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Event Notification Report for April 12, 2013

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/11/2013 - 04/12/2013

** EVENT NUMBERS **


48809 48884 48888 48889 48913 48914 48915 48916

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 48809
Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [ ] [ ]
RX Type: [1] GE-3
NRC Notified By: JACK EARSLEY
HQ OPS Officer: VINCE KLCO
Notification Date: 03/06/2013
Notification Time: 12:52 [ET]
Event Date: 03/06/2013
Event Time: 04:01 [CST]
Last Update Date: 04/11/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
NICK VALOS (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

MOMENTARY LOSS OF SHUTDOWN COOLING

"At 0401 CST on 3/6/2013, while in RHR-High [Residual Heat Removal-High] water level the plant experienced a momentary Loss of Shutdown Cooling which resulted in a loss of safety function for Residual Heat Capability. Division 2 RHR shutdown cooling was restored within approximately 90 seconds without issue. No changes were experienced in refuel volume temperature or level during the loss of RHR shutdown cooling. This occurred shortly after a flow adjustment on the system was made utilizing the outboard valve. The inboard valve was reopened and an investigation is in progress. At the time of the valve closure, decay heat removal continued from Reactor Water Cleanup in heat reject mode and fuel pool cooling (with the fuel pool gates removed) is in service. Division 1 RHR (Shutdown Cooling) was available (not Operable) at the time of the loss. It is not currently understood why the injection valve closed. All systems functioned as required except for the spurious closing of MO-2015 (the Div 2 RHR inboard injection valve). The following make-up sources are available: Divisions 1 and 2 RHR, Divisions 1 and 2 Core Spray, CRD [Control Rod Drive], CST [Condensate Storage Tank] via a Core Spray with pressurizing station bypassed."

The licensee notified the NRC Resident Inspector.

* * * RETRACTION AT 1419 EDT ON 4/11/2013 FROM RYAN RICHARDS TO MARK ABRAMOVITZ * * *

"On March 6, 2013 (Notification No. 48809) NSPM [Northern States Power Monticello] reported in accordance with 10 CFR 50.72 (b)(3)(v)(B), a momentary closure of valve MO-2015 in the operating Residual Heat Removal (RHR) subsystem as an event or condition that at the time of discovery could have prevented the fulfillment of a safety function. Following the event, the RHR SDC [shut down cooling] subsystem was removed from operation for equipment forensics and troubleshooting. Results validated that valve MO-2015 was operable and no issues were identified with the associated electrical circuitry, or the RHR SDC subsystem. The decay heat removal requirements of LCO 3.9.7, RHR - High Water Level, were met and there was not a loss of safety function. Therefore, NSPM retracts the March 6, 2013 notification for this event."

The licensee notified the NRC Resident Inspector, state and local authorities, and may make a press release.

Notified the R3DO (Passehl).

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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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Agreement State Event Number: 48888
Rep Org: WA DIVISION OF RADIATION PROTECTION
Licensee: PEKINS ELMER
Region: 4
City: RICHLAND State: WA
County:
License #:
Agreement: Y
Docket:
NRC Notified By: KRISTEN SCHWAB
HQ OPS Officer: VINCE KLCO
Notification Date: 04/04/2013
Notification Time: 16:08 [ET]
Event Date: 03/18/2013
Event Time: [PDT]
Last Update Date: 04/04/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY KELLAR (R4DO)
FSME RESOURCES (EMAI)

Event Text

AGREEMENT STATE REPORT - SHIPMENT EXCEEDED SURFACE CONTAMINATION LIMITS

The following information was received from the Washington State Division of Radiation Protection by email:

"PermaFix Northwest received a shipment from Perkin Elmer, Inc. that consisted of 32 packages, 4 plastic drums and 28 metal drums, and was shipped as an exclusive use shipment. Upon receipt, the drums were surveyed and 2 plastic drums were found to exceed the 49 CFR 173.443 non-removable contamination limit of 2,200 dpm/cm2 for an exclusive use shipment. The drum survey results were reported as 44,391 dpm/100 cm2 H-3 and 18,080 dpm/100 cm2 C-14; 20,127 dpm/100 cm2 H-3 and 18,508 dpm/100 cm2 C-14, and 13,323 dpm/100 cm2 H-3 and 10,019 dpm/100 cm2 C-14. This most contaminated drum was manifested with only H-3 and C-14, the other 2 drums were manifested with only C-14."

Washington Incident Number: WA-13-021

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Agreement State Event Number: 48889
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: JACOBSEN CONSULTING
Region: 4
City: MODESTO State: CA
County:
License #: 6370-39
Agreement: Y
Docket:
NRC Notified By: KAMANI HEWADIKARAM
HQ OPS Officer: VINCE KLCO
Notification Date: 04/04/2013
Notification Time: 17:43 [ET]
Event Date: 04/03/2013
Event Time: [PDT]
Last Update Date: 04/04/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY KELLAR (R4DO)
FSME RESOURCES (EMAI)
MEXICO (EMAI)
ILTAB (EMAI)

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

Event Text

AGREEMENT STATE REPORT - LOST MOISTURE GAUGE

The following information was from the State of California via email:

"On 04/04/13, [the licensee] RSO, called RHB [California Radiologic Health Branch] to report a lost gauge. The gauge is a Model 503 DR CPN moisture gauge (S/N H33064926) containing 50 mCi (max) of Americium 241:Be. [The RSO] stated that he placed the gauge in the back of his truck next to the tailgate, then got distracted by a telephone call and started driving from 4181 Brew Master Dr, Suite 4, Ceres, CA, on Crows Landing, Hwy N 99 and then onto Hwy 88 without securing the gauge. He discovered the gauge missing [at 1600 PDT] on 04/03/13, upon arrival at a jobsite. The Ceres Police Department was notified of the lost gauge (case # 213-001653). Licensee was advised to place an advertisement in a local paper/craigslist offering a reward of $4000.00 for the safe return of the gauge. RHB will be investigating the incident and licensee will be cited for the items of non compliance associated with this incident."

California Report: #040413

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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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.

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Power Reactor Event Number: 48914
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: JAMES KURAS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/11/2013
Notification Time: 16:47 [ET]
Event Date: 04/11/2013
Event Time: 15:10 [CDT]
Last Update Date: 04/12/2013
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
RICK DEESE (R4DO)
JANE MARSHALL (IRD)
ART HOWELL (RA)
DAN DORMAN (NRR)
JOHN MONNINGER (NRR)

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

Event Text

UNUSUAL EVENT FOR A FIRE LASTING GREATER THAN 15 MINUTES

"The fire started at 1455 CDT in the turbine building southeast stairwell and on the auxiliary boiler room roof. Fire fighting efforts continue as fire exists inside the wall between the turbine building and the auxiliary boiler room.

The licensee notified the NRC Resident Inspector, state, and local governments.

Notified DHS, FEMA, and the NICC.

* * * UPDATE FROM WARREN BRANDT TO PETE SNYDER AT 0100 EDT ON 4/12/13 * * *

"Wolf Creek declared a NOUE at 15:10 CDT on 4/11/13 due to a fire that started at 14:55 [CDT] in the Turbine Building SE stairwell and on the Auxiliary Boiler room roof. The fire was extinguished at 15:19 [CDT], and cool to the touch at 16:48 [CDT]. No offsite fire response support was required. The fire did not impact any safety related equipment.

"The NOUE was terminated at 17:03 CDT 4/11/13. The cause of the fire is under investigation."

Notified R4DO (Deese), NRR EO (Monninger), IRD (Marshall), DHS, FEMA and NICC (via email).

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Power Reactor Event Number: 48915
Facility: HARRIS
Region: 2 State: NC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP
NRC Notified By: LEWIS ROGERS
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/11/2013
Notification Time: 18:19 [ET]
Event Date: 04/11/2013
Event Time: 15:41 [EDT]
Last Update Date: 04/11/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
MALCOLM WIDMANN (R2DO)

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

TECHNICAL SUPPORT CENTER COOLERS OUT OF SERVICE

"This event is reportable per 10 CFR 50.72(b)(3)(xiii) as described in NUREG-1022, based on 'Loss of Assessment' capability.

"This is a non-emergency notification. This condition does not affect the health and safety of the public or the operation of the facility. At approximately 15:41 EDT on 4/11/2013, AH-11 and AH-17, Technical Support Center (TSC) Air Handling Units' coolers were not working. The cause of the condition has not been identified. However, troubleshooting efforts are being planned and will be worked immediately.

"TSC functionality requires all areas of the TSC be maintained between 60.8 degrees F and 82.4 degrees F. Actual TSC area temperatures have reached 77 degrees F. If the facility were activated with a full staff, temperatures could rise above the 82.4 degree F limit. Should the TSC need to be activated for an event, we have compensatory measures which would include relocating the TSC to the Alternate Emergency Facility per PEP-240. This decision would be based on the existing event conditions and coordinated with the Emergency Response Manager, SEC-MCR, and Radiological Control Manager. The Alternate TSC has been verified to have electrical power, ventilation, and communication capability. The Technical Support Center-Site Emergency Coordinator has been notified."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 48916
Facility: QUAD CITIES
Region: 3 State: IL
Unit: [1] [ ] [ ]
RX Type: [1] GE-3,[2] GE-3
NRC Notified By: KEVIN HOLLE
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/11/2013
Notification Time: 21:10 [ET]
Event Date: 04/11/2013
Event Time: 13:00 [CDT]
Last Update Date: 04/11/2013
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
DAVE PASSEHL (R3DO)

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

DEGRADED ELECTRICAL CONNECTIONS

"On April 11, 2013, at 1300 hours, during the performance of On-Line Automatic Depressurization System (ADS) Blowdown Logic Testing, two poor wiring connections were identified (the electrical leads were not properly compressed at their termination point). The electrical leads are associated with the B and C ADS valves. Quad Cities has five ADS valves which can be used to depressurize the Reactor Pressure Vessel under accident conditions. While the solenoids of these valves were actuated successfully during the recent Unit 1 refueling outage (which ended on April 8, 2013), the less than optimum configuration could have prevented the valves from actuating under design basis conditions. The degraded wiring for both valves was restored at 1741 hours [CDT].

"Given the potential impact on the ADS depressurization function, this event is reportable under 50.72(b)(3)(v)(D) as an event or condition that could have prevented the fulfillment of a safety function."

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Friday, April 12, 2013
Friday, April 12, 2013