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List of results

• ML15188A383  + (NUREG-1930, Supplement 2, Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Plant, Units 2 and 3.)
• ML093170451  + (NUREG-1930, Vol 1, Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3)
• ML093170671  + (NUREG-1930, Vol. 2, Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3)
• ML093170780  + (NUREG-1931, (1:2) Cover - Page 3-94, Safety Evaluation Report Related to the License Renewal of Susquehanna Steam Electric Station, Units 1 and 2)
• NUREG-1931, (2:2) Page 3-95 - End, Safety Evaluation Report Related to the License Renewal of Susquehanna Steam Electric Station, Units 1 and 2  + (NUREG-1931, (2:2) Page 3-95 - End, Safety Evaluation Report Related to the License Renewal of Susquehanna Steam Electric Station, Units 1 and 2)
• NUREG-1933, Containing the Atom, Nuclear Regulation in a Changing Environment, 1962-1971  + (NUREG-1933: Containing the Atom, Nuclear Regulation in a Changing Environment, 1962-1971)
• NUREG-1943 Volume 1, Environmental Impact Statement for Combined Licenses (Cols) for Comanche Peak Nuclear Power Plant, Units 3 and 4, (Final Report)  + (NUREG-1943 Vol. 1, Environmental Impact Statement for Combined Licenses (Cols) for Comanche Peak Nuclear Power Plant, Units 3 and 4, (Final Report))
• NUREG-1944, Safety Evaluation Report Related to the License Renewal of Cooper Nuclear Station  + (NUREG-1944 Safety Evaluation Report Related to the License Renewal of Cooper Nuclear Station)
• NUREG-1953, Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models - Surry and Peach Bottom  + (NUREG-1953 Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models - Surry and Peach Bottom)
• NUREG-1958, (1:2) Cover-Section 2, Safety Evaluation Report Related to the License Renewal of Kewaunee Power Station  + (NUREG-1958, (1:2) Cover-Section 2, Safety Evaluation Report Related to the License Renewal of Kewaunee Power Station)
• ML110340148  + (NUREG-1958, (2:2) Section 3-End, Safety Evaluation Report Related to the License Renewal of Kewaunee Power Station.)
• NUREG-1960, Supp 1, Safety Evaluation Report Related to the License Renewal of Prairie Island Nuclear Generating Plants, Unit 1 and 2  + (NUREG-1960 Supp 1, Safety Evaluation Report Related to the License Renewal of Prairie Island Nuclear Generating Plants, Unit 1 and 2)
• ML11235A622  + (NUREG-1960, Safety Evaluation Report Related to the License Renewal of Prairie Island Nuclear Generating Plant, Units 1 and 2.)
• NUREG-1961, Safety Evaluation Report Related to the License Renewal of Palo Verde Nuclear Generating Station, Units 1,2 and 3  + (NUREG-1961 Safety Evaluation Report Related to the License Renewal of Palo Verde Nuclear Generating Station, Units 1,2 and 3)
• NUREG-2101, Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station  + (NUREG-2101 Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station)
• NUREG-2102, Safety Evaluation Report Related to the License Renewal of Hope Creek Generating Station  + (NUREG-2102 Safety Evaluation Report Related to the License Renewal of Hope Creek Generating Station)
• NUREG-2103, Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Westinghouse AP1000 Pressurized Water Reactors Final Report  + (NUREG-2103, Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Westinghouse AP1000 Pressurized Water Reactors Final Report)
• NUREG-2123, V1 Safety Evaluation Report Related to the License Renewal of Columbia Generating Station  + (NUREG-2123 V1 Safety Evaluation Report Related to the License Renewal of Columbia Generating Station)
• NUREG-2123 Volume 2, Safety Evaluation Report Related to the License Renewal of Columbia Generating Station  + (NUREG-2123, Vol 2 Safety Evaluation Report Related to the License Renewal of Columbia Generating Station)
• NUREG-2152, Q & a  + (NUREG-2152 Q & a)
• NUREG-2155, Rev 2, Implementation Guidance for 10 CFR Part 37, Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material  + (NUREG-2155, Rev 2, Implementation Guidance for 10 CFR Part 37, Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material)
• NUREG-2158, Final Draft Guidance, Acceptable Standard Format and Content for the Material Control and Accounting Plan Required for Low-Enriched Uranium Enrichment Facilities  + (NUREG-2158, Final Draft Guidance, Acceptable Standard Format and Content for the Material Control and Accounting Plan Required for Low-Enriched Uranium Enrichment Facilities)
• NUREG-2159, Revision 1, Final, Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required for Special Nuclear Material of Moderate Strategic Significance  + (NUREG-2159, Revision 1, Final, Acceptable Standard Format and Content for the Fundamental Nuclear Material Control Plan Required for Special Nuclear Material of Moderate Strategic Significance)
• ML15344A400  + (NUREG-2163 - Technical Basis for Regulatory Guidance on the Alternate Pressurized Thermal Shock Rule)
• NUREG-2172, Safety Evaluation Report Related to the License Renewal of Callaway Plant, Unit 1  + (NUREG-2172, Safety Evaluation Report Related to the License Renewal of Callaway Plant, Unit 1)

• NUREG-2173, Rev. 1 - Tribal Protocol Manual - July 2018  + (NUREG-2173, Rev. 1 - Tribal Protocol Manual - July 2018)

• ML19162A406  + (NUREG-2178 DFC, Vol. 2, Revised, Refining and Characterizing Heat Release Rates from Electrical Enclosures During Fire (RACHELLE-FIRE) - Volume 2: Fire Modeling Guidance for Electrical Cabinets, Electric Motors, Indoor Dry Transformers, and)
• ML19087A210  + (NUREG-2178, Vol. 2, Draft Refining and Charactering Heat Release Rate from Electrical Enclosures During Fire (RACHELLE-FIRE)- Volume 2: Fire Modeling Guidance for Electrical Cabinets, Electric Motors, Indoor Dry Transformers and the Main Co)
• NUREG-2178 Volume 2, Refining and Characterizing Heat Release Rates from Electrical Enclosures During Fire. (RACHELLE-FIRE), Volume 2: Fire Modeling Guidance for Electrical. Cabinets, Electric Motors, Indoor Dry Transformers, and the Main  + (NUREG-2178, Volume 2, Refining and Characterizing Heat Release Rates from Electrical Enclosures During Fire. (RACHELLE-FIRE), Volume 2: Fire Modeling Guidance for Electrical. Cabinets, Electric Motors, Indoor Dry Transformers, and the Main)
• ML24143A010  + (NUREG-2180, Supplement 1, Determining the Effectiveness, Limitations, and Operator Response for Very Early Warning Fire Detection Systems in Nuclear Facilities – Update to Event Tree Parameters (Alpha and Pi) and Integration of NUREG-2230 M)
• ML15187A206  + (NUREG-2181 Safety Evaluation Report Related to the License Renewal of Sequoyah Nuclear Plant Units 1 and 2 Docket Numbers 50-327 and 50-328 Tennessee Valley Authority)
• NUREG-2181, Supplement. 1, Safety Evaluation Report Related to the License Renewal of Sequoyah Nuclear Plant Units 1 and 2  + (NUREG-2181, Supplement. 1, Safety Evaluation Report Related to the License Renewal of Sequoyah Nuclear Plant Units 1 and 2)
• NUREG-2183, Supplement 1, Environmental Impact Statement Related to the Operating License for the Shine Medical Isotope Production Facility Final Report  + (NUREG-2183, Supplement 1, Environmental Impact Statement Related to the Operating License for the Shine Medical Isotope Production Facility Final Report)
• ML16021A423  + (NUREG-2187, Vol. 1, Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models-Byron Unit 1. Chapters 1 to 8, Appendices a to C)
• ML16022A062  + (NUREG-2187, Vol. 2, Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models-Byron Unit 1. Appendices D to G)
• NUREG-2189, Safety Evaluation Report - Related to Shine Medical Technologies, Inc. Construction Permit Application for a Medical Radioisotope Production Facility  + (NUREG-2189, Safety Evaluation Report - Related to Shine Medical Technologies, Inc. Construction Permit Application for a Medical Radioisotope Production Facility)
• NUREG-2190, V2 - Safety Evaluation Report, Related to the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2  + (NUREG-2190 V2 - Safety Evaluation Report, Related to the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2)
• NUREG-2190 Volume 1, Safety Evaluation Report, Related to the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2  + (NUREG-2190, Vol 1, Safety Evaluation Report, Related to the License Renewal of Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2)
• NUREG-2191 Volume 1, Rev. 1, Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Final Report  + (NUREG-2191, Vol. 1, Rev. 1, Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Final Report)
• NUREG-2191 Volume 2, Rev. 1, Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Final Report  + (NUREG-2191, Vol. 2, Rev. 1, Generic Aging Lessons Learned for Subsequent License Renewal (GALL-SLR) Final Report)
• NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report  + (NUREG-2192, Rev. 1, Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants Final Report)
• NUREG-2193, Suppl 1, Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station. Docket Number 50-346, Firstenergy Nuclear Operating Company  + (NUREG-2193, Suppl 1, Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station. Docket Number 50-346, Firstenergy Nuclear Operating Company)
• NUREG-2193 Volume 1, Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station Docket Number 50-346 Firstenergy Nuclear Operating Company Sections 1 to 3  + (NUREG-2193, Vol. 1, Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station Docket Number 50-346 Firstenergy Nuclear Operating Company Sections 1 to 3)
• NUREG-2193 Volume 2, Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station. Docket Number 50-346, Firstenergy Nuclear Operating Company Sections 4 to 6 Appendices  + (NUREG-2193, Vol. 2, Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station. Docket Number 50-346, Firstenergy Nuclear Operating Company Sections 4 to 6 Appendices)
• NUREG-2194 Volume 1, Rev. 1, Standard Technical Specifications, Westinghouse Advanced Passive 1000 (AP1000) Plants, Volume 1: Specifications  + (NUREG-2194, Vol. 1, Rev. 1, Standard Technical Specifications, Westinghouse Advanced Passive 1000 (AP1000) Plants, Volume 1: Specifications)
• NUREG-2194 Volume 2, Rev. 1, Standard Technical Specifications, Westinghouse Advanced Passive 1000 (AP1000) Plants, Volume 2: Bases  + (NUREG-2194, Vol. 2, Rev. 1, Standard Technical Specifications, Westinghouse Advanced Passive 1000 (AP1000) Plants, Volume 2: Bases)
• ML18122A012  + (NUREG-2195, Consequential SGTR Analysis for Westinghouse and Combustion Engineering Plants with Thermally Treated Alloy 600 and 690 Steam Generator Tubes)
• NUREG-2198, Figures Final  + (NUREG-2198 - Figures Final)
• ML22035A173  + (NUREG-2199, Vol. 3, Testing the Integrated Human Event Analysis System for Nuclear Power Plant Internal Events At-Power Application (IDHEAS AT-POWER))
• NUREG-2205, Safety Evaluation Report - Related to the License Renewal of LaSalle County Station, Units 1 and 2 - Docket Nos. 50-373 and 50-374 - Exelon Generation Company, Llc  + (NUREG-2205, Safety Evaluation Report - Related to the License Renewal of LaSalle County Station, Units 1 and 2 - Docket Nos. 50-373 and 50-374 - Exelon Generation Company, Llc)
• NUREG-2206, Technical Basis for the Containment Protection and Release Reduction Rulemaking for Boiling Water Reactors with Mark I and Mark II Containments  + (NUREG-2206 - Technical Basis for the Containment Protection and Release Reduction Rulemaking for Boiling Water Reactors with Mark I and Mark II Containments)