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 Regarding RCS Pressure Boundary Leakage Due to Primary Water Stress Corrosion Cracking (PWSCC) |
| 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
Loading map... | |
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
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