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Event Notification Report for February 10, 2015

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
02/09/2015 - 02/10/2015

** EVENT NUMBERS **


49700 50746 50779 50780 50787 50797 50798 50799 50800

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 49700
Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [ ] [ ]
RX Type: [2] GE-5
NRC Notified By: QUOC VO
HQ OPS Officer: DAN LIVERMORE
Notification Date: 01/07/2014
Notification Time: 16:07 [ET]
Event Date: 01/07/2014
Event Time: 12:10 [PST]
Last Update Date: 02/09/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
BOB HAGAR (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 MONITOR TEMPORARILY OUT OF SERVICE FOR MAINTENANCE

"At 1210 PST on January 7, 2014 the Reactor Building Stack Radiation Monitor- Intermediate Range detector was declared non-functional due to scheduled maintenance on supporting equipment. The monitor is expected to be out of service for approximately 1 hour. Preplanned compensatory actions have been implemented.

"This event is being reported as a loss of emergency assessment capability in accordance with 10 CFR 50.72(b)(3)(xiii).

"At 1238 PST on January 7, 2014 the Reactor Building Stack Radiation Monitor -Intermediate Range detector was declared functional following scheduled maintenance on supporting equipment. Emergency Assessment Capability has been restored. Preplanned compensatory actions have been secured.

"The licensee has notified the NRC Resident Inspector."

* * * RETRACTION FROM MATT REID TO DANIEL MILLS AT 1636 EST ON 02/09/2015 * * *

"Licensee is retracting this event notification based on the following: Regulatory guidance in NUREG-1022 Revision 3 allows for not reporting EP equipment outages that are planned (i.e., maintenance) when outage time is not expected to exceed or does not exceed 72 hours, and when there are viable compensatory measures in place. Verification of the Control Room Logs indicates Columbia had viable compensatory measures in place during the maintenance outage and the outage duration was less than 72 hours. Columbia met the conditions in NUREG-1022; therefore, this event did not represent a loss of emergency assessment capability."

The licensee has notified the NRC Resident Inspector.

Notified R4DO (Allen).

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Agreement State Event Number: 50746
Rep Org: NJ RAD PROT AND REL PREVENTION PGM
Licensee: THE COLLEGE OF NEW JERSEY
Region: 1
City: EWING State: NJ
County:
License #: 507375
Agreement: Y
Docket:
NRC Notified By: JAMES T MCCULLOUGH
HQ OPS Officer: VINCE KLCO
Notification Date: 01/20/2015
Notification Time: 15:44 [ET]
Event Date: 01/14/2015
Event Time: [EST]
Last Update Date: 02/09/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY MCKINLEY (R1DO)
NMSS EVENTS (EMAI)
ILTAB (EMAI)

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

Event Text

AGREEMENT STATE REPORT - LOST GENERALLY LICENSED TRITIUM EXIT SIGNS

The following information was received by email:

"Event Description: A specific licensee reported the loss (potential theft) of two generally licensed tritium (H-3) exit signs. The signs had been removed from installation and are missing from the storage location. The licensee became aware of the missing material on 1/14/2015, however, it is possible the material was missing for approximately one month. The devices were last seen by licensee staff in mid-December 2014. Specific details about the device model and activity have not yet been provided, potentially up to 15 Ci H-3 per device. An NJDEP [New Jersey Department of Environmental Protection] inspector will visit the site to investigate the incident."

New Jersey Event: #C545467

* * * UPDATE FROM JAMES MCCULLOUGH TO JEFF HERRERA ON 2/9/15 AT 1638 EST * * *

The following update was received from the New Jersey Department of Environmental Protection via email:

"The College of New Jersey (TCNJ) reported the loss or possible theft of two radioluminescent exit signs. The signs had been removed from installation and were placed into storage. The signs were discovered to be missing from the storage location on 1/14/2015. However, TCNJ stated that it was possible the signs had been missing for approximately one month. The signs were last seen by TCNJ in mid-December 2014. Each sign contained approximately 137 GBq (3.7 Ci) of H-3. A New Jersey Department of Environmental Protection inspector visited the site on 1/21/2015 and determined the most likely scenario was accidental disposal. The licensee submitted a full report in accordance with N.J.A.C. 7:28-6.1 [10 CFR 20.2201]. The missing signs were not located. Although there was no evidence of contamination, the licensee estimated a dose of 8.5 mrem if the signs had been broken.

"NJDEP tracked the event as Incident # C545467 and Investigation #: 507375-INV15001.

"Corrective Actions: Commitment to increased security should they be in possession of other sources. [The College of New Jersey] reports no inventory of generally licensed devices.

"Device Number: 1
Device/Equipment: RADIOLUMINESCENT EXIT SIGN
Model Number: LE
Manufacturer: SAFETY LIGHT CORP
Serial Number: 201864

"Device Number: 2
Device/Equipment: RADIOLUMINESCENT EXIT SIGN
Model Number: LE
Manufacturer: SAFETY LIGHT CORP
Serial Number: 201865"

Notified R1DO(Powell), NMSS Events Notification and ILTAB (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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Agreement State Event Number: 50779
Rep Org: CALIFORNIA RADIATION CONTROL PRGM
Licensee: GILES ENGINEERING ASSOCIATES
Region: 4
City: ORANGE State: CA
County:
License #: 4592-30
Agreement: Y
Docket:
NRC Notified By: DONALD OESTERLE
HQ OPS Officer: CHARLES TEAL
Notification Date: 01/30/2015
Notification Time: 15:42 [ET]
Event Date: 01/30/2015
Event Time: [PST]
Last Update Date: 01/30/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
GEOFFREY MILLER (R4DO)
NMSS EVENTS NOTIFICA (EMAI)
MEXICO (FAX)
DARYL JOHNSON (ILTA)

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

Event Text

AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE

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

"On January 30, 2015, a telephone report was made to the [California Department of Public Health] CDPH Director's office that a gauge had been stolen. The person making the report was difficult to understand, but the Director's office was able to ascertain the contact telephone number. Upon receiving notice of the call, a representative from [Radiologic Health Branch] (RHB) immediately called that telephone number (at approximately 1100 PST on January 30, 2015), and spoke with the RSO of Giles Engineering Associates, RML #4592-30. [The RSO] stated that a moisture/density gauge (CPN, MC-1DRP, serial #MD20506575 containing 0.370 GBq of Cs-137 and 1.85 GBq of Am-241) had been stolen from a transport vehicle in front of a Comfort Inn at 1185 Admiral Callahan Lane, Vallejo, CA. The authorized gauge user had left the radioactive gauge chained and locked in the back of his vehicle at approximately 0600 PST and went back inside the Comfort Inn to complete some paper work. When he returned to his vehicle at approximately 0625 PST to go to the worksite, [the authorized gauge user] noticed that the chains had been cut through and that the radioactive gauge had been removed from his vehicle. [The authorized gauge user] contacted the RSO of Giles Engineering Associates, who stated he had attempted to notify Local Law Enforcement officials in Vallejo to report the theft. [The RSO] was directed to fill out a report online as that was the policy of the Vallejo Police Department in regards to all theft cases not involving immediate threats to persons. When [the RSO] receives [the authorized user's] written report and the police report, he will forward them to RHB Brea. [The RSO] will utilize local papers in the Vallejo area to attempt to retrieve the stolen gauge. Additionally he will notify local vendors who service radioactive gauges to be alert for the serial number of the stolen gauge in case it turns up at any of their facilities."

CA 5010 #: 013015

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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Agreement State Event Number: 50780
Rep Org: NE DIV OF RADIOACTIVE MATERIALS
Licensee: OMAHA PUBLIC POWER DISTRICT
Region: 4
City: OMAHA State: NE
County:
License #: 01-39-04
Agreement: Y
Docket:
NRC Notified By: BRYAN MILLER
HQ OPS Officer: JEFF ROTTON
Notification Date: 01/30/2015
Notification Time: 16:31 [ET]
Event Date: 01/30/2015
Event Time: 08:20 [CST]
Last Update Date: 02/05/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL VASQUEZ (R4DO)
NMSS EVENTS NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - FIXED GAUGE SHUTTER FAILED TO CLOSE

While attempting to close the shutter on a Kay-Ray fixed gauge at a coal fired power plant located at 24th and Craig Street in Omaha, NE, the cable operating the shutter mechanism broke. The gauge contained 50 mCi of Cs-137. Plant operators manually closed the gauge shutter. There were no exposures to workers in the area.

The state will provide additional information when it is available.

* * * UPDATE FROM BRYAN MILLER TO JOHN SHOEMAKER AT 0908 EST ON 2/5/15 * * *

The following event update was received from the State of Nebraska via email:

"The Nebraska Department of Health and Human Services, Radioactive Materials Program, was notified at 1455 hours [CST] on 01/30/2015 by the Tech. Supervisor, at Omaha Public Power District that a Kay Ray fixed gauge Model Number 7080, housing serial number 16784Y, source shutter failed to close. The device originally installed in 1984 with approximately 50 millicuries Cesium 137 now contains approximately 25 millicuries. The gauge which is part of a hopper level sensor is mounted between two fly ash hoppers approximately 20 feet off of the floor. The source closure mechanism on the gauge is connected to a handle located at floor level by a flexible cable. The closure cable are secured so that when the floor handle is operated, the control cable slides inside of the sheath thus opening/closing the shutter. One of the station's chemists was restoring the source to service following a maintenance outage. The 'external' source closure mechanism for Unit 4 precipitator was being placed in the open position when a metallic snap was heard when opening the source shutter. The source handle was half way to the open position when this noise was heard. The operator then proceeded to check the cables function by trying to move the shutter to the closed position . The source shutter did not move. Scaffolding was erected and an inspection of the device showed the source shutter was in the open position and that the cable was not connected to the gauge operating mechanism. The source shutter mechanism was moved manually to the closed position and the cable reattached and tested several times using the remote actuator. All functions were noted to be in working condition.

"No personnel were unintentionally exposed to radiation during this event.

"Cause: Defective or Failed Part.

"Corrective Action Information: Equipment maintenance and repairs made without engineering change to the system."

Device/Associated Equipment: Kay-Ray/Sensall/Fixed Gauge, Model Number 7080, Serial Number 16784Y.
Source of Radiation: Amersham, Sealed Source Gauge, Model CDC 800, Serial Number 15112-V, with a CS-137 .025 Ci source

Nebraska Item Number: NE150001

Notified the R4DO (Miller) and NMSS Events Notification via email.

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!!!!! THIS EVENT HAS BEEN RETRACTED. THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 50787
Facility: ZION
Region: 3 State: IL
Unit: [1] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAN GIERNOTH
HQ OPS Officer: DANIEL MILLS
Notification Date: 02/04/2015
Notification Time: 19:15 [ET]
Event Date: 02/03/2015
Event Time: 19:01 [CST]
Last Update Date: 02/09/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
72.75(d)(1) - SFTY EQUIP. DISABLED OR FAILS TO FUNCTION
Person (Organization):
LAURA KOZAK (R3DO)

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

Event Text

SAFETY EQUIPMENT DISABLED DUE TO SNOW

"On 2/3/2015 at 1901 [CST], equipment important to safety failed to function as designed: 33 NAC MAGNASTOR systems containing Spent Nuclear Fuel, and 1 NAC MAGNASTOR system containing GTCC [Greater than Class C] waste, had air inlet vent partial blockage, totaling 50 percent or greater, due to environmental conditions, i.e., snow. (Please Note, no VCC systems reached full blockage.)

"NO personnel radiation exposure.

"Actions Taken lAW the NAC FSAR, Rev. 5, which included actions to immediately return the systems to less than 50 percent blockage and ongoing maintenance activities to return all systems to full operability.

"Additional information:
1. On 2/4/2015 at 0445 hrs. All 34 failed systems were restored to less than 50 percent blockage.
2. lAW the NAC FSAR we have 30 days from time of discovery to return each system to full operability.
3. A report will be followed up within 60 days per 10 CFR 72.75.g"

The licensee will notify the NRC Inspector and the State of Illinois.

* * * RETRACTION FROM MARK BITTMAN TO JEFF HERRERA ON 2/9/15 AT 1736 EST * * *

"This phone notification is being made to retract an earlier '24 Hour Report' made on February 4, 2015 at 1815 CST, NRC event #50787. On February 4, 2015 at 1810 CST, Zion Station notified NRC that on February 3, 2015 at 1901 CST, Equipment Important To Safety failed to function as designed that being 33 NAC MAGNASTOR systems containing Spent Nuclear Fuel and 1 NAC MAGNASTOR containing GTCC waste had their Inlet vents partially blocked, totaling 50% or greater, due to environmental conditions, i.e. Snow.

"This appeared to meet criteria of Non-Emergency notification under 10 CFR 72.75d(1)(i).

"NAC International has provided documentation stating we have 58 hours to perform the immediate action to unblock the VCC vents to greater than 50% and 30 days to completely unblock all the vents. This documentation is attached to this notification.

"Upon further review by Exelon Management, Zion Solutions Management and NAC, using criteria established in Sections 4.3.7.1 and 12.2.2 of the SER for CoC 72-1031, Amendment 0, no limits were exceeded. Actions were immediately initiated to restore the 34 failed systems to less than 50% blockage and were completed in less than 10 Hours. This is well within the 58 hour SAR basis. This is the basis for retracting the notification.

"Based on the above, [the licensee] management concludes this event does not meet the 24-hour reporting criteria established in 10 CFR 72.75d(1)(i)."

The R3DO(Pelke) was notified.

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Power Reactor Event Number: 50797
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: MICHEL CICCONE
HQ OPS Officer: VINCE KLCO
Notification Date: 02/09/2015
Notification Time: 11:05 [ET]
Event Date: 02/09/2015
Event Time: 08:24 [EST]
Last Update Date: 02/09/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RAY POWELL (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

STACK HIGH RANGE RADIATION MONITOR OUT OF SERVICE FOR PLANNED MAINTENANCE

The Unit 2 Stack High Range Radiation Monitor (RM-8168) was removed for service for planned maintenance. There is no significant effect of this planned maintenance on the plant.

The licensee notified the NRC Resident Inspector, the State of Connecticut and Waterford township.

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Power Reactor Event Number: 50798
Facility: VOGTLE
Region: 2 State: GA
Unit: [3] [4] [ ]
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: FREDERICK WILLIS
HQ OPS Officer: JEFF HERRERA
Notification Date: 02/09/2015
Notification Time: 11:36 [ET]
Event Date: 08/25/2014
Event Time: 08:00 [EST]
Last Update Date: 02/09/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.55(e) - CONSTRUCT DEFICIENCY
Person (Organization):
ROBERT HAAG (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

BREAKDOWN IN THE QUALITY ASSURANCE PROGRAM FOR VOGTLE 3&4 CONSTRUCTION PROJECT

"This is a 10 CFR 50.55 initial notification for a significant breakdown in the Quality Assurance (QA) Program of Chicago Bridge & Iron (CB&I), an agent for the Licensee of the Vogtle 3&4 Construction Project.

"In August 2014, deviations were found in sub-modules CA03-06, -08, and -09, which initiated the discovery and evaluation processes for both Part 21 and 10 CFR 50.55 . The conditions were determined to be not reportable by CB&I under 10 CFR 21, but an evaluation of the root cause analysis results concluded that a significant QA program breakdown had occurred that could have produced a defect. No defect has been identified.

"This initial notification is being made in accordance with 10 CFR 50.55 (4)(iii) and 10 CFR 50.55 (5)(i)."

The NRC Resident Inspector will be notified.

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Part 21 Event Number: 50799
Rep Org: VALCOR ENGINEERING CORPORATION
Licensee: VALCOR ENGINEERING CORPORATION
Region: 1
City: SPRINGFIELD State: NJ
County:
License #:
Agreement: Y
Docket:
NRC Notified By: FRAN LUCANO
HQ OPS Officer: CHARLES TEAL
Notification Date: 02/09/2015
Notification Time: 17:17 [ET]
Event Date: 02/09/2015
Event Time: [EST]
Last Update Date: 02/09/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(a)(2) - INTERIM EVAL OF DEVIATION
Person (Organization):
RAY POWELL (R1DO)
ROBERT HAAG (R2DO)
PATTY PELKE (R3DO)
DON ALLEN (R4DO)
PART 21/50.55 REACT (EMAI)

Event Text

PART 21 REPORT - POSSIBLE ASSEMBLY ERROR IN SOLENOID VALVE

"[The licensee] has discovered a possible assembly error that may result in compromising the capability to isolate the solenoid housing internals from a LOCA environment on some of our solenoid valve models that use grafoil packing for sealing the NEMA 4 enclosure. We are in the process of identifying the valve models affected and will notify all customers affected."

Description of Defect/Non-Compliance:

"As noted on MRR997W the packing ring which seals the solenoid on valve model V526-5631-36 used in Qualification and Production were not matched to the procedure invoked on valve drawing."

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Power Reactor Event Number: 50800
Facility: FORT CALHOUN
Region: 4 State: NE
Unit: [1] [ ] [ ]
RX Type: (1) CE
NRC Notified By: SCOTT MOECK
HQ OPS Officer: VINCE KLCO
Notification Date: 02/10/2015
Notification Time: 01:25 [ET]
Event Date: 02/09/2015
Event Time: 17:30 [CST]
Last Update Date: 02/10/2015
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
DON ALLEN (R4DO)

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

SAFETY INJECTION TANK LEVEL RESULTS IN AN UNANALYZED CONDITION

"On October 14, 2013 a calculation for the containment internal structural analysis was revised and accepted by the station. This calculation limited the Safety injection tank level to 74%. On October 16, 2013 Safety injection tank level was raised to 100% for approximately 13 hours in preparations for plant start-up. While the plant was safely in a cold shutdown condition, this represents a reportable unanalyzed condition. This issue is of a historical nature and does not question the current operability of any plant systems or structures. This was self identified during a Fort Calhoun calculation review."

The licensee notified the NRC Resident Inspector.

Page Last Reviewed/Updated Tuesday, February 10, 2015
Tuesday, February 10, 2015