ENS 40295
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ENS Event | |
|---|---|
06:00 Nov 4, 2003 | |
| Title | Number of Steam Generator Tubes Requiring Repair Exceeds 1 Percent |
| Event Description | At 0400 CDT on November 4, 2003 with Waterford 3 refueled, steam generator inspection was being performed in accordance with Technical Specification (TS) 4.4.4.2, Steam Generator Tube Sample Selection and Inspection. The results of the on-going inspection performed on Steam Generator 31 indicated that greater than 1% of the inspected tubes require repair. The number of inspected tubes for SG 31 is 8906 and to date 98 tubes require repair. Based on TS 4.4.4.2.C, this determination results in the Category C-3. The current inspection results do not meet the criteria specified for steam generator tube degradation in NUREG 1022, Event Reporting Guidelines 10 CFR 50.72 and 10 CFR 50.73. However, for Category C-3, TS Table 4.4-2, Steam Generator Tube Inspection, requires that the results of the inspection be reported under 10 CFR 50.72(b)(2), which was superceded by an 8 hr notification in accordance with 50.72(b)(3)(ii).
Per TS 4.4.4.5, the final results of the SG 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. The licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
Waterford  Louisiana (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+6.13 h0.255 days <br />0.0365 weeks <br />0.0084 months <br />) | |
| Opened: | Ron Williams 12:08 Nov 4, 2003 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Nov 4, 2003 |
| 40295 - 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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