ENS 46933
From kanterella
Jump to navigation
Jump to search
ENS Event | |
|---|---|
12:00 Jun 7, 2011 | |
| Title | Errors in Methodology Used for Emergency Core Cooling System Performance Requirements |
| Event Description | On Tuesday, June 7, 2011, at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />, Pilgrim Station reviewed General Electric Hitachi (GEH) 10 CFR 50.46 Notification Letters 2011-02 and 2011-03. These letters indicate that certain errors were discovered in the methodology application and inputs used by GEH for nuclear fuel core configurations with GE14 and GNF2 fuel, and when corrected may increase the Peak Cladding Temperature (PCT) limits in excess of 2200 degrees F under Loss of Coolant Accident (LOCA) conditions. Pilgrim's core contains both GE14 and GNF2 fuel. 10 CFR 50.46 paragraph (b) defines the acceptance criteria for the LOCA analysis process. The Pilgrim licensing basis PCT is evaluated for compliance with the criterion 50.46(b)(1) and must not exceed a PCT of 2200?F.
GEH had provided a compensatory measure in the form of multiplier to be applied to the MAPLHGR (Maximum Average Planar Linear Heat Generation Rate) limit so that Pilgrim operates within 50.46 limits. Entergy/Pilgrim implemented the compensatory measure and as a result the errors reported have no impact on current plant operation or public health and safety. This 8-hour notification is being reported for conservative purposes in accordance with 10 CFR 50.72 (b)(3)(ii)(B). Based on 50.46(a)(3)(ii) criteria, Entergy/Pilgrim will submit a report within 30 days. Entergy/Pilgrim has notified the NRC Senior Resident Inspector." The licensee also plans to notify the State of Massachusetts. |
| Where | |
|---|---|
| Pilgrim Massachusetts (NRC Region 1) | |
| Reporting | |
| 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
| Time - Person (Reporting Time:+3.5 h0.146 days <br />0.0208 weeks <br />0.00479 months <br />) | |
| Opened: | Paul Gallant 15:30 Jun 7, 2011 |
| NRC Officer: | Bill Huffman |
| Last Updated: | Jun 7, 2011 |
| 46933 - 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 46933\u003C/a\u003E - \u003Ca href=\"/Pilgrim\" title=\"Pilgrim\"\u003EPilgrim\u003C/a\u003E\n\u003C/p\u003E\u003C/div\u003E\u003C/b\u003E\u003Cdiv class=\"mw-parser-output\"\u003E\u003Cp\u003EErrors in Methodology Used for Emergency Core Cooling System Performance Requirements\n\u003C/p\u003E\u003C/div\u003E","title":"ENS 46933 - Pilgrim\n","link":"","lat":41.942861111111114,"lon":-70.57673055555556,"icon":""}],"imageoverlays":null} | |
Unit 1 | |
|---|---|
| Reactor critical | Critical |
| Scram | No |
| Before | Power Operation (100 %) |
| After | Power Operation (100 %) |
Pilgrim with 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition | |
WEEKMONTHYEARENS 532872018-03-25T20:16:00025 March 2018 20:16:00
[Table view]10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition, 10 CFR 50.72(b)(3)(ii)(A), Seriously Degraded Control Rod Drive Piping Potentially Inoperable ENS 519242016-05-12T20:47:00012 May 2016 20:47:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Deterioration of Spent Fuel Pool Rack Neutron Absorbing Material ENS 514562015-10-05T21:25:0005 October 2015 21:25:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Safe Shutdown Analysis for Fire Event - Open Item with Potential to Impact Capability to Operate Motor Operated Valves ENS 472882011-09-22T18:52:00022 September 2011 18:52:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Salt Service Water Pump Inoperability During Postulated Degraded Voltage Conditions ENS 469332011-06-07T12:00:0007 June 2011 12:00:00 10 CFR 50.72(b)(3)(ii)(B), Unanalyzed Condition Errors in Methodology Used for Emergency Core Cooling System Performance Requirements 2018-03-25T20:16:00 | |
Retrieved from "https://kanterella.com/w/index.php?title=ENS_46933&oldid=424603"