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Event Notification Report for February 12, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/11/2013 - 02/12/2013

** EVENT NUMBERS **


48740 48741 48743 48744

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Power Reactor Event Number: 48740
Facility: CLINTON
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: JAMES LUCAS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 02/11/2013
Notification Time: 12:59 [ET]
Event Date: 02/11/2013
Event Time: 07:56 [CST]
Last Update Date: 02/11/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
PATTY PELKE (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 97 Power Operation 97 Power Operation

Event Text

FITNESS FOR DUTY - CONFIRMED POSITIVE FFD TEST

A non-licensed, supervisory employee had a confirmed positive for alcohol during a random fitness-for-duty test. The employee's access to the plant has been restricted.

The licensee notified the NRC Resident Inspector.

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Part 21 Event Number: 48741
Rep Org: TOPWORX
Licensee: TOPWORX
Region: 1
City: LOUISVILLE State: KY
County:
License #:
Agreement: Y
Docket:
NRC Notified By: BRIAN HAMPTON
HQ OPS Officer: DONALD NORWOOD
Notification Date: 02/11/2013
Notification Time: 15:26 [ET]
Event Date: 10/12/2012
Event Time: [CST]
Last Update Date: 02/11/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
GEORGE HOPPER (R2DO)
PATTY PELKE (R3DO)
BOB HAGAR (R4DO)
PART 21 RX GROUP (E-MA)

Event Text

PART 21 REPORT - SWITCHES BUILT WITH ADHESIVE BEYOND ITS EXPIRATION DATE

TopWorx discovered that switches were built and shipped using adhesive G909 that was beyond its manufacturer's recommended expiration date. Adhesion properties of the expired adhesive cannot be guaranteed against the deleterious effects of seismic events, thermal aging, and high dose radiation. The switches involved were TopWorx M8-24521-P4 shipped on 12 October 2012 and TopWorx M8-2352T-P4 shipped on 8 November 2012. Both shipments were sent to PGS Enrique Maria Hierro S.L. in Spain.

If the units mentioned above are found to be installed in an environment that may expose them to the conditions of seismic events, thermal aging, and/or high dose radiation, then the units should be replaced.

Per TopWorx, there were 13 switches shipped. All switches were shipped to Spain. No switches were shipped to US licensees.

Technical questions or concerns should be addressed to Alex Murphy, Manager, Quality, (502) 873-4602.

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Power Reactor Event Number: 48743
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: RICHARD PROBASCO
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/11/2013
Notification Time: 20:34 [ET]
Event Date: 02/11/2013
Event Time: 14:35 [EST]
Last Update Date: 02/11/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ANTHONY DIMITRIADIS (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

LOSS OF EMERGENCY RESPONSE CAPABILITY - JOINT INFORMATION CENTER (JIC) UNAVAILABLE

"On Monday, February 11, 2013 at 1435 EST with Pilgrim Nuclear Power Station (PNPS) at 0% core thermal power, the Joint Information Center (JIC) was determined to be unavailable and was declared non-operational. [Power was lost] to the facility [due] to winter storm Nemo. This facility serves as the Joint Information Center for Entergy, State, and Federal organizations during an emergency response.

"Existing emergency procedures direct the responsible Emergency Plant Manager to relocate the JIC staff to the designated alternate location (Bridgewater State University) as required. It has been confirmed that the alternate location is available for use.

"The Emergency Response Organization has been informed to establish the JIC at the Moakley Center at Bridgewater State University in the event of a declared emergency classification requiring activation of this Emergency Response Facility.

"The licensee has notified the NRC Senior Resident Inspector and the Commonwealth of Massachusetts.

"This eight-hour notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) due to the loss of an emergency offsite response facility.

"An update will be provided when power has been restored to the JIC and the facility is available to be activated if called upon."

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Power Reactor Event Number: 48744
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [3] [ ] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: TIM JONES
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 02/12/2013
Notification Time: 00:45 [ET]
Event Date: 02/11/2013
Event Time: 22:36 [EST]
Last Update Date: 02/12/2013
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):
GEORGE HOPPER (R2DO)

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 DUE TO TURBINE TRIP ON LOSS OF CONDENSER VACUUM

"This is a non-emergency event notification to the NRCOC [Nuclear Regulatory Commission Operations Center] in accordance with 10 CFR 50.72(b)(2)(iv)(B) for a valid actuation of the Reactor Protection System (RPS) (four hour notification) and 10 CFR 50.72(b)(3)(iv)(A) for a valid Engineered Safeguards (ESF) actuation due to Auxiliary Feedwater (AFW) initiation (eight hour notification).

"On 2/11/2013 at 2236 EST Unit 3 experienced a loss of condenser vacuum. An automatic Turbine Trip signal was generated which initiated a Reactor Trip signal. The reactor tripped as required on the automatic trip signal. Auxiliary feedwater water actuated automatically based on low steam generator levels following the trip. Unit 3 is currently in Mode 3 and stable. Steam generator levels have been returned to normal levels . The loss of vacuum is under investigation at this time. All other plant systems are working as designed."

The reactor trip was uncomplicated. All control rods fully inserted. The plant is stable at normal temperature and pressure. AFW has been secured and main feedwater is being used for Steam Generator water level control. The main condenser is unavailable and decay heat removal is to atmosphere via the atmospheric steam dumps. There are no indications of primary to secondary leakage. Unit 3 is in a normal offsite power electrical alignment. There is no impact on Unit 4.

The licensee has notified the NRC Resident Inspector.

Page Last Reviewed/Updated Tuesday, February 12, 2013
Tuesday, February 12, 2013