Event Notification Report for July 06, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
07/05/2023 - 07/06/2023
Agreement State
Event Number: 56654
Rep Org: WA Office of Radiation Protection
Licensee: BP Products North America, Inc.
Region: 4
City: Blaine State: WA
County:
License #: WN-I064-1
Agreement: Y
Docket:
NRC Notified By: James Killingbeck
HQ OPS Officer: Bill Gott
Licensee: BP Products North America, Inc.
Region: 4
City: Blaine State: WA
County:
License #: WN-I064-1
Agreement: Y
Docket:
NRC Notified By: James Killingbeck
HQ OPS Officer: Bill Gott
Notification Date: 08/03/2023
Notification Time: 19:19 [ET]
Event Date: 07/06/2023
Event Time: 00:00 [PDT]
Last Update Date: 08/03/2023
Notification Time: 19:19 [ET]
Event Date: 07/06/2023
Event Time: 00:00 [PDT]
Last Update Date: 08/03/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Azua, Ray (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Azua, Ray (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - FIXED GAUGE SHUTTER STUCK IN THE ON POSITION
The following information was provided by the Washington State Office of Radiation Protection via email:
"During the semi-annual routine shutter tests on a fixed gauge, the gauge was found to be stuck in the 'ON' position. This malfunction did not pose any additional risk to personnel in the 'ON' position; it only inhibited the ability to lock the gauge in the 'OFF' position for maintenance. The gauge manufacturer was contacted, and a service engineer was able to move the source tube assembly to the 'OFF' position by applying lubricant to the handle rod and gently twisting and pulling on it. This event appears to have occurred due to a lack of lubricant on the handle rod, or from the dust conditions that the gauge is located in, resulting in the source tube assembly becoming stuck inside the source housing. Going forward, a few drops of lubricant will be added during the semi-annual shutter checks to prevent the source tube assembly from becoming stuck again."
There were no personnel overexposures due to this event.
Device/Source Details: VEGA Americas, Inc., model number: HLG-2, serial number: 13570676, containing a 2 Ci (original activity) Cs-137 source.
Reference Document Number: WA-23-013.
The following information was provided by the Washington State Office of Radiation Protection via email:
"During the semi-annual routine shutter tests on a fixed gauge, the gauge was found to be stuck in the 'ON' position. This malfunction did not pose any additional risk to personnel in the 'ON' position; it only inhibited the ability to lock the gauge in the 'OFF' position for maintenance. The gauge manufacturer was contacted, and a service engineer was able to move the source tube assembly to the 'OFF' position by applying lubricant to the handle rod and gently twisting and pulling on it. This event appears to have occurred due to a lack of lubricant on the handle rod, or from the dust conditions that the gauge is located in, resulting in the source tube assembly becoming stuck inside the source housing. Going forward, a few drops of lubricant will be added during the semi-annual shutter checks to prevent the source tube assembly from becoming stuck again."
There were no personnel overexposures due to this event.
Device/Source Details: VEGA Americas, Inc., model number: HLG-2, serial number: 13570676, containing a 2 Ci (original activity) Cs-137 source.
Reference Document Number: WA-23-013.
Power Reactor
Event Number: 56610
Facility: Millstone
Region: 1 State: CT
Unit: [2] [] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: Jason Paris
HQ OPS Officer: Karen Cotton-Gross
Region: 1 State: CT
Unit: [2] [] []
RX Type: [1] GE-3,[2] CE,[3] W-4-LP
NRC Notified By: Jason Paris
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 07/06/2023
Notification Time: 16:48 [ET]
Event Date: 07/06/2023
Event Time: 12:32 [EDT]
Last Update Date: 07/10/2023
Notification Time: 16:48 [ET]
Event Date: 07/06/2023
Event Time: 12:32 [EDT]
Last Update Date: 07/10/2023
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(ii)(B) - Unanalyzed Condition
10 CFR Section:
50.72(b)(3)(ii)(B) - Unanalyzed Condition
Person (Organization):
Lilliendahl, Jon (R1DO)
Lilliendahl, Jon (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 |
EN Revision Imported Date: 7/11/2023
EN Revision Text: UNANALYZED CONDITION
The following information was provided by the licensee via email:
"On July 6, 2023, at 1232 EDT, while operating in Mode 1 at 100 percent power, the supply check valve from the number 2 steam generator to the turbine driven auxiliary feedwater pump was determined during troubleshooting that it is not able to perform its isolation function. This failure would have resulted in the blowdown of both steam generators during a main steam line break in the number 2 steam generator main steam line upstream of the main steam isolation valves until the operators could isolate the faulted steam generator. Previous evaluation has determined that this condition constituted an unanalyzed condition that could impact containment pressure.
"There was no radioactive release to the environment. The steam line from the steam generator to the turbine driven auxiliary feedwater pump was isolated by use of a motor operated valve in the discharge line of the number 2 steam generator. There was no impact to Unit 3 which remains at 100 percent power.
"The NRC Senior Resident Inspector was notified.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(B) as a condition that resulted in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety."
EN Revision Text: UNANALYZED CONDITION
The following information was provided by the licensee via email:
"On July 6, 2023, at 1232 EDT, while operating in Mode 1 at 100 percent power, the supply check valve from the number 2 steam generator to the turbine driven auxiliary feedwater pump was determined during troubleshooting that it is not able to perform its isolation function. This failure would have resulted in the blowdown of both steam generators during a main steam line break in the number 2 steam generator main steam line upstream of the main steam isolation valves until the operators could isolate the faulted steam generator. Previous evaluation has determined that this condition constituted an unanalyzed condition that could impact containment pressure.
"There was no radioactive release to the environment. The steam line from the steam generator to the turbine driven auxiliary feedwater pump was isolated by use of a motor operated valve in the discharge line of the number 2 steam generator. There was no impact to Unit 3 which remains at 100 percent power.
"The NRC Senior Resident Inspector was notified.
"This condition is being reported pursuant to 10 CFR 50.72(b)(3)(ii)(B) as a condition that resulted in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety."