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Event Notification Report for May 04, 2018

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
5/3/2018 - 5/4/2018

** EVENT NUMBERS **


53356 53363 53364 53380 53381 53382 53385

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!!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 53356
Facility: WATTS BAR
Region: 2     State: TN
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JUSTIN GALLAGHER
HQ OPS Officer: DAVID AIRD
Notification Date: 04/22/2018
Notification Time: 04:28 [ET]
Event Date: 04/22/2018
Event Time: 02:22 [EDT]
Last Update Date: 05/04/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
ALAN BLAMEY (R2DO)
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

BOTH TRAINS OF RESIDUAL HEAT REMOVAL INOPERABLE

"On April 22, 2018 at 0222 EDT, Watts Bar Nuclear Plant (WBN) Unit 2 entered TS [Technical Specifications] LCO [Limiting Condition for Operation] 3.0.3 due to both trains of the Residual Heat Removal System (RHRS) becoming inoperable. During surveillance testing, the gas void values on Emergency Core Cooling System (ECCS) piping common to both trains did not meet acceptance criteria. This caused both RHRS trains to become inoperable. Operations subsequently vented the RHRS to meet the acceptance criteria and exited TS LCO 3.0.3 at 0227 EDT. More frequent surveillances will be conducted to monitor gas void volumes while additional analysis is being performed to determine corrective actions."

The NRC Resident Inspector has been notified.

* * * RETRACTION FROM TONY PATE TO HOWIE CROUCH ON 5/4/18 AT 1455 EDT * * *

"This event is being retracted. The initial report was based on a conservative acceptance criteria for gas accumulation adopted on April 19, 2018 when it was determined that the previously used acceptance criteria for gas accumulation in the ECCS was non-conservative. Additional analysis has subsequently been performed and determined that a higher gas accumulation acceptance criteria does not challenge operability. With a void of less than the acceptance criteria, in the event of ECCS actuation, the system piping support loads will remain within structural limits and the piping system will remain operable. Therefore, both trains of Unit 2 RHRS were operable and the previously reported 10 CFR 50.72(b)(3)(v)(B) event is being retracted.

"The NRC Resident Inspector staff has been informed of this event retraction."

Notified R2DO (Desai) of this retraction.

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Agreement State Event Number: 53363
Rep Org: ARKANSAS DEPARTMENT OF HEALTH
Licensee: ALBEMARLE CORPORATION
Region: 4
City: MAGNOLIA   State: AR
County:
License #: ARK-0717-03120
Agreement: Y
Docket:
NRC Notified By: DAVID STEPHENS
HQ OPS Officer: STEVEN VITTO
Notification Date: 04/26/2018
Notification Time: 10:31 [ET]
Event Date: 04/24/2018
Event Time: 14:00 [CDT]
Last Update Date: 04/26/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL VASQUEZ (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - STUCK SHUTTERS

The following was received from the State of Arkansas via email:

"At approximately 1400 [CDT] on 4/24/2018 the Arkansas Department of Heath Radioactive Materials Program received a phone call from the licensee stating that during routine shutter tests two fixed gauge shutters were not functioning properly; one had a stuck shutter and the other was stiff and might become stuck. The gauges are Thermo MeasureTech Model 7063S, source serial numbers S97D2112 (stuck shutter) and S97D2109 (stiff shutter), each originally containing 2 Ci of Cs137.

"Discussion with the licensee indicates that the gauges are mounted on a reactor, outside of normal employee traffic. It is normally open during operations and is only closed during maintenance of the reactor, which is not planned. Cautionary signage is already present. The licensee representative stated that the staff will be made aware of the situation. Licensee maintenance is assessing the situation and will advise the ADH Radioactive Materials program of the plan for handling this situation.

"The State of Arkansas is awaiting a written report from the licensee and final disposition information for the gauge. The State's event number is AR-2018-004."

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Agreement State Event Number: 53364
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: BLUE CUBE OPERATIONS LLC
Region: 4
City: FREEPORT   State: TX
County:
License #: L 06926
Agreement: Y
Docket:
NRC Notified By: ART TUCKER
HQ OPS Officer: BETHANY CECERE
Notification Date: 04/26/2018
Notification Time: 17:36 [ET]
Event Date: 04/26/2018
Event Time: 00:00 [CDT]
Last Update Date: 04/26/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL VASQUEZ (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - STUCK SHUTTER

The following was received from the state of Texas via email:

"On April 26, 2018, the Agency [Texas Department of State Health Services] was notified by the licensee's radiation safety officer (RSO) that while performing routine testing of an Ohmart Vega model SH-F1 gauge containing a 5 milliCurie cesium - 137 source, the shutter would not fully close. The RSO stated open is the normal operating condition for the gauge and it does not create an exposure risk to any individual. The gauge is used for level indication. The RSO stated they have contacted a service company and they will be on site on April 27, 2018, to inspect the gauge. Additional information will be provided as it is received in accordance with - SA-300."

TX Incident #: 9564

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Power Reactor Event Number: 53380
Facility: COMANCHE PEAK
Region: 4     State: TX
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: LOREN STUCK
HQ OPS Officer: OSSY FONT
Notification Date: 05/03/2018
Notification Time: 18:40 [ET]
Event Date: 05/03/2018
Event Time: 12:20 [CDT]
Last Update Date: 05/03/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
Person (Organization):
RAY AZUA (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

LOSS OF EMERGENCY ASSESSMENT CAPABILITY

"During planned maintenance on Unit 2 Radiation Monitor 2-RE-4270 (Service Water Train B to Discharge Canal Rad Monitor), at 1220 CDT, several other Unit 2 Radiation Monitors that are used for Emergency Action Level evaluation became nonfunctional for about 1 hour. With these radiation monitors non-functional, all of the Emergency Action Levels associated with these monitors could neither be evaluated nor monitored. This unplanned condition is reportable as a loss of assessment capability per 10 CFR 50.72(b)(3)(xiii). A PC11 computer reboot restored the affected radiation monitors to a functional status.

"The NRC Resident Inspector has been notified."

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Power Reactor Event Number: 53381
Facility: DAVIS BESSE
Region: 3     State: OH
Unit: [1] [] []
RX Type: [1] B&W-R-LP
NRC Notified By: BILL RAYBURN
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/04/2018
Notification Time: 12:50 [ET]
Event Date: 03/08/2018
Event Time: 13:23 [EST]
Last Update Date: 05/04/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
Person (Organization):
BILLY DICKSON (R3DO)
BO PHAM (IRD)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling

Event Text

60-DAY OPTIONAL TELEPHONIC NOTIFICATION FOR AN INVALID EDG START DURING OUTAGE TESTING

"On March 8, 2018, an invalid system actuation occurred while preparations were underway to perform Safety Features Actuation System (SFAS) integrated response time surveillance testing during the recent Davis Besse Nuclear Power Station refueling outage. Several minutes after connecting a data recorder to monitor the Emergency Diesel Generator (EDG) 1 start signal, at 1323 hours [EST], the EDG started with no valid actuation signals or test inputs present. The EDG successfully came up to speed and voltage as expected. The associated essential 4160 volt electrical bus remained energized from the normal power supply, therefore, the EDG output breaker did not close to supply power to the bus. Troubleshooting determined the inadvertent actuation was due to a short in the test lead wires at the recorder connection caused by a faulty test lead. The test lead was replaced and the SFAS surveillance testing completed satisfactorily.

"This event is being reported as an invalid system actuation per 10 CFR 50.73(a)(2)(iv)(A); this 60-day optional telephone notification is being made per 10 CFR 50.73(a)(i) in lieu of submitting a written Licensee Event Report.

"The NRC Resident Inspector was notified of the inadvertent EDG start at the time of the event and has been notified of this invalid specified system actuation notification."

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Power Reactor Event Number: 53382
Facility: RIVER BEND
Region: 4     State: LA
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: MIKE BRANSCUM
HQ OPS Officer: HOWIE CROUCH
Notification Date: 05/04/2018
Notification Time: 13:50 [ET]
Event Date: 05/04/2018
Event Time: 11:29 [CDT]
Last Update Date: 05/04/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(A) - POT UNABLE TO SAFE SD
50.72(b)(3)(v)(B) - POT RHR INOP
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
RAY AZUA (R4DO)
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

UNANALYZED CONDITION ASSOCIATED WITH DAMAGING EFFECTS OF TORNADOS

"During performance of an extent of condition evaluation of protection for Technical Specification (TS) equipment from the damaging effects of tornados, River Bend Station identified non-conforming conditions in the plant design such that specific TS equipment is considered to not be adequately protected from tornado missiles. The reportable condition is postulated by tornado missiles entering the Diesel Generator Building through conduit and pipe penetrations. A tornado could generate multiple missiles capable of striking Division 1, Division 2, and Division 3 Diesel Generator support equipment rendering all Safety Related Diesel Generators inoperable.

"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) 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 (A) Shut down the reactor and maintain it in a safe shutdown condition, (B) Remove residual heat, or (D) Mitigate the consequences of an accident.

"This condition was identified as part of an on-going extent of condition review of potential tornado missile related site impacts.

"Enforcement discretion per Enforcement Guidance Memorandum EGM 15-002 has been implemented and required actions taken. Corrective actions will be documented in a follow-on licensee event report.

"The licensee has notified the NRC Resident Inspector."

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Power Reactor Event Number: 53385
Facility: FERMI
Region: 3     State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: CHRISTOPHER ROBINSON
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/04/2018
Notification Time: 16:20 [ET]
Event Date: 05/04/2018
Event Time: 14:12 [EDT]
Last Update Date: 05/04/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
BILLY DICKSON (R3DO)
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

OFFSITE NOTIFICATION

"At 1412 EDT, a portable chemical toilet was found tipped over. Approximately 1 gallon of contents spilled to gravel only. A notification to the Michigan Department of Environmental Quality and local health department is required, as well as a press release.

"This event is being reported pursuant to 10CFR50.72(b)(2)(xi)."

The licensee will notify the NRC Resident Inspector.


Page Last Reviewed/Updated Monday, June 18, 2018
Monday, June 18, 2018