Event Notification Report for October 17, 2022
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/16/2022 - 10/17/2022
Fuel Cycle Facility
Event Number: 56149
Facility: Nuclear Fuel Services Inc.
Region: 2 State: TN
Unit: [] [] []
RX Type: Uranium Fuel Fabrication
Comments: Heu Conversion & Scrap Recovery
Naval Reactor Fuel Cycle
Leu Scrap Recovery
NRC Notified By: Tom Holly
HQ OPS Officer: Adam Koziol
Region: 2 State: TN
Unit: [] [] []
RX Type: Uranium Fuel Fabrication
Comments: Heu Conversion & Scrap Recovery
Naval Reactor Fuel Cycle
Leu Scrap Recovery
NRC Notified By: Tom Holly
HQ OPS Officer: Adam Koziol
Notification Date: 10/06/2022
Notification Time: 13:06 [ET]
Event Date: 10/05/2022
Event Time: 15:00 [EDT]
Last Update Date: 10/14/2022
Notification Time: 13:06 [ET]
Event Date: 10/05/2022
Event Time: 15:00 [EDT]
Last Update Date: 10/14/2022
Emergency Class: Non Emergency
10 CFR Section:
PART 70 APP A (b)(2) - Loss Or Degraded Safety Items
10 CFR Section:
PART 70 APP A (b)(2) - Loss Or Degraded Safety Items
Person (Organization):
Miller, Mark (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Fuels Group, - (EMAIL)
Miller, Mark (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Fuels Group, - (EMAIL)
EN Revision Imported Date: 10/14/2022
EN Revision Text: DEGRADATION OF SAFETY ITEMS
The following information was provided by the licensee via e-mail:
"NFS [Nuclear Fuel Services, Inc.] evaluated a degraded Item Relied On For Safety (IROFS) in accordance with the documented Integrated Safety Analysis. During this review, the event was determined to be NON-REPORTABLE as additional controls were available and performance criteria maintained. However, during the detailed review of past performance, when the IROFS that was available in this scenario failed, the redundant IROFS would have been degraded.
"There were no actual radiological or other nuclear safety consequences to the public, workers, or the environment.
"The Senior Resident Inspector and Region II staff were notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The plant was shutdown pending repair or implementation of compensating measures.
EN Revision Text: DEGRADATION OF SAFETY ITEMS
The following information was provided by the licensee via e-mail:
"NFS [Nuclear Fuel Services, Inc.] evaluated a degraded Item Relied On For Safety (IROFS) in accordance with the documented Integrated Safety Analysis. During this review, the event was determined to be NON-REPORTABLE as additional controls were available and performance criteria maintained. However, during the detailed review of past performance, when the IROFS that was available in this scenario failed, the redundant IROFS would have been degraded.
"There were no actual radiological or other nuclear safety consequences to the public, workers, or the environment.
"The Senior Resident Inspector and Region II staff were notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The plant was shutdown pending repair or implementation of compensating measures.
Agreement State
Event Number: 56154
Rep Org: Virginia Rad Materials Program
Licensee: Quinn Consulting Services, Incorporated
Region: 1
City: Chantilly State: VA
County:
License #: 600-496-1
Agreement: Y
Docket:
NRC Notified By: Asfaw Fenta
HQ OPS Officer: Lloyd Desotell
Licensee: Quinn Consulting Services, Incorporated
Region: 1
City: Chantilly State: VA
County:
License #: 600-496-1
Agreement: Y
Docket:
NRC Notified By: Asfaw Fenta
HQ OPS Officer: Lloyd Desotell
Notification Date: 10/07/2022
Notification Time: 16:48 [ET]
Event Date: 10/07/2022
Event Time: 11:30 [EDT]
Last Update Date: 10/07/2022
Notification Time: 16:48 [ET]
Event Date: 10/07/2022
Event Time: 11:30 [EDT]
Last Update Date: 10/07/2022
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Ferdas, Marc (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Ferdas, Marc (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - DAMAGE TO PORTABLE DENSITY GAUGE
The following information was provided by the Virginia Department of Health via email:
"On October 7, 2022 at 1500 EDT, the Virginia Radioactive Materials Program (VRMP) received a report from a licensee's Radiation Safety Officer (RSO) via telephone that a portable nuclear moisture/density gauge was damaged by a dump truck at a jobsite located near the intersection of I-66 and I-28 in Chantilly, VA. The incident occurred on October 7, at about 1130 EDT. The report indicated that a Troxler density gauge (Model 3440, Serial # 77069, containing 8.0 millicuries of Cesium-137 and 40.0 millicuries of Am-241) was being used at the road construction site when a dump truck drove into and hit the gauge. During the incident, the gauge housing (the plastic cover and electronic system) was damaged, but the source appeared to remain intact within the housing. The site was cordoned off with a 15 foot radius. The licensee's survey of the gauge yielded readings of background at 15 feet and 0.5 mR/hr at about 3 feet from the gauge. The gauge was taken to the licensee's storage facility located at the project site. The RSO mentioned that wipe samples taken for leakage will be sent for analysis. The VRMP is working with the licensee to obtain additional information. This report will be updated once the licensee's investigation is complete, and the information is received. According to the RSO, no public exposure occurred."
Virginia Event Report ID No.: VA220003
The following information was provided by the Virginia Department of Health via email:
"On October 7, 2022 at 1500 EDT, the Virginia Radioactive Materials Program (VRMP) received a report from a licensee's Radiation Safety Officer (RSO) via telephone that a portable nuclear moisture/density gauge was damaged by a dump truck at a jobsite located near the intersection of I-66 and I-28 in Chantilly, VA. The incident occurred on October 7, at about 1130 EDT. The report indicated that a Troxler density gauge (Model 3440, Serial # 77069, containing 8.0 millicuries of Cesium-137 and 40.0 millicuries of Am-241) was being used at the road construction site when a dump truck drove into and hit the gauge. During the incident, the gauge housing (the plastic cover and electronic system) was damaged, but the source appeared to remain intact within the housing. The site was cordoned off with a 15 foot radius. The licensee's survey of the gauge yielded readings of background at 15 feet and 0.5 mR/hr at about 3 feet from the gauge. The gauge was taken to the licensee's storage facility located at the project site. The RSO mentioned that wipe samples taken for leakage will be sent for analysis. The VRMP is working with the licensee to obtain additional information. This report will be updated once the licensee's investigation is complete, and the information is received. According to the RSO, no public exposure occurred."
Virginia Event Report ID No.: VA220003
Agreement State
Event Number: 56155
Rep Org: SC Dept of Health & Env Control
Licensee: Summit Engineering
Region: 1
City: State: SC
County:
License #: 777
Agreement: Y
Docket:
NRC Notified By: Leeland Cave
HQ OPS Officer: Lloyd Desotell
Licensee: Summit Engineering
Region: 1
City: State: SC
County:
License #: 777
Agreement: Y
Docket:
NRC Notified By: Leeland Cave
HQ OPS Officer: Lloyd Desotell
Notification Date: 10/10/2022
Notification Time: 15:52 [ET]
Event Date: 10/10/2022
Event Time: 12:30 [EDT]
Last Update Date: 10/10/2022
Notification Time: 15:52 [ET]
Event Date: 10/10/2022
Event Time: 12:30 [EDT]
Last Update Date: 10/10/2022
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Ferdas, Marc (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Ferdas, Marc (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - DAMAGED GAUGE
The following is a summary of information received from the South Carolina Department of Health and Environmental Control [the Department] via email:
At 1420 EDT on October 10, 2022, the Department received a call from Summit Engineering (the licensee) to report that at approximately 1230 EDT, a double pin road roller used for paving hit a Troxler 3440 gauge (SN #34989), cracking its plastic outer covering. The licensee's radiation safety officer arrived onsite and arranged to have the gauge transported back to the licensee's office. The Department traveled to the licensee's office to survey the damaged gauge. The Department found the gauge's source in the shielded position and surveys read no higher than 8 mR/hr on the surface of the gauge and no higher than 0.06 mR/hr at a foot away. The licensee stated that the gauge would be sent back to the manufacture for repair.
The following is a summary of information received from the South Carolina Department of Health and Environmental Control [the Department] via email:
At 1420 EDT on October 10, 2022, the Department received a call from Summit Engineering (the licensee) to report that at approximately 1230 EDT, a double pin road roller used for paving hit a Troxler 3440 gauge (SN #34989), cracking its plastic outer covering. The licensee's radiation safety officer arrived onsite and arranged to have the gauge transported back to the licensee's office. The Department traveled to the licensee's office to survey the damaged gauge. The Department found the gauge's source in the shielded position and surveys read no higher than 8 mR/hr on the surface of the gauge and no higher than 0.06 mR/hr at a foot away. The licensee stated that the gauge would be sent back to the manufacture for repair.
Fuel Cycle Facility
Event Number: 56159
Facility: Global Nuclear Fuel - Americas
Region: 2 State: NC
Unit: [] [] []
RX Type: Uranium Fuel Fabrication
Comments: Leu Conversion (Uf6 To Uo2)
Leu Fabrication
Lwr Commerical Fuel
NRC Notified By: Phillip Ollis
HQ OPS Officer: Ian Howard
Region: 2 State: NC
Unit: [] [] []
RX Type: Uranium Fuel Fabrication
Comments: Leu Conversion (Uf6 To Uo2)
Leu Fabrication
Lwr Commerical Fuel
NRC Notified By: Phillip Ollis
HQ OPS Officer: Ian Howard
Notification Date: 10/13/2022
Notification Time: 10:39 [ET]
Event Date: 10/12/2022
Event Time: 13:11 [EDT]
Last Update Date: 10/13/2022
Notification Time: 10:39 [ET]
Event Date: 10/12/2022
Event Time: 13:11 [EDT]
Last Update Date: 10/13/2022
Emergency Class: Non Emergency
10 CFR Section:
PART 70 APP A (c) - Offsite Notification/News Rel
10 CFR Section:
PART 70 APP A (c) - Offsite Notification/News Rel
Person (Organization):
Miller, Mark (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Miller, Mark (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
OFFSITE NOTIFICATION
The following information was provided by the licensee via email:
"At approximately 1311 (EDT) on October 12th, 2022, the New Hanover County Deputy Fire Marshall was notified per State code requirements that the fire suppression system encompassing the Fuel Manufacturing Operation (FMO) was impaired. During a flow test, the backup diesel fire pump experienced an overheating condition. As a result, the diesel fire pump was placed in the manual 'Off' position. The electric fire pump remained fully operational and available to perform its safety function. The diesel pump was repaired and returned to operation at approximately 1000 (EDT) on Thursday, October 13th. The New Hanover County Deputy Fire Marshall was notified of restoration at 1020 (EDT). Because the New Hanover County Deputy Fire Marshall was notified, a concurrent notification to the NRC Operations Center is being made per 10 CFR 70, Appendix A(c)."
The licensee will notify the State and NRC Region II.
The following information was provided by the licensee via email:
"At approximately 1311 (EDT) on October 12th, 2022, the New Hanover County Deputy Fire Marshall was notified per State code requirements that the fire suppression system encompassing the Fuel Manufacturing Operation (FMO) was impaired. During a flow test, the backup diesel fire pump experienced an overheating condition. As a result, the diesel fire pump was placed in the manual 'Off' position. The electric fire pump remained fully operational and available to perform its safety function. The diesel pump was repaired and returned to operation at approximately 1000 (EDT) on Thursday, October 13th. The New Hanover County Deputy Fire Marshall was notified of restoration at 1020 (EDT). Because the New Hanover County Deputy Fire Marshall was notified, a concurrent notification to the NRC Operations Center is being made per 10 CFR 70, Appendix A(c)."
The licensee will notify the State and NRC Region II.
Fuel Cycle Facility
Event Number: 56161
Facility: Honeywell International, Inc.
Region: 2 State: IL
Unit: [] [] []
RX Type: Uranium Hexafluoride Production
NRC Notified By: Sean Patterson
HQ OPS Officer: Kerby Scales
Region: 2 State: IL
Unit: [] [] []
RX Type: Uranium Hexafluoride Production
NRC Notified By: Sean Patterson
HQ OPS Officer: Kerby Scales
Notification Date: 10/13/2022
Notification Time: 19:12 [ET]
Event Date: 10/13/2022
Event Time: 17:25 [CDT]
Last Update Date: 10/13/2022
Notification Time: 19:12 [ET]
Event Date: 10/13/2022
Event Time: 17:25 [CDT]
Last Update Date: 10/13/2022
Emergency Class: Alert
10 CFR Section:
40.35(f) - Emergency Declared
10 CFR Section:
40.35(f) - Emergency Declared
Person (Organization):
Miller, Mark (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Lubinksi, John (NMSS)
Dudes, Laura (R2RA)
Whited, Jeffrey (IR)
Miller, Mark (R2DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Lubinksi, John (NMSS)
Dudes, Laura (R2RA)
Whited, Jeffrey (IR)
ALERT DECLARED DUE TO A FIRE IN LABORATORY BUILDING UNDER RENOVATION
On 10/13/2022 at 1725 CDT, the licensee declared an Alert due to a fire in a laboratory building under renovation. The licensee contacted local Fire and Emergency Medical Service who responded and extinguished the fire. There was no offsite release of radiological material.
The licensee notified local authorities and the Illinois Emergency Management Agency of the event.
* * * UPDATE ON 10/13/22 AT 1851 CDT FROM SEAN PATTERSON TO KERBY SCALES * * *
At 1851 CDT, the licensee terminated the Alert and reported the fire was out.
Notified DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, CISA Central Watch Officer, EPA EOC, R2DO (Miller), IRMOC (Whited), Director DFM (Helton).
On 10/13/2022 at 1725 CDT, the licensee declared an Alert due to a fire in a laboratory building under renovation. The licensee contacted local Fire and Emergency Medical Service who responded and extinguished the fire. There was no offsite release of radiological material.
The licensee notified local authorities and the Illinois Emergency Management Agency of the event.
* * * UPDATE ON 10/13/22 AT 1851 CDT FROM SEAN PATTERSON TO KERBY SCALES * * *
At 1851 CDT, the licensee terminated the Alert and reported the fire was out.
Notified DHS SWO, FEMA Ops Center, USDA Ops Center, HHS Ops Center, DOE Ops Center, CISA Central Watch Officer, EPA EOC, R2DO (Miller), IRMOC (Whited), Director DFM (Helton).
Power Reactor
Event Number: 56163
Facility: Limerick
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: William Balafka
HQ OPS Officer: Karen Cotton-Gross
Region: 1 State: PA
Unit: [1] [] []
RX Type: [1] GE-4,[2] GE-4
NRC Notified By: William Balafka
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 10/14/2022
Notification Time: 18:03 [ET]
Event Date: 10/14/2022
Event Time: 10:07 [EDT]
Last Update Date: 10/14/2022
Notification Time: 18:03 [ET]
Event Date: 10/14/2022
Event Time: 10:07 [EDT]
Last Update Date: 10/14/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Schroeder, Dan (R1DO)
Schroeder, Dan (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
HIGH PRESSURE COOLANT INJECTION INOPERABLE
The following information was provided by the licensee via email:
"Unit 1 High Pressure Coolant Injection (HPCI) was declared inoperable due to an inadvertent division 2 isolation signal and subsequent valve closure.
"This report is being made pursuant to 10 CFR 50.72(b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfillment of the safety function of a system that is needed to mitigate the consequences of an accident."
The NRC Resident will be notified.
The following information was provided by the licensee via email:
"Unit 1 High Pressure Coolant Injection (HPCI) was declared inoperable due to an inadvertent division 2 isolation signal and subsequent valve closure.
"This report is being made pursuant to 10 CFR 50.72(b)(3)(v)(D) as a condition that at the time of discovery could have prevented the fulfillment of the safety function of a system that is needed to mitigate the consequences of an accident."
The NRC Resident will be notified.
Power Reactor
Event Number: 56165
Facility: Catawba
Region: 2 State: SC
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Will Fowler
HQ OPS Officer: Karen Cotton-Gross
Region: 2 State: SC
Unit: [2] [] []
RX Type: [1] W-4-LP,[2] W-4-LP
NRC Notified By: Will Fowler
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 10/15/2022
Notification Time: 15:46 [ET]
Event Date: 10/15/2022
Event Time: 11:59 [EDT]
Last Update Date: 10/15/2022
Notification Time: 15:46 [ET]
Event Date: 10/15/2022
Event Time: 11:59 [EDT]
Last Update Date: 10/15/2022
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):
Miller, Mark (R2DO)
Miller, Mark (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 2 | N | N | 0 | Refueling | 0 | Refueling |
REACTOR VESSEL HEAD PENETRATION REPAIR DEGRADED
The following information was provided by the licensee via email:
"On 10/15/2022 at 1159 [EDT], during the Catawba Nuclear Station Unit 2 refueling outage, it was determined that the results of a planned surface examination Liquid Penetrant test (PT) performed on a previous overlay repair on nozzle number 74 of the reactor vessel closure head (RVCH) did not meet applicable acceptance standards. The examination was being performed to meet the requirements of Relief Request RA-21-0144, 'Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant'. The penetration required repairs for the discovered indications. The repairs have been completed in accordance with the ASME Code of Record prior to returning the vessel head to service. This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
"The original indication that led to the overlay repair was discovered in April 2021, during ultrasonic testing and reported to the NRC and assigned EN55201."
The following information was provided by the licensee via email:
"On 10/15/2022 at 1159 [EDT], during the Catawba Nuclear Station Unit 2 refueling outage, it was determined that the results of a planned surface examination Liquid Penetrant test (PT) performed on a previous overlay repair on nozzle number 74 of the reactor vessel closure head (RVCH) did not meet applicable acceptance standards. The examination was being performed to meet the requirements of Relief Request RA-21-0144, 'Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant'. The penetration required repairs for the discovered indications. The repairs have been completed in accordance with the ASME Code of Record prior to returning the vessel head to service. This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A).
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.
"The original indication that led to the overlay repair was discovered in April 2021, during ultrasonic testing and reported to the NRC and assigned EN55201."
Power Reactor
Event Number: 56058
Facility: Grand Gulf
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Paul Lyne
HQ OPS Officer: Donald Norwood
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Paul Lyne
HQ OPS Officer: Donald Norwood
Notification Date: 08/19/2022
Notification Time: 20:46 [ET]
Event Date: 08/19/2022
Event Time: 12:15 [CDT]
Last Update Date: 10/17/2022
Notification Time: 20:46 [ET]
Event Date: 08/19/2022
Event Time: 12:15 [CDT]
Last Update Date: 10/17/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
10 CFR Section:
50.72(b)(3)(v)(D) - Accident Mitigation
Person (Organization):
Werner, Greg (R4DO)
Werner, Greg (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 63 | Power Operation |
EN Revision Imported Date: 10/17/2022
EN Revision Text: FOUR AUTOMATIC DEPRESSURIZATION SYSTEM VALVES INOPERABLE
The following information was provided by the licensee via email:
"At 1215 CDT on 8/19/2022, with Grand Gulf Nuclear Station in Mode 1 and at 100 percent power, four Automatic Depressurization System (ADS) valves were rendered inoperable due to a loss of system pressure. The station entered Technical Specification 3.5.1 Condition G.
"This event is being reported under 10 CFR 50.72(b)(3)(v)(D) as an event or condition that could have prevented the fulfillment of a safety function.
"There were no other systems affected as a result of this condition.
"The NRC Senior Resident Inspector was notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: Plans are to remain in Mode 1 until corrected or until driven by the Technical Specifications to shut down (12-hour LCO from 1215 CDT on 8/19/2022).
* * * RETRACTION ON 10/14/22 AT 1311 EDT FROM JEFF HARDY TO KAREN COTTON * * *
"Grand Gulf Nuclear Station (GGNS) is performing this notification to retract event EN 56058 that was reported on August 19, 2022. Previously, GGNS notified the NRC that four Automatic Depressurization System (ADS) valves were inoperable due to a loss of system pressure.
"Based upon further investigation, the condition reported in EN 56058 was found to affect only a single ADS valve. As a result, it was determined that an event or condition that could have prevented the fulfillment of a safety function did not exist at GGNS. Sufficient redundancy existed to perform the safety function.
"The NRC Resident Inspector has been notified of the retraction."
R4DO (Kellar) was notified.
EN Revision Text: FOUR AUTOMATIC DEPRESSURIZATION SYSTEM VALVES INOPERABLE
The following information was provided by the licensee via email:
"At 1215 CDT on 8/19/2022, with Grand Gulf Nuclear Station in Mode 1 and at 100 percent power, four Automatic Depressurization System (ADS) valves were rendered inoperable due to a loss of system pressure. The station entered Technical Specification 3.5.1 Condition G.
"This event is being reported under 10 CFR 50.72(b)(3)(v)(D) as an event or condition that could have prevented the fulfillment of a safety function.
"There were no other systems affected as a result of this condition.
"The NRC Senior Resident Inspector was notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: Plans are to remain in Mode 1 until corrected or until driven by the Technical Specifications to shut down (12-hour LCO from 1215 CDT on 8/19/2022).
* * * RETRACTION ON 10/14/22 AT 1311 EDT FROM JEFF HARDY TO KAREN COTTON * * *
"Grand Gulf Nuclear Station (GGNS) is performing this notification to retract event EN 56058 that was reported on August 19, 2022. Previously, GGNS notified the NRC that four Automatic Depressurization System (ADS) valves were inoperable due to a loss of system pressure.
"Based upon further investigation, the condition reported in EN 56058 was found to affect only a single ADS valve. As a result, it was determined that an event or condition that could have prevented the fulfillment of a safety function did not exist at GGNS. Sufficient redundancy existed to perform the safety function.
"The NRC Resident Inspector has been notified of the retraction."
R4DO (Kellar) was notified.
Power Reactor
Event Number: 56059
Facility: Grand Gulf
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Paul Lyne
HQ OPS Officer: Bethany Cecere
Region: 4 State: MS
Unit: [1] [] []
RX Type: [1] GE-6
NRC Notified By: Paul Lyne
HQ OPS Officer: Bethany Cecere
Notification Date: 08/20/2022
Notification Time: 02:11 [ET]
Event Date: 08/19/2022
Event Time: 23:42 [CDT]
Last Update Date: 10/17/2022
Notification Time: 02:11 [ET]
Event Date: 08/19/2022
Event Time: 23:42 [CDT]
Last Update Date: 10/17/2022
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(i) - Plant S/D Reqd By Ts
10 CFR Section:
50.72(b)(2)(i) - Plant S/D Reqd By Ts
Person (Organization):
Werner, Greg (R4DO)
Werner, Greg (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 40 | Power Operation | 0 | Hot Standby |
EN Revision Imported Date: 10/17/2022
EN Revision Text: TECHNICAL SPECIFICATION REQUIRED SHUTDOWN
The following information was provided by the licensee via fax or email:
"At 2342 CDT on August 19, 2022, with Grand Gulf Nuclear Station in Mode 1 and at 40 percent power, the station initiated a normal shutdown to comply with its Technical Specifications (TS). The station entered Mode 3 at 0000 CDT August 20, 2022 to comply with (LCO) 3.5.1 Condition G Action G.1 due to the condition reported to NRC previously (EN 56058).
"This event is being reported under 10 CFR 50.72(b)(2)(i) as a shutdown required by the plant's technical specifications.
"The NRC Senior Resident Inspector was notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The plant is now in a 36-hour LCO to be in Mode 4 due to Low Low Set Valves inoperability per TS 3.6.1.6.
* * * RETRACTION ON 10/14/2022 AT 1311 FROM JEFF HARDY TO LAUREN BRYSON * * *
"Grand Gulf Nuclear Station (GGNS) is performing this notification to retract event EN 56059 that was reported on August 20, 2022. Previously, GGNS notified the NRC that it had initiated a shutdown required by Technical Specifications to comply with Limiting Condition of Operation (LCO) 3.5.1 Condition G.1 due to the inoperability of four Automatic Depressurization System (ADS) valves.
"Following the shutdown, GGNS completed walkdowns and determined that the condition affected only one ADS valve. As a result, the shutdown to satisfy the required actions of TS LCO 3.5.1 Condition G.1 was not required.
"The NRC Resident Inspector has been notified of the retraction."
R4DO (Kellar) was notified.
EN Revision Text: TECHNICAL SPECIFICATION REQUIRED SHUTDOWN
The following information was provided by the licensee via fax or email:
"At 2342 CDT on August 19, 2022, with Grand Gulf Nuclear Station in Mode 1 and at 40 percent power, the station initiated a normal shutdown to comply with its Technical Specifications (TS). The station entered Mode 3 at 0000 CDT August 20, 2022 to comply with (LCO) 3.5.1 Condition G Action G.1 due to the condition reported to NRC previously (EN 56058).
"This event is being reported under 10 CFR 50.72(b)(2)(i) as a shutdown required by the plant's technical specifications.
"The NRC Senior Resident Inspector was notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The plant is now in a 36-hour LCO to be in Mode 4 due to Low Low Set Valves inoperability per TS 3.6.1.6.
* * * RETRACTION ON 10/14/2022 AT 1311 FROM JEFF HARDY TO LAUREN BRYSON * * *
"Grand Gulf Nuclear Station (GGNS) is performing this notification to retract event EN 56059 that was reported on August 20, 2022. Previously, GGNS notified the NRC that it had initiated a shutdown required by Technical Specifications to comply with Limiting Condition of Operation (LCO) 3.5.1 Condition G.1 due to the inoperability of four Automatic Depressurization System (ADS) valves.
"Following the shutdown, GGNS completed walkdowns and determined that the condition affected only one ADS valve. As a result, the shutdown to satisfy the required actions of TS LCO 3.5.1 Condition G.1 was not required.
"The NRC Resident Inspector has been notified of the retraction."
R4DO (Kellar) was notified.
Agreement State
Event Number: 56156
Rep Org: Minnesota Department of Health
Licensee: Mayo Clinic
Region: 3
City: Rochester State: MN
County:
License #: 1047
Agreement: Y
Docket:
NRC Notified By: Tyler Kruse
HQ OPS Officer: Brian Lin
Licensee: Mayo Clinic
Region: 3
City: Rochester State: MN
County:
License #: 1047
Agreement: Y
Docket:
NRC Notified By: Tyler Kruse
HQ OPS Officer: Brian Lin
Notification Date: 10/10/2022
Notification Time: 14:18 [ET]
Event Date: 09/28/2022
Event Time: 00:00 [CDT]
Last Update Date: 10/19/2022
Notification Time: 14:18 [ET]
Event Date: 09/28/2022
Event Time: 00:00 [CDT]
Last Update Date: 10/19/2022
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Betancourt-Roldan, Diana (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Betancourt-Roldan, Diana (R3DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
EN Revision Imported Date: 10/19/2022
EN Revision Text: AGREEMENT STATE REPORT - MEDICAL MISADMINSTRATION
The following summary was received from the Minnesota Department of Health via email:
A patient undergoing Lu-177 therapy was administered 110 mCi vice the prescribed 200 mCi. An investigation is in progress by the Minnesota Department of Health.
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
Minnesota Event ID: MN220005
* * * UPDATE FROM TYLER KRUSE TO DONALD NORWOOD AT 0907 EDT ON 10/17/2022 * * *
The following information was received via email:
"The event date for this event was 09/28/2022. This event was discovered while investigating the event that occurred on 09/27/2022." [That event is recorded as EN56137.]
Notified R3DO (Kunowski) and NMSS Events Notification email group.
EN Revision Text: AGREEMENT STATE REPORT - MEDICAL MISADMINSTRATION
The following summary was received from the Minnesota Department of Health via email:
A patient undergoing Lu-177 therapy was administered 110 mCi vice the prescribed 200 mCi. An investigation is in progress by the Minnesota Department of Health.
A Medical Event may indicate potential problems in a medical facility's use of radioactive materials. It does not necessarily result in harm to the patient.
Minnesota Event ID: MN220005
* * * UPDATE FROM TYLER KRUSE TO DONALD NORWOOD AT 0907 EDT ON 10/17/2022 * * *
The following information was received via email:
"The event date for this event was 09/28/2022. This event was discovered while investigating the event that occurred on 09/27/2022." [That event is recorded as EN56137.]
Notified R3DO (Kunowski) and NMSS Events Notification email group.