Semantic search
Jump to navigation
Jump to search
| Issue date | Title | Topic | |
|---|---|---|---|
| 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 Methodologies | 6 June 2022 | Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies | Stroke time Anticipated operational occurrence Safe Shutdown Earthquake Operating Basis Earthquake MELLLA |
| L-MT-22-004, Technical Specification 5.6.4 Post Accident Monitoring Report | 20 January 2022 | Technical Specification 5.6.4 Post Accident Monitoring Report | Post Accident Monitoring |
| ML21211A596 | 30 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 | Shutdown Margin Safety Limit Minimum Critical Power Ratio Stroke time Anticipated operational occurrence Feedwater Controller Failure MELLLA Time Critical Operator Action Fuel cladding |
| L-MT-21-016, Nuclear Material Transaction Report | 25 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 Flange | 31 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 | Finite Element Analysis Weak link |
| ML19308A056 | 8 October 2019 | Enclosure 1 - Notification of Changes to the Emergency Response Data System (ERDS) | Reactor Vessel Water Level Met Tower |
| 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 .. | 25 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 .. | High winds Tornado Missile FLEX Design basis earthquake Severe Accident Management Guideline Hardened vent |
| 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 4 | 26 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 | Tornado Missile Safe Shutdown Earthquake Operator Manual Action FLEX Fukushima Dai-Ichi Spent Fuel Pool Instrumentation B.5.b Mitigating Strategies |
| L-MT-16-010, Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+). | 29 February 2016 | Enclosure 2 Areva Report ANP-3295NP, Rev. 3, Monticello Licensing Analysis for EFW (Epu/Mella+). | Safe Shutdown Shutdown Margin Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Feedwater Controller Failure MELLLA Fuel cladding |
| ML15274A475 | 29 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) | MELLLA |
| 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 Affidavits | 29 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 | MELLLA |
| ML15274A474 | 29 September 2015 | Enclosure 4, Engineering Evaluation, EC 25987, Calculation Framework for the Extended Flow Window Stability (Efws) Setpoints | Power change |
| ML16035A184 | 30 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. | |
| ML16035A186 | 30 January 2015 | 54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 2 of 3 | |
| ML16035A185 | 30 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-14-103 | 31 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 | |
| ML16005A110 | 25 September 2014 | Redacted 2014 Decommissioning Cost Analysis for the Prairie Island Nuclear Generating Plant | |
| ML14269A325 | 5 September 2014 | LTR-BWR-ENG-14-037-NP, Alternate Power Ascension Process. | |
| ML14269A323 | 5 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. | |
| ML14176A961 | 24 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 | Fire Barrier Coatings Foreign Material Exclusion |
| ML18100A190 | 22 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. | 9 May 2014 | ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis. | |
| ML14069A005 | 11 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 | Unanalyzed Condition Safe Shutdown Earthquake Fukushima Dai-Ichi Earthquake |
| ML14064A186 | 25 February 2014 | Structural Integrity Associates, Inc., Evaluation File No. 1301525.301, Monticello Shroud Support Structure Flaw Evaluation Review and Support Plate Weld Inspection Recommendations | EVT-1 |
| 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 Information | 31 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 | Shutdown Margin Anticipated operational occurrence Feedwater Controller Failure Fuel cladding Grace period |
| ML13358A373 | 31 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 | Shutdown Margin Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Feedwater Controller Failure MELLLA |
| ML13200A196 | 31 July 2013 | ANP-3211(NP), Rev. 1, Monticello EPU LOCA Break Spectrum Analysis for Atrium 10XM Fuel. | Stroke time Fuel cladding |
| ML13200A192 | 31 July 2013 | ANP-3092(NP), Rev. 0, Monticello Thermal-Hydraulic Design Report for Atrium 10XM Fuel Assemblies. | Anticipated operational occurrence Minimum Critical Power Ratio MELLLA |
| ML13200A195 | 30 June 2013 | ANP-3213(NP), Rev. 1, Monticello Fuel Transition Cycle 28 Reload Licensing Analysis (Epu/Mellla). | Safe Shutdown Shutdown Margin Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence Feedwater Controller Failure MELLLA Fuel cladding |
| ML13200A190 | 30 June 2013 | ANP-3224NP, Rev. 2, Applicability of Areva Np BWR Methods to Monticello. | Shutdown Margin Safety Limit Minimum Critical Power Ratio Stroke time Anticipated operational occurrence FLEX Feedwater Controller Failure Fuel cladding |
| ML13191B128 | 26 June 2013 | NEDO-33820, Revision 0, Monticello Nuclear Generating Plant Upper Shelf Energy Evaluation for Plate C2220 Material for 54 EFPY, Enclosure 5 | Finite Element Analysis |
| ML13200A200 | 31 May 2013 | ANP-3139(NP), Rev. 1, Nuclear Fuel Design Report Monticello Cycle 28 Atrium 10XM Fuel. | Shutdown Margin |
| ML13200A199 | 31 May 2013 | ANP-3221NP, Rev. 0, Fuel Rod Thermal-Mechanical Design for Monticello Atrium 10XM Fuel Assemblies, Cycle 28. | Anticipated operational occurrence MELLLA |
| ML13200A197 | 31 May 2013 | ANP-3212(NP), Rev. 0, Monticello EPU LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel. | Stroke time Fuel cladding |
| ML13200A194 | 31 May 2013 | ANP-3215(NP), Rev. 0, Monticello Fuel Transition Cycle 28 Fuel Cycle Design (Epu/Mellla). | Shutdown Margin MELLLA |
| ML13092A349 | 29 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. | |
| 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. | 29 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. | |
| ML13092A350 | 29 March 2013 | Enclosure 11 to L-MT-13-029 - WCAP-17251-NP, Revision 1, Monticello Replacement Steam Dryer Four-Line Acoustic Subscale Testing Report. | |
| ML13092A351 | 29 March 2013 | Enclosure 12 to L-MT-13-029 - WCAP-17252-NP, Revision 3, Acoustic Loads Definition for the Monticello Steam Dryer Replacement Project. | |
| ML13092A352 | 29 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. | Finite Element Analysis |
| ML13037A201 | 31 January 2013 | NEDO-33800, Rev. 0, Monticello Nuclear Generating Plant Automatic Depressurization System Bypass Timer Extended Power Uprate. | |
| ML13200A189 | 30 November 2012 | ANP-2637, Rev. 4, Boiling Water Reactor Licensing Methodology Compendium. | Shutdown Margin Safety Limit Minimum Critical Power Ratio Anticipated operational occurrence FLEX Feedwater Controller Failure Earthquake Fuel cladding Power change Flow Induced Vibration |
| ML13200A191 | 31 October 2012 | ANP-3119NP, Rev. 0, Mechanical Design Report for Monticello Atrium 10XM Fuel Assemblies. | Anticipated operational occurrence Finite Element Analysis |
| ML12300A220 | 31 October 2012 | Attachment 10: BWROG-TP-12-018, Revision 0, Task 3 - Pump Operation at Reduced Npsha Conditions (Cvds Pump) | Mission time |
| 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 Pressure | 28 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 | Safe Shutdown Ultimate heat sink Mission time Probabilistic Risk Assessment Multiple Spurious Operation Backfit |
| ML12307A434 | 31 August 2012 | ANP-3113(NP), Rev. 0, Monticello Nuclear Plant Spent Fuel Storage Pool Criticality Safety Analysis for Atrium 10XM Fuel. | |
| ML12300A224 | 31 August 2012 | Attachment 13: BWROG-TP-12-014, Revision 0, Task 6 - Npshr Test Instrument Inaccuracy Effect on Published Results (Cvds Pump) | |
| ML12300A222 | 31 August 2012 | Attachment 12: BWROG-TP-12-013, Revision 0, Task 5 - Effects of Non-Condensible Gases on Seals (Cvds Pump) | |
| ML12300A221 | 31 August 2012 | Attachment 11: BWROG-TP-12-012, Revision 0, Task 4 - Operation in the Maximum Erosion Rate Zone (Cvds Pump) | Mission time |
| ML12300A219 | 31 August 2012 | Attachment 9: BWROG-TP-12-011, Revision 0, Task 2 - Equation for Pump Speed Correction (Cvds Pump) |