ENS 47619: Difference between revisions
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| event date = 01/23/2012 13:00 EST | | event date = 01/23/2012 13:00 EST | ||
| last update date = 01/26/2012 | | last update date = 01/26/2012 | ||
| title = Breach | | title = Breach in High Energy Line Break Barrier | ||
| event text = At 1300 EST on 1/23/12, it was determined that an unanalyzed condition existed for the Unit 1 Cable Spreading Room. A high energy line break (HELB) barrier issue was discovered while performing a HELB inspection and the condition is believed to have existed from initial plant construction. A HELB barrier was found to have a breach in it that could allow steam from a high energy line break in the Unit 1 Turbine Building [into the cable spreading room and thus into the control room]. The Control Room is not analyzed for a steam environment. The degree of the impact could not be readily determined, but could likely affect the safety related equipment in the Cable Spreading Room. Therefore, an 8-hour report to the NRC is required under 10 CFR 50.72(b)(3)(ii)(B), 'Any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.' | | event text = At 1300 EST on 1/23/12, it was determined that an unanalyzed condition existed for the Unit 1 Cable Spreading Room. A high energy line break (HELB) barrier issue was discovered while performing a HELB inspection and the condition is believed to have existed from initial plant construction. A HELB barrier was found to have a breach in it that could allow steam from a high energy line break in the Unit 1 Turbine Building [into the cable spreading room and thus into the control room]. The Control Room is not analyzed for a steam environment. The degree of the impact could not be readily determined, but could likely affect the safety related equipment in the Cable Spreading Room. Therefore, an 8-hour report to the NRC is required under 10 CFR 50.72(b)(3)(ii)(B), 'Any event or condition that results in the nuclear power plant being in an unanalyzed condition that significantly degrades plant safety.' | ||
The licensee will notify the NRC Resident Inspector. | The licensee will notify the NRC Resident Inspector. | ||
Latest revision as of 22:04, 1 March 2018
| Where | |
|---|---|
Calvert Cliffs  Maryland (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+2.98 h0.124 days <br />0.0177 weeks <br />0.00408 months <br />) | |
| Opened: | Joe Gioffre 20:59 Jan 23, 2012 |
| NRC Officer: | John Knoke |
| Last Updated: | Jan 26, 2012 |
| 47619 - NRC Website
| |