ENS 40277
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ENS Event | |
|---|---|
04:00 Oct 25, 2003 | |
| Title | Degradation of the Reactor Coolant System (Rcs) Pressure Boundary |
| Event Description | During inspection of the hot leg nozzles on RCP loop #2 in accordance with the Alloy 600 Program Plan during Refuel 12, evidence of leakage was identified on nozzle RC-IPT-0106B. This constitutes degradation of the RCS pressure boundary. Corrective action is being evaluated.
RC-IPT-0106B is a pressure transmitter that taps off of reactor coolant system hot leg (loop) # 2 . The location of the Pressure transmitter is found in Waterford Unit 3, FSAR Chapter 5.1, Flow Diagram Reactor Coolant System, Figure 5.1-3. The license said that the picture indicates a small amount of boric acid crystals in the area of the leakage. Licensee did not know if the leakage is from a weld, pin hole leak, etc. The NRC Resident Inspector was 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:+3.88 h0.162 days <br />0.0231 weeks <br />0.00531 months <br />) | |
| Opened: | Oscar Pipkins 07:53 Oct 25, 2003 |
| NRC Officer: | John Mackinnon |
| Last Updated: | Oct 25, 2003 |
| 40277 - 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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