| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
02/01/2018 - 02/02/2018 ** EVENT NUMBERS ** |
 | Agreement State | Event Number: 53182 | Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: EXXON MOBIL OIL CORPORATION
Region: 4
City: BEAUMONT State: TX
County:
License #: 00603
Agreement: Y
Docket:
NRC Notified By: KAREN BLANCHARD
HQ OPS Officer: JEFF HERRERA | Notification Date: 01/25/2018
Notification Time: 17:16 [ET]
Event Date: 01/25/2018
Event Time: [CST]
Last Update Date: 01/25/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG PICK (R4DO)
NMSS_EVENTS_NOTIFICA (EMAI)
| Event Text AGREEMENT STATE REPORT - TWO NUCLEAR GAUGES FOUND WITH SHUTTERS STUCK OPEN
The following report was received from the Texas Department of State Health Services via email:
"On January 25, 2018, the Agency [Texas Department of State Health Services] was notified that two of the licensee's Ohmart-Vega Model SHLG fixed nuclear gauges were found to have shutters stuck in the open position during preventative maintenance. These gauges normally operate with the shutter in the open position. There is no increased risk of exposure to any member of the public or licensee employees. Coordination is underway between the licensee, the service company, and the manufacturer for the gauges to be removed and returned to the manufacturer for repair or disposal.
"Source Information:
SN: 3253CM 2,000 milliCuries cesium-137
SN: 4021CM 2,000 milliCuries cesium-137"
Texas Incident #: I-9533 |
| Power Reactor | Event Number: 53190 | Facility: NINE MILE POINT
Region: 1 State: NY
Unit: [ ] [2] [ ]
RX Type: [1] GE-2,[2] GE-5
NRC Notified By: GREG BIXBY
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/01/2018
Notification Time: 11:59 [ET]
Event Date: 02/01/2018
Event Time: 11:08 [EST]
Last Update Date: 02/01/2018 | Emergency Class: UNUSUAL EVENT
10 CFR Section:
50.72(a) (1) (i) - EMERGENCY DECLARED
| Person (Organization):
DONNA JANDA (R1DO)
JEFFERY GRANT (IRD)
MICHELE EVANS ()
DAN COLLINS (R1 D)
|
| 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 UNUSUAL EVENT - FIRE IN THE TURBINE BUILDING LASTING GREATER THAN 15 MINUTES
"Nine Mile Point unit 2 experienced an unusual event due to a small fire in the turbine building that was immediately extinguished and then reflashed. The fire was declared out at 1119 [EST], 2/1/18. The fire was caused when steam leak repair injection equipment failed and leaked onto hot piping. There was no equipment damage or impact to plant operation. The fire was extinguished by the fire brigade. Offsite assistance was not required."
The fire resulted from Furmanite repair of a Moisture Separator Reheater inlet flow control valve. The unusual event will be terminated when sufficient lagging is removed to verify the extent of leaked fluid.
The licensee notified the NRC Resident Inspector.
Notified DHS SWO, FEMA, DHS NICC, and NNSA (via e-mail).
* * * UPDATE AT 1240 EST ON 2/1/2018 FROM ANTHONY PETRELLI TO MARK ABRAMOVITZ * * *
The unusual event was terminated at 1211 EST.
The licensee notified the NRC Resident Inspector.
Notified the R1DO (Janda), NRR EO (Miller), IRD MOC (Grant), DHS SWO, FEMA, DHS NICC, and NNSA (via e-mail). |
| Power Reactor | Event Number: 53191 | Facility: DAVIS BESSE
Region: 3 State: OH
Unit: [1] [ ] [ ]
RX Type: [1] B&W-R-LP
NRC Notified By: MICHAEL BOLES
HQ OPS Officer: VINCE KLCO | Notification Date: 02/01/2018
Notification Time: 13:50 [ET]
Event Date: 02/01/2018
Event Time: 07:49 [EST]
Last Update Date: 02/01/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
BILLY DICKSON (R3DO)
FFD GROUP (EMAI)
|
| 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 - CONFIRMED POSITIVE TEST
"A non-licensed [employee] supervisor had a confirmed positive test for alcohol during a random fitness-for-duty [FFD] test. The individual's unescorted access to the plant has been [terminated].
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 53192 | Facility: RIVER BEND
Region: 4 State: LA
Unit: [1] [ ] [ ]
RX Type: [1] GE-6
NRC Notified By: Timothy Gates
HQ OPS Officer: VINCE KLCO | Notification Date: 02/01/2018
Notification Time: 14:23 [ET]
Event Date: 02/01/2018
Event Time: 10:57 [CST]
Last Update Date: 02/01/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
RICK DEESE (R4DO)
|
| Unit | SCRAM Code | RX CRIT | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 27 | Power Operation | 0 | Hot Shutdown | Event Text MANUAL REACTOR SCRAM
"At 1057 CST on February 1, 2018 with the unit in Mode 1 at approximately 27% power, a manual actuation of the Reactor Protection System (RPS) was initiated due to an unexpected trip of the B Recirc Pump with A Recirc Pump in fast speed. B Recirc Pump tripped during transfer from slow to fast speed resulting in single loop operation. Operators were unable to reconcile differing indications of core flow. This resulted in a conservative decision to initiate a manual scram. The cause of the B Recirc Pump trip and the apparent issues with core flow indication are under investigation. The plant is currently stable in Mode 3.
"The plant response to the scram was as expected. All control rods [fully] inserted as expected; the feedwater system is maintaining reactor vessel water level in the normal control band and reactor pressure is being maintained with steam line drains and main turbine bypass valves.
"The NRC Senior Resident [Inspector] has been notified." |
| Part 21 | Event Number: 53193 | Rep Org: XCEL ENERGY
Licensee: WESTINGHOUSE ELECTRIC COMPANY
Region: 3
City: MONTECELLO State: MN
County:
License #:
Agreement: Y
Docket: 50-263
NRC Notified By: STEVE SOLLOM
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 02/01/2018
Notification Time: 16:23 [ET]
Event Date: 01/26/2018
Event Time: [CST]
Last Update Date: 02/01/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
BILLY DICKSON (R3DO)
PART 21/50.55 REACTO (EMAI)
| Event Text PART-21 NOTIFICATION - IMPROPER LUGS IN A BREAKER CUBICLE
The following notification is an excerpt from the received report:
"On November 30, 2017, an internal wire in a 480VAC cubicle, breaker B3424, was discovered to be terminated using incorrect size wire lugs. This deviation was identified by Monticello Nuclear Generating Plant (MNGP) electrical maintenance staff during bench testing of the cubicles in preparation for implementation of a modification.
"The cubicles were received by MNGP in September, 2017 from Westinghouse Electric Co.
"On January 26, 2017, MNGP completed an evaluation of this deviation and concluded this condition represents a significant safety hazard. As a result, this condition is a defect and is reportable pursuant to 10 CFR 21.21 (d)(4).
"Basic Component: Westinghouse: Eaton Breaker Cubicle Part No. 10149D92G05
"On November 30, 2017, an internal wire in a 480VAC cubicle, breaker 83424, was discovered to be terminated using incorrect size wire lugs. This condition was discovered during bench testing in preparation for implementing a modification to the Control Room Ventilation (CRV) system. The wire connection was found loose and was able to be lifted off of the terminal without removing the screw. Upon further examination, the internal diameter of ring termination lugs was found to be too large, providing only a partial surface area for screw head contact.
"The affected lugs were on contactor coil resistor terminations internal to the cubicle. Without sufficient contact area or connection to the wiring on the resistor, control power could be lost to the contactor coil resulting in the fan V-EF-40A not starting, which would prevent proper ventilation to the room housing safety related batteries required to be operable during an accident scenario. Therefore, MNGP determined that a substantial safety hazard could have been created had the breaker cubicle been installed with the defect uncorrected.
"This defect was evaluated according to the station's Part 21 reporting process. The evaluation was completed on January 26, 2018 and the reporting officer was informed on January 30, 2018.
"Westinghouse was notified of this condition and the condition was incorporated into their corrective action program, number 100506324. The Westinghouse contact person is Adam Tokar, 724-722-6042. No further information on the vendor's corrective actions is known.
"MNGP entered the condition into the MNGP Corrective Action Program under 501000005918. Monticello has corrected the lugs on the installed breaker, B4423. The remaining uninstalled cubicles purchased by Monticello are being corrected in accordance with MNGP procedure MWl-8-M-4.06, Conductor Termination, prior in installation in the plant." | |