ML12033A180
From kanterella
Revision as of 04:09, 3 March 2018 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
ML12033A180 | |
Person / Time | |
---|---|
Site: | Monticello |
Issue date: | 02/17/2011 |
From: | McGruder W S Xcel Energy |
To: | Office of Nuclear Reactor Regulation |
References | |
L-MT-12-002, SIA 1000847.301 CA 11-020, QF-0549 (FP-E-CAL-01), Rev 7 | |
Download: ML12033A180 (31) | |
Similar Documents at Monticello | |
---|---|
Category:Calculation
MONTHYEARL-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023
[Table view]Subsequent License Renewal Application Supplement 3 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 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 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 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. 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. 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 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 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 ML12033A1812011-02-17017 February 2011 Calculation CA 11-005, Revised P-T Curves Calculation, Enclosure 8 ML12033A1802011-02-17017 February 2011 Calculation CA 11-020, Finite Element Analysis of RPV Recirculation Inlet Nozzle, Enclosure 7 ML1018803142010-07-0707 July 2010 ODCM-APP-A, Revision 1, Offsite Dose Calculation Manual ML1013900682010-05-14014 May 2010 Revisions to Offsite Dose Calculation Manual, Enclosure 3 L-MT-09-026, Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac)2009-05-31031 May 2009 Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac) ML0914101232009-05-0606 May 2009 Monticello - Calculation 96-054, Rev 5, Turbine Stop Valve Closure/Generator Load Reject Scram Bypass ML0914101212008-12-19019 December 2008 Monticello - Calculation CA-95-073, Revision 4, Reactor Low Water Level SCRAM Setpoint ML0914101222008-12-18018 December 2008 Monticello - Calculation CA-95-075, Revision 1, Main Steam Line High Flow Setpoint L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis.2008-10-31031 October 2008 Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis. L-MT-08-045, Response to Requests for Additional Information for License Amendment Request: Revision to the Allowable Value and Channel Calibration Surveillance Interval for the Recirculation Riser Differential Pressure - High Function2008-09-0808 September 2008 Response to Requests for Additional Information for License Amendment Request: Revision to the Allowable Value and Channel Calibration Surveillance Interval for the Recirculation Riser Differential Pressure - High Function ML0914101242008-08-11011 August 2008 Monticello - Calculation CA-08-050, Rev. 0, Instrument Setpoint Calculation - Average Power Range Monitor (APRM) Non-Flow Eiased Prnm Setpoints for Cl Tp and EPU ML0915405202008-05-14014 May 2008 Enclosure 3 - Monticello Revisions to ODCM-01.01, Offsite Dose Calculation Manual ML0814002672008-05-0606 May 2008 Offsite Dose Calculation Manual ML0713601792007-05-0808 May 2007 Off-Site Dose Calculation Manual ML0602304362006-01-23023 January 2006 ITS Conversion Beyond Scope Issue 1h 2023-07-04 Category:Report MONTHYEARL-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024
[Table view]Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) ML23172A1112023-06-21021 June 2023 SLRA - Requests for Confirmation of Information - Set 1 L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022 Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies L-MT-22-004, Technical Specification 5.6.4 Post Accident Monitoring Report2022-01-20020 January 2022 Technical Specification 5.6.4 Post Accident Monitoring Report ML21211A5962021-06-30030 June 2021 Attachments 9a, B, 10a, B, 11a, 12a and 13a and 13b, Including ANP-3933NP, Revision 0, Monticello ATWS-I Evaluation for Atrium 11 Fuel, Affidavit L-MT-21-016, Nuclear Material Transaction Report2021-03-25025 March 2021 Nuclear Material Transaction Report L-MT-20-002, 10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange2020-01-31031 January 2020 10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange ML19308A0562019-10-0808 October 2019 Enclosure 1 - Notification of Changes to the Emergency Response Data System (ERDS) L-MT-19-020, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ..2019-04-25025 April 2019 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions .. L-MT-17-060, Steam Dryer Visual Inspection Report2017-08-10010 August 2017 Steam Dryer Visual Inspection Report L-MT-17-055, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 42017-07-26026 July 2017 Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 4 ML17088A5272017-03-31031 March 2017 NSIR Dpcp Confirmatory Review Report, 10 CFR 50.54(p)(2) Changes to the Security Plan, Revision 16, Northern States Power Company, Monticello Nuclear Generating Plant L-MT-17-015, Mitigating Strategies Flood Hazard Assessment (MSA) Submittal2017-03-28028 March 2017 Mitigating Strategies Flood Hazard Assessment (MSA) Submittal ML16302A2462016-10-28028 October 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima.. ML16221A2752016-07-31031 July 2016 ANP-3274NP, Revision 2, Analytical Methods for Monticello ATWS-I. L-MT-16-037, ANP-3284NP, Revision 1, Results of Analysis and Benchmarking of Methods for Monticello ATWS-I.2016-07-31031 July 2016 ANP-3284NP, Revision 1, Results of Analysis and Benchmarking of Methods for Monticello ATWS-I. L-MT-16-010, Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+).2016-02-29029 February 2016 Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+). ML15274A4752015-09-29029 September 2015 Enclosure 6, Areva Report ANP-3435NP, Revision 0 to Are VA Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW LAR (Non-Proprietary) L-MT-15-065, Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits2015-09-29029 September 2015 Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits ML15274A4742015-09-29029 September 2015 Enclosure 4, Engineering Evaluation, EC 25987, Calculation Framework for the Extended Flow Window Stability (Efws) Setpoints ML15175A3362015-07-0808 July 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near Term Task Force ML15169A3582015-06-11011 June 2015 PSP Rev 14 Technical Review 06-11-15 ML16035A1842015-01-30030 January 2015 Document 51-9234641-001, Technical Report of the Demonstration of UT NDE Procedure 54-UT-114-000, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. ML16035A1862015-01-30030 January 2015 54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 2 of 3 ML16035A1852015-01-30030 January 2015 54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 1 of 3 L-MT-14-103, Areva Report ANP-3376NP, Rev. 0, Supplement to Xcel Energy License Amendment Request for Areva Extended Flow Window, Enclosure 2 to L-MT-14-1032014-12-31031 December 2014 Areva Report ANP-3376NP, Rev. 0, Supplement to Xcel Energy License Amendment Request for Areva Extended Flow Window, Enclosure 2 to L-MT-14-103 ML16005A1102014-09-25025 September 2014 Redacted 2014 Decommissioning Cost Analysis for the Prairie Island Nuclear Generating Plant L-MT-14-075, LTR-BWR-ENG-14-043-NP, Responses to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set 8.2014-09-19019 September 2014 LTR-BWR-ENG-14-043-NP, Responses to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set #8. ML14269A3252014-09-0505 September 2014 LTR-BWR-ENG-14-037-NP, Alternate Power Ascension Process. ML14269A3232014-09-0505 September 2014 LTR-BWR-ENG-14-034-NP, Investigation Into the Cause of Exceeding the Level 1 (L1) and Level 2 (L2) Limit Curves Generated Based on 2011 Monticello Main Steam Line Strain Gauge Data. ML14204A6232014-07-18018 July 2014 Enclosure 3, Attachment - Response to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Accoustic/Structural Ananlyses Set #7 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML18100A1902014-05-22022 May 2014 Enclosure 8 - Structural Integrity Associates, Inc. Report 130415.403, Revision 2, Assessment of Monticello Spent Fuel Canister Closure Plate Welds Based on Welding Video Records ML14136A2892014-05-12012 May 2014 14C4229-RPT-001, Revision 3, Monticello Nuclear Generating Plant Seismic Hazard and Screening Report. L-MT-14-041, ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis.2014-05-0909 May 2014 ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis. ML14069A0052014-04-11011 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of NTTF Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14014A2682014-02-28028 February 2014 Staff Review and Evaluation of the Fifth 10-Year Interval Inservice Inspection Program Plan 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 L-MT-14-003, Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information2014-01-31031 January 2014 Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information ML13358A3732013-12-31031 December 2013 Enclosure 1, Reload 26 Cycle 27 Supplemental Reload Licensing Report, 000N0154-SRLR, Revision 5, Extended Power Uprate and Maximum Extended Load Line Limit Plus L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit2013-12-20020 December 2013 Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit ML13282A1422013-10-0404 October 2013 GE-MNGP-AEP-3304R1, Enclosure 2, GEH Response to Mella + RAI 2 L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages2013-10-0404 October 2013 GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages ML13248A3442013-08-29029 August 2013 WCAP-17548-NP, Revision 2 - Signal Processing Performed on Monticello MSL Strain Gauge and Rsd Instrumentation Data, Enclosure 10 ML13248A3452013-08-29029 August 2013 WCAP-17251-NP, Revision 2 - Monticello Replacement Steam Dryer Four-Line Acoustic Subscale Testing Report, Enclosure 11 ML13248A3462013-08-29029 August 2013 WCAP-17252-NP, Revision 4 - Acoustic Loads Definition for the Monticello Steam Dyer Replacement Project, Enclosure 12 ML13248A3482013-08-29029 August 2013 WCAP-17549-NP, Revision 2 - Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, Enclosure 13 L-MT-13-091, WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 142013-08-29029 August 2013 WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14 ML13200A1962013-07-31031 July 2013 ANP-3211(NP), Rev. 1, Monticello EPU LOCA Break Spectrum Analysis for Atrium 10XM Fuel. ML13200A1922013-07-31031 July 2013 ANP-3092(NP), Rev. 0, Monticello Thermal-Hydraulic Design Report for Atrium 10XM Fuel Assemblies. 2024-06-10 Category:Technical MONTHYEARL-MT-24-019, Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii)2024-06-10010 June 2024
[Table view]Submittal of ASME Section XI, Section IWB-3720 Analytical Evaluation in Accordance with 10 CFR 50.55a(b)(2)(xliii) L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022 Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies L-MT-22-004, Technical Specification 5.6.4 Post Accident Monitoring Report2022-01-20020 January 2022 Technical Specification 5.6.4 Post Accident Monitoring Report ML21211A5962021-06-30030 June 2021 Attachments 9a, B, 10a, B, 11a, 12a and 13a and 13b, Including ANP-3933NP, Revision 0, Monticello ATWS-I Evaluation for Atrium 11 Fuel, Affidavit L-MT-21-016, Nuclear Material Transaction Report2021-03-25025 March 2021 Nuclear Material Transaction Report L-MT-20-002, 10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange2020-01-31031 January 2020 10 CFR 50.55a(z)(1) Request RR-015: Proposed Alternative for Examination of ASME Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange ML19308A0562019-10-0808 October 2019 Enclosure 1 - Notification of Changes to the Emergency Response Data System (ERDS) L-MT-19-020, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions ..2019-04-25025 April 2019 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions .. L-MT-17-055, Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 42017-07-26026 July 2017 Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 4 L-MT-16-010, Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+).2016-02-29029 February 2016 Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+). ML15274A4752015-09-29029 September 2015 Enclosure 6, Areva Report ANP-3435NP, Revision 0 to Are VA Responses to RAI-8 and RAI-32 from Srxb and Snpb on MNGP EFW LAR (Non-Proprietary) L-MT-15-065, Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits2015-09-29029 September 2015 Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva Affidavits ML15274A4742015-09-29029 September 2015 Enclosure 4, Engineering Evaluation, EC 25987, Calculation Framework for the Extended Flow Window Stability (Efws) Setpoints ML16035A1842015-01-30030 January 2015 Document 51-9234641-001, Technical Report of the Demonstration of UT NDE Procedure 54-UT-114-000, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. ML16035A1862015-01-30030 January 2015 54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 2 of 3 ML16035A1852015-01-30030 January 2015 54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 1 of 3 L-MT-14-103, Areva Report ANP-3376NP, Rev. 0, Supplement to Xcel Energy License Amendment Request for Areva Extended Flow Window, Enclosure 2 to L-MT-14-1032014-12-31031 December 2014 Areva Report ANP-3376NP, Rev. 0, Supplement to Xcel Energy License Amendment Request for Areva Extended Flow Window, Enclosure 2 to L-MT-14-103 ML16005A1102014-09-25025 September 2014 Redacted 2014 Decommissioning Cost Analysis for the Prairie Island Nuclear Generating Plant L-MT-14-075, LTR-BWR-ENG-14-043-NP, Responses to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set 8.2014-09-19019 September 2014 LTR-BWR-ENG-14-043-NP, Responses to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Acoustic/Structural Analyses Set #8. ML14269A3252014-09-0505 September 2014 LTR-BWR-ENG-14-037-NP, Alternate Power Ascension Process. ML14269A3232014-09-0505 September 2014 LTR-BWR-ENG-14-034-NP, Investigation Into the Cause of Exceeding the Level 1 (L1) and Level 2 (L2) Limit Curves Generated Based on 2011 Monticello Main Steam Line Strain Gauge Data. ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML18100A1902014-05-22022 May 2014 Enclosure 8 - Structural Integrity Associates, Inc. Report 130415.403, Revision 2, Assessment of Monticello Spent Fuel Canister Closure Plate Welds Based on Welding Video Records L-MT-14-041, ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis.2014-05-0909 May 2014 ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis. ML14069A0052014-04-11011 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of NTTF Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident 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 L-MT-14-003, Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information2014-01-31031 January 2014 Enclosures 2 & 3 to L-MT-14-003, ANP-3286NP, Rev. 0, Responses to RAI from Srxb on MNGP Transition to Areva Fuel & Areva Atrium 10XM Fuel Transition - Response to Requests for Additional Information ML13358A3732013-12-31031 December 2013 Enclosure 1, Reload 26 Cycle 27 Supplemental Reload Licensing Report, 000N0154-SRLR, Revision 5, Extended Power Uprate and Maximum Extended Load Line Limit Plus ML13200A1962013-07-31031 July 2013 ANP-3211(NP), Rev. 1, Monticello EPU LOCA Break Spectrum Analysis for Atrium 10XM Fuel. ML13200A1922013-07-31031 July 2013 ANP-3092(NP), Rev. 0, Monticello Thermal-Hydraulic Design Report for Atrium 10XM Fuel Assemblies. ML13200A1952013-06-30030 June 2013 ANP-3213(NP), Rev. 1, Monticello Fuel Transition Cycle 28 Reload Licensing Analysis (Epu/Mellla). ML13200A1902013-06-30030 June 2013 ANP-3224NP, Rev. 2, Applicability of Areva Np BWR Methods to Monticello. ML13191B1282013-06-26026 June 2013 NEDO-33820, Revision 0, Monticello Nuclear Generating Plant Upper Shelf Energy Evaluation for Plate C2220 Material for 54 EFPY, Enclosure 5 ML13200A2002013-05-31031 May 2013 ANP-3139(NP), Rev. 1, Nuclear Fuel Design Report Monticello Cycle 28 Atrium 10XM Fuel. ML13200A1992013-05-31031 May 2013 ANP-3221NP, Rev. 0, Fuel Rod Thermal-Mechanical Design for Monticello Atrium 10XM Fuel Assemblies, Cycle 28. ML13200A1972013-05-31031 May 2013 ANP-3212(NP), Rev. 0, Monticello EPU LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel. ML13200A1942013-05-31031 May 2013 ANP-3215(NP), Rev. 0, Monticello Fuel Transition Cycle 28 Fuel Cycle Design (Epu/Mellla). ML13092A3512013-03-29029 March 2013 Enclosure 12 to L-MT-13-029 - WCAP-17252-NP, Revision 3, Acoustic Loads Definition for the Monticello Steam Dryer Replacement Project. ML13092A3502013-03-29029 March 2013 Enclosure 11 to L-MT-13-029 - WCAP-17251-NP, Revision 1, Monticello Replacement Steam Dryer Four-Line Acoustic Subscale Testing Report. L-MT-13-029, Enclosure 14 to L-MT-13-029 - WCAP-17716-NP, Revision 0, Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project.2013-03-29029 March 2013 Enclosure 14 to L-MT-13-029 - WCAP-17716-NP, Revision 0, Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project. ML13092A3492013-03-29029 March 2013 Enclosure 10 to L-MT-13-029 - WCAP-17548-NP, Revision 1, Signal Processing Performed on Monticello MSL Strain Gauge and Rsd Instrumentation Data. ML13092A3522013-03-29029 March 2013 Enclosure 13 to L-MT-13-029 - WCAP-17549-NP, Revision 1, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using Ace. ML13037A2012013-01-31031 January 2013 NEDO-33800, Rev. 0, Monticello Nuclear Generating Plant Automatic Depressurization System Bypass Timer Extended Power Uprate. ML13200A1892012-11-30030 November 2012 ANP-2637, Rev. 4, Boiling Water Reactor Licensing Methodology Compendium. ML13200A1912012-10-31031 October 2012 ANP-3119NP, Rev. 0, Mechanical Design Report for Monticello Atrium 10XM Fuel Assemblies. ML12300A2202012-10-31031 October 2012 Attachment 10: BWROG-TP-12-018, Revision 0, Task 3 - Pump Operation at Reduced Npsha Conditions (Cvds Pump) L-MT-12-082, Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Supplement to Address Secy 11-0014 Use of Containment Accident Pressure2012-09-28028 September 2012 Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Supplement to Address Secy 11-0014 Use of Containment Accident Pressure ML12307A4342012-08-31031 August 2012 ANP-3113(NP), Rev. 0, Monticello Nuclear Plant Spent Fuel Storage Pool Criticality Safety Analysis for Atrium 10XM Fuel. ML12300A2192012-08-31031 August 2012 Attachment 9: BWROG-TP-12-011, Revision 0, Task 2 - Equation for Pump Speed Correction (Cvds Pump) ML12300A2212012-08-31031 August 2012 Attachment 11: BWROG-TP-12-012, Revision 0, Task 4 - Operation in the Maximum Erosion Rate Zone (Cvds Pump) 2024-06-10 |
Retrieved from "https://kanterella.com/w/index.php?title=ML12033A180&oldid=459281"