Event Notification Report for October 12, 2023
U.S. Nuclear Regulatory Commission
Operations Center
EVENT REPORTS FOR
10/11/2023 - 10/12/2023
Agreement State
Event Number: 56776
Rep Org: Florida Bureau of Radiation Control
Licensee: James Hardie Building Products, Inc
Region: 1
City: Plant City State: FL
County:
License #: GO663
Agreement: Y
Docket:
NRC Notified By: John A. Williamson
HQ OPS Officer: Karen Cotton-Gross
Licensee: James Hardie Building Products, Inc
Region: 1
City: Plant City State: FL
County:
License #: GO663
Agreement: Y
Docket:
NRC Notified By: John A. Williamson
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 10/04/2023
Notification Time: 14:37 [ET]
Event Date: 10/04/2023
Event Time: 00:00 [EDT]
Last Update Date: 10/05/2023
Notification Time: 14:37 [ET]
Event Date: 10/04/2023
Event Time: 00:00 [EDT]
Last Update Date: 10/05/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Young, Matt (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Young, Matt (R1DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - LOSS OF CONTROL
The following information was provided by the Florida Bureau of Radiation Control [the Bureau] via email:
"On October 4, 2023, a gamma density gauge (DensityPro Gamma Density System, Model Number 5201A, 20 mCi Cs-137) was discovered in a rejected load of scrap metal at NuCor Steel. The Bureau inspector took custody of the gauge and transported it to Orlando. Upon further cleaning, the description plate revealed a serial and model number. The gauge was determined to belong to James Hardie Building Products (licensee). The licensee will be contacted and further corrective actions will be referred to the materials group at the Bureau."
Florida Incident number - FL23-152
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 provided by the Florida Bureau of Radiation Control [the Bureau] via email:
"On October 4, 2023, a gamma density gauge (DensityPro Gamma Density System, Model Number 5201A, 20 mCi Cs-137) was discovered in a rejected load of scrap metal at NuCor Steel. The Bureau inspector took custody of the gauge and transported it to Orlando. Upon further cleaning, the description plate revealed a serial and model number. The gauge was determined to belong to James Hardie Building Products (licensee). The licensee will be contacted and further corrective actions will be referred to the materials group at the Bureau."
Florida Incident number - FL23-152
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
Agreement State
Event Number: 56777
Rep Org: Colorado Dept of Health
Licensee: University of Colorado Hospital
Region: 4
City: Aurora State: CO
County:
License #: CO 828-01
Agreement: Y
Docket:
NRC Notified By: Meghan Cromie
HQ OPS Officer: Ian Howard
Licensee: University of Colorado Hospital
Region: 4
City: Aurora State: CO
County:
License #: CO 828-01
Agreement: Y
Docket:
NRC Notified By: Meghan Cromie
HQ OPS Officer: Ian Howard
Notification Date: 10/05/2023
Notification Time: 10:14 [ET]
Event Date: 10/04/2023
Event Time: 00:00 [MDT]
Last Update Date: 10/05/2023
Notification Time: 10:14 [ET]
Event Date: 10/04/2023
Event Time: 00:00 [MDT]
Last Update Date: 10/05/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Kellar, Ray (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Kellar, Ray (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - MEDICAL UNDERDOSE
The following information was provided by the Colorado Department of Public Health and Environment (the Agency) via email:
"On October 4, 2023, the radiation safety officer of the University of Colorado Hospital reported a medical event to the emergency response line. The medical event occurred during the administration of a Y-90 TheraSphere treatment that took place that day. The authorized user stated that high back pressure was observed during administration so only 71.2 percent of the prescribed dose was delivered to the treatment area. This is the third medical event (May 18, 2023 - CO230012 and May 24, 2023 - CO230014) with Y-90 TheraSpheres at this facility in the last six months. Different authorized users and IR [Interventional Radiology] technologists were present at each medical event. The Agency is currently waiting for additional information from the hospital and the Agency intends to follow up with an in-person investigation."
Event Report ID No.: CO2300034
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.
The following information was provided by the Colorado Department of Public Health and Environment (the Agency) via email:
"On October 4, 2023, the radiation safety officer of the University of Colorado Hospital reported a medical event to the emergency response line. The medical event occurred during the administration of a Y-90 TheraSphere treatment that took place that day. The authorized user stated that high back pressure was observed during administration so only 71.2 percent of the prescribed dose was delivered to the treatment area. This is the third medical event (May 18, 2023 - CO230012 and May 24, 2023 - CO230014) with Y-90 TheraSpheres at this facility in the last six months. Different authorized users and IR [Interventional Radiology] technologists were present at each medical event. The Agency is currently waiting for additional information from the hospital and the Agency intends to follow up with an in-person investigation."
Event Report ID No.: CO2300034
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.
Agreement State
Event Number: 56778
Rep Org: Texas Dept of State Health Services
Licensee: Covestro LLC
Region: 4
City: Baytown State: TX
County:
License #: 01577
Agreement: Y
Docket:
NRC Notified By: Karen Blanchard
HQ OPS Officer: Karen Cotton-Gross
Licensee: Covestro LLC
Region: 4
City: Baytown State: TX
County:
License #: 01577
Agreement: Y
Docket:
NRC Notified By: Karen Blanchard
HQ OPS Officer: Karen Cotton-Gross
Notification Date: 10/05/2023
Notification Time: 12:53 [ET]
Event Date: 09/26/2023
Event Time: 00:00 [CDT]
Last Update Date: 10/05/2023
Notification Time: 12:53 [ET]
Event Date: 09/26/2023
Event Time: 00:00 [CDT]
Last Update Date: 10/05/2023
Emergency Class: Non Emergency
10 CFR Section:
Agreement State
10 CFR Section:
Agreement State
Person (Organization):
Kellar, Ray (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
Kellar, Ray (R4DO)
NMSS_EVENTS_NOTIFICATION (EMAIL)
AGREEMENT STATE REPORT - FIXED GAUGE STUCK SHUTTER
The following information was provided by the Texas Department of State Health Services (the Agency) via email:
"On October 5, 2023, Covestro LLC (the licensee) reported to the Agency that on September 26, 2023, during routine 6-month checks, the shutter on one of its VEGA SHLG-1 fixed nuclear gauges, containing 1.5 curies cesium-137, was found stuck in the open position. Open is the normal operating position for this gauge. There were no [personnel] exposures and none are anticipated as the gauge is mounted on the side of a vessel and secured from access. The licensee has contacted the manufacturer and is trying to make arrangements for repair or replacement. An investigation into this event is ongoing. More information will be provided as it is obtained in accordance with SA-300."
Texas Incident Number: 10056
The following information was provided by the Texas Department of State Health Services (the Agency) via email:
"On October 5, 2023, Covestro LLC (the licensee) reported to the Agency that on September 26, 2023, during routine 6-month checks, the shutter on one of its VEGA SHLG-1 fixed nuclear gauges, containing 1.5 curies cesium-137, was found stuck in the open position. Open is the normal operating position for this gauge. There were no [personnel] exposures and none are anticipated as the gauge is mounted on the side of a vessel and secured from access. The licensee has contacted the manufacturer and is trying to make arrangements for repair or replacement. An investigation into this event is ongoing. More information will be provided as it is obtained in accordance with SA-300."
Texas Incident Number: 10056
Power Reactor
Event Number: 56785
Facility: Palo Verde
Region: 4 State: AZ
Unit: [1] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: Juan Melendez
HQ OPS Officer: Ernest West
Region: 4 State: AZ
Unit: [1] [] []
RX Type: [1] CE,[2] CE,[3] CE
NRC Notified By: Juan Melendez
HQ OPS Officer: Ernest West
Notification Date: 10/10/2023
Notification Time: 00:38 [ET]
Event Date: 10/09/2023
Event Time: 15:07 [MST]
Last Update Date: 10/10/2023
Notification Time: 00:38 [ET]
Event Date: 10/09/2023
Event Time: 15:07 [MST]
Last Update Date: 10/10/2023
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):
Kellar, Ray (R4DO)
Kellar, Ray (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | N | 0 | Cold Shutdown | 0 | Cold Shutdown |
REACTOR COOLANT SYSTEM PRESSURE BOUNDARY DEGRADED
The following information was provided by the licensee via email:
"On October 9, 2023, during the Palo Verde Nuclear Generating Station Unit 1 refueling outage, while performing a small nozzle inspection in support of boric acid walkdowns, boric acid leakage was found on the area of the weld of a pressurizer thermowell. At 1507 MST, non-destructive examination of the weld indicated leakage through the reactor coolant pressure boundary. The exam result constitutes welding or material defects in the primary coolant system that are unacceptable under ASME Section XI. 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 following information was provided by the licensee via email:
"On October 9, 2023, during the Palo Verde Nuclear Generating Station Unit 1 refueling outage, while performing a small nozzle inspection in support of boric acid walkdowns, boric acid leakage was found on the area of the weld of a pressurizer thermowell. At 1507 MST, non-destructive examination of the weld indicated leakage through the reactor coolant pressure boundary. The exam result constitutes welding or material defects in the primary coolant system that are unacceptable under ASME Section XI. 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."
Power Reactor
Event Number: 56786
Facility: Cooper
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: Randy Koube
HQ OPS Officer: Adam Koziol
Region: 4 State: NE
Unit: [1] [] []
RX Type: [1] GE-4
NRC Notified By: Randy Koube
HQ OPS Officer: Adam Koziol
Notification Date: 10/10/2023
Notification Time: 19:44 [ET]
Event Date: 10/10/2023
Event Time: 15:53 [CDT]
Last Update Date: 10/10/2023
Notification Time: 19:44 [ET]
Event Date: 10/10/2023
Event Time: 15:53 [CDT]
Last Update Date: 10/10/2023
Emergency Class: Non Emergency
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification
10 CFR Section:
50.72(b)(2)(xi) - Offsite Notification
Person (Organization):
Groom, Jeremy (R4DO)
Groom, Jeremy (R4DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
OFFSITE NOTIFICATION - SPURIOUS ALARM ACTUATION
The following information was provided by the licensee via fax:
"On October 10, 2023, at 1553 CDT, Cooper Nuclear Station (CNS) was notified of a spurious actuation of a single alert notification system siren in Nemaha, Nebraska. The CNS Emergency Alert System (EAS) was not activated. The actuation occurred during siren testing conducted at approximately 1545 CDT. No emergency conditions are present at Cooper Nuclear Station.
"A press release from Nebraska Public Power District is not planned at this time.
"This condition is reportable under 10CFR 50.72(b)(2)(xi) for any event or situation for which a news release is planned or notification to other government agencies has been or will be made which is related to heightened public or government concern.
"The NRC Senior Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Offsite notification was to local Nemaha County Emergency Management.
The following information was provided by the licensee via fax:
"On October 10, 2023, at 1553 CDT, Cooper Nuclear Station (CNS) was notified of a spurious actuation of a single alert notification system siren in Nemaha, Nebraska. The CNS Emergency Alert System (EAS) was not activated. The actuation occurred during siren testing conducted at approximately 1545 CDT. No emergency conditions are present at Cooper Nuclear Station.
"A press release from Nebraska Public Power District is not planned at this time.
"This condition is reportable under 10CFR 50.72(b)(2)(xi) for any event or situation for which a news release is planned or notification to other government agencies has been or will be made which is related to heightened public or government concern.
"The NRC Senior Resident Inspector has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
Offsite notification was to local Nemaha County Emergency Management.
Power Reactor
Event Number: 56787
Facility: North Anna
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: Bob Page
HQ OPS Officer: Ernest West
Region: 2 State: VA
Unit: [1] [] []
RX Type: [1] W-3-LP,[2] W-3-LP,[3] M-4-LP
NRC Notified By: Bob Page
HQ OPS Officer: Ernest West
Notification Date: 10/11/2023
Notification Time: 11:00 [ET]
Event Date: 06/18/2023
Event Time: 00:00 [EDT]
Last Update Date: 10/11/2023
Notification Time: 11:00 [ET]
Event Date: 06/18/2023
Event Time: 00:00 [EDT]
Last Update Date: 10/11/2023
Emergency Class: Non Emergency
10 CFR Section:
50.73(a)(1) - Invalid Specif System Actuation
10 CFR Section:
50.73(a)(1) - Invalid Specif System Actuation
Person (Organization):
Miller, Mark (R2DO)
Miller, Mark (R2DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | N | Y | 100 | Power Operation | 100 | Power Operation |
60 DAY NOTIFICATION FOR AN INVALID SPECIFIED SYSTEM ACTUATION
The following information was provided by the licensee via phone and email:
"This 60-day telephone notification is being made per the reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1) to describe an invalid specific system actuation of the North Anna Power Station Unit 1 Emergency Core Cooling System (ECCS).
"On 6/18/2023, a comparator card power supply associated with 1-CH-PC-1121A, charging pressure low-standby pump start signal comparator, failed and caused the `A' and `B' charging pumps to auto-start and the previously running `C' charging pump to trip and lock-out.
"This event is considered an invalid system actuation because the actuation was not initiated in response to actual plant conditions or parameters and was not a manual initiation. The ECCS pumps functioned as expected in response to the actuation. The `A' Charging pump was shut down in accordance with plant procedures following replacement of the comparator card. There was no impact on the health and safety of the public or plant personnel.
"The reportability requirement was determined beyond the 60-day notification requirement on 9/21/2023. The NRC Resident Inspector has been notified."
The following information was provided by the licensee via phone and email:
"This 60-day telephone notification is being made per the reporting requirements specified by 10 CFR 50.73(a)(2)(iv)(A) and 10 CFR 50.73(a)(1) to describe an invalid specific system actuation of the North Anna Power Station Unit 1 Emergency Core Cooling System (ECCS).
"On 6/18/2023, a comparator card power supply associated with 1-CH-PC-1121A, charging pressure low-standby pump start signal comparator, failed and caused the `A' and `B' charging pumps to auto-start and the previously running `C' charging pump to trip and lock-out.
"This event is considered an invalid system actuation because the actuation was not initiated in response to actual plant conditions or parameters and was not a manual initiation. The ECCS pumps functioned as expected in response to the actuation. The `A' Charging pump was shut down in accordance with plant procedures following replacement of the comparator card. There was no impact on the health and safety of the public or plant personnel.
"The reportability requirement was determined beyond the 60-day notification requirement on 9/21/2023. The NRC Resident Inspector has been notified."
Part 21
Event Number: 56789
Rep Org: DC COOK
Licensee: DC COOK
Region: 3
City: Bridgman State: MI
County:
License #:
Agreement: N
Docket:
NRC Notified By: Steve Mitchell
HQ OPS Officer: John Russell
Licensee: DC COOK
Region: 3
City: Bridgman State: MI
County:
License #:
Agreement: N
Docket:
NRC Notified By: Steve Mitchell
HQ OPS Officer: John Russell
Notification Date: 10/12/2023
Notification Time: 12:17 [ET]
Event Date: 08/11/2023
Event Time: 00:00 [EDT]
Last Update Date: 10/12/2023
Notification Time: 12:17 [ET]
Event Date: 08/11/2023
Event Time: 00:00 [EDT]
Last Update Date: 10/12/2023
Emergency Class: Non Emergency
10 CFR Section:
21.21(a)(2) - Interim Eval Of Deviation
10 CFR Section:
21.21(a)(2) - Interim Eval Of Deviation
Person (Organization):
Orth, Steve (R3DO)
Part 21/50.55 Reactors, - (EMAIL)
Orth, Steve (R3DO)
Part 21/50.55 Reactors, - (EMAIL)
PART 21 REPORT - EMERGENCY DIESEL GENERATOR DIGITAL REFERENCE UNIT PROBLEM
The following information was provided by the licensee via email:
"Donald C. Cook Nuclear Power Plant completed an internal Part 21 evaluation concerning an issue with an Emergency Diesel Generator (EDG) Digital Reference Unit (DRU) supplied by Engine Systems Incorporated (Appendix B Supplier for Woodward Governors). [On August 8, 2023,] a potential defect was identified [during a surveillance test] concerning a marginal solder joint on the DRU electronic circuit board that can result in a loss of continuity between the termination strip and the electronic board, causing a loss of setpoint output from the DRU to the Electronic Governor, and a subsequent loss of fuel to the EDG and inability to support any load. A formal failure analysis is ongoing at the time of this notification. A written notification will be provided within 30 days.
"Affected known plants include only Donald C. Cook Nuclear Power Plant Units 1 and 2 at the time of notification.
"The NRC Resident has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The EDG DRU was replaced after discovery of the potential defect and the EDG is currently operable.
The following information was provided by the licensee via email:
"Donald C. Cook Nuclear Power Plant completed an internal Part 21 evaluation concerning an issue with an Emergency Diesel Generator (EDG) Digital Reference Unit (DRU) supplied by Engine Systems Incorporated (Appendix B Supplier for Woodward Governors). [On August 8, 2023,] a potential defect was identified [during a surveillance test] concerning a marginal solder joint on the DRU electronic circuit board that can result in a loss of continuity between the termination strip and the electronic board, causing a loss of setpoint output from the DRU to the Electronic Governor, and a subsequent loss of fuel to the EDG and inability to support any load. A formal failure analysis is ongoing at the time of this notification. A written notification will be provided within 30 days.
"Affected known plants include only Donald C. Cook Nuclear Power Plant Units 1 and 2 at the time of notification.
"The NRC Resident has been notified."
The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:
The EDG DRU was replaced after discovery of the potential defect and the EDG is currently operable.
Power Reactor
Event Number: 56790
Facility: Ginna
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: Gabe Kiever
HQ OPS Officer: Lawrence Criscione
Region: 1 State: NY
Unit: [1] [] []
RX Type: [1] W-2-LP
NRC Notified By: Gabe Kiever
HQ OPS Officer: Lawrence Criscione
Notification Date: 10/12/2023
Notification Time: 23:31 [ET]
Event Date: 10/12/2023
Event Time: 21:27 [EDT]
Last Update Date: 10/12/2023
Notification Time: 23:31 [ET]
Event Date: 10/12/2023
Event Time: 21:27 [EDT]
Last Update Date: 10/12/2023
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):
Carfang, Erin (R1DO)
Carfang, Erin (R1DO)
| Unit | SCRAM Code | RX Crit | Initial PWR | Initial RX Mode | Current PWR | Current RX Mode |
|---|---|---|---|---|---|---|
| 1 | M/R | Y | 100 | Power Operation | 0 | Hot Standby |
MANUAL REACTOR TRIP
The following information was provided by the licensee via email:
"On 10/12/23 at 2127 EDT, with the Unit 1 in Mode 1 at 100% Power, operators identified degrading condenser vacuum and manually tripped the reactor. All control rods inserted as expected. The trip was not complex, and all systems responded normally post-trip. The cause of the degraded condenser vacuum was an unexpected closure of the condenser air ejector regulator. The cause of the air ejector regulator going closed is not fully understood and is being investigated.
"Following the SCRAM, Operators responded and stabilized the plant. Decay heat is being removed by the Main Steam System through the Atmospheric Relief Valves (ARVs) and Auxiliary Feed Water (AFW) systems. Due to the Reactor Protection System (RPS) actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B) and an eight-hour non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) for a valid specified system actuation.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."
The following information was provided by the licensee via email:
"On 10/12/23 at 2127 EDT, with the Unit 1 in Mode 1 at 100% Power, operators identified degrading condenser vacuum and manually tripped the reactor. All control rods inserted as expected. The trip was not complex, and all systems responded normally post-trip. The cause of the degraded condenser vacuum was an unexpected closure of the condenser air ejector regulator. The cause of the air ejector regulator going closed is not fully understood and is being investigated.
"Following the SCRAM, Operators responded and stabilized the plant. Decay heat is being removed by the Main Steam System through the Atmospheric Relief Valves (ARVs) and Auxiliary Feed Water (AFW) systems. Due to the Reactor Protection System (RPS) actuation while critical, this event is being reported as a four-hour, non-emergency notification per 10 CFR 50.72(b)(2)(iv)(B) and an eight-hour non-emergency notification per 10 CFR 50.72(b)(3)(iv)(A) for a valid specified system actuation.
"There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified."