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 Issue dateTitleTopic
ML23172A11121 June 2023SLRA - Requests for Confirmation of Information - Set 1Fire 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 Methodologies6 June 2022Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome MethodologiesStroke time
Anticipated operational occurrence
Safe Shutdown Earthquake
Operating Basis Earthquake
MELLLA
L-MT-22-004, Technical Specification 5.6.4 Post Accident Monitoring Report20 January 2022Technical Specification 5.6.4 Post Accident Monitoring ReportPost Accident Monitoring
ML21211A59630 June 2021Attachments 9a, B, 10a, B, 11a, 12a and 13a and 13b, Including ANP-3933NP, Revision 0, Monticello ATWS-I Evaluation for Atrium 11 Fuel, AffidavitShutdown 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 Report25 March 2021Nuclear 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 Flange31 January 202010 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 FlangeFinite Element Analysis
Weak link
ML19308A0568 October 2019Enclosure 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 2019Report 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 Report10 August 2017Steam Dryer Visual Inspection ReportEarthquake
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 426 July 2017Seismic Mitigating Strategies Assessment (MSA) Report for the Reevaluated Seismic Hazard Information - NEI 12-06, Revision 4, Appendix H, H.4.4, Path 4Tornado Missile
Safe Shutdown Earthquake
Operator Manual Action
FLEX
Fukushima Dai-Ichi
Spent Fuel Pool Instrumentation
B.5.b Mitigating Strategies
ML17088A52731 March 2017NSIR Dpcp Confirmatory Review Report, 10 CFR 50.54(p)(2) Changes to the Security Plan, Revision 16, Northern States Power Company, Monticello Nuclear Generating PlantCyber Security
L-MT-17-015, Mitigating Strategies Flood Hazard Assessment (MSA) Submittal28 March 2017Mitigating Strategies Flood Hazard Assessment (MSA) SubmittalHigh winds
Ultimate heat sink
FLEX
Fukushima Dai-Ichi
ML16302A24628 October 2016Spent 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
ML16221A27531 July 2016ANP-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 2016ANP-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 2016Enclosure 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
ML15274A47429 September 2015Enclosure 4, Engineering Evaluation, EC 25987, Calculation Framework for the Extended Flow Window Stability (Efws) SetpointsPower change
ML15274A47529 September 2015Enclosure 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 Affidavits29 September 2015Enclosure 8, Areva Report ANP-3424NP, Revision 1 to Areva Responses to RAI from Scvb on MNGP EFW LAR (Non-Proprietary) and Enclosure 9, Areva AffidavitsMELLLA
ML15175A3368 July 2015Staff 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 ForceSafe Shutdown
Safe Shutdown Earthquake
Operating Basis Earthquake
Fukushima Dai-Ichi
Earthquake
ML15169A35811 June 2015PSP Rev 14 Technical Review 06-11-15
ML16035A18530 January 201554-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 1 of 3
ML16035A18630 January 201554-PQ-114-001, Technical Justification, Phased Array Ultrasonic Examination of Dry Storage Canister Lid Welds. Part 2 of 3
ML16035A18430 January 2015Document 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-14-10331 December 2014Areva Report ANP-3376NP, Rev. 0, Supplement to Xcel Energy License Amendment Request for Areva Extended Flow Window, Enclosure 2 to L-MT-14-103
ML16005A11025 September 2014Redacted 2014 Decommissioning Cost Analysis for the Prairie Island Nuclear Generating Plant
ML14269A3255 September 2014LTR-BWR-ENG-14-037-NP, Alternate Power Ascension Process.
ML14269A3235 September 2014LTR-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.
ML14204A62318 July 2014Enclosure 3, Attachment - Response to the Us NRC Request for Additional Information Relative to the Monticello Replacement Steam Dryer Accoustic/Structural Ananlyses Set #7
ML14176A96124 June 2014Submittal 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, 2014Fire Barrier
Coatings
Foreign Material Exclusion
ML18100A19022 May 2014Enclosure 8 - Structural Integrity Associates, Inc. Report 130415.403, Revision 2, Assessment of Monticello Spent Fuel Canister Closure Plate Welds Based on Welding Video Records
ML14136A28912 May 201414C4229-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 2014ANP-3304NP, Rev. 0, Areva Response to NRC Follow-Up on Srxb RAI-6: ASME Overpressure Analysis.
ML14069A00511 April 2014Staff Assessment of the Seismic Walkdown Report Supporting Implementation of NTTF Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant AccidentUnanalyzed Condition
Safe Shutdown Earthquake
Fukushima Dai-Ichi
Earthquake
ML14014A26828 February 2014Staff Review and Evaluation of the Fifth 10-Year Interval Inservice Inspection Program PlanIncorporated by reference
Aging Management
ML14064A18625 February 2014Structural Integrity Associates, Inc., Evaluation File No. 1301525.301, Monticello Shroud Support Structure Flaw Evaluation Review and Support Plate Weld Inspection RecommendationsEVT-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 Information31 January 2014Enclosures 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 InformationShutdown Margin
Anticipated operational occurrence
Feedwater Controller Failure
Fuel cladding
Grace period
ML14077A09530 January 2014BWROG-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 8Mission time
ML14077A09031 December 2013BWROG-TP-13-021, Rev. 0, Containment Accident Pressure Committee (344) Task 4 - Operation in Maximum Erosion Rate Zone (Cvic Pump), Attachment 11Mission time
ML13358A37331 December 2013Enclosure 1, Reload 26 Cycle 27 Supplemental Reload Licensing Report, 000N0154-SRLR, Revision 5, Extended Power Uprate and Maximum Extended Load Line Limit PlusShutdown 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 Affidavit20 December 2013Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and AffidavitMELLLA
ML13282A1424 October 2013GE-MNGP-AEP-3304R1, Enclosure 2, GEH Response to Mella + RAI 2
L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages4 October 2013GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages
ML13248A34629 August 2013WCAP-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 1429 August 2013WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14
ML13248A34829 August 2013WCAP-17549-NP, Revision 2 - Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, Enclosure 13Finite Element Analysis
ML13248A34429 August 2013WCAP-17548-NP, Revision 2 - Signal Processing Performed on Monticello MSL Strain Gauge and Rsd Instrumentation Data, Enclosure 10
ML13248A34529 August 2013WCAP-17251-NP, Revision 2 - Monticello Replacement Steam Dryer Four-Line Acoustic Subscale Testing Report, Enclosure 11
ML13200A19231 July 2013ANP-3092(NP), Rev. 0, Monticello Thermal-Hydraulic Design Report for Atrium 10XM Fuel Assemblies.Anticipated operational occurrence
Minimum Critical Power Ratio
MELLLA
ML13200A19631 July 2013ANP-3211(NP), Rev. 1, Monticello EPU LOCA Break Spectrum Analysis for Atrium 10XM Fuel.Stroke time
Fuel cladding
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