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Event Notification Report for May 14, 2018

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
5/11/2018 - 5/14/2018

** EVENT NUMBERS **


53383 53384 53395 53396 53398 53399 53401

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Agreement State Event Number: 53383
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: TEAM INDUSTRIAL SERVICE INC
Region: 4
City: ALVIN   State: TX
County:
License #: L 00087
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/04/2018
Notification Time: 13:52 [ET]
Event Date: 05/04/2018
Event Time: 09:27 [CDT]
Last Update Date: 05/04/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY AZUA (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
JIM WHITNEY (ILTAB)

Event Text

AGREEMENT STATE REPORT - BOMB THREAT

The following information was obtained from the state of Texas via email:

"On May 4, 2018, the Agency [Texas Department of State Health Services] was notified by the licensee that on May 4, 2018, at 0927 hours [CDT], one of their managers had received a phone call from an individual who made a bomb threat against the licensee's offices in Beaumont, Texas. The licensee contacted local law enforcement (LLE) who then contacted the Federal Bureau of Investigation (FBI). LLE responded to the location within 7 minutes of the call to them and the FBI was at the location before the radiation safety officer (RSO) arrived at the office 12 minutes after the call was received. The fire department also responded. The building was evacuated and the FBI, LLE, bomb squad, Fire Marshall, and the RSO inspected the building and the areas around the building. No explosive device was found. The facility was released at 1029 hours [CDT]. Additional information will be provided as it is received in accordance with SA-300."

TX Incident #: 9568

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Fuel Cycle Facility Event Number: 53384
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: TIM KNOWLES
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/04/2018
Notification Time: 15:40 [ET]
Event Date: 05/04/2018
Event Time: 11:45 [EDT]
Last Update Date: 05/04/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
PART 70 APP A (c) - OFFSITE NOTIFICATION/NEWS REL
Person (Organization):
BINOY DESAI (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
- FUELS GROUP (EMAIL)

Event Text

CONCURRENT REPORT FOR AN OFFSITE NOTIFICATION MADE TO THE STATE OF TENNESSEE

"This is a concurrent report of a 24-hour report that was made to the state of Tennessee regarding a break in the main fire water loop due to construction activities. The fire loop is fed by city water. The fire water pipe break was isolated by closing isolation valves upstream of the break. A portion of the water and dirt from the excavation flowed into a nearby storm water drainage system. This drainage system has a storm gate which was closed prior to the event to contain the dirt and water. The dirt is still contained in the storm water system located within the protected area of NFS. The dirt is currently being removed from the storm water system. The storm gate will remain closed until the dirt removal activity has been completed.

Potential health and safety consequences to the workers, the public and the environment: "There are no actual safety consequences to workers, the public, or the environment. The potential consequence was a slightly elevated but less than the 10 CFR 20 Table 2 limits of contaminated liquid effluent from a construction accident.

"The licensee notified the NRC Resident Inspector."

Fire watches have been established for the areas affected by the fire loop break. No criticality controls were affected by this event.

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Power Reactor Event Number: 53395
Facility: NINE MILE POINT
Region: 1     State: NY
Unit: [] [2] []
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: CHRIS MOORHEAD
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/10/2018
Notification Time: 08:59 [ET]
Event Date: 05/10/2018
Event Time: 02:48 [EDT]
Last Update Date: 05/11/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
ANNE DeFRANCISCO (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

VALID EMERGENCY DIESEL START ON PARTIAL LOSS OF OFFSITE POWER

"At 0248 [EDT], with the plant shutdown in Mode 4, Nine Mile Point Unit 2 experienced a partial loss of off-site power during relay testing that resulted in an automatic start of the Division 2 Emergency Diesel Generator. All systems responded as expected for the event. The cause is being investigated. The station responded in accordance with appropriate Special Operating Procedures and restored impacted systems.

"This event is being reported in accordance with 10CFR50.72(b)(3)(iv)(A)"

At the time of the report, the emergency diesel generators are loaded and supplying plant safety equipment.

The licensee has notified the state of New York Emergency Management Agency and the NRC Resident Inspector.

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Power Reactor Event Number: 53396
Facility: OCONEE
Region: 2     State: SC
Unit: [] [] [3]
RX Type: [1] B&W-L-LP,[2] B&W-L-LP,[3] B&W-L-LP
NRC Notified By: BEN MCCALL
HQ OPS Officer: THOMAS KENDZIA
Notification Date: 05/10/2018
Notification Time: 17:03 [ET]
Event Date: 05/10/2018
Event Time: 16:17 [EDT]
Last Update Date: 05/11/2018
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
FRANK EHRHARDT (R2DO)
WILLIAM GOTT (IRD)
CHRIS MILLER (NRR EO)
BRIAN HOLIAN (DNRR)
LAURA DUDES (R2DRA)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
3 N N 0 Refueling 0 Refueling

Event Text

NOTIFICATION OF UNUSUAL EVENT

"Unit 3 experienced a loss of AC power while in Mode 6. Power was regained automatically from Keowee via the underground path.

"Decay heat removal has been restored. Spent fuel cooling has been restored.

"Emergency procedures [are] in progress."

The Licensee notified the senior NRC resident inspector, State of South Carolina and local authorities.

The total loss of 4160 volt AC power was for approximately 30 seconds. The unit is refueled and reactor reassembly complete up to bolting on the reactor head. There was no effect on Units 1 and 2.

Notified DHS SWO, FEMA Ops Center, FEMA NWC, DHS NICC, and NuclearSSA

* * * UPDATE FROM SCOTT HAWKESWORTH TO HOWIE CROUCH AT 0554 EDT ON 5/11/18 * * *

At 0530 EDT, Oconee terminated the notification of unusual event on Unit 3. The basis for termination was that offsite power was restored and the plant is now in its normal shutdown electrical lineup.

The licensee has notified Oconee and Pickens counties and will be notifying the NRC Resident Inspector.

Notified R2DO (Ehrhardt), NRR EO (Miller), IRD MOC (Gott), DHS SWO, FEMA Operations Center, DHS NICC, FEMA NWC (email) and NuclearSSA (email).

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Power Reactor Event Number: 53398
Facility: WATTS BAR
Region: 2     State: TN
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: CHUCK BROESCHE
HQ OPS Officer: DONALD NORWOOD
Notification Date: 05/11/2018
Notification Time: 15:19 [ET]
Event Date: 05/11/2018
Event Time: 10:11 [EDT]
Last Update Date: 05/11/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
FRANK EHRHARDT (R2DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 N Y 58 Power Operation 58 Power Operation

Event Text

CONTAINMENT SHIELD BUILDING INOPERABLE

"At 1011 EDT on May 11, 2018, Containment Shield Building Annulus differential pressure exceeded the required limit. The Shield Building was declared inoperable requiring entry into Technical Specification (TS) 3.6.15 Conditions A and B. The event was initiated by failure of the operating annulus vacuum fan. Main Control Room Operators manually started the stand-by annulus vacuum fan to recover pressure. Shield Building Annulus differential pressure was restored to the required value at 1016 EDT and TS 3.6.15 Condition A and B were exited on May 11, 2018 at 1016 EDT.

"The failure mechanism for the annulus vacuum fan is being investigated.

"The Containment Shield Building ensures the release of radioactive material from the containment atmosphere is restricted to those leakage paths and associated leakage rates assumed in the accident analysis during a Loss of Coolant Accident (LOCA). The Emergency Gas Treatment System (EGTS) would have automatically started and performed its design function to maintain the Shield Building Annulus differential pressure within required limits.

"The event is being reported pursuant to 10 CFR 50.72(b)(3)(v)(C) and 10 CFR 50.72(b)(3)(v)(D). The NRC Resident has been notified."

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Power Reactor Event Number: 53399
Facility: GRAND GULF
Region: 4     State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: WESLEY MARSHALL
HQ OPS Officer: OSSY FONT
Notification Date: 05/12/2018
Notification Time: 06:58 [ET]
Event Date: 05/11/2018
Event Time: 23:27 [CDT]
Last Update Date: 05/12/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
MARK HAIRE (R4DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling

Event Text

INADVERTENT ACTUATION OF THE EMERGENCY DIESEL GENERATOR

"On 5/11/2018, at 2327 hours CDT, with the plant in Mode 5, Grand Gulf Nuclear Station was making preparations for surveillance test 06-OP-1P75-R-0003, Standby Diesel Generator 1 Functional Test. The Grand Gulf Nuclear Station experienced an auto-start of the Division 1 [Emergency] Diesel Generator [EDG] when the 15AA Bus Potential Transformer (PT) fuse drawer was racked out instead of the line PT fuse drawer for Bus 15AA feeder breaker 152-1514. This resulted in the 15AA Incoming Feeder Breaker 152-1511 from Engineered Safety Features Transformer 12 opening, de-energizing the 15AA Bus. The Division 1 EDG started and energized Bus 15AA. The Division 1 LSS SYSTEM FAIL annunciator was received and Standby Service Water A failed to start due to the 15AA Bus PT fuse drawer being racked out. Standby Gas Treatment Train B was manually initiated per the Loss Of AC Power Off Normal Emergency Procedure. Station equipment operated as expected based on the PT fuse drawer that was racked out.

"The Division 1 EDG was manually tripped from the Control Room because cooling from the Standby Service Water A was not available.

"RHR [residual heat removal] B was in Shutdown Cooling [mode] and was verified not affected"

The licensee has notified the NRC Resident Inspector.

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Power Reactor Event Number: 53401
Facility: CALVERT CLIFFS
Region: 1     State: MD
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: DAN GENEVA
HQ OPS Officer: DONALD NORWOOD
Notification Date: 05/14/2018
Notification Time: 13:17 [ET]
Event Date: 05/14/2018
Event Time: 13:05 [EDT]
Last Update Date: 05/14/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
GLENN DENTEL (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

SALTWATER SYSTEM NON-CONFORMING WITH LICENSING BASIS FOR TORNADO GENERATED MISSILES

"On May 14, 2018, during evaluation of protection for Technical Specification (TS) equipment from the damaging effects of a tornado generated missile, Calvert Cliffs identified a non-conforming condition in the plant design such that specific TS equipment is considered to not be adequately protected from a tornado generated missile. A tornado could generate a missile that could strike the Unit 1 Saltwater system header and associated piping. This could result in damage to the unit 1 Saltwater system header which could affect the ability of the Unit 1 Saltwater subsystems to perform their design function if such a tornado would occur.

"This condition is reportable per 10 CFR 50.72(b)(3)(ii)(B) for any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety, and per 10 CFR 50.72(b)(3)(v)(D) for any 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.

"This condition is being addressed in accordance with NRC enforcement guidance provided in EGM 15-002 and DSS-ISG-2016-01. Compensatory measures have been implemented in accordance with these documents.

"The NRC Resident Inspector has been informed of this notification."


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