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MONTHYEARL-MT-16-024, Flood Hazard Reevaluation Report2016-04-21021 April 2016 Flood Hazard Reevaluation Report Project stage: Request ML16145A1792016-05-12012 May 2016 Response to Post-Fukushima Near-Term Task Force (Ntif) Recommendation 2.1. Flooding - Flood Hazard Reevaluation Report Project stage: Request ML16152A1252016-06-0707 June 2016 Nuclear Regulatory Commission Plan for the Audit of Northern States Power Company Minnesota'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1-Flooding for Monticello Nuclear Generating Plan Project stage: Other ML16248A0032016-09-16016 September 2016 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation Project stage: Other ML16245A7202016-09-16016 September 2016 MSFHI Tables Final 8-31-2016 Project stage: Other ML16323A3292016-09-23023 September 2016 Flood Hazard Reevaluation Report - Response to Requested Information Project stage: Other L-MT-17-015, Mitigating Strategies Flood Hazard Assessment (MSA) Submittal2017-03-28028 March 2017 Mitigating Strategies Flood Hazard Assessment (MSA) Submittal Project stage: Other L-MT-17-024, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Focused Evaluation2017-04-0303 April 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Focused Evaluation Project stage: Request ML17096A4432017-04-18018 April 2017 Audit Report Relating to the Flood Hazard Reevaluation Report Project stage: Other ML17104A3102017-04-24024 April 2017 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation Project stage: Other 2016-09-23
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MONTHYEARL-MT-21-068, 2021 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462021-12-15015 December 2021 2021 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-18-071, Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462018-12-12012 December 2018 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 ML16245A7202016-09-16016 September 2016 MSFHI Tables Final 8-31-2016 ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T L-MT-14-054, Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462014-06-17017 June 2014 Thirty-Day Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 ML14141A3992014-05-27027 May 2014 Correction Letter for License Amendment No. 180 Maximum Extended Load Line Limit Plus (Mellla+) L-MT-13-034, Extended Power Uprate (Epu): Response to Request for Additional Information - Electrical Engineering Branch (TAC MD9990), Page 58 of 96 Through End2013-04-10010 April 2013 Extended Power Uprate (Epu): Response to Request for Additional Information - Electrical Engineering Branch (TAC MD9990), Page 58 of 96 Through End ML13105A1882013-04-10010 April 2013 Monticello Extended Power Uprate (Epu): Response to Request for Additional Information - Electrical Engineering Branch (TAC MD9990), Page 1 of 96 Through Page 57 of 96 L-MT-08-058, Thirty (30) Day Notification Pursuant to 10CFR72.212, Conditions of General License Issued Under 6 72.210, for Storage of Spent Fuel2008-10-16016 October 2008 Thirty (30) Day Notification Pursuant to 10CFR72.212, Conditions of General License Issued Under 6 72.210, for Storage of Spent Fuel ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0612402692006-06-0505 June 2006 Attachment 6 - Table R - Relocated Specifications for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues ML0612402662006-06-0505 June 2006 Attachment 5 - Table La - Removed Details for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues ML0612402642006-06-0505 June 2006 Attachment 4 - Table L - Less Restrictive Changes for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues ML0612402592006-06-0505 June 2006 Attachment 3 - Table M - More Restrictive Changes for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues ML0612402552006-06-0505 June 2006 Attachment 2 - Table a - Administrative Changes for Monticello, Amendment 146 for the Conversion to the Improved Technical Specifications with Beyond-Scope Issues ML0613901442005-08-0404 August 2005 Web References for Monticello Dseis: Socioeconomics ML0520105032005-08-0101 August 2005 Xcel Energy - Migratory Bird Reporting Form and Flow Chart, Revised 2003 ML0520104582005-04-11011 April 2005 NCDC Listing of Nonattainment Status for Each County by Year, as of April 11, 2005 ML0434501802003-12-11011 December 2003 NMC Program Health Status Fleet Program at a Glance 2021-12-15
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Monticello Nuclear Generating Plant, Unit 1 Table 1. Current Design Basis Flood Hazards for Use in the MSA Mechanism Stillwater Waves/ Design Basis Reference Elevation Runup Hazard Elevation Local Intense Precipitation Not included Not included Not included FHRR Section 1.5, 2.1.3 & Table 5 in DB in DB in DB Streams and Rivers Mississippi River Probable 939.2 ft Not 939.2 ft FHRR Section 1.5.1 Maximum Precipitation NGVD29 applicable NGVD29 Failure of Dams and Onsite Water Control/Storage Structures Not included Not included Not included FHRR Section 1.5 in DB in DB in DB Storm Surge Not included Not included Not included FHRR Section 1.5 in DB in DB in DB Seiche Not included Not included Not included FHRR Section 1.5 in DB in DB in DB Tsunami Not included Not included Not included FHRR Section 1.5 in DB in DB in DB Ice-Induced Flooding No Impact No Impact No Impact FHRR Section 1.5.2 on the Site on the Site on the Site Identified Identified Identified Channel Migrations/Diversions Not included Not included Not included FHRR Section 1.5 in DB in DB in DB Note 1: Reported values are rounded to the nearest one-tenth of a foot.
Monticello Nuclear Generating Plant, Unit 1 Table 2. Reevaluated Flood Hazards for Flood-Causing Mechanisms for Use in the MSA Mechanism Stillwater Waves/ Reevaluated Reference Elevation Runup Hazard Elevation Local Intense Precipitation 935.8 ft Minimal 935.8 ft FHRR Section 2.1.2 & Tables 5 and 6 NGVD29 NGVD29 Note 1: The licensee is expected to develop flood event duration parameters and applicable flood associated effects to conduct the MSA. The staff will evaluate the flood event duration parameters (including warning time and period of inundation) and flood associated effects during its review of the MSA.
Note 2: Reevaluated hazard mechanisms bounded by the current design basis (see Table 1) are not included in this table Note 3: Reported values are rounded to the nearest one-tenth of a foot.