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 Issue dateTitle
ML23006A14819 December 20220 to Updated Safety Analysis Report, Section 14, Plant Safety Analysis
ML23006A15519 December 20220 to Updated Safety Analysis Report, Section 3, Reactor
L-MT-21-044, License Amendment Request: Application to Adopt Advanced Framatome Methodologies29 July 2021License Amendment Request: Application to Adopt Advanced Framatome Methodologies
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, Affidavit
ML21070A11111 February 20218 to Updated Safety Analysis Report, Section 3, Reactor
ML21070A11511 February 20218 to Updated Safety Analysis Report, Section 14, Plant Safety Analysis
L-MT-20-023, License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR3 November 2020License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR
L-MT-19-049, Technical Specification Bases8 November 2019Technical Specification Bases
ML19074A26922 April 2019Non-Proprietary - Issuance of Amendment Revision to Technical Specifications 2.1.2 Safety Limit Minimum Critical Power Ratio
L-MT-18-060, License Amendment Request: Revise the Safety Limit Minimum Critical Power Ratio in Reactor Core Safety Limit 2.1.112 November 2018License Amendment Request: Revise the Safety Limit Minimum Critical Power Ratio in Reactor Core Safety Limit 2.1.1
ML16271A09228 September 2016Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: October 11, 2016
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+).
ML15154A4775 June 2015Safety Evaluation Regarding License Amendment No. 188 Associated with Areva Atrium 10XM Fuel Transition (TAC No. MF2479) - (Redacted)
ML15072A1415 June 2015Issuance of Amendment No. 188 Regarding Transition to Areva Atrium 10XM Fuel and Areva Safety Analysis Methods
ML15110A28015 April 2015Operating License and Technical Specifications
ML15022A65326 January 2015Biweekly Sholly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: February 3, 2015
L-MT-14-044, ANP-3135NP, Applicability of Areva BWR Methods to Extended Flow Window for Monticello.30 April 2014ANP-3135NP, Applicability of Areva BWR Methods to Extended Flow Window for Monticello.
L-MT-14-033, Areva Atrium 10XM Fuel Transition - Supplement to Describe the Effect of Local Power Range Monitor Surveillance Grace Period29 April 2014Areva Atrium 10XM Fuel Transition - Supplement to Describe the Effect of Local Power Range Monitor Surveillance Grace Period
ML14087A01328 March 2014Safety Evaluation Regarding the Maximum Extended Load Line Limit Plus (Mellla+) Review (non-proprietary Version)
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 Plus
ML13343A0069 December 2013Extended Power Uprate Final Safety Evaluation (non-proprietary) Redacted
ML13261A14612 September 2013MNGP Technical Specification Bases Updating Instructions
ML13200A19030 June 2013ANP-3224NP, Rev. 2, Applicability of Areva Np BWR Methods to Monticello.
ML13200A19530 June 2013ANP-3213(NP), Rev. 1, Monticello Fuel Transition Cycle 28 Reload Licensing Analysis (Epu/Mellla).
L-MT-13-053, 0000-0146-5423-SRLR, Rev. 1, Supplemental Reload Licensing Report for Monticello, Reload 26 Cycle 27 Extended Power Uprate (EPU)31 January 20130000-0146-5423-SRLR, Rev. 1, Supplemental Reload Licensing Report for Monticello, Reload 26 Cycle 27 Extended Power Uprate (EPU)
ML13200A18930 November 2012ANP-2637, Rev. 4, Boiling Water Reactor Licensing Methodology Compendium.
L-MT-12-054, Enclosure 3, Global Nuclear Fuel, 0000-0092-5740-SRLR, Rev. 3, Supplemental Reload Licensing Report for Monticello, Reload 25 Cycle 26, Maximum Extended Load Line Limit Plus (Mellla+).31 January 2012Enclosure 3, Global Nuclear Fuel, 0000-0092-5740-SRLR, Rev. 3, Supplemental Reload Licensing Report for Monticello, Reload 25 Cycle 26, Maximum Extended Load Line Limit Plus (Mellla+).
L-MT-10-072, Extended Power Uprate: Updates to Docketed Information21 December 2010Extended Power Uprate: Updates to Docketed Information
L-MT-10-055, License Amendment Request: Revise the Minimum Critical Power Ratio Safety Limit in Reactor Core Safety Limit 2.1.1.217 September 2010License Amendment Request: Revise the Minimum Critical Power Ratio Safety Limit in Reactor Core Safety Limit 2.1.1.2
L-MT-09-017, Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 200919 March 2009Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 2009
ML0832301115 November 2008Monticello Nuclear Generating Plant, License Amendment Request: Extended Power Uprate
L-MT-08-049, Submittal of Response to Requests for Additional Information for License Amendment Request for Power Range Neutron Monitoring System Upgrade16 September 2008Submittal of Response to Requests for Additional Information for License Amendment Request for Power Range Neutron Monitoring System Upgrade
ML08101019331 March 2008Monticello, License Amendment Request: Extended Power Uprate
L-MT-04-068, Submittal of Revision 21 to the Updated Safety Analysis Report22 December 2004Submittal of Revision 21 to the Updated Safety Analysis Report
L-MT-03-085, Technical Specification Bases Pages Changes11 November 2003Technical Specification Bases Pages Changes
L-MT-03-039, Revised Monticello Nuclear Generating Plant Technical Specifications Bases Pages22 May 2003Revised Monticello Nuclear Generating Plant Technical Specifications Bases Pages
L-MT-03-033, Submittal of Core Operating Limits Report for Cycle 2214 May 2003Submittal of Core Operating Limits Report for Cycle 22
ML03003048019 December 2002Technical Specification Bases Pages
ML02275043519 September 2002Technical Specification Bases Pages
ML02220042429 July 2002Technical Specification Bases Change 128a Correct Drywell to Suppression Chamber Vaccum Breaker Indicating Light Description
ML20202H6864 December 1997Rev 1 to Application for Amend to License DPR-22,increasing Plant Max Power Level from 1670 Mwt to 1775 Mwt
ML20116G89126 July 1996Application for Amend to License DPR-22,proposing Increase Max Reactor Core Power Level by 6.3% to 1,775 Mwt from Current 1,670 Mwt.Request Also Changes TSs Based on Power Rerate Evaluations
ML20101K85429 February 1996Application of 'Regional Exclusion w/Flow-Biased APRM Neutron Flux Scram' Stability Solution (Option I-D) to Monticello Nuclear Generating Plant
ML20087F30428 February 1995Non-proprietary Application of 'Regional Exclusion w/Flow- Biased APRM Neutron Flux Scram' Stability Solution (Option I-D) to Monticello Npp
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