Skip to main content

Event Notification Report for July 20, 2016

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
07/19/2016 - 07/20/2016

EVENT NUMBERS
52111521135210752109

Agreement State
Event Number: 52111
Rep Org: TENNESSEE DIV OF RAD HEALTH
Licensee: MANUFACTURING SCIENCES CORP.
Region: 1
City: OAK RIDGE   State: TN
County:
License #: S-01046-B20
Agreement: Y
Docket:
NRC Notified By: DEBRA SHULTS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/20/2016
Notification Time: 15:48 [ET]
Event Date: 07/20/2016
Event Time: 12:30 [EDT]
Last Update Date: 07/20/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
ANNE DeFRANCISCO (R1DO)
NMSS_EVENTS_NOTIFICA (EMAI)
Event Text
AGREEMENT STATE REPORT - LOSS OR THEFT OF DEPLETED URANIUM OXIDE

The following report was received via e-mail:

"On Monday, July 18, Manufacturing Sciences Corp. [MSC] shipped five pallets (18 drums) of product containing depleted uranium oxide [DU] to a customer, Clariant, in Louisville, KY. On Wednesday, July 20, the customer contacted MSC to report only four pallets containing 14 drums were received by Clariant. When the bill of lading was examined by the customer, 5 and 18 had been marked through by hand and changed to 4 and 14. The carrier, was contacted and is conducting a thorough search of its terminal and investigating to locate the missing material. The carrier is routinely used by MSC for transport of product. Total activity of missing material: 271,285 microcuries DU."

Tennessee Report: TN-16-100

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


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)
Power Reactor Unit Info
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."


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: 07/21/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ANN MARIE STONE (R3DO)
Power Reactor Unit Info
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."

* * * UPDATE FROM RYAN CHAMBERLAIN TO DANIEL MILLS ON 07/21/2016 AT 1757 EDT * * *

"At 1619 CST on July 21, 2016, Dresden TSC ventilation has been restored and is now functional."

The licensee has notified the NRC Resident Inspector

Notified R3DO (Stone).


Agreement State
Event Number: 52109
Rep Org: COLORADO DEPT OF HEALTH
Licensee: COLORADO SPRINGS II SILVERCREST APARTMENTS
Region: 4
City: COLORADO SPRINGS   State: CO
County:
License #: GL
Agreement: Y
Docket:
NRC Notified By: LINDA BARTISH
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 07/20/2016
Notification Time: 12:04 [ET]
Event Date: 07/20/2016
Event Time: 00:00 [MDT]
Last Update Date: 07/20/2016
Emergency Class: NON EMERGENCY
10 CFR Section:
Person (Organization):
MICHAEL VASQUEZ (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
Event Text
AGREEMENT STATE REPORT - LOST TRITIUM EXIT SIGNS

The following is a synopsis of information received via e-mail:

The current property manager for Colorado Springs II Silvercrest Apartments completed an inspection of the facility without locating any tritium exit signs in their buildings. Two fire safety companies provided safety signs over a period of 16 years and no tracking records were kept regarding the disposition of tritium exit signs or their disposal. The current fire safety company has no further information regarding the disposition of the exit signs.

Six Tritium Exit signs had been shipped from the manufacturer on 12/13/2000 to Colorado Springs II Silvercrest Apartments. Since these signs could not be located, they are being reported as lost. These six signs were manufactured by Safety Light Corporation, model number - 2040, serial numbers - unknown.

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