| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
5/17/2018 - 5/18/2018 ** EVENT NUMBERS ** |
| Agreement State | Event Number: 53397 | Rep Org: LOUISIANA RADIATION PROTECTION DIV
Licensee: EXXON MOBIL CHEMICAL CO.
Region: 4
City: BATON ROUGE State: LA
County:
License #: LA-2349-L01, Amd.36
Agreement: Y
Docket:
NRC Notified By: JOE NOBLE
HQ OPS Officer: DONALD NORWOOD | Notification Date: 05/10/2018
Notification Time: 17:20 [ET]
Event Date: 05/01/2018
Event Time: 00:00 [CDT]
Last Update Date: 05/10/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
MARK HAIRE (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL) | Event Text AGREEMENT STATE REPORT - STUCK PROCESS GAUGE SHUTTER
The following is a synopsis of information received via E-mail:
On 5/9/2018, the Radiation Safety Officer (RSO) for ExxonMobil Chemical Co. (EMCo) reported a device failure to the Louisiana Department of Environmental Quality. On 5/1/2018 during routine annual maintenance and preventive maintenance checks it was discovered that a level density gauge had a shutter stuck in the open position.
The gauge was a Ronan Engineering Co. gauge, Model Number SA1-C5 loaded with 100 mCi Cs-137 (10/95). The device s/n is EE815. The source and source holder usually have one s/n for the whole device. A RONAN engineering sales and service company was contacted to fix the problem by repairing the gauge and the shutter to function properly. The gauge is installed on processes and does not pose a health and safety threat to the general public or the EMCo employees. The gauge will remain on the operational process until the repair is made to the device. A service order number was generated by EMCo for the device repair. The shutter was stuck in the open position due to the buildup of grime and corrosive material from the operational environment. This is considered an equipment failure for reporting requirements.
Louisiana Event Report ID No.: LA-180008 |
| Power Reactor | Event Number: 53405 | Facility: SOUTH TEXAS
Region: 4 State: TX
Unit: [1] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ANDY DUNLAP
HQ OPS Officer: ANDREW WAUGH | Notification Date: 05/16/2018
Notification Time: 23:29 [ET]
Event Date: 05/16/2018
Event Time: 22:02 [CDT]
Last Update Date: 05/17/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
HEATHER GEPFORD (R4DO) | | 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 OF FIRES IN THE OWNER CONTROLLED AREA
"On May 16, 2018 at approximately 1425 CDT, two grass fires started in the Owner Controlled Area surrounding South Texas Project (STP) Nuclear Generating Station. The Bay City Volunteer Fire Department was called to the site to fight the fire. Reinforcements from Tres Palacios Oaks, Midfield and Markham Fire Departments were called in to assist with firefighting efforts. The grass fires were extinguished on May 16, 2018 at 2046 CDT. The fires occurred outside the protected area of the plant and presented no danger to the public or the safe operation of the units.
"On May 16, 2018 at 2202 CDT, STP Nuclear Generating Station issued a press release to inform area residents."
The licensee notified the NRC Resident Inspector.
* * * UPDATE ON MAY 17, 2018 AT 13:33 EDT FROM BILLY HERZOG TO THOMAS KENDZIA * * *
"On May 17, 2018, at 11:10 CDT STP Nuclear Generating Station notified the Texas Commission on Environmental Quality (TCEQ) of the grass fires, resulting in visible emissions, that occurred in the Owner Controlled Area of the STP Nuclear Generating Station on May 16, 2018, between the times of 14:25 and 20:46 CDT.
"No further press releases are planned."
The licensee notified the NRC Resident Inspector.
Notified R4DO (Gepford). |
| Power Reactor | Event Number: 53406 | Facility: BRUNSWICK
Region: 2 State: NC
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: MICHAEL LONG
HQ OPS Officer: STEVEN VITTO | Notification Date: 05/17/2018
Notification Time: 14:26 [ET]
Event Date: 05/17/2018
Event Time: 10:45 [EDT]
Last Update Date: 05/17/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
ANTHONY MASTERS (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 EMERGENCY NOTIFICATION SIREN MALFUNCTIONING
"On May 17, 2018, at approximately 1045 Eastern Daylight Time (EDT), Duke Energy confirmed that one emergency notification siren (i.e., B03) located in Brunswick County was malfunctioning. The siren was making an abnormal sound, alternating between low and high pitch. At approximately 1103 EDT, the siren was deactivated. There are a total of 38 sirens located in Brunswick and New Hanover Counties. No other siren was affected.
"Duke Energy notified the State of North Carolina, Brunswick County, and New Hanover County of the issue.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 53408 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: WAYNE SEXSON
HQ OPS Officer: THOMAS KENDZIA | Notification Date: 05/17/2018
Notification Time: 17:33 [ET]
Event Date: 05/17/2018
Event Time: 11:15 [CDT]
Last Update Date: 05/17/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
| Person (Organization):
KARLA STOEDTER (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 AUTOMATIC ACTUATION OF EMERGENCY DIESEL GENERATOR
"At 1115 (CDT) on May 17, 2018 with Unit 2 in Mode 1 at 100% power, the station experienced an auto-start of Emergency Diesel Generator, D5. Preliminary information indicates that the Bus 25 Potential Transformer (PT) fuse drawer was inadvertently opened, causing Breaker 25-16 to open and de-energize bus 25. Operators were able to manually close the D5 EDG output breaker to re-energize bus 25. 22 Component Cooling (CC) Pump auto-started on the loss of 21 CC Pump due to low pressure in the CC system as designed. All equipment functioned as designed.
"This event is being reported in accordance with 10 CFR 50.72(b)(3)(iv)(A) as an event that results in a valid actuation of the EDG.
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Senior Resident Inspector has been notified." |
| Power Reactor | Event Number: 53409 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DALE SHELTON
HQ OPS Officer: STEVEN VITTO | Notification Date: 05/17/2018
Notification Time: 23:02 [ET]
Event Date: 05/17/2018
Event Time: 15:03 [CDT]
Last Update Date: 05/17/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
KARLA STOEDTER (R3DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown | Event Text EMERGENCY DIESEL GENERATORS INOPERABLE
"On May 17, 2018, with the Unit in Mode 4, Clinton Power Station experienced the concurrent inoperability of two Emergency Diesel Generators (DG). This event is being reported as an 8-hour non-emergency notification per 10 CFR 50.72(b)(3)(v) as, 'Any event or condition that at the time of discovery could have prevented the fulfillment of the safety function of structures or systems that are needed to mitigate the consequences of an accident.'
"On May 17, 2018, at 15:03 CDT, it was identified that the Division 2 DG air start receiver isolation valves 1DG160 and 1DG161 were shut. With these valves shut, the Division 2 DG is inoperable. At the time, Division 1 DG was also inoperable for a 4160V 1A1 partial bus outage. The Technical Specification (TS) Actions for TS 3.8.2, AC Sources Shutdown, and TS 3.5.2, RPV Water Inventory Control, were entered as a result of the inoperability of the onsite AC power sources to isolation valves being credited to limit RPV DRAIN TIME.
"Division 2 DG air receivers were realigned at 15:45 CDT and the Division 2 DG auto start function was restored. Offsite power was available throughout this event and there was no impact to the health and safety of the public or plant personnel.
"Investigation is ongoing. It has been determined that the air start receiver isolation valves remained closed following system restoration on May 11, 2018. However, the Division 2 DG was not required to be Operable by TS until 00:45 CDT on May 14, 2018 when the Division 1 DG was made inoperable as a result of scheduled plant maintenance.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 53410 | Facility: COLUMBIA GENERATING STATION
Region: 4 State: WA
Unit: [2] [] []
RX Type: [2] GE-5
NRC Notified By: SEAN KEEHN
HQ OPS Officer: STEVEN VITTO | Notification Date: 05/18/2018
Notification Time: 13:27 [ET]
Event Date: 05/18/2018
Event Time: 06:51 [PDT]
Last Update Date: 05/18/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
HEATHER GEPFORD (R4DO)
JEFFERY GRANT (IRD)
MICHAEL F. KING (NRR EO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | A/R | Y | 100 | Power Operation | 0 | Hot Shutdown | Event Text AUTOMATIC REACTOR SCRAM CAUSED BY MAIN TRANSFORMER TRIP
"At 0651 [PDT] on May 18th, 2018, Columbia Generating station experienced a Main Transformer trip, that caused a Reactor Scram. Reactor Power, Pressure and Level were maintained as expected for this condition. MS-RV-1A (Safety Relief Valve) and MS-RV-1B (Safety Relief Valve) opened on reactor high pressure during the initial transient. MS-RV-1B appeared to remain open after pressure lowered below the reset point. The operating crew removed power supply fuses for MS-RV-1B and it currently indicates intermediate position. SRV (Safety Relief Valve) tail pipe temperatures indicate all valves are closed. Suppression pool level and temperature have remained steady within normal operating levels.
"All control rods inserted and reactor power is being maintained subcritical.
"RPV (Reactor Pressure Vessel) water level is being maintained with condensate and feed system with startup flow control valves in automatic. Reactor Pressure is being maintained with the Turbine Bypass valves controlling in automatic. The main condenser is the heat sink.
"No ECCS (Emergency Core Cooling Systems) systems actuated or injected; the EOC-RPT (End of Cycle-Recirculation Pump Trip) and RPS (Reactor Protection System) systems actuated causing a trip of the RRC pumps and a reactor scram.
"Core recirculation is being maintained with RRC-P-1A (Reactor Recirculation Pump) running.
"No release has occurred.
"At this time there will be no notifications to state, local or other public agencies.
"The NRC Senior Resident has been notified.
"The cause of the event is currently under investigation. Plant conditions are stable."
The plant is in its normal electrical alignment and offsite power is available to the site. | |