Event Notification Report for January 31, 2020
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
01/30/2020 - 01/31/2020
EVENT NUMBERS
54503545055450654504
Power Reactor
Event Number: 54503
Facility: FITZPATRICK
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ROBERT GRAHAM
HQ OPS Officer: THOMAS KENDZIA
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: ROBERT GRAHAM
HQ OPS Officer: THOMAS KENDZIA
Notification Date: 01/31/2020
Notification Time: 09:46 [ET]
Event Date: 01/31/2020
Event Time: 05:55 [EST]
Last Update Date: 01/31/2020
Notification Time: 09:46 [ET]
Event Date: 01/31/2020
Event Time: 05:55 [EST]
Last Update Date: 01/31/2020
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
MARK HENRION (R1DO)
MARK HENRION (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | A/R | Y | 38 | Power Operation | 0 | Hot Shutdown |
AUTOMATIC REACTOR SCRAM DUE TO MAIN TURBINE TRIP
"At 0555 [EST], on January 31, 2020, James A. FitzPatrick was at 38 percent power when an automatic scram occurred as a result of a main turbine trip on high Reactor Pressure Vessel (RPV) water level. The plant was at reduced power in preparation for maintenance activities. The 'A' Reactor Feed Pump (RFP) was being removed from service when a perturbation in reactor water level reached the high RPV water level setpoint. This resulted in a main turbine trip and 'B' RFP trip.
"The automatic scram inserted all control rods. A subsequent low water level resulted in a successful Group 2 isolation. The plant is stable in Mode 3 with the 'B' RFP maintaining RPV water level. The initiation of the reactor protection systems (RPS) due to the automatic scram signal at critical power is reportable per 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). The general containment Group 2 isolations are reportable per 10 CFR 50.72(b)(3)(iv)(A)."
The licensee notified the NRC Resident Inspector, and the State and Local government for the scram.
Decay heat is being removed via the main condenser.
"At 0555 [EST], on January 31, 2020, James A. FitzPatrick was at 38 percent power when an automatic scram occurred as a result of a main turbine trip on high Reactor Pressure Vessel (RPV) water level. The plant was at reduced power in preparation for maintenance activities. The 'A' Reactor Feed Pump (RFP) was being removed from service when a perturbation in reactor water level reached the high RPV water level setpoint. This resulted in a main turbine trip and 'B' RFP trip.
"The automatic scram inserted all control rods. A subsequent low water level resulted in a successful Group 2 isolation. The plant is stable in Mode 3 with the 'B' RFP maintaining RPV water level. The initiation of the reactor protection systems (RPS) due to the automatic scram signal at critical power is reportable per 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A). The general containment Group 2 isolations are reportable per 10 CFR 50.72(b)(3)(iv)(A)."
The licensee notified the NRC Resident Inspector, and the State and Local government for the scram.
Decay heat is being removed via the main condenser.
Agreement State
Event Number: 54505
Rep Org: ARIZONA DEPT OF HEALTH SERVICES
Licensee: VANN ENGINEERING
Region: 4
City: PHOENIX State: AZ
County:
License #: 07-263
Agreement: Y
Docket:
NRC Notified By: BRIAN GORETZKI
HQ OPS Officer: DONALD NORWOOD
Licensee: VANN ENGINEERING
Region: 4
City: PHOENIX State: AZ
County:
License #: 07-263
Agreement: Y
Docket:
NRC Notified By: BRIAN GORETZKI
HQ OPS Officer: DONALD NORWOOD
Notification Date: 01/31/2020
Notification Time: 15:35 [ET]
Event Date: 01/31/2020
Event Time: 00:00 [MST]
Last Update Date: 01/31/2020
Notification Time: 15:35 [ET]
Event Date: 01/31/2020
Event Time: 00:00 [MST]
Last Update Date: 01/31/2020
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
10 CFR Section:
AGREEMENT STATE
Person (Organization):
RAY AZUA (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
RAY AZUA (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - MOISTURE DENSITY GAUGE RUN OVER BY VEHICLE
The following information was received via E-mail:
"The Department [Arizona Department of Health Services] received notification from the licensee that a technician had backed up over a portable moisture density gauge with their truck. The gauge is a Troxler 3430, Serial Number 35062, containing approximately 8 milliCuries of cesium-137 and 40 milliCuries of americium-241:beryllium. The Department has requested additional information and continues to investigate the event.
Arizona Incident: 20-002
The following information was received via E-mail:
"The Department [Arizona Department of Health Services] received notification from the licensee that a technician had backed up over a portable moisture density gauge with their truck. The gauge is a Troxler 3430, Serial Number 35062, containing approximately 8 milliCuries of cesium-137 and 40 milliCuries of americium-241:beryllium. The Department has requested additional information and continues to investigate the event.
Arizona Incident: 20-002
Part 21
Event Number: 54506
Rep Org: FAIRBANKS MORSE
Licensee: FAIRBANKS MORSE
Region: 3
City: Beloit State: WI
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MARTIN KURR
HQ OPS Officer: KERBY SCALES
Licensee: FAIRBANKS MORSE
Region: 3
City: Beloit State: WI
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MARTIN KURR
HQ OPS Officer: KERBY SCALES
Notification Date: 01/31/2020
Notification Time: 16:32 [ET]
Event Date: 01/31/2020
Event Time: 00:00 [CST]
Last Update Date: 01/31/2020
Notification Time: 16:32 [ET]
Event Date: 01/31/2020
Event Time: 00:00 [CST]
Last Update Date: 01/31/2020
Emergency Class: NON EMERGENCY
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
10 CFR Section:
21.21(d)(3)(i) - DEFECTS AND NONCOMPLIANCE
Person (Organization):
MARK HENRION (R1DO)
JAMES BAPTIST (R2DO)
- PART 21/50.55 REACTORS (EMAIL)
MARK HENRION (R1DO)
JAMES BAPTIST (R2DO)
- PART 21/50.55 REACTORS (EMAIL)
Part 21 - UNKNOWN TIGHTNESS OF CAM THRUST LOCK NUT ASSEMBLY
The following information is a summary of information received via facsimile:
On January 31, 2020, Fairbanks Morse (FM) submitted information of a defect or failure of the unknown tightness of the opposed piston (OP) diesel engine cam thrust lock washer and lock nut assembly for emergency diesel generators (EDGs).
FM assembled and completed a factory acceptance test on a 1000 rpm new opposed piston diesel engine generator set. Upon post-test inspection it was discovered that the lock nut and lock washer had fallen off of the camshaft. The failure did not prevent the engine from starting, accelerating to rated speed as well as accepting and sustaining rated load. The failure does not result in an immediate engine shutdown or load rejection. The timing chain restrains the camshaft adequately for the engine to perform its emergency function. However, it cannot be concluded that the engine would continue to operate for the entire duration of its safety function.
This Part 21 notification is being issued for subject engines with less than 98 hours of operation since the camshaft lock nut assembly was tightened. This Part 21 notification is being applied only to engines with less than 98 operating hours since the cam lock nut assembly was tightened for the following two reasons: 1) There are no known occurrences of cam lock nut assembly failures on any 900 rpm FM OP engines. All FM OP engines in service as EDGs in the United States are 900 rpm and 2) A laboratory analysis of the failed components conclusively shows this failure is an infant mortality. In the event the cam lock nut is loose, the lock washer will fail very quickly upon engine operation.
FM has defined the appropriate tightening value to the cam lock nut assembly in Service Information Letter SIL-40 and has provided this guidance to all licensees that possess FM OP engines. FM has updated all internal engineering specifications and manufacturing instructions to include the newly specified tightening requirements. There are no 10 CFR 50 Appendix B FM OP engines being newly constructed.
A list of affected customers are: Exelon - Peach Bottom Nuclear Generating Station and Southern Nuclear / Georgia Power - Hatch Nuclear Power Plant
FM Notification Report Serial Number 20-01
The following information is a summary of information received via facsimile:
On January 31, 2020, Fairbanks Morse (FM) submitted information of a defect or failure of the unknown tightness of the opposed piston (OP) diesel engine cam thrust lock washer and lock nut assembly for emergency diesel generators (EDGs).
FM assembled and completed a factory acceptance test on a 1000 rpm new opposed piston diesel engine generator set. Upon post-test inspection it was discovered that the lock nut and lock washer had fallen off of the camshaft. The failure did not prevent the engine from starting, accelerating to rated speed as well as accepting and sustaining rated load. The failure does not result in an immediate engine shutdown or load rejection. The timing chain restrains the camshaft adequately for the engine to perform its emergency function. However, it cannot be concluded that the engine would continue to operate for the entire duration of its safety function.
This Part 21 notification is being issued for subject engines with less than 98 hours of operation since the camshaft lock nut assembly was tightened. This Part 21 notification is being applied only to engines with less than 98 operating hours since the cam lock nut assembly was tightened for the following two reasons: 1) There are no known occurrences of cam lock nut assembly failures on any 900 rpm FM OP engines. All FM OP engines in service as EDGs in the United States are 900 rpm and 2) A laboratory analysis of the failed components conclusively shows this failure is an infant mortality. In the event the cam lock nut is loose, the lock washer will fail very quickly upon engine operation.
FM has defined the appropriate tightening value to the cam lock nut assembly in Service Information Letter SIL-40 and has provided this guidance to all licensees that possess FM OP engines. FM has updated all internal engineering specifications and manufacturing instructions to include the newly specified tightening requirements. There are no 10 CFR 50 Appendix B FM OP engines being newly constructed.
A list of affected customers are: Exelon - Peach Bottom Nuclear Generating Station and Southern Nuclear / Georgia Power - Hatch Nuclear Power Plant
FM Notification Report Serial Number 20-01
Agreement State
Event Number: 54504
Rep Org: FLORIDA BUREAU OF RADIATION CONTROL
Licensee: BDJL ENTEPRISES LLC DBA BLUE WATER SPA COVERS
Region: 1
City: Apopka State: FL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MATTHEW SENISON
HQ OPS Officer: KERBY SCALES
Licensee: BDJL ENTEPRISES LLC DBA BLUE WATER SPA COVERS
Region: 1
City: Apopka State: FL
County:
License #:
Agreement: Y
Docket:
NRC Notified By: MATTHEW SENISON
HQ OPS Officer: KERBY SCALES
Notification Date: 01/31/2020
Notification Time: 14:56 [ET]
Event Date: 01/31/2020
Event Time: 00:00 [EST]
Last Update Date: 02/03/2020
Notification Time: 14:56 [ET]
Event Date: 01/31/2020
Event Time: 00:00 [EST]
Last Update Date: 02/03/2020
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MARK HENRION (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
OIP_Notifications Resource (EMAIL)
MARK HENRION (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
OIP_Notifications Resource (EMAIL)
GAMMA ALARM FIXED RADIATION PORTAL MONITOR
The following was received from the state of Florida Bureau of Radiation Control via fax:
"[Customs and Border Protection] CBP called the [Bureau of Radiation Control Incident Response Center] BRC IRC to report that at 1105 EST, CBP had a gamma alarm from a fixed radiation portal monitor for a 20 ft. sea container manifested as containing PVC Leather, Buckles, and Grommets. A CBP officer inspected the container using a RadSeeker DL RIID (1.5x1.5in LaBr3). The RIID identified Th-232, and this was confirmed manually by CBP lab personnel using PeakEasy gamma spectroscopy software. The highest reported dose rate was 103 microR/hr at contact with the sea container (1034 cps at contact); this is approximately 9-10 times the average background dose rate for this location. The radiation was distributed throughout the entire length of the container. Guidance requested as to whether or not CBP should refuse entry on the shipment, or if it is acceptable to release it into commerce. There are concerns as to whether or not this product may contain one-twentieth of one percent (0.05 percent) or more by weight of Th-232, violate other radiological regulations, or pose additional concerns."
Notified R1DO (Henrion), NMSS Events (email), OIP Notifications Resource (email)
Florida Incident Number: FL20-011
* * * UPDATE ON 2/3/20 AT 1400 EST FROM MATTHEW SENISON TO KERBY SCALES * * *
"This morning between 0800 and 0900 EST, [BRC IRC] inspector went to the Blount Island Marine Terminal in Jacksonville, FL to inspect a container that US Customs and Border Protection had identified as having higher than background levels of radiation. The container was opened for [the inspector], and [the inspector] found the items in the container did match the information that was reported to the Bureau of Radiation Control (BRC). Specifically, spools of faux-leather, and boxes that contained plastic grommets and buckles. These items were manufactured or assembled in China for delivery to a pool cover supply company in Apopka, FL. The boxes did not contain radiation levels above background. The spools of faux-leather had slightly higher than background levels of radiation when unrolled. Their spindles were made of cardboard and did not have higher than background levels of radiation. When the faux-leather was rolled up, the radioactivity increased.
"The BRC has given the guidance that the container and its contents may be released, but this has not happened yet. If it is released, the BRC is of the opinion that the intended recipient should be surveyed for radiation, in case this is a common occurrence."
Notified R1DO (Henrion), NMSS Events (email), and OIP Notifications Resource (email)
The following was received from the state of Florida Bureau of Radiation Control via fax:
"[Customs and Border Protection] CBP called the [Bureau of Radiation Control Incident Response Center] BRC IRC to report that at 1105 EST, CBP had a gamma alarm from a fixed radiation portal monitor for a 20 ft. sea container manifested as containing PVC Leather, Buckles, and Grommets. A CBP officer inspected the container using a RadSeeker DL RIID (1.5x1.5in LaBr3). The RIID identified Th-232, and this was confirmed manually by CBP lab personnel using PeakEasy gamma spectroscopy software. The highest reported dose rate was 103 microR/hr at contact with the sea container (1034 cps at contact); this is approximately 9-10 times the average background dose rate for this location. The radiation was distributed throughout the entire length of the container. Guidance requested as to whether or not CBP should refuse entry on the shipment, or if it is acceptable to release it into commerce. There are concerns as to whether or not this product may contain one-twentieth of one percent (0.05 percent) or more by weight of Th-232, violate other radiological regulations, or pose additional concerns."
Notified R1DO (Henrion), NMSS Events (email), OIP Notifications Resource (email)
Florida Incident Number: FL20-011
* * * UPDATE ON 2/3/20 AT 1400 EST FROM MATTHEW SENISON TO KERBY SCALES * * *
"This morning between 0800 and 0900 EST, [BRC IRC] inspector went to the Blount Island Marine Terminal in Jacksonville, FL to inspect a container that US Customs and Border Protection had identified as having higher than background levels of radiation. The container was opened for [the inspector], and [the inspector] found the items in the container did match the information that was reported to the Bureau of Radiation Control (BRC). Specifically, spools of faux-leather, and boxes that contained plastic grommets and buckles. These items were manufactured or assembled in China for delivery to a pool cover supply company in Apopka, FL. The boxes did not contain radiation levels above background. The spools of faux-leather had slightly higher than background levels of radiation when unrolled. Their spindles were made of cardboard and did not have higher than background levels of radiation. When the faux-leather was rolled up, the radioactivity increased.
"The BRC has given the guidance that the container and its contents may be released, but this has not happened yet. If it is released, the BRC is of the opinion that the intended recipient should be surveyed for radiation, in case this is a common occurrence."
Notified R1DO (Henrion), NMSS Events (email), and OIP Notifications Resource (email)