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Event Notification Report for January 7, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
01/06/2014 - 01/07/2014

** EVENT NUMBERS **


49680 49692 49693 49694 49697 49698

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Agreement State Event Number: 49680
Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: DEL-TIN FIBER, LLC
Region: 4
City: EL DORADO State: AR
County:
License #: ARK-0874-0312
Agreement: Y
Docket:
NRC Notified By: TAMMY KRIESEL
HQ OPS Officer: DONG HWA PARK
Notification Date: 12/30/2013
Notification Time: 12:04 [ET]
Event Date: 12/27/2013
Event Time: [CST]
Last Update Date: 12/30/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GEOFFREY MILLER (R4DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - GAUGE SHUTTER FAILURE

The following information was received via email from Arkansas Department of Health:

"The licensee notified the [Arkansas] Department [of Health] on December 27, 2013 via email that a Ronan source holder model SA1-F37 shutter failed. The source holder serial number is M4785, and the source contains 100 mCi of Cesium-137. The problem was discovered during shutter checks. [According to the licensee], it appears the shutter handle is spinning on the shaft that rotates [to] open [and] close the shutter. [This] may be a result of a sheared pin that connects the handle to the shaft. Per the RSO, the gauge is still in use, and there have been no exposures to employees or members of the public. The RSO has notified applicable facility personnel.

"The licensee indicated the manufacturer was contacted on December 27, 2013 and repairs should be performed the week of January 6th-13th.

"The State of Arkansas is awaiting a written report after repairs. The State's event number is ARK-2013-013."

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Power Reactor Event Number: 49692
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JIM KURAS
HQ OPS Officer: CHARLES TEAL
Notification Date: 01/06/2014
Notification Time: 06:56 [ET]
Event Date: 01/06/2014
Event Time: 03:30 [CST]
Last Update Date: 01/06/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
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

LOSS OF THREE EMERGENCY PLAN SIRENS

"While operating in Mode 1 at 100% rated thermal power, the City of Burlington Kansas emergency dispatch center notified Wolf Creek Nuclear Operating Corporation (WCNOC) Security that two emergency plan sirens in Burlington, Kansas and one emergency plan siren in New Strawn, Kansas failed to function when they were actuated to call out a local fire response . These three sirens also function as part of the Emergency Plan Alert and Notification System. WCNOC Emergency Plan personnel have been notified of the three siren failures and the cause is under investigation.

"Wolf Creek Generating Station (WCGS) remains at 100% rated thermal power.

"The WCGS NRC Resident [Inspector] has been notified and local government."

* * * UPDATE AT 1408 EST ON 01/06/14 FROM PIERCE MOORE III TO JEFF ROTTON * * *

"At 0922 CST, the three sirens were returned service.

"WCGS NRC Resident has been notified. "

Notified R4DO (Hagar).

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Power Reactor Event Number: 49693
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [ ] [3]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: TODD FISHER
HQ OPS Officer: CHARLES TEAL
Notification Date: 01/06/2014
Notification Time: 10:09 [ET]
Event Date: 01/06/2014
Event Time: 08:51 [EST]
Last Update Date: 01/06/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
WAYNE SCHMIDT (R1DO)

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

Event Text

RADIATION MONITOR TAKEN OUT OF SERVICE FOR PLANNED MAINTENANCE

"The Supplementary Leakage Collection and Release System ventilation process flow radiation monitor 3HVR*RE19A has been removed from service for pre-planned maintenance. The monitor will be returned to service after maintenance is complete."

The NRC Resident Inspector, state, and local agencies have been informed.

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Power Reactor Event Number: 49694
Facility: COOPER
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: BRIAN HASSELBRING
HQ OPS Officer: CHARLES TEAL
Notification Date: 01/06/2014
Notification Time: 10:31 [ET]
Event Date: 01/06/2014
Event Time: 02:45 [CST]
Last Update Date: 01/06/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
BOB HAGAR (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

SECONDARY CONTAINMENT DIFFERENTIAL PRESSURE EXCEEDED TECHNICAL SPECIFICATION

"At 0245 CST secondary containment differential pressure exceeded the Technical Specifications limit due to a personnel error manipulating an incorrect component. This caused entry into LCO 3.6.4.1 for secondary containment inoperability. An event or condition that could have prevented fulfillment of a safety function requires an 8 hour report per 10CFR50.72(b)(3)(v)(C) for Control of Rad Release and 10CFR50.72(b)(3)(v)(D) for Accident Mitigation. The error was corrected and secondary containment pressure was restored to greater than or equal to 0.25 inch vacuum water gauge and secondary containment was declared operable at 0302 CST. The NRC Resident has been informed of this condition."

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Power Reactor Event Number: 49697
Facility: BEAVER VALLEY
Region: 1 State: PA
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DAVE GIBSON
HQ OPS Officer: JEFF ROTTON
Notification Date: 01/06/2014
Notification Time: 19:09 [ET]
Event Date: 01/06/2014
Event Time: 16:59 [EST]
Last Update Date: 01/06/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
WAYNE SCHMIDT (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP DUE TO MAIN TRANSFORMER FAULT

"At 1659 EST hours on January 6, 2014, Beaver Valley Power Station Unit 1 automatically tripped from 100% power. The cause of the reactor trip was a main transformer differential trip. All rods fully inserted into the core and the plant is stable in Mode 3. All three auxiliary feedwater pumps automatically started as expected. Normal and Emergency Busses are being powered by Offsite Power. The cause of the main transformer differential trip is being investigated. All other equipment functioned as expected. At 1757 EST hours the Emergency Operating Procedures were exited.

"Resident inspector has been notified."

Decay heat is being removed via the turbine bypass valves to the condenser. No primary or secondary safety valves lifted. Unit 2 was unaffected.

Licensee notified the States of Pennsylvania, Ohio, and West Virginia and the Counties of Beaver, PA, Hancock, OH, and Columbiana, OH.

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Power Reactor Event Number: 49698
Facility: INDIAN POINT
Region: 1 State: NY
Unit: [ ] [3] [ ]
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: GEORGE KELLER
HQ OPS Officer: STEVE SANDIN
Notification Date: 01/06/2014
Notification Time: 21:55 [ET]
Event Date: 01/06/2014
Event Time: 21:15 [EST]
Last Update Date: 01/06/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
WAYNE SCHMIDT (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
3 A/R Y 100 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP ON LOW STEAM GENERATOR WATER LEVEL DUE TO A FAILED MAIN FEEDWATER REG VALVE

"On January 6th, 2014 at 2115 EST Indian Point Unit 3 experienced an Automatic Reactor Trip due to '33 Steam Generator Steam flow/Feed flow Mismatch.' Operators entered emergency procedure E-0, Reactor Trip or Safety Injection. All control rods fully inserted, all safety systems responded as expected, and off-site power remained in-service. No primary or secondary safety valves actuated due to the trip. This is reportable under 10CFR50.72(b)(2)(iv)(B). The main condenser is being used for heat sink. Unit 2 remains stable at 100% power.

The Auxiliary Feedwater System actuated following the automatic trip as expected. This is reportable under 10CFR50.72(b)(3)(iv)(A).

"Investigation is underway to determine the cause of the 33 Steam Generator Mismatch condition."

The licensee will inform local and other government agencies and issue a press release. The licensee has informed the State of New York and the NRC Resident Inspector.

Page Last Reviewed/Updated Wednesday, May 14, 2014
Wednesday, May 14, 2014