Event Notification Report for April 20, 2018
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
04/19/2018 - 04/20/2018
EVENT NUMBERS
53352533535335455658
Power Reactor
Event Number: 53352
Facility: SUSQUEHANNA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVID HOPPE
HQ OPS Officer: JEFF HERRERA
Region: 1 State: PA
Unit: [1] [2] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: DAVID HOPPE
HQ OPS Officer: JEFF HERRERA
Notification Date: 04/20/2018
Notification Time: 16:05 [ET]
Event Date: 04/20/2018
Event Time: 00:00 [EDT]
Last Update Date: 04/20/2018
Notification Time: 16:05 [ET]
Event Date: 04/20/2018
Event Time: 00:00 [EDT]
Last Update Date: 04/20/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
26.719 - FITNESS FOR DUTY
10 CFR Section:
26.719 - FITNESS FOR DUTY
Person (Organization):
JON LILLIENDAHL (R1DO)
FFD GROUP (EMAIL)
JON LILLIENDAHL (R1DO)
FFD GROUP (EMAIL)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
| 2 | N | Y | 100 | Power Operation | 100 | Power Operation |
FITNESS FOR DUTY POLICY VIOLATION
A non-licensed supervisory contract worker was found in violation of the Fitness for Duty Program. The individual's access to the plant has been terminated.
The licensee notified the NRC Resident Inspector.
A non-licensed supervisory contract worker was found in violation of the Fitness for Duty Program. The individual's access to the plant has been terminated.
The licensee notified the NRC Resident Inspector.
Power Reactor
Event Number: 53353
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ALEX TRESPALACIOS
HQ OPS Officer: DONG HWA PARK
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: ALEX TRESPALACIOS
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/20/2018
Notification Time: 17:57 [ET]
Event Date: 04/20/2018
Event Time: 10:42 [CDT]
Last Update Date: 04/20/2018
Notification Time: 17:57 [ET]
Event Date: 04/20/2018
Event Time: 10:42 [CDT]
Last Update Date: 04/20/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
10 CFR Section:
50.72(b)(3)(v)(B) - POT RHR INOP
Person (Organization):
KENNETH RIEMER (R3DO)
KENNETH RIEMER (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
BOTH DIESEL GENERATORS INOPERABLE
On Friday, April 20, 2018 at 1042 CDT, Braidwood Station Unit 1 was at 0 percent power in Mode 6. The 1A Diesel Generator (DG) was inoperable with troubleshooting in progress. The 1B DG was being run for a normal monthly run in accordance with 1 BwOSR 3.8.1.2-2, 'Unit One 1B Diesel Generator Operability Surveillance,' and subsequently tripped. The trip was due to a failure of the overspeed butterfly valve actuator and springs, and not an actual overspeed condition. The unit entered Technical Specification (TS) 3.8.2, 'AC Sources - Shutdown,' Condition B for required DG inoperable. All required TS actions were met at the time of the 1B DG inoperability. The offsite power source remains available. At no time was residual heat removal lost.
"This event is reportable under 10 CFR 50.72(b)(3)(v)(B) 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 remove residual heat.
"The licensee has notified the NRC Resident Inspector."
On Friday, April 20, 2018 at 1042 CDT, Braidwood Station Unit 1 was at 0 percent power in Mode 6. The 1A Diesel Generator (DG) was inoperable with troubleshooting in progress. The 1B DG was being run for a normal monthly run in accordance with 1 BwOSR 3.8.1.2-2, 'Unit One 1B Diesel Generator Operability Surveillance,' and subsequently tripped. The trip was due to a failure of the overspeed butterfly valve actuator and springs, and not an actual overspeed condition. The unit entered Technical Specification (TS) 3.8.2, 'AC Sources - Shutdown,' Condition B for required DG inoperable. All required TS actions were met at the time of the 1B DG inoperability. The offsite power source remains available. At no time was residual heat removal lost.
"This event is reportable under 10 CFR 50.72(b)(3)(v)(B) 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 remove residual heat.
"The licensee has notified the NRC Resident Inspector."
Power Reactor
Event Number: 53354
Facility: BRAIDWOOD
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICH ROWE
HQ OPS Officer: DONG HWA PARK
Region: 3 State: IL
Unit: [1] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: RICH ROWE
HQ OPS Officer: DONG HWA PARK
Notification Date: 04/20/2018
Notification Time: 22:22 [ET]
Event Date: 04/20/2018
Event Time: 17:30 [CDT]
Last Update Date: 04/20/2018
Notification Time: 22:22 [ET]
Event Date: 04/20/2018
Event Time: 17:30 [CDT]
Last Update Date: 04/20/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
10 CFR Section:
50.72(b)(3)(ii)(A) - DEGRADED CONDITION
Person (Organization):
KENNETH RIEMER (R3DO)
KENNETH RIEMER (R3DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Refueling | 0 | Refueling |
DEGRADED REACTOR VESSEL HEAD
"On Friday, April 20, 2018 at 1730 CDT, during the Braidwood Station Unit 1 refueling outage (A1R20), a scheduled ultrasonic test (UT) was performed on the top head to upper center disc weld of the Unit 1 reactor head. The UT identified 19 indications, 9 of which are not acceptable per ASME Section XI, 2001 Edition, 2003 Addenda, Paragraph IWB-3510.
"This event is reportable under 10 CFR 50.72(b)(3)(ii)(A) for 'Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded'.
"The licensee notified the NRC Resident Inspector."
"On Friday, April 20, 2018 at 1730 CDT, during the Braidwood Station Unit 1 refueling outage (A1R20), a scheduled ultrasonic test (UT) was performed on the top head to upper center disc weld of the Unit 1 reactor head. The UT identified 19 indications, 9 of which are not acceptable per ASME Section XI, 2001 Edition, 2003 Addenda, Paragraph IWB-3510.
"This event is reportable under 10 CFR 50.72(b)(3)(ii)(A) for 'Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded'.
"The licensee notified the NRC Resident Inspector."
Agreement State
Event Number: 55658
Rep Org: Minnesota Department of Health
Licensee: New Flyer
Region: 3
City: St. Cloud State: MN
County:
License #: General License
Agreement: Y
Docket:
NRC Notified By: Sherrie Flaherty
HQ OPS Officer: Mike Stafford
Licensee: New Flyer
Region: 3
City: St. Cloud State: MN
County:
License #: General License
Agreement: Y
Docket:
NRC Notified By: Sherrie Flaherty
HQ OPS Officer: Mike Stafford
Notification Date: 12/16/2021
Notification Time: 14:17 [ET]
Event Date: 04/20/2018
Event Time: 00:00 [CST]
Last Update Date: 12/16/2021
Notification Time: 14:17 [ET]
Event Date: 04/20/2018
Event Time: 00:00 [CST]
Last Update Date: 12/16/2021
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Skokowski, Richard (R3)
NMSS_Events_Notification, (EMAIL)
ILTAB, (EMAIL)
CNSC (Canada), - (FAX)
Skokowski, Richard (R3)
NMSS_Events_Notification, (EMAIL)
ILTAB, (EMAIL)
CNSC (Canada), - (FAX)
EN Revision Imported Date: 1/14/2022
EN Revision Text: AGREEMENT STATE REPORT - LOST STATIC ELIMINATOR
The following information was received from the state of Minnesota via email:
"It has come to our attention during our IMPEP review that we have some events that were not directly reported to the HOO as required. They were reported to NMED, but we are now reporting them directly to the HOO.
"New Flyer reported the loss of a static elimination device (NRD model P-2021, serial #A2KY665) that contained a 370 MBq (10 milliCi) Po-210 source. While New Flyer was preparing to replace their devices, they discovered that one device was missing. They performed an investigation, which included searching the painters' lockers and totes, but were unable to find the device. The manufacturer was notified. The cause of the event was determined to be lack of procedure. Corrective actions included connecting static elimination devices to dedicated air lines to ensure they will not be misplaced."
Minnesota event number: 180001
THIS MATERIAL EVENT CONTAINS A 'Less than Cat 3' LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf
EN Revision Text: AGREEMENT STATE REPORT - LOST STATIC ELIMINATOR
The following information was received from the state of Minnesota via email:
"It has come to our attention during our IMPEP review that we have some events that were not directly reported to the HOO as required. They were reported to NMED, but we are now reporting them directly to the HOO.
"New Flyer reported the loss of a static elimination device (NRD model P-2021, serial #A2KY665) that contained a 370 MBq (10 milliCi) Po-210 source. While New Flyer was preparing to replace their devices, they discovered that one device was missing. They performed an investigation, which included searching the painters' lockers and totes, but were unable to find the device. The manufacturer was notified. The cause of the event was determined to be lack of procedure. Corrective actions included connecting static elimination devices to dedicated air lines to ensure they will not be misplaced."
Minnesota event number: 180001
THIS MATERIAL EVENT CONTAINS A 'Less than Cat 3' LEVEL OF RADIOACTIVE MATERIAL
Sources that are "Less than IAEA Category 3 sources," are either sources that are very unlikely to cause permanent injury to individuals or contain a very small amount of radioactive material that would not cause any permanent injury. Some of these sources, such as moisture density gauges or thickness gauges that are Category 4, the amount of unshielded radioactive material, if not safely managed or securely protected, could possibly - although it is unlikely - temporarily injure someone who handled it or were otherwise in contact with it, or who were close to it for a period of many weeks. For additional information go to http://www-pub.iaea.org/MTCD/publications/PDF/Pub1227_web.pdf