ENS 42904
ENS Event | |
|---|---|
15:34 Oct 13, 2006 | |
| Title | Initiation of Reactor Shutdown Required by Technical Specification 3.1.7, Action C.1 |
| Event Description | On October 13, 2006, at 1034 hours0.012 days <br />0.287 hours <br />0.00171 weeks <br />3.93437e-4 months <br />, a Reactor Shutdown was initiated in response to Technical Specification 3.1.7, Action C.1.
At 2236 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.50798e-4 months <br /> on October 12, 2006, it was determined that the Standby Liquid Control tank had a pinhole leak. In accordance with ASME Code requirements for Class 2 pressure boundaries, the SLC tank was declared inoperable, rendering the SLC system inoperable. TS Action 3.1.7, Action B.1, was entered at 2236 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.50798e-4 months <br /> on October 12, 2006 and TS Action 3.1.7, Action C.1, was entered at 0636 hours0.00736 days <br />0.177 hours <br />0.00105 weeks <br />2.41998e-4 months <br /> on October 13, 2006. The SLC tank and system remain available. The pinhole leak does not affect the structural integrity of the tank, and the level, temperature and concentration of the boron solution are being maintained per requirements. All ECCS and EDGs are operable and available and the electrical grid is stable. The licensee informed the NRC Resident Inspector. At 1130 CDT, the licensee received a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> extension in getting to Mode 3 (Hot Shutdown). The licensee is currently holding reactor power at 82% in anticipation of bringing the reactor to 100% full power while in parallel performing the necessary repairs to the Standby Liquid Control tank. |
| Where | |
|---|---|
Quad Cities  Illinois (NRC Region 3) | |
| Reporting | |
| 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown | |
| Time - Person (Reporting Time:+-3.8 h-0.158 days <br />-0.0226 weeks <br />-0.00521 months <br />) | |
| Opened: | Kevin Cravens 11:46 Oct 13, 2006 |
| NRC Officer: | John Mackinnon |
| Last Updated: | Oct 13, 2006 |
| 42904 - NRC Website
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Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (89 %) |
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 477992012-04-02T19:52:0002 April 2012 19:52:00 10 CFR 50.72(b)(3)(v)(D), Loss of Safety Function - Mitigate the Consequences of an Accident, 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Initiation of Reactor Shutdown Required by Technical Specifications (Ts) 3.8.1.F ENS 453332009-09-09T01:10:0009 September 2009 01:10:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Reactor Shutdown Required by Technical Specifications Due to an Unisolable Leak in a Core Spray Minimum Flow Line ENS 429042006-10-13T15:34:00013 October 2006 15:34:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Initiation of Reactor Shutdown Required by Technical Specification 3.1.7, Action C.1 ENS 422602006-01-15T17:04:00015 January 2006 17:04:00 10 CFR 50.72(b)(2)(i), Tech Spec Required Shutdown Ts Shutdown Due to Electromatic Relief Valves (Ervs) Declared Inoperable 2014-03-31T18:02:00 | |