ENS 45710
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ENS Event | |
|---|---|
00:15 Feb 19, 2010 | |
| Title | Rcs Pressure Boundary Leakage Identified on Rtd Weld |
| Event Description | Catawba Nuclear Station is making an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> notification due to a pressure boundary leak on the A loop of the Unit 1 Reactor Coolant System. The leak was found to be originating from 1A Reactor Coolant System hot leg [Resistance Temperature Detector] RTD penetration. Since the allowance for pressure boundary leakage is zero, this is being considered a degraded principal safety barrier. No safety signals were received and no actuations occurred as a result of this leak. The amount of the leak is small and is contained inside containment. No release to the environment occurred and there is no danger to the public. Repair will require the plant to enter Mode 5.
The pressure boundary leakage is 0.08 GPM. The licensee is in a 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> LCO 3.4.13(B)(2), and plans to be in Mode 5 this evening. The licensee has notified the NRC Resident Inspector. |
| Where | |
|---|---|
Catawba  South Carolina (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-4.55 h-0.19 days <br />-0.0271 weeks <br />-0.00623 months <br />) | |
| Opened: | Tom Poetzsch 19:42 Feb 18, 2010 |
| NRC Officer: | Dong Park |
| Last Updated: | Feb 18, 2010 |
| 45710 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Shutdown (0 %) |
| After | Hot Shutdown (0 %) |
WEEKMONTHYEARENS 561652022-10-15T15:59:00015 October 2022 15:59:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Vessel Head Penetration Repair Degraded ENS 552752021-05-25T21:51:00025 May 2021 21:51:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Unit 2 Containment Local Leak Rate and As-Found Integrated Overall Leakage Rate Exceeded Acceptance Criteria ENS 552012021-04-21T02:30:00021 April 2021 02:30:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System (Rcs) Pressure Boundary Degraded ENS 547072020-05-13T02:20:00013 May 2020 02:20:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Coolant System Pressure Boundary Degraded ENS 457102010-02-19T00:15:00019 February 2010 00:15:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Rcs Pressure Boundary Leakage Identified on Rtd Weld ENS 410482004-09-17T14:00:00017 September 2004 14:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Apparent Pressure Boundary Leakage Identified on Steam Generator Bowl Drains ENS 403722003-12-03T20:00:0003 December 2003 20:00:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 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 Backward Installation of Containment Loop Seal Penetration Vacuum Breakers 2022-10-15T15:59:00 | |
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