United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2019 > January 09

Event Notification Report for January 09, 2019

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
1/8/2019 - 1/9/2019

** EVENT NUMBERS **


53552 53817 53818 53819

To top of page
Power Reactor Event Number: 53552
Facility: THREE MILE ISLAND
Region: 1     State: PA
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] B&W-L-LP
NRC Notified By: ERIC MASCHUCK
HQ OPS Officer: ANDREW WAUGH
Notification Date: 08/17/2018
Notification Time: 08:17 [ET]
Event Date: 08/16/2018
Event Time: 15:19 [EDT]
Last Update Date: 01/08/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
MATT YOUNG (R1DO)
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

Event Text

FITNESS-FOR-DUTY TEST POSITIVE FOR NON-LICENSED EMPLOYEE

At 1519 EDT on August 16, 2018, Exelon determined a non-licensed employee had a confirmed positive for a controlled substance during a random Fitness-for-Duty test. The employee's unescorted access to the plant has been terminated.

The NRC Resident Inspector has been notified.


* * * UPDATE FROM MICHAEL FITZWATER TO DONALD NORWOOD AT 1310 EST ON 1/8/2019 * * *

The following is a correction to the reason for the Fitness-for-Duty test:

At 1519 EDT on August 16, 2018, Exelon determined a non-licensed employee had a confirmed positive for a controlled substance during a follow-up Fitness-for-Duty test. The employee's unescorted access to the plant has been terminated.

The NRC Resident Inspector has been notified of this correction.

Notified R1DO (Bower) and FFD E-mail group.

To top of page
Power Reactor Event Number: 53817
Facility: HATCH
Region: 2     State: GA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: NICHOLAS HIGHTOWER
HQ OPS Officer: JEFFREY WHITED
Notification Date: 01/08/2019
Notification Time: 08:12 [ET]
Event Date: 11/12/2018
Event Time: 13:31 [EST]
Last Update Date: 01/08/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.73(a)(1) - INVALID SPECIF SYSTEM ACTUATION
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

Event Text

INVALID SPECIFIED SYSTEM ACTUATION

"On November 12, 2018, at 1331 EST, Unit 1 secondary containment isolated and Standby Gas Treatment (SBGT) systems started on Unit 1 and Unit 2 due to a blown fuse. The blown fuse was caused by a degraded refuel floor radiation monitoring relay, causing the radiation monitor to trip and resulted in an invalid actuation of the Unit 1 Group 10 and Group 11 primary containment isolation valves, all Unit 1 secondary containment isolation valves, and auto start of the Unit 1 and Unit 2 SBGT system. The Unit 1 Fission Product Monitor isolated and tripped and both Unit 1 H202 Analyzers isolated.

"This event is reportable per 10 CFR 50.73(a)(2)(iv)(A) since the containment isolation and auto-start of SBGT on both units was not part of a pre-planned sequence and the event resulted in the invalid actuation of general containment isolation valves in more than one system.

"All primary and secondary containment isolation valves, with the exception of the 2T41F003A, Refueling Floor Inboard Vent Supply Isolation valve, functioned successfully. The refuel floor inboard vent supply isolation valve failed to travel fully closed on the secondary containment isolation signal and was therefore declared inoperable. The 2T41F003B refuel floor outboard vent supply isolation valve was verified to go fully closed and therefore isolation of that associated penetration line was successful. After assistance from maintenance, the valve was verified to be fully closed.

"All SBGT systems functioned successfully. The associated fuse and relay were replaced, and secondary containment was returned to normal service.

"The licensee notified the NRC Resident Inspector."

To top of page
Power Reactor Event Number: 53818
Facility: PILGRIM
Region: 1     State: MA
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: J. WEBERS
HQ OPS Officer: DONALD NORWOOD
Notification Date: 01/08/2019
Notification Time: 15:45 [ET]
Event Date: 01/08/2019
Event Time: 09:45 [EST]
Last Update Date: 01/08/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
Person (Organization):
FRED BOWER (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

REACTOR CORE ISOLATION COOLING DECLARED INOPERABLE

"On January 8, 2019, at 0945 EST Pilgrim Nuclear Power Station discovered that the Reactor Core Isolation Cooling (RCIC) system failed to meet its surveillance test requirements and was declared inoperable; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v), 'event or condition that could have prevented the fulfillment of a safety function: (D), mitigate the consequences of an accident.'

"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."

To top of page
Power Reactor Event Number: 53819
Facility: PALISADES
Region: 3     State: MI
Unit: [1] [] []
RX Type: [1] CE
NRC Notified By: DAN GEERLINGS
HQ OPS Officer: KARL DIEDERICH
Notification Date: 01/09/2019
Notification Time: 13:23 [ET]
Event Date: 01/09/2019
Event Time: 10:34 [EST]
Last Update Date: 01/09/2019
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):
DAVID HILLS (R3DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 A/R Y 100 Power Operation 0 Hot Standby

Event Text

REACTOR TRIP FROM FULL POWER DUE TO RPS TESTING

"At 1034 EST on January 9, 2019, with the reactor at 100% power, an automatic reactor trip was initiated. The trip occurred while Reactor Protection System testing was in progress. The trip was uncomplicated with all systems responding normally following the rip. Troubleshooting and investigation of the cause is ongoing.

"All full-length control rods inserted fully. Auxiliary Feedwater System actuated as designed in response to low steam generator water levels. Operations stabilized the plant in Mode 3 (hot standby). Decay heat is being removed by the turbine bypass valve.

"This condition has no impact to the health and safety of the public."

The licensee notified the NRC Resident Inspector.


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