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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• ML102460762  + (NSP000062-Licensing Bases for PINGP Turbine Building Internal Flooding)
• ML102460760  + (NSP000063-PINGP Presentation Slides at 2010 Turbine Building Flooding Regulatory Conference)
• ML102460764  + (NSP000064-March 2010 PINGP Management Safety Review Committee Meeting Minutes)
• ML102460761  + (NSP000065-2008 USA PINGP Nuclear Safety Culture Assessment Report)
• ML102460759  + (NSP000066-PINGP Corrective Backlog 2010)
• ML102460765  + (NSP000067-Nuclear Safety Culture/Site Wide Stand Down – Required Briefing by Department Managers January 2009)
• ML102460770  + (NSP000068-PINGP Nuclear Oversight 1st Quarter 2010 Assessment Report)
• ML102460768  + (NSP000069-NRC December 21, 2007 PI&R Report)
• ML102460771  + (NSP000070-PINGP Pride Initiative Focus 2010)
• ML102460769  + (NSP000071-INPO 05-005, Guidelines for Performance Improvement at Nuclear Power Stations)
• L-PI-09-086, NSPM Comments on NRC Safety Evaluation Report with Open Items Related to Renewal of Operating Licenses  + (NSPM Comments on NRC Safety Evaluation Report with Open Items Related to Renewal of Operating Licenses)
• L-PI-10-006, NSPM Comments on NRC Supplemental Environmental Impact Statement Related to Renewal of Operating Licenses  + (NSPM Comments on NRC Supplemental Environmental Impact Statement Related to Renewal of Operating Licenses)
• ML101670198  + (NSPM Letter to the Board Informing That Northern States Power Co. and Prairie Island Indian Community Have Been Unsuccessful in Efforts to Negotiate a Settlement of PIICs Safety Culture Contention)
• ML101200499  + (NSPM Motion Regarding Scope of Disclosures for the PIICs Safety Culture Contention)
• ML090680627  + (NSPM Motion for Protective Order and Non-Disclosure Agreement Regarding Proprietary Documents)
• ML090720857  + (NSPMs Consent Motion for Extension)
• ML090900332  + (NSPMs First Supplemental Disclosure)
• ML102110497  + (NSPMs Initial Statement of Position on Safety Culture Contention)
• ML102110488  + (NSPMs Initial Submittals on Safety Culture Contention)
• ML102250504  + (NSPMs Rebuttal Submittals on Safety Culture Contention)
• ML102420854  + (NSPMs Response in Support of Staffs Motion in Limine Regarding Testimony Filed by the Prairie Island Indian Community)
• L-PI-13-088, NSPMs Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS  + (NSPMs Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident- 1.5 Year Response for CEUS Si)
• ML102460444  + (NSPMs Revised Submittals on Safety Culture Contention)
• ML091200370  + (NSPMs Second Supplemental Disclosure)
• ML102250506  + (NSPMs Supplemental Statement of Position on Safety Culture Contention)

• ML091490607  + (NSPMs Third Supplemental Disclosure)

• ML20045A490  + (NSS Savannah Survey Rept, Conducted on 920324-25)
• ML20003F743  + (NSSS Equipment Qualification Rept)
• ML20024E468  + (NSSS New Loads Design Adequacy Evaluation Final Summary Rept)
• ML20064M898  + (NSSS Panel Design Evaluation for Electrical Separation,Ie & Non-IE Interface. Reactor Protection Sys Motor Generator Set Missile Analysis Encl)
• ML20035G204  + (NSSS Setpoint Evaluation,Protection Sys Channels, Eagle 21 Version,Non-Westinghouse Channels, Rev 0)
• ML20248F421  + (NSSS Stretch Rating-3,083.4 Mwt Licensing Rept)
• ML25262A141  + (NSTS Licensee Govdelivery Message)
• ML21356A002  + (NSTS PRA Statement Landing Page 12-21-2021)
• ML18008A031  + (NTH-TR-01 Decrease in Heat Removal by Secondary Sys)
• ML20134P255  + (NUFREQ-NP:A Digital Computer Code for the Linear Stability Analysis of Boiling Water Nuclear Reactors)
• ML21160A278  + (NUGEQ 5-13-21 Presentation on DG-1361)
• ML22249A229  + (NUGEQ Letter and Comments on IP 71111.21N.03 Commercial Grade Dedication Inspection Procedure)
• ML22270A240  + (NUGEQ Presentation Slides for September 20, 2022 Public Meeting on CGD Inspections)
• ML19028A061  + (NUH-003, Submittal of Updated Final Safety Analysis Report (UFSAR) for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel, Revision 18)
• ML21022A396  + (NUH-003, Updated Final Safety Analysis Report (UFSAR) for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel, Revision 19)
• ML24024A014  + (NUH-003, Updated Final Safety Analysis Report (UFSAR) for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel, Revision 22 and 10 CFR 72.48 Summary Report for the Period 07/28/22 to 01/24/24)
• ML18079A005  + (NUH-003, Updated Final Safety Analysis Report (UFSAR) for the Standardized Nuhoms Horizontal Modular Storage System for Irradiated Nuclear Fuel, Revision 17)
• ML18079A006  + (NUH-003, Updated Final Safety Analysis Report (UFSAR) for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel, Revision 17)
• ML23213A028  + (NUH-003, Updated Final Safety Analysis Report (UFSAR) for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel, Revision 21)
• ML15075A339  + (NUH32PHB-0101, Revision 4, Design Criteria Document (DCD) for the NUHOMS 32PHB System for Storage)
• ML14212A308  + (NUH32PHB-011, Rev 3, Design Report for 32PHB Dsc)
• ML15075A345  + (NUH32PHB-0203, Revision 1, PWR Fuel Rod Accident Side Drop Loading Stress Analysis for NUHOMS 32 Phb System, Non-Proprietary)
• ML15075A346  + (NUH32PHB-0203, Revision 2, PWR Fuel Rod Accident Side Drop Loading Stress Analysis for NUHOMS 32 Phb System, Non-Proprietary)
• ML15075A340  + (NUH32PHB-0400, Revision 2, Benchmarking of the Ansys Model of the OS200FC Transfer Cask)
• ML15075A348  + (NUH32PHB-0401, Revision 2, Thermal Evaluation of NUHOMS 32PHB Transfer Cask for Normal, Off Normal, and Accident Conditions with Force Cooling (Steady State), Non-Proprietary)