ENS Event | |
|---|---|
07:45 Mar 27, 2013 | |
| Title | Reactor Pressure Boundary Leakage |
| Event Description | On March 26, 2013, at 1635 [CDT], with Unit 1 shutdown for refueling, leakage was identified from the 2-inch reactor head vent line during a Reactor Pressure Vessel (RPV) pressure test. The leakage was approximately 20 drops per minute. The RPV pressure test was stopped and the reactor vessel depressurized to facilitate examination of the piping and associated flange connections. At 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br /> on March 27, 2013, the leak was confirmed to be through-wall originating from a socket weld (i.e., pipe elbow). The cause and resolution are under evaluation. The condition is being reported under 50.72(b)(3)(ii)(A) given the defect was associated with the primary coolant system pressure boundary.
The licensee notified the NRC Resident Inspector |
| Where | |
|---|---|
Quad Cities  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-3.4 h-0.142 days <br />-0.0202 weeks <br />-0.00466 months <br />) | |
| Opened: | Drew Griffiths 04:21 Mar 27, 2013 |
| NRC Officer: | Vince Klco |
| Last Updated: | Mar 27, 2013 |
| 48853 - NRC Website
Loading map... | |
Unit 1 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Cold Shutdown (0 %) |
| After | Cold Shutdown (0 %) |
WEEKMONTHYEARENS 499772014-03-31T18:02:00031 March 2014 18:02:00
[Table view]10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Unit 2 Reactor Pressure Boundary Leakage and Unit Shutdown ENS 488532013-03-27T07:45:00027 March 2013 07:45:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Reactor Pressure Boundary Leakage ENS 478062012-04-04T22:16:0004 April 2012 22:16:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Identified Reactor Pressure Vessel Test Leakage ENS 424552006-03-31T03:00:00031 March 2006 03:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Feedwater Check Valve Leakage Above Allowable Limits 2014-03-31T18:02:00 | |