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Event Notification Report for January 17, 2019

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
1/16/2019 - 1/17/2019

** EVENT NUMBERS **


53804 53828 53829 53830 53831 53832 53833 53834

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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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Power Reactor Event Number: 53828
Facility: FITZPATRICK
Region: 1     State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: JOHN WALKOWIAK
HQ OPS Officer: DONALD NORWOOD
Notification Date: 01/16/2019
Notification Time: 08:12 [ET]
Event Date: 01/16/2019
Event Time: 01:37 [EST]
Last Update Date: 01/16/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
Person (Organization):
ERIN CARFANG (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

SECONDARY CONTAINMENT DIFFERENTIAL PRESSURE EXCEEDED TECHNICAL SPECIFICATION ALLOWED VALUE

"On January 16, 2019, with James A. Fitzpatrick Nuclear Power Plant operating at 100 percent power, the Emergency and Plant Information Computer (EPIC) indicated that Secondary Containment differential pressure exceeded the Technical Specification Surveillance Requirement of greater than or equal to 0.25 inches of vacuum water gauge while isolating Reactor Building Ventilation. The Secondary Containment differential pressure was less than 0.25 inches of vacuum water gauge for approximately ten (10) seconds, and then immediately returned to greater than or equal to 0.25 inches of vacuum water gauge.

"This condition did not impact the leak tightness of Secondary Containment or the ability of the Standby Gas Treatment system to establish and maintain the required differential pressure. When Secondary Containment did not meet the Technical Specification Surveillance Requirement 3.6.4.1.1 for differential pressure, the Limiting Condition of Operation (LCO) was not met. Therefore, Secondary Containment was inoperable. This event is being reported under 10 CFR 50.72(b)(3)(v)(C)."

"The licensee has notified the NRC Resident Inspector."

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Power Reactor Event Number: 53829
Facility: DIABLO CANYON
Region: 4     State: CA
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DONALD TOWNSEND
HQ OPS Officer: THOMAS KENDZIA
Notification Date: 01/16/2019
Notification Time: 15:10 [ET]
Event Date: 01/15/2019
Event Time: 15:09 [PST]
Last Update Date: 01/16/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
JAMES DRAKE (R4DO)
FFD GROUP (EMAIL)
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

FITNESS-FOR-DUTY REPORT REGARDING A NON-LICENSED SUPERVISOR

"A non-licensed supervisor failed to disclose information as required by the fitness-for-duty program. The employee's access to the plant has been terminated.

"The NRC Resident Inspector has been informed."

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Power Reactor Event Number: 53830
Facility: FERMI
Region: 3     State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: JEFF MEYERS
HQ OPS Officer: THOMAS KENDZIA
Notification Date: 01/16/2019
Notification Time: 18:38 [ET]
Event Date: 01/16/2019
Event Time: 09:00 [EST]
Last Update Date: 01/16/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
PATRICIA PELKE (R3DO)
FFD GROUP (EMAIL)
WILLIAM GOTT (IRD)
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

SIGNIFICANT FITNESS-FOR-DUTY POLICY VIOLATION

"At 0900 EST on 01/16/2019, it was discovered that a licensee manager intentionally failed to re-approve the list of individuals granted unescorted access to verify each individual was subject to a behavioral observation program. Compensatory actions have been taken in response to this event. Personnel affected have had their access authorization suspended.

"This is reportable under the provisions of 10 CFR 26.719(b)(3) as an intentional act that casts doubt on the integrity of the Fitness-For-Duty program.

"The licensee notified the NRC Resident Inspector."

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Power Reactor Event Number: 53831
Facility: FORT CALHOUN
Region: 4     State: NE
Unit: [1] [] []
RX Type: (1) CE
NRC Notified By: SHERYL LEMIEUX
HQ OPS Officer: BRIAN P. SMITH
Notification Date: 01/16/2019
Notification Time: 23:51 [ET]
Event Date: 01/16/2019
Event Time: 19:08 [CST]
Last Update Date: 01/16/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
JAMES DRAKE (R4DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Defueled 0 Defueled

Event Text

OFFSITE NOTIFICATION DUE TO FIRE REQUIRING LOCAL FIRE DEPARTMENT RESPONSE

"At 1908 CST, a fire was reported in an unoccupied exclusion area opening (EAO) enclosure outside of the Fort Calhoun Station protected area. Offsite fire departments responded at 1923 CST and the fire was extinguished by 1930 CST. There were no injuries reported.

"The State Fire Marshal of Nebraska was notified by the Blair (Nebraska) Fire Department at approximately 1913 CST. His investigation determined the cause to be a malfunctioning heating element in a climate control unit. There was no release of radioactivity or hazardous materials."

The climate control unit was clarified to be a ceiling mounted heater in the enclosure.

The licensee notified the NRC Decommissioning Inspector.

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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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Friday, May 03, 2019