Search by property
Jump to navigation
Jump to search
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
- ML22049A114 + (Rev. 16 to Updated Final Safety Analysis Report, Revs. 25 & 24 to Fire Protection Reports, Vol. 1 & 2)
- ML20323A171 + (Rev. 162 to the Technical Requirements Manual)
- ML20323A170 + (Rev. 17 to Fire Protection Safe Shutdown Capability)
- ML103050193 + (Rev. 18 to Emergency Plan Implementing Procedure, IP-EP-250, Emergency Operations Facility)
- ML061280268 + (Rev. 18 to Section I, Radiological Effluent Monitoring Manual for the Haddam Neck Plant)
- ML061280276 + (Rev. 18 to Section II, Offsite Dose Calculation Manual for the Haddam Neck Plant)
- 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)