| U.S. Nuclear Regulatory Commission
Operations Center Event Reports For
9/11/2018 - 9/12/2018 ** EVENT NUMBERS ** |
| Power Reactor | Event Number: 53593 | Facility: WATTS BAR
Region: 2 State: TN
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JUSTIN GALLAGHER
HQ OPS Officer: OSSY FONT | Notification Date: 09/11/2018
Notification Time: 05:17 [ET]
Event Date: 09/11/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/11/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
ALAN BLAMEY (R2DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 1 | N | Y | 97 | Power Operation | 97 | Power Operation | Event Text CONTROL ROOM EMERGENCY VENTILATION SYSTEM INOPERABLE
"At 0113 EDT on September 11, 2018, it was discovered both trains of CREVS [control room emergency ventilation system] were simultaneously inoperable; therefore, this condition is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(v).
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified."
The door to the main control room habitability zone from the turbine building was left open and unattended for about a minute, breaking the pressure boundary in the room, resulting in an alarm. The door was closed, clearing the alarm and the CREVS was considered operable. |
| Power Reactor | Event Number: 53594 | Facility: PEACH BOTTOM
Region: 1 State: PA
Unit: [2] [3] []
RX Type: [2] GE-4,[3] GE-4
NRC Notified By: TOM DINGEL
HQ OPS Officer: STEVEN VITTO | Notification Date: 09/11/2018
Notification Time: 17:14 [ET]
Event Date: 09/11/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/11/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(xiii) - LOSS COMM/ASMT/RESPONSE
| Person (Organization):
RAY MCKINLEY (R1DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | Y | 97 | Power Operation | 97 | Power Operation | | 3 | N | Y | 88 | Power Operation | 88 | Power Operation | Event Text TECHNICAL SUPPORT CENTER VENTILATION NON-FUNCTIONAL
"On September 11, 2018 the Technical Support Center (TSC) ventilation was discovered to be non-functional during system testing. At 1310 EDT, an air leak was identified that prevented the modulating dampers to operate as designed to maintain required pressure. The air leak was not able to be repaired within a 60 minute period. This failure affected the ability of the TSC ventilation system to maintain adequate radiological habitability in the event of an emergency with an airborne radiological release. All other capabilities of the TSC are unaffected by this emergent condition. The air leak has been repaired and post maintenance testing was completed satisfactory at 1654 [EDT], restoring the TSC ventilation to a functional condition.
"This notification is being made in accordance with 10 CFR 50.72(b)(3)(xiii) due to the potential loss of an emergency response facility because of the unavailability of the ventilation system."
The NRC Resident Inspector has been notified. |
| Power Reactor | Event Number: 53595 | Facility: VOGTLE
Region: 2 State: GA
Unit: [3] [4] []
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: KARA STACY
HQ OPS Officer: STEVEN VITTO | Notification Date: 09/11/2018
Notification Time: 17:53 [ET]
Event Date: 09/11/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/11/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
MIKE ERNSTES (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 CONTRACTOR SUPERVISOR TESTS POSITIVE ON FITNESS-FOR-DUTY TEST
"At 1430 EDT on September 11, 2018, Southern Nuclear Operating Company (SNC) determined a contractor supervisor confirmed positive for drugs during a Fitness-for-Duty (FFD) test. The employee's unescorted access to the plant has been suspended. The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 53597 | Facility: MONTICELLO
Region: 3 State: MN
Unit: [1] [] []
RX Type: [1] GE-3
NRC Notified By: RODNEY COONS
HQ OPS Officer: STEVEN VITTO | Notification Date: 09/11/2018
Notification Time: 18:42 [ET]
Event Date: 09/11/2018
Event Time: 00:00 [CDT]
Last Update Date: 09/11/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(B) - UNANALYZED CONDITION
50.72(b)(3)(v)(C) - POT UNCNTRL RAD REL
50.72(b)(3)(v)(D) - ACCIDENT MITIGATION
| Person (Organization):
JOHN HANNA (R3DO) | | 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 UNANALYZED CONDITION
"On 9/10/2018, the 11 Core Spray (CSP) loop was placed in service to support quarterly surveillance testing. With the 11 CSP pump in service it was identified that the check valves isolating the 11 CSP system from the keep fill supply were leaking by. At 1129 CDT on 9/11/2018, it was identified that this leakage may have exceeded the leakage rate assumptions made in the dose analysis calculation for emergency core cooling system (ECCS) leakage outside containment following a loss of coolant accident (LOCA). Therefore, this is being reported in accordance with 10 CFR 50.72(b)(3)(ii)(B) for an unanalyzed condition that significantly degrades plant safety and 10 CFR 50.72(b)(3)(v) for 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: (C) Control the release of radioactive material; or (D) Mitigate the consequences of an accident.
"The potential ECCS leak pathway has been isolated. There is no impact to health and safety of the public.
"The NRC Resident Inspector has been notified." |
| Power Reactor | Event Number: 53598 | Facility: SAINT LUCIE
Region: 2 State: FL
Unit: [] [2] []
RX Type: [1] CE,[2] CE
NRC Notified By: ANDREW TERERAKIS
HQ OPS Officer: STEVEN VITTO | Notification Date: 09/11/2018
Notification Time: 23:23 [ET]
Event Date: 09/11/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/11/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
| Person (Organization):
MIKE ERNSTES (R2DO) | | Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode | | 2 | N | N | 0 | | 0 | | Event Text WELD DEFECT ON PRESSURIZER INTERFACE
"At 2200 EDT on September 11, 2018, during inspections as part of the pressurizer bare metal inspection program, an apparent weld defect was identified on Class 1 pressurizer level piping at the piping to pressurizer interface. The reactor is currently defueled in a refueling outage. Appropriate repairs will be made during the refueling outage."
NRC Resident Inspector has been notified. |
| Power Reactor | Event Number: 53599 | Facility: VOGTLE
Region: 2 State: GA
Unit: [3] [4] []
RX Type: [3] W-AP1000,[4] W-AP1000
NRC Notified By: CURTIS CASTELL
HQ OPS Officer: ANDREW WAUGH | Notification Date: 09/12/2018
Notification Time: 14:14 [ET]
Event Date: 09/12/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/12/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
| Person (Organization):
MIKE ERNSTES (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 CONTRACTOR SUPERVISOR TESTS POSITIVE ON FITNESS-FOR-DUTY TEST
"At 1115 EDT on September 12, 2018, Southern Nuclear Operating Company (SNC) determined a contractor supervisor confirmed positive for drugs during a Fitness-for-Duty (FFD) test. The employee's unescorted access to the plant has been suspended. The Resident Inspector has been notified." |
| Part 21 | Event Number: 53600 | Rep Org: ENGINE SYSTEMS, INC
Licensee: ENGINE SYSTEMS, INC
Region: 1
City: ROCKY MOUNT State: NC
County:
License #:
Agreement: Y
Docket:
NRC Notified By: DAN ROBERTS
HQ OPS Officer: STEVEN VITTO | Notification Date: 09/12/2018
Notification Time: 16:19 [ET]
Event Date: 07/19/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/12/2018 | Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
| Person (Organization):
MIKE ERNSTES (R2DO)
PART 21 GROUP (EMAIL) | Event Text PART 21 - MOTOR OPERATED POTENTIOMETER DEFECT
"A batch of Motor Operated Potentiometers (MOPs) supplied by ESI [Engine Systems Inc.] were found to contain motors that, as they accumulate run time, exhibit increasing current draw and eventually exceed the MOP circuit allowance. Consequently, the motor operation becomes erratic which leads to a sluggish MOP. The MOP is used in a safety-related system to control emergency diesel generator (EDG) output voltage. Failure of the MOP to operate properly can negatively affect the EDG output voltage which affects associated components required to safely shutdown the nuclear reactor.
"ESI will revise the test procedure to incorporate an extended run time while trending the motor for any adverse changes. This will be completed within 30 days and will prevent reoccurrence.
"For Catawba, any MOPs from this batch are considered suspect and may be returned to ESI for rework or replacement. For units installed, the motor performance should be assessed prior to continued use. The voltage measured across terminals 3(-) and 4(+) while the MOP is operating should remain steady within a range of 22.8 to 25.2 VDC. Any step change or reduction in voltage is an indication of motor deterioration.
"The root cause of the excessive current draw was found to be build-up of carbonaceous deposits between the commutator sections of the motor either from the carbon brushes, contamination, or a combination of the two. As the motor accumulated run time, the deposits propagated to the point of a low resistance path between commutator sections which are wired to the armature poles. This affected the magnetic field within the motor which had a direct impact on motor performance. ESI has limited the issue to a single date code of motors supplied within a single batch of MOPs, as listed.
"Motor Operated Potentiometer, PIN 72-07900-100-ESI.
"Duke Energy Catawba, Customer PO 196046, Qty: 6, ESI Serial Number 3013905-1.1-1 thru 6, MOP Serial Number - H01931980, H01995582, H01995584, H01995585, H01995586, H01995587, C-of-C Date: 5/30/2015." | |