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Technical Specification, Bases Change, Emergency Preparedness-Emergency Plan  and Letter type:L

Environmental Protection Agency +, Federal Emergency Management Agency +  and Federal Aviation Administration +

ARP-6-C-13 +  and ARP-4-A-12 +

Boron +, Iodine +, Oxygen +, Hydrogen +  and Lead +

10 CFR 50.72 +, 10 CFR 50 +, 10 CFR 50 Appendix E +, 10 CFR 72.32 +, 10 CFR 50.54#q +, 10 CFR 50.54#q5 +, 10 CFR 50.47#b +, 10 CFR 50.109#a4ii +  and 10 CFR 72.44#f +

SECY 91-283 +, ND-95208 +  and ND-95209 +

05000263  +  and 00263  +

Technical Support Center +  and Emergency Operations Facility +

Minnesota +, Xcel Energy +  and Neal M +

NRC Generic Letter 88-17, Loss of Decay Heat Removal +  and NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +

L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change +, L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change +, L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change +, L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change +, L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change +, L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change +, L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change +, L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change +, L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change +, L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change +, L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change +, L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change +, L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change +, L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change +  and L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change +

ND-95209 +  and ND-95208 +

NEI 12-02 +, NEI 03-12 +  and NEI 99-01, SNC Slides - SNC Fleet - Pre-Submittal Meeting - LAR for EAL Scheme Change to NEI 99-01 Rev 7 +

NUREG-1228 +, NUREG-1567 +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, NUREG-1449, Summary of 930826-27 Meeting W/Og to Discuss Status of Activities to Implement Tsip & Development of Lps Ts.Meeting Attendees & Agenda Encl +, NUREG-1140, Forwards Draft Technical Position on Design of Erosion Protection Covers for Stabilization of U Mill Tailings Sites & NUREG-1140.W/o Encls +, NUREG-1022, Rev. 3, Supplement 2, Event Report Guidelines 10 CFR 50.72(b)(3)(ii) and 10 CFR 50.73(a)(2)(ii) Final Report +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

AOP +, CH +, Emergency Operating Procedure +  and EP-FAQ-2018-04 +

Regulatory Guide 1.1 +, Regulatory Guide 1.155 +, Regulatory Guide 1.3 +, Regulatory Guide 1.101 +, Regulatory Guide 1.2 +  and Regulatory Guide 2.1 +

RIS 2003-18, Use of Nuclear Energy Institute (NEI) 99-01, Methodology for Development of Emergency Action Levels, Revision 4, Dated January 2003 +  and RIS 2007-02, Clarification of NRC Guidance for Emergency Notifications During Quickly Changing Events +

Manual Scram +  and Automatic Scram +

Washington +  and Minnesota +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Reactor Core Isolation Cooling +, Primary containment +, Safety Parameter Display System +, Reactor Pressure Vessel +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Standby Liquid Control +, Circulating Water System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +  and Main Steam +

TS-3.6.4.1 +, TS-3.8.1 +, TS-3.6.1.1 +, TS-3.8.7 +, TS-3.8.5 +, TS-3.8.4 +, TS-3.8.2 +, TS-3.4.4 +, TS-3.7.6 +, TS-3.6.4.2 +, TS-3.6.4.3 +, TS-3.4.6 +, TS-3.10.1 +, TS-5.4.1 +, TS-3.9 +, TS-1.2 +  and TS-1.2.7 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Safe Shutdown +, Time of Discovery +, High winds +, Reactor Vessel Water Level +, Ultimate heat sink +, Fire Barrier +, Safe Shutdown Earthquake +, Post Accident Monitoring +, Hydrostatic +, Probabilistic Risk Assessment +, Operating Basis Earthquake +, Operator Manual Action +, Design basis earthquake +, Loss of Offsite Power +, Spent Fuel Pool Instrumentation +, Severe Accident Management Guideline +, Containment high range radiation monitor +, Safeguards Contingency Plan +, Battery sizing +, Earthquake +, Fuel cladding +, Pressure Boundary Leakage +, Fire Protection Program +, Grace period +, Backfit +, Unidentified leakage +, Failure to Scram +, Operational leakage +  and Spill +