Category:Calculation
MONTHYEARL-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023 Subsequent License Renewal Application Supplement 3 ML20136A0162020-05-15015 May 2020 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual ML18100A1932018-04-0505 April 2018 Enclosure 13 - Tn Americas LLC Calculation 11042-0207, Revision 1, Nuhoms 61BTH Type 1 DSC Itcp and Otcp Maximum Weld Flaw Evaluation ML17095A1132017-03-31031 March 2017 License Amendment Request to Revise Emergency Action Level Scheme: Attachment 4, Supporting Calculations for EAL Thresholds, Part 1 of 5 ML17095A1142017-03-31031 March 2017 License Amendment Request to Revise Emergency Action Level Scheme: Attachment 4, Supporting Calculations for EAL Thresholds, Part 2 of 5 ML17095A1182017-03-31031 March 2017 License Amendment Request to Revise Emergency Action Level Scheme: Attachment 4, Supporting Calculations for EAL Thresholds, Part 4 of 5 ML17095A1152017-03-31031 March 2017 License Amendment Request to Revise Emergency Action Level Scheme: Attachment 4, Supporting Calculations for EAL Thresholds, Part 3 of 5 ML17095A1202017-03-31031 March 2017 License Amendment Request to Revise Emergency Action Level Scheme: Attachment 4, Supporting Calculations for EAL Thresholds, Part 5 of 5 ML17130A9702017-02-27027 February 2017 Offsite Dose Calculation Manual, Revision 30 ML17130A9712016-10-13013 October 2016 Offsite Dose Calculation Manual, Revision 31 L-PI-16-037, Transmittal of 2015 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual2016-05-0505 May 2016 Transmittal of 2015 Annual Radioactive Effluent Report and Offsite Dose Calculation Manual L-MT-16-016, Redacted - Calculation 11042-0205, Revision 3, 61BTH Itcp and Otcp Closure Weld Flaw Evaluation.2016-03-21021 March 2016 Redacted - Calculation 11042-0205, Revision 3, 61BTH Itcp and Otcp Closure Weld Flaw Evaluation. L-MT-16-001, 54005-CALC-001, Revision 2, Evaluation of Risk Significance of Permanent ILRT Extension2016-02-0808 February 2016 54005-CALC-001, Revision 2, Evaluation of Risk Significance of Permanent ILRT Extension ML16049A0812016-01-27027 January 2016 Redacted Monticello - Calculation No. 11042-0205, Revision 2, 61BTH Itcp and Otcp Closure Weld Flaw Evaluation. ML15275A0242015-09-29029 September 2015 Calculation 11042-0204, Revision 3, Allowable Flaw Size Evaluation in the Inner Top Cover Plate Closure Weld for DSC No. 16. L-MT-15-056, Redacted - Calculation 1042-0205, Revision 1, 61BTH Itcp and Otcp Closure Weld Flaw Evaluation.2015-09-10010 September 2015 Redacted - Calculation 1042-0205, Revision 1, 61BTH Itcp and Otcp Closure Weld Flaw Evaluation. ML15162A3082015-05-26026 May 2015 Calculation 180461.51.1011, Revision 2, Site Specific PMP and Ancillary Meteorological Analysis. ML15128A2412015-05-0505 May 2015 H4, Offsite Dose Calculation Manual (Ocdm), Revision 29 ML15162A3102015-04-17017 April 2015 Calculation 15-031, Revision 0, Site Specific PMP and Ancillary Meteorological Analysis. L-MT-14-082, Exemption Request for Dry Shielded Canisters 11-16 Dye Penetrant Examinations, Supplemental Information2014-11-0303 November 2014 Exemption Request for Dry Shielded Canisters 11-16 Dye Penetrant Examinations, Supplemental Information ML15275A0252014-10-23023 October 2014 Calculation Package 1301415.301, Revision 0, Development of an Analysis Based Stress Allowable Reduction Factor (Sarf) - Dry Shielded Canister (DSC) Top Closure Weldments. L-PI-14-072, License Amendment Request (LAR) to Revise the Licensing Basis Analysis for a Waste Gas Decay Tank Rupture2014-08-21021 August 2014 License Amendment Request (LAR) to Revise the Licensing Basis Analysis for a Waste Gas Decay Tank Rupture ML15348A2142014-07-31031 July 2014 Enclosure 3, Calculation NEDC-33859 - Non-Proprietary, Instrumentation Limits Calculation, Monticello Nuclear Generating Plant, Average Power Range Monitor Numac Prnm Setpoints - Extended Flow Window Stability, Revision 0, July 2014 L-MT-14-016, Calculation 11042-0204, Revision 2, Structural and Allowable Flaw Size Evaluation of the Spent Fuel Storage Canisters with Nonconforming Closure Welds at Monticello Nuclear Generating Plant2014-07-0707 July 2014 Calculation 11042-0204, Revision 2, Structural and Allowable Flaw Size Evaluation of the Spent Fuel Storage Canisters with Nonconforming Closure Welds at Monticello Nuclear Generating Plant ML14139A0892014-05-15015 May 2014 Offsite Dose Calculation Manual ML14175B1972014-05-0909 May 2014 Enclosure 4 - H4, Offsite Dose Calculation Manual (Odcm), Revision 28, Effective Date: 11/27/13 ML14064A1862014-02-25025 February 2014 Structural Integrity Associates, Inc., Evaluation File No. 1301525.301, Monticello Shroud Support Structure Flaw Evaluation Review and Support Plate Weld Inspection Recommendations ML13135A0132013-05-10010 May 2013 Offsite Dose Calculation Manual ML13308B2212013-04-10010 April 2013 Enclosure 5 - Structural Integrity Associates, Inc. Evaluation File No. 1300180.302 - Evaluation of the Monticello Shroud H10 Weld ML13308B2202013-04-0404 April 2013 Enclosure 4 - Structural Integrity Associates, Inc. Evaluation File No. 1300180.301 - Evaluation of Shear Capacity of Monticello Shroud Welds H8 and H9 ML13039A2022013-01-21021 January 2013 Enclosures 1 & 2 to L-MT-12-114 - Responses to the Gap Analysis and Marked Up Page Changes to EPU Documentation Based on the Gap Analysis Results, Part 2 of 3 L-MT-13-019, Calculation 03-036, Revision 1, Instrument Setpoint Calculation - Reactor Low Pressure Permissive Bypass Timer.2012-09-24024 September 2012 Calculation 03-036, Revision 1, Instrument Setpoint Calculation - Reactor Low Pressure Permissive Bypass Timer. ML12230A0982012-08-0707 August 2012 Calculation Package 1101463.301 Regarding Monticello ISI Relief Request RR-002 ML13133A0632012-06-27027 June 2012 H4, Rev. 27, Offsite Dose Calculation Manual (Odcm). ML12136A1532012-05-10010 May 2012 Enclosure 3, Offsite Dose Calculation Manual ML1211704882012-04-25025 April 2012 Pump P-109A, 11-RHRSW Stuffing Box with Through-Wall Leak at Monticello Plant L-MT-12-011, Supplement to 10CFR50.55a Requests Associated with the Fourth and Fifth Lnservice Lnspection Ten-Year Intervals2012-02-15015 February 2012 Supplement to 10CFR50.55a Requests Associated with the Fourth and Fifth Lnservice Lnspection Ten-Year Intervals ML12033A1782011-07-29029 July 2011 Calculation CA 11-003, Evaluation of Adjusted Reference Temperatures and Reference Temperature Shifts, Enclosure 5 ML11133A3892011-05-12012 May 2011 Offsite Dose Calculation Manual ML13191A0392011-05-0202 May 2011 Evaluation of the Monticello Shroud Support Plate Uplift Load with Indications in the H8 and H9 Welds ML13191A0382011-04-15015 April 2011 Evaluation of the Monticello Shroud Support Leg Indications Considering Indications at Welds H8 and H9 ML1120701782011-03-31031 March 2011 NRC-DCM Annual Calculation, Enclosure 2 ML12033A1792011-02-17017 February 2011 Calculation CA 11-004, Finite Element Stress Analysis of Monticello RPV Feedwater Nozzle, Enclosure 6 ML12033A1802011-02-17017 February 2011 Calculation CA 11-020, Finite Element Analysis of RPV Recirculation Inlet Nozzle, Enclosure 7 ML12033A1812011-02-17017 February 2011 Calculation CA 11-005, Revised P-T Curves Calculation, Enclosure 8 L-PI-10-076, Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 52010-07-23023 July 2010 Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 5 ML1023002962010-07-23023 July 2010 Calculation No. GEN-PI-078, Revision 1, Main Steam Line Break (MSLB) Accident Analysis Using AST, Attachment 2 ML1023002972010-07-23023 July 2010 Calculation No. GEN-PI-081, Revision 1, Eab, LPZ, and CR Doses Due to Steam Generator Tube Rupture Accident - AST, Attachment 3 ML1023002982010-07-23023 July 2010 Calculation No. GEN-PI-082, Revision 1, Control Rod Ejection Accident - AST, Attachment 4 ML1018803142010-07-0707 July 2010 ODCM-APP-A, Revision 1, Offsite Dose Calculation Manual 2023-07-04
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