ENS 42455
ENS Event | |
|---|---|
03:00 Mar 31, 2006 | |
| Title | Feedwater Check Valve Leakage Above Allowable Limits |
| Event Description | At 21:00 hours on 3/30/06, Unit Two feed water header check valves 2-0220-58A and 2-0220-62A LLRT [local leak rate test] results were both indeterminate, as a result both were greater than the allowable La containment leakage rate allowed by Tech Spec 5.5.12." La is defined as the maximum allowable leak rate at a specified pressure.
This is reportable under 10CFR50.72(b)(3)(ii). The "indeterminate" leak rate was higher than the test equipment could read. The licensee notified the NRC Resident Inspector.
The licensee is retracting this report based on the following: ENS Retraction - Feed Water Header Check Valve Leakage > La Containment Leakage The purpose of this notification is to retract the ENS report made on 3/31/2006 at 0226 EDT (Event # 42455). The initial report was made when it appeared the Unit 2 feed water header check valves 2-0220-58A and 2-0220-62A LLRT (local leak rate test) results were both indeterminate. As a result, both valves appeared to have had a leakage rate greater than the allowable La containment leakage rate allowed by Tech Spec 5.5.12, where La is defined as the maximum allowable primary containment leak rate at accident pressure. Quad Cities assigned all leakage experienced during this test to the primary containment isolation valves being tested and reported the situation as a condition that seriously degraded the nuclear power plant per 10CFR50.72(b)(3)(ii)(A). Subsequently, Quad Cities Station performed testing on 4/2/06 utilizing a higher fill rate test methodology. The subsequent test was completed with satisfactory results. Based on this subsequent testing, ENS report (# 42455) is being retracted. The licensee informed the NRC Resident Inspector. Notified R3DO (Pelke). |
| Where | |
|---|---|
Quad Cities  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-0.57 h-0.0238 days <br />-0.00339 weeks <br />-7.80786e-4 months <br />) | |
| Opened: | Walt Coombs 02:26 Mar 31, 2006 |
| NRC Officer: | Mark Abramovitz |
| Last Updated: | May 8, 2006 |
| 42455 - NRC Website
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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 | |