United States Nuclear Regulatory Commission - Protecting People and the Environment
Home > NRC Library > Document Collections > Reports Associated with Events > Event Notification Reports > 2017 > May 3

Event Notification Report for May 3, 2017

U.S. Nuclear Regulatory Commission
Operations Center

Event Reports For
05/02/2017 - 05/03/2017

** EVENT NUMBERS **


52706 52722 52724 52725

To top of page
Agreement State Event Number: 52706
Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: EQUISTAR CHEMICAL LP
Region: 4
City: PASADENA State: TX
County:
License #: 01854
Agreement: Y
Docket:
NRC Notified By: CHRIS MOORE
HQ OPS Officer: MARK ABRAMOVITZ
Notification Date: 04/25/2017
Notification Time: 15:45 [ET]
Event Date: 04/25/2017
Event Time: [CDT]
Last Update Date: 04/25/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MICHAEL HAY (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)

Event Text

AGREEMENT STATE REPORT - FIXED NUCLEAR GAUGE STUCK SHUTTER

The following report was submitted via e-mail:

"On April 25, 2017, the Agency [Texas Department of State Health Services] was contacted by a licensee to report that a gauge would not close during a preventive maintenance check and the shutter is stuck. The gauge is an Ohmart SH-F1A, serial number 6228GK, containing a 50 mCi Cs-137 source. The shutter is stuck in the normal [open] operating position. The licensee is in contact with the manufacturer for a repair plan and with licensing for an exemption to operate the gauge temporarily with a stuck shutter. No exposures to the public are expected."

Texas Incident: I-9480

To top of page
Power Reactor Event Number: 52722
Facility: PALISADES
Region: 3 State: MI
Unit: [1] [ ] [ ]
RX Type: [1] CE
NRC Notified By: BARBARA DOTSON
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/02/2017
Notification Time: 15:26 [ET]
Event Date: 05/02/2017
Event Time: 09:28 [EDT]
Last Update Date: 05/02/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
ROBERT ORLIKOWSKI (R3DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 N N 0 Refueling 0 Refueling

Event Text

FAILED ULTRASONIC TESTING OF WELD

"On May 2, 2017, during planned inspections, an ultrasonic examination performed on weld PCS-4-PRS-1P1-1, revealed an axial indication in the pressurizer nozzle to safe end area of the weld. This indication does not meet applicable acceptance criteria under ASME, Section XI.

"The plant was in cold shutdown at 0% power for a planned refueling outage at the time of discovery. The condition will be resolved prior to plant startup.

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

"The licensee notified the NRC Senior Resident Inspector.

"This report is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A), since an indication was found that did not meet acceptance criteria referenced in ASME Code, Section XI.

To top of page
Power Reactor Event Number: 52724
Facility: FERMI
Region: 3 State: MI
Unit: [2] [ ] [ ]
RX Type: [2] GE-4
NRC Notified By: KELLEY BELENKY
HQ OPS Officer: BETHANY CECERE
Notification Date: 05/02/2017
Notification Time: 18:34 [ET]
Event Date: 05/02/2017
Event Time: 17:00 [EDT]
Last Update Date: 05/02/2017
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
Person (Organization):
ROBERT ORLIKOWSKI (R3DO)

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

UNANALYZED CONDITION FOR COMBUSTION TURBINE GENERATOR CONFIGURATION

"On May 2, 2017, while performing a past operability review associated with Combustion Turbine Generator (CTG) 11-1, it was determined that a past configuration of CTG 11-1 could not have assured all of the applicable Appendix R success criteria under all of the postulated scenarios described in the Updated Final Safety Analysis Report [UFSAR]. From November 21, 2016 until March 18, 2017 when Mode 4 was entered, CTG 11-1 was in a configuration where it could not be started from the dedicated shutdown panel, although it could be started locally. One of the specific scenarios for Appendix R in the UFSAR credits CTG 11-1 to support a safe shutdown based on an assumed time required to start CTG 11-1 and then provide flow to the reactor pressure vessel using the Standby Feedwater System. During the time period where CTG 11-1 could only be started locally, this assumed time would have been exceeded. Therefore, this event is being reported as an 'unanalyzed condition that significantly affects plant safety' under 50.72(b)(3)(ii)(B). At the time of discovery, CTG 11-1 was fully operable and the described condition had already been corrected.

"The NRC Resident Inspector has been notified."

To top of page
Power Reactor Event Number: 52725
Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [ ] [ ]
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: BILL SPRINKLE
HQ OPS Officer: DONG HWA PARK
Notification Date: 05/02/2017
Notification Time: 22:33 [ET]
Event Date: 05/02/2017
Event Time: 19:45 [EDT]
Last Update Date: 05/02/2017
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):
RANDY MUSSER (R2DO)

Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
1 M/R Y 26 Power Operation 0 Hot Standby

Event Text

MANUAL REACTOR TRIP DUE TO FAILED REACTOR COOLANT PUMP POWER TRANSFER

"On May 2nd, 2017, at 1945 EDT, Watts Bar Nuclear [WBN] Plant Unit 1 reactor was manually tripped due to a failure of the #3 Reactor Coolant Pump normal feeder breaker to close during the planned power transfer to unit power following startup. 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 main steam dump systems. Unit 1 is in a normal shutdown electrical alignment.

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

"There was no effect on WBN Unit 2.

"The NRC Senior Resident [Inspector] has been notified."

Page Last Reviewed/Updated Wednesday, May 03, 2017
Wednesday, May 03, 2017