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Event Notification Report for May 22, 2019

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
5/21/2019 - 5/22/2019

** EVENT NUMBERS **


53822 53982 54063 54075 54077 54078

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!!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 53822
Facility: FERMI
Region: 3     State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: GREG MILLER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 01/11/2019
Notification Time: 10:07 [ET]
Event Date: 01/11/2019
Event Time: 09:11 [EST]
Last Update Date: 05/21/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
DAVID HILLS (R3DO)
FFD GROUP (EMAIL)
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



EN Revision Imported Date : 5/22/2019

EN Revision Text: FITNESS FOR DUTY

A non-licensed employee disclosed that he had previously used illegal drugs. The employee's access to the plant has been terminated.

The licensee notified the NRC Resident Inspector.


* * * RETRACTION FROM ETHAN HAUSER TO DONALD NORWOOD AT 1456 EDT ON 5/21/2019 * * *

"The following event notifications are retracted: EN 53822 reported on 1/11/2019 and EN 53982 reported on 4/5/2019.

"Subsequent to the initial notification, further investigation revealed that no new information was discovered that would meet the criteria for reporting under RG 5.62 or NUREG-1304. Further the events were also determined to be limited to an act of personal deception by those applying for unescorted access, without intent to commit or cause events identified in paragraphs I (a) and (d) of Appendix G to Part 73, and is not a programmatic breakdown. Based on this information, and consistent with the NRC memorandum dated May 19, 1995, 'Access Authorization Reportability and Enforcement Issues,' this event does not meet the threshold for reporting.

"The NRC Resident Inspector has been notified."

Notified R3DO (Cameron) and via E-mail the FFD E-mail group.

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!!!!! THIS EVENT HAS BEEN RETRACTED.THIS EVENT HAS BEEN RETRACTED !!!!!
Power Reactor Event Number: 53982
Facility: FERMI
Region: 3     State: MI
Unit: [2] [] []
RX Type: [2] GE-4
NRC Notified By: ETHAN HAUSER
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/05/2019
Notification Time: 12:19 [ET]
Event Date: 04/05/2019
Event Time: 11:25 [EDT]
Last Update Date: 05/21/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
JOHN HANNA (R3DO)
FFD GROUP (EMAIL)
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



EN Revision Imported Date : 5/22/2019

EN Revision Text: FITNESS-FOR-DUTY: FALSIFIED PRE-EMPLOYMENT INFORMATION

A non-licensed employee falsified pre-employment information. The employee's access to the plant has been terminated.


* * * RETRACTION FROM ETHAN HAUSER TO DONALD NORWOOD AT 1456 EDT ON 5/21/2019 * * *

"The following event notifications are retracted: EN 53822 reported on 1/11/2019 and EN 53982 reported on 4/5/2019.

"Subsequent to the initial notification, further investigation revealed that no new information was discovered that would meet the criteria for reporting under RG 5.62 or NUREG-1304. Further the events were also determined to be limited to an act of personal deception by those applying for unescorted access, without intent to commit or cause events identified in paragraphs I (a) and (d) of Appendix G to Part 73, and is not a programmatic breakdown. Based on this information, and consistent with the NRC memorandum dated May 19, 1995, 'Access Authorization Reportability and Enforcement Issues,' this event does not meet the threshold for reporting.

"The NRC Resident Inspector has been notified."

Notified R3DO (Cameron) and via E-mail the FFD E-mail group.

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Agreement State Event Number: 54063
Rep Org: WISCONSIN RADIATION PROTECTION
Licensee: TC TRANSCONTINENTAL
Region: 3
City: MENASHA   State: WI
County:
License #: 139-1408-01
Agreement: Y
Docket:
NRC Notified By: JERRY LEE
HQ OPS Officer: JEFFREY WHITED
Notification Date: 05/13/2019
Notification Time: 13:40 [ET]
Event Date: 05/10/2019
Event Time: 16:00 [CDT]
Last Update Date: 05/13/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
KARLA STOEDTER (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)

Event Text

AGREEMENT STATE REPORT - SHUTTER STUCK IN OPEN POSITION

The following was received via e-mail:

"On May 13, 2019, the Wisconsin Department of Health Services (DHS) was notified by the licensee TC Transcontinental that at around 1600 CDT on Friday, May 10, 2019, a shutter got stuck in the open position. A ThermoFisher technician was on site doing regular maintenance checks on a Kr-85 Thermo EGS Gauging Model TFC-185 when the shutter got stuck in the open position. The licensee cordoned off the area to prevent unauthorized access to the vicinity.

"ThermoFisher was on site Saturday, May 11, 2019 and repaired the stuck shutter. The shutter now opens and closes as expected.

"The Wisconsin DHS will perform a reactive inspection with the licensee."

Event Report ID No.: WI 190004

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Power Reactor Event Number: 54075
Facility: SUMMER
Region: 2     State: SC
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-AP1000,[3] W-AP1000
NRC Notified By: BETH DALICK
HQ OPS Officer: THOMAS KENDZIA
Notification Date: 05/21/2019
Notification Time: 17:14 [ET]
Event Date: 05/20/2019
Event Time: 18:33 [EDT]
Last Update Date: 05/21/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
72.75(d)(1) - SFTY EQUIP. DISABLED OR FAILS TO FUNCTION
Person (Organization):
SCOTT SHAEFFER (R2DO)
NMSS_EVENTS_NOTIFICATION (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

POTENTIAL MISSED SURVEILLANCE FOR ISFSI

"At approximately 1833 EDT on 5/20/2019, VC Summer Nuclear Station identified a potential missed surveillance of the Spent Fuel Storage Canister Heat Removal System Surveillance Requirement (SR) 3.1.2. This is a surveillance requirement in the Holtec CoC No. 1032 Amendment 0, Revision 1 for the HI-STORM FW. It was identified that the station suspended verifying all overpack inlets and outlets were free of blockage from solid debris or floodwater every 24 hours and began utilizing the alternate surveillance method of installed temperature monitoring equipment. However, this monitoring equipment had not been declared operable from the completion of the Dry Cask Storage Campaign on April 11, 2019. This surveillance was last performed satisfactorily on May 15, 2019.

"The station has documented this missed surveillance in the Corrective Action Program under CR-19-01866.

"The NRC Senior Resident has been notified."

The licensee stated that the temperature monitoring equipment while not operable, was functional. The licensee successfully performed the surveillance requirement on 5/21/2019.

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Power Reactor Event Number: 54077
Facility: WATTS BAR
Region: 2     State: TN
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BRIAN MCILNAY
HQ OPS Officer: JEFFREY WHITED
Notification Date: 05/22/2019
Notification Time: 05:45 [ET]
Event Date: 05/22/2019
Event Time: 02:33 [EDT]
Last Update Date: 05/22/2019
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):
SCOTT SHAEFFER (R2DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
2 M/R Y 95 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO FAILURE OF MAIN FEEDWATER REGULATING VALVE

"On May 22, 2019, at 0233 EDT, Watts Bar Nuclear Plant (WBN) Unit 2 reactor was manually tripped due to a failure of the #2 Main Feedwater Regulating Valve during power ascension following a refueling outage. Concurrent with the reactor trip, the Auxiliary Feedwater system actuated as designed.

"All Control and Shutdown rods fully inserted. All safety systems responded as designed. The unit is currently stable in Mode 3, with decay heat removal via Auxiliary Feedwater and Steam Dumps. Unit 2 is in a normal shutdown electrical alignment.

"This reactor trip and system actuation is being reported under 10 CFR 50.72(b)(3)(iv)(A) and 10 CFR 50.72(b)(2)(iv)(B).

"There was no impact to WBN Unit 1.

"The NRC Senior Resident has been notified."

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Power Reactor Event Number: 54078
Facility: SUSQUEHANNA
Region: 1     State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DARVIN DUTTRY
HQ OPS Officer: JEFFREY WHITED
Notification Date: 05/22/2019
Notification Time: 06:01 [ET]
Event Date: 05/22/2019
Event Time: 02:56 [EDT]
Last Update Date: 05/22/2019
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(i) - PLANT S/D REQD BY TS
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)(C) - POT UNCNTRL RAD REL
Person (Organization):
FRANK ARNER (R1DO)
Unit SCRAM Code RX Crit Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N Y 100 Power Operation 80 Power Operation
2 N Y 100 Power Operation 80 Power Operation

Event Text

TECHNICAL SPECIFICATION REQUIRED SHUTDOWN

"On 5/22/2019, the 'A' Control Structure Chiller (Div I) tripped due to a loss of [motor control center] MCC 0B136. The 'B' Control Structure Chiller was already inoperable due to Div II [Emergency Service Water] ESW being out of service for planned maintenance. With the loss of Control Structure HVAC System the ability to maintain temperatures in various spaces including relay rooms, Control Room Floor Cooling and Emergency Switchgear rooms was lost. The 'B' Control Structure Chiller was restarted at 0251 EDT and cooling was reestablished to the required areas, however the 'B' chiller is not considered operable at this time.

"Units 1 and 2 entered [Technical Specification] TS 3.0.3 at 0256 EDT and a controlled shutdown of both units commenced, Unit 2 at 0340 EDT and Unit 1 0350 EDT.

"This constitutes a TS required shutdown and requires a 4 hour [Emergency Notification System] ENS notification in accordance with 10 CFR 50.72(b)(2)(i). The failure also requires an 8 hour ENS notification in accordance with 10 CFR 50.72(b)(3)(v) due to the loss of a safety function."

The licensee needs to restore the 'B' loop of ESW to exit the Limiting Condition of Operation (LCO). The licensee is currently performing a flow surveillance, once complete and assuming the data is acceptable, the licensee will be able to exit the LCO.

The units are in a normal electrical lineup.

The licensee will be notifying the state of Pennsylvania FEMA Operations Center.

The licensee has notified the NRC Resident Inspector.


Page Last Reviewed/Updated Thursday, July 11, 2019
Thursday, July 11, 2019