ENS 50953
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ENS Event | |
|---|---|
21:31 Apr 3, 2015 | |
| Title | Liquid Penetration Examination Results in Indication on Reactor Vessel Head Penetration |
| Event Description | On April 3, 2015, during the Braidwood Station Unit 1 refueling outage (A1R18), an in-service Liquid Penetration examination was performed on the previously repaired control rod drive mechanism (CRDM) penetration 69. During the examination on the weld build up for CRDM penetration 69, a 3/8 inch rounded indication was discovered located at 0 degrees on the reactor head portion of the weld build up, and it is 4 inches from the transition of the head to penetration. 0 degrees is located at the outermost portion of the penetration on the flange side. The transition is the point where the vertical portion of the penetration meets the horizontal area of the reactor head.
Rounded indications that exceed 3/16 inch are rejectable per ASME Code Case N-729-1. This is reportable pursuant to 10CFR50.72(b)(3)(ii)(A), 'Any event or condition that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded' 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. The NRC Resident Inspector has been informed. |
| Where | |
|---|---|
Braidwood  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| LER: | 05000456/LER-2015-002 |
| Time - Person (Reporting Time:+-1.9 h-0.0792 days <br />-0.0113 weeks <br />-0.0026 months <br />) | |
| Opened: | Murtaza Abbas 19:37 Apr 3, 2015 |
| NRC Officer: | Steve Sandin |
| Last Updated: | Apr 3, 2015 |
| 50953 - 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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