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The following information was provided by … The following information was provided by the licensee via email:</br>At 0854 (CDT) on April 23, 2022, while performing volumetric inspections required by ASME Code Case N-729-6, a rejectable indication on Reactor Vessel Head Penetration 75 Core Exit Thermocouple (CETC) was identified. The indication is located inboard of the J-groove weld and is OD-initiated (outer diameter - initiated). This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A). </br>There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.</br>The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:</br>The repair is scheduled during the refueling outage.</br>* * * UPDATE ON 04/29/22 AT 1112 EDT FROM BRYAN LYKKEBAK TO OSSY FONT * * *</br>The following information was provided by the licensee via telephone and email:</br>The rejectable indication on Reactor Vessel Head Penetration 75 Core Exit Thermocouple (CETC) initiated on the outside diameter (OD) of the nozzle in an area that was not surface stress mitigated (peened). The indication was found to be acceptable for continued operation under CFR and ASME requirements and will not be repaired during this outage.</br>The licensee notified the NRC Resident Inspector.</br>Notified R3DO (Ziolkowski).ent Inspector.
Notified R3DO (Ziolkowski). +
13:54:00, 23 April 2022 +
55,857 +
16:27:00, 23 April 2022 +
13:54:00, 23 April 2022 +
The following information was provided by … The following information was provided by the licensee via email:</br>At 0854 (CDT) on April 23, 2022, while performing volumetric inspections required by ASME Code Case N-729-6, a rejectable indication on Reactor Vessel Head Penetration 75 Core Exit Thermocouple (CETC) was identified. The indication is located inboard of the J-groove weld and is OD-initiated (outer diameter - initiated). This event is being reported as an eight-hour, non-emergency notification per 10 CFR 50.72(b)(3)(ii)(A). </br>There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified.</br>The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance:</br>The repair is scheduled during the refueling outage.</br>* * * UPDATE ON 04/29/22 AT 1112 EDT FROM BRYAN LYKKEBAK TO OSSY FONT * * *</br>The following information was provided by the licensee via telephone and email:</br>The rejectable indication on Reactor Vessel Head Penetration 75 Core Exit Thermocouple (CETC) initiated on the outside diameter (OD) of the nozzle in an area that was not surface stress mitigated (peened). The indication was found to be acceptable for continued operation under CFR and ASME requirements and will not be repaired during this outage.</br>The licensee notified the NRC Resident Inspector.</br>Notified R3DO (Ziolkowski).ent Inspector.
Notified R3DO (Ziolkowski). +
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05000455/LER-2022-001-01, Volumetric Examinations of Reactor Pressure Vessel Head Core Exit Thermocouple Penetration P-75 Identified an Indication Attributed to Primary Water Stress Corrosion Cracking +, 05000455/LER-2022-001, Volumetric Examinations of Reactor Pressure Vessel Head Core Exit Thermocouple Penetration P-75 Identified an Indication Attributed to Primary Water Stress Corrosion Cracking + and Volumetric Examinations of Reactor Pressure Vessel Head Core Exit Thermocouple Penetration P-75 Identified an Indication Attributed to Primary Water Stress Corrosion Cracking +
00:00:00, 29 April 2022 +
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