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Event Notification Report for August 23, 2018

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
8/22/2018 - 8/23/2018

** EVENT NUMBERS **


53556 53557 53558 53559

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Power Reactor Event Number: 53556
Facility: LIMERICK
Region: 1     State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: RICHARD WAGNER
HQ OPS Officer: BETHANY CECERE
Notification Date: 08/22/2018
Notification Time: 02:00 [ET]
Event Date: 08/21/2018
Event Time: 23:12 [EDT]
Last Update Date: 08/22/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
Person (Organization):
DONNA JANDA (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
2 N Y 100 Power Operation 100 Power Operation

Event Text

OFFSITE NOTIFICATION DUE TO HOLDING POND OVERFLOW

"At 2322 EDT, Limerick Generating Station notified the Pennsylvania DEP [Department of Environmental Protection] that our plant waste water pond (holding pond) overflowed due to heavy rainfall in the area. Plant alignment changes were made and the holding pond stopped overflowing at 0017 EDT. Limerick Generating Station has not determined this release to contain oil, grease, or pollutants hazardous to the public."

The licensee notified the NRC Resident Inspector.

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Power Reactor Event Number: 53557
Facility: WATTS BAR
Region: 2     State: TN
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DEAN BAKER
HQ OPS Officer: BETHANY CECERE
Notification Date: 08/22/2018
Notification Time: 11:23 [ET]
Event Date: 08/22/2018
Event Time: 09:43 [EDT]
Last Update Date: 08/22/2018
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)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 A/R Y 100 Power Operation 0 Hot Standby

Event Text

AUTOMATIC REACTOR TRIP

"At 0943 EDT on August 22, 2018, the Watts Bar Unit 2 reactor automatically tripped while operating at 100 percent power. All control and shutdown bank rods inserted properly in response to the automatic reactor trip. All safety systems including Auxiliary Feedwater actuated as designed. The plant is stable with decay heat removal through Auxiliary Feedwater and Steam Dump Systems.

"The reactor automatically tripped due to a main turbine trip signal. An investigation is in progress.

"The automatic actuation of the Reactor Protection System (RPS) is being reported as a four-hour report under 10 CFR 50.72 (b)(2)(iv)(B).

"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).

"The NRC Senior Resident Inspector has been notified for this event."

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Power Reactor Event Number: 53558
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: CHRIS BENNETT
HQ OPS Officer: OSSY FONT
Notification Date: 08/22/2018
Notification Time: 19:35 [ET]
Event Date: 08/22/2018
Event Time: 18:03 [CDT]
Last Update Date: 08/22/2018
Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
Person (Organization):
BRIAN BONSER (R2DO)
CATHY HANEY (RII RA)
BRIAN MCDERMOTT (ET RX)
WILLIAM GOTT (IRD)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 79 Power Operation 79 Power Operation
2 N Y 100 Power Operation 100 Power Operation
3 N Y 100 Power Operation 100 Power Operation

Event Text

NOTIFICATION OF UNUSUAL EVENT DECLARED DUE TO FIRE

"On 08/22/2018 at 1803 hours CDT, Browns Ferry Nuclear Plant declared an Unusual Event per EAL HU4, a fire potentially degrading the level of safety of the plant.

"At 1748 CDT Unit 1 received a call reporting smoke coming from the 480V Condensate Demineralizer Panel 3 in the Unit 3 turbine building elevation 557'. At approximately 1803 [CDT], the incident commander on the scene confirmed a fire inside the panel and all three units entered 0-AOI-26-1, Fire Response. The board was subsequently de-energized by operations personnel and the fire was extinguished at 1806 CDT. SM [Shift Manager] exited EAL HU4 and all three units exited 0-AOI-26-1 at 1840 CDT.

"Fire operations remain on scene to monitor. A team is being assembled for damage assessment and recovery.

"The fire did not affect any safety systems, no plant transients resulted, and no injuries were reported.

"This event is reportable within 1 hour IAW 10 CFR 50.72(a)(1)(i).

"The NRC Resident inspector has been notified."

Notified DHS SWO, FEMA Ops, DHS NICC, FEMA NWC (email) and NuclearSSA (email).

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Power Reactor Event Number: 53559
Facility: WATERFORD
Region: 4     State: LA
Unit: [3] [] []
RX Type: [3] CE
NRC Notified By: JOHN JARRELL
HQ OPS Officer: DONG HWA PARK
Notification Date: 08/23/2018
Notification Time: 12:11 [ET]
Event Date: 08/14/2018
Event Time: 16:00 [CDT]
Last Update Date: 08/23/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
NICK TAYLOR (R4DO)
PART 21/50.55 REACTORS (EMAIL)
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

PART 21 REPORT - DEFECT OF WESTINGHOUSE 7300 PROCESS ANALOG CONTROL SYSTEM CIRCUIT CARDS

"This is a non-emergency notification from Waterford 3.

"10 CFR Part 21 Notification - Defect of Westinghouse 7300 Process Analog Control System circuit cards

"On August 14, 2018, Entergy Operations, Inc. (Entergy) completed an evaluation of a deviation at Waterford Steam Electric Station, Unit 3 (Waterford 3) which concluded the condition constitutes a defect pursuant to 10 CFR Part 21. The Waterford 3 Site Vice President was notified of the result of this evaluation on August 21, 2018. An interim report stating that an evaluation of this deviation was in progress was submitted to the NRC on July 5, 2018 (Entergy letter W3F1-2018-0040, ADAMS Accession Number ML18186A694).

"Three Westinghouse 7300 Process Analog Control System (PAC) circuit cards were identified to be failed due to failed hex inverter chips. Some of these cards were installed in applications which support the Ultimate Heat Sink (UHS) at Waterford 3. These PAC cards use Texas Instruments Part Number SN74LS04N, W113 hex inverter chips. The circuit card types of concern are Analog Comparator model number 2838A32G01, Control Board model number 2838A30G011, and Prom Logic model number 2838A33G01. Entergy concluded that this condition could have prevented the UHS from performing its safety function and thus could have created a substantial safety hazard.

"The NRC Resident Inspector has been notified."


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Friday, May 03, 2019