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Event Notification Report for July 21, 2016

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
07/20/2016 - 07/21/2016

** EVENT NUMBERS **


52081 52096 52107 52113

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Agreement State Event Number: 52081
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: METRIC ENGINEERING
Region: 1
City: MIAMI State: FL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: KELLIE ANDERSON
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/12/2016
Notification Time: 16:41 [ET]
Event Date: 07/12/2016
Event Time: [EDT]
Last Update Date: 07/12/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MARC FERDAS (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)

This material event contains a "Less than Cat 3 " level of radioactive material.

Event Text

AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE

A Troxler moisture density gauge was stolen overnight from a locked overpack in a truck. The gauge contained both Am-241 and Cs-137 sources. The licensee contacted local law enforcement. Gauge serial number: 34700

Florida Incident: FL16-079

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

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Power Reactor Event Number: 52096
Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [1] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: JAMES REVELLE
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/18/2016
Notification Time: 14:48 [ET]
Event Date: 07/18/2016
Event Time: 07:30 [EDT]
Last Update Date: 07/20/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MARC FERDAS (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 100 Power Operation
2 N Y 100 Power Operation 100 Power Operation

Event Text

LOSS OF OFFSITE COMMUNICATIONS CAPABILITY

"This 8-hour non-emergency report is being made based upon requirements of 10 CFR 50.72(b)(3)(xiii) which states, 'The licensee shall notify the NRC as soon as practical and in all cases within eight hours of the occurrence of any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g., significant portion of control room indication, Emergency Notification System, or offsite notification system).'

"On 07-18-2016 at 0730 [EDT], both Control Rooms were notified by the Emergency Preparedness Manager, that the Everbridge Emergency Response Organization [ERO] Notification System may not notify all ERO individuals within the required 10 minutes of system initiation. This constitutes a loss of offsite communications capability. The Everbridge vendor is working to resolve the issue. Compensatory measures are in place."

All ERO personnel received the page but not all received the notification within the required ten minutes.

The licensee notified the NRC Resident Inspector and the State.

* * * UPDATE AT 1728 EDT ON 7/20/2016 FROM CLARK WILLETT TO MARK ABRAMOVITZ * * *

"The Everbridge System was restored and retested at 1930 EDT on 7-19-2016 to provide offsite communications capability."

The licensee notified the NRC Resident Inspector and the state.

Notified the R1DO (DeFrancisco).

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Power Reactor Event Number: 52107
Facility: DRESDEN
Region: 3 State: IL
Unit: [ ] [2] [3]
RX Type: [1] GE-1,[2] GE-3,[3] GE-3
NRC Notified By: SCOTT BRILEY
HQ OPS Officer: DONALD NORWOOD
Notification Date: 07/20/2016
Notification Time: 12:02 [ET]
Event Date: 07/20/2016
Event Time: 11:30 [CDT]
Last Update Date: 07/20/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ANN MARIE STONE (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 100 Power Operation 100 Power Operation
3 N Y 100 Power Operation 100 Power Operation

Event Text

TECHNICAL SUPPORT CENTER VENTILATION OUT-OF-SERVICE FOR PLANNED PREVENTATIVE MAINTENANCE

"At 1130 CDT on Wednesday, July 20, 2016, the Dresden Nuclear Power Station (DNPS) Technical Support Center (TSC) emergency ventilation system will be removed from service for planned maintenance activities. During the maintenance, the TSC ventilation will be shut down. The TSC air filtration fan and dampers will be non-functional, rendering the TSC HVAC accident mode non-functional. This maintenance is scheduled to minimize out-of-service time. The planned TSC ventilation outage is scheduled to be completed in approximately 14 hours.

"Contingency plans are in place so that if an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing Emergency Planning (EP) procedures and checklists. If radiological or environmental conditions require TSC facility evacuation during ventilation system restoration, the Station Emergency Director will relocate the TSC staff in accordance with station procedures."

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 52113
Facility: BROWNS FERRY
Region: 2 State: AL
Unit: [1] [ ] [ ]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: DAVID RENN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/20/2016
Notification Time: 20:33 [ET]
Event Date: 07/20/2016
Event Time: 12:45 [CDT]
Last Update Date: 07/20/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
REBECCA NEASE (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

HIGH PRESSURE COOLANT INJECTION INOPERABLE

"On 07/20/2016 at 1245 CDT, the Browns Ferry Nuclear Plant Unit 1 High Pressure Coolant Injection (HPCI) Steam Line Inboard Isolation Valve was declared inoperable.

"HPCI was declared inoperable at 0300 CDT on 7/18/2016 when it was taken out of service for planned maintenance. A 14 day LCO [Limiting Conditions for Operation] was entered and will expire at 0300 CDT on 8/1/2016.

"HPCI was being returned to service after the planned maintenance period. The inboard isolation valve and the bypass around the outboard isolation valve were open to warm and pressurize the HPCI steam line. HPCI steam line pressure stabilized at approximately 50 psig. The outboard isolation valve was slowly opened to determine if the inboard isolation valve was actually open. There was no change in steam line pressure or indications of flow at the valves. Based on this information, the HPCI Steam Line Inboard Isolation Valve was declared inoperable for its Primary Containment Isolation function. The appropriate Technical Specification Limiting Conditions for Operation (LCOs) were entered and the HPCI steam line was isolated.

"This constitutes an unplanned HPCI system inoperability and requires an 8 hour ENS notification in accordance with 10 CFR 50.72(b)(3)(v)(D), due to the failure of a single train system affecting accident mitigation and a 60 day written report in accordance with 10 CFR 50.73(a)(2)(v)(D).

"The Senior NRC Resident Inspector has been notified."

Page Last Reviewed/Updated Thursday, July 21, 2016
Thursday, July 21, 2016