ENS 41069
ENS Event | |
|---|---|
18:00 Sep 24, 2004 | |
| Title | Nureg-1022 Clarification Revised Results of Past Steam Generator Tube Insepctions |
| Event Description | On September 24,2004, the NRC published a Notice of Clarification for NUREG-1022 Reporting Guidelines for 10 CFR 50.72 and 50.73. The Notice of Clarification revised the criterion used to determine if the results of steam generator tube inspections were reportable. In this Notice of Clarification, the NRC further directed the plants to consider the results of previous steam generator tube inspections against the new criterion.
Crystal River Unit 3 (CR3) has reviewed the results of the steam generator tube inspection that occurred in the refueling outage of 2003. Specifically, the previously performed Condition Monitoring assessment of the CR3's steam generators concluded that the structural requirements were met and the as-found projected leakage values for a Main Steam Line Break were exceeded. Previously, NUREG-1022 required that both the structural and the leakage criteria must be exceeded for this condition to be reportable. The revision to NUREG-1022 will indicate that only one of the two criteria need be exceeded to be considered reportable per 10 CFR 50.72. Accordingly, CR3 reports per 10 CFR 50.72 (b) (3) (ii) (A) that steam generator projected leakage values for a Main Steam Line Break were exceeded. Immediate corrective actions to reduce the projected accident leakage were completed during the 2003 refueling outage prior to plant startup. The NRC Resident Inspector was notified of this by the licensee. |
| Where | |
|---|---|
| Crystal River Florida (NRC Region 2) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded | |
| Time - Person (Reporting Time:+-0.12 h-0.005 days <br />-7.142857e-4 weeks <br />-1.64376e-4 months <br />) | |
| Opened: | Bill Bandhauer 17:53 Sep 24, 2004 |
| NRC Officer: | John Mackinnon |
| Last Updated: | Sep 24, 2004 |
| 41069 - 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 41069\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\u003ENureg-1022 Clarification Revised Results of Past Steam Generator Tube Insepctions\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 41069 - 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 | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
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 | |