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Event Notification Report for April 21, 2014

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
04/18/2014 - 04/21/2014

** EVENT NUMBERS **


50027 50028 50029 50043 50044 50045 50046 50047

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Agreement State Event Number: 50027
Rep Org: OHIO BUREAU OF RADIATION PROTECTION
Licensee: BP HUSKY REFINERY
Region: 3
City: TOLEDO State: OH
County:
License #: 31201 49 0001
Agreement: Y
Docket:
NRC Notified By: KARL VON AHN
HQ OPS Officer: DONALD NORWOOD
Notification Date: 04/11/2014
Notification Time: 09:00 [ET]
Event Date: 04/10/2014
Event Time: [EDT]
Last Update Date: 04/11/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
PATTY PELKE (R3DO)
FSME EVENTS RESOURCE (EMAI)

Event Text

PROCESS GAUGE WITH SOURCE EXPOSED

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

"The assistant RSO of BP Husky refinery called the Ohio Department of Health Bureau of Radiation Protection [Department] at 0933 EDT on April 10, 2014 to report an incident that happened overnight.

"Thermo Fisher had been contracted to remove an old Ohmart gauge for disposal. During the removal of the gauge, the gauge and the gauge rigging fell. The gauge was still attached to the source well and was being removed as a single unit. The damaged gauge fell and became stuck inside the vessel tower skirt. During the fall, the gauge was damaged and the source became exposed. The dose rate from the device is 640 mRem/hr at 1 ft. The area, which is located inside a secured refinery, is roped and barricaded. No personnel were injured during the incident.

"The gauge is an Ohmart SHRM-BW. It contained 1000 mCi of Cs-137 when installed in 1966.

"The Department sent an inspector to the site to observe the source and gauge recovery efforts on April 10, 2014. VEGA (the successor company of Ohmart) sent a field service representative to provide technical assistance. As of 1830 CDT on April 10, 2014, efforts to return the source to the shielded position were unsuccessful.

"The Department continues to monitor efforts to secure the source in a shielded position."

* * * UPDATE FROM KARL VON AHN TO CHARLES TEAL ON 4/11/14 AT 1556 EDT * * *

"At 1530 EDT on April 11, 2014, the BP Husky Refinery RSO called the Department to report that the VEGA and Thermo Fisher service personnel were able to retract the sealed source back into the shielded position. A preliminary check of the sealed source leak tests did not indicate any leakage of the sealed source."

Notified R3DO (Pelke) and FSME Events Resource.

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Non-Agreement State Event Number: 50028
Rep Org: QAL-TEK ASSOCIATES
Licensee: QAL-TEK ASSOCIATES
Region: 4
City: IDAHO FALLS State: ID
County:
License #: 11-27610-01
Agreement: N
Docket:
NRC Notified By: MONTE POPE
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/11/2014
Notification Time: 15:50 [ET]
Event Date: 04/11/2014
Event Time: [MDT]
Last Update Date: 04/17/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
20.2201(a)(1)(i) - LOST/STOLEN LNM>1000X
Person (Organization):
JAMES DRAKE (R4DO)
FSME EVENTS RESOURCE (EMAI)
CANADA (FAX)

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

Event Text

MOISTURE DENSITY GAUGE LOST DURING SHIPMENT

The licensee shipped a moisture density gauge to a customer in Billings, Montana. However, the customer notified the licensee that the package had not arrived.

The licensee contacted the common carrier. The common carrier was able to confirm that they had weighed the package at their facility in Salt Lake City, Utah on 4/5/14 and it was scanned at that same facility on 4/9/14. The common carrier said that the normal routing for the package is through the Denver, Colorado office. A search of that facility did not find the package.

The moisture density gauge is a Troxler Model 3440 containing 8 mCi of Cs-137 and 40 mCi of Am/Be as of 2004.

* * * UPDATE FROM MONTE POPE TO DANIEL MILLS ON 4/17/2014 AT 1318 EDT * * *

The licensee notified NRC that the moisture density gauge was found by the common carrier at the Denver, Colorado office. The gauge was found undamaged, and indications are that the gauge never left the Denver office. The common carrier delivered the gauge to the correct address on 4/17/14.

Notified R4DO (Gaddy), FSME (Email), and Canada (Fax).

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: 50029
Rep Org: COLORADO DEPT OF HEALTH
Licensee: AG WASSENAAR, INC
Region: 4
City: UNKNOWN State: CO
County:
License #: CO 212-01
Agreement: Y
Docket:
NRC Notified By: PHILLIP PETERSON
HQ OPS Officer: CHARLES TEAL
Notification Date: 04/11/2014
Notification Time: 21:29 [ET]
Event Date: 04/11/2014
Event Time: [MDT]
Last Update Date: 04/11/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
JAMES DRAKE (R4DO)
FSME EVENTS RESOURCE (EMAI)

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

Event Text

AGREEMENT STATE REPORT - MISSING/LOST PORTABLE GAUGE

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

"The State of Colorado needs to report a missing/lost portable gauge. The licensee is AG Wassenaar, Inc. (Colorado license number CO 212-01). The gauge is a Troxler model 3430, serial number 36856 with 333 MBq (9 mCi) of Cs-137 and 1.63 GBq (44 mCi) Am-241:Be.

"The technician who was using the gauge was working at one job site and then drove to a 2nd job site. The technician cannot remember if he placed the portable gauge in the transportation box or not, and whether or not the gauge was secured for transport appropriately. When the technician arrived at the 2nd job site at approximately 1430 MDT on 4/11/14, he noticed that the gauge was missing. The technician and radiation safety officer have traveled the area between the two job sites and were not able to locate the missing gauge. The licensee reported the missing gauge at approximately 1750 MDT on 4/11/14.

"The investigation by the licensee and the Department [State of Colorado] is ongoing."

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: 50043
Facility: COMANCHE PEAK
Region: 4 State: TX
Unit: [ ] [2] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JOHN RASMUSSEN
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/18/2014
Notification Time: 14:35 [ET]
Event Date: 04/18/2014
Event Time: 12:52 [CDT]
Last Update Date: 04/18/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
VINCENT GADDY (R4DO)

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

Event Text

CABLE ROUTING UNANALYZED FOR FIRE SAFE SHUTDOWN BARRIER

"While implementing a multiple spurious operations (MSO's) modification during a refueling outage, it was identified that a fire safe shutdown cable routing location may have been in question. On 04/18/2014 at 1252 CDT, it was determined that this cable was routed through a cable tray that was not designed to have a fire safe shutdown barrier. This created an unanalyzed condition that significantly degrades plant safety, consistent with NUREG 1022, Rev. 3 guidance.

"This cable is associated with a Motor Operated Valve (MOV) used to isolate the containment sump from the Residual Heat Removal (RHR) pump suction during normal system operations.

"Compensatory measures in this area were already in effect for the resolution of MSO's scenarios. The compensatory measures assure the Systems, Structures, and Components (SSC's) associated with this cable remain operable."

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 50044
Facility: SUMMER
Region: 2 State: SC
Unit: [1] [ ] [ ]
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: MIKE MOORE
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/18/2014
Notification Time: 22:55 [ET]
Event Date: 04/18/2014
Event Time: 20:39 [EDT]
Last Update Date: 04/18/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
ALAN BLAMEY (R2DO)

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

Event Text

DEGRADED CONDITION DUE TO REACTOR HEAD VESSEL PENETRATION INDICATIONS

"On April 18, 2014, V.C. Summer Nuclear Station (VCSNS) Unit 1 identified 3 reactor vessel head penetrations (9, 43 and 51) that did not meet the requirements of 10 CFR 50.55a(g)(6)(ii)(D) and ASME Code Case N-729-1. The station is in a refueling outage (RF21) and the plant is currently shutdown and defueled. The reactor vessel head contains a total of 66 penetrations and the volumetric inspection efforts are complete.

"The indications are not through wall as indicated by volumetric and bare metal visual inspections. The penetrations will be repaired to meet the requirements of 10 CFR 50.55a prior to returning the vessel head to service. The inspection results are reportable pursuant to 10 CFR 50.72(b)(3)(ii)(A).

"The NRC Resident Inspector has been notified. The licensee will notify the State of South Carolina and local counties."

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Power Reactor Event Number: 50045
Facility: MILLSTONE
Region: 1 State: CT
Unit: [ ] [2] [ ]
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: TODD STRINGFELLOW
HQ OPS Officer: DANIEL MILLS
Notification Date: 04/19/2014
Notification Time: 11:53 [ET]
Event Date: 04/19/2014
Event Time: 11:00 [EDT]
Last Update Date: 04/19/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
ART BURRITT (R1DO)

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

Event Text

LOSS OF ASSESSMENT CAPABILITY DUE TO PLANNED MAINTENANCE ON MAIN STEAM LINE RADIATION MONITORS

Main steam line radiation monitors RM-4299A, RM4299B, RM4299C will be removed from service for a period of approximately 4 days during planned maintenance on the power supplies. This constitutes a loss of assessment capability. The radiation monitors will be returned to service following maintenance.

The licensee has notified the NRC Resident Inspector, the State of Connecticut, and the local government.

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Power Reactor Event Number: 50046
Facility: BRUNSWICK
Region: 2 State: NC
Unit: [ ] [2] [ ]
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MITCH STACY
HQ OPS Officer: JEFF ROTTON
Notification Date: 04/20/2014
Notification Time: 08:08 [ET]
Event Date: 04/20/2014
Event Time: 02:15 [EDT]
Last Update Date: 04/20/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
ALAN BLAMEY (R2DO)

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

LOSS OF SECONDARY CONTAINMENT DUE TO OPENING IN REACTOR BUILDING ROOF DRAIN PIPING

"Due to openings found in degraded roof drain piping, Brunswick Nuclear Power Plant Unit 2 secondary containment was declared inoperable at 0215 [EDT] on 04/20/2014. During operator rounds the Reactor Building Aux Operator noted rainwater coming out of a roof drain line into the Reactor building. Upon further investigation a rusted area 2 foot by 2 inches was found on the pipe. Several through wall holes were found in this rusted area and the remainder of the rusted area was allowing water to weep through. The openings resulting from the through wall holes and rusted area exceeded the allowable openings in secondary containment, and this would have challenged secondary containment from performing its safety function. This event did not result in any adverse impact to the health and safety of the public. This is a non-emergency notification.

"INITIAL SAFETY SIGNIFICANCE EVALUATION: At the time that is was discovered that Unit 2 Secondary Containment was inoperable. Unit 2 was at 100% steady state conditions. Reactor building ventilation was in service in a normal alignment. The Unit 2 reactor building differential pressure was normal during the entire time secondary containment was inoperable. At no time was there a release of radioactive material from Unit 2 secondary containment.

"CORRECTIVE ACTIONS: The Unit 2 reactor building roof drain line has had a temporary repair applied. This repair has been evaluated by the Engineering department with site procedures and meets the requirements to maintain Secondary Containment operable. Unit 2 Secondary Containment operability was restored at 04/20/2014 0600 [EDT]."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 50047
Facility: WOLF CREEK
Region: 4 State: KS
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP
NRC Notified By: P.C. MOORE
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/20/2014
Notification Time: 19:58 [ET]
Event Date: 04/20/2014
Event Time: 14:42 [CDT]
Last Update Date: 04/20/2014
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
VINCENT GADDY (R4DO)

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

EMERGENCY CORE COOLING SYSTEM PIPING LEAK WHILE SHUTDOWN

"A leak was discovered in the area of EPV0109, COMBINED SI/RHR [Safety Injection/Residual Heat Removal] TO ACCUMULATOR D OUTLET LINE VENT. The leak rate was estimated at 2.5 gallons per hour. The plant is in Mode 5, RCS [Reactor Coolant System] depressurized.

"This leak is considered a material problem that causes abnormal degradation of or stress upon the reactor coolant system pressure boundary, reportable in accordance with 10CFR 50.72(b)(3)(ii)(A).

"Efforts are underway to characterize the leak and plan for repairs. The leak has been secured after realigning RHR cooling from the B to the A train.

"The Resident Inspector has been notified."

The cause of the leak is being investigated.

Page Last Reviewed/Updated Wednesday, May 14, 2014
Wednesday, May 14, 2014