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Event Notification Report for April 22, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/19/2013 - 04/22/2013

** EVENT NUMBERS **


48859 48917 48937 48939 48945 48947 48948 48949 48950

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Agreement State Event Number: 48859
Rep Org: MA RADIATION CONTROL PROGRAM
Licensee: MASSACHUSETTS PORT AUTHORITY
Region: 1
City: WORCHESTER State: MA
County:
License #: N/A
Agreement: Y
Docket:
NRC Notified By: TONY CARPENTINO
HQ OPS Officer: HOWIE CROUCH
Notification Date: 03/27/2013
Notification Time: 17:02 [ET]
Event Date: 01/16/2013
Event Time: [EDT]
Last Update Date: 04/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
PAUL KROHN (R1DO)
FSME EVENTS RESOURCE (EMAI)

This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

DISCOVERY OF TWO RADIOACTIVE GAUGES IN LOCKED STORAGE

The following information was obtained from the Commonwealth of Massachusetts via email:

"[On approximately] 1/16/13, two surface gauges [manufactured in 1961 were] found in locked storage within [a] remote airfield facilities building at Worcester Regional Airport, Worcester, MA. Third-party waste brokers [were] contacted to bid on proper removal. Wipe tests by a third-party waste broker indicate no leakage of radioactive contamination from [the] gauge sources. [The Massachusetts Radiation Control Program (the Agency) received the information via email] on 3/19/13. The Agency conducted a site visit to confirm device identifications on 3/26/13. A waste brokers' bid [was] accepted [and] packaging and removal [is] scheduled for 4/17/13. Gauges [are being] held in locked storage until removal by [the] waste broker.

"[The] items [are] described as one Nuclear-Chicago Corporation Model P21 Surface Moisture Probe, SN 136, containing 5 mCi Ra-Be, date stamped 5/2/61; and one Nuclear-Chicago Corporation Model P22A Surface Density Probe, SN 139, containing 3 mCi Cs-137, date stamped 5/23/61.

"The Agency considers this matter to be open until [the] items [are] confirmed removed on 4/17/13."

* * * UPDATE FROM ANTHONY CARPENITO TO CHARLES TEAL ON 4/19/13 AT 1132 EDT * * *

"4/19/13 UPDATE - The Agency [Massachusetts Radiation Control Program] considers this matter to be OPEN until items confirmed removed for disposal.

"Agency [Massachusetts Radiation Control Program] regulation 105 CMR 120.281 (A)(1) and USNRC regulation 20.2201 (a)(1)(i) requires 'immediate' telephone reporting of stolen, lost or missing licensed radioactive material in specified quantities under circumstances that it appears an exposure could result to individuals in unrestricted areas. The situation in this case involved 'found' radioactive material, devices already wipe tested to confirm no leakage of radioactive contamination and stored in a 'secure' location to prevent exposure to individuals until such time that scheduled packaging and removal by a waste broker is completed, and therefore, did not warrant immediate notification. This case was determined to be included in the 30-day notification category. The written report to NMED was issued one day after the Agency [Massachusetts Radiation Control Program] confirmatory site visit of 3/26/13."

NMED Report #: 130149

Notified R1DO (Cook) and FSME Event Resource via email.

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

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Non-Agreement State Event Number: 48917
Rep Org: U.S. ARMY
Licensee: U.S. ARMY
Region: 1
City: CAMP LEJEUNE State: NC
County:
License #: 21-32838-01
Agreement: Y
Docket:
NRC Notified By: THOMAS GIZICKI
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/12/2013
Notification Time: 11:46 [ET]
Event Date: 04/11/2013
Event Time: 13:00 [EDT]
Last Update Date: 04/12/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(1) - UNPLANNED CONTAMINATION
Person (Organization):
DAVE PASSEHL (R3DO)
FSME EVENTS RESOURCE ()
JAMES TRAPP (R1DO)

Event Text

TRITIUM LAMP BROKEN DURING MAINTENANCE OF A MORTAR SIGHT

On 4/11/13 at 1300 EDT, a 1 Ci tritium lamp was broken during routine maintenance on a M64 mortar sight unit. The sealed source tritium lamp broke when a wrench hit the tritium module. Surveys were conducted, but the results will not be available until next week. Bioassays are being perform on 4 individuals and based on historic records, the RSO expects minimal intake of less than 5 mrem. The device was bagged, tagged and placed in a secure storage area for future disposal.

The licensee attempted to notify R3 (McCraw).

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 48937
Facility: PERRY
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: GLENDON BURNHAM
HQ OPS Officer: BILL HUFFMAN
Notification Date: 04/17/2013
Notification Time: 05:20 [ET]
Event Date: 04/16/2013
Event Time: 23:23 [EDT]
Last Update Date: 04/20/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
STEVE ORTH (R3DO)

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

Event Text

DEGRADED FLOW IN EMERGENCY SERVICE WATER SYSTEM 'A'

"The Perry Nuclear Power Plant is reporting an event or condition pursuant to 10 CFR 50.72(b)(3)(v)(D).

"On April 16, 2013, at 2323 EDT, it was identified that Emergency Service Water (ESW) pump 'A' was inoperable due to an inability to maintain minimum flow requirements. As a result, ESW 'A' and the supported Division 1 Emergency Diesel Generator (EDG) were declared inoperable. Coincident with this discovery, a test of the Division 2 emergency systems was in progress with the associated ESW 'B' pump and Division 2 EDG inoperable. Division 2 EDG was available to support the Shutdown Defense In-Depth Strategy. Division 3 EDG was operable and could supply High Pressure Core Spray system injection, if needed.

"Both EDGs were inoperable simultaneously and Technical Specification 3.8.2 'AC Sources-Shutdown' was entered and required actions taken. These actions included immediately suspending core alterations and immediately initiating actions to restore the required EDG. The test of Division 2 emergency systems was suspended and ESW 'B' and the Division 2 EDG were restored to operable status at 0135 EDT on April 17, 2013.

"The failure of ESW 'A' minimum flow is currently under investigation.

"The Resident Inspector has been notified."

* * * RETRACTION FROM JOHN PELCIC TO CHARLES TEAL ON 4/20/13 AT 1355 EDT * * *

"Engineering personnel performed an immediate investigation of the ESW 'A' minimum flow condition. The investigation results showed that the ESW 'A' pump flow exceeded the minimum flow requirement to protect the ESW 'A' system. Therefore, continued operation of ESW 'A' was acceptable and the minimum flow condition originally reported did not cause the Division 1 Emergency Diesel Generator to be inoperable.

"The condition would not have prevented the fulfillment of a safety function to mitigate the consequences of an accident. Reporting is not required under 10 CFR 50.72(b)(3)(v)(D) and this notification is retracted.

"The NRC Resident Inspector has been notified."

Notified R3DO (Orth).

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Power Reactor Event Number: 48939
Facility: LASALLE
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] GE-5,[2] GE-5
NRC Notified By: DAN SZUMSKI
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/17/2013
Notification Time: 16:59 [ET]
Event Date: 04/17/2013
Event Time: 15:11 [CDT]
Last Update Date: 04/21/2013
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(A) - ECCS INJECTION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
STEVE ORTH (R3DO)
JEFFERY GRANT (IRD)
DAVID SKEEN (NRR)
JENNIFER UHLE (NRR)
ANNE BOLAND (R3)

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

Event Text

NOTIFICATION OF UNUSUAL EVENT DECLARED DUE TO LOSS OF OFFSITE POWER FROM A LIGHTNING STRIKE

"LaSalle Unit 1 and LaSalle Unit 2 have both experienced an automatic reactor scram, in conjunction with a loss of offsite power. This was caused by an apparent lightning strike in the main 345kV/138kV switchyard during a thunderstorm. 138kV line 0112 has been inspected in the field, and heavy damage has been noted on the insulators on two of the three phases on a line lightning arrestor line side.

"The plant systems have all responded as expected. All five diesel generators started, and have loaded on to their respective buses as designed. All rods went full in on both units during the respective scrams. HPCS [High Pressure Core Spray] system was started on each unit and automatically aligned for injection for initial level control."

The MSIVs [Main Steam Isolation Valves] are shut on both units with decay heat being removed via the safety relief valves. Suppression pool cooling is in progress.

The licensee will notify the NRC Resident Inspector and has notified the State.

Notified DHS, FEMA, USDA, HHS, DOE, NICC, EPA, and Nuclear SSA via email.

* * * UPDATE FROM DON PUCKETT TO VINCE KLCO AT 2113 EDT ON 4/17/2013 * * *

"In addition to information [previously provided], LaSalle Unit 2 received a high drywell pressure signal [1.77 psig] due to loss of containment cooling from the loss of power. At the time of this high drywell pressure signal, high pressure core spray pump and 2B residual heat removal [RHR] pump was already in operation, the low pressure core spray system and 2A residual heat removal system was secured and [placed] in pull to lock. When the signal was satisfied the ECCS [Emergency Core Cooling Systems] signal was processed but only the 2C RHR pump would have started. In this case, the 2C RHR pump tripped when the signal was received. There is no evidence of reactor coolant leakage. There was no additional ECCS systems discharging into the RCS [Reactor Coolant System]. As [initially stated], level was controlled using High Pressure Core Spray and level control is now being maintained using the Reactor Core Isolation Cooling [RCIC] systems. The 2C RHR pump trip is under investigation.

"Due to the initial loss of offsite power for both Unit 1 and Unit 2 reported at 1511 [CDT], multiple containment isolation valves isolated and closed as expected. Once initial containment isolations were verified, two Unit 2 primary containment vent and purge valves were opened to vent the Unit 2 containment. Once Unit Two containment pressure reached 1.77 [psig], these two vent valves isolated as expected.

"Due to the loss of offsite power, the Station Vent Stack Wide Range Gas Monitor (WRGM) and the Standby Gas Treatment Wide Range Gas Monitor (VGWRGM) also lost power. Manual sampling has been implemented and power is restored to the VGWRGM, however the VGWRGM has not been declared operable yet. Normal radiation levels have been reported from the manual sampling. [This is being reported in accordance with 10CFR50.72(b)(3)(xiii).]"

The licensee notified the NRC Resident Inspector and the State of Illinois.

Notified the R3 IRC, NRR EO(Skeen), IRD MOC (Grant).

* * * UPDATE AT 0057 EDT ON 04/18/13 FROM MIKE LAWRENCE TO S. SANDIN * * *

"After the Unit 2 primary containment vent and purge system isolated on the Unit 2 containment High Pressure signal, Venting of the Unit 1 primary containment was commenced. At 2005 CDT, Unit 1 primary containment pressure reached the Group 2 primary containment isolation system setpoint (1.77 PSIG) causing the primary containment vent and purge valves being used to vent the Unit 1 containment to isolate. Unit 1 primary containment venting was being performed through the Standby Gas Treatment system which is a filtered system.

"In addition to the primary containment isolation signal on high drywell pressure, an ECCS initiation on high drywell pressure also occurred. The ECCS signal resulted in an auto start of the 1C RHR system. The 1B RHR system was already running in suppression pool cooling mode. 1A RHR and LPCS had been secured to prevent overloading the common diesel generator for division 1. The common diesel generator supplies both Unit 1 and Unit 2 division 1 ESF busses."

The licensee informed the NRC Resident Inspector. Notified NRR EO (Skeen), IRD MOC (Grant) and R3IRC (Louden).

* * * UPDATE AT 0947 EDT ON 04/18/13 FROM JUSTIN FREEMAN TO PETE SNYDER * * *

"LaSalle has terminated the unusual event which was initiated at 1511 on 4/17/13 and reported under EN 48939. This unusual event has been terminated based on meeting the following established criteria. This report is being made in accordance with 10CFR50.72.(c)(1)(iii).

"1) Off-site power has been restored to all ESF busses
"2) Fuel Pool Cooling has been restored on both units
"3) Primary Containment Chillers have been restored on both units
"4) Drywell pressure is less than ECCS initiation setpoint
"5) ECCS signals cleared to allow diesels to be placed in stand by

"Recovery of remaining plant systems will be managed through the Outage Control Center (OCC)."

The licensee informed the NRC Resident Inspector. Notified R3DO (Orth), NRR EO (Chernoff), IRD (Grant), DHS, FEMA, USDA, HHS, DOE, NICC, EPA, and Nuclear SSA via email.

* * * UPDATE AT 1711 EDT ON 4/21/2013 FROM GREG LECHTENBERG TO MARK ABRAMOVITZ * * *

"In addition to the 10 CFR 50.72 Sections initially identified, the Loss of Offsite Power was also reportable under 10 CFR 50.72(b)(3)(v)(D) as an event or condition that could have prevented the fulfillment of the safety function of systems needed mitigate the consequences of an accident. This event is considered a safety system functional failure for both Units 1 and 2."

The licensee will notify the NRC Resident Inspector.

Notified the R3DO (Orth).

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Power Reactor Event Number: 48945
Facility: COOK
Region: 3 State: MI
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RANDY ROSE
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/19/2013
Notification Time: 12:30 [ET]
Event Date: 04/18/2013
Event Time: 23:12 [EDT]
Last Update Date: 04/19/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
STEVE ORTH (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling
2 N Y 100 Power Operation 100 Power Operation

Event Text

INADVERTENT ACTIVATION OF AN EMERGENCY SIREN

"On 4/18/13 at 2312 EDT, Emergency Siren 955 inadvertently actuated for approximately 5 minutes. The cause of the actuation is under investigation but believed to be due to rain water intrusion. The siren stopped on its own, and was subsequently disconnected by the siren vendor to prevent further erroneous actuation. The siren remains out service and is the only siren out of service within the 10 mile Emergency Planning Zone (EPZ). There are a total of 70 sirens.

"The siren is located in a state park not currently inhabited by campers; due to the siren location and time of activation the impact on the surrounding population was minimal. The event was therefore determined to not be reportable.

"A subsequent review of the event, considering communications made between Cook Nuclear Plant and the Berrien County 911 Dispatch Center, as well as recent industry operating experience of similar events, was performed; its conclusion was to conservatively make a report under 10 CFR 50.72(b)(2)(xi).

"The licensee has notified the NRC Resident Inspector."

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Power Reactor Event Number: 48947
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JIM BUTLER
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/19/2013
Notification Time: 15:56 [ET]
Event Date: 04/19/2013
Event Time: 15:18 [EDT]
Last Update Date: 04/19/2013
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
WILLIAM COOK (R1DO)
BILL DEAN (R1RA)
JENNIFER UHLE (NRR)
JEFFERY GRANT (IRD)

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

NOTIFICATION OF UNUSUAL EVENT DECLARED DUE TO INABILITY TO CONFIRM A FIRE IN THE PROTECTED AREA WITHIN 15 MINUTES

"Fire within the Protected Area not verified within 15 minutes. Emergency Action Level HU 2.1 declared at 1518 EDT. Confirmation of no fire completed at 1526 EDT."

The fire alarm occurred in the Rad Waste Building. Due to the location of the alarm, the licensee was not able to validate alarm within 15 minutes which led to the emergency declaration. Once access to the area was obtained, there was no fire observed. The cause of the inadvertent fire alarm is under investigation.

The licensee has notified Lower Alloways Creek Township, the State of New Jersey, the State of Delaware and the NRC Resident Inspector.

Notified DHS, FEMA, NICC and NuclearSSA via email.

* * * UPDATE FROM MARTIN FRANKLIN TO HOWIE CROUCH AT 1731 EDT ON 4/19/13 * * *

At 1725 EDT, the licensee terminated the Notification of Unusual Event. The affected fire alarm was placed out of service and a fire watch has been established.

The licensee has notified Lower Alloways Creek Township, the State of New Jersey, the State of Delaware and the NRC Resident Inspector.

Notified R1DO (Cook), IRD (Grant), NRR EO (Skeen), DHS, FEMA, NICC, and NuclearSSA via email.

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Power Reactor Event Number: 48948
Facility: TURKEY POINT
Region: 2 State: FL
Unit: [ ] [4] [ ]
RX Type: [3] W-3-LP,[4] W-3-LP
NRC Notified By: ROBERT PELL
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/19/2013
Notification Time: 18:08 [ET]
Event Date: 04/19/2013
Event Time: 17:20 [EDT]
Last Update Date: 04/19/2013
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
STEVEN VIAS (R2DO)
VICOTR MCCREE (R2RA)
JENNIFER UHLE (NRR)
JEFFERY GRANT (IRD)
DAVID SKEEN (NRR)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
4 A/R Y 29 Power Operation 0 Hot Standby

Event Text

UNUSUAL EVENT DUE TO LOSS OF OFFSITE POWER GREATER THAN 15 MINUTES

"An Unusual Event was declared on Unit 4 at 1730 EDT due to a loss of offsite power for greater than 15 minutes. Emergency buses are being powered from the Emergency Diesel Generators. All rods inserted. The plant is stabilizing on natural circulation in Mode 3. Emergency buses failed to auto-transfer to the startup transformer."

AFW initiated and is supplying water to the steam generators. There was no impact on Unit #3. The failure of the auto-transfer of the startup transformer is under investigation.

Notified DHS, FEMA, NICC and NuclearSSA via email. The licensee notified State of Florida, Miami Dade county, the NRC Resident Inspector.

* * * UPDATE FROM ROBERT PELL TO CHARLES TEAL ON 4/19/13 AT 1911 EDT * * *

"At 1854 EDT Turkey Point Unit 4 continues to be in an Unusual Event due to a loss of offsite power. The emergency buses were energized from the start up transformer at 1824 EDT. Two reactor coolant pumps have been started and are running. The plant is stabilizing in Mode 3. In addition, per 10 CFR 50.72(b)(iv)(B) and 10 CFR 50.72(b)(iv)(A) notifications are being made for the Reactor Protection Actuation for loss of power and the Emergency Safety Function actuations of the Emergency Diesel Generators and Auxiliary Feedwater."

The licensee notified State of Florida, Miami Dade county, the NRC Resident Inspector. Notified R2DO (Vias), NRR (Skeen), and IRD (Grant).

* * * UPDATE FROM ROBERT PELL TO CHARLES TEAL ON 4/19/13 AT 1943 EDT * * *

"All emergency buses are powered from offsite power. Unit 4 is stable in Mode 3. The Unusual Event was terminated at 1915 EDT on 4/19/13."

The licensee notified State of Florida, Miami Dade county, the NRC Resident Inspector. Notified R2DO (Vias), NRR (Skeen), and IRD (Grant). Notified DHS, FEMA, NICC and NuclearSSA via email

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Power Reactor Event Number: 48949
Facility: SALEM
Region: 1 State: NJ
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: HARRY WIEDMAN
HQ OPS Officer: PETE SNYDER
Notification Date: 04/20/2013
Notification Time: 09:46 [ET]
Event Date: 04/20/2013
Event Time: 04:22 [EDT]
Last Update Date: 04/20/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
WILLIAM COOK (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

ACCIDENT MITIGATION - COMMON CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM

"Salem Unit 2 was placed in a configuration that affected the ability to mitigate the consequences of an accident due to an inadvertent actuation of the common control room emergency air conditioning system (CREACS). CREACS was actuated as a result of an invalid Control Room air intake duct radiation monitor signal initiated on April 20, 2013 at 0422 hours [EDT].

"Salem Unit 1 is currently in Mode 6 with core offload in progress. Salem Unit 2 is in Mode 1 at 100% power. Unit 2 has two shutdown LCOs in effect. The first is for the CREACS, which is shared between Unit 1 & 2, being aligned for single train operation with the Unit 1 CREACS train out of service per LCO 3.7.6. The second shutdown LCO is for single source of offsite power due to scheduled maintenance.

"With Unit 1 having an invalid radiation monitor signal, the CREACS automatically aligned to accident pressurized mode. This mode of actuation starts the CREACS fans, isolates the Control Room Envelope from the normal control room ventilation system and aligns the two sets of CREACS outside air intake dampers. With a Unit 1 radiation monitor signal the Unit 1 CREACS intake dampers close and the Unit 2 CREACS intake dampers open. These damper positions are locked in until manually reset. With only one train of CREACS operable, the dose analysis indicates that the requirements of General Design Criteria (GDC) 19 can only be met during the worst case design basis accident if the Unit 2 CREACS intake dampers are closed and the Unit 1 CREACS intake dampers [are] open. Therefore, until the CREACS intake dampers were reset and realigned, Salem Unit 2 would not have been able to mitigate the consequences of an accident and is reportable in accordance with 10CFR50.72(b)(3)(v).

"The CREACS system actuation was reset after the failed radiation monitor (2R1B ch. II) was removed from service and the dampers were realigned to their pre-actuation alignment at 0457 hours, restoring Salem Unit 2 to within the assumptions of the dose analysis. Total duration in the condition was 35 minutes.

"The only pieces of major equipment out of service on Salem Unit 2 are the 4 Station Power Transformer and 23 Station Power Transformer which are out of service for scheduled maintenance."

The licensee will notifying Lower Alloways Creek township and the NRC Resident Inspector.

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Power Reactor Event Number: 48950
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAMON FEGLEY
HQ OPS Officer: PETE SNYDER
Notification Date: 04/21/2013
Notification Time: 02:29 [ET]
Event Date: 04/21/2013
Event Time: 02:11 [EDT]
Last Update Date: 04/21/2013
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
STEVEN VIAS (R2DO)
VICTOR MCCREE (R2)
JENNIFER UHLE (NRR)
DAVID SKEEN (NRR)
JEFFERY GRANT (IRD)
DARYL JOHNSON (ILTA)
JIM WIGGINS (NSIR)

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

NOTIFICATION OF UNUSUAL EVENT DUE TO SHOTS FIRED WITHIN THE OWNER CONTROLLED AREA

An unidentified individual fired a shot at a site security vehicle. "Watts Bar Nuclear Plant Declared a Notice of Unusual Event (NOUE) at 0211 EDT April 21, 2013. [The licensee notified] Rhea and Meigs County Sheriff departments for on-site support.

"A notification of the event discussed above was made to the State of Tennessee. A notification of the event discussed above was made [to the] U.S. Department of Energy (DOE) Electricity Delivery and Energy Reliability."

The licensee notified the NRC Resident Inspector.

Notified DHS, FEMA, USDA, HHS, DOE, NICC, EPA, FBI SIOC and Nuclear SSA via email.

* * * UPDATE FROM DAMON FEGLEY TO PETE SNYDER AT 0634 EDT ON 4/21/13 * * *

"This information is being provided to the NRC for a 10CFR50.72(b)(2)(xi) notification.

"TVA is planning on making a news release to local media affiliates and posting the news release on TVA's website. This news release is in reference to the Notification of Unusual Event (NOUE) Watts Bar Nuclear Plant recently entered for a security condition."

Notified R2DO (Vias).

* * * TERMINATION AT 1301 EDT ON 4/21/2013 FROM MICHAEL BOTTORFF TO MARK ABRAMOVITZ * * *

"[At] 1230 EDT Watts Bar Nuclear plant terminated the Notification of Unusual Event.

"TVA is planning on making an additional news release to local media affiliates and posting the news release on TVA's website. This news release is in reference to the Notification of Unusual Event (NOUE) Watts Bar Nuclear Plant recently terminated.

"The licensee notified the NRC Senior Resident Inspector."

Notified the R2 IRC, IRD (Grant), NSIR (Wiggins), NRR (Uhle), ILTAB (Johnson), DHS, FEMA, USDA, HHS, DOE, NICC, EPA, FBI SIOC and Nuclear SSA via email.

Page Last Reviewed/Updated Monday, April 22, 2013
Monday, April 22, 2013