ENS 49796
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ENS Event | |
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18:00 Feb 5, 2014 | |
Title | Degraded Condition Discovered on Pressurizer Nozzle Weld During Testing |
Event Description | On February 5, 2014, during planned inspections, an ultrasonic examination performed on weld PCS-6-PRS-1C1-1 (RV-1041) revealed two axial indications in the root area of the weld. The weld containing the indications is the nozzle to safe end dissimilar metal weld on the flange for pressurizer safety valve RV-1041. These two indications do not meet applicable acceptance criteria under ASME,Section XI, IWB-3600, 'Analytical Evaluation of Flaws,' or ASME Section Xl, Table IWB-3410, 'Acceptance Standards,' and will require a repair or replacement activity in order return the weld to an acceptable condition.
The plant was in cold shutdown at 0% power for a planned refueling outage at the time of discovery. Replacement or repair actions will be completed prior to plant startup from the outage. 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 indications were found that did not meet acceptance criteria referenced in ASME Code,Section XI. |
Where | |
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Palisades Michigan (NRC Region 3) | |
Reporting | |
10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
Time - Person (Reporting Time:+-1.72 h-0.0717 days <br />-0.0102 weeks <br />-0.00236 months <br />) | |
Opened: | Barb Dotson 16:17 Feb 5, 2014 |
NRC Officer: | Jeff Rotton |
Last Updated: | Feb 5, 2014 |
49796 - 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] | |
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