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Event Notification Report for June 4, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
06/03/2014 - 06/04/2014

** EVENT NUMBERS **


50144 50164 50165 50166 50168 50169 50170

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Agreement State Event Number: 50144
Rep Org: TEXAS DEPARTMENT OF HEALTH
Licensee: GLOBAL X-RAY AND TESTING CORPORATION
Region: 4
City: ARANSAS PASS State: TX
County:
License #: L03663
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: VINCE KLCO
Notification Date: 05/27/2014
Notification Time: 16:22 [ET]
Event Date: 04/25/2014
Event Time: [CDT]
Last Update Date: 05/27/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL VASQUEZ (R4DO)
FSME RESOURCES (EMAI)
WILLIAM GOTT (IRD)
MATTHEW HAHN (ILTA)

This material event contains a "Category 2 " level of radioactive material.

Event Text

AGREEMENT STATE REPORT - STOLEN AND FOUND RADIOGRAPHY CAMERA

The following information was received from the State of Texas by email:

"On May 19, 2014, the Agency [Texas Department of State Health Services] received a complaint alleging multiple rule violations had been committed by an industrial radiographer working for the licensee. On May 27, 2014, during the complaint investigation, the licensee's site radiation safety officer (SRSO) stated that on April 25, 2014, the radiographer had taken one of the licensee's radiography trucks which contained a SPEC 150 exposure device with a 23 curie iridium-192 source following completion of a job in San Antonio, Texas. The radiographer had possession of the truck and exposure device with its source until April 30, 2014. The licensee's SRSO stated they attempted during that time to contact the radiographer and to locate the truck using its GPS locator system, but they were unsuccessful. The licensee located the truck at a recreational vehicle park in Portland, Texas. The licensee's SRSO stated the exposure device was found laying in the floor of the dark room, the dark room door was not locked, and the dark room's alarm was not activated. The SRSO stated to the Agency investigator during the May 27th telephone interview that it did appear to him that an exposure could have resulted to persons in an unrestricted area during the event. An investigation into this event is ongoing and more information will be provided as it is obtained in accordance with SA-300."

Texas Incident: I-9196

THIS MATERIAL EVENT CONTAINS A "CATEGORY 2" LEVEL OF RADIOACTIVE MATERIAL

Category 2 sources, if not safely managed or securely protected, could cause permanent injury to a person who handled them, or were otherwise in contact with them, for a short time (minutes to hours). It could possibly be fatal to be close to this amount of unshielded radioactive material for a period of hours to days. These sources are typically used in practices such as industrial gamma radiography, high dose rate brachytherapy and medium dose rate brachytherapy. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf

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Power Reactor Event Number: 50164
Facility: VERMONT YANKEE
Region: 1 State: VT
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BENJAMIN EGNEW
HQ OPS Officer: DANIEL MILLS
Notification Date: 06/03/2014
Notification Time: 06:42 [ET]
Event Date: 04/05/2014
Event Time: 07:00 [EDT]
Last Update Date: 06/03/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
PAUL KROHN (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

Event Text

INVALID PRIMARY CONTAINMENT ISOLATION SYSTEM ACTUATION

"This notification is being made in accordance with 10 CFR 50.73 (a)(2)(iv)(A) to provide information pertaining to an invalid Primary Containment Isolation System (PCIS) Group 3 actuation signal that affected containment valves in more than one system.

"On April 5, 2014, with the reactor at 100% power, an invalid PCIS Group 3 actuation occurred from a momentary spike of the 'A' Refuel Floor radiation monitor which reached the instrument's high radiation trip set point. A radiation protection technician was dispatched to the refuel floor and dose rates in the vicinity of the 'A' radiation monitor detector were verified to be normal and below the alarm set points. The radiation monitor was verified to be indicating normal expected radiation levels. The detector was replaced, a functional check and calibration of the radiation monitor was completed satisfactory and the instrument channel was returned to service. The issue has been entered into the station's corrective action program.

"Both trains of Standby Gas Treatment System started as designed and Reactor Building ventilation isolated as a result of the invalid PCIS actuation.

"The PCIS functioned successfully, providing a complete Group 3 isolation. PCIS Group 3 involves the following system isolation valves:

"Drywell and Suppression Chamber Air and Vent: V16-19-6, 6A, 6B, 7, 7A, 7B, 8, 9, 10, 23
"Containment Makeup: V-16-20-20, 22A, 22B
"Containment Air Sampling: VG-23, 26, V109-76A, 76B
"Containment Air Compressor Suction: V72-38A, 38B
"Containment Air Dilution: VG-9A, 9B, 22A, 22B, NG-11A, 11B, 12A, 12B, 13A, 13B

"Since no actual high radiation condition existed which required the PCIS Group 3 isolation, and the actuation was not in response to actual plant conditions satisfying the requirements for isolation, this event has been classified as an invalid actuation.

"This event did not result in any adverse impact to the health and safety of the public.

"In accordance with 10 CFR 50.73(a)(1) a telephone notification is being made instead of submitting a written Licensee Event Report. The licensee has notified the NRC resident inspector."

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Power Reactor Event Number: 50165
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: VINCE WESSLING
HQ OPS Officer: CHARLES TEAL
Notification Date: 06/03/2014
Notification Time: 13:41 [ET]
Event Date: 06/03/2014
Event Time: 09:33 [EDT]
Last Update Date: 06/03/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
PAUL KROHN (R1DO)

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 RANGE STACK MONITOR TAKEN OUT OF SERVICE FOR PLANNED MAINTENANCE

At 0933 EDT, Millstone Station Unit 2 removed the Stack High Range Radiation Monitor RM-8168 from service for planned maintenance. Maintenance and testing were completed and the Stack Radiation Monitor returned to service at 1252 EDT.

The licensee informed both State and local agencies and the NRC Resident Inspector.

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Power Reactor Event Number: 50166
Facility: WATTS BAR
Region: 2 State: TN
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JIM O'DELL
HQ OPS Officer: CHARLES TEAL
Notification Date: 06/03/2014
Notification Time: 14:15 [ET]
Event Date: 06/03/2014
Event Time: [EDT]
Last Update Date: 06/03/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.55(e) - CONSTRUCT DEFICIENCY
Person (Organization):
SCOTT FREEMAN (R2DO)
OMID TABABAI (NRO)
PART 21/50.55 GROUP (EMAI)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Under Construction 0 Under Construction

Event Text

WATTS BAR UNIT 2 POTENTIALLY DEFECTIVE FUSES INSTALLED

"WBN [Watts Bar Nuclear] Unit 2 (under construction) determined that Littelfuse Part Number FLAS005.T fuses manufactured under three date codes are potentially susceptible to nuisance opening according to Littelfuse letter dated April 30, 2014. Littelfuse Part Number FLAS005.T fuses are commercial grade and dedicated by TVA for use as a basic component in safety related systems. No confirmed examples have been identified that would have created a substantial safety hazard at this time. The potentially defective fuses were purchased for WBN Unit 2 and have been installed on WBN Unit 2 only. No potentially defective fuses have been installed on WBN Unit 1, SQN [Sequoyah] Units 1 or 2, or BFN [Browns Ferry Nuclear] Units 1, 2, or 3. At this time, there is no safety significance because fuel has not been loaded on WBN Unit 2. Installed and potentially defective Part Number FLAS005.T fuses will be replaced prior to obtaining a WBN Unit 2 Operating License. This issue has been documented in TVA's corrective action program as Problem Evaluation Report 878252 and is being conservatively reported by WBN Unit 2 under 10 CFR 50.55(e)."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 50168
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MICHAEL SOCHA
HQ OPS Officer: CHARLES TEAL
Notification Date: 06/03/2014
Notification Time: 15:40 [ET]
Event Date: 06/03/2014
Event Time: 12:59 [EDT]
Last Update Date: 06/03/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
PAUL KROHN (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N Y 60 Power Operation 60 Power Operation

Event Text

HIGH AND LOW RANGE VENTILATION PROCESS RADIATION MONITOR PRE-PLANNED MAINTENANCE

At 1259 EDT, Millstone Station Unit 3 removed the High and Low Range Ventilation Process Radiation Monitors from service for planned maintenance. The radiation monitor is expected to be out of service for approximately less than 24 hours. Compensatory measures are in place.

The licensee informed both State and local agencies and the NRC Resident Inspector.

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Power Reactor Event Number: 50169
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: TYLER ROBESON
HQ OPS Officer: CHARLES TEAL
Notification Date: 06/03/2014
Notification Time: 20:06 [ET]
Event Date: 06/03/2014
Event Time: 16:50 [EDT]
Last Update Date: 06/03/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
SCOTT FREEMAN (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

OFFSITE NOTIFICATION DUE TO SPILL OF TREATED DOMESTIC WATER

"At approximately 4:50 PM EDT on June 3, 2014 Duke Energy personnel notified the North Carolina Department of Environment and Natural Resources of a spill of treated domestic waste water. The waste water was released through a valve onto the surrounding ground and may have entered the plant's storm drain system. The release has been stopped. An investigation is in progress to determine the cause and additional corrective actions.

"There is no impact to public health and safety or the environment due to this incident.

"This event is reportable per 10 CFR 50.72(b)(2)(xi), an event related to protection of the environment for which a notification to other government agencies has been made.

"The NRC Resident Inspector has been notified."

The gray water was dripping from a valve onto the ground. The total quantity of the seepage is unknown.

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Power Reactor Event Number: 50170
Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: DARRELL LAPCINSKI
HQ OPS Officer: CHARLES TEAL
Notification Date: 06/03/2014
Notification Time: 23:22 [ET]
Event Date: 06/03/2014
Event Time: 19:02 [CDT]
Last Update Date: 06/03/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
ANN MARIE STONE (R3DO)

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

DIESEL GENERATORS DECLARED INOPERABLE DUE TO NOT MEETING HIGH ENERGY LINE BREAK REQUIREMENTS

"D1 and D2 Emergency Diesel Generators (DG) were declared inoperable at 1902 CDT due to the station identifying that the Turbine Building HELB [High Energy Line Break] heatup analysis temperature of 270 F exceeded the maximum temperature limit of 200 F for both diesel generators supply and exhaust fan blade positioners.

"LCO 3.8.1 Condition B was entered for both DGs and LCO 3.8.1 Condition E was entered for two DGs inoperable on the same unit. The DGs could start and run if required at the time of entry.

"This condition is reportable per 10 CFR 50.72(b)(3)(v) as an event or condition that could have prevented the fulfillment of a safety function.

"Unit 1 continued to operate in Mode 1 at 100% power while bypasses were being put in-service to fail the diesel generators supply and exhaust fan blade positioners in the full cooling mode to allow the LCO conditions to be exited.

"At 2002 CDT the bypasses were installed on the D1 Diesel Generator Supply and Exhaust Fan Blade Positioners therefore LCO 3.8.1 Condition E was exited for both D1 and D2 Emergency Diesel Generators being inoperable. In addition LCO 3.8.1 Condition B was exited for D1 Diesel Generator due to it being declared Operable.

"At 2056 CDT the bypasses were installed on the D2 Diesel Generator Supply and Exhaust Fan Blade Positioners therefore LCO 3.8.1 Condition B was exited for D2 Diesel Generator due to it being declared Operable.

"At no time was the health and safety of the public threatened.

"The Senior NRC Resident has been notified."

Page Last Reviewed/Updated Wednesday, June 04, 2014
Wednesday, June 04, 2014