ENS Event | |
|---|---|
09:30 Oct 3, 2004 | |
| Title | |
| Event Description | During a review of outage clearances, it was discovered that a Caution tag out for Service Air to the Drywell was active and the valves were open. This rendered the valves inoperable and Technical Specification 3.6.1.3 action B for one penetration with two inoperable PCIVs was entered. The action was to isolate the penetration by closing one valve within one hour. The event was discovered at 0530 and the outboard valve was closed at 0655 . Since the one hour time limit was exceeded, Technical Specification 3.6.1.3 action E (Mode 3 in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Mode 4 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />) was entered at 0630 and exited at 0655. Technical Specification 3.6.1.3 action A, which is the Tech. Spec. for one inoperable isolation valve will remain in effect. The plant entered Mode 3 at 1530 on 10/01/04. Mode 3 requires primary containment and all PCIVs to be operable. This condition of non-compliance existed from 1530 on 10/01/04 until 0655 on 10/03/04.
The licensee notified the NRC Resident Inspector. |
| Where | |
|---|---|
Hatch  Georgia (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material | |
| Time - Person (Reporting Time:+1.27 h0.0529 days <br />0.00756 weeks <br />0.00174 months <br />) | |
| Opened: | Barry D. Coleman 10:46 Oct 3, 2004 |
| NRC Officer: | Jeff Rotton |
| Last Updated: | Oct 3, 2004 |
| 41086 - NRC Website
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Unit 2 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (20 %) |
| After | Power Operation (20 %) |
WEEKMONTHYEARENS 525632017-02-17T19:14:00017 February 2017 19:14:00
[Table view]10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Secondary Containment Inoperable ENS 435032007-07-18T16:20:00018 July 2007 16:20:00 10 CFR 50.72(b)(3)(v)(A), Loss of Safety Function - Shutdown the Reactor, 10 CFR 50.72(b)(3)(v)(B), Loss of Safety Function - Remove Residual Heat, 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Unanalyzed Condition - Vent Space Less than Design Basis ENS 410862004-10-03T09:30:0003 October 2004 09:30:00 10 CFR 50.72(b)(3)(v)(C), Loss of Safety Function - Release of Radioactive Material Primary Containment Penetration Isolation Valves Inoperable 2017-02-17T19:14:00 | |