ENS Event | |
|---|---|
23:30 Sep 11, 2020 | |
| Title | Degraded Condition |
| Event Description | At 1930 EDT, on September 11, 2020, Palisades Nuclear Plant was conducting ultrasonic data analysis from reactor vessel closure head in-service inspections. During this analysis, signals that display characteristics consistent with primary water stress corrosion cracking were identified in head penetration 34. No leak path signal was identified during ultrasonic testing.
The plant was in cold shutdown at 0% power and in Mode 6 for a refueling outage at the time of discovery. 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. This report is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A) for degradation of a principal safety barrier. This is the only indication that is currently present, however, if additional indications are found, they will also be repaired prior to the plant startup. The licensee notified the NRC Senior Resident Inspector. |
| Where | |
|---|---|
Palisades  Michigan (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-0.6 h-0.025 days <br />-0.00357 weeks <br />-8.2188e-4 months <br />) | |
| Opened: | Jamie Hansen 22:54 Sep 11, 2020 |
| NRC Officer: | Andrew Waugh |
| Last Updated: | Sep 11, 2020 |
| 54897 - NRC Website | |
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] | |