ENS 52722
ENS Event | |
|---|---|
13:28 May 2, 2017 | |
| Title | Failed Ultrasonic Testing of Weld |
| Event Description | On May 2, 2017, during planned inspections, an ultrasonic examination performed on weld PCS-4-PRS-1P1-1, revealed an axial indication in the pressurizer nozzle to safe end area of the weld. This indication does not meet applicable acceptance criteria under ASME,Section XI.
The plant was in cold shutdown at 0% power for a planned refueling outage at the time of discovery. The condition will be resolved prior to plant startup. This condition has no impact to the health and safety of the public. The licensee notified the NRC Senior Resident Inspector. This report is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A), since an indication was found that did not meet acceptance criteria referenced in ASME Code,Section XI.
Additional evaluations of the recorded indication concluded that the indication was attributed to an erroneous ultrasonic response. This was the result of a combined effect of compromised surface contact at the area of the recorded indication and associated examination scan speed. The contact issue is attributed to the specific tooling configuration required for this exam. The combination of these factors resulted in the introduction of an erroneous reflector in the area of interest that had characteristics of a relevant indication. The vendor repeated the entire examination for axial flaws and there were no service induced indications recorded. A review of the newly acquired data by site, vendor and EPRI personnel confirmed that no service induced flaws are present. The licensee has notified the NRC Resident Inspector. Notified the R3DO (Hills). |
| Where | |
|---|---|
Palisades  Michigan (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+1.97 h0.0821 days <br />0.0117 weeks <br />0.0027 months <br />) | |
| Opened: | Barbara Dotson 15:26 May 2, 2017 |
| NRC Officer: | Dong Park |
| Last Updated: | May 9, 2017 |
| 52722 - NRC Website
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WEEKMONTHYEARENS 548972020-09-11T23:30:00011 September 2020 23:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | Degraded Condition ENS 537492018-11-21T05:00:00021 November 2018 05:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Identified During Surface Inspection of Reactor Head Nozzle Penetration ENS 537342018-11-11T04:00:00011 November 2018 04:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Indication During Ultrasonic Inspection of Reactor Head Nozzle Penetration ENS 537332018-11-10T05:00:00010 November 2018 05:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Boric Acid Identified on Reactor Vessel Head Penetration ENS 527222017-05-02T13:28:0002 May 2017 13:28:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Failed Ultrasonic Testing of Weld ENS 497962014-02-05T18:00:0005 February 2014 18:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Discovered on Pressurizer Nozzle Weld During Testing ENS 497732014-01-29T14:00:00029 January 2014 14:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Indications Identified on Control Rod Drive Mechanism Housings ENS 481822012-08-12T08:18:00012 August 2012 08:18:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Reported Based on the Discovery of Pressure Boundary Leakage ENS 411282004-10-16T21:30:00016 October 2004 21:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Vessel Head Nozzle Cracking 2020-09-11T23:30:00 [Table view] | |