ENS 51410
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ENS Event | |
|---|---|
01:00 Sep 19, 2015 | |
| Title | Reactor Vessel Head Penetration Repair Did Not Meet Acceptance Criteria |
| Event Description | On 9/18/2015 at 20:00 [CDT], during the Byron Station Unit 1 refueling outage, it was determined that the results of a planned Liquid Penetrant (PT) examination performed on a previous overlay repair of the reactor vessel head did not meet applicable acceptance criteria. The penetration requires repairs prior to returning the vessel head to service. These indications are not in the reactor coolant pressure boundary; however they are very near the previously repaired J-groove weld. The examination was being performed to meet the requirements of 10 CFR 50.55a(g)(6)(ii)(D) and ASME Code Case N-729-1, to ensure the structural integrity of the reactor vessel head pressure boundary. No ultrasonic indications have been identified at this time. Repairs are currently being planned in accordance with the ASME Code of Record. The repairs will be completed prior to returning the vessel head to service.
This event is being reported under 10 CFR 50.72(b)(3)(ii)(A) for 'Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.' The licensee has notified the NRC Resident Inspector. Per regulatory commitment, Exelon Generation Company, LLC (EGC) is notifying NRC staff of the Division of Component Integrity or its successor, of changes in indication(s) or findings of new indication(s) in the penetration nozzle or J-groove weld beneath a seal weld repair, or new linear indications in the seal weld repair, prior to commencing repair activities. The original indications that led to the overlay repairs were discovered during ultrasonic testing and were reported to the NRC and assigned EN46686 and EN48311. |
| Where | |
|---|---|
Byron  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| LER: | 05000454/LER-2015-005 |
| Time - Person (Reporting Time:+-0.82 h-0.0342 days <br />-0.00488 weeks <br />-0.00112 months <br />) | |
| Opened: | Shane Harvey 00:11 Sep 19, 2015 |
| NRC Officer: | Jeff Herrera |
| Last Updated: | Sep 19, 2015 |
| 51410 - 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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