ENS 41024
ENS Event | |
|---|---|
05:00 Sep 8, 2004 | |
| Title | Potential Reactor Coolant System Pressure Boundary Leak Located |
| Event Description | At 0100 on September 8, 2004, while in Mode 3 conducting a Reactor Building walkdown after an unplanned reactor trip during Tropical Storm Frances, Crystal River Unit 3 identified a potential Reactor Coolant System pressure boundary leak located on a weld associated with a pressurizer level sensing line (upstream of reactor coolant isolation valve RCV-75). The cause of the leak is not known at this time, and the leak did not have a significant effect on plant operation. The last unidentified leak rates that were completed prior to the plant shutdown were 0.10 - 0.13 gpm. This defect in the primary coolant system is unacceptable per ASME Section XI. The condition is 8-Hour reportable per 10CFR 50.72 (b)(3)(ii)(A). The plant will be cooled down to Mode 5 and additional inspections and necessary repairs implemented.
Dry boron crystal deposit are on the sensing line upstream of RCV-75 . See similar event reported by Crystal River Unit 3 on 10/04/03 (event # 40222) The NRC Resident Inspector was notified of this event by the licensee.
At 0311 on 9/8/04, Crystal River Unit 3 made an 8-Hour ENS notification in accordance with 10CFR50.72 (b)(3)(ii)(A) concerning a potential Reactor Coolant System pressure boundary leak (Event Notification 41024). The leak was presumed to exist based on the presence of white, crystalline material deposited on the pipe. The material has been sampled and does NOT contain boron. The presumed leak site has been cleaned and visually inspected with no evidence of a defect in the weld joint or pipe. These additional inspections have demonstrated that the material deposited on the pipe does NOT constitute pressure boundary leakage, and therefore EN 41024 is retracted. The licensee has notified the NRC resident inspector. |
| Where | |
|---|---|
Crystal River  Florida (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-1.82 h-0.0758 days <br />-0.0108 weeks <br />-0.00249 months <br />) | |
| Opened: | Larry Moffatt 03:11 Sep 8, 2004 |
| NRC Officer: | John Mackinnon |
| Last Updated: | Sep 9, 2004 |
| 41024 - NRC Website
Loading map... {"minzoom":false,"maxzoom":false,"mappingservice":"leaflet","width":"350px","height":"250px","centre":false,"title":"","label":"","icon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"zoom":6,"defzoom":14,"layers":["OpenStreetMap"],"image layers":[],"overlays":[],"resizable":false,"fullscreen":false,"scrollwheelzoom":true,"cluster":false,"clustermaxzoom":20,"clusterzoomonclick":true,"clustermaxradius":80,"clusterspiderfy":true,"geojson":"","clicktarget":"","imageLayers":[],"locations":[{"text":"\u003Cb\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003E\u003Ca class=\"mw-selflink selflink\"\u003EENS 41024\u003C/a\u003E - \u003Ca href=\"/Crystal_River\" title=\"Crystal River\"\u003ECrystal River\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003EPotential Reactor Coolant System Pressure Boundary Leak Located\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 41024 - Crystal River\n","link":"","lat":28.959783333333334,"lon":-82.69345555555556,"icon":"/w/images/7/75/Duke_Energy_icon.png"}],"imageoverlays":null} | |
Unit 3 | |
|---|---|
| Reactor critical | Not Critical |
| Scram | No |
| Before | Hot Standby (0 %) |
| After | Hot Standby (0 %) |
WEEKMONTHYEARENS 440372008-03-06T02:00:0006 March 2008 02:00:00
[Table view]10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Circumferential Piping Crack ENS 410692004-09-24T18:00:00024 September 2004 18:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Nureg-1022 Clarification Revised Results of Past Steam Generator Tube Insepctions ENS 410242004-09-08T05:00:0008 September 2004 05:00:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Potential Reactor Coolant System Pressure Boundary Leak Located ENS 402222003-10-04T14:32:0004 October 2003 14:32:00 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Degraded Condition Due to Rcs Pressure Boundary Leakage 2008-03-06T02:00:00 | |