| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
5/16/2018 - 5/17/2018 ** EVENT NUMBERS ** |
| Power Reactor | Event Number: 53290 | Facility: FARLEY
Region: 2 State: AL
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP
NRC Notified By: DOUGLAS HOBSON
HQ OPS Officer: DONALD NORWOOD | Notification Date: 03/26/2018
Notification Time: 18:19 [ET]
Event Date: 03/26/2018
Event Time: 13:38 [CDT]
Last Update Date: 05/16/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
OTHER UNSPEC REQMNT
| Person (Organization):
STEVE ROSE (R2DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Hot Standby | 0 | Hot Standby | Event Text TECHNICAL SPECIFICATIONS REQUIRED SHUTDOWN DUE TO INOPERABLE MAIN STEAM ISOLATION VALVE
"On March 25, 2018 at 1833 CDT, while at 100 percent power, Farley Unit 1 (FNP-1) conservatively declared a single Main Steam Isolation Valve (MSIV) inoperable on the 1C Steam Generator line due to indication of Steam Generator pressure rise with a corresponding reduction in flow of that loop. FNP-1 began a reactor shutdown at 0400 CDT on March 26, 2018 to establish plant conditions to support testing the affected main steam line MSIVs while in the required action time of Technical Specification 3.7.2. At 1338 CDT on March 26, 2018, testing confirmed that the single MSIV was inoperable and that valve disassembly will be required. The duration of the valve repair would exceed the required action time of Technical Specification 3.7.2. This report is being made in accordance with 10 CFR 50.72(b)(2)(i), as a plant shutdown required by technical specifications.
"The licensee has notified the NRC Resident Inspector."
* * * UPDATE FROM DOUGLAS HOBSON TO KEN MOTT AT 0202 EDT ON 5/16/18 * * *
"This EN [event notification] is being updated to clarify the reporting criteria as 'Voluntary'. Farley Technical Specification 3.7.2 allows continuous operation in MODE 2 with an INOPERABLE MSIV as long as the other MSIV in the affected Main Steam Line is closed. The initiation of the shutdown was performed as a prudent action to repair and restore OPERABILITY of the affected MSIV and was not a requirement of the Farley Technical Specifications."
The licensee notified the NRC Resident Inspector.
The R2DO (Masters) was notified. |
| Non-Agreement State | Event Number: 53394 | Rep Org: WEYERHAEUSER CORP.
Licensee: WEYERHAEUSER CORP.
Region: 4
City: SEATTLE State: WA
County:
License #: 25-15644-01
Agreement: Y
Docket:
NRC Notified By: TIM TADLOCK
HQ OPS Officer: BETHANY CECERE | Notification Date: 05/08/2018
Notification Time: 14:33 [ET]
Event Date: 05/05/2018
Event Time: 09:30 [MDT]
Last Update Date: 05/08/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
30.50(b)(2) - SAFETY EQUIPMENT FAILURE
| Person (Organization):
MARK HAIRE (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL) | Event Text STUCK SHUTTERS ON TWO GAUGES
During a periodic inventory check at the Columbia Falls, MT location, the Facility Radiation Safety Officer discovered two Ohmart SHF1 source holders with inoperable shutter mechanisms. Both Cs-137 sources (10 milliCuries and 50 milliCuries) are in areas where exposure to the sources is minimized by their inaccessible locations. Weyerhaeuser has been in contact with the manufacturer of the level gauge (Ohmart/Vega) about removing the inoperable source holders and replacing with two (2) new source holders.
The licensee contacted NRC Region 4 (Torres). |
| Power Reactor | Event Number: 53403 | Facility: VOGTLE
Region: 2 State: GA
Unit: [3] [4] []
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: DANIEL MICKINAC
HQ OPS Officer: ANDREW WAUGH | Notification Date: 05/16/2018
Notification Time: 16:51 [ET]
Event Date: 05/16/2018
Event Time: 11:33 [EDT]
Last Update Date: 05/16/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
ANTHONY MASTERS (R2DO)
FFD GROUP (EMAIL) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 3 | N | N | 0 | Under Construction | 0 | Under Construction | | 4 | N | N | 0 | Under Construction | 0 | Under Construction | Event Text FITNESS-FOR-DUTY TEST POSITIVE FOR NON-LICENSED SUPERVISOR
At 1133 EDT on May 16, 2018, Southern Nuclear Operating Company determined a non-licensed contractor supervisor 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 suspended.
The NRC Resident Inspector has been notified. |
| Power Reactor | Event Number: 53404 | Facility: ARKANSAS NUCLEAR
Region: 4 State: AR
Unit: [1] [] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: KEVIN PARKS
HQ OPS Officer: DONALD NORWOOD | Notification Date: 05/16/2018
Notification Time: 22:19 [ET]
Event Date: 05/16/2018
Event Time: 17:50 [CDT]
Last Update Date: 05/16/2018 | 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):
HEATHER GEPFORD (R4DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 10 | Power Operation | 0 | Hot Standby | Event Text AUTOMATIC REACTOR TRIP DUE TO LOSS OF MAIN FEEDWATER PUMP
"At 1750 CDT, the Arkansas Nuclear One, Unit 1 (ANO-1) reactor tripped due to the trip of the 'B' Main Feedwater Pump. Unit 1 was at 10 percent power with escalation of power in progress with one Main Feedwater Pump in service. Investigation is in progress as to the cause of the Main Feedwater Pump trip. The Main Feedwater Pump trip resulted in RPS [reactor protection system] actuation on loss of both Main Feedwater Pumps and resulted in Emergency Feedwater (EFW) actuation. All Control Rods inserted into the core properly and the reactor was verified shutdown.
"EFW experienced a half-trip on the 'A' train of Emergency Feedwater Initiation and Control (EFIC) at time of system actuation, but was successfully actuated manually immediately upon discovery. Train 'B' EFIC actuated in Automatic as designed. The half-trip of the 'A' train of EFIC is currently believed to be associated with EFIC Channel 'C'; however, investigation is underway to verify this.
"Currently, ANO-1 has been stabilized and is being maintained in Mode 3 with Auxiliary Feedwater in service. Heat removal is via Turbine Bypass valves to the Condenser.
"No radiological releases have occurred due to this event."
There was no effect on Arkansas Nuclear One, Unit 2. The licensee notified the NRC Resident Inspector and the State of Arkansas. |
| 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." | |