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 Issue dateTitleTopic
ML12300A22131 August 2012Attachment 11: BWROG-TP-12-012, Revision 0, Task 4 - Operation in the Maximum Erosion Rate Zone (Cvds Pump)Mission time
ML12300A22231 August 2012Attachment 12: BWROG-TP-12-013, Revision 0, Task 5 - Effects of Non-Condensible Gases on Seals (Cvds Pump)
ML12300A22431 August 2012Attachment 13: BWROG-TP-12-014, Revision 0, Task 6 - Npshr Test Instrument Inaccuracy Effect on Published Results (Cvds Pump)
ML12307A43431 August 2012ANP-3113(NP), Rev. 0, Monticello Nuclear Plant Spent Fuel Storage Pool Criticality Safety Analysis for Atrium 10XM Fuel.
ML13037A20131 January 2013NEDO-33800, Rev. 0, Monticello Nuclear Generating Plant Automatic Depressurization System Bypass Timer Extended Power Uprate.
ML13064A43520 March 2008CA-95-075, Main Steam Line High Flow Setpoint, Attachment 4Zebra Mussel
Large early release frequency
License Renewal
Control of Heavy Loads
Fuel cladding
Fire Protection Program
Environmental Justice
Power Uprate
Affidavit
ML13092A34929 March 2013Enclosure 10 to L-MT-13-029 - WCAP-17548-NP, Revision 1, Signal Processing Performed on Monticello MSL Strain Gauge and Rsd Instrumentation Data.
ML13092A35029 March 2013Enclosure 11 to L-MT-13-029 - WCAP-17251-NP, Revision 1, Monticello Replacement Steam Dryer Four-Line Acoustic Subscale Testing Report.
ML13092A35129 March 2013Enclosure 12 to L-MT-13-029 - WCAP-17252-NP, Revision 3, Acoustic Loads Definition for the Monticello Steam Dryer Replacement Project.
ML13092A35229 March 2013Enclosure 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
ML13191B12826 June 2013NEDO-33820, Revision 0, Monticello Nuclear Generating Plant Upper Shelf Energy Evaluation for Plate C2220 Material for 54 EFPY, Enclosure 5Finite Element Analysis
ML13200A18930 November 2012ANP-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
ML13200A19030 June 2013ANP-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
ML13200A19131 October 2012ANP-3119NP, Rev. 0, Mechanical Design Report for Monticello Atrium 10XM Fuel Assemblies.Anticipated operational occurrence
Finite Element Analysis
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
ML13200A19330 August 2012ANP-3138(NP), Rev. 0, Monticello Improved K-factor Model for Ace/Atrium 10XM Critical Power Correlation.Anticipated operational occurrence
ML13200A19431 May 2013ANP-3215(NP), Rev. 0, Monticello Fuel Transition Cycle 28 Fuel Cycle Design (Epu/Mellla).Shutdown Margin
MELLLA
ML13200A19530 June 2013ANP-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
ML13200A19631 July 2013ANP-3211(NP), Rev. 1, Monticello EPU LOCA Break Spectrum Analysis for Atrium 10XM Fuel.Stroke time
Fuel cladding
ML13200A19731 May 2013ANP-3212(NP), Rev. 0, Monticello EPU LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel.Stroke time
Fuel cladding
ML13200A19931 May 2013ANP-3221NP, Rev. 0, Fuel Rod Thermal-Mechanical Design for Monticello Atrium 10XM Fuel Assemblies, Cycle 28.Anticipated operational occurrence
MELLLA
ML13200A20031 May 2013ANP-3139(NP), Rev. 1, Nuclear Fuel Design Report Monticello Cycle 28 Atrium 10XM Fuel.Shutdown Margin
ML13234A3188 September 2011Enclosure 2 - Revision 0 to Monticello Nuclear Generating Plant Pressure & Temperature Limits Report Up to 54 Effective Full-Power Years.Hydrostatic
Pressure and Temperature Limits Report
MELLLA
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
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
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
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
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.
ML14269A3255 September 2014LTR-BWR-ENG-14-037-NP, Alternate Power Ascension Process.
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
ML16005A11025 September 2014Redacted 2014 Decommissioning Cost Analysis for the Prairie Island Nuclear Generating Plant
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.
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
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
ML19308A0568 October 2019Enclosure 1 - Notification of Changes to the Emergency Response Data System (ERDS)Reactor Vessel Water Level
Met Tower
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
NRC Generic Letter 1979-4525 September 1979NRC Generic Letter 1979-045: Transmittal of Reports Regarding Foreign Reactor Operation ExperiencesBoric Acid
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