ENS 47466: Difference between revisions
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| event date = 11/21/2011 17:00 EST | | event date = 11/21/2011 17:00 EST | ||
| last update date = 11/22/2011 | | last update date = 11/22/2011 | ||
| title = Confinement Not Maintained | | title = Confinement Not Maintained as Required by Technical Specifications | ||
| event text = Yesterday afternoon, while performing retests on replacement control shim arm switches, reactor operators placed the reactor in a condition that would allow more than one shim control rod to be withdrawn. This violated Technical Specification 3.4.1, "Operations that require confinement." The reactor facility did not have full confinement in place at that time. The specific language of Technical Specification 3.4.1 is "Confinement shall be maintained when changes of components or equipment within the confines of the thermal shield, other than rod drop tests or movement of experiments, are being made which could cause a significant change in reactivity." Although the shim control rods were not withdrawn and the rod bottom lights never cleared, the circumstances, in the licensee's opinion, were that they could have caused a significant change in reactivity, allowing more than one control rod to be withdrawn when the reactor was not in full confinement. | | event text = Yesterday afternoon, while performing retests on replacement control shim arm switches, reactor operators placed the reactor in a condition that would allow more than one shim control rod to be withdrawn. This violated Technical Specification 3.4.1, "Operations that require confinement." The reactor facility did not have full confinement in place at that time. The specific language of Technical Specification 3.4.1 is "Confinement shall be maintained when changes of components or equipment within the confines of the thermal shield, other than rod drop tests or movement of experiments, are being made which could cause a significant change in reactivity." Although the shim control rods were not withdrawn and the rod bottom lights never cleared, the circumstances, in the licensee's opinion, were that they could have caused a significant change in reactivity, allowing more than one control rod to be withdrawn when the reactor was not in full confinement. | ||
The licensee notified the NRC Reactor Inspector. | The licensee notified the NRC Reactor Inspector. | ||
Revision as of 21:05, 1 March 2018
| Where | |
|---|---|
| National Inst Of Standards & Tech Gaithersburg, Maryland (NRC Region 1) | |
| License number: | Tr-5 |
| Reporting | |
| Non | |
| Time - Person (Reporting Time:+16.72 h0.697 days <br />0.0995 weeks <br />0.0229 months <br />) | |
| Opened: | David Shawn O'Kelley 14:43 Nov 22, 2011 |
| NRC Officer: | Donald Norwood |
| Last Updated: | Nov 22, 2011 |
| 47466 - NRC Website | |