ENS Event | |
|---|---|
13:54 Apr 23, 2022 | |
| Title | Ultrasonic Examination Results - Reactor Vessel Head Penetration |
| Event Description | The following information was provided by the licensee via email:
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). There was no impact on the health and safety of the public or plant personnel. The NRC Resident Inspector has been notified. The following additional information was obtained from the licensee in accordance with Headquarters Operations Officers Report Guidance: The repair is scheduled during the refueling outage.
The following information was provided by the licensee via telephone and email: 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. The licensee notified the NRC Resident Inspector. Notified R3DO (Ziolkowski). |
| Where | |
|---|---|
Byron  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+2.55 h0.106 days <br />0.0152 weeks <br />0.00349 months <br />) | |
| Opened: | Bryan Lykkebak 16:27 Apr 23, 2022 |
| NRC Officer: | Kerby Scales |
| Last Updated: | Apr 29, 2022 |
| 55857 - NRC Website | |
WEEKMONTHYEARENS 558572022-04-23T13:54:00023 April 2022 13:54:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Ultrasonic Examination Results - Reactor Vessel Head Penetration ENS 525922017-03-05T14:00:0005 March 2017 14:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Planned Ultrasonic Test on Previously Repaired Reactor Vessel Penetration Did Not Meet Acceptance Criteria ENS 525912017-03-03T23:05:0003 March 2017 23:05:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Previous Overlay Repair Did Not Meet Acceptance Criteria ENS 514102015-09-19T01:00:00019 September 2015 01:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Vessel Head Penetration Repair Did Not Meet Acceptance Criteria ENS 505172014-10-08T00:00:0008 October 2014 00:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Ultrasonic Testing Reveal Degraded Condition on One Control Rod Drive Mechanism Penetration ENS 483112012-09-15T00:00:00015 September 2012 00:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Indications on Reactor Vessel Head During Dye Penetrant Test ENS 466862011-03-19T13:00:00019 March 2011 13:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Ultrasonic Examination Results in Indications on Two Reactor Head Penetrations 2022-04-23T13:54:00 | |