ENS 46686
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ENS Event | |
|---|---|
13:00 Mar 19, 2011 | |
| Title | Ultrasonic Examination Results in Indications on Two Reactor Head Penetrations |
| Event Description | On March 19, 2011, during the Byron Station Unit 1 refueling outage, it was determined that the results of planned ultrasonic (UT) examinations performed on two penetrations of the reactor vessel head would not meet the applicable acceptance criteria. Both require repair prior to returning the vessel head to service. These indications are not in the reactor coolant pressure boundary; however they are very near the toe of the J-groove weld. The examinations were being performed to meet the requirements of 10CFR50.55a(g)(6)(ii)(D) and ASME Code Case N-729-1, to ensure the structural integrity of the reactor vessel head pressure boundary. The UT examinations continue for the remaining head penetrations. All of the penetrations will be examined during the current refueling outage. Repairs are currently being planned and will be competed prior to startup.
This is reportable pursuant to 10CFR50.72(b)(3)(ii)(A) since the as found indications did not meet the applicable acceptance criteria referenced in ASME Code Case N-729-1 to remain in-service without repair. The NRC Resident Inspector has been notified.
Ultrasonic examination [made on March 19, 2011] resulted in indications on two reactor head penetrations. As mentioned in Event Notification 46686, reactor vessel head penetrations [In-service inspection] ISI examinations were still in progress. On Wednesday, March 30, 2011, two additional Unit 1 reactor head penetrations were found to contain indications that will require repair prior to returning the reactor head to service. The indications on these two penetrations are within the reactor vessel head pressure boundary. The NRC Resident Inspector has been notified by the licensee. Notified the R3DO (Peterson). |
| Where | |
|---|---|
Byron  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+3.35 h0.14 days <br />0.0199 weeks <br />0.00459 months <br />) | |
| Opened: | Mike Lindemann 16:21 Mar 19, 2011 |
| NRC Officer: | Donald Norwood |
| Last Updated: | Mar 30, 2011 |
| 46686 - NRC Website
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WEEKMONTHYEARENS 573212024-09-13T13:23:00013 September 2024 13:23:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Reactor Vessel Closure Head Penetration ENS 558572022-04-23T13:54:00023 April 2022 13:54:00 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 2024-09-13T13:23:00 | |
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