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Event Notification Report for February 11, 2013

U.S. Nuclear Regulatory Commission
Operations Center

EVENT REPORTS FOR
02/10/2013 - 02/11/2013

EVENT NUMBERS
488714874248743487444874048904

Power Reactor
Event Number: 48871
Facility: WATTS BAR
Region: 2     State: TN
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: GORDON ARENT
HQ OPS Officer: JOHN SHOEMAKER
Notification Date: 04/01/2013
Notification Time: 09:52 [ET]
Event Date: 02/11/2013
Event Time: 00:00 [EDT]
Last Update Date: 04/01/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.55(e) - CONSTRUCT DEFICIENCY
Person (Organization):
DEBORAH SEYMOUR (R2DO)
NRR 50.55 COORD (EMAI)
Power Reactor Unit Info
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
INSTRUMENTATION LINES NOT INSPECTED COMPLETELY FOR PROPER SLOPE

"WBN [Watts Bar Nuclear] Unit 2 (under construction) determined that a portion of a number of instrumentation lines within multiple systems may have not been inspected completely for proper slope. This condition may have resulted in sense lines being installed with less than the 1/4" per foot minimum slope. No confirmed examples have been identified that would have created a substantial safety hazard at this time. However, walkdowns and evaluations are still underway to confirm that no substantial safety hazards exist. If any examples are found, they will be corrected prior to system turnover to Plant Operations. Therefore, at this time, the safety significance remains indeterminate. This issue has been documented in TVA's corrective action program as Problem Evaluation Report 680826 and is being conservatively reported as a programmatic breakdown by WBN Unit 2 under 10 CFR 50.55(e)."

The licensee has notified the NRC Resident Inspector.


Non-Agreement State
Event Number: 48742
Rep Org: DEPARTMENT OF VETERANS AFFAIRS
Licensee: CARL VINSON VA MEDICAL CENTER
Region: 1
City: DUBLIN   State: GA
County:
License #: 03-23853-01VA
Agreement: Y
Docket:
NRC Notified By: THOMAS HUSTON
HQ OPS Officer: BILL HUFFMAN
Notification Date: 02/11/2013
Notification Time: 18:01 [ET]
Event Date: 02/11/2013
Event Time: 14:00 [EST]
Last Update Date: 02/18/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
20.1906(d)(1) - SURFACE CONTAM LEVELS > LIMITS
Person (Organization):
PATTY PELKE (R3DO)
FSME EVENTS RESOURCE (E-MA)
Event Text
PACKAGE RECEIVED AT VA MEDICAL CENTER WITH OUTSIDE CONTAMINATION EXCEEDING LIMITS

"[The Department of Veterans Affairs, Veterans Health Administration (VHA) National Health Physics Programs] has a master materials license from Nuclear Regulatory Commission. License number is 03-23853-01VA.

"Per 10 CFR 20.1906(d), [the VHA] is reporting receipt of a package of radioactive material with removable surface contamination on the outside of the package greater than NRC reporting limits.

"The package was received today (February 11, 2013) at around 2:00 PM ET by Carl Vinson VA Medical Center, Dublin, Georgia. This medical center holds permit number 10-09569-01 under the VHA master materials license.

"Wipe tests performed on the external surface of the package indicated a removable contamination level of 561 dpm/cm2 as compared to the regulatory limit of 220 dpm/cm2 for beta-gamma emitters.

"The package contained two radiopharmaceuticals dosages of Technetium-99m and two doses of Thallium-201 and was shipped from Cardinal Health in Augusta, Georgia. The inner packaging materials were not contaminated, and the four dosages were able to be used.

"The VA facility Nuclear Medicine Technologist immediately notified the vendor/shipper, who serves as the final delivery carrier, about the contaminated package at about 2:30 PM ET.

"As corrective actions: the packaging materials were set aside in a restricted area at the VA Medical Center for decay; staff with access to the area were notified about the contaminated packaging materials; and surveys were performed to ensure that contamination did not spread beyond the immediate area where the package was received and checked in.

"[The VHA has also] notified NRC Region III (P. Pelke) of this event."


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: 02/12/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ANTHONY DIMITRIADIS (R1DO)
Power Reactor Unit Info
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."


* * * UPDATE FROM DAVID NOYES TO DONALD NORWOOD AT 1616 ON 2/12/2013 * * *

"Power has been restored to the Joint Information Center (JIC). At approximately 1000 on 2/12/13 the JIC was deemed to be available for activation if called upon by the Emergency Preparedness Department. The Emergency Response Organization has been informed to establish the primary JIC 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."

Notified R1DO (Dimitriadis).


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)
Power Reactor Unit Info
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.


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)
Power Reactor Unit Info
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.


Power Reactor
Event Number: 48904
Facility: BROWNS FERRY
Region: 2     State: AL
Unit: [] [] [3]
RX Type: [1] GE-4,[2] GE-4,[3] GE-4
NRC Notified By: TODD CHRISTENSEN
HQ OPS Officer: VINCE KLCO
Notification Date: 04/09/2013
Notification Time: 17:07 [ET]
Event Date: 02/11/2013
Event Time: 06:13 [CDT]
Last Update Date: 04/09/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
MALCOLM WIDMANN (R2DO)
Power Reactor Unit Info
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N N 0 Hot Shutdown 0 Hot Shutdown
Event Text
MANUAL INITIATION OF REACTOR CORE ISOLATION COOLING SYSTEM

"On February 11, 2013, at 0613 hours [CDT], the Reactor Core Isolation Cooling (RCIC) system was manually started during a planned Unit 3 reactor shutdown. A Reactor Feedwater recirculation piping separation resulted in the loss of condenser vacuum and subsequent unavailability of the Main Turbine Bypass Valves. The RCIC system was manually started at 9.2" of condenser vacuum in order to control reactor water level in anticipation of loss of Reactor Feedwater Pumps (RFPs) which occurs at 7" of condenser vacuum. Safety Relief Valves (SRVs) were manually operated to maintain reactor pressure. The reactor water level was controlled in the normal band by RCIC, and Reactor Pressure was controlled with a combination of Reactor Core Isolation Cooling (RCIC) system and SRV manual operation. All systems operated as designed and Reactor water level was maintained in the prescribed band. No Emergency Core Cooling System (ECCS) or Reactor Core Isolation Cooling (RCIC) reactor water level initiation set points were reached. RCIC operation was secured at 1449 [CDT] on 2/11/2013.

"This event is reportable within 8 hours per 10CFR50.72(b)(3)(iv)(A). During a review of operating logs it was identified that this event met reporting requirements and had not been reported. Therefore, this report does not comply with the 8 hour requirement. This condition has been entered into the corrective action program. Additionally, an LER is required within 60 days per 10CFR50.73(a)(2)(iv)(A).

"The NRC Resident Inspector has been notified."