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List of results

• ML033290610  + (Rev. 18 to Table of Contents, Rev. 7 to EAL EBD-A, Rev. 2 to EAL EBD-DEF, and Rev. 7 to EAL EBD-H)
• ML23067A179  + (Rev. 18 to Technical Specification Bases, Implemented Change Notice Log)
• ULNRC-06782, Rev. 18 to Technical Specification Bases, List of Effective Sections  + (Rev. 18 to Technical Specification Bases, List of Effective Sections)
• ML23067A177  + (Rev. 18 to Technical Specification Bases Change, Chapter B3, Safety Limits (Sls))
• ML23067A180  + (Rev. 18 to Technical Specification Bases, Chapter 3.1, Reactivity Control Systems)
• ML23067A176  + (Rev. 18 to Technical Specification Bases, Chapter 3.5, Emergency Core Cooling System S(Eccs))
• ML23067A175  + (Rev. 18 to Technical Specification, Bases Change, Chapter 3.3, Instrumentation)
• ML23067A184  + (Rev. 18 to Technical Specification, Bases Change, Chapter 3.4, Reactor Coolant System)
• ML23067A181  + (Rev. 18 to Technical Specification, Bases Change, Chapter B2, Safety Limits (Sls))
• ML23067A185  + (Rev. 18 to Technical Specification, Bases Change, Chapter B 3.9, Refueling Operations)
• ML23067A178  + (Rev. 18 to Technical Specification, Bases Change, Chapter 3.6, Containment Systems)
• ML23067A186  + (Rev. 18 to Technical Specification, Bases Change, Chapter 3.2, Power Distribution Limits)
• ML23067A182  + (Rev. 18 to Technical Specification, Bases Change, Chapter 3.8, Electrical Power Systems)
• ML23067A183  + (Rev. 18 to Technical Specification, Bases Change, Table of Contents)
• ML23067A174  + (Rev. 18 to Technical Specifications, Bases Change, Chapter 3.7, Plant Systems)
• ML061280286  + (Rev. 19 to Section I, Radiological Effluent Monitoring Manual for the Haddam Neck Plant)
• ML061280296  + (Rev. 19 to Section II, Offsite Dose Calculation Manual for the Haddam Neck Plant)
• RIS 2005-20, Rev. 1: Revision to NRC Inspection Manual Part 9900 Technical Guidance, Operability Determinations & Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality or Safety  + (Rev. 1: Revision to NRC Inspection Manual Part 9900 Technical Guidance, Operability Determinations & Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality or Safety)
• RIS 2002-12I, Rev. 1: Transporation of Spent Nuclear Fuel Greater than 100 Grams - NRC Threat Advisory and Protection Measures System  + (Rev. 1: Transporation of Spent Nuclear Fuel Greater than 100 Grams - NRC Threat Advisory and Protection Measures System)
• ML21048A448  + (Rev. 2)
• ML21092A134  + (Rev. 2 ACRS Version)
• ML053010055  + (Rev. 2 to GE Report GENE-0000-0041-1656-01, Test and Analysis Report, Quad Cities New Design Steam Dryer, Dryer 2 Experimental Modal Analysis and Correlation with Finite Element Results)
• ML033360592  + (Rev. 2 to RA-EP-02710, Reentry)
• ML073400092  + (Rev. 2 to SG-CDME-07-7, Condition Monitoring and Operational Assessment: GL-95-05 Alternate Repair Criterion End of Cycle 14, 90 Day Report for Sequoyah Unit 2)
• L-2013-198, Rev. 2 to Seismic Walkdown Report, in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Turkey Point Unit 4  + (Rev. 2 to Seismic Walkdown Report, in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Turkey Point Unit 4)
• ML13213A190  + (Rev. 2 to Seismic Walkdown Report, in Response to the 50.54(f) Information Request Re Fukushima Near-Term Task Force Recommendation 2.3: Seismic for Turkey Point Unit 3)

• ML20097E377  + (Rev. 2 to Technical Requirements Manual)
• ML20097D302  + (Rev. 2 to Technical Requirements Manual)

• ML052450157  + (Rev. 2 to Technical Specification Bases Unit 1 Manual)
• ML15107A412  + (Rev. 2, Criteria and Design Features for Inspection of Water Control Structures Associated with Nuclear Power Plants, Feb. 2016)
• Regulatory Guide 1.187  + (Rev. 2, Guidance for Implementation of 10 CFR 50.59, Changes, Tests and Experiments)
• ML103210345  + (Rev. 2, Nuclear Criticality Safety Standards for Fuels and Material Facilities)
• ML113540207  + (Rev. 2, Preoperational Testing of Emergency Core Cooling Systems for Pressurized-Water Reactors)
• ML23198A311  + (Rev. 2, Qualification of Safety-Related Actuators in Production and Utilization Facilities)
• RIS 2005-20, Rev. 2, Revision to NRC Inspection Manual Part 9900 Technical Guidance, Operability Determinations & Functionality Assessments for Resolution of Degraded Or Nonconforming Conditions Adverse To Quality or Safety  + (Rev. 2, Revision to NRC Inspection Manual Part 9900 Technical Guidance, Operability Determinations & Functionality Assessments for Resolution of Degraded Or Nonconforming Conditions Adverse To Quality or Safety)
• ML15106A484  + (Rev. 2, Revision to NRC Inspection Manual Part 9900 Technical Guidance, Operability Determinations & Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality or Safety)
• ML112580358  + (Rev. 2, Thermal Overload Protection for Electric Motors on Motor-Operated Valves)
• ML24033A311  + (Rev. 2, Updated Acceptance Determination Transmittal for the BWRX-300 Steel-Composite Containment Vessel and Reactor Building Structural Design LTR)
• ML24033A312  + (Rev. 2, Updated NRC 898 - Acceptance Determination for the BWRX-300 Steel-Composite Containment Vessel and Reactor Building Structural Design LTR)
• ML071290353  + (Rev. 20 to Offsite Dose Calculation Manual)
• ML20323A141  + (Rev. 20 to Updated Final Safety Analysis Report)
• ML20323A139  + (Rev. 20 to Updated Final Safety Analysis Report, Chapter 2, Appendix 2A)
• ML20323A145  + (Rev. 20 to Updated Final Safety Analysis Report, Chapter 2, Appendix 2B)
• ML20323A142  + (Rev. 20 to Updated Final Safety Analysis Report, Chapter 2, Appendix 2C)
• ML20323A144  + (Rev. 20 to Updated Final Safety Analysis Report, Chapter 2, Appendix 2D)
• ML20323A140  + (Rev. 20 to Updated Final Safety Analysis Report, Chapter 2, Appendix 2E)
• ML20323A148  + (Rev. 20 to Updated Final Safety Analysis Report, Chapter 2, Appendix 2F)
• ML20323A155  + (Rev. 20 to Updated Final Safety Analysis Report, Chapter 3, Appendix 3I)
• ML20323A120  + (Rev. 20 to Updated Final Safety Analysis Report, Chapter 4, Reactor)
• ML20323A122  + (Rev. 20 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses)
• ML20323A119  + (Rev. 20 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems)
• ML20323A161  + (Rev. 20 to Updated Final Safety Analysis Report, Chapter 3, Figures, Part 3)