ENS 41659
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ENS Event | |
|---|---|
12:55 May 2, 2005 | |
| Title | During Steam Generator Tube Inspection - Greater than 1% (106 Tubes) of the Tubes Were Found Defective |
| Event Description | On May 2, 2005, with Waterford 3 in Mode 6, it was determined that Steam Generator 1 In-Service Inspection had identified more than 1 % defective tubes. Per Technical Specification table 4.4.2-C. this percentage of defective tubes is characterized as "C-3" and should be reported to the NRC. Accordingly, this event is being reported pursuant to 10CFR50.72(b)(3)(ii) as an 8-Hr Non-Emergency Degraded Condition.
In addition, per Technical Specification 4.4.4.5, the final results of the Steam Generator tube inspection, which fall into category C-3, shall be reported in a special report within 30 days and prior to resumption of plant operation. Defective tubes will be plugged. The NRC Resident Inspector was notified. |
| Where | |
|---|---|
Waterford  Louisiana (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-0.62 h-0.0258 days <br />-0.00369 weeks <br />-8.49276e-4 months <br />) | |
| Opened: | Murillo/ Scott 12:18 May 2, 2005 |
| NRC Officer: | Chauncey Gould |
| Last Updated: | May 2, 2005 |
| 41659 - NRC Website
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WEEKMONTHYEARENS 568342023-11-05T16:33:0005 November 2023 16:33:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition - Two Steam Generator Tube Failures Identified ENS 538372019-01-18T19:33:00018 January 2019 19:33:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Weld Does Not Meet Acceptance Criteria ENS 538342019-01-17T06:00:00017 January 2019 06:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Relevant Indication of Degraded Condition ENS 478972012-05-03T21:13:0003 May 2012 21:13:00 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 Both Trains of the Controlled Ventilation Area System Inoperable ENS 455262009-11-29T05:44:00029 November 2009 05:44:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Containment Minimum Pathway Leak Rate Was Exceeded ENS 416592005-05-02T12:55:0002 May 2005 12:55:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded During Steam Generator Tube Inspection - Greater than 1% (106 Tubes) of the Tubes Were Found Defective ENS 416172005-04-19T22:51:00019 April 2005 22:51:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Found at Waterford Unit 3 ENS 402952003-11-04T06:00:0004 November 2003 06:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Number of Steam Generator Tubes Requiring Repair Exceeds 1 Percent ENS 402782003-10-27T01:00:00027 October 2003 01:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Indication of Leakage ENS 402772003-10-25T04:00:00025 October 2003 04:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degradation of the Reactor Coolant System (Rcs) Pressure Boundary 2023-11-05T16:33:00 | |
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