| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/14/2015 - 10/16/2015 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 51327 | Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: UNKNOWN
Region: 1
City: JERSEY CITY State: NJ
County:
License #:
Agreement: Y
Docket:
NRC Notified By: JAMES McCOLLOUGH
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 08/18/2015
Notification Time: 12:15 [ET]
Event Date: 08/15/2015
Event Time: [EDT]
Last Update Date: 10/15/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
ANNE DeFRANCISCO (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - ORPHAN SOURCE FOUND IN A GARBAGE TRUCK
"A garbage truck containing a radioactive source was reported by local police in Union City, NJ. NJ State police preliminarily identified Ra-226, which was confirmed by NJDEP Radiation Program staff who responded to the event. Exposure rate was measured as 60 mR/hr on contact on the truck. Based on measurements, activity was estimated to be 10 mCi. The US DOT was contacted, and approved issuance of a DOT Special Permit 11406 even though readings exceeded 50 mR/hr. Truck was moved to truck owner's (Galaxy Sanitation) location in Jersey City, NJ., where the hired contractor sorted the load and found a small radium source. No identifying information was on the source. It has been adequately shielded and secured at the site pending disposal.
"NJDEP will continue to monitor the situation and provide updates as necessary."
The garbage truck made a pickup in Union City, New Jersey and was stopped by the police because the truck was leaking liquid. As the officer approached the truck, his paging radiac alarmed.
New Jersey Incident: C569188
* * * UPDATE PROVIDED BY JAMES MCCULLOUGH TO JEFF ROTTON AT 1607 EDT ON 10/15/2015 * * *
The following information was provided by the State of New Jersey via email:
Consultant was able to reduce the surface exposure rate below 50 Mr/hr so that the DOT Special Permit 11406 could be issued. The item was removed from the site by a licensed waste broker on 8/25/2015.
Notified R1DO (Jackson) and NMSS Events Notification group via email. |
| Fuel Cycle Facility | Event Number: 51471 | Facility: B&W NUCLEAR OPERATING GROUP, INC.
RX Type: URANIUM FUEL FABRICATION
Comments: HEU FABRICATION & SCRAP
Region: 2
City: LYNCHBURG State: VA
County: CAMPBELL
License #: SNM-42
Agreement: N
Docket: 070-27
NRC Notified By: DAVE SPANGLER
HQ OPS Officer: JEFF ROTTON | Notification Date: 10/15/2015
Notification Time: 15:26 [ET]
Event Date: 10/15/2015
Event Time: 08:30 [EDT]
Last Update Date: 10/15/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
JONATHAN BARTLEY (R2DO)
NMSS_EVENTS_NOTIFIC (EMAI)
| Event Text ALCOHOL DISCOVERED INSIDE THE PROTECTED AREA
On October 15, 2015 at approximately 0830 EDT, BWXT NOG-L Security management determined alcohol had been introduced into the Protected Area. The item in question was a single bottle of beer which was identified amongst the personal items on display in a contracted employee's office.
BWXT Security Management contacted the Fitness for Duty Coordinator, who escorted the bottle of beer out of the Protected Area.
BWXT NOG-L Management will conduct an evaluation of the incident to include root cause analysis and corrective actions to prevent recurrence.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 51472 | Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: NATHAN BLANTON
HQ OPS Officer: STEVE SANDIN | Notification Date: 10/15/2015
Notification Time: 20:54 [ET]
Event Date: 10/15/2015
Event Time: 15:54 [EDT]
Last Update Date: 10/15/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
JONATHAN BARTLEY (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text TECHNICAL SUPPORT CENTER VENTILATION SYSTEM OUT OF SERVICE DUE TO DISCOVERED CONDITION
"This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability. This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) as the discovered condition affects the functionality of an emergency response facility.
"A condition impacting functionality of the TSC Ventilation system was discovered on October 15, 2015 at 1554 EDT. The issue involved a loss of heating capability of the TSC Ventilation system due to failed ventilation system components. The review of the impact of this equipment failure on the habitability of the TSC over the 30 day mission time determined that this condition was reportable as a loss of emergency assessment capability. The repair of the equipment failure is currently being planned.
"If an emergency is declared requiring TSC activation during the non-functional period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the Emergency Director will relocate the TSC staff to an alternate location in accordance with applicable site procedures. This condition does not affect the health and safety of the public or station employees.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 51473 | Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: SEAN DUNFEE
HQ OPS Officer: JEFF ROTTON | Notification Date: 10/15/2015
Notification Time: 22:02 [ET]
Event Date: 10/14/2015
Event Time: 12:20 [CDT]
Last Update Date: 10/15/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
| Person (Organization):
GEOFFREY MILLER (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 | Event Text TWO CONTAINMENT ISOLATION VALVES NOT PROPERLY TESTED PER TECHNICAL SPECIFICATIONS
"At 1220 CDT on October 14, 2015, GGNS identified that in June 2013, testing of two containment isolation valves in a penetration were not tested in accordance with Technical Specification Surveillance Requirement 3.6.1.3.9. Specifically, the pressure used to demonstrate operability of the penetration did not meet the post-Extended Power Uprate expected highest Containment pressure during an accident.
"The valves were declared inoperable and isolated in accordance with Technical Specification 3.6.1.3, Primary Containment Isolation Valves (PCIVs) . Even though a reasonable assurance that the safety function could be met existed based on previous analysis and testing, the containment penetration was declared inoperable until appropriate testing could be completed to demonstrate operability. Testing of the penetration was completed at 1101 CDT on October 15, 2015 and demonstrated that both penetration valves were operable at the higher test pressure for the entire time period between June 2013 and October 15, 2015.
"In accordance with NUREG-1022, Event Reporting Guidelines 10 CFR 50.72 and 50.73, Section 3.2.7, Event or Condition that Could Have Prevented Fulfillment of a Safety Function, requires that when a signal train system is declared inoperable the condition must be reported under 10CFR 50.72(b)(3)(v)(C)."
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 51474 | Facility: MCGUIRE
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KEVIN BURIANEK
HQ OPS Officer: JEFF ROTTON | Notification Date: 10/15/2015
Notification Time: 22:18 [ET]
Event Date: 10/07/2015
Event Time: 06:55 [EDT]
Last Update Date: 10/15/2015 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
JONATHAN BARTLEY (R2DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | Hot Shutdown | 0 | Hot Shutdown | Event Text UNPLANNED AFW ACTUATION DURING REFUELING OUTAGE TESTING
"On October 7, 2015, with McGuire Nuclear Station Unit 2 in Mode 4, operators were testing the main turbine and main feedwater pump turbines, 2A safety injection (SI) train trip functions. At the time of the test, the 2A and 2B Auxiliary Feedwater (AFW) pumps were in operation to provide make-up to the steam generators. The main feedwater system was not in service. During realignment activities from the 2A Sl test, the 2A AFW train actuation signal was unblocked when the '2A AFW auto start defeat' switch was returned to 'reset.' This caused the 2A AFW train control valves to fully open, and the associated steam generator sampling and blowdown valves to close. The actuation occurred as designed and there was no adverse impact to the Unit. Public health and safety were not impacted by this event.
"Based on a review of the Event Reporting Guidelines and the plant licensing basis, this event was initially determined to be an invalid actuation. However, after further review and discussions with the NRC, Duke Energy concluded the event should be reported as an 8-hour non-emergency in accordance with 10 CFR 50.72 (b)(3)(iv)(A) as a valid actuation of the Auxiliary Feedwater System. A Nuclear Condition Report was initiated for the late notification.
"The NRC Resident Inspector has been notified." | |