ENS 48940: Difference between revisions
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| event date = 04/17/2013 16:00 EDT | | event date = 04/17/2013 16:00 EDT | ||
| last update date = 06/12/2013 | | last update date = 06/12/2013 | ||
| title = Degraded Condition Due | | title = Degraded Condition Due to Suspected Valve Body Leakage | ||
| event text = On April 17, 2013 at 1600 [EDT], while performing a valve inspection/repair of the Unit 2 'A' Reactor Coolant Loop Fill Valve (2- RC-HCV-2556A), the as-found inspection results identified evidence of a suspected flaw causing leakage from the valve body to the threads of a stud housing of the valve. This valve is a 2 [inch] 316 SS [Stainless Steel] cast ASME XI (Class 1) 1500 psi valve body of a globe style design. Due to this design and the installed orientation, the RCS pressure medium fills the upper portion of the valve bonnet where the leak is located during normal plant operations. Therefore, this leakage would be considered pressure boundary leakage. 2-RC-HCV-2556A is currently isolated from the Reactor Vessel and is at atmospheric pressure. | | event text = On April 17, 2013 at 1600 [EDT], while performing a valve inspection/repair of the Unit 2 'A' Reactor Coolant Loop Fill Valve (2- RC-HCV-2556A), the as-found inspection results identified evidence of a suspected flaw causing leakage from the valve body to the threads of a stud housing of the valve. This valve is a 2 [inch] 316 SS [Stainless Steel] cast ASME XI (Class 1) 1500 psi valve body of a globe style design. Due to this design and the installed orientation, the RCS pressure medium fills the upper portion of the valve bonnet where the leak is located during normal plant operations. Therefore, this leakage would be considered pressure boundary leakage. 2-RC-HCV-2556A is currently isolated from the Reactor Vessel and is at atmospheric pressure. | ||
This inspection was performed in response to dry discolored boric acid identified during the normal operating pressure boric acid accumulation inspection procedure during the Spring 2013 Unit 2 refueling outage shutdown. An engineering evaluation of the suspected defect will be performed and corrective actions implemented. | This inspection was performed in response to dry discolored boric acid identified during the normal operating pressure boric acid accumulation inspection procedure during the Spring 2013 Unit 2 refueling outage shutdown. An engineering evaluation of the suspected defect will be performed and corrective actions implemented. | ||
Latest revision as of 22:00, 1 March 2018
| Where | |
|---|---|
North Anna  Virginia (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+3.32 h0.138 days <br />0.0198 weeks <br />0.00455 months <br />) | |
| Opened: | Lee Kelly 23:19 Apr 17, 2013 |
| NRC Officer: | Vince Klco |
| Last Updated: | Jun 12, 2013 |
| 48940 - NRC Website
| |