZZ/NLI does not have sufficient information to determine if the subject condition would, or has, created a Substantial Safety Hazard or would have created a Technical Specification Safety Limit violation as it relates to the subject plant applications.
"The specific part which fails to comply or contains a defect:
"As of 2009-2010, Allen Bradley relays base model 700RTC, contain an unevaluated CPLD (Complex Programmable Logic Device). This was an unpublished design change that was implemented to replace an obsolete integrated circuit chip. The undocumented design change did not result in a part number change from Allen-Bradley. There was no change to the appearance of the relay that would identify any design changes were made to the relay configuration. Therefore, NLI qualification/dedication of the relays after 2009 have not included additional testing for the new CPLD component.
"The timing relay model 700RTC has been dedicated/qualified for multiple applications for various plants.
"Between 2009-2010 Allen Bradley made a design change without changing the part number of the commercial relay or providing any documented evidence of a design change. The manufacturer specification data sheets maintain the classification that the relays are 'solid state', which would imply that there are no digital devices installed in the relay. However, after inspection of the internals of the timing relay (Figure 2), it has been identified that the unit does contain a CPLD which meets the definition of a digital device under the guidance of NEI 01-01."
Potentially affected plants include Browns Ferry, Ginna, Millstone, Nine Mile Point, North Anna, Ft. Calhoun, Perry, River Bend, South Texas Project, and St. Lucie.
* * * UPDATE FROM TRACY BOLT TO JOHN SHOEMAKER AT 1744 EDT ON 4/8/16 * * *
AZZ/NLI Nuclear Logistics provided additional information regarding Part 21 Report No: P21-04302015, Rev. 1.
Notified R1DO (Rogge), R2DO (Nease), R3DO(Skokowski), R4DO (Kellar), and PART 21/50.55 REACTORS via email.
* * * UPDATE FROM LES TAGGART TO BETHANY CECERE AT 0951 EDT ON 5/26/16 * * *
AZZ/NLI Nuclear Logistics provided Revision 2 to Part 21 Report No: P21-04302015 to correct the referenced EPRI TR-102323 Rev. 3 to Rev. 4 and change 'timing' contacts to 'instantaneous' contacts as shown below:
"(vii) The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action.
"The relays that are currently in stock at NLI have been placed on hold until after the units have been determined to be qualified for the specific application. NU has completed the EMC qualification testing per the requirements of EPRI TR-102323 Rev. 4 for the following tests, as applicable: CE101, CE102, RE101, RE102, RS101, RS103, CS101, CS114, CS115 and CS116.
"The results were satisfactory with exception of the following condition: During Conducted Susceptibility CS114 onto the power lines, with the timing circuit in operation, the instantaneous contacts exhibited chatter in the range of 2.6 MHz to 20.3 MHz. The unit requires a ferrite to be installed onto the input power lines of the relay with 3 turns through the ferrite core. In this modified configuration, the relay was not susceptible to Conducted Susceptibility and successfully passed the required test per CS114."
Notified R1DO (Lilliendahl), R2DO (Guthrie), R3DO(Kunowski), R4DO (Werner), and PART 21/50.55 REACTORS via email.
* * * UPDATE FROM TRACY BOLT TO DONG PARK AT 1807 EDT ON 8/15/16 * * *
AZZ/NLI Nuclear Logistics provided additional information regarding Part 21 Report No: P21-04302015, Rev. 3, correcting the date the change occurred to October 2008.
Notified R1DO (Jackson), R2DO (Shaeffer), R3DO (Riemer), R4DO (Proulx), and PART 21/50.55 REACTORS via email.
* * * UPDATE FROM TRACY BOLT TO DONG PARK AT 1833 EDT ON 8/26/16 * * *
AZZ/NLI Nuclear Logistics is making a word correction in Part 21 Report No: P21-04302015, Rev. 4.
Notified R1DO (Dimitriadis), R2DO (Michel), R3DO (Cameron), R4DO (Kellar), and PART 21/50.55 REACTORS via email. |
| Agreement State | Event Number: 52189 | Rep Org: NV DIV OF RAD HEALTH
Licensee: DESERT SOILS GEOTECHNICAL
Region: 4
City: LAS VEGAS State: NV
County:
License #: 00-11-0726-01
Agreement: Y
Docket:
NRC Notified By: MIKE SCHMIDT
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/18/2016
Notification Time: 13:23 [ET]
Event Date: 08/11/2016
Event Time: [PDT]
Last Update Date: 08/18/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
DAVID PROULX (R4DO)
NMSS_EVENTS_NOTIFIC (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - TWO MOISTURE-DENSITY GAUGES STOLEN
"On August 11, 2016 at 1240 [PDT], it was reported to the State of Nevada, Radiation Control Program (RCP) that two Troxler model 3440, Serial No. 24693 and model 3430, Serial No. 31409 portable gauges had been stolen from a storage location in Las Vegas, Nevada. The storage location is in a residential location. The RSO [Radiation Safety Officer] reported that at 0800 he removed the gauges from storage for routine maintenance. The gauges were in the lab with the door open and not secured or under surveillance for approximately three hours. When he returned the gauges were missing, no other equipment was missing. The RSO is the only employee. The Las Vegas Metropolitan Police, ARMOR division went to the storage address and took a police report. The RCP is following the incident and working with local authorities to recover the missing/stolen portable gauges. Follow-up information will be provide to the NRC as it becomes available. A press release was dispersed through law enforcement and the media."
Troxler 3440: 40 mCi Am-241 and 8 mCi Cs-137
Troxler 3430: 40 mCi Am-241 and 8 mCi Cs-137
NMED NV160013
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: 52190 | Facility: NUCLEAR FUEL SERVICES INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU CONVERSION & SCRAP RECOVERY
NAVAL REACTOR FUEL CYCLE
LEU SCRAP RECOVERY
Region: 2
City: ERWIN State: TN
County: UNICOI
License #: SNM-124
Agreement: Y
Docket: 07000143
NRC Notified By: RANDY SHACKELFORD
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/18/2016
Notification Time: 16:32 [ET]
Event Date: 08/17/2016
Event Time: 17:39 [EDT]
Last Update Date: 08/18/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
70.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
SHANE SANDAL (R2DO)
NMSS_EVENTS_NOTIFIC (EMAI)
FUELS GROUP (EMAI)
| Event Text FAILURE OF A SPEAKER IN AN AREA POTENTIALLY REQUIRING PERSONNEL EVACUATION
"On August 17, 2016 at approximately 1739 hours (EDT), one speaker in Building 120 was identified as non-operational while performing a functional test of the system. This speaker is designed to annunciate alarms generated from the Criticality Accident Alarm System (CAAS) required by 10CFR70.24, alarms generated from the Fire Alarm Control Panel, and Public Address System announcements. Additional functional testing identified that no redundant speaker could adequately provide speaker coverage for all affected areas of this building. Special Nuclear Materials are not processed, handled, or stored within the area where the speaker failed; however, this area requires evacuation in the unlikely event of a nuclear criticality accident as described in the NFS Emergency Plan. There were no actual radiological or other nuclear safety consequences. The potential consequence was that in the event of a nuclear criticality accident, evacuation could have been delayed for those personnel within Building 120 with a resultant increase of postulated doses. A series of compensatory actions were taken to restore compliance including installation of a temporary speaker and limiting equipment operation to limit background noise. On August 18, 2016, at approximately 1100 hours (EDT), full compliance was restored as demonstrated by successfully performing a speaker test in the affected area.
"The licensee notified the NRC Resident Inspector on August 18, 2016." |
| Part 21 | Event Number: 52204 | Rep Org: CRANE NUCLEAR, INC.
Licensee: CRANE NUCLEAR, INC.
Region: 3
City: BOLINGBROOK State: IL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BURT ANDERSON
HQ OPS Officer: DONG HWA PARK | Notification Date: 08/26/2016
Notification Time: 18:00 [ET]
Event Date: 08/03/2016
Event Time: [CDT]
Last Update Date: 08/26/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
ERIC MICHEL (R2DO)
JAMNES CAMERON (R3DO)
RAY KELLAR (R4DO)
PART 21/50.55 REACT (EMAI)
| Event Text PART 21 - SAFETY RELATED COMPONENT WELDING BY AN UNQUALIFIED WELDER
The following was excerpted from a letter by Crane Nuclear, Inc.:
"Shielded metal arc welding (SMAW) with F-5 filler metal was welded on safety related components by an unqualified welder.
"Crane Nuclear Quality Assurance Manual, 12th Edition Rev. 2, dated 8/8/16 requires that welder performance qualification shall conform to the requirements of ASME Section IX for processing ASME B&PV Section Ill and safety related valve and valve part orders. During processing of a safety related order, it was identified that one welder was missing the required qualification documentation to perform weld repairs with F-5 filler metals (as defined in ASME Section IX) using the shielded metal arc welding process (SMAW). The safety hazard which could be created by such a defect could be a potential weld failure.
"Crane Nuclear has completed a review of all applicable welding records based on the welder hire date of September, 2011. We identified a total of 10 orders that were supplied with welding performed by an unqualified welder. Notification has been made to the purchasers of the affected safety related orders on the same date as this notification.
"Should you have any questions regarding this matter, please contact Burt Anderson, Site Leader, at (630) 226-4990, Rosalie Nava, Director of Safety and Quality at (630) 226-4940, or Jason Klein, Engineering Manager at (630) 226-4953."
The following facilities received these safety related orders: Duke-McGuire, Exelon-Byron, Duke-Brunswick, Entergy-ANO, Exelon-TMI, Exelon-Quad Cities, Exelon-Dresden. |
| Power Reactor | Event Number: 52205 | Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: CHRIS MCEACHRAN
HQ OPS Officer: DONG HWA PARK | Notification Date: 08/27/2016
Notification Time: 17:48 [ET]
Event Date: 08/27/2016
Event Time: 15:00 [EDT]
Last Update Date: 08/27/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
JAMNES CAMERON (R3DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 53 | Power Operation | 53 | Power Operation | Event Text SECONDARY CONTAINMENT TECHNICAL SPECIFICATION NOT MET
"On August 27, 2016, at 1500 EDT a severe thunderstorm occurred in Monroe County, including the Fermi 2 site. Due to high winds encountered during the thunderstorm, the Technical Specification (TS) for secondary containment pressure boundary was not met numerous times. The duration of time that the secondary containment Technical Specification was not met was approximately 1 second for each event.
"All plant equipment responded as required to the changing environmental conditions and Reactor Building HVAC returned secondary containment pressure within TS limits. At 1540 EDT, secondary containment vacuum was greater than the TS operability limit of 0.125 inches of vacuum water gauge (TS SR 3.6.4.1.1) and steady, and the LCO was exited. There were no radiological releases associated with this event.
"Declaring secondary containment inoperable is reportable under 10 CFR 50.72(b)(3)(v)(C) as an event or condition that could have prevented the fulfillment of a safety function needed to control the release of radioactive material.
"The licensee has notified the NRC Resident Inspector." | |