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Issue date | Title | Topic | |
---|---|---|---|
ML23172A111 | 21 June 2023 | SLRA - Requests for Confirmation of Information - Set 1 | Fire Barrier Aging Management |
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-17-060, Steam Dryer Visual Inspection Report | 10 August 2017 | Steam Dryer Visual Inspection Report | Earthquake |
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 |
ML17088A527 | 31 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 | Cyber Security |
L-MT-17-015, Mitigating Strategies Flood Hazard Assessment (MSA) Submittal | 28 March 2017 | Mitigating Strategies Flood Hazard Assessment (MSA) Submittal | High winds Ultimate heat sink FLEX Fukushima Dai-Ichi |
ML16302A246 | 28 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.. | Safe Shutdown Earthquake Probabilistic Risk Assessment Fukushima Dai-Ichi Design basis earthquake Earthquake |
ML16221A275 | 31 July 2016 | ANP-3274NP, Revision 2, Analytical Methods for Monticello ATWS-I. | Power change |
L-MT-16-037, ANP-3284NP, Revision 1, Results of Analysis and Benchmarking of Methods for Monticello ATWS-I. | 31 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+). | 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 |
ML15274A474 | 29 September 2015 | Enclosure 4, Engineering Evaluation, EC 25987, Calculation Framework for the Extended Flow Window Stability (Efws) Setpoints | Power change |
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 |
ML15175A336 | 8 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 | Safe Shutdown Safe Shutdown Earthquake Operating Basis Earthquake Fukushima Dai-Ichi Earthquake |
ML15169A358 | 11 June 2015 | PSP Rev 14 Technical Review 06-11-15 | |
ML16035A185 | 30 January 2015 | 54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 1 of 3 | |
ML16035A186 | 30 January 2015 | 54-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 2 of 3 | |
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. | |
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. | |
ML14204A623 | 18 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 | |
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 | |
ML14136A289 | 12 May 2014 | 14C4229-RPT-001, Revision 3, Monticello Nuclear Generating Plant Seismic Hazard and Screening Report. | Safe Shutdown Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Design basis earthquake Earthquake |
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 |
ML14014A268 | 28 February 2014 | Staff Review and Evaluation of the Fifth 10-Year Interval Inservice Inspection Program Plan | Incorporated by reference Aging Management |
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 |
ML14077A095 | 30 January 2014 | BWROG-TP-14-001, Rev. 0, Containment Accident Pressure Committee (344) Task 1 - Cfd Report and Combined Npshr Uncertainty for Browns Ferry/ Peach Bottom Cvic RHR Pumps, Attachment 8 | Mission time |
ML14077A090 | 31 December 2013 | BWROG-TP-13-021, Rev. 0, Containment Accident Pressure Committee (344) Task 4 - Operation in Maximum Erosion Rate Zone (Cvic Pump), Attachment 11 | Mission time |
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 |
L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit | 20 December 2013 | Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit | MELLLA |
ML13282A142 | 4 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 Pages | 4 October 2013 | GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages | |
ML13248A346 | 29 August 2013 | WCAP-17252-NP, Revision 4 - Acoustic Loads Definition for the Monticello Steam Dyer Replacement Project, Enclosure 12 | |
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 14 | 29 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 | |
ML13248A348 | 29 August 2013 | WCAP-17549-NP, Revision 2 - Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, Enclosure 13 | Finite Element Analysis |
ML13248A344 | 29 August 2013 | WCAP-17548-NP, Revision 2 - Signal Processing Performed on Monticello MSL Strain Gauge and Rsd Instrumentation Data, Enclosure 10 | |
ML13248A345 | 29 August 2013 | WCAP-17251-NP, Revision 2 - Monticello Replacement Steam Dryer Four-Line Acoustic Subscale Testing Report, Enclosure 11 | |
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 |
ML13200A196 | 31 July 2013 | ANP-3211(NP), Rev. 1, Monticello EPU LOCA Break Spectrum Analysis for Atrium 10XM Fuel. | Stroke time Fuel cladding |