| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
11/03/2016 - 11/04/2016 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 52322 | Rep Org: NJ DEPT OF ENVIRONMENTAL PROTECTION
Licensee: RUTGERS UNIVERSITY
Region: 1
City: NEWARK State: NJ
County:
License #: 450669
Agreement: Y
Docket:
NRC Notified By: JAMES MCCULLOUGH
HQ OPS Officer: BETHANY CECERE | Notification Date: 10/27/2016
Notification Time: 12:20 [ET]
Event Date: 10/26/2016
Event Time: 14:00 [EDT]
Last Update Date: 10/27/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
BLAKE WELLING (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - RESEARCH IRRADIATOR SAMPLE DOOR FAILED TO OPEN
"A specific licensee reported a malfunction with one self-shielded irradiator, J.L. Shepherd model Mark I-68A, Serial # 1083 containing two Cs-137 sources with a total current activity of 6822 Ci. At approximately 2PM [EDT] on 10/26/16 [the licensee performed] an irradiation of 8 mice and were unable to open the sample port. They reported that both visual indicators and survey instruments show the source in the safe, shielded position.
"The licensee is in contact with the manufacturer to assist with a repair.
"This is a 24-hour reportable incident under N.J.A.C. 7:28-51.1 (10 CFR 30.50(b)2). NJDEP is tracking this incident internally as incident ID# C620765. NMED Report No. is yet to be assigned and will be reported later." |
| Agreement State | Event Number: 52323 | Rep Org: COLORADO DEPT OF PUBLIC HEALTH
Licensee: CITY OF LAMAR
Region: 4
City: LAMAR State: CO
County:
License #: GENERAL LICEN
Agreement: Y
Docket:
NRC Notified By: LINDA BARTISH
HQ OPS Officer: BETHANY CECERE | Notification Date: 10/27/2016
Notification Time: 12:26 [ET]
Event Date: 06/01/2016
Event Time: [MDT]
Last Update Date: 10/27/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGN
The following was received by the State of Colorado, Department of Public Health and Environment (CDPHE) via email:
"The Waste Water Treatment Plant at the City of Lamar was in construction during the time period the tritium exit sign was ordered by the contractor on the project. An intermediary electrician was brought in to help with the installation of the exit signs. Two signs were ordered and shipped separately. The City of Lamar responded to the annual general license notifications and explained the 2nd exit sign was never received. No further information is available. The tritium exit sign that is lost was manufactured by: Best Lighting Products Inc. AKA Forever Lites, Model #SLXTU1GW20, Serial Number #318952, Isotope: H-3, Activity: 11470 mCi. Date shipped 2-3-2011.
"The City of Lamar was not able to locate the contractor or electrician who worked on the project. Sign is reported lost. The remaining tritium sign will be tracked and annual reports to CDPHE, General License, will be sent in. Should the city decide to remove the sign, notification will be sent in to Radioactive Materials Unit at CDPHE."
Colorado Event Report ID No.: CO16-I16-25
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 |
| Non-Agreement State | Event Number: 52325 | Rep Org: INTERTEK ASSET INTEGRITY MANAGEMENT
Licensee: INTERTEK ASSET INTEGRITY MANAGEMENT
Region: 4
City: Morgan City State: LA
County:
License #: 17-2930801
Agreement: Y
Docket: 03037816
NRC Notified By: ALAN PHILLIPS
HQ OPS Officer: BETHANY CECERE | Notification Date: 10/27/2016
Notification Time: 17:01 [ET]
Event Date: 09/21/2016
Event Time: 11:00 [EDT]
Last Update Date: 10/27/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
BLAKE WELLING (R1DO)
THOMAS FARNHOLTZ (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text SAFETY EQUIPMENT FAILED TO FUNCTION - RADIOGRAPHY SOURCE FAILED TO RETRACT
"On 09/21/2016, a radiography crew was working on a pipeline ROW [right of way] located off of Wolf Run-Poplar Springs Road near Cameron, WV. After developing film shot earlier in the morning, the crew reattached the control cables and guide tube to the exposure device and moved to the next weld. After setup an attempt to make an exposure was made. The radiographer recalled the source assembly felt slightly obstructed upon entry into the guide tube. Upon verification that the guide tube was not kinked, an attempt to retract the source was made. Based on survey meter readings, it was determined the source was not retracting back into the camera, and somehow became disconnected. At this point the radiographer 'pushed' the source out to the collimator to provide some shielding. The crew then established a new 2 mR/hr boundary, advised site personnel of the situation, and notified [the] Pittsburgh site [Radiation Safety Officer] RSO. The [Corporate Assistant RSO] was notified and immediately dispatched [a source retriever] to the site for source retrieval.
"At approximately 1430 EDT [the source retriever, who is also] the site RSO in Dover, OH, arrived at the location. After reviewing the circumstances leading to the disconnect and an inspection of the area, a plan to safely retrieve the source was [successfully] enacted.
"All personnel involved acted as safely as possible considering the situation. The radiographer and their assistant immediately established a restricted area around the source and maintained visual surveillance of the area. At no time was any member of the public exposed to greater than 2 mR/hr. The three technicians involved with the monitoring and retrieval of the source followed company procedures and all were wearing the required radiation PPE. No one received a dose greater than 100 mrem during the entire operation. Film badge readings for the period were all within normal range." |
| Power Reactor | Event Number: 52344 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [ ] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: FATRI IBRAHIMI
HQ OPS Officer: DONALD NORWOOD | Notification Date: 11/03/2016
Notification Time: 08:54 [ET]
Event Date: 11/03/2016
Event Time: 03:00 [EDT]
Last Update Date: 11/03/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
DAN SCHROEDER (R1DO)
BERNARD STAPLETON (IRD)
|
| 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 SERVICE WATER LEAK IDENTIFIED IN THE VAPOR CONTAINMENT BUILDING
"At 0300 EDT on November 3, 2016, it was identified that a Service Water leak existed in the Vapor Containment Building of Indian Point Unit 3. The leak was determined to be from 31 Fan Cooler Unit and was subsequently isolated at 0344 EDT by shutting the Service Water isolation valves to 31 Fan Cooler Unit. This isolation meets the Technical Specification 3.6.1 Condition A Required Action. The leaking defect could have resulted in post-LOCA air leakage out of containment in excess of that allowed by Technical Specification 3.6.1 (Containment) which requires leakage rates to comply with 10 CFR 50, Appendix J. This event had no effect on the health and safety of the public.
"This event is being reported under 10 CFR 50.72(b)(3) and the guidance of NUREG 1022, section 3.2.7 as a loss of safety function."
The licensee notified the NRC Resident Inspector. | |