ENS 40278
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ENS Event | |
|---|---|
01:00 Oct 27, 2003 | |
| Title | Indication of Leakage |
| Event Description | Inspection of the pressurizer bottom nozzles in accordance with the Alloy 600 Program during Refuel 12 identified a wet stain on heater sleeve C1, and a nozzle with a white substance extruding from a portion of the penetration on heater sleeve C3. The substance could not be verified at the time, and further investigation is required to determine if the substance is boron on heater sleeve C3. This condition constitutes a degradation of the RCS Pressure Boundary and is reportable pursuant to 10 CFR 50.72(b)(3)(ii)(A).
The NRC Resident Inspector will be notified of this event by the licensee. |
| Where | |
|---|---|
Waterford  Louisiana (NRC Region 4) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| LER: | 05000382/LER-2003-003 |
| Time - Person (Reporting Time:+-0.65 h-0.0271 days <br />-0.00387 weeks <br />-8.9037e-4 months <br />) | |
| Opened: | Robert Murillo 00:21 Oct 27, 2003 |
| NRC Officer: | John Mackinnon |
| Last Updated: | Oct 27, 2003 |
| 40278 - NRC Website
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Unit 3 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
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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