ENS 40721
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ENS Event | |
|---|---|
19:38 Apr 30, 2004 | |
| Title | "on 4/30/2004, During Refueling Outage 1 R18, Ultrasonic Testing of the Reactor Vessel Head Identified Two Axial Indications on Control Rod Drive Mechanism, Nozzle 61. the Indications Were Located on the Outside Diameter of the Nozzle on the Lower Hillside. One of the Flaws Was at the Toe of the Fillet Weld and Extended Below the Fillet Weld Cap. the Second Flaw Extended the Full Length of the Weld and Just Below the Toe of the Fillet Weld. |
| Event Description | There were no indications that either of the flaws was through-wall or through-weld and both were typical of Primary Water Stress Corrosion Cracking. No formal evaluation of these flaws has been completed; however, based on past analysis it is expected that they would not be found acceptable under ASME standards and, therefore, represent degradation of a principal safety barrier reportable under the referenced criterion. This condition was determined to be reportable at 0839 CDT on 5/3/2004.
The nozzle will be repaired prior to startup from the current refueling outage. The reactor vessel head inspection was subsequently completed with no additional flaws identified. The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Arkansas Nuclear  Arkansas (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+67.85 h2.827 days <br />0.404 weeks <br />0.0929 months <br />) | |
| Opened: | R.H.Schneider 15:29 May 3, 2004 |
| NRC Officer: | Joseph Taylor |
| Last Updated: | May 3, 2004 |
| 40721 - NRC Website
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WEEKMONTHYEARENS 573692024-10-08T19:31:0008 October 2024 19:31:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition ENS 534562024-10-07T09:43:0007 October 2024 09:43:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressure Boundary Leakage Identified While Shutdown ENS 555062021-10-04T19:33:0004 October 2021 19:33:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Discovered on Reactor Vessel Head Penetration ENS 457972010-03-27T20:31:00027 March 2010 20:31:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Potentially Degraded Pressurizer Level Tap Identified ENS 414732005-03-09T11:37:0009 March 2005 11:37:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Pressurizer Heater Sleeve Leakage ENS 407212004-04-30T19:38:00030 April 2004 19:38:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded "on 4/30/2004, During Refueling Outage 1 R18, Ultrasonic Testing of the Reactor Vessel Head Identified Two Axial Indications on Control Rod Drive Mechanism, Nozzle 61. the Indications Were Located on the Outside Diameter of the Nozzle on the Lower Hillside. One of the Flaws Was at the Toe of the Fillet Weld and Extended Below the Fillet Weld Cap. the Second Flaw Extended the Full Length of the Weld and Just Below the Toe of the Fillet Weld. ENS 402162003-10-02T22:15:0002 October 2003 22:15:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Rcs Boundary Leakage Due to Small Crack on Drain Line Welded Cap 2024-10-08T19:31:00 | |
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