ENS 41048
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ENS Event | |
|---|---|
14:00 Sep 17, 2004 | |
| Title | Apparent Pressure Boundary Leakage Identified on Steam Generator Bowl Drains |
| Event Description | On September 16, 2004 examinations of the steam generator (SG) bowl drains (SGBDs) for the 2A, 2C and 2D SGs were performed as part of the Alloy 600 program during 2EOC13. These examinations determined that the 2C and 2D SGBDs had leakage and the leakage appeared to be pressure boundary leakage. The 2A SGBD examination determined that the ASME code acceptance limits were satisfied. An evaluation of the leakage indications determined that the leakage had existed for some time prior to the Unit 2 shutdown. The evaluation of this condition on September 17, 2004, determined that this met the reportability criteria of 10 CFR 50.72 (b)(3)(ii)(A). Unit 2 is currently in MODE 6 and this event has no impact on current plant operation. Engineering and plant management are evaluating repair methods to be completed during this refueling outage. This event is not applicable to Unit 1 because the Unit 1 steam generators are of a different design and do not have a drain line in the bottom channel head.
The licensee will notify 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:+-2.48 h-0.103 days <br />-0.0148 weeks <br />-0.0034 months <br />) | |
| Opened: | Michael T Lee 11:31 Sep 17, 2004 |
| NRC Officer: | Gerry Waig |
| Last Updated: | Sep 17, 2004 |
| 41048 - NRC Website
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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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