ENS 48311
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ENS Event | |
---|---|
00:00 Sep 15, 2012 | |
Title | Degraded Condition Due to Indications on Reactor Vessel Head During Dye Penetrant Test |
Event Description | On September 14, 2012, during the Byron Station Unit 1 refueling outage, it was determined that the results of planned Liquid Penetrant (PT) examinations performed on two previous overlay repairs of the reactor vessel head do not meet applicable acceptance criteria. Both penetrations require 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 examinations were 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, which will include buff of the rejectable area and retest, and will be completed prior to returning the vessel head to service. If retest of the rejectable areas is unacceptable, then additional repairs will be required prior to returning the vessel head to service.
This condition is reportable pursuant to 10 CFR 50.72(b)(3)(ii)(A) since the as found indications did not meet applicable acceptance criteria referenced in ASME Code Case N-729-1 to remain in-service without repair. Any further examination failures and repairs will be updated under this ENS Notification. The NRC Resident Inspector has been notified. The original indications that led to the two overlay repairs were discovered during ultrasonic testing and were reported to the NRC and assigned EN#46686. |
Where | |
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Byron Illinois (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
LER: | 05000454/LER-2012-004 |
Time - Person (Reporting Time:+3.17 h0.132 days <br />0.0189 weeks <br />0.00434 months <br />) | |
Opened: | Harris Welt 03:10 Sep 15, 2012 |
NRC Officer: | Howie Crouch |
Last Updated: | Sep 15, 2012 |
48311 - 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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