ML13127A030
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| ML13127A030 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/20/2013 |
| From: | Exelon Generation Co, Exelon Nuclear |
| To: | Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards |
| References | |
| CY-LG-170-301, Rev 26 | |
| Download: ML13127A030 (330) | |
Similar Documents at Limerick | |
|---|---|
Category:Calculation
MONTHYEARML18129A3332018-05-0404 May 2018
[Table view]Instrument Nozzle N-160 Repair Weld Residual Stress Analysis, Areva Document No. 32-9277502-000 (Non-Proprietary) ML18129A3322018-05-0404 May 2018 Instrumentation Nozzle N-16D As-Left J-Groove Weld Analysis, Areva Document No. 32-9281804-000 (Non-Proprietary Version) ML15133A1242015-04-24024 April 2015 Offsite Dose Calculation Manual, Revision 27 ML13127A0302013-03-20020 March 2013 CY-LG-170-301, Rev. 26, Offsite Dose Calculation Manual, Attachment 2 ML12129A3922011-08-23023 August 2011 CY-LG-170-301, Rev. 25, Limerick'S Offsite Dose Calculation Manual ML1020701972010-03-12012 March 2010 Attachment 3, Exelon Generation Company, Calculation LE-0113, Rev. 1, Reactor Core Thermal Power Uncertainty Calculation Unit 1 ML1008504102010-01-20020 January 2010 Calculation LE-0107, Rev. 1, GE Numac Prnm Setpoint Study ML1008504062009-12-0202 December 2009 Calculation LE-0113, Rev. 0, Reactor Core Thermal Power Uncertainty Calculation Unit 1 ML1035100272009-11-20020 November 2009 Loop Uncertainty Calculation TE-055-1N028B ML0912804322008-06-30030 June 2008 CY-LG-170-301, Revision 24, Offsite Dose Calculation Manual ML0812606842008-04-30030 April 2008 Rev. 23 to Offsite Dose Calculation Manual ML0617800472006-06-16016 June 2006 Calculation No. LM-0646, Rev 2, Re-Analysis of Loss of Coolant Accident (LOCA) Using Alternative Source Terms, Attachment 2 ML0617800462006-06-14014 June 2006 Calculation No. LM-0646, Rev 2, Re-Analysis of Loss of Coolant Accident (LOCA) Using Alternative Source Terms. Attachment 1 ML0533303732005-09-27027 September 2005 Calculation LM-0645, Rev 1, Re-analysis of Fuel Handling Accident (FHA) Using Alternative Source Terms, Attachment 009 ML0533303612005-09-27027 September 2005 Calculation LM-0642, Rev 0, Suppression Pool Ph Calculation for Alternative Source Terms, Attachment 002 ML0533303822005-09-21021 September 2005 Calculation LM-0646, Rev 1, Re-analysis of Loss of Coolant Accident (LOCA) Using Alternative Source Terms, Attachment 1 Design Analysis Cover Sheet ML0533303642005-09-21021 September 2005 Calculation LM-0643, Rev 1, Re-analysis of Control Rod Drop Accident (CRDA) Using Alternative Source Terms, Attachment 006 ML0533303702005-09-20020 September 2005 Calculation LM-0644, Rev 1, Re-analysis of Main Stream Line Break (MSLB) Accident Using Alternative Source Terms, Attachment 007 ML0533303572004-08-30030 August 2004 Calculation LM-0641, Rev 0, Calculation of Alternative Source Term (AST) Onsite and Offsite X/Q Values, Attachment 001 ML1001305452003-08-11011 August 2003 CAL-DSU-NU-000002 Rev 00A, Limerick Unit 1 Radiochemical Assay Comparisons to SAS2H Calculations. ML0706002112003-01-17017 January 2003 GE # Index 9-3, Rev. 1; an ASME Section Viii Evaluation of Oc Drywell for Without Sand Case Part 1 Stress Analysis, 2/91 2018-05-04 |
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