| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
07/05/2016 - 07/06/2016 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 51911 | Rep Org: ALABAMA RADIATION CONTROL
Licensee: MILLENNIUM RESOURCES, LLC
Region: 1
City: GRAYSVILLE State: AL
County:
License #: G/L
Agreement: Y
Docket:
NRC Notified By: MYRON K. RILEY
HQ OPS Officer: HOWIE CROUCH | Notification Date: 05/06/2016
Notification Time: 10:24 [ET]
Event Date: 05/06/2016
Event Time: 09:15 [CDT]
Last Update Date: 07/05/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
FRED BOWER (R1DO)
NMSS_EVENTS_NOTIFIC (EMAI)
|
| This material event contains a "Less than Cat 3 " level of radioactive material. | Event Text ALABAMA AGREEMENT STATE REPORT - LOST GENERALLY LICENSED PROCESS GAUGE
The following information was obtained from the State of Alabama via facsimile:
"On May 5, 2016, it was determined that Millennium Resources, LLC, Graysville, Alabama had lost control and possession of a generally licensed device (Ronan SA1-C5 #2255GO containing 5 mCi of Cs-137).
"During a requested visit by the new owner Cane Creek, LLC on April 7, 2016, it was determined that they possessed a new generally licensed device. The new owners only knew that the site once contained a similar plant which contained a device with radioactive material. The old plant was constructed in 1997, and our [Alabama Department of Public Health - Office of Radiation Control] records show that device being received by Millennium Resources, LLC on November 14, 1997. The plant was torn down and sold for scrap during the year of 2006. The new owners had no information in regards to whom the scrap was sold or the whereabouts of the device.
"On April 7, 2016, the Agency [Alabama Department of Public Health - Office of Radiation Control] contacted Ronan and their records indicated no transfer for disposal. During the next few weeks, several calls were made to the Alabama Department of Environmental Management and the Alabama Surface Mining Commission to determine if any new information could be obtained. None of the representatives could provide any additional information.
"As of today [5/6/16], 0915 CDT, the device containing radioactive material has not been recovered. This incident remains open until further investigation can be completed."
Alabama Incident 16-15
* * * UPDATE FROM MYRON RILEY TO VINCE KLCO ON 7/5/2106 AT 1257 EDT * * *
The following information was received from the State of Alabama via facsimile:
"SUBJECT: Update - Lost Gauge Containing Radioactive Material - Alabama Incident 16-15
"On May 5, 2016, it was determined that Millennium Resources, LLC, Graysville, Alabama had lost control and possession of a generally licensed device (Ronan SA1-C5 #2255GO containing 5 mCi of Cs-137).
"On April 7, 2016, the Agency contacted Ronan and there records indicated no transfer for disposal. During the next few weeks, several calls were made to the Alabama Department of Environmental Management and the Alabama Surface Mining Commission to determine if any new information could be obtained. None of the representatives could provide any additional information.
"On June 9, 2016, the Agency could not determine any information on the whereabouts of the Ronan device from manufacturers, service companies, waste brokers or past employees. As of today, [1245 CDT], the device containing radioactive material has not been recovered."
Notified the R1DO (Bower) and NMSS Events 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 |
| Research Reactor | Event Number: 52062 | Facility: U. S. GEOLOGICAL SURVEY
RX Type: 1000 KW TRIGA MARK I
Comments:
Region: 0
City: DENVER State: CO
County: DENVER
License #: R-113
Agreement: Y
Docket: 05000274
NRC Notified By: TIM DEBEY
HQ OPS Officer: JEFF HERRERA | Notification Date: 07/05/2016
Notification Time: 14:56 [ET]
Event Date: 07/01/2016
Event Time: 09:14 [MDT]
Last Update Date: 07/05/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
RESEARCH AND TEST REACTOR EVENT
| Person (Organization):
GEOFF WERTZ (RTR)
ANTHONY MENDIOLA (EMAI)
| Event Text USGS RESEARCH REACTOR SCRAM DUE TO ONE OF THREE POWER INSTRUMENTS NOT FUNCTIONING
"At 0914 MDT on 7/1/16, a routine GSTR [Geological Survey TRIGA Reactor] startup and ascent to 900 kW was initiated after successful completion of the daily prestart checks and an excess reactivity check. At 0919 as power was passing through approximately 50 kW, it was clear to the operator that one of the three power instruments (the NP1000) was not functioning since it was still reading 0 percent when it should have been reading >5 percent. The reactor was scrammed, Reactor Supervisor notified, and troubleshooting commenced. Shortly after this, the NP1000 signal cable was found to have an intermittent connection through a tee connector that was installed at the instrument box. The connector was replaced to resolve the problem and tested satisfactorily. At 1050 the reactor was started up again. All power instrumentation operated correctly and the daily power operation was performed without further problems.
"The NP1000 is a required safety instrument for operation of the reactor, so malfunction of the instrument is a violation of the facility's Technical Specifications.
"Specifically, Specification E.7 states: 'The type and minimum number of safety systems which shall be operable for reactor operation are shown in Table I.' Table I requires the NP1000 to provide a high power scram at 110 percent power, but the connector problem would have prevented a high power scram from occurring in that instrument."
The licensee notified the NRC Project Manager and the NRC SME (Subject Matter Expert) for Research and Test Reactors. |
| Power Reactor | Event Number: 52064 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MICHAEL NAYLOR
HQ OPS Officer: VINCE KLCO | Notification Date: 07/05/2016
Notification Time: 20:01 [ET]
Event Date: 07/05/2016
Event Time: 16:40 [EDT]
Last Update Date: 07/05/2016 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
MARVIN SYKES (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text HIGH PRESSURE COOLANT INJECTION (HPCI) SYSTEM DECLARED INOPERABLE
"On July 5, 2016, at 1640 Eastern Daylight Savings Time (EDT) the Unit 2 HPCI system was declared inoperable due to apparent failure of the HPCI Auxiliary Oil Pump after the 'HPCI Aux Oil Pump Motor Overload' control room annunciator was received. Failure of the HPCI Auxiliary Oil Pump prevents the HPCI system from performing its design safety function. As such, this event is being reported in accordance with 10 CFR 50.72(b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfillment of the safety function of a system that is needed to mitigate the consequences of an accident.
"This event did not result in any adverse impact to the health and safety of the public.
"The NRC Senior Resident Inspector has been notified.
"The safety significance of this condition is minimal. All other Emergency Core Cooling Systems and the Reactor Core Isolation Cooling (RCIC) system remain operable.
"Troubleshooting activities are in progress. The HPCI system will remain inoperable until the cause of the failure has been corrected." |
| Power Reactor | Event Number: 52065 | Facility: COOK
Region: 3 State: MI
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRANDY WARK
HQ OPS Officer: DONG HWA PARK | Notification Date: 07/06/2016
Notification Time: 01:02 [ET]
Event Date: 07/06/2016
Event Time: 00:38 [EDT]
Last Update Date: 07/06/2016 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
PATTY PELKE (R3DO)
CHRIS MILLER (NRR)
BILL GOTT (IRD)
CYNTHIA PEDERSON (R3RA)
BILL DEAN (NRR)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP AND UNUSUAL EVENT DECLARATION DUE TO STEAM LEAK IN TURBINE BUILDING
"On July 6, 2016, at 0038 [EDT], DC Cook Unit 2 Reactor was manually tripped and at 0050 [EDT] an Unusual Event (N-7 'Unanticipated Explosion') Emergency Declaration was made due to steam leak and associated damage to the turbine building.
"In accordance with Emergency Plan procedures, notifications of Berrien County and State of Michigan were completed. The licensee has notified the NRC Senior Resident Inspector. The Unusual Event was terminated at 0207 [EDT].
"This notification is being made in accordance with 10 CFR 50.72 (a)(1)(i) due to declaration of an emergency class. Original notification to NRC made at 0100 EDT via ENS. This event is reportable under 10 CFR 50.72(b)(2)(iv)(B), Reactor Protection System (RPS) actuation and 10 CFR 50.72(b)(2)(xi) Offsite Notification, as a four (4) hour report, and under 10 CFR 50.72(b)(3)(iv)(A), specified system actuation of the Auxiliary Feedwater System, as an eight (8) hour report. The DC Cook NRC Resident Inspector has been notified. Press release is planned.
"Unit 2 is being supplied by offsite power. All control rods fully inserted. Decay heat is being removed via Steam Generator PORVs [Power Operated Relief Valve]. Preliminary evaluation indicates all plant systems functioned normally following the Reactor Trip. DC Cook Unit 2 remains stable in Mode 3 while conducting the Post Trip Review. No radioactive release is in progress as a result of this event."
Notified DHS SWO, FEMA Ops Center, DHS NICC. Notified FEMA National Watch and Nuclear SSA via email. | |