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| Entered date | Event description | |
|---|---|---|
| ENS 40721 | 3 May 2004 15:29:00 | 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. |