| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
10/27/2018 - 10/29/2018 ** EVENT NUMBERS ** |
| Agreement State | Event Number: 53679 | Rep Org: TEXAS DEPT OF STATE HEALTH SERVICES
Licensee: DESERT NDT LLC
Region: 4
City: ABILENE State: TX
County:
License #: LICEN-RAM-L06462
Agreement: Y
Docket:
NRC Notified By: ARTHUR TUCKER
HQ OPS Officer: DONALD NORWOOD | Notification Date: 10/21/2018
Notification Time: 16:19 [ET]
Event Date: 10/20/2018
Event Time: 00:00 [CDT]
Last Update Date: 10/21/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
| Person (Organization):
GREG PICK (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL) | Event Text AGREEMENT STATE REPORT - RADIOGRAPHY SOURCE FAILURE TO RETRACT
The following information was received via E-mail:
"On October 20, 2018, the agency [Texas Department of State Health Services] was notified by the licensee's radiation safety officer (RSO) that one of its radiography crews was unable to return an 80 curie iridium-192 source to the fully shielded position in an INC IR 100 exposure device. The RSO stated that the event occurred near Pecos, Texas. The RSO stated that the radiographers had established a 2 millirem boundary.
"An individual listed on their license responded to perform the source retrieval. The location where the event occurred was remote and the event did not present an exposure risk to any individual. The RSO stated that there are very few people at the site.
"Once the individual who was sent to retrieve the source arrived, they inspected the exposure device and guide tube. The inspection discovered the radiographers had bent the guide tube to get it through some pipes and the angle of the bend was what had prevented the source from being retracted. The guide tube was straightened and the source was retracted to the fully shielded position at 2100 hours. The guide tube was inspected and did not have any damage. The RSO stated that no overexposures had occurred."
Texas Incident Number: 9622 |
| Power Reactor | Event Number: 53696 | Facility: GINNA
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: WADE WEBER
HQ OPS Officer: OSSY FONT | Notification Date: 10/27/2018
Notification Time: 01:50 [ET]
Event Date: 10/26/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/27/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
DONNA JANDA (R1DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | N | 0 | Refueling | 0 | Refueling | Event Text AUTOMATIC START OF THE EMERGENCY DIESEL GENERATOR AND LOSS OF RADIATION MONITOR
"RCS [Reactor Coolant System] Pressure: vented to containment, refueling cavity greater than 23ft. [above reactor vessel]. RCS temperature: 96 degrees Fahrenheit.
"The 12A bus de-energized, 'A' EDG [Emergency Diesel Generator] automatically started and loaded on [emergency] buses 14 and 18. The RCS configuration is refueling cavity level greater than 23ft. above the reactor flange with no impact to shutdown cooling.
"Radiation monitor R-1, Control Room radiation monitor, lost power for 2 hrs 10 min. This placed Ginna in a major loss of emergency preparedness capabilities. A temporary radiation monitor has been installed in the Control Room."
Prior to the notification, the licensee had restored the 12A bus from offsite power and the R-1 monitor was re-energized.
The licensee notified the NRC Resident Inspector. |
| Power Reactor | Event Number: 53697 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: DAVID ALLEN
HQ OPS Officer: DONG HWA PARK | Notification Date: 10/27/2018
Notification Time: 16:52 [ET]
Event Date: 10/27/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/27/2018 | 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):
ERIC MICHEL (R2DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 21 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP FOLLOWING STARTUP
"On October 27, 2018, at 1533 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. [Main Steam Isolation Valves] MSIVs were required to be isolated due to cooldown. All safety systems responded as designed. The unit is currently stable in Mode 3, with decay heat removal via Auxiliary Feedwater and Steam Generator Atmospheric Dump Valves. 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 has been notified." |
| Power Reactor | Event Number: 53698 | Facility: CLINTON
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: DAVID LIVINGSTON
HQ OPS Officer: MARK ABRAMOVITZ | Notification Date: 10/28/2018
Notification Time: 08:57 [ET]
Event Date: 10/28/2018
Event Time: 00:00 [CDT]
Last Update Date: 10/28/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
MICHAEL KUNOWSKI (R3DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | A/R | Y | 1 | Startup | 0 | Hot Shutdown | Event Text AUTOMATIC REACTOR SCRAM DURING A REACTOR SHUTDOWN
"At 0445 [CDT], with reactor power less than 1% rated thermal power on Instrument Range Monitor (IRM) ranges 6 and 7, Clinton Power Station received an automatic Reactor Protection System (RPS) actuation. The Reactor Scram Off Normal procedure was entered and all control rods were verified to be fully inserted. The apparent cause of the scram is cold water injection causing an upscale trip of the IRMs due to Motor Driven Reactor Feedwater Pump (MDRFP) Feedwater Regulating valve 1FW004 valve coming off the full shut seat momentarily. All systems responded appropriately following the scram and the plant is currently stable. Clinton Power Station will be proceeding to Mode 4 to support the planned Maintenance Outage.
"The NRC Senior Resident Inspector has been notified." |
| Power Reactor | Event Number: 53699 | Facility: INDIAN POINT
Region: 1 State: NY
Unit: [2] [] []
RX Type: [2] W-4-LP,[3] W-4-LP
NRC Notified By: MICHAEL WEEDEN
HQ OPS Officer: KAREN COTTON | Notification Date: 10/28/2018
Notification Time: 15:10 [ET]
Event Date: 10/28/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/28/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
50.72(b)(3)(v)(B) - POT RHR INOP
| Person (Organization):
DONNA JANDA (R1DO) | | 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 NON ESSENTIAL SERVICE WATER INOPERABLE
"During the performance of Service Water Essential header swap, SWN-6 (Supply to Turbine Building Oil Coolers) valve stem became disconnected from its gear box at 85% open and could not be operated. Therefore, the non-essential service water system was inoperable. LCO 3.0.3 was entered at 0930 [EDT] with required actions to be in Mode 3 in 7 hours, Mode 4 in 13 hours and Mode 5 in 37 hours. Repair efforts were successful at shutting SWN-6, and LCO 3.0.3 was exited at 1305 [EDT] before adding any negative reactivity in support of shutdown. ('TS Required S/D' box not checked.)
"This condition constituted a loss of safety function which requires an 8 hour report [in accordance with] IAW 50.72(b)(3)(v)(B): Without the ability to close SWN-6, the non-seismic portion of the conventional Service Water System could not be isolated as required in the event of either a seismic event or as required in the EOPs. The nonessential service water system is required to support the recirculation phase post [Design Basis Accident] DBA for accident mitigation."
The licensee notified the NRC Resident Inspector and the State of New York. |
| Power Reactor | Event Number: 53700 | Facility: PRAIRIE ISLAND
Region: 3 State: MN
Unit: [1] [2] []
RX Type: [1] W-2-LP,[2] W-2-LP
NRC Notified By: JEFF HUMAN
HQ OPS Officer: VINCE KLCO | Notification Date: 10/28/2018
Notification Time: 21:44 [ET]
Event Date: 10/28/2018
Event Time: 00:00 [CDT]
Last Update Date: 10/28/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
MICHAEL KUNOWSKI (R3DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 29 | Power Operation | 29 | Power Operation | | 2 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text SEISMIC MONITORING PANEL SYSTEM INOPERABLE
"This event is being reported pursuant to 10 CFR 50.72(b)(3)(xiii) for a major loss of emergency assessment capability at the Prairie Island Nuclear Generating Plant.
"At 1435 CDT on October 28, 2018, troubleshooting of the Seismic Monitoring Panel resulting from the receipt of Control Room annunciator 47023-0603 (Seismic Monitor Panel) determined that the '[Operational Basis Earthquake] OBE Exceedance' alarm on the Seismic Monitoring Panel will not alarm and determined the panel is non-functional.
"The Seismic Monitoring Panel system functions to provide indication that the OBE threshold has been exceeded following a seismic event and is used in the Prairie Island Nuclear Generating Plant Emergency Plan to perform classification of Initiating Condition 'Seismic event greater than OBE levels' and Emergency Action Level HU2.1.
"Station personnel are monitoring the seismic recorders for event alarms on a 15 minute frequency due to alarm function failure. The station is developing repair plans for restoration of the alarm function.
"This event does not adversely affect the safe operation of the plant or health and safety of the public.
"The licensee has notified the NRC Resident Inspector." |
| Power Reactor | Event Number: 53702 | Facility: PALO VERDE
Region: 4 State: AZ
Unit: [1] [2] [3]
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: JORDAN ANDAZOLA
HQ OPS Officer: ANDREW WAUGH | Notification Date: 10/29/2018
Notification Time: 12:56 [ET]
Event Date: 10/29/2018
Event Time: 00:00 [MST]
Last Update Date: 10/29/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(xi) - OFFSITE NOTIFICATION
| Person (Organization):
CALE YOUNG (R4DO)
CHRIS MILLER (NRR EO)
WILLIAM GOTT (IRD) | | 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 | N | 0 | Defueled | 0 | Defueled | | 3 | N | Y | 100 | Power Operation | 100 | Power Operation | Event Text OFFSITE NOTIFICATION OF NON- WORK RELATED FATALITY
"The following event description is based on information currently available. If through subsequent reviews of this event additional information is identified that is pertinent to this event or alters the information being provided at this time, a follow-up notification will be made via the ENS or under the reporting requirements of 10CFR50.73.
"At approximately 03:30 MST on October 29, 2018, an Arizona Public Service Company (APS) employee developed a personal medical condition in the Owner Controlled Area outside of the Secured Owner Controlled Area at Palo Verde Generation Station (PVGS). PVGS Emergency Medical Technicians responded and transported the individual to an offsite emergency trauma center. Upon arrival at the trauma center, medical personnel declared the individual deceased at approximately 05:35 MST.
"The fatality was not work related and the individual was outside of the Radiological Controlled Area and no radioactive material or contamination was involved.
"No news release by APS is planned. Notifications were made to the Arizona Division of Occupational Safety and Health at 08:15 MST.
"The NRC Resident Inspectors have been notified." |
| Power Reactor | Event Number: 53703 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [1] [] []
RX Type: [1] CE,[2] CE
NRC Notified By: REESE KILIAN
HQ OPS Officer: ANDREW WAUGH | Notification Date: 10/29/2018
Notification Time: 16:47 [ET]
Event Date: 10/29/2018
Event Time: 00:00 [EDT]
Last Update Date: 10/29/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
| Person (Organization):
ERIC MICHEL (R2DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby | Event Text MANUAL REACTOR TRIP DUE TO INADEQUATE FEEDWATER FLOW
"On October 29, 2018 at 1317 EDT, with St. Lucie Unit 1 in Mode 1 at 100% power, the reactor was manually tripped due to inadequate feedwater flow to both 1A and 1B Steam Generators (S/Gs). The trip was uncomplicated with all systems responding normally post-trip. [All control rods fully inserted and there were no specified system actuations.] Operators responded and stabilized the plant in Mode 3. The cause of the inadequate feed flow to the 1A and 1B Steam Generators is currently under investigation.
"Decay Heat removal is being accomplished through forced circulation with stable conditions from Main Feedwater and the Steam Bypass Control System to the Main Condenser. Currently maintaining Pressurizer pressure at 2250 psia and Reactor Coolant System temperature at 532 degrees F.
"St. Lucie Unit 2 was unaffected and remains in Mode 1 at 100% power.
"This report is submitted in accordance with 10CFR50.72(b)(2)(iv)(B) for the reactor trip.
"The NRC Senior Resident Inspector has been notified." | |