[미국법] 미국 NRC 규제지침(Regulatory Guides, RG) 정리

지난 시간에는 미국 연방법 CFR과 관련하여 알아보았다.

 

https://madso.tistory.com/191

원자력 관련 미국 연방법(Code of Fedral Regulations, CFR) 체계 정리

 

이번 시간에는 미연방법에 이어서, 가장 실무에 자주 사용되는  U.S. NRC 규제지침에 대하여 알아보자.

 

 

 

 

 

미국 원자력규제위원회 U.S. Nuclear Regulatory Commission (U.S. NRC)는

 

미연방법 중 에너지분야 10 CFR에서의 Chapter 1 (Part 1~ 199)을 전담하고 있다.

 

NRC는 허가(License) 소지자/신청자를 위해 상기 연방법을 이해하고, 준수하는데 도움이 되는 규제지침 시리즈를 제공한다.

 

규제지침 시리즈는 허가 소지자 및 신청자에게 NRC 규정의 특정 부분을 이행하는 방법, NRC 직원이 특정 문제(Specific Problems)또는 가상 사고(Postulated Accidents)를 평가하는 데 사용하는 기법, 그리고 허가 또는 면허 신청 검토에 필요한 데이터에 대한 지침을 제공한다.

 

https://www.nrc.gov/reading-rm/doc-collections/reg-guides/index

 

 

규제지침 시리즈는 10개 분야(Division로 구성되어있다.

1. Power Reactors
2. Research and Test Reactors
3. Fuels and Materials Facilities
4. Environmental and Siting
5. Materials and Plant Protection
6. Products
7. Transportation
8. Occupational Health
9. Antitrust and Financial Review
10. General

 

1. Power Reactors

RG NO	RG TITLE	Rev.No
1.1	Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal System Pumps (Safety Guide 1)	WITH DRAWN
1.2	Thermal Shock to Reactor Pressure Vessels (Safety Guide 2)	WITH DRAWN
1.3	Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors	WITH DRAWN
1.4	Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors	WITH DRAWN
1.5	Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam Line Break Accident for Boiling Water Reactors (Safety Guide 5)	WITH DRAWN
1.6	Independence Between Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems (Safety Guide 6)	0
1.7	Control of Combustible Gas Concentrations in Containment	3
1.8	Qualification and Training of Personnel for Nuclear Power Plants	4
1.9	Application and Testing of Safety-Related Diesel Generators in Nuclear Power Plants	5 (DG)
1.10	Mechanical (Cadweld) Splices in Reinforcing Bars of Category I Concrete Structures	WITH DRAWN
1.11	Instrument Lines Penetrating Primary Reactor Containment	1
1.12	Nuclear Power Plant Instrumentation for Earthquakes	3
1.13	Spent Fuel Storage Facility Design Basis	2
1.14	Reactor Coolant Pump Flywheel Integrity	1
1.15	Testing of Reinforcing Bars for Category I Concrete Structures	WITH DRAWN
1.16	Reporting of Operating Information -- Appendix A Technical Specifications (for Comment)	WITH DRAWN
1.17	Protection of Nuclear Power Plants Against Industrial Sabotage	WITH DRAWN
1.18	Structural Acceptance Test for Concrete Primary Reactor	WITH DRAWN
1.19	Nondestructive Examination of Primary Containment Liner Welds	WITH DRAWN
1.20	Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing	4
1.21	Measuring, Evaluating, and Reporting Radioactive Material in Liquid and Gaseous Effluents and Solid Waste	3
1.22	Periodic Testing of Protection System Actuation Functions (Safety Guide 22)	0
1.23	Meteorological Monitoring Programs for Nuclear Power Plants	1
1.24	Assumptions Used for Evaluating the Potential Radiological Consequences of a Pressurized Water Reactor Radioactive Gas Storage Tank Failure (Safety Guide 24)	0
1.25	Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors (Safety Guide 25)	WITH DRAWN
1.26	Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants	6
1.27	Ultimate Heat Sink for Nuclear Power Plants	3
1.28	Quality Assurance Program Criteria (Design and Construction)	5
1.29	Seismic Design Classification for Nuclear Power Plants	6
1.30	Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment (Safety Guide 30)	1
1.31	Control of Ferrite Content in Stainless Steel Weld Metal	4
1.32	Criteria for Power Systems for Nuclear Power Plants	4
1.33	Quality Assurance Program Requirements (Operation)	3
1.34	Control of Electroslag Weld Properties	1
1.35	Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments	WITH DRAWN
1.35.1	Determining Prestressing Forces for Inspection of Prestressed Concrete Containments	0
1.36	Nonmetallic Thermal Insulation for Austenitic Stainless Steel	1
1.37	Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants	WITH DRAWN
1.38	Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants	WITH DRAWN
1.39	Housekeeping Requirements for Water-Cooled Nuclear Power Plants	WITH DRAWN
1.40	Qualification of Continuous Duty Safety-Related Motors for Nuclear Power Plants	1
1.41	Preoperational Testing of Redundant On-Site Electric Power Systems To Verify Proper Load Group Assignments	WITH DRAWN
1.42	Interim Licensing policy on as low as Practicable for Gaseous Radiodine Releases from Light-Water-Cooled Nuclear Power Reactors.	WITH DRAWN
1.43	Control of Stainless Steel Weld Cladding of Low-Alloy Steel Components	1
1.44	Control of the Processing and Use of Stainless Steel	1
1.45	Guidance on Monitoring and Responding to Reactor Coolant System Leakage	1
1.46	Protection Against Pipe Whip Inside Containment	WITH DRAWN
1.47	Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems	1
1.48	Design Limit and Loading Combinations for Seismic Category I Fluid System Components	WITH DRAWN
1.49	Power Levels of Nuclear Power Plants	WITH DRAWN
1.50	Control of Preheat Temperature for Welding of Low-Alloy Steel	1
1.51	Inservice Inspection of ASME Code Class 2 and 3 Nuclear Power Plants components	WITH DRAWN
1.52	Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Post-Accident Engineered-Safety-Feature Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants	4
1.53	Application of the Single-Failure Criterion to Safety Systems	2
1.54	Service Level I, II, and III Protective Coatings Applied to Nuclear Power Plants	3
1.55	Concrete Placement in Category I Structures	WITH DRAWN
1.56	Maintenance of Water Purity in Boiling Water Reactors (for Comment)	WITH DRAWN
1.57	Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components	2
1.58	Qualification of Nuclear Power Plant Inspection, Examination and Testing Personnel	WITH DRAWN
1.59	Design Basis Floods for Nuclear Power Plants	3 (DG)
1.60	Design Response Spectra for Seismic Design of Nuclear Power Plants	2
1.61	Damping Values for Seismic Design of Nuclear Power Plants	2
1.62	Manual Initiation of Protective Actions	1
1.63	Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants	3
1.64	Quality Assurance Requirements for the Design of Nuclear Power plants	WITH DRAWN
1.65	Materials and Inspections for Reactor Vessel Closure Studs	1
1.66	Nondestructive Examination of Tubular Products	WITH DRAWN
1.67	Installation of Overpressure Protection Devices	WITH DRAWN
1.68	Initial Test Programs for Water-Cooled Nuclear Power Plants	4
1.68.1	Initial Test Program of Condensate and Feedwater Systems for Light-Water Reactors	2
1.68.2	Initial Startup Test Program To Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants	2
1.68.3	Preoperational Testing of Instrument and Control Air Systems	1
1.69	Concrete Radiation Shields and Generic Shield Testing for Nuclear Power Plants	1
1.70	Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition)	3
1.71	Welder Qualification for Areas of Limited Accessibility	1
1.72	Spray Pond Piping Made from Fiberglass-Reinforced Thermosetting Resin	2
1.73	Qualification Tests for Safety-Related Actuators in Nuclear Power Plants	2
1.74	Quality Assurance Terms and Definitions	WITH DRAWN
1.75	Physical Independence of Electric Systems	3
1.76	Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants	1
1.77	Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors	WITH DRAWN
1.78	Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release	2
1.79	Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors	2
1.79.1	Initial Test Program of Emergency Core Cooling Systems for New Boiling-Water Reactors	0
1.8	Preoperational Testing of Instrument Air Systems	WITH DRAWN
1.81	Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants	1
1.82	Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident	5
1.83	Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes	WITH DRAWN
1.84	Design, Fabrication, and Materials Code Case Acceptability, ASME Section III	40
1.85	Materials code case Acceptability - - ASME Section III, Division 1	WITH DRAWN
1.86	Termination of Operating Licenses for Nuclear Reactors	WITH DRAWN
1.87	Acceptability of ASME Code Section III, Division 5, 'High Temperature Reactors'	3
1.88	Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records	WITH DRAWN
1.89	Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants	2
1.90	Inservice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons	2
1.91	Evaluations of Explosions Postulated To Occur on Transportation Routes Near Nuclear Power Plants	3
1.92	Combining Modal Responses and Spatial Components in Seismic Response Analysis	3
1.93	Availability of Electric Power Sources	1
1.94	Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants	WITH DRAWN
1.95	Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release	WITH DRAWN
1.96	Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants	1
1.97	Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants	5
1.98	Assumptions Used for Evaluating the Potential Radiological Consequences of a Radioactive Offgas System Failure in a Boiling Water Reactor (for Comment)	0
1.99	Radiation Embrittlement of Reactor Vessel Materials	2
1.100	Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants	4
1.101	Emergency Planning and Preparedness for Nuclear Power Reactors	7
1.102	Flood Protection for Nuclear Power Plants	1
1.103	Post-tensioned Prestressing Systems for Concrete Reactor and Containment	WITH DRAWN
1.104	Overhead Crane Handling Systems for Nuclear Power Plants	WITH DRAWN
1.105	Setpoints for Safety-Related Instrumentation	4
1.106	Thermal Overload Protection for Electric Motors on Motor-Operated Valves	2
1.107	Qualifications for Cement Grouting for Prestressing Tendons in Containment Structures	2
1.108	Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants	WITH DRAWN
1.109	Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I	1
1.110	Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear Power Reactors	1
1.111	Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors	1
1.112	Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors	1
1.113	Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I	1
1.114	Guidance to Operators at the Controls and to Senior Operators in the Control Room of a Nuclear Power Unit	3
1.115	Protection Against Turbine Missiles	2
1.116	Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems	WITH DRAWN
1.117	Protection Against Extreme Wind Events and Missiles for Nuclear Power Plants	2
1.118	Periodic Testing of Electric Power and Protection Systems	3
1.119	Surveillance Program for New Fuel Assembly Designs	WITH DRAWN
1.120	Fire Protection Guidelines for Nuclear Power Plants	WITH DRAWN
1.121	Bases for Plugging Degraded PWR Steam Generator Tubes (for Comment)	0
1.122	Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components	1
1.123	Quality Assurance Requirements for Control of Procurement of Items and Service for Nuclear Power Plants	WITH DRAWN
1.124	Service Limits and Loading Combinations for Class 1 Linear-Type Supports	3
1.125	Physical Models for Design and Operation of Hydraulic Structures and Systems for Nuclear Power Plants	2
1.126	An Acceptable Model and Related Statistical Methods for the Analysis of Fuel Densification	2
1.127	Inspection of Water-Control Structures Associated with Nuclear Power Plants	2
1.128	Installation Design and Installation of Vented Lead-Acid Storage Batteries for Nuclear Power Plants	3
1.129	Maintenance, Testing, and Replacement of Vented Lead-Acid Storage Batteries for Nuclear Power Plants	4
1.130	Service Limits and Loading Combinations for Class 1 Plate-and-Shell-Type Component Supports	3
1.131	Qualification Tests of Electric Cables, Field Splices, and Connections for Light-Water-Cooled Nuclear Power Plants (for Comment)	WITH DRAWN
1.132	Geologic and Geotechnical Site Characterization Investigations for Nuclear Power Plants	3
1.133	Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors	1
1.134	Medical Assessment of Licensed Operators or Applicants for Operator Licenses at Nuclear Power Plants	4
1.135	Normal Water Level and Discharge at Nuclear Power Plants (for Comment)	WITH DRAWN
1.136	Design Limits, Loading Combinations, Materials, Construction, and Testing of Concrete Containments	4
1.137	Fuel Oil Systems for Emergency Power Supplies	2
1.138	Laboratory Investigations of Soils and Rocks for Engineering Analysis and Design of Nuclear Power Plants	3
1.139	Guidance for Residual Heat Removal (for Comment)	WITH DRAWN
1.140	Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Normal Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants	3
1.141	Containment Isolation Provisions for Fluid Systems	1
1.142	Safety-Related Concrete Structures for Nuclear Power Plants (Other than Reactor Vessels and Containments)	3
1.143	Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants	2
1.144	Auditing of Quality Assurance Programs for Nuclear Power Plants	WITH DRAWN
1.145	Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants	1
1.146	Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants	WITH DRAWN
1.147	Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1	21
1.148	Functional Specification for Active Valve Assemblies in Systems Important to Safety in Nuclear Power Plants	WITH DRAWN
1.149	Nuclear Power Plant Simulation Facilities for Use in Operator Training, License Examinations, and Applicant Experience Requirements	4
1.150	Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations	WITH DRAWN
1.151	Instrument Sensing Lines	2
1.152	Criteria for Use of Computers in Safety Systems of Nuclear Power Plants	4
1.153	Criteria for Safety Systems (12/85)	DG (2)
1.154	Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors	WITH DRAWN
1.155	Station Blackout	0
1.156	Qualification of Connection Assemblies for Nuclear Power Plants	2
1.157	Best-Estimate Calculations of Emergency Core Cooling System Performance	0
1.158	Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants	1
1.159	Assuring the Availability of Funds for Decommissioning Nuclear Reactors	2
1.160	Monitoring the Effectiveness of Maintenance at Nuclear Power Plants	4
1.161	Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 Ft-Lb	0
1.162	Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels	0
1.163	Performance-Based Containment Leak-Test Program	1
1.164	Dedication of Commercial-Grade Items for Use in Nuclear Power Plants	1
1.165	Identification and Characterization of Seismic Sources and Determination of Safe Shutdown Earthquake Ground Motion	WITH DRAWN
1.166	Pre-Earthquake Planning, Shutdown, and Restart of a Nuclear Power Plant Following an Earthquake	1
1.167	Restart of a Nuclear Power Plant Shut Down by a Seismic Event	WITH DRAWN
1.168	Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants	2
1.169	Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear Power Plants	1
1.170	Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants	1
1.171	Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants	1
1.172	Software Requirement Specifications for Digital Computer Software and Complex Electronics Used in Safety Systems of Nuclear Power Plants	1
1.173	Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Systems of Nuclear Power Plants	1
1.174	An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis	3
1.175	Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing	1
1.176	An Approach for Plant-Specific, Risk-Informed Decisionmaking: Graded Quality Assurance	WITH DRAWN
1.177	Plant-Specific, Risk-Informed Decisionmaking:  Technical Specifications	2
1.178	An Approach for Plant-Specific Risk-Informed Decisionmaking for Inservice Inspection of Piping	2
1.179	Standard Format and Content of License Termination Plans for Nuclear Power Reactors	2
1.180	Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems	2
1.181	Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e)	0
1.182	Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants	WITH DRAWN
1.183	Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors	1
1.184	Decommissioning of Nuclear Power Reactors	1
1.185	Standard Format and Content for Post-Shutdown Decommissioning Activities Report	1
1.186	Guidance and Examples for Identifying 10 CFR 50.2 Design Bases	0
1.187	Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments	3
1.188	Standard Format and Content for Applications To Renew Nuclear Power Plant Operating Licenses	2
1.189	Fire Protection for Nuclear Power Plants	5
1.190	Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence	0
1.191	Fire Protection Program for Nuclear Power Plants During Decommissioning and Permanent Shutdown	1
1.192	Operation and Maintenance Code Case Acceptability, ASME OM Code	5
1.193	ASME Code Cases Not Approved for Use	8
1.194	Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants	0
1.195	Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors	0
1.196	Control Room Habitability at Light-Water Nuclear Power Reactors	1
1.197	Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors	0
1.198	Procedures and Criteria for Assessing Seismic Soil Liquefaction at Nuclear Power Plant Sites	0
1.199	Anchoring Components and Structural Supports in Concrete	1
1.200	Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities	3
1.201	Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance	1
1.202	Standard Format and Content of Decommissioning Cost Estimates for Nuclear Power Reactors	0
1.203	Transient and Accident Analysis Methods	0
1.204	Guidelines for Lightning Protection of Nuclear Power Plants	1
1.205	Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants	2
1.206	Applications for Nuclear Power Plants	1
1.207	Guidelines for Evaluating Fatigue Analyses Incorporating the Life Reduction of Metal Components Due to the Effects of the Light-Water Reactor Environment for New Reactors	1
1.208	A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion	0
1.209	Guidelines for Environmental Qualification of Safety-Related Computer-Based Instrumentation and Control Systems in Nuclear Power Plants	0
1.210	Qualification of Safety-Related Battery Chargers and Inverters for Nuclear Power Plants	1
1.211	Qualification of Safety-Related Cables and Field Splices for Nuclear Power Plants	DG (1)
1.212	Sizing of Large Lead-Acid Storage Batteries	2
1.213	Qualification of Safety-Related Motor Control Centers for Nuclear Power Plants	0
1.214	Response Strategies for Potential Aircraft Threats (OUO-SRI)	1
1.215	"Guidance for ITAAC Closure Under 10 CFR Part 52."	2
1.216	Containment Structural Integrity Evaluation for Internal Pressure Loadings Above Design-Basis Pressure	0
1.217	Guidance for the Assessment of Beyond-Design-Basis Aircraft Impacts	0
1.218	Condition Monitoring Techniques for Electric Cables Used in Nuclear Power Plants	0
1.219	Guidance on Making Changes to Emergency Plans for Nuclear Power Reactors	1
1.220	-	-
1.221	Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants	0
1.222	Conducting Periodic Testing for Breakaway Oxidation Behavior	DG
1.223	Testing for Postquench Ductility	DG
1.224	Establishing Analytical for Zirconium Based Alloy Cladding	DG
1.225	-	-
1.226	Flexible Mitigation Strategies for Beyond-Design-Basis Events	0
1.227	Wide-Range Spent Fuel Pool Level Instrumentation	0
1.228	Integrated Response Capabilities for Beyond-Design Basis Events	DG
1.229	Alternative Risk-Informed Approach for Addressing the Effects of Debris on Post Accident Long-Term Core Cooling	DG
1.230	Regulatory Guidance on the Alternate Pressurized Thermal Shock Rule	0
1.231	Acceptance of Commercial-Grade Design and Analysis Computer Programs Used in Safety-Related Applications for Nuclear Power Plants	0
1.232	Developing Principal Design Criteria for Non-Light Water Reactors	0
1.233	Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light Water Reactors	0
1.234	Evaluating Deviations and Reporting Defects and Noncompliance Under 10 CFR Part 21	1
1.235	Emergency Planning for Decommissioning Power Reactors	DG
1.236	Pressurized-Water Reactor Control Rod Ejection and Boiling-Water Reactor Control Rod Drop Accidents	0
1.237	Guidance for Changes During Construction for New Nuclear Power Plants Being Constructed Under a Combined License Referencing a Certified Design Under 10 CFR Part 52	0
1.238	Criteria for The Protection of Safety-Related (Class 1E) Power Systems and Equipment for Nuclear Power Plants	0
1.239	Licensee Actions to Address Nonconservative Technical Specifications	0
1.240	Fresh and Spent Fuel Pool Criticality Analysis	0
1.241	-	-
1.242	Performance-Based Emergency Preparedness for Small Modular Reactors, Non-Light-Water Reactors, and Non-Power Production or Utilization Facilities	0
1.243	Safety-Related Steel Structures and Steel-Plate Composite (SC) Walls for other than Reactor Vessels and Containments	0
1.244	Control of Heavy Loads at Nuclear Facilities	0
1.245	Preparing Probabilistic Fracture Mechanics (PFM) Submittals	DG (1)
1.246	Acceptability of ASME Code, Section XI, Division 2, Requirements for RIM Programs for NPPs, for Non-LWRs	0
1.247	TRIAL - Acceptability of Probabilistic Risk Assessment Results for Non-Light Water Reactor Risk-Informed Activities	TRIAL
1.248	Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Production and Utilization Facilities	0
1.249	Use of ARCON Methodology For Calculation Of Accident-Related Offsite Atmospheric Dispersion Factors	0
1.250	Dedication of Commercial-Grade Digital I&C Items for Use in Nuclear power Plants	0
1.253	Guidance for a Technology-Inclusive Content of Application Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors	0
1.256	Guidance for Assessment of Flooding Hazards Due to Water Control Structure Failures and Incidents	DG
1.257	Qualification of Fiber-Optic Cables, Connections, and Optical Fiber Splices for Use in Safety Systems for Production and Utilization Facilities	0
1.261	Guidance for Technology-Inclusive Risk Informed Change Evaluation, "Technology Inclusive Risk Informed Change Evaluation" (based on NEI 22-05)	DG
1.262	ASME Code Cases Approved for Use Without Conditions	0

 

 

2. Research and Test Reactors

RG NO	RG TITLE	Rev.No
2.1	Shield Test Program for Evaluation of Installed Biological Shielding in Research and Training Reactors	WITH DRAWN
2.2	Development of Technical Specifications for Experiments in Research Reactors	0
2.3	Quality Verification for Plate-Type Uranium-Aluminum Fuel Elements for Use in Research Reactors	2
2.4	Review of Experiments for Research Reactors	WITH DRAWN
2.5	Quality Assurance Program Requirements for Research and Test Reactors	1
2.6	Emergency Planning for Research and Test Reactors	2
2.7	Preparation of Updated Final Safety Analysis Reports for Non-Power Production or Utilization Facilities	0
2.8	Guidance for Implementation of 10 CFR 50.59, “Changes, Tests, And Experiments,” At Non-Power Production or Utilization Facilities	0

 

3. Fuels and Materials Facilities

RG NO	RG TITLE	Rev.No
3.1	Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material	WITH DRAWN
3.2	Efficiency Testing of Air-Cleaning Systems Containing Devices for Removal of Particles	WITH DRAWN
3.3	Quality Assurance Program Requirements for Fuel Reprocessing Plants and for Plutonium Processing and Fuel Fabrication Plants	1
3.4	Nuclear Criticality Safety in Operations with Fissionable Materials at Fuels and Materials Facilities	WITH DRAWN
3.5	Standard Format and Content of License Applications for Uranium Mills (for Comment)	1
3.6	Content of Technical Specifications for Fuel Reprocessing Plants	0
3.7	Monitoring of Combustible Gases and Vapors in Plutonium Processing and Fuel Fabrication Plants	1
3.8	Preparation of Environmental Reports for Uranium Mills	2
3.9	Concrete Radiation Shields	WITH DRAWN
3.10	Liquid Waste Treatment System Design Guide for Plutonium Processing and Fuel Fabrication Plants	0
3.11	Design, Construction, and Inspection of Embankment Retention Systems at Uranium Recovery Facilities	3
3.11.1	Operational Inspection and Surveillance of Embankment Retention Systems for Uranium Mill Tailings	WITH DRAWN
3.12	General Design Guide for Ventilation Systems of Plutonium Processing and Fuel Fabrication Plants	1
3.13	Design, Construction, and Inspection of Embankment Retention Systems at Fuel Cycle Facilities	1
3.14	Seismic Design Classification for Plutonium Processing and Fuel Fabrication Plants	0
3.15	Standard Format and Content of License Applications for Storage Only of Unirradiated Power Reactor Fuel and Associated Radioactive Material	2
3.16	General Fire Protection Guide for Plutonium Processing and Fuel Fabrication Plants	1
3.17	Earthquake Instrumentation for Fuel Reprocessing Plants	0
3.18	Confinement Barriers and Systems for Fuel Reprocessing Plants	0
3.19	Reporting of Operating Information for Fuel Reprocessing Plants	0
3.20	Process Offgas Systems for Fuel Reprocessing Plants	0
3.21	Quality Assurance Requirements for Protective Coatings Applied to Fuel Reprocessing and to Plutonium Processing and Fuel Fabrication Plants	0
3.22	Periodic Testing of Fuel Reprocessing Plant Protection System Actuation Functions	0
3.23	Stabilization of Uranium-Thorium Milling Waste Retention Systems	WITH DRAWN
3.24	Guidance on the License Application, Siting, Design and Plant Protection for an Independent Spent Fuel Storage Installation	WITH DRAWN
3.25	Standard Format and Content of Safety Analysis Reports for Uranium Enrichment Facilities	WITH DRAWN
3.26	Standard Format and Content of Safety Analysis Reports for Fuel Reprocessing Plants	0
3.27	Nondestructive Examination of Welds in the Liners of Concrete Barriers in Fuel Reprocessing Plants	1
3.28	Welder Qualification for Welding in Areas of Limited Accessibility in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants	WITH DRAWN
3.29	Preheat and Interpass Temperature Control for the Welding of Low-Alloy Steel for Use in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants	WITH DRAWN
3.30	Selection, Application, and Inspection of Protective Coatings (Paints) for Fuel Reprocessing Plants	O-R
3.31	Emergency Water Supply Systems for Fuel Reprocessing Plants	O-R
3.32	General Design Guide for Ventilation Systems for Fuel Reprocessing Plants (for Comment)	0
3.33	Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Fuel Reprocessing Plant	WITH DRAWN
3.34	Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Uranium Fuel Fabrication Plant	WITH DRAWN
3.35	Assumptions Used for Evaluating the Potential Radiological Consequences of Accidental Nuclear Criticality in a Plutonium Processing and Fuel Fabrication Plant	WITH DRAWN
3.36	Nondestructive Examination of Tubular Products for Use in Fuel Reprocessing Plants and in Plutonium Plants	WITH DRAWN
3.37	Guidance for Avoiding Intergranular Corrosion and Stress Corrosion in Austenitic Stainless Steel Components of Fuel Reprocessing Plants (for Comment)	0
3.38	General Fire Protection Guide for Fuel Reprocessing Plants (for Comment)	WITH DRAWN
3.39	Standard Format and Content of License Applications for Plutonium Processing and Fuel Fabrication Plants	1
3.40	Design Basis Floods for Fuel Reprocessing Plants and for Plutonium Processing and Fuel Fabrication Plants	1
3.41	Nuclear Criticality in Operations with Fissionable Materials at Fuels and Materials Facilities	WITH DRAWN
3.42	Emergency Planning for Fuel Cycle Facilities and Plants Licensed Under 10 CFR Parts 50 and 70	WITH DRAWN
3.43	Nuclear Criticality Safety in the Storage of Fissile Materials	WITH DRAWN
3.44	Standard Format and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation (Water-Basin Type)	WITH DRAWN
3.45	Nuclear Criticality Safety for the Steel-Pipe Intersections Containing Aqueous Solutions of Fissile Materials	WITH DRAWN
3.46	Standard Format and Content of License Applications, Including Environmental Reports, for In Situ Uranium Solution Mining	0
3.47	Nuclear Criticality Control and Safety of Homogeneous Plutonium-Uranium Fuel Mixtures Outside Reactors	WITH DRAWN
3.48	Standard Format and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation or Monitored Retrievable Storage Installation (Dry Storage)	1
3.49	Design of an Independent Spent Fuel Storage Installation (Water-Basin Type)	WITH DRAWN
3.50	Standard Format and Content for a Specific License Application for An Independent Spent Fuel Storage Installation or Monitored Retrievable Storage Facility	2
3.51	Calculational Models for Estimating Radiation Doses to Man from Airborne Radioactive Materials Resulting from Uranium Milling Operations	0
3.52	Standard Format and Content for the Health and Safety Sections of License Renewal Applications for Uranium Processing and Fuel Fabrication	2
3.53	Applicability of Existing Regulatory Guides to the Design and Operation of an Independent Spent Fuel Storage Installation	WITH DRAWN
3.54	Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation	4
3.55	Standard Format and Content for the Health and Safety Sections of License Renewal Applications for Uranium Hexafluoride Production	0
3.56	General Guidance for Designing, Testing, Operating, and Maintaining Emission Control Devices at Uranium Mills	0
3.57	Administrative Practices for Nuclear Criticality Safety at Fuels and Materials Facilities	WITH DRAWN
3.58	Criticality Safety for Handling, Storing, and Transporting LWR Fuel at Fuels and Materials Facilities	WITH DRAWN
3.59	Methods for Estimating Radioactive and Toxic Airborne Source Terms for Uranium Milling Operations	0
3.60	Design of an Independent Spent Fuel Storage Installation (Dry Storage)	0
3.61	Standard Format and Content for a Topical Safety Analysis Report for a Spent Fuel Dry Storage Cask	0
3.62	Standard Format and Content for the Safety Analysis Report for Onsite Storage of Spent Fuel Storage Casks	0
3.63	Onsite Meteorological Measurement Program for Uranium Recovery Facilities -- Data Acquisition and Reporting	0
3.64	Calculation of Radon Flux Attenuation by Earthen Uranium Mill Tailings Covers	0
3.65	Standard Format and Content of Decommissioning Plans for Materials Licensees	WITH DRAWN
3.66	Standard Format and Content of Financial Assurance Mechanisms	1
3.67	Standard Format and Content for Emergency Plans for Fuel Cycle and Materials Facilities	1
3.68	Nuclear Criticality Safety Training	WITH DRAWN
3.69	Topical Guidelines for the Licensing Support Network	1
3.70	Use of Fixed Neutron Absorbers at Fuels and Materials Facilities	WITH DRAWN
3.71	Nuclear Criticality Safety Standards for Nuclear Materials Outside Reactor Cores	3
3.72	Guidance for Implementation of 10 CFR 72.48, Changes, Tests, and Experiments	1
3.73	Site Evaluations and Design Earthquake Ground Motion for Dry Cask Independent Spent Fuel Storage and Monitored Retrievable Storage Installations	0
3.74	Guidance for Fuel Cycle Facility Change Processes	0
3.75	Corrective Action Programs for Fuel Cycle Facilities	0
3.76	Implementation of Aging Management Requirements for Spent Fuel Storage Renewals	0
3.77	Weather Related Administrative Controls at Independent Spent Fuel Storage Installation	0
3.78	Acceptable ASME Section XI Inservice Inspection Code Cases for 10 CFR Part 72	0

 

4. Environmental and Siting

RG NO	RG TITLE	Rev.No
4.1	Radiological Environmental Monitoring for Nuclear Power Plants	2
4.2	Preparation of Environmental Reports for Nuclear Power Stations	3
4.2S1	Supplement 1 to Regulatory Guide 4.2, Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications	2
4.3	Measurements of Radionuclides in the Environment, Analysis of I-131 in Milk	WITH DRAWN
4.4	Reporting Procedure for Mathematical Models Selected To Predict Heated Effluent Dispersion in Natural Water Bodies	WITH DRAWN
4.5	Measurements of Radionuclides in the Environment--Sampling and Analysis of Plutonium in Soil	WITH DRAWN
4.6	Measurements of Radionuclides in the Environment-- Strontium-89 and Strontium-90 Analyses	WITH DRAWN
4.7	General Site Suitability Criteria for Nuclear Power Stations	4
4.8	Environmental Technical Specifications for Nuclear Power Plants	WITH DRAWN
4.9	Preparation of Environmental Reports for Commercial Uranium Enrichment Facilities	1
4.10	Irreversible and Irretrievable Commitment of Material Resources	WITH DRAWN
4.11	Terrestrial Environmental Studies for Nuclear Power Stations	2
4.12	-	-
4.13	Performance, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications	2
4.14	Radiological Effluent and Environmental Monitoring at Uranium Mills	1
4.15	Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination) -- Effluent Streams and the Environment	2
4.16	Monitoring and Reporting Radioactivity in Releases of Radioactive Materials in Liquid and Gaseous Effluents from Nuclear Fuel Processing and Fabrication Plants and Uranium Hexafluoride Production Plants	2
4.17	Standard Format and Content of Site Characterization Plans for High-Level-Waste Geologic Repositories	1
4.18	Standard Format and Content of Environmental Reports for Near-Surface Disposal of Radioactive Waste	0
4.19	Guidance for Selecting Sites for Near-Surface Disposal of Low-Level Radioactive Waste	0
4.20	Constraint on Releases of Airborne Radioactive Materials to the Environment for Licensees other than Power Reactors	1
4.21	Minimization of Contamination and Radioactive Waste Generation:  Life-Cycle Planning	0
4.22	Decommissioning Planning During Operations	0
4.23	-	-
4.24	Aquatic Environmental Studies for Nuclear Power Stations	0
4.25	Assessment of Abnormal Radionuclide Discharges in Ground Water to the Unrestricted Area at Nuclear Power Plant Sites	0
4.26	Volcanic Hazards Assessment for Proposed Nuclear Power Reactor Sites	1
4.27	Use Of Plant Parameter Envelope In Early Site Permit Applications	0
4.28	Use of ARCON Methodology For Calculation Of Accident-Related Offsite Atmospheric Dispersion Factors	Cxl
4.29	Graded Approach to Site Characterization	DG

5. Materials and Plant Protection

RG NO	RG TITLE	Rev.No
5.1	Serial Numbering of Fuel Assembles for Light-Water-Cooled Nuclear Power Reactors	WITH DRAWN
5.2	Classification of Unirradiated Plutonium and Uranium Scrap	WITH DRAWN
5.3	Statistical Terminology and Notation for Special Nuclear Materials Control and Accountability	WITH DRAWN
5.4	Standard Analytical Methods for the Measurement of Uranium Tetrafluoride (UF4) and Uranium Hexafluoride (UF6)	0
5.5	Standard Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets	0
5.6	Standard Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Plutonium Dioxide Powerders and Pellets and Nuclear-Grade Mixed Oxides	WITH DRAWN
5.7	Entry/Exit Control for Protected Areas, Vital Areas, and Material Access Areas	1
5.8	Design Considerations for Minimizing Residual Holdup of Special Nuclear Material in Drying and Fluidized Bed Operations	1
5.9	Guidelines for Germanium Spectroscopy Systems for Measurement of Special Nuclear Material	2
5.10	Selection and Use of Pressure-Sensitive Seals on Containers for Onsite Storage of Special Nuclear Material	WITH DRAWN
5.11	Nondestructive Assay of Special Nuclear Material Contained in Scrap and Waste	1
5.12	General Use of Locks in the Protection and Control of Facilities and Special Nuclear Materials, Classified Matter, and Safeguards Information	1
5.13	Conduct of Nuclear Material Physical Inventories	WITH DRAWN
5.14	Use of Observation (Visual Surveillance) Techniques in Material Access Areas	WITH DRAWN
5.15	Tamper-Indicating Seals for the Protection and Control of Special Nuclear Material	WITH DRAWN
5.16	Standard Methods for Chemical, Mass Spectrometric, Spectrochemical Nuclear and Radiochemical Analysis of Nuclear-Grade Plutonium Nitrate Solutions and Plutonium Metal	WITH DRAWN
5.17	Truck Identification Markings	WITH DRAWN
5.18	Limit of Error Concepts and Principles of Calculation in Nuclear Materials Control	WITH DRAWN
5.19	Methods for the Accountability of Plutonium Nitrate Solutions	WITH DRAWN
5.20	Training, Equipping, and Qualifying of Guards and Watchmen	0
5.21	Nondestructive Uranium-235 Enrichment Assay by Gamma Ray Spectrometry	1
5.22	Assessment of the Assumption of Normality (Employing Individual Observed Values)	WITH DRAWN
5.23	In Situ Assay of Plutonium Residual Holdup	1
5.24	Analysis and Use of Process Data for the Protection of Special Nuclear Material	WITH DRAWN
5.25	Design Considerations for Minimizing Residual Holdup of Special Nuclear Material in Equipment for Wet Process Operations	0
5.26	Selection of Material Balance Areas and Item Control Areas	1
5.27	Special Nuclear Material Doorway Monitors	1
5.28	Evaluation of Shipper-Receiver Differences in the Transfer of Special Nuclear Materials	WITH DRAWN
5.29	Nuclear Material Control systems for Nuclear Power Plants	2
5.30	Materials Protection Contingency Measures for Uranium and Plutonium Fuel Manufacturing Plants	WITH DRAWN
5.31	Specially Designed Vehicle with Armed Guards for Road Shipment of Special Nuclear Material	1
5.32	Communication with Transport Vehicles	WITH DRAWN
5.33	Statistical Evaluation of Material Unaccounted For	WITH DRAWN
5.34	Nondestructive Assay for Plutonium in Scrap Material by Spontaneous Fission Detection	1
5.35	Calorimetric Assay of Plutonium	WITH DRAWN
5.36	Recommended Practice for Dealing with Outlying Observations	WITH DRAWN
5.37	In Situ Assay of Enriched Uranium Residual Holdup	1
5.38	Nondestructive Assay of High-Enrichment Uranium Fuel Plates by Gamma Ray Spectrometry	1
5.39	General Methods for the Analysis of Uranyl Nitrate Solutions for Assay, Isotopic Distribution, and Impurity Determinations	0
5.40	Methods for the Accountability of Plutonium Dioxide Powder	WITH DRAWN
5.41	Shipping, Receiving, and Internal Transfer of Special Nuclear Material At Fuel Cycle Facilities	0
5.42	Design Considerations for Minimizing Residual Holdup of Special Nuclear Material in Equipment for Dry Process Operations	0
5.43	Plant Security Force Duties	WITH DRAWN
5.44	Perimeter Intrusion Alarm Systems	DG
5.45	Standard Form and Content for the Special Nuclear Material Control and Accounting Section of a Special Nuclear Material License Application (including That for a Uranium Enrichment Facility)	WITH DRAWN
5.46	-	-
5.47	Control and Accountability of Plutonium in Waste Material	WITH DRAWN
5.48	Design Considerations--Systems for Measuring the Mass of Liquids	0
5.49	Internal Transfers of Special Nuclear Material	WITH DRAWN
5.50	-	-
5.51	Management Review of Nuclear Material Control and Accounting Systems	1
5.52	Standard Format and Content of a Licensee Physical Protection Plan for Strategic Special Nuclear Material at Fixed Sites (Other than Nuclear Power Plants)	3
5.53	Qualification, Calibration, and Error Estimation Methods for Nondestructive Assay	1
5.54	Standard Format and Content of Safeguards Contingency Plans for Nuclear Power Plants (SGI)	1
5.55	Standard Format and Content of Safeguards Contingency Plans for Fuel Cycle Facilities	0
5.56	Standard Format and Content of Safeguards Contingency Plans for Transportation	WITH DRAWN
5.57	Shipping and Receiving Control of Strategic Special Nuclear Material	WITH DRAWN
5.58	Considerations for Establishing Traceability of Special Nuclear Material Accounting Measurements	1
5.59	Standard Format and Content for a Licensee Physical Security Plan for the Protection of Special Nuclear Material of Moderate or Low Strategic Significance	1
5.60	Standard Format and Content of a Licensee Physical Protection Plan for Strategic Special Nuclear Material in Transit	0
5.61	Intent and Scope of the Physical Protection Upgrade Rule Requirements for Fixed Sites	WITH DRAWN
5.62	Reporting of Safeguards Events	3
5.63	Physical Protection for Transient Shipments	0
5.64	-	-
5.65	Vital Area Access Controls, Protection of Physical Security Equipment, and Key and Lock Controls	WITH DRAWN
5.66	Access Authorization Program for Nuclear Power Plants	2
5.67	Material Control and Accounting for Uranium Enrichment Facilities Authorized To Produce Special Nuclear Material of Low Strategic Significance	WITH DRAWN
5.68	Protection Against Malevolent Use of Vehicles at Nuclear Power Plants	WITH DRAWN
5.69	Guidance for the Application of Radiological Sabotage Design-Basis Threat in the Design, Development and Implementation of a Physical Security Program that Meets 10 CFR 73.55 Requirements (SGI)	1
5.70	Guidance for the Application of the Theft and Diversion Design-Basis Treat in the Design Development, and Implementation of a Physical Security Program that Meets CFR 73.45 and 73.46 (Classified)	1
5.71	Cyber Security Programs for Nuclear Power Reactors	1
5.72	-	-
5.73	Fatigue Management for Nuclear Power Plant Personnel	0
5.74	Managing the Safety/Security Interface	1
5.75	Training and Qualification of Security Personnel at Nuclear Power Reactor Facilities	1
5.76	Physical Protection Programs at Nuclear Power Reactors (SGI)	1
5.77	Insider Mitigation Program	1
5.78	Physical Protection of Mixed Oxide Fuels in Nuclear Power Plants (SGI)	0
5.79	Protection of Safeguards Information	0
5.80	Pressure-Sensitive And Tamper-Indicating Device Seals For Material Control And Accounting Of Special Nuclear Material	0
5.81	Target Set Identification and Development for Nuclear Power Reactors (OUO-SRI)	DG (2)
5.82	-	-
5.83	Cyber Security Event Notifications	1
5.84	Fitness-For-Duty Programs at New Reactor Construction Sites	0
5.85	Security Performance (Adversary) Characteristics for Physical Security Programs for 10 CFR Part 72 Licensees (OUO-SGI)	DG
5.86	Applying for Enhanced Weapons Authority, Applying for Preemption Authority, and Performing Firearms Background Checks Under 10 CFR Part 73	1
5.87	Suspicious Activity Reporting Under 10 CFR Part 73	1
5.88	Physical Inventories and Material Balances at Fuel Cycle Facilities	0
5.89	Fitness-for-Duty Programs for Commercial Power Reactor and Category I Special Nuclear Material Licensees	0
5.90	Guidance for Alternative Physical Security Requirements for Small Modular Reactors and Non-Light-Water Reactors	DG
5.91	Cyber Security Programs for Nuclear Fuel Cycle Facilities	DG
5.92	Guidance On Controlling Changes to The Security Plan for Nuclear Power Reactors	DG
5.93	Technology-Inclusive Determination of Source Terms	CANCELLED
5.94	Fitness-For-Duty Programs for Commercial Nuclear Plants and Manufacturing Facilities Licensed Under 10 CFR Part 53	DG
5.95	Access Authorization Program for Commercial Nuclear Plants	DG
5.96	Establishing Cybersecurity Programs for Commercial Nuclear Plants Licensed Under 10 CFR Part 53	DG
5.97	Guidance for Technology Inclusive Requirements for Physical Protection of Licensed Activities at Commercial Nuclear Plants	DG
5.98	SAT-based Training Program Review Guidance	DG
5.99	Fatigue Management for Nuclear Power Plant Personnel at Commercial Nuclear Plants Licensed Under 10 CFR Part 53	DG
5.100	Security Plan Changes that Utilize Modeling and Simulation Tools	DG

 

6. Products

RG NO	RG TITLE	Rev.No
6.1	Leak Testing Radioactive Brachytherapy Sources	WITH DRAWN
6.2	Integrity and Test Specifications for Selected Brachytherapy Sources	WITH DRAWN
6.3	Design, Construction, and Use of Radioisotopic Power Generators for Certain Land and Sea Applications	WITH DRAWN
6.4	Verification of Containment Properties of Sealed Radioactive Sources	WITH DRAWN
6.5	General Safety Standard for Installations Using Nonmedical Sealed Gamma-Ray Sources	WITH DRAWN
6.6	Acceptance Sampling Procedures for Exempted and Generally Licensed Items Containing Byproduct Material	WITH DRAWN
6.7	Preparation of an Environmental Report To Support a Rule Making Petition Seeking an Exemption for a Radionuclide-Containing Product	2
6.8	Identification Plaque for Irretrievable Well-Logging Sources	WITH DRAWN
6.9	Establishing Quality Assurance Programs for the Manufacture and Distribution of Sealed Sources and Devices Containing Byproduct Material	WITH DRAWN

 

7. Transportation

RG NO	RG TITLE	Rev.No
7.1	Administrative Guide for Packaging and Transporting Radioactive Material	WITH DRAWN
7.2	Packaging and Transportation of Radioactively Contaminated Biological Materials	WITH DRAWN
7.3	Procedures for Picking Up and Receiving Packages of Radioactive Material	WITH DRAWN
7.4	Leakage Tests on Packages for Shipment of Radioactive Materials	2
7.5	Administrative Guide for Obtaining Exemptions from Certain NRC Requirements over Radioactive Material Shipments	WITH DRAWN
7.6	Design Criteria for the Structural Analysis of Shipping Cask Containment Vessels	1
7.7	Administrative Guide for Verifying Compliance with Packaging Requirements for Shipments of Radioactive Materials (for Comment)	1
7.8	Load Combinations for the Structural Analysis of Shipping Casks for Radioactive Material	1
7.9	Standard Format and Content of Part 71 Applications for Approval of Packages for Radioactive Material	DG (3)
7.10	Establishing Quality Assurance Programs for Packaging Used in Transport of Radioactive Material	3
7.11	Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with a Maximum Wall Thickness of 4 Inches (0.1 m)	0
7.12	Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask Containment Vessels with a Wall Thickness Greater than 4 Inches (0.1 m) But Not Exceeding 12 Inches (0.3 m)	0
7.13	Transportation Security Plans for Classified Matter Shipments	0

8. Occupational Health

RG NO	RG TITLE	Rev.No
8.1	Radiation Symbol	WITH DRAWN
8.2	Administrative Practices in Radiation Surveys and Monitoring	1
8.3	Film Badge Performance Criteria	WITH DRAWN
8.4	Personnel Monitoring Device—Direct-Reading Pocket Dosimeters	1
8.5	Criticality and Other Interior Evacuation Signals	WITH DRAWN
8.6	Standard Test Procedure for Geiger-Muller Counters	WITH DRAWN
8.7	Instructions for Recording and Reporting Occupational Radiation Exposure Data	4
8.8	Information Relevant to Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be as Low as Is Reasonably Achievable	3
8.9	Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program	1
8.10	Operating Philosophy for Maintaining Occupational Radiation Exposures as Low as Is Reasonably Achievable	2
8.11	Applications of Bioassay for Uranium	1
8.12	Criticality Accident Alarm Systems	WITH DRAWN
8.13	Instruction Concerning Prenatal Radiation Exposure	3
8.14	Personnel Neutron Dosimeters	WITH DRAWN
8.15	Acceptable Programs for Respiratory Protection	1
8.16	-	-
8.17	-	-
8.18	Information Relevant to Ensuring that Occupational Radiation Exposures at Medical Institutions Will Be as Low as Reasonably Achievable	2
8.19	Occupational Radiation Dose Assessment in Light-Water Reactor Power Plants -- Design Stage Man-Rem Estimates	1
8.20	Applications of Bioassay for Radioiodine	2
8.21	Health Physics Surveys for Byproduct Material at NRC-Licensed Processing and Manufacturing Plants	WITH DRAWN
8.22	Bioassay at Uranium Mills	2
8.23	Radiation Safety Surveys at Medical Institutions	WITH DRAWN
8.24	Health Physics Surveys During Enriched Uranium-235 Processing and Fuel Fabrication	2
8.25	Air Sampling in the Workplace	1
8.26	Applications of Bioassay for Fission and Activation Products	0
8.27	Radiation Protection Training for Personnel at Light-Water-Cooled Nuclear Power Plants	0
8.28	Audible-Alarm Dosimeters	0
8.29	Instruction Concerning Risks from Occupational Radiation Exposure	1
8.30	Health Physics Surveys in Uranium Recovery Facilities	1
8.31	Information Relevant to Ensuring that Occupational Radiation Exposures at Uranium Recovery Facilities Will Be as Low as Is Reasonably Achievable	1
8.32	Criteria for Establishing a Tritium Bioassay Program	0
8.33	Quality Management Program	WITH DRAWN
8.34	Monitoring Criteria and Methods To Calculate Occupational Radiation Doses	1
8.35	Planned Special Exposures	1
8.36	Radiation Dose to the Embryo/Fetus	0
8.37	ALARA Levels for Effluents from Materials Facilities	0
8.38	Control of Access to High and Very High Radiation Areas of Nuclear Plants	1
8.39	Release of Patients Administered Radioactive Materials	DG (2)
8.40	Methods for Measuring Effective Dose Equivalent from External Exposure	0

 

9. Antitrust and Financial Review

RG NO	RG TITLE	Rev.No
9.1	Regulatory Staff Position Statement on Antitrust Matters	WITH DRAWN
9.2	Information Needed by the NRC Staff in Connection with its Antitrust Review of Construction Permit Applications for Nuclear Power Plants	WITH DRAWN
9.3	Information Needed by the AEC Regulatory Staff in Connection with its Antitrust Review of Operating License Applications for Nuclear Power Plants	WITH DRAWN
9.4	Suggested Format for Cash Flow Statements Submitted as Guarantees of Payment of Retrospective	WITH DRAWN
9.5	Foreign Ownership, Control, or Domination of Nuclear Power and Non-Power Production or Utilization Facility	DG
9.6	Financial Qualifications for Power Reactors and Non-Power Production or Utilization Facilities	DG
9.7	Standard Format and Content for Insurance and Indemnity Requirement Report	DG

 

10. General

RG NO	RG TITLE	Rev.No
10.1	Compilation of Reporting Requirements for Persons Subject to NRC Regulations	WITH DRAWN
10.2	Guidance to Academic Institutions Applying for Specific Byproduct Material Licenses of Limited Scope	WITH DRAWN
10.3	Guide for the Preparation of Applications for Special Nuclear Material Licenses of Less than Critical Mass Quantities	WITH DRAWN
10.4	Guide for the Preparation of Applications for Licenses To Process Source Material	WITH DRAWN
10.5	Applications for a Type A License of Broad Scope	WITH DRAWN
10.6	Guide for the Preparation of Applications for an Industrial Radiography License	WITH DRAWN
10.7	Guide for the Preparation of Applications for Licenses for Laboratory and Industrial Use of Small Quantities of Byproduct Material	WITH DRAWN
10.8	Guide for the Preparation of Applications for Medical Use Programs	WITH DRAWN
10.9	Guide for the Preparation of Applications for Licenses for the Use of Self-Contained Dry Source-Storage Gamma Irradiators	WITH DRAWN
10.10	Guide for the Preparation of Applications for Radiation Safety Evaluation and Registration of Devices Containing Byproduct Material (Withdrawn -- 01/22/1999)	WITH DRAWN
10.11	Guide for the Preparation of Applications for Radiation Safety Evaluation and Registration of Sealed Sources Containing Byproduct Material	WITH DRAWN
10.12	Preparation of Petitions for Rulemaking Under 10 CFR 2.802 and Preparation and Submission of Proposals for Regulatory Guidance Documents	WITH DRAWN

 

10. General 은 최근 모두 철회가된 상황이다.

 

모든 법과 규제가 그러하듯 US NRC RG는 계속 유동적으로 개정되고 변화한다.

 

[Drafting (Draft Guide, DG)-> Public Comment -> Resolution -> Fianl Issuance]

 

규제지침이라는 특성상 Withdrawn(철회/폐지)되었다고해서 void가 되는 경우보다는 10 CFR Chapter 1로 편입되거나, 여러 RG가 합쳐지거나 다른 RG로 갈음되는 경우가 많다.(각 withdrawn 사유는 US NRC RG 페이지에서 확인이 가능하다.)

 

또한, 과거에 적용되어 운영중인 원전이나, 시설들은 withdrawn 된 RG들을 따랐을 것이므로 withdrawn 되었다고 완전히 void 처럼 무효화된것이라고 인지하지 않는 것이 중요하다. 이런경우는 취소/삭제(Cancelled)로 구분한다.

 

withdrawn 문서들도 이러한 점에서 현재 Active한 RG만큼 중요하기 때문에, NRC 홈페이지도 그렇고 이 블로그에서 정리한 글도 그렇고 목록에 수록하였다. 

 

US NRC RG 를 2022년쯤 한번 전체적으로 정리한 후, 2026년 2월 다시한번 현황을 정리해 보았는데, 생각보다 많이 추가되고 개정/철회되어 놀랐다.

 

RG를 자주 사용하는 업무를 하고 있다면, 주기적으로 현황을 체크하는 것이 좋을 듯 하다!