ENS 49343
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ENS Event | |
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07:00 Sep 14, 2013 | |
Title | Liquid Penetration Examination Results in Indication on Reactor Vessel Head Penetration |
Event Description | On September 14, 2013, during the A1R17 Braidwood Station Unit 1 refueling outage, an inservice Liquid Penetration examination was performed on the previously repaired Penetration 69. This repair was performed during A1R16. The PT [Penetrant Testing] examination revealed 22 recordable indication and 5 non-relevant indications. Rounded indications that exceed 3/16" are rejectable. All 22 indications are rounded and 13 of these indications exceed the 3/16" criteria.
This is reportable pursuant to 10 CFR 50.72(b)(3)(ii)(A) since the as found indication did not meet the applicable acceptance criteria referenced in ASME Code Case N-729-1 to remain in-service without repair. NRC Resident Inspector has been informed. |
Where | |
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Braidwood Illinois (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
LER: | 05000456/LER-2013-002 |
Time - Person (Reporting Time:+-1.22 h-0.0508 days <br />-0.00726 weeks <br />-0.00167 months <br />) | |
Opened: | James Ledbetter 05:47 Sep 14, 2013 |
NRC Officer: | Dong Park |
Last Updated: | Sep 14, 2013 |
49343 - NRC Website
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WEEKMONTHYEARENS 561532022-10-07T06:19:0007 October 2022 06:19:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Control Rod Drive Mechanism (CRDM) Penetration Degraded ENS 536522018-10-08T05:00:0008 October 2018 05:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Leakage ENS 533542018-04-20T22:30:00020 April 2018 22:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Reactor Vessel Head ENS 522752016-10-02T21:00:0002 October 2016 21:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Liquid Penetration Examination Results in Indications on Reactor Vessel Head Penetration ENS 509532015-04-03T21:31:0003 April 2015 21:31:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Liquid Penetration Examination Results in Indication on Reactor Vessel Head Penetration ENS 493532013-09-18T10:10:00018 September 2013 10:10:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Boroscopic Inspection of Reactor Vessel Head Determined Evidence of Boundary Leakage ENS 493432013-09-14T07:00:00014 September 2013 07:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Liquid Penetration Examination Results in Indication on Reactor Vessel Head Penetration ENS 479342012-04-23T06:00:00023 April 2012 06:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Ultrasonic Examination Results in an Indication on the Reactor Pressure Vessel Head Penetration 2022-10-07T06:19:00 | |
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