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Event Notification Report for January 18, 2019

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
1/17/2019 - 1/18/2019

** EVENT NUMBERS **


53752 53804 53820 53821 53832 53833 53834 53837

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!!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 53752
Facility: MILLSTONE
Region: 1     State: CT
Unit: [] [2] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: RYAN ROBILLARD
HQ OPS Officer: DAN LIVERMORE
Notification Date: 11/25/2018
Notification Time: 02:47 [ET]
Event Date: 11/24/2018
Event Time: 20:15 [EST]
Last Update Date: 01/18/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RAY POWELL (R1DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N N 0 Cold Shutdown 0 Cold Shutdown

Event Text

LOSS OF CONTROL ROOM ENVELOPE DUE TO DOOR FAILURE

"On 11/24/18 at 2015 EST, a loss of Control Room Envelope (CRE) was declared due to failure of the control room boundary door, 204-36-008. [Abnormal Operating Procedure 8588A Mitigating Actions for Control Boundary Breach was implemented]. The door was repaired at 2030 EST, restoring CRE to operable [status]."

A mechanical failure of the control room door latch prevented the door from closing.

The licensee notified the NRC Resident Inspector.



* * * RETRACTION ON 01/18/19 AT 1457 EST FROM GARY CLOSIUS TO JEFFREY WHITED * * *

"The purpose of this call is to retract a report made on November 25, 2018, NRC Event Number EN53752.

"NRC Event Report number EN53752 describes a condition at Millstone Power Station Unit 2 (MPS2) in which a control room envelope boundary door was discovered to not be able to fully close due to the latching mechanism being stuck in the extended position.

"The condition was reported to the NRC pursuant to 10 CFR 50.72(b)(3)(v)(D) via an 8-hour prompt report as an event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.

"Upon further review, MPS2 determined that there was no loss of safety function. An engineering evaluation determined that even with the control room boundary door unable to be fully closed due to the latching mechanism being stuck in the extended position, control room air in-leakage would not have been sufficient to prevent the control room emergency ventilation system from performing its safety function.

"Therefore, this condition is not reportable and NRC Event Number EN53752 is being retracted.

"The basis for this conclusion has been provided to the NRC Resident Inspector."

Notified the R1DO (Carfang).

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Agreement State Event Number: 53804
Rep Org: WA OFFICE OF RADIATION PROTECTION
Licensee: SWEDISH MEDICAL CENTER
Region: 4
City: SEATTLE   State: WA
County:
License #: WN-M008-1
Agreement: Y
Docket:
NRC Notified By: ANDREW HALLORAN
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 12/21/2018
Notification Time: 15:55 [ET]
Event Date: 12/19/2018
Event Time: 00:00 [PST]
Last Update Date: 01/17/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RYAN ALEXANDER (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - RADIOACTIVE SOURCE FAILS LEAK TEST

The following report was received via e-mail:

"A routine leak test at the Swedish Cancer Institute found a leaking Cs-137 e-vial source in the Physics Lab. The initial leak test was taken 12/19/2018 and analyzed on 12/20/2018. It revealed an activity of approximately 10 nanoCuries, and additional confirmation tests found contamination above the regulatory threshold for a leaking source.

"The source was immediately removed from service, contained within multiple non-permeable barriers, and placed into a larger pig while it is being held for disposal. Surveys of the original storage pig and the hot lab where the source was utilized found no removable contamination and there was no personnel contamination detected.

"The RSO [Radiation Safety Officer] was notified of the positive results the morning of 12/21/2018 and provided notification to DOH [Washington State Department of Health] at 1114 PST on 12/21/2018."


* * * UPDATE ON 01/17/2019 AT 1201 EST FROM ANDREW HALLORAN TO JEFFREY WHITED * * *

The following report was received via e-mail:

"A leaking sealed source was discovered at The Swedish Cancer Institute during periodic leak tests performed by the health physics staff. The source (MED3550 Gamma Reference Standard, SN 11345, Cs-137, initial activity 209.6 micro-Ci, reference date 8/1/2001) was used in the A Level Physics Lab as part of routine radiation oncology operations. The source was initially received by Swedish 12/6/2007.

"The sample was collected on 12/19/2018 using an alcohol wipe, and analyzed on 12/20/2018 using a Ludlum 261 single channel analyzer coupled with a NaI well detector. The system was set to detect the 662 keV photon energy for Cs-137, with a calculated efficiency of 11.71 percent. The result of the wipe test analysis was a removable activity of 9.92 Nano-Ci, above the 5 Nano-Ci threshold for a leaking source.

"After the RSO was notified of the positive result on 12/21/2018, the source was immediately removed from service, contained within multiple non-permeable barriers, and placed into a lead pig. The pig is currently being stored in the Radiation Safety Office Lab awaiting disposal. Wipes of the A Level Physics Lab source storage cabinet and all surfaces of the pig used to house the source when it was in service yielded no detectable removable contamination.

"After reviewing the final report of the licensee, this event is now closed as of 1/3/2018. DOH will verify that the source has been disposed of during the next routine inspection of the licensee."

Washington Event Report ID: WA-18-031

Notified R4DO (Drake) and NMSS Event Notification (e-mail).

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Agreement State Event Number: 53820
Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: H & H X-RAY SERVICES, INC
Region: 4
City: WEST MONROE   State: LA
County: RED RIVER PARISH
License #: LA-2970-L01
Agreement: Y
Docket:
NRC Notified By: JOSEPH NOBLE
HQ OPS Officer: ANDREW WAUGH
Notification Date: 01/10/2019
Notification Time: 13:32 [ET]
Event Date: 01/08/2019
Event Time: 00:30 [CST]
Last Update Date: 01/10/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CALE YOUNG (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - UNABLE TO RETRACT RADIOGRAPHY SOURCE

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

"On 01/08/2019, 1535 CST, [the licensee] called the Louisiana Department of Environmental Quality (LDEQ) to report a source would not retrieve back into the shielded position. The event happened at approximately 0030 CST at a temporary jobsite in Loggy Bayou, LA Red River Parish.

"The camera was being used at this temporary jobsite. The exposure was made and the source would not retract into the shielded position. The reportable event was the 'drive cable' in the crankout handle broke in the associated equipment being used with this QSA Global, Model 880 Delta gamma camera/exposure device. The SN for the 880D is #14342. The device was loaded with 72.7 Ci of Ir-192 with the SN# 73586G.

"The Industrial Radiography Crew followed the H & H Safety Procedures and contacted the radiation safety officer. A three-man crew performed the source retrieval and equipment evaluation after the repair/fix. The exposure device was put back into service after the repair. Two personnel involved in this retrieval received exposures of 40 mrem and the other individual's exposure was 50 mrem. The Industrial Radiography Crew's pocket dosimeter readings were 13 mrem and 11 mrem for the shift when the incident occurred. There were no excessive exposures associated with this event."

Event Report ID No.: LA-190001

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Agreement State Event Number: 53821
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: ARLANXEO USA LLC
Region: 4
City: ORANGE   State: TX
County:
License #: L06785
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: ANDREW WAUGH
Notification Date: 01/10/2019
Notification Time: 17:25 [ET]
Event Date: 01/10/2019
Event Time: 00:00 [CST]
Last Update Date: 01/10/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CALE YOUNG (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - DAMAGED GAUGE

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

"On January 10, 2019, during a routine gauge inspection/shutter check, the handle broke off the rod that turns the shutter on an Ohmart Model HM-10 source holder which contained 5,000 milliCuries of cesium-137 (original activity) (SN: 6967). The shutter is in the closed position and there is no risk of exposure. External corrosion was observed. The licensee plans, at this time, to replace the gauge and further evaluation will be performed at the time of replacement. More information will be provided as it is obtained in accordance with SA-300."

Texas Incident #: I-9649

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Power Reactor Event Number: 53832
Facility: VOGTLE
Region: 2     State: GA
Unit: [3] [4] []
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: LINDSEY GRISSOM
HQ OPS Officer: CATY NOLAN
Notification Date: 01/17/2019
Notification Time: 16:00 [ET]
Event Date: 01/17/2019
Event Time: 08:45 [EST]
Last Update Date: 01/17/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
NICOLE COOVERT (R2DO)
FFD GROUP (EMAIL)
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

FITNESS-FOR-DUTY - CONTRACTOR SUPERVISOR CONFIRMED POSITIVE FOR ALCOHOL

A non-licensed contractor supervisor had a confirmed positive for alcohol during a for-cause fitness-for-duty test. The contractor's access to the plant has been terminated.

The NRC Resident Inspector has been notified.

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Part 21 Event Number: 53833
Rep Org: WESCHLER INSTRUMENTS
Licensee: WESCHLER INSTRUMENTS
Region: 1
City: CORAL SPRINGS   State: FL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: NANCY HUGHES
HQ OPS Officer: CATY NOLAN
Notification Date: 01/17/2019
Notification Time: 14:50 [ET]
Event Date: 01/11/2019
Event Time: 00:00 [EST]
Last Update Date: 01/17/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
ERIN CARFANG (R1DO)
NICOLE COOVERT (R2DO)
PATRICIA PELKE (R3DO)
JAMES DRAKE (R4DO)
- PART 21/50.55 REACTORS (EMAIL)

Event Text

PART 21 - POTENTIAL DEFECT IN WESCHLER KX-241AXIAL, VX-252, AND VC-252 INSTRUMENT MODELS

The following is a summary of the Part 21 report:

There is a potential defect identified in Weschler KX-241 axial, VX-252, and VC-252 instrument models. The condition could result in the instrument's inability to perform its safety-related function, which is accurate indication of a measured process. The symptom of this inability to perform its safety-related function is changing indication, which is not accurately reflective of the monitored process. This symptom may exhibit as a wandering indication or difficulty in maintaining a stable zero scale setting.

The condition is due to a dimension of a component of the assembly being beyond lower tolerance limits. The part, known as the insulating bushing, is part number 186N051H01. It is used as one of the two anchor and centering points for the part of the instrument that the pointer is attached to.

The subject instrument models are and have been sold as commercial, nuclear designated and nuclear safety-related.

The affected production period is from August 15, 2018, when the non-compliant bushings were received from the supplier, through January 11, 2019, when the condition was discovered by production personnel.

The initial analysis of the movement of bushings through inventory suggests that non-conforming bushings may not have been used on safety-related instruments, or were used in a quantity of less than 10 units.

If you have any questions related to this information please contact:
Nancy Hughes
Quality Assurance Manager
Weschler Instruments
Division of Hughes Corporation
4000 N.W. 121" Ave.
Coral Springs, Florida 33065
Email: nancy.hughes@weschler.com

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Power Reactor Event Number: 53834
Facility: WATERFORD
Region: 4     State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: KEVIN HALE
HQ OPS Officer: JEFFREY WHITED
Notification Date: 01/17/2019
Notification Time: 23:07 [ET]
Event Date: 01/17/2019
Event Time: 18:58 [CST]
Last Update Date: 01/17/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
JAMES DRAKE (R4DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N N 0 Refueling 0 Refueling

Event Text

RELEVANT INDICATION OF DEGRADED CONDITION

"This is a non-emergency notification from Waterford 3.

"On January 17, 2019, a relevant indication was detected in the performance of Phased Array Ultrasonic Examinations of A600 Dissimilar Metal Piping Welds during planned inspections. The indication was observed during the analysis of data recorded of the Reactor Coolant System (RCS) Loop 1A Reactor Coolant Pump Suction Drain Nozzle to Safe-End Butt Weld (07-009). This indication does not meet applicable acceptance criteria under American Society of Mechanical Engineers (ASME) Section Xl.

"The plant was in Mode 6 (Refueling) at 0 percent power for a planned refueling outage at the time of discovery. The condition will be resolved prior to plant startup. This condition has no impact to the health and safety of the public. This report is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A), 'Any event or condition that results in: (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded,' because an indication was found that did not meet acceptance criteria referenced in ASME Section Xl. IWB-3514-2 and Code Case N-770-2, 3132.

"The NRC Resident Inspector has been notified.

"Reference: CR-WF3-2019-0967"

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Power Reactor Event Number: 53837
Facility: WATERFORD
Region: 4     State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: JERRY BROWN
HQ OPS Officer: JEFFREY WHITED
Notification Date: 01/18/2019
Notification Time: 17:03 [ET]
Event Date: 01/18/2019
Event Time: 13:33 [CST]
Last Update Date: 01/18/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
JAMES DRAKE (R4DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N N 0 Refueling 0 Refueling

Event Text

REACTOR COOLANT SYSTEM WELD DOES NOT MEET ACCEPTANCE CRITERIA

"This is a non-emergency notification from Waterford 3.

"On January 18, 2019, a relevant indication was detected in the performance of Phased Array Ultrasonic Examinations of A600 Dissimilar Metal Piping Welds during planned inspections. The indication was observed during the analysis of data recorded of the Reactor Coolant System (RCS) Loop 2A Reactor Coolant Pump Suction Drain Nozzle to Safe-End Butt Weld (11-007). This indication does not meet applicable acceptance criteria under American Society of Mechanical Engineers (ASME) Section XI. The plant was in Mode 6 (Refueling) at 0 percent power for a planned refueling outage at the time of discovery. The condition will be resolved prior to plant startup. This condition has no impact to the health and safety of the public. This report is being made in accordance with 10 CFR 50 .72(b)(3)(ii)(A), 'Any event or condition that results in: (A) The condition of the nuclear power plant, including its principal safety barriers, being seriously degraded,' because an indication was found that did not meet acceptance criteria referenced in ASME Section XI , IWB-3514-2 and Code Case N-770-2, 3132.

"The NRC Resident Inspector has been notified.

"Reference: CR-WF3-2019-01041"


Page Last Reviewed/Updated Friday, May 03, 2019
Friday, May 03, 2019