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Event Notification Report for April 01, 2019

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
3/29/2019 - 4/1/2019

** EVENT NUMBERS **


53949 53950 53951 53952 53961 53966 53967

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Agreement State Event Number: 53949
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: COVESTRO LLC
Region: 4
City: BAYTOWN   State: TX
County:
License #: L01577
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 03/21/2019
Notification Time: 11:14 [ET]
Event Date: 03/20/2019
Event Time: 00:00 [CDT]
Last Update Date: 03/21/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
NEIL O'KEEFE (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - FIXED GAUGE STUCK SHUTTER

The following report was received from the state of Texas via e-mail:

"On March 21, 2019, the licensee notified the Agency [Texas Department of State Health Services] that during routine shutter checks on March 20, 2019, it had discovered that the shutter on one of the Ronan Model SA-1 gauges (SN: M-3824) was stuck in the open position. Open is the normal operating position for this gauge. The gauge contains a cesium-137 source with a calculated current activity of 10 milliCuries. Due to the location of the gauge, there is no increased risk of exposure. The licensee plans to replace the gauge."

Texas Incident #9667

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Agreement State Event Number: 53950
Rep Org: ALABAMA RADIATION CONTROL
Licensee: TTL, INC
Region: 1
City: MONTGOMERY   State: AL
County:
License #: 512
Agreement: Y
Docket:
NRC Notified By: CASON COAN
HQ OPS Officer: JEFFREY WHITED
Notification Date: 03/21/2019
Notification Time: 16:04 [ET]
Event Date: 03/19/2019
Event Time: 20:00 [CDT]
Last Update Date: 03/21/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB (EMAIL)
This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - STOLEN MOISTURE DENSITY GAUGE

The following was received from the state of Alabama via fax:

"On March 20, 2019 at approximately 0800 [CDT], [an individual] of Alabama licensee TTL, lnc. notified the Alabama Office of Radiation Control [Agency] that gauge make and model Troxler 3440P was stolen from a technician's vehicle between approximately 2000 [CDT] March 19, and 0500 [CDT] March 20, 2019. The technician was working at a temporary job site in Auburn, AL, and the truck parked in the hotel parking lot. [The individual] reported that the technician stored the gauge in a gauge box; the gauge box was appropriately secured to the truck bed. The technician reported the theft to the local police department before contacting the Agency. The Agency has no further information regarding the whereabouts of this gauge as of today, March 21, 2019.

"TTL, Inc. is authorized to possess gauges under Alabama license 512. The stolen gauge is identified as Troxler model 3440P [serial number] 72314, with maximum source activities of 10 mCi Cs-137 and 50 mCi Am/Be-241."

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: 53951
Rep Org: GEORGIA RADIOACTIVE MATERIAL PGM
Licensee: GE HEALTHCARE
Region: 1
City: ATLANTA   State: GA
County:
License #: GA 1166-1
Agreement: Y
Docket:
NRC Notified By: IRENE BENNETT
HQ OPS Officer: JEFFREY WHITED
Notification Date: 03/21/2019
Notification Time: 15:44 [ET]
Event Date: 03/18/2019
Event Time: 00:00 [EDT]
Last Update Date: 03/21/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
ILTAB (EMAIL)
- CNSC (CANADA) (EMAIL)
This material event contains a "Less than Cat 3" level of radioactive material.

Event Text

AGREEMENT STATE REPORT - GENERATOR LOST IN TRANSIT

The following was received from the state of George via e-mail:

"On January 17, 2019, GE Healthcare in Atlanta (GA 1166-1) consigned a Mo-99/Tc-99m generator (5.14 mCi at the time of shipment) to [common carrier] for delivery to Medi-Ray in Tuckahoe, NY for recycling (the trip included a transit stop in Charlotte, NC). As of March 20, 2019, the device has not arrived at its final destination. On March 18, 2019, [the common carrier] formally notified GE Healthcare that the device was lost in transit.

"This information was received on March 20, 2019."

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: 53952
Rep Org: PA BUREAU OF RADIATION PROTECTION
Licensee: US STEEL CORPORATION
Region: 1
City: BRADDOCK   State: PA
County:
License #: PA-G0310
Agreement: Y
Docket:
NRC Notified By: JOHN CHIPPO
HQ OPS Officer: JEFFREY WHITED
Notification Date: 03/22/2019
Notification Time: 14:22 [ET]
Event Date: 03/21/2019
Event Time: 00:00 [EDT]
Last Update Date: 03/22/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
CHRISTOPHER CAHILL (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - FAILED MOISTURE GAUGE SHUTTER

The following was received from the Commonwealth of Pennsylvania via e-mail:

"The licensee reported that on March 21, 2019, the Berthold Technologies Model LB-7 410 moisture gauge containing 300 milliCuries of americium-241 was not able to operate as designed; the shutter locking mechanism cylinder was able to be pulled out of the gauge. The gauge was being removed from the east side of #3 Blast Furnace to the storage area at the Blast Furnace spares building. A service provider was already scheduled on site to observe removal and transport of the gauge. A contract employee working with the service provider stated that the cylinder was able to be pulled out of the gauge. The cylinder was never fully removed, but if it was, this would allow the shutter to be manually opened or closed. The cylinder locking device was depressed by the service provider employee and it is currently in that condition. The shutter can't be moved with the cylinder depressed. The gauge is currently locked in the storage area at the Blast Furnace spares building.

All work was performed using ALARA principles and at no point were employees exposed to excess levels of radiation. Survey results indicated no abnormal amounts of radiation in the area before, during, or after the removal of the device. Berthold has been contact for repair or replacement."

PA Event Report ID No: PA19001

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Power Reactor Event Number: 53961
Facility: BRUNSWICK
Region: 2     State: NC
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DEREK WATSON
HQ OPS Officer: JEFF HERRERA
Notification Date: 03/28/2019
Notification Time: 15:07 [ET]
Event Date: 03/28/2019
Event Time: 14:50 [EDT]
Last Update Date: 03/29/2019
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
50.72(b)(2)(i) - PLANT S/D REQD BY TS
Person (Organization):
BRIAN BONSER (R2DO)
JEFFERY GRANT (IRD)
JOEL MUNDAY (R2)
HO NIEH (NRR)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 58 Power Operation

Event Text

UNUSUAL EVENT DECLARED DUE TO RCS UNIDENTIFIED LEAKAGE

At 1450 EDT on March 28, 2019, the licensee observed that the Unit 1 unidentified Reactor Coolant System (RCS) leakage was greater than 10 gallons per minute (gpm) for greater than or equal to 15 minutes. The licensee declared an Unusual Event in accordance with their EAL SU 5.1. The licensee initiated a unit shutdown in accordance with their procedures and the unit was approximately 58 percent reactor power at 1507 EDT, with unit shutdown in progress. The licensee also received an alarm due to increasing Drywell Pressure at 1.7 pounds drywell pressure.

At 1600 EDT the licensee called with an update. Unit 1 was still in an Unusual Event with the unit at 37 percent power with the shutdown continuing. Drywell Pressure had decreased to 0.8 pounds. At 1603 the licensee scrammed Unit 1.

Notified DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

* * * UPDATE ON 3/28/2019 AT 1808 EDT FROM MARK TURKAL TO THOMAS KENDZIA * * *

"At 1437 EDT on March 28, 2019, with Unit 1 in Mode 1 at approximately 100 percent power, a Technical Specification-required shutdown was initiated due to indication of a leak in the drywell. Technical Specification Action 3.4.4.A, Unidentified Reactor Coolant System (RCS) leakage increase not within limit, requires RCS leakage to be reduced to within limits within 8 hours.

"It is expected that the leakage would not have been reduced to within limits within the required Technical Specification completion time; therefore, this event is being reported in accordance with 10 CFR 50.72(b)(2)(i).

"There was no impact on the health and safety of the public or plant personnel.

"The NRC Resident Inspector has been notified."

* * * UPDATE ON 03/29/19 AT 0302 EDT FROM TOM FIENO TO BETHANY CECERE * * *

At 0259 EDT on March 29, 2019, the Unusual Event was terminated because RCS leakage was reduced to less than 10 gallons per minute. The most recent leakage rate measured at 0225 EDT was 3.9 gpm. The source of the leak will be identified when plant conditions allow containment entry. No elevated radiation levels were observed during this event. Drywell pressure is currently 0.0 psig. Unit 1 is in Mode 4.

The licensee notified the NRC Resident Inspector.

Notified R2DO (Bonser), NRR EO (Miller), IRD MOC (Grant), DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email), DHS Nuclear SSA (email), and FEMA NRCC SASC (email).

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Power Reactor Event Number: 53966
Facility: BRUNSWICK
Region: 2     State: NC
Unit: [] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: BRIAN MOSCHET
HQ OPS Officer: THOMAS KENDZIA
Notification Date: 03/30/2019
Notification Time: 21:06 [ET]
Event Date: 03/30/2019
Event Time: 17:47 [EDT]
Last Update Date: 03/30/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
BRIAN BONSER (R2DO)
JEFFERY GRANT (IRD)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 23 Power Operation 0 Hot Shutdown

Event Text

MANUAL REACTOR SCRAM AND SPECIFIED SYSTEM ACTUATION

"At 17:47 Eastern Daylight Time (EDT) on March 30, 2019, with Unit 2 in Mode 1 at approximately 23 percent reactor power and main turbine startup in progress coming out of a refuel outage, a high temperature was sensed at main turbine bearing #9. As a result of and to arrest the high temperature condition, the main control room inserted a manual reactor scram.

"All control rods inserted as expected during the scram. When the scram was inserted, reactor water level dropped below the Low Level 1 actuation setpoint. Per design, the Low Level 1 signal resulted in Group 2 (i.e., floor and equipment drain isolation valves), Group 6 (i.e., monitoring and sampling isolation valves) and Group 8 (i.e., shutdown cooling isolation valves) isolations.

"The main control room manually closed all Main Steam Isolation Valves (MSIVs), in anticipation of a low vacuum prior to the Group 1 automatic closure signal being received. High Pressure Coolant Injection (HPCI) was aligned for pressure control and Reactor Coolant Isolation System (RCIC) was aligned for level control. The Reactor Coolant Sample Line Isolation valves closed as expected on low main condenser vacuum.

"All systems responded as designed.

"This event is being reported in accordance with 10 CFR 50.72(b)(2)(iv)(B) for RPS actuation and 10 CFR 50.72(b)(3)(iv)(A) as an event that results in valid actuations of the Primary Containment Isolation System.

"There was no impact on the health and safety of the public or plant personnel.

"The NRC Resident Inspector has been notified."

At the time of notification, decay heat was being removed by the condenser through one open MSIV and a feedwater pump running.

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Power Reactor Event Number: 53967
Facility: VOGTLE
Region: 2     State: GA
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: KENNY MCKAY
HQ OPS Officer: CATY NOLAN
Notification Date: 03/31/2019
Notification Time: 00:17 [ET]
Event Date: 03/30/2019
Event Time: 21:30 [EDT]
Last Update Date: 03/31/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
BRIAN BONSER (R2DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 30 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO MSIV FAILING CLOSED

"At 2130 [EDT] on March 30, 2019, with Unit 2 in Mode 1 at 30 percent reactor power, the reactor was manually tripped due to a main steam isolation valve failing closed. The trip was not complex, with all systems responding normally. Operations stabilized the plant in Mode 3. Decay heat is being removed through the main steam lines through the steam dumps and into the condenser.

"The expected actuation of the Auxiliary Feedwater System (an engineered safety feature) is being reported as an eight hour report under 10 CFR 50.72 (b)(3)(iv)(A).

"Unit 1 was not affected.

"There was no impact to the health and safety of the public or plant personnel.

"The NRC Resident Inspectors have been notified."


Page Last Reviewed/Updated Monday, April 01, 2019
Monday, April 01, 2019