ENS 49163: Difference between revisions
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| event date = 07/01/2013 11:03 EDT | | event date = 07/01/2013 11:03 EDT | ||
| last update date = 07/01/2013 | | last update date = 07/01/2013 | ||
| title = Degraded Condition Due | | title = Degraded Condition Due to Rcp Seal Line Pressure Boundary Leakage | ||
| event text = On 07/01/2013 at 1103 [EDT], inspection personnel identified leakage from a 3/4 inch small-bore pipe socket weld for RCP 1-2 first stage seal cavity vent line. At current Reactor Coolant System conditions (Normal Operating Pressure and Temperature), the leak rate is approximately 8 to 9 drops per minute. | | event text = On 07/01/2013 at 1103 [EDT], inspection personnel identified leakage from a 3/4 inch small-bore pipe socket weld for RCP 1-2 first stage seal cavity vent line. At current Reactor Coolant System conditions (Normal Operating Pressure and Temperature), the leak rate is approximately 8 to 9 drops per minute. | ||
The plant entered Technical Specification (TS) Limiting Condition for Operation (LCO) 3.4.13, 'RCS Operational Leakage', Condition B. Repairs to the line are being evaluated. | The plant entered Technical Specification (TS) Limiting Condition for Operation (LCO) 3.4.13, 'RCS Operational Leakage', Condition B. Repairs to the line are being evaluated. | ||
Latest revision as of 22:00, 1 March 2018
| Where | |
|---|---|
Davis Besse  Ohio (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| LER: | 05000346/LER-2013-002 |
| Time - Person (Reporting Time:+0.4 h0.0167 days <br />0.00238 weeks <br />5.4792e-4 months <br />) | |
| Opened: | Craig Gillig 15:27 Jul 1, 2013 |
| NRC Officer: | Howie Crouch |
| Last Updated: | Jul 1, 2013 |
| 49163 - NRC Website
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