Event Notification Report for September 12, 2019

U.S. Nuclear Regulatory Commission Operations Center Event Reports For 9/11/2019 - 9/12/2019 ** EVENT NUMBERS **

 

54254

54255

54266

54267

54268

54271

54272

Agreement State	Event Number: 54254
Rep Org: MARYLAND DEPT OF THE ENVIRONMENT Licensee: MEDSTAR FRANKLIN SQUARE MEDICAL CENTER Region: 1 City: ROSSVILLE   State: MD County: License #: MD-05-032-01 Agreement: Y Docket: NRC Notified By: ALAN GOLDEY HQ OPS Officer: KERBY SCALES	Notification Date: 09/03/2019 Notification Time: 14:36 [ET] Event Date: 08/30/2019 Event Time: 13:10 [EDT] Last Update Date: 09/03/2019
Emergency Class: NON EMERGENCY 10 CFR Section: AGREEMENT STATE	Person (Organization): ERIN CARFANG (R1DO) NMSS_EVENTS_NOTIFICATION (EMAIL)

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

Event Text

AGREEMENT STATE REPORT - MOBILE LEAD SHIELD SHIPPED WITH SOURCE INSIDE The following report was received from the Maryland Department of the Environment (MDE) Radiological Health Program (RHP) via email: "On August 30, 2019, at 13:10 [EDT], the MDE-RHP was contacted by telephone by medical licensee, MedStar Franklin Square Medical Center nuclear medicine department (MD-05-032-01). "An order had been placed by the medical center's Biomedical Department through eBay for a mobile lead shield for a Co-57 flood reference source. Upon receipt of the mobile shield, a Co-57 flood source was discovered inside. Only the mobile shield was ordered. The flood source was identified as an Eckert & Ziegler Feather Lite model MED3709 (S/N 159-062), 10 mCi as of June 1, 2011. The current activity was calculated to be 4.61 microCuries at time of receipt. The medical center's Radiation Safety Officer was notified. The sealed source was leak tested and evaluated using a Capintec Captus 3000 well counter with an efficiency of 37 percent. The leak test result was less than 0.005 microCuries. "Eckert & Ziegler was contacted on August 30, 2019. The flood source was sold to Lower Oconne Community Hospital. The Co-57 flood source was originally shipped on April 20, 2011. The community hospital closed on February 14, 2014. The Georgia Radioactive Materials Program was contacted on August 30, 2019 at 1300 [EDT] with preliminary information concerning this sealed source. Georgia radioactive materials license No. 1389 for the community hospital was terminated June 2016. "MDE-RHP will further investigate this incident. Eckert & Ziegler will provide a Return Kit for disposal. The source is currently secured in a waste storage room at MedStar Franklin Square Medical Center." 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

Fuel Cycle Facility	Event Number: 54255
Facility: NUCLEAR FUEL SERVICES INC. RX Type: URANIUM FUEL FABRICATION Comments: HEU CONVERSION & SCRAP RECOVERY NAVAL REACTOR FUEL CYCLE LEU SCRAP RECOVERY Region: 2 City: ERWIN   State: TN County: UNICOI License #: SNM-124 Docket: 07000143 NRC Notified By: RON RICE HQ OPS Officer: JEFFREY WHITED	Notification Date: 09/04/2019 Notification Time: 16:55 [ET] Event Date: 09/04/2019 Event Time: 03:46 [EDT] Last Update Date: 09/04/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 70.50(b)(1) - UNPLANNED CONTAMINATION	Person (Organization): SCOTT SHAEFFER (R2DO) NMSS_EVENTS_NOTIFICATION (EMAIL) - FUELS GROUP (EMAIL)

Event Text

UNPLANNED CONTAMINATION EVENT The following was received via e-mail: "On September 4, 2019, at approximately 0346 EDT, a glass component failed, resulting in an unplanned contamination event. The release was limited to an area inside of the Radiologically Controlled Area. This area is designed for radiological work. There has been no personnel contamination. Airborne radioactivity samples are below action levels. Cleanup and Decontamination activities were safely and promptly initiated, but due to the complexity and space constraints of the system components, normal access to the area is not likely be restored within 24 hours. There has been no exposures or releases to the environment or public. "The licensee has notified the NRC Resident Inspector."

Power Reactor	Event Number: 54266
Facility: BROWNS FERRY Region: 2     State: AL Unit: [1] [2] [3] RX Type: [1] GE-4,[2] GE-4,[3] GE-4 NRC Notified By: RYAN GRIMME HQ OPS Officer: THOMAS KENDZIA	Notification Date: 09/11/2019 Notification Time: 03:10 [ET] Event Date: 09/10/2019 Event Time: 19:34 [CDT] Last Update Date: 09/11/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(ii)(B) - UNANALYZED CONDITION	Person (Organization): FRANK EHRHARDT (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

3

N

Y

100

Power Operation

100

Power Operation

Event Text

UNANALYZED CONDITION DUE TO LIGHTNING STRIKE "A lightning strike occurred at approximately 1502 CDT on 09/10/2019, and a resulting power surge damaged some of the security door card reader system equipment. However, this did not affect access to plant areas for personnel who were already within protected area. At 1830 on 09/10/2019, it was discovered that some of the oncoming night shift personnel could not access particular areas that required the use of security card readers. Extent of condition check at 1934 on 09/10/2019 determined that access to 1A and 3A Electric Board Rooms, which contain remote shutdown panels and Fire Safe Shutdown equipment. was prohibited for the night shift personnel. This condition is reportable under 10 CFR 50.72(b)(3)(ii)(B) - Any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety. Access was restored to all plant areas at 2106 on 9/10/2019. No plant events occurred during the time frame that the 1A & 3A Electric Board Rooms inaccessible that would have required access to these areas. "The NRC Resident Inspector has been notified."

Fuel Cycle Facility	Event Number: 54267
Facility: GLOBAL NUCLEAR FUEL - AMERICAS RX Type: URANIUM FUEL FABRICATION Comments: LEU CONVERSION (UF6 TO UO2) LEU FABRICATION LWR COMMERICAL FUEL Region: 2 City: WILMINGTON   State: NC County: NEW HANOVER License #: SNM-1097 Docket: 07001113 NRC Notified By: PHILLP OLLIS HQ OPS Officer: DONALD NORWOOD	Notification Date: 09/11/2019 Notification Time: 14:04 [ET] Event Date: 09/11/2019 Event Time: 10:01 [EDT] Last Update Date: 09/11/2019
Emergency Class: NON EMERGENCY 10 CFR Section: PART 70 APP A (c) - OFFSITE NOTIFICATION/NEWS REL	Person (Organization): FRANK EHRHARDT (R2DO) NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

OFFSITE NOTIFICATION DUE TO WASTE TREATMENT LAGOON DISCHARGE TO THE SOIL "In preparation for Hurricane Dorian, the Waste Treatment Operator in Responsible Charge (ORC) decided to lower the level in the Waste Treatment Central Lagoon by treating and transferring to Process Lagoons. Piping was damaged and not noticed during a walkdown prior to pumping from waste treatment to the process lagoons. This resulted in water being discharged to the soil. "Upon discovery, the water was contained and sampled. Sample results were all below regulatory limits. The pipe was repaired. The NPDES permit requires a report to North Carolina Division of Water Resources (NC DWR). This report was made at 10:01 am on 9/11/2019. Because NC DWR was notified, a concurrent notification to the NRC Operations Center is being made per 10 CFR 70, Appendix A(c)." The Licensee will be notifying the Region II office.

Power Reactor	Event Number: 54268
Facility: OCONEE Region: 2     State: SC Unit: [1] [2] [3] RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP NRC Notified By: RODNEY ROBINSON HQ OPS Officer: DONALD NORWOOD	Notification Date: 09/11/2019 Notification Time: 17:58 [ET] Event Date: 09/11/2019 Event Time: 12:48 [EDT] Last Update Date: 09/11/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 26.719 - FITNESS FOR DUTY	Person (Organization): FRANK EHRHARDT (R2DO) 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

2

N

Y

100

Power Operation

100

Power Operation

3

N

Y

100

Power Operation

100

Power Operation

Event Text

FITNESS-FOR-DUTY REPORT INVOLVING A CONTRACT SUPERVISOR A non-licensed contract supervisor had a confirmed positive for illegal drugs during a random fitness-for-duty test. The individual's authorization for site access has been terminated. The NRC Resident Inspector has been notified.

Power Reactor	Event Number: 54271
Facility: GRAND GULF Region: 4     State: MS Unit: [1] [] [] RX Type: [1] GE-6 NRC Notified By: GERRY ELLIS HQ OPS Officer: JEFF HERRERA	Notification Date: 09/12/2019 Notification Time: 00:49 [ET] Event Date: 09/11/2019 Event Time: 17:19 [CDT] Last Update Date: 09/12/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL	Person (Organization): RYAN ALEXANDER (R4DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

1

N

Y

81

Power Operation

81

Power Operation

Event Text

PRIMARY CONTAINMENT AIRLOCK DOOR NOT IN FULLY SEATED POSITION "On September 11, 2019 at 1719 CDT, plant personnel identified a condition in which the 208 foot elevation inner primary containment airlock door was not in its fully seated and latched position while the 208 foot elevation outer primary containment airlock door was opened. The 208 foot elevation outer containment airlock door was subsequently closed by the individual exiting the area. The time that both 208 foot elevation containment airlock doors were not in their fully seated and latched positions was less than 1 minute. Following this occurrence, maintenance personnel inspected the 208 foot elevation inner containment airlock door and re-positioned this door to its fully seated and latched position. There was no radioactive release as a result of this event. "This condition requires an 8-hour non-emergency notification in accordance with 10CFR50.72(b)(3)(v)(C) as an event or condition that could have prevented fulfillment of a safety function needed to control the release of radioactive material. "The NRC Resident Inspector has been notified."

Power Reactor	Event Number: 54272
Facility: PALO VERDE Region: 4     State: AZ Unit: [] [] [3] RX Type: [1] CE,[2] CE,[3] CE NRC Notified By: JASON HILL HQ OPS Officer: JEFF HERRERA	Notification Date: 09/12/2019 Notification Time: 03:25 [ET] Event Date: 09/11/2019 Event Time: 18:24 [MST] Last Update Date: 09/12/2019
Emergency Class: NON EMERGENCY 10 CFR Section: 50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE	Person (Organization): RYAN ALEXANDER (R4DO)

Unit

SCRAM Code

RX Crit

Initial PWR

Initial RX Mode

Current PWR

Current RX Mode

3

N

Y

100

Power Operation

100

Power Operation

Event Text

MAIN STEAM LINE RADIATION MONITOR COMMUNICATION FAILURE "The following event description is based on information currently available. If through subsequent reviews of this event, additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73. "Radiation monitor RU-140 (#2 Steam Generator Main Steam Line radiation monitor) experienced a communication failure on both ports A and B. The RU-140 monitor is off line and non-functional at this time. "At least one channel of RU-140 is required to perform a Steam Generator Tube Rupture (SGTR) dose assessment. This represents an unplanned loss of radiological assessment capability for the inability to perform dose assessments that require the radiation monitor. The ability to make emergency classifications from other radiological data collection methods such as field sampling remains available. Actions have been initiated to restore the radiation monitor. "The NRC Resident Inspector has been informed."