United States Nuclear Regulatory Commission - Protecting People and the Environment

Event Notification Report for April 11, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/10/2013 - 04/11/2013

** EVENT NUMBERS **


48874 48875 48876 48884 48906 48907 48908 48909 48910 48911 48912 48913

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Agreement State Event Number: 48874
Rep Org: COLORADO DEPT OF HEALTH
Licensee: TERRACON, INC.
Region: 4
City: COLORADO SPRINGS State: CO
County:
License #: 664-02
Agreement: Y
Docket:
NRC Notified By: MARK DATER
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/02/2013
Notification Time: 10:55 [ET]
Event Date: 03/29/2013
Event Time: 10:06 [MDT]
Last Update Date: 04/02/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY KELLAR (R4DO)
FSME EVENTS RESOURCE ()

Event Text

AGREEMENT STATE REPORT - DAMAGED TROXLER MOISTURE DENSITY GAUGE

The following information was received from the State of Colorado via email:

"At 10:06 am on Friday, March 29, 2013 the Emergency Response Duty Officer was notified that there was an incident involving a portable moisture density gauge that had been run over by a piece of heavy construction equipment. The [Colorado] Department [of Public Health and Environment] responded by phone and contacted the RSO [Radiation Safety Officer] for Terracon, Inc., who was on site supervising the incident. The RSO reported that the gauge had been backed over by a Bobcat loader. The Bobcat loader had a counter balance weight on the rear of the equipment and this contacted the gauge damaging the outer casing. The RSO reported that the source had been fully retracted and was in the safe (shielded position). The RSO conducted a survey and the reading was 0.2 mr/hr at 1 foot. The gauge was loaded into the transport box and readied for transport back to storage at the Tarracon facility. The transport index on the box was 0.1 mr/hr and the RSO was given permission to transport gauge back to storage and perform a leak test before sending off for repair. The leak tests proved negative and the gauge was [shipped] for repair. This licensee will be issued a Notice of Violation of Part 4.26.1: 'The licensee shall control and maintain constant surveillance of licensed or registered radioactive material that is in an unrestricted area and that is not in storage or in a patient.'

"Licensee causing incident: Terracon, Inc., Colo. License number 664-02
"Density gauge model and serial number: Troxler model 3430 s/n 28184
"Isotopes in gauge: Cs-137 (9mCi); Am-241 (40mCi)
"Survey meter used by RSO: Radiation Alert Monitor 4, s/n 42585, Cal. Date: August 7, 2012"

Incident number: I13-03

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Agreement State Event Number: 48875
Rep Org: NC DIV OF RADIATION PROTECTION
Licensee: GOODYEAR TIRE & RUBBER COMPANY
Region: 1
City: FAYETTEVILLE State: NC
County:
License #: 026-0352-0G
Agreement: Y
Docket:
NRC Notified By: WILLIAM JOHNSON
HQ OPS Officer: PETE SNYDER
Notification Date: 04/02/2013
Notification Time: 13:24 [ET]
Event Date: 03/30/2013
Event Time: 17:08 [EDT]
Last Update Date: 04/02/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES DWYER (R1DO)
FSME EVENT RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - FIRE IN PLANT MAY HAVE DAMAGED TWO PROCESS GAUGES

The following information was received via facsimile:

Two process gauges containing Sr-90 (approximately 50 mCi ea.) at the Goodyear Tire and Rubber Company facility in Fayetteville, NC may have sustained damage as a result of a fire. No leakage is reported. The gauges were mounted in a "LOW - Minimal or Low risk area."

The State of North Carolina will be investigating.

NC Incident No. 13-06.

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Non-Agreement State Event Number: 48876
Rep Org: RAPID CITY REGIONAL HOSPITAL
Licensee: RAPID CITY REGIONAL HOSPITAL
Region: 4
City: RAPID CITY State: SD
County:
License #: 40-00238-04
Agreement: N
Docket:
NRC Notified By: JAMES McKEE
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/02/2013
Notification Time: 14:50 [ET]
Event Date: 02/26/2013
Event Time: [MDT]
Last Update Date: 04/02/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
35.3045(a)(1) - DOSE <> PRESCRIBED DOSAGE
Person (Organization):
RAY KELLAR (R4DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

MEDICAL EVENT INVOLVING DELIVERED DOSE EXCEEDING PRESCRIBED DOSE >20%

During a review of post implant dosimetry for prostate cancer treatment at 0800 hours [MDT] on 4/02/13, it was discovered that a patient received 145 gray vice 110 gray prescribed as a "boost" treatment. The prescribing physician will inform the patient and consult with the urologist. The error occurred due to not taking into account that the prescribed dose was a "boost" to the previously delivered 45 gray on 2/14/13, and used the default value of 145 gray for initial treatment. The physician is evaluating any potential adverse consequences for the patient.

A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.

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Agreement State Event Number: 48884
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: NONDESTRUCTIVE & VISUAL INSPECTION
Region: 4
City: GRAY State: LA
County:
License #: LA-5601-L01
Agreement: Y
Docket:
NRC Notified By: JOE NOBLE
HQ OPS Officer: PETE SNYDER
Notification Date: 04/03/2013
Notification Time: 16:20 [ET]
Event Date: 04/01/2013
Event Time: [CDT]
Last Update Date: 04/03/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY KELLAR (R4DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

AGREEMENT STATE REPORT - POSSIBLE OVEREXPOSURE OF RADIATION WORKER

The following information was received from the State of Louisiana via email:

"On 04/01/2013 [the] RSO for NVI [Nondestructive & Visual Inspection], notified the Department [Louisiana Department of Environmental Quality] that his personnel monitoring processing company, Landauer, notified him that one of his monitors was processed with a result of 108 R exposure. The monitor was assigned to an individual who had been terminated at the beginning of February 2013 for chemical dependency. The individual could not be directly contacted and the monitor was missing for the month of February. The monitor appeared in the cab of a rig truck for radiography. The employee had not been employed or working in a radiation environment for NVI about 2-3 weeks when the monitor surfaced. Attempts were made to make contact with the individual, but [there was] no response.

"[The RSO] stated that he was trying to reach the individual to provide him with medical assistance. At a minimum, he wanted to do blood work Cytogenetics/Biodosimetry on the individual. This is a possible but, not probable excessive exposure to this individual.

"At 8:00 AM on 04/02/2013 [the RSO] called to update the Department and stated that the individual returned his call at [11:00 PM] on 04/01/2013 and consented to accept the medical assistance. The employee has not been sick or had any visible signs of radiation sickness. The trip to a physician office and a call to REACTS in Oak Ridge, TN set up the process for Monday April 8, 2013. The process needs fresh blood within 24 hours for the test. At this time, the Department considers this incident pending the outcome of the test."

LA Event Report ID: LA-120014

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Power Reactor Event Number: 48906
Facility: VOGTLE
Region: 2 State: GA
Unit: [3] [4] [ ]
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: HOWARD MAHAN
HQ OPS Officer: HOWIE CROUCH
Notification Date: 04/10/2013
Notification Time: 09:47 [ET]
Event Date: 12/06/2012
Event Time: 08:00 [EDT]
Last Update Date: 04/10/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.55(e) - CONSTRUCT DEFICIENCY
Person (Organization):
MALCOLM WIDMANN (R2DO)

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

Event Text

FAILURE TO COMPLY WITH CONDITIONS OF CONSTRUCTION PERMIT

"50.55(e) initial notification for failure to comply with requirements of 10 CFR 50 Appendix B, Criterion VII for procurement of safety-related components associated with AP1000 Nuclear Power Plant construction by CB&I (formerly Shaw Nuclear).

"This 50.55(e) initial notification addresses a failure to comply by CB&I, an agent of Southern Company for Vogtle 3&4, to meet the requirements of Appendix B, Criterion VII. It is concluded that the QA programmatic issues, as identified by the root cause analysis associated with NRC violation 05200025/2012-004-02, could have produced a defect and this condition is reportable in accordance with 10 CFR 50.55(e)(3)(iii)(C). The root cause of the programmatic procurement problems was that the existing Shaw Nuclear procurement and quality oversight and inspection program did not include a sufficiently strategic, integrated, and graded approach to assure the required quality of material, equipment, and services. This notification closes the interim report submitted on February 4, 2013 by Southern Company.

"This 50.55(e) initial notification is being submitted pursuant to the requirements of 10 CFR 50.55(e)(3)(iii)(C)."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 48907
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: DAVE RICHARDSON
HQ OPS Officer: PETE SNYDER
Notification Date: 04/10/2013
Notification Time: 11:06 [ET]
Event Date: 04/10/2013
Event Time: 11:30 [EDT]
Last Update Date: 04/10/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAMES TRAPP (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

PLANNED TECHNICAL SUPPORT CENTER OUTAGE

"A planned work package (52343687-01) at the James A. FitzPatrick (JAF) Nuclear Power Plant will be performed for DOP/Freon Testing TSCVASS as required per TS 5.5.8 Ventilation Filter Testing Program. The testing requires breaking the boundary into the Technical Support Center (TSC) ventilation system to obtain a charcoal sample. Therefore, the TSC ventilation system will be rendered nonfunctional during the duration of this work activity. The TSC ventilation is expected to be out of service for approximately 6 hours.

"If an emergency is declared requiring TSC activation during this period, the TSC will be staffed and activated using existing emergency planning procedures unless the TSC becomes uninhabitable due to ambient temperature, radiological, or other conditions. If relocation of the TSC becomes necessary, the station Emergency Plant Manager will relocate the TSC staff to an alternate TSC location In accordance with applicable site procedures giving first consideration to the Control Room. TSC facility leads have been made aware of this contingency.

"This notification is being made in accordance with 10CFR50.72(b)(3)(xiii) due to the potential loss of an emergency response facility (ERF). An update will be provided once the TSC ventilation has been restored to normal operation.

"The NRC Resident Inspector has been notified."

* * * UPDATE ON 4/10/13 AT 1717 EDT FROM DAVE RICHARDSON TO DONG PARK * * *

"This is an update from EN #48907. Planned maintenance has been completed on the Technical Support Center (TSC) ventilation system. The TSC filtered ventilation system has been restored to normal standby lineup.

"The NRC Resident Inspector has been informed."

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Power Reactor Event Number: 48908
Facility: HOPE CREEK
Region: 1 State: NJ
Unit: [1] [ ] [ ]
RX Type: [1] GE-4
NRC Notified By: JOHN PANAGOTOPULOS
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/10/2013
Notification Time: 13:13 [ET]
Event Date: 04/10/2013
Event Time: 09:30 [EDT]
Last Update Date: 04/10/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
JAMES TRAPP (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

LOSS OF EMERGENCY NOTIFICATION SYSTEM TELEPHONE

"On April 10, 2013 at 0930 [EDT] Hope Creek Operations personnel identified that the NRC ENS phone line was unavailable for Hope Creek Generating Station. The loss of the NRC ENS line was verified by the Hope Creek Shift Manager via backup land line communication to the NRC. The NRC Operations Center has an open repair ticket with the phone service provider.

"The loss of the phone line had no effect on plant operation and the unit remains at 100% power.

"Additionally, Emergency Response Data System (ERDS) capability was verified to remain intact and is available to transmit data.

"No personnel injuries resulted from the event.

"The NRC Resident Inspector has been informed."

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Power Reactor Event Number: 48909
Facility: PILGRIM
Region: 1 State: MA
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JOHN OHRENBERGER
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/10/2013
Notification Time: 16:19 [ET]
Event Date: 04/10/2013
Event Time: 13:14 [EDT]
Last Update Date: 04/10/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JAMES TRAPP (R1DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 86 Power Operation 86 Power Operation

Event Text

MASSACHUSETTS AGENCIES NOTIFIED REGARDING NEUTRALIZING SUMP DISCHARGE LINE INSPECTION

"At 1314 hours on Wednesday, April 10, 2013 during a boroscopic inspection of the sub-surface portions of the Neutralizing Sump Discharge Line, Pilgrim Station discovered indications of a separation in the line. The line is currently isolated and no discharges were in progress during the planned inspection. This line is used infrequently to discharge permitted liquids that have the potential to contain radiological contamination. This
notification is conservatively being made in accordance with Pilgrim site procedures with direct voluntary communications with offsite agencies.

"There is no impact on the safe operation of the plant and personnel are investigating the cause.

"The [NRC] Resident Inspector staff has been informed of this notification.

"This notification is being made in accordance with 10 CFR 50.72(b)(2)(xi).

"The licensee will notify the Massachusetts Emergency Management Agency (MEMA) and other state agencies."

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Power Reactor Event Number: 48910
Facility: SUMMER
Region: 2 State: SC
Unit: [ ] [2] [3]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: J. FINDLAY SALTER
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/10/2013
Notification Time: 16:44 [ET]
Event Date: 12/06/2012
Event Time: 08:00 [EDT]
Last Update Date: 04/10/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.55(e) - CONSTRUCT DEFICIENCY
Person (Organization):
MALCOLM WIDMANN (R2DO)

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

Event Text

FAILURE TO COMPLY WITH CONDITIONS OF CONSTRUCTION PERMIT

"50.55(e) initial notification for failure to comply with requirements of 10 CFR 50 Appendix B, Criterion VII for procurement of safety-related components associated with AP1000 Nuclear Power Plant construction by CB&I (formerly Shaw Nuclear).

"This 50.55(e) initial notification addresses a failure to comply by CB&I, an agent of South Carolina Electric & Gas (SCE&G) for Virgil C. Summer 2 & 3, to meet the requirements of Appendix B, Criterion VII. It is concluded that the QA programmatic issues, as identified by the root cause analysis associated with NRC violation 05200025/2012-004-02, could have produced a defect and this condition is reportable in accordance with 10 CFR 50.55(e)(3)(iii)(C). The root cause of the programmatic procurement problems was that the existing Shaw Nuclear procurement and quality oversight and inspection program did not include a sufficiently strategic, integrated, and graded approach to assure the required quality of material, equipment, and services. This notification closes the interim report submitted on February 4, 2013 by SCE&G.

"This 50.55(e) initial notification is being submitted pursuant to the requirements of 10 CFR 50.55(e)(3)(iii)(C)."

The licensee has notified the NRC Resident Inspector.

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Part 21 Event Number: 48911
Rep Org: CRANE NUCLEAR
Licensee: CRANE NUCLEAR
Region: 3
City: BOLINGBROOK State: IL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: ROSALIE NAVA
HQ OPS Officer: STEVE SANDIN
Notification Date: 04/10/2013
Notification Time: 20:29 [ET]
Event Date: 03/25/2010
Event Time: [CDT]
Last Update Date: 04/10/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
DAVE PASSEHL (R3DO)
MALCOLM WIDMANN (R2DO)
RICK DEESE (R4DO)
NRR PART 21 GROUP (EMAI)

Event Text

PART 21 INVOLVING A POTENTIAL WELD DEFECT

The following information was received via fax as a supplement to a report originally submitted to the NRC Document Control Desk:

"This is a supplement to the above subject Part 21 letter issued by Crane Nuclear, Inc. on March 25, 2010 and NRC ref. ML100920093.

"In the referenced letter, Crane Nuclear Inc., located at [860 Remington Boulevard, Bolingbrook, Illinois 60440], filed a 10CFR21 Notification of a Potential Weld Defect to the US Nuclear Regulatory Commission and also the affected customers. Copies of these letters were provided to the NRC.

"This letter is intended to supplement that initial notification letter by providing further details on when Crane Nuclear became aware of the issue and the potential safety hazard associated with the issue.

"During the NUPIC [Nuclear Procurement Issues Committee] Audit of Crane Nuclear the week of February 2, 2010 an audit finding was issued to Crane Nuclear for not effectively reviewing a customer complaint. The complaint was relative to a potentially undersized fillet weld and the audit finding documented that Crane Nuclear did not review the issue through to completion, or with regard to potentially affecting other customers. In response to the NUPIC Audit Finding, Crane Nuclear generated a Corrective Action Report (CAR) CAR 10-22 on 03/01/10. This CAR identified two required actions and they were: 1) Create a formal procedure that ensures all customer complaints are thoroughly investigated until they are complete and that Part 21 applicability is considered for the initial complaint and the potential it affects other customers; and, 2) Evaluate the complaint on the potentially undersized fillet weld to determine if Part 21 reporting is required.

"During that NUPIC Audit, Crane was asked to provide a statement relative to the potential defect or failure and the safety hazard which is created or could be created by a potentially undersized weld and the following statement was provided to the NUPIC Audit team and as of today this statement has been provided to the customers that received the initial notification - the following is the Statement that was provided to NUPIC and the notified customers:

"Assessment of Undersized Weld on Valve Safety Function

"Auxiliary connections on valve bodies, bonnets and covers are used for drains, vents or leak-off. The welds used to attach these connections are tested as part of the pressure boundary and subjected to ASME/ANSI hydrostatic test pressure (1.5 X cold working pressure). Because the pipe nipples used are short and fairly rigid, if the lines remained capped and not connected to a piping system it is unlikely that the combined stresses due to pressure and bending at the weld due to seismic accelerations would exceed the stress due to the pressure load applied during the hydrostatic test. However, a complete and instantaneous failure of the weld could result in a capped line becoming a missile and pressure boundary violation. If a line was connected to a piping system, if properly supported it is also unlikely the welded joint would see loads that would over stress the weld. However, if loads were generated at the welded connection that exceeded the strength of the weld a crack could be initiated and the pressure boundary violated.

"In response to the first required corrective action, Crane Nuclear created and released a robust customer complaint procedure CCP-1 titled, 'Customer Complaint Procedure.' This procedure requires a documented management review by the Customer Service Manager, Engineering Manager, Site Leader and Quality Director, for each and every customer complaint. The complaint form requires completion of a 'yes or no' check box that needs to be completed with respect to 10CFR21 applicability and it also has a 'yes or no' check box to document whether other customers are affected.

"In response to the second required action on the CAR, all Crane Nuclear designs with any kind of bleed off or other venting/leak type designs using fillet welds were isolated and each inspection 'as-built' record for each design and order were reviewed. The review of the 'as-built' inspection records confirmed that the fillet welds were in compliance with the drawing except for potentially those that were identified in the Part 21 notification referenced above. The review of all inspection documentation was completed on Friday March 19th and in accordance with our procedure the President was notified at 8:48PM that evening and the notification was completed on March 2, 2010. CAR 12-26 was later generated on 07/27/12 and closed on 08/21/12 for filing the report on the 6th day. If you have any further questions please contact [Rosalie Nava] at one of the following, phone 630-226-4940, email rnava@cranevs.com., or by fax 630-226-4646."

Affected licensees include Dominion, Duke Energy, Omaha Public Power District and TVA Nuclear.

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Power Reactor Event Number: 48912
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: MARK MITCHELL
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/10/2013
Notification Time: 20:40 [ET]
Event Date: 04/10/2013
Event Time: 09:52 [PDT]
Last Update Date: 04/10/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RICK DEESE (R4DO)

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

REACTOR BUILDING STACK ACCESS DOOR NOT FULLY CLOSED

"On April 10, 2013, at 0952 [PDT] it was discovered that an access door to the reactor building stack was not fully closed. The door was subsequently closed by operations. On March 16, 2013, the reactor building exhaust flow rate took a step change decrease. Initially the reduction in flow was thought to be a reactor building ventilation damper issue. On April 3, 2013, after walkdown of the reactor building dampers and verification of proper system lineup, the reactor building exhaust flow rate monitor was declared inoperable and a substitute value was used for the exhaust flow rate in accordance with station procedures.

"Had an actual event involving an offsite release occurred during the time period from March 16, 2013, to April 3, 2013, an inaccurate reactor building exhaust flow rate might have been used to calculate offsite dose. This would only impact dose calculations at lower doses and potentially delay declaration of an Unusual Event. This is being reported as a major loss of assessment capability. At higher dose rates, the reactor building ventilation isolates and Standby Gas Treatment is operated. Standby Gas Treatment flow rate measurement would be unaffected. The intermediate and high range radiation monitors for the reactor building effluent remained fully functional and would have provided an accurate measure of activity concentration.

"Upon closure of the reactor building stack door, the reactor building exhaust flow rate returned to normal and emergency preparedness assessment capability was restored."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 48913
Facility: SAN ONOFRE
Region: 4 State: CA
Unit: [ ] [2] [3]
RX Type: [1] W-3-LP,[2] CE,[3] CE
NRC Notified By: ADAM MANELLA
HQ OPS Officer: PETE SNYDER
Notification Date: 04/11/2013
Notification Time: 04:29 [ET]
Event Date: 04/10/2013
Event Time: 23:26 [PDT]
Last Update Date: 04/11/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
RICK DEESE (R4DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Cold Shutdown 0 Cold Shutdown
3 N N 0 Defueled 0 Defueled

Event Text

FBI NOTIFIED DUE TO DEGRADED SECURITY RADIO COMMUNICATIONS

"At 2253 PDT on 4/10/13, SONGS experienced degraded on-site radio communications during planned maintenance on radio systems. Radio communications were restored at 2315 PDT."

The licensee will notify the NRC Resident Inspector.

Page Last Reviewed/Updated Thursday, April 11, 2013
Thursday, April 11, 2013