ENS 49038
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ENS Event | |
|---|---|
10:49 May 15, 2013 | |
| Title | Technical Specification Required Shutdown Due to Discovery of an Unacceptable Flaw During Data Review |
| Event Description | On May 13, 2013, during a secondary review of ultrasonic data of the reactor vessel head penetrations performed during Harris Nuclear Plant spring 2012 refueling outage, it was determined that the results for one of the penetrations appeared to not meet the applicable acceptance criteria. Further evaluation completed on May 15, 2013, characterized the flaw as a 0.26 inch flaw an nozzle 49 that overlaps the J-grove weld and exhibits characteristics of primary water stress corrosion cracking. The original examinations were performed per NRC requirements.
Initial evaluation indicates that the flaw is not through wall and there is no evidence of leakage based on inspections performed on the top of the reactor vessel head during the spring 2012 refueling outage. Operators are shutting down the unit to make the necessary repairs. There is no impact to the health and safety of employees or the public. The NRC resident inspector has been informed. This report is being made in accordance with 10 CFR 50.72(b)(3)(ii)(A), discovery of a degraded condition, 10 CFR 50.72(b)(2)(i), plant shutdown required by technical specifications, and 10 CFR 50.72(b)(3)(v)(C), a condition which could have prevented the fulfillment of a safety function to control the release of radioactive material. |
| Where | |
|---|---|
| Harris North Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | |
| Time - Person (Reporting Time:+9.1 h0.379 days <br />0.0542 weeks <br />0.0125 months <br />) | |
| Opened: | Arthur Pan 19:55 May 15, 2013 |
| NRC Officer: | Pete Snyder |
| Last Updated: | May 15, 2013 |
| 49038 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Harris | |
WEEKMONTHYEARENS 533262018-04-11T18:30:00011 April 2018 18:30:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Indication During Ultrasonic Examination of Reactor Nozzle Penetration ENS 522972016-10-15T12:57:00015 October 2016 12:57:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Vessel Head Penetration Nozzle Flaw ENS 509622015-04-07T15:47:0007 April 2015 15:47:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Vessel Head Penetration Flaw Identified During Inservice Inspection ENS 495532013-11-18T13:00:00018 November 2013 13:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Ultrasonic Examination Identified Flaw in Reactor Vessel Head Penetration ENS 490382013-05-15T10:49:00015 May 2013 10:49:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Technical Specification Required Shutdown Due to Discovery of an Unacceptable Flaw During Data Review ENS 491312012-04-27T18:33:00027 April 2012 18:33:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Head Nozzle Penetration Flaws Identified ENS 478572012-04-21T09:15:00021 April 2012 09:15:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Main Steam Isolation Valves Fail to Shut 2018-04-11T18:30:00 | |
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