Event Notification Report for October 04, 2021
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/03/2021 - 10/04/2021
Non-Power Reactor
Event Number: 55509
Rep Org: Missouri U of Science & Tech (MIST)
Licensee: Missouri University Of Science And Technology
Region: 0
City: Rolla State: MO
County: Phelps
License #: R-79
Agreement: Y
Docket: 0500123
NRC Notified By: Ethan Taber
HQ OPS Officer: Brian Lin
Licensee: Missouri University Of Science And Technology
Region: 0
City: Rolla State: MO
County: Phelps
License #: R-79
Agreement: Y
Docket: 0500123
NRC Notified By: Ethan Taber
HQ OPS Officer: Brian Lin
Notification Date: 10/05/2021
Notification Time: 13:20 [ET]
Event Date: 10/04/2021
Event Time: 00:00 [CDT]
Last Update Date: 10/05/2021
Notification Time: 13:20 [ET]
Event Date: 10/04/2021
Event Time: 00:00 [CDT]
Last Update Date: 10/05/2021
Emergency Class: Non Emergency
10 CFR Section:
10 CFR Section:
Person (Organization):
TAKAS, MICHAEL (NPR)
TORRES, PAULETTE (PM)
TAKAS, MICHAEL (NPR)
TORRES, PAULETTE (PM)
EN Revision Imported Date: 11/5/2021
EN Revision Text: TECHNICAL SPECIFICATION VIOLATION
"The Missouri University of Science and Technology Reactor (MSTR) is required by facility Technical Specification 3.3.2 to maintain pool water resistivity above 0.2 MOhm-cm so long as fuel elements are in the pool. TS 3.3.2 continues that 'This requirement may be waived for a period of up to 3 weeks once every 3 years.' On September 13, 2021, pool resistivity dropped below the 0.2 MOhm-cm threshold, triggering the three-week waiver to support water deionization system maintenance. Ion exchange resins for this system were replaced, but the system was not able to be restored to an operational status prior to exceeding the three-week waiver. It is noted that pool resistivity recovered above 0.2 MOhm-cm by September 14, 2021 and was maintained until the system was removed from service to replace the resins (September 28, 2021).
"This report is being made under the provisions of MSTR Technical Specification 6.7.2, requiring a report by telephone to the NRC Headquarters Operations Center no later than the following working day. Under the provisions of MSTR Technical Specification 6.7.2, a written follow-up report will be submitted to the Commission within 14 days. Additional replacement parts will need to be secured and repairs performed to restore operability. It is anticipated that full compliance with TS 3.3.2 will be restored within two weeks (by October 19, 2021)."
EN Revision Text: TECHNICAL SPECIFICATION VIOLATION
"The Missouri University of Science and Technology Reactor (MSTR) is required by facility Technical Specification 3.3.2 to maintain pool water resistivity above 0.2 MOhm-cm so long as fuel elements are in the pool. TS 3.3.2 continues that 'This requirement may be waived for a period of up to 3 weeks once every 3 years.' On September 13, 2021, pool resistivity dropped below the 0.2 MOhm-cm threshold, triggering the three-week waiver to support water deionization system maintenance. Ion exchange resins for this system were replaced, but the system was not able to be restored to an operational status prior to exceeding the three-week waiver. It is noted that pool resistivity recovered above 0.2 MOhm-cm by September 14, 2021 and was maintained until the system was removed from service to replace the resins (September 28, 2021).
"This report is being made under the provisions of MSTR Technical Specification 6.7.2, requiring a report by telephone to the NRC Headquarters Operations Center no later than the following working day. Under the provisions of MSTR Technical Specification 6.7.2, a written follow-up report will be submitted to the Commission within 14 days. Additional replacement parts will need to be secured and repairs performed to restore operability. It is anticipated that full compliance with TS 3.3.2 will be restored within two weeks (by October 19, 2021)."
Power Reactor
Event Number: 55504
Facility: Ginna
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: Eric Matz
HQ OPS Officer: Jeffrey Whited
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: Eric Matz
HQ OPS Officer: Jeffrey Whited
Notification Date: 10/04/2021
Notification Time: 08:05 [ET]
Event Date: 10/04/2021
Event Time: 00:31 [EDT]
Last Update Date: 10/04/2021
Notification Time: 08:05 [ET]
Event Date: 10/04/2021
Event Time: 00:31 [EDT]
Last Update Date: 10/04/2021
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
10 CFR Section:
50.72(b)(3)(iv)(A) - Valid Specif Sys Actuation
Person (Organization):
CARFANG, ERIN (R1)
CARFANG, ERIN (R1)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Hot Standby | 0 | Hot Shutdown |
EN Revision Imported Date: 11/4/2021
EN Revision Text: VALID SYSTEM ACTUATION
"The 'A' Steam Generator Narrow Range Water Level went less than 17 percent causing an Auxiliary Feed Water System valid actuation signal.
"The Auxiliary Feed Water System was in service at the time of the event providing decay heat removal. There was no adverse effect on plant systems. The Steam Generator Narrow Range Water Level was restored to normal operating band.
"This is being reported per 10 CFR 50.72(b)(3)(iv)(A), which states, 'Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) of this section, except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.'
"[Reactor Coolant System] RCS Pressure 340 pounds and RCS Temperature 340 Degrees F."
The NRC Resident Inspector was notified.
EN Revision Text: VALID SYSTEM ACTUATION
"The 'A' Steam Generator Narrow Range Water Level went less than 17 percent causing an Auxiliary Feed Water System valid actuation signal.
"The Auxiliary Feed Water System was in service at the time of the event providing decay heat removal. There was no adverse effect on plant systems. The Steam Generator Narrow Range Water Level was restored to normal operating band.
"This is being reported per 10 CFR 50.72(b)(3)(iv)(A), which states, 'Any event or condition that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) of this section, except when the actuation results from and is part of a pre-planned sequence during testing or reactor operation.'
"[Reactor Coolant System] RCS Pressure 340 pounds and RCS Temperature 340 Degrees F."
The NRC Resident Inspector was notified.
Power Reactor
Event Number: 55506
Facility: Arkansas Nuclear
Region: 4 State: AR
Unit: [2] [] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: Derek Mosher
HQ OPS Officer: Howie Crouch
Region: 4 State: AR
Unit: [2] [] []
RX Type: [1] B&W-L-LP,[2] CE
NRC Notified By: Derek Mosher
HQ OPS Officer: Howie Crouch
Notification Date: 10/04/2021
Notification Time: 19:59 [ET]
Event Date: 10/04/2021
Event Time: 14:33 [CDT]
Last Update Date: 10/04/2021
Notification Time: 19:59 [ET]
Event Date: 10/04/2021
Event Time: 14:33 [CDT]
Last Update Date: 10/04/2021
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):
DIXON, JOHN (R4)
DIXON, JOHN (R4)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
EN Revision Imported Date: 11/4/2021
EN Revision Text: DEGRADED CONDITION DISCOVERED ON REACTOR VESSEL HEAD PENETRATION
"At 1433 CDT, on October 4, 2021, Arkansas Nuclear One, Unit 2 (ANO-2) completed the analysis related to an indication revealed on head penetration 46 during Reactor Vessel Closure Head inspections. It was determined the indication is not acceptable under ASME code requirements. The indication displays characteristics consistent with primary water stress corrosion cracking. No leak path signal was identified during ultrasonic testing.
"The plant was in cold shutdown at 0 percent power and in Mode 6 for a refueling outage at the time of discovery. Repair actions will be completed prior to plant startup from the outage. This condition has no impact to the health and safety of the public.
"This report is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A) for degradation of a principal safety barrier. This is the only indication that is currently present, however, if additional indications are found, they will also be repaired prior to the plant startup.
"The NRC Senior Resident Inspector has been notified."
EN Revision Text: DEGRADED CONDITION DISCOVERED ON REACTOR VESSEL HEAD PENETRATION
"At 1433 CDT, on October 4, 2021, Arkansas Nuclear One, Unit 2 (ANO-2) completed the analysis related to an indication revealed on head penetration 46 during Reactor Vessel Closure Head inspections. It was determined the indication is not acceptable under ASME code requirements. The indication displays characteristics consistent with primary water stress corrosion cracking. No leak path signal was identified during ultrasonic testing.
"The plant was in cold shutdown at 0 percent power and in Mode 6 for a refueling outage at the time of discovery. Repair actions will be completed prior to plant startup from the outage. This condition has no impact to the health and safety of the public.
"This report is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A) for degradation of a principal safety barrier. This is the only indication that is currently present, however, if additional indications are found, they will also be repaired prior to the plant startup.
"The NRC Senior Resident Inspector has been notified."