Event Notification Report for September 14, 2018
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
09/13/2018 - 09/14/2018
Power Reactor
Event Number: 53606
Facility: SALEM
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JUSTIN HARGRAVE
HQ OPS Officer: BRIAN LIN
Region: 1 State: NJ
Unit: [] [2] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: JUSTIN HARGRAVE
HQ OPS Officer: BRIAN LIN
Notification Date: 09/14/2018
Notification Time: 16:28 [ET]
Event Date: 09/14/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/14/2018
Notification Time: 16:28 [ET]
Event Date: 09/14/2018
Event Time: 00:00 [EDT]
Last Update Date: 09/14/2018
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
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL 50.72(b)(3)(iv)(A) - VALID SPECIF SYS ACTUATION
Person (Organization):
RAY MCKINLEY (R1DO)
RAY MCKINLEY (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | A/R | Y | 90 | Power Operation | 0 | Hot Standby |
AUTOMATIC REACTOR TRIP DUE TO A FAILURE OF THE STEAM GENERATOR FEED REGULATING VALVE
"At 1323 [EDT] on 9/14/18, with Unit 2 in Mode 1 at 90% power, the reactor automatically tripped due to a failure of 23BF19, 23 Steam Generator (SG) Feed Regulating Valve. The trip was not complex, with all systems responding normally post-trip. No equipment was inoperable prior to the event. An actuation of the auxiliary feedwater system occurred following the automatic reactor trip. The reason for the auxiliary feed water system auto-start was due to low level in the steam generator. Operations responded and stabilized the plant. Decay heat is being removed by the main steam dumps and auxiliary feedwater system. Unit 1 is not affected.
"Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non- emergency notification per 10 CFR 50.72(b)(2)(iv)(B). 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 auxiliary feed water system.
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified. The Lower Alloways Creek Township will be notified."
"At 1323 [EDT] on 9/14/18, with Unit 2 in Mode 1 at 90% power, the reactor automatically tripped due to a failure of 23BF19, 23 Steam Generator (SG) Feed Regulating Valve. The trip was not complex, with all systems responding normally post-trip. No equipment was inoperable prior to the event. An actuation of the auxiliary feedwater system occurred following the automatic reactor trip. The reason for the auxiliary feed water system auto-start was due to low level in the steam generator. Operations responded and stabilized the plant. Decay heat is being removed by the main steam dumps and auxiliary feedwater system. Unit 1 is not affected.
"Due to the Reactor Protection System actuation while critical, this event is being reported as a four-hour, non- emergency notification per 10 CFR 50.72(b)(2)(iv)(B). 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 auxiliary feed water system.
"There was no impact on the health and safety of the public or plant personnel.
"The NRC Resident Inspector has been notified. The Lower Alloways Creek Township will be notified."
Agreement State
Event Number: 53607
Rep Org: NV DIV OF RAD HEALTH
Licensee: AZTECH MATERIALS AND TESTING, LLC
Region: 4
City: LAS VEGAS State: NV
County:
License #: RML 00-11-0482-01
Agreement: Y
Docket:
NRC Notified By: JOHN FOLLETTE
HQ OPS Officer: THOMAS KENDZIA
Licensee: AZTECH MATERIALS AND TESTING, LLC
Region: 4
City: LAS VEGAS State: NV
County:
License #: RML 00-11-0482-01
Agreement: Y
Docket:
NRC Notified By: JOHN FOLLETTE
HQ OPS Officer: THOMAS KENDZIA
Notification Date: 09/14/2018
Notification Time: 18:25 [ET]
Event Date: 09/14/2018
Event Time: 00:00 [PDT]
Last Update Date: 09/14/2018
Notification Time: 18:25 [ET]
Event Date: 09/14/2018
Event Time: 00:00 [PDT]
Last Update Date: 09/14/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
AGREEMENT STATE
10 CFR Section:
AGREEMENT STATE
Person (Organization):
MARK HAIRE (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
LANCE ENGLISH (ILTAB)
MARK HAIRE (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
LANCE ENGLISH (ILTAB)
AGREEMENT STATE REPORT - STOLEN MOSITURE DENSITY GAUGE
The following information was received from the State of Nevada via email:
"Around 0900 PDT on September 14, 2018 the State of Nevada Radiation Control Program was informed by Aztech Inspection & Testing, LLC, RML 00-11-0482-01, that a Humboldt, Model 5001EZ, Serial Number 1142, containing 10 millicuries (mCi) of cesium-137 and 40 mCi americium-241: beryllium, was stolen from the licensee's vehicle parked in the parking lot of the gauge user's residence. The gauge was secured to the steering wheel using a chain and lock inside of the cab of a locked pickup truck. The State is following the incident and working with local authorities to develop a press release. Local Law enforcement and the FBI have been notified. Follow-up information will be provided to NRC on the recovery of the stolen gauge and entered into NMED [Nuclear Material Event Database]."
Nevada NMED report number NV180004
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
The following information was received from the State of Nevada via email:
"Around 0900 PDT on September 14, 2018 the State of Nevada Radiation Control Program was informed by Aztech Inspection & Testing, LLC, RML 00-11-0482-01, that a Humboldt, Model 5001EZ, Serial Number 1142, containing 10 millicuries (mCi) of cesium-137 and 40 mCi americium-241: beryllium, was stolen from the licensee's vehicle parked in the parking lot of the gauge user's residence. The gauge was secured to the steering wheel using a chain and lock inside of the cab of a locked pickup truck. The State is following the incident and working with local authorities to develop a press release. Local Law enforcement and the FBI have been notified. Follow-up information will be provided to NRC on the recovery of the stolen gauge and entered into NMED [Nuclear Material Event Database]."
Nevada NMED report number NV180004
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
Power Reactor
Event Number: 53608
Facility: GRAND GULF
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: GERRY ELLIS
HQ OPS Officer: ANDREW WAUGH
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: GERRY ELLIS
HQ OPS Officer: ANDREW WAUGH
Notification Date: 09/14/2018
Notification Time: 21:09 [ET]
Event Date: 09/14/2018
Event Time: 00:00 [CDT]
Last Update Date: 09/14/2018
Notification Time: 21:09 [ET]
Event Date: 09/14/2018
Event Time: 00:00 [CDT]
Last Update Date: 09/14/2018
Emergency Class: NON EMERGENCY
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
10 CFR Section:
50.72(b)(2)(iv)(B) - RPS ACTUATION - CRITICAL
Person (Organization):
MARK HAIRE (R4DO)
MARK HAIRE (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Shutdown |
MANUAL REACTOR SCRAM
"At 1644 [CDT] a manual reactor scram was inserted by placing the Reactor Mode Switch to Shutdown. At 1643 [CDT] the Condensate Booster Pump A tripped on low suction pressure. At 1644 [CDT] the Reactor Feed Pump A tripped on low suction pressure. A Recirculation Flow Control Valve runback occurred as designed. Reactor Water level was approaching the Automatic Low Water Level 3 (11.4 inches) scram set point and manual actions were taken by placing the Mode Switch to Shutdown before the low level set point was reached. All systems responded as expected following the manual scram. The plant is stable in mode 3. This event is being reported under 10CFR 50.72(b)(2)(iv)(B), as any event or condition that results in actuation of the Reactor Protection System (RPS), when the reactor is critical.
"The NRC Senior Resident Inspector has been notified."
All control rods fully inserted, and decay heat is being removed through the turbine bypass valves to the main condenser. The licensee is investigating the cause of the event.
"At 1644 [CDT] a manual reactor scram was inserted by placing the Reactor Mode Switch to Shutdown. At 1643 [CDT] the Condensate Booster Pump A tripped on low suction pressure. At 1644 [CDT] the Reactor Feed Pump A tripped on low suction pressure. A Recirculation Flow Control Valve runback occurred as designed. Reactor Water level was approaching the Automatic Low Water Level 3 (11.4 inches) scram set point and manual actions were taken by placing the Mode Switch to Shutdown before the low level set point was reached. All systems responded as expected following the manual scram. The plant is stable in mode 3. This event is being reported under 10CFR 50.72(b)(2)(iv)(B), as any event or condition that results in actuation of the Reactor Protection System (RPS), when the reactor is critical.
"The NRC Senior Resident Inspector has been notified."
All control rods fully inserted, and decay heat is being removed through the turbine bypass valves to the main condenser. The licensee is investigating the cause of the event.