Report a Safety Concern
Search
Home NRC Library Document Collections Events, Reports Associated with Event Notification Reports 2019

Event Notification Report for September 06, 2019

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
9/5/2019 - 9/6/2019

** EVENT NUMBERS **


54243542455425654257


Agreement State Event Number: 54243
Rep Org: OR DEPT OF HEALTH RAD PROTECTION
Licensee:
Region: 4
City: HERMISTON   State: OR
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DARYL LEON
HQ OPS Officer: RICHARD SMITH 		Notification Date: 08/28/2019
Notification Time: 16:35 [ET]
Event Date: 08/28/2019
Event Time: 11:02 [PDT]
Last Update Date: 08/28/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY AZUA (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - MOISTURE DENSITY GAUGE FOUND IN SCRAP YARD

The following is a summary of information received from the State of Oregon via phone call:

On August 28, 2019, at 1102 PDT, the Oregon Department of Health and Radiation Protection received a report from the R.S. Davis Scrap Yard, that a moisture density gauge was found in a 55 gallon drum that was crimped at the top so the gauge will not fall out. The gauge is a CPN MC-3 Porta Probe with a 10 mCi Cs-137 source and a 50 mCi Am/Be 241 source. The scrap yard employed a contractor to take radiation readings and perform a swipe test of the gauge. The gauge housing appears to be damaged but the source housing seems intact. The contractor was unable to inspect the bottom of the gauge inside the drum.

The following was measured:
A reading of 13 mR/hr on contact at the side
A reading of 200 mR/hr on contact at the bottom
A reading of 3 mR/hr one foot from the side
Swipe Test results were less than background

The State of Oregon Radiation Inspector believes the gauge is damaged because normal radiation readings for a similar gauge at one meter would be 0.4 mR/hr.

The State of Oregon will be conducting an investigation of this event. The gauge is currently under the control of the scrap yard.

Oregon Event Reference Number: 19-0037.

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


Agreement State Event Number: 54245
Rep Org: OK DEQ RAD MANAGEMENT
Licensee: HOLLYFRONTIER TULSA REFINING
Region: 4
City: TULSA   State: OK
County: TULSA
License #: GLD0027
Agreement: Y
Docket:
NRC Notified By: KEVIN SAMPSON
HQ OPS Officer: BRIAN LIN 		Notification Date: 08/29/2019
Notification Time: 17:18 [ET]
Event Date: 08/28/2019
Event Time: 00:00 [CDT]
Last Update Date: 08/29/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY AZUA (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - SHUTTER FAILURE

The following was received from the Oklahoma Department of Environmental Quality via email:

"The State of Oklahoma reported that a generally-licensed Ronan Model SA-F37 fixed gauge (S/N M2265) containing 1.5 Ci of Cs-137 experienced a shutter failure during routine maintenance. The source holder is being removed from service and will be stored pending disposal."


Power Reactor Event Number: 54256
Facility: CATAWBA
Region: 2     State: SC
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: SCOTT MILTON
HQ OPS Officer: JEFFREY WHITED 		Notification Date: 09/05/2019
Notification Time: 16:53 [ET]
Event Date: 04/28/2019
Event Time: 22:00 [EDT]
Last Update Date: 09/05/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
SCOTT SHAEFFER (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

TECHNICAL SUPPORT CENTER VENTILATION SYSTEM OUT OF SERVICE DUE TO DISCOVERED CONDITION

"This is a non-emergency eight hour notification for a loss of Emergency Assessment Capability.

"A condition impacting functionality due to a loss of cooling of the Technical Support Center (TSC) ventilation system occurred on 4/28/19. Filtration capability was not impacted by this condition. Maintenance subsequently repaired the condition and the TSC ventilation system was returned to service on 5/1/19. This condition did not affect the health and safety of the public or station employees.

"The NRC Resident Inspector has been notified.

"This event is reportable in accordance with 10 CFR 50.72(b)(3)(xiii) as the discovered condition affected the functionality of an emergency response facility."


Power Reactor Event Number: 54257
Facility: SOUTH TEXAS
Region: 4     State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: MICHAEL CHANDLER
HQ OPS Officer: CATY NOLAN 		Notification Date: 09/06/2019
Notification Time: 02:47 [ET]
Event Date: 09/05/2019
Event Time: 21:15 [CDT]
Last Update Date: 09/06/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
NEIL O'KEEFE (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

CONTAINMENT PENETRATION DISCOVERED NOT ISOLATED

"At 2115 CDT on 9/5/2019, an inside containment test connection and inoperable outside containment isolation valve were discovered to be open for a containment air sample penetration. This resulted in the containment penetration not being isolated. The inside containment test connection was closed at 2322 CDT on 9/5/2019.

"This event is being reported under 10 CFR 50.72(b)(3)(v)(C) and (D) and 10 CFR 50.72(b)(3)(ii)(B).

"There was no impact to the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. "

Page Last Reviewed/Updated Wednesday, March 24, 2021