ENS 41048: Difference between revisions
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| event date = 09/17/2004 10:00 EDT | | event date = 09/17/2004 10:00 EDT | ||
| last update date = 09/17/2004 | | last update date = 09/17/2004 | ||
| title = Apparent Pressure Boundary Leakage Identified | | title = Apparent Pressure Boundary Leakage Identified on Steam Generator Bowl Drains | ||
| event text = 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. | | event text = 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. | The licensee will notify the NRC Resident Inspector. | ||
Latest revision as of 22:22, 1 March 2018
| 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
| |