ML20134N370
| ML20134N370 | |
| Person / Time | |
|---|---|
| Issue date: | 11/01/1996 |
| From: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| References | |
| RTR-REGGD-GENERA NUDOCS 9611260298 | |
| Download: ML20134N370 (39) | |
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
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- 4) p5 November 1,1996 REGULATORY GUIDE LIST This complete list of the Regulatory Guide Series is being distributed to advise of the wide range of regulatory guides that are available and to list all published versions of each guide.
The Regulatory Guide Series has been developed to describe and make available to the public such information as methods acceptable to the NRC staff for implementing specific parts of the Commis-sion's regulations, techniques used by the staff in evaluating specific problems or postulated acci-dents, and data needed by the staff in its review of applications for permits or licenses. The guides are issued in the following ten broad divisions:
- 1. Power Reactors 6. Products
- 2. Research and Test Reactors 7. Transportation
- 3. Fuels and Materials Facilities 8. Occupational Health
- 4. Environmental and Siting 9. Antitrust and Financial Review
- 5. Materials and Plant Protection 10. General S Draft regulatory guides are issued for public comment in the early stages of the development of a i regulatory position. They have not received complete staff review and do not present an official
_/ NRC staff position.
Regulatory guides may be withdrawn when they are superseded by the Commission's regulations, when equivalent recommendations have been incorporated in applicable approved codes and stan-dards, or when changes in methods and techniques or in the need for specific guidance have made them obsolete. The withdrawal of a guide does not alter any prior or existing licensing commitments based on its use. j Single copies of regulatory guides, both active and draft, may be obtained free of charge by writing the Office of Administration, Attn: Distribution and Services Section, USNRC, Washington, DC l 20555-0001, or by fax at (301) 415-2260. Active guides may also be purchased from the National Technical Information Service on a standing order basis. Details on this service may be obtained by writing NTIS, 5285 Port Royal Road, Springfield, VA 22161.
Requests for placement on an automatic distribution list for single copies of future draft guides in specific divisions should be made in writing to the U.S. Nuclear Regulatory Commission, Washing-ton, DC 20555, Attention: Distribution and Mail Services Section. Requests for draft guides will be filled as long as supplies last.
If you have a question on specific guides in this list, please contact Ann Beranek, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555, telephone (301) 415-5890.
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U.S. NUCLEAR REGULATORY COMMISSION l REGULATORY GUIDE SERIES !
DIVISION 1 - POWER REACTORS l l
ACTIVE REGULATORY GUIDES Guide Published Number Title Rev. Month / Year I 1.1 Net Positive Suction liead for Emergency Core Cooling and Containment IIeat -
11/70 Removal System Pumps (Safety Guide 1) 1.2 (Withdrawn-See 56 FR 36175, 7/31/91) - -
)
1.3 Assumptions Used for Evaluating the Potential Radiological Consequences of a -
11/70 Loss of Coolant Accident for Boiling Water Reactors 1 06/73 2 06/74 1.4 Assumptions Used for Evaluating the Potential Radiological Consequences of a -
11/70 Loss of Coolant Accident for Pressurized Water Reactors 1 06/73 2 06/74 1.5 Assumptions Used for Evaluating the Potential Radiological Consequences of a -
03/71 I Steam Line Break Accident for Boiling Water Reactors (Safety Guide 5) 1.6 Independence Betw;en Redundant Standby (Onsite) Power Sources and -
03/71 Between Their Distribution Systems (Safety Guide 6) 1.7 Control of Combustible Gas Concentrations in Containment Following a Loss- -
03/71 of-Coolant Accident 1 09/76 2 11/78 1.8 Qualification and Training of Personnel for Nuclear Power Plants (Draft RS -
03/71 807-5, Proposed Revision 2, published 2/79; Draft RS 807-5, Second 1 09/75 Proposed Revision 2, published 9/80; Draft OL 403-5, Third Proposed 1-R 05/77 Revision 2, published 1/85; Draft DG-1012. Proposed Revision 3, published 2 04/87 9/96) 1.9 Selection, Design, Qualification, and Testing of Emergency Diesel Generator -
03/71 Units Used as Class 1E Onsite Electric Power Systems at Nuclear Power Piants 1 11/78 12/79
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(Draft RS 802-5, Proposed Revision 3, published 11/88) (Draft DG-1021, 2 Second Proposed Revision 3, published 4/92) 3 07/93 1.10 (Withdrawn-See 46 FR 37579, 7/21/81) - -
1.11 Instrument Lines Penetrating Primary Reactor Containment (Safety Guide 11) -
03/71 l Supplement to Safety Guide 11, Backfitting Considerations 02/72 l 1.12 Instrumentation for Earthquakes (Draft MS 140-5, Proposed Revision 2, -
03/71 published 7/81) (DG-1016, the Second Proposed Revision 2, 1 04/74 published 11/92) 1.13 Spent Fuel Storage Facility Design Basis (for Comment) (Draft CE 913-5, - 03/71 Proposed Revision 2, published 12/81) 1 12/75 1.14 Reactor Coolant Pump Flywheel Integrity (for Comment) - 10/71 1 08/75 1 Division 1
mm immi e mm Guide Number Published Title Rev. Month / Year 1.15 (Withdrawn-See 46 FR 37579, 7/21/81) - -
1.16 Reporting of Operating Information-Appendix A Technical Specifications -
10/71 (for Comment) 1 10/73 2 09/74 3 01/75 4 08/75 1.17 (Withdrawn-See 56 FR 30777, 7/5/91) - -
1.18 (Withdrawn-See 46 FR 37579, 7/21/81) - -
1.19 (Withdrawn-See 46 FR 37579, 7/21/81) - -
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1.20 Comprehensive Vibration Assessment Program for Reactor Internals During -
12/71 Preoperational and Initial Startup Testing 1 06/75 2 05/76 1.21 Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and -
12/71 Releases of Radioactive Materials in Liquid and Gaseous Effluents from 1 06/74 Light Water-Cooled Nuclear Power Plants 1.22 Periodic Testing of Protection System Actuation Functions (Safety Guide 22) -
02/72 l
1.23 Onsite Meteorological Programs (Safety Guide 23) (Draft SS 926-4, Proposed -
02/72 :
Revision 1, published 9/80) (Draft ES 926-4, Second Proposed Revision 1, I published 4/86) 1.24 Assumptions Used for Evaluating the Potential Radiological Consequences of a -
03/72 ,
Pressurized Water Reactor Radioactive Gas Storage Tank Failure (Safety Guide 24) 4 l
1.25 Assumptions Used for Evaluating the Potential Radiological Consequences of a -
03/72 Fuel Handling Accident in the Fuel Handling and Storage Facility for Dolling and Pressurized Water Reactors (Safety Guide 25) 1.26 Quality Group Classifications and Standards for Water , Steam , and -
03/72 Radioactive-Waste-Containing Components of Nuclear Power Plants 1 09/74 (for Comment) 2 06/75 3 02/76 i
1.27 Ultimate Heat Sink for Nuclear Power Plants (for Comment) -
03/72 !
1 03/74 l 2 01/76 I i
1.2G Quality Assurance Program Requirements (Design and Construction) (Draft -
06/72 I RS 002-5, Proposed Revision 3, published 3/81) (Draft DG-1010, 1 03/78 !
Proposed Revision 4, published 11/92) 2 02/79 l 3 08/85 l 1
1.29 Seismic Design Classification -
06/72 1 08/73 2 02/76 3 09/78 1.30 Quality Assurance Requirements for the Installation, Inspection, and Testing of -
08/72 Instrumentation and Electric Equipment (Safety Guide 30)
Division 1 2
Guide Published Number Title Rev. Month / Year 1.31 Control of Ferrite Content in Stainless Steel Weld Metal -
08/72 1 06/73 2 05/77 3 04/78 1.32 Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants -
08/72 1 03/76 2 02/77 1.33 Quality Assurance Program Requirements (Operation) (Draft RS 902-4, -
11/72 Proposed Revision 3, published 8/79) (Draft RS 902-4, Second Proposed 1 02/77 Revision 3, published 11/80) 2 02/78 1.34 Control of Electroslag Weld Properties -
12/72 1.35 Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments -
02/73 (Draft SC 810-4, Proposed Revision 3, published 4/79) 1 06/74 2 01/76 3 07/90 1.35.1 Determining Prestressing Forces for Inspection of Prestressed Concrete -
07/90 Containments (Draft SC 807-4 published 4/79) 1.36 Nonmetallic Thermal Insulation for Austenitic Stainless Steel -
02/73 l
1.37 Quality Assurance Requirements for Cleaning of Fluid Systems and Associated -
03/73 Components of Water-Cooled Nuclear Power Plants 1.38 Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, -
03/73 and Handling of Items for Water-Cooled Nuclear Power Plants 1 10/76 2 05/77 1.39 Housekeeping Requirements for Water-Cooled Nuclear Power Plants -
03/73 1 10/76 2 09/77 1.40 Qualification Tests of Continuous-Duty Motors Installed Inside the Containment -
03/73 of Water-Cooled Nuclear Power Plants 1.41 Preoperational Testing of Redundant On-Site Electric Power Systems To Verify -
03/73 Proper Load Group Assignments 1.42 (Withdrawn-See 41 FR 11891, 3/22/76) - -
1.43 Control of Stainless Steel Weld Cladding of Low-Alloy Steel Components -
05/73 1.44 Control of the Use of Sensitized Stainless Steel -
05/73 1.45 Reactor Coolant Pressure Boundary Leakage Detection Systems -
05/73 1.46 (Withdrawn-See 50 FR 9732,3/11/85) - -
1.47 Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety -
05/73 l Systems 1.48 (Withdrawn-See 50 FR 9732, 3/11/85) - -
3 Division 1
Guide Published Number Title Rev. Month / Year 1.49 Power Levels of Nuclear Power Plants -
05/73 1 12/73 l 1.50 Control of Preheat Temperature for Welding of Low-Alloy Steel -
05/73 1.51 (Withdrawn-See 40 FR 30510, 7/21/75) - -
1.52 Design, Testing, and Maintenance Criteria for Postaccident Engineered-Safety- -
06/73 l Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of 1 07/76 l Light-Water-Cooled Nuclear Power Plants 2 03/78 4 1.53 Application of the Single-Failure Criterion to Nuclear Power Plant Protection -
06/73 Systems 1,54 Quality Assurance Requirements for Protective Coatings Applied to Water-Cooled - 06/73 Nuclear Power Plants 1.55 (Withdrawn-See 46 FR 37579, 7/21/81) - -
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1.56 Maintenance of Water Purity in Boiling Water Reactors (for Comment) -
06/73 1 07/78 1.57 Design Limits and Loading Combinations for Metal Primary Reactor - 06/73 Containment System Components 1.58 (Withdrawn-See 56 FR 36175,7/31/91) - -
1.59 Design Basis Floods for Nuclear Power Plants (Errata published 7/30/80) - 08/73 1 04/76 2 08/77 l 1.60 Design Response Spectra for Seismic Design of Nuclear Power Plants -
10/73 1 12/73 l 1.61 Damping Values for Seismic Design of Nuclear Power Plants -
10/73 1.62 Manual Initiation of Protective Actions -
10/73 1.63 Electric Penetration Assemblies in Containment Structures for Nuclear Power -
10/73 Plants (Draft EE 405-4, Proposed Revision 3, published 6/86) 1 05/77 !
1 2 07/78 3 02/87 1.64 (Withdrawn-See 56 FR 36175, 7/31/91) - -
1.65 Materials and Inspections for Reactor Vessel Closure Studs -
10/73 1,66 (Withdrawn-See 42 FR 54478,10/6/77) - -
1.67 (Withdrawn-See 48 FR 19101, 4/27/83) - --
1.68 Initial Test Programs for Water-Cooled Nuclear Power Plants -
11/73 1 01/77 2 08/78 1,68.1 Preoperational and initial Startup Testing of Feedwater and Condensate -
12/75' Systems for Boiling Water Reactor Power Plants 1 01/77 l
Division 1 4
Guide Published Number Title Rev. Month / Year 1.68.2 Initial Startup Test Program To l'emonstrate Remote Shutdown -
01/77 Capability for Water-Cooled Nuclear Power Plants 1 07/78 1.68.3 Preoperational Testing of Instrument and Control Air Systems (Draft -
04/82 RS 709-4, a proposed revision to Regulatory Guide 1.80, published 10/80) 1.69 Concrete Radiation Shields for Nuclear Power Plants -
12/73 1.70 Standard Format and Content of Safety Analysis Reports for Nuclear Power -
02/72 Plants (LWR Edition) 1 10/72 2 09/75 3 11/78 1.71 Welder Qualification for Areas of Limited Accessibility -
12/73 1.72 Spray Pond Piping Made from Fiberglass-Reinforced Thermosetting Resin -
12/73 1 01/78 2 11/78 1.73 Qualification Tests of Electric Valve Operators Installed inside the Containment -
01/74 of Nuclear Power Plants 1.74 (Withdrawn-See 54 FR 38919, 9/21/89) - -
1.75 Physical Independence of Electric Systems -
02/74 1 01/75 2 09/78 1.76 Design Basis Tornado for Nuclear Power Plants -
04/74 1.77 Assumptions Used for Evaluating a Control Rod Ejection Accident for -
05/74 Pressurized Water Reactors 1.78 Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control -
06/74 Room During a Postulated Hazardous Chemical Release 1.79 Preoperational Testing of Emergency Core Cooling Systems for Pressurized -
06/74 Water Reactors 1 09/75 1.80 (Withdrawn-See 47 FR 19258, 5/4/82) Reissued as Regulatory Guide 1.68.3, - -
a renumbered revision to this guide with an expanded scope that addresses control air systems.
1.81 Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power -
06/74 Plants 1 01/75 1.82 Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant -
06/74 Accident (Draft MS 203-4, Proposed Revision 1, published 5/83) (Draft 1 11/85 DG-1038, Proposed Revision 2, published 7/95) 2 05/96 1.83 Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes -
06/74 1 07/75 1.84 Design and Fabrication Code Case Acceptability-ASME Section 111 Division 1 Because this guide is frequently revised, only the current revision and date are listed in the appropriate columns. Previous revisions and their publication dates follow: 0, 6/74; 1, 4/75; 2, 6/75; 3, 9/75; 4, 11/75; 5, 2/76; 6, 5/76; 7, 8/76; I 8, 11/76; 9, 3/77; 10, 8/77; 11, 11/77; 12, 3/78; 13, 7/78; 14, 11/78; 15, 5/79; 16, 5/80; 17, 12/80; 18, 8/81; 19, 4/82; 20, 11/82; 21, 9/83; 22, 7/84; 23, 9/85; 24, 6/86; 25, 5/88; 26, 7/89; 27, 11/90; 28, 4/92; 29, 7/93. 30 10/94 5 Division 1
Guide Published Number Title Rev. Month / Year l 1.85 Materials Code Case Acceptability-ASME Section III, Division 1 Because this guide is frequently revised, only the current revision and date are listed in the appropriate columns. Previous revisions and their publication dates follow: 0, 6/74; 1, 4/75; 2, 6/75: 3, 9/75; 4, 11/75; 5, 2/76; 6, 5/76; 7, 8/76; 8, 11/76; 9, 3/77; 10, 8/77; 11, 11/77; 12, 3/78; 13, 7/78; 14, 11/78; 15, 5/79; 16, 5/80; 17, 12/80; 18, 8/81; 19, 4/82: 20, 11/82; 21, 9/83; 22, 7/84; 23, 9/85; 24, 6/86; 25, S/88; 26, 7/89; 27, 11/90; 28, 4/92; 29, 7/93. 30 10/94 1.86 Termination of Operating Licenses for Nuclear Reactors --
06/74 1.37 Guidance for Construction of Class 1 Components in Elevated-Temperature -
06/74 Reactors (Supplement to ASME Section III Code Cases 1592, 1593, 1594, 1595, 1 06/75 l and 1596) i 1.08 (Withdrawn-See 56 FR 36175, 7/31/91) - -
l I
1.G9 Environmentai Qualification of Certain Electric Equipment Important to Safety -
11/74 1 for Nuclear Power Plants (Draft EE 042-2, Proposed Revision 1, published 2/82) 1 06/84 )
i 1.90 Inservice Inspection of Prestressed Concrete Containment Structures with -
11/74 Grouted Tendons 1 08/77 1.91 Evaluations of Explosions Postulated To Occur on Transportation Routes Near -
01/75 Nuclear Power Plants 1 02/78 1.92 Combining Modal Responses and Spatial Components in Seismic Response -
12/74 Analysis 1 02/76 1.93 Availability of Electric Power Sources -
12/74 1.94 Quality Assurance Requirements for Installation, Inspection, and Testing of -
04/75 Structural Concrete and Structural Steel During the Construction Phase of 1 04/76 Nuclear Power Plants (Draft RS 908-5, Proposed Revision 2, published 9/79) 1.95 Protecticn of Nuclear Power Plant Control Room Operators Agairist an -
02/75 Accidental Chlorine Release 1 01/77 1.96 Design of Main Steam Isolation Valve Leakage Control Systems for Boiling -
05/75 Water Reactor Nuclear Power Plants 1 06/76 1.97 Instruinentation for Light-Water-Cooled Nuclear Power Plants To Assess Plant -
12/75 and Environs Conditions During and Following an Accident (Errata published 1 08/77 7/81) (Draft RS 917-4, Proposed Revision 2, published 12/79) 2 12/80 3 05/83 1.98 Assumptions Used for Evaluating the Potential Radiological Consequences of a -
03/76 Ra6ioactive Offgas System Failure in a Boiling Water Reactor (for Comment) 1.99 Radiation Embrittlement of Reactor Vessel Materials (Draft ME 305-4, -
07/75 Proposed Revision 2, published 2/86) 1 04/77 2 05/88 1.100 Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power -
03/76 Plants (Draft EE 108-5, Proposed Revision 2, published 8/87) 1 08/77 2 06/88 1.101 Emergency Planning and Preparedness for Nuclear Power Reactors (Revision 1 -
11/75 to this guide entitled " Emergency Planning for Nuclear Power Plants" was 1 03/77 withdrawn-see 45 FR 69610,10/21/80.) (Draft DG-1022, Proposed 2 10/81 Revision 3, published 2/92) 3 08/92 Division 1 6
Guide Published Number Title Rev. Month / Year D 1.102 Flood Protection for Nuclear Power Plants -
1 10/75 09/76 1.103 (Withdrawn-See 46 FR 37579, 7/21/81) - -
1.104 (Withdrawn-See 44 FR 49321, 8/22/79) See NUREG-0554, " Single-Failure- - -
Proof Cranes for Nuclear Power Plants."
1.105 Instrument Setpoints for Safety-Related Systerns (Draft IC 010-5, Proposed -
11/75 Revision 2, published 12/81) (Draft DG-1045, Proposed Revision 3, 1 11/76 published 10/96) 2 02/86 1.106 Thermal Overload Protection for Electric Motors on Motor-Operated Valves -
11/75 1 03/77 1,107 Qualifications for Cement Grouting for Prestressing Tendons in Containment -
11/75 Structures 1 02/77 1.108 (Withdrawn-See 58 FR 41813, 8/5/93) (Periodic Testing of Diesel Generator - -
Units Used as Onsite Electric Power Systems at Nuclear Power Plants) 1.109 Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents -
03/76 for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I 1 10/77 j 1.110 Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled Nuclear -
03/76 l Power Reactors (for Comment) )
D 1.111 Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors 1
03/76 07/77 1.112 Calculation of Releases of Radioactive Materials in Gaseous and Liquid -
04/76 Effluents from Light-Water-Cooled Power Reactors O-R 05/77 l 1.113 Estimating Aquatic Dispersion of Effluents from Accidental and Routine 05/76 Reactor Releases for the Purpose of Impleinenting Appendix I 1 04/77 1 1
1.114 Guidance to Operators at the Controls and to Senior Operators in the Control -
02/76 Room of a Nuclear Power Unit (Draft HF 601-4, Proposed Revision 2, 1 11/76 )
published 12/86) 2 05/89 l 1.115 Protection Against Low-Trajectory Turbine Missiles -
03/76 1 07/77-1.116 Quality Assurance Requirements fbr Installation, Inspection, and Testing of -
06/76 Mechanical Equipment and Systems 0-R 05/77 1.117 Tomado Design Classification -
06/76 1 04/78 i 1.118 Periodic Testing of Electric Power and Protection Systems (DG-1028, -
06/76 Proposed Revision 3. published 9/94) 1 11/77 2 06/78 3 04/95 1.119 (Withdrawn-See 42 FR 33387, 6/30/77) - -
1.120 Fire Protection Guidelines for Nuclear Power Plants (for Comment) -
06/76 1 11/77 l
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Guide Number Published Title Rev. Month / Year 1.121 Bases for Plugging Degraded PWR Steam Generator Tubes (for Comment) -
08/76 1.122 Development of Floor Design Response Spectra for Seismic Design of Floor- -
09/76 Supported Equipment or Components 1 02/78 1.123 (Withdrawn-See 56 FR 36175, 7/31/91) - -
1.124 Service Limits and Loading Combinations for Class 1 Linear-Type Component -
11/76 Supports 1 01/78 1.125 Physical Models for Design and Operation of Hydraulic Structures and Systems -
03/77 for Nuclear Power Plants 1 10/78 1.126 An Acceptable Model and Related Statistical Methods for the Analysis of Fuel -
03/77 Densification 1 03/78 1.127 Inspection of Water-Control Structures Associated with Nuclear Power Plants -
04/77 1 03/78 1.128 Installation Design and Installation of Large Lead Storage Batteries for Nuclear -
04/77 Power Plants 1 10/78 1.129 Maintenance, Testing, and Replacement of Large Lead Storage Batteries for -
04/77 Nuclear Power Plants 1 02/78 1.130 Service Limits and Loading Combinations for Class 1 Plate-and-Shell-Type -
07/77 Component Supports 1 10/78 1.131 Qualification Tests of Electric Cables, Field Splices, and Connections for -
08/77 Light-Water-Cooled Nuclear Power Plants (for Comment) (Draft RS 050-2, Proposed Revision 1, published 8/79) 1.132 Site Investigations for Foundations of Nuclear Power Plants -
09/77 1 03/79 1.133 Loose-Part Detection Program for the Primary System of Light-Water-Cooled -
09/77 Reactors 1 05/81 1.134 Medical Evaluation of Licensed Personnel for Nuclear Power Plants (Draft -
09/77 OL 401-5, Proposed Revision 2, published 11/84) 1 03/79 2 04/87 1.135 Normal Water Level and Discharge at Nuclear Power Plants (for Comment) -
09/77 1.136 Materials, Construction, and Testing of Concrete Containments (Articles -
11/77 CC-1000. -2000, and -4000 through -6000 of the " Code for Concrete 1 10/78 Reactor Vessels and Containments") (Draft SC 814-5, Proposed Revision 2, 2 06/81 published 11/79) 1.137 Fuel-Oil Systems for Standby Diesel Gencrators -
01/78 1 10/79 1.138 Laboratory Investigations of Soils for Engineering Analysis and Design of -
04/78 Nuclear Power Plants (for Comment) 1.139 Guidance for Residual Heat Removal (for Comment) -
05/78 1.140 Design, Testing, and Maintenance Criteria for Normal Ventilation Exhaust -
03/78 System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear 1 10/79 Power Plants Ditision 1 8
Guide Published Number Title Rev. Month / Year D 1.141 Containment Isolation Provisions for Fluid Systems (for Comment) -
04/78 1.142 Safety-Related Concrete Structures for Nuclear Power Plants (Other than -
04/78 Reactor Vessels and Containments) 1 10/81 1.143 Design Guidance for Radioactive Waste Management Systems, Structures, and -
07/78 Components Installed in Light-Water-Cooled Nuclear Power Plants 1 10/79 1.144 (Withdrawn-See 56 FR 36175, 7/31/91) - -
1.145 Atmospheric Dispersion Models for Potential Accident Consequence -
08/79 Assessments at Nuclear Power Plants (Reissued 2/83 to correct page 1.145-7) 1 11/82 1.146 (Withdrawn-See 56 FR 36175, 7/31/91) - -
1.147 Inservice Inspection Code Case Acceptability-ASME Section XI, Division 1 11 10/94 (Draft SC 721-4 published 8/79) Previous revisions and their publication dates follow: 0, 2/81; 1, 2/82; 2, 6/83; 3, 7/84; 4, 9/85; 5, 8/86; 6, 5/88; 7, 7/89; 8, 11/90; 9, 4/92; 10, 7/93.
1.148 Functional Specification for Active Valve Assemblies in Systems Important to -
03/81 Safety in Nuclear Power Plants (Draft SC 704-5 published 2/79) 1.149 Nuclear Power Plant Simulation Facilities for Use in Operator License -
04/81 Examinations (Draft RS 110-5 published 7/80) (Draft OL 402-5, Proposed 1 04/87 Revision 1, published 11/84) (Draft DG-1043, Proposed Revision 2 to 2 04/96 Regulatory Guide 1.149, published 6/95) 1.150 Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice -
06/81 D Examinations (Draft SC 705-4 published 5/79) 1.151 Instrument Sensing Lines (Draft IC 126-5 published 3/82) -
1 02/83 07/83 1.152 Criteria for Digital Computers in Safety Systems of Nuclear Power Piants -
11/85 (Draft IC 127-5 published 3/83) (Draft DG-1039, Proposed Revision 1, 1 01/96 published 5/95) 1.153 Criteria for Safety Systems (Draft IC 609-5 published 12/82) (Draft -
12/85 DG-1042 Proposed Revision 1, published 11/95) 1 06/96 1.154 Format and Content of Plant-Specific Pressurized Thermal Shock Safety -
01/87 Analysis Reports for Pressurized Water Reactors (Draft SI 502-4 published 1/86) 1.155 Station Blackout (Draft SI 501-4 published 3/86) (Issued June 1988, reissued -
08/88 August 1988 with corrected tables) 1.156 Environmental Qualification of Connection Assemblies for Nuclear Power Plants -
11/87 (Draft EE 404-4 published 5/87) 1.157 Best-Estimate Calculations of Emergency Core Cooling System Performance -
05/89 (Draft RS 701-4 published 3/87) 1.158 Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants -
02/89 (Draft EE 006-5 published 8/87) 1.159 Assuring the Availability of Funds for Decommissioning Nuclear Reactors -
08/90 (Draft DG-1003 published 5/89) 1.160 Monitoring the Effectiveness of Maintenance at Nuclear Power Plants -
06/93 (Draft DG-1020 published 11/9^2) (Draft DG-1031, Proposed Revision 1, 1 01/95 published 6/94) (Draft DG-1051, Proposed Revision 2, published 8/96) 9 Division 1 l
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Guide Number Published Title Rev. Month / Year 1.161 Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less -
06/95 Than 50 Ft-Lb (Draft DG-1023 published 9/93) 1.162 Format and Content of Report for Thermal Annealing of Reactor Pressure -
02/96 l
Vessels (Draft DG-1027 published 10/94) 1.163 Performance-Based Containment Leak-Test Program (Draft DG-1037 -
09/95 .
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DIVISION 1 l DRAFT REGULATORY GUIDES Task Number Published Title Month / Year CE 913-5 (Proposed Revision 2 to Regulatory Guide 1.13) Spent Fuel Storage Facility 12/81 Design Basis DG-1001 Maintenance Prograrns for Nuclear Power Plants 08/89 DG-1005 Standard Format and Content for Decommissioning Plans for Nuclear Reactors 09/89 DG-1006 Records important for Decommissioning of Nuclear Reactors 09/89 DC -1008 Reactor Coolant Pump Seals 04/91 DG 1010 (Proposed Revision 4 to Regulatory Guide 1.28) Quality Assurance Program 11/92 Requirements 50-1012 (Proposed Revision 3 to Regulatory Guide 1.8) Qualification and Training of 09/96 Personnel for Nuclear Power Plants DG-1025 Calculational and Dosimetry Methods for Determining Pressure Vessel 09/93 Neutron Fluence DG-1032 Identification and Characterization of Seismic Sources, Deterministic Source 02/95 Earthquakes, and Ground Motion (DG-1015 issued 11/92)
I DG-1033 (Second Proposed Revision 2 to Regulatory Guide 1.12, previously issued as 02/95 MS 140-5 and DG-1016) Nuclear Power Plant Instrumentation for Earthquakes DG-1034 Pre-Farthquake Planning and Immediate Nuclear Power Plant Operator 02/95 Postearthquake Actions (Previously issued as DG-1017)
DG-1035 Restart of a Nuclear Power Plant Shut Down by a Seismic Event 02/95 (Previously issued as DG-1018)
DG-1040 Time Response Design Criteria for Safety-Related Operator Actions 06/95 DG-1045 (Proposed Revision 3 to Regulatory Guide 1.105) Setpoints for Safety-Related 10/96 Instrumentation DG-1046 Guidelines for Reporting Reliability and Availability Information for 04/96 Risk-Significant Systems and Equipment in Nuclear Power Plants DG-1047 Standard Format and Content for Applications To Renew Nuclear Power 08/96 Plant Operating Licenses (Supersedes DG-1009)
DG-1051 (Proposed Revision 2 to Regulatory Guide 1.160) Monitoring the Effectiveness 08/96 of Maintenance at Nuclear Power Plants DG-1054 Verification, Validation, Reviews, and Audits for Digital Computer Software Used 08/96 in Safety Systems of Nuclear Power Plants DG-1055 Configuration Management Plans for Digital Computer Software Used in Safety 08/96 Systems of Nuclear Power Plants y DG-1056 Software Test Documentation for Digital Computer Software Used in Safety Systems
! 08/96 of Nuclear Power Plants 11 Division 1
Task Published Number Title Month / Year DG-1057 Software Unit Testing for Digital Computer Software Used in Safety Syums 08/96 of Nuclear Power Plants DG-1058 Software Requirements Specifications for Digital Computer Software Used 08/96 in Safety Systems of Nuclear Power Plants DG-1059 Developing Software Life Cycle Processes for Digital Computer Software 08/96 Used in Safety Systems of Nuclear Power Plants EM 805-5 Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power 02/79 Plants ES 926-4 (Second Proposed Revision 1 to Regulatory Guide 1.23) Meteorological 04/86 Measurement Program for Nuclear Power Plants FP 811-4 Safety-Related Permanent Dewatering Systems for Nuclear Power Plants 09/79 j l
IC 121-5 Response-Time Testing of Protection System Instrument Channels 01/82 IC 131-5 Installation of Transducers 03/82 MS 021-5 Containment System Leakage Testing 10/86 MS 901-4 Identification of Valves for Inclusion in Inservice Testing Programs 11/81 RS 050-2 (Proposed Revision 1 to Regulatory Guide 1.131) Qualification Tests of Electric 08/79 Cables and Field Splices for Light-Water-Cooled Nuclear Power Plants RS 705-4 Lightning Protection for Nuclear Power Plants 08/79 RS 809-5 Qualification Test for Cable Penetration Fire Stops for Use in Nuclear Power Plants 07/79 RS 902-4 (Second Proposed Revision 3 to Regulatory Guide 1.33) Quality Assurance Program 11/80 l Requirements (Operation) l RS 908-5 (Proposed Revision 2 to Regulatory Guide 1.94) Quality Assurance Requirements 09/79 l for Installation, Inspection, and Testing of Structural Concrete, Structural Steel, l Soils, and Foundations During the Construction Phase of Nuclear Power Plants I !
SC 521-4 LWR Core Reloads; Guidance on Applications for Amendments to Operating 09/79 Licenses and on Refueling and Startup Tests SC 708-4 (Withdrawn-See 54 FR 16030, 4/20/89) -
O Division 1 12 t----------
U.S. NUCLEAR' REGULATORY COMMISSION REGULATORY GUIDE SERIES I
DIVISION 2 - RESEARCH AND TEST REACTORS ACTIVE REGULATORY GUIDES Guide Published Number Title Rev. Month / Year 2.1 Shield Test Program for Evaluation of Installed Biological Shielding in Research -
05/73 and Training Reactors 2.2 Development of Technical Specifications for Experiments in Research Reactors -
11/73 2.3 Quality Verification for Plate-Type Uranium-Aluminum Fuel Elements for Use -
09/75 in Research Reactors 1 07/76 2.4 Review of Experiments for Research Reactors -
07/76 O-R 05/77 2.5 Quality Assurance Program Requirements for Research Reactors -
05/77 O-R 10/77 2.6 Emergency Planning for Research and Test Reactors (Draft HF 201-4, Proposed -
01/79 Revision 1, published 3/82) 1 03/83 I
i m
\
y/
13 Division 2
1 U.S. NUCLEAR REGULATORY COMMISSION l REGULATORY GUIDE SERIES l DIVISION 3 - FUELS AND MATERIALS FACILITIES ACTIVE REGULATORY GUIDES Guide Number Published Title Rev. Month / Year 3.1 Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of -
01/73 Fissile Material (Draft FP 027-5, Proposed Revision 1, published 5/81) (Draft 1 01/82 CE 602-4, Proposed Revision 2, published 3/87) 2 09/87 3.2 Efficiency Testing of Air-Cleaning Systems Containing Devices for Removal of -
01/73 Particles 3.3 Ouality Assurance Program Requirements for Fuel Reprocessing Plants and for -
01/73 Plutonium Processing and Fuel Fabrication Plants 1 03/74 3.4 Nuclear Criticality Safety in Operations with Fissionable Materials at Fuels and -
01/73 Materials Facilities (Draft CE 404-4, Proposed Revision 2, published 4/85) 1 08/77 1-R 02/78 2 03/86 3.5 Standard Format and Content of License Applications for Uranium Mills (for -
02/73 Comment) (Draft WM 039-4, Proposed Revision 2, published 8/81) 1 11/77 3.6 Content of Technical Specifications for Fuel Reprocessing Plants -
04/73 3.7 Monitoring of Combustible Gases and Vapors in Plutonium Processing and Fuel -
03/73 Fabrication Plants 3.0 Preparation of Environmental Reports for Uranium Mills -
04/73 1 09/78 2 10/82 3.9 Concrete Radiation Shields -
06/73 3.10 Liquid Waste Treatment System Design Guide for Plutonium Processing and Fuel -
06/73 Fabrication Plants 3.11 Design, Construction, and Inspection of Embankment Retention Systems for -
06/73 Uranium Mills 1 03/77 2 12/77 3.11.1 Operational Inspection and Surveillance of Embankment Retention -
04/79 Systems for Uranium Mill Tailings 1 10/80 3.12 General Design Guide for Ventilation Systems of Plutonium Processing and Fuel -
08/73 Fabrication Plants 3.13 Guide for Acceptable Waste Storage Methods at UFe Production Plants -
10/73 3.14 Seismic Design Classification for Plutonium Processing and Fuel Fabrication -
10/73 Plants 3.15 Standard Format and Content of License Applications for Storage Only of -
10/73 Unitradiated Power Reactor Fuel and Associated Radioactive Material (Draft 1 04/83 CE 219-4, Proposed Revision 1, published 8/82)
Division 3 14
r --
Guide Number Title Published I Rev. Month / Year 3.16 General Fire Protection Guide for Plutonium Processing and Fuel Fabrication Plants 01/74 3.17 Earthquake Instrumentation for Fuel Reprocessing Plants -
02/74 3.18 Confinement Barriers and Systems for Fuel Reprocessing Plants -
02/74 3.19 Reporting of Operating Information for Fuel Reprocessing Plants -
02/74 3.20 Process Offgas Systems for Fuel Reprocessing Plants -
02/74 3.21 Quality Assurance Requirements for Protective Coatings Applied to Fuel -
03/74 Reprocessing and to Plutonium Processing and Fuel Fabrication Plants 3.22 Periodic Testing of Fuel Reprocessing Plant Protection System Actuation -
06/74 Functions 3.23 (Withdrawn-See 45 FR 71876,10/30/80) - -
3.24 (Withdrawn-See 46 FR 14507, 2/27/81) - -
3.25 Standard Format and Content of Safety Analysis Reports for Uranium Enrichment Facilities 12/74 3.26 Standard Format and Content of Safety Analysis Reports for Fuel Reprocessing -
02/75 Plants I 3.27 Nondestructive Reprocessing PlantsExamination of Welds in the Liners of Concrete Barriers in Fuel 05/75 1 05/77 3.28 Welder Qualification for Welding in Areas of Limited Accessibility in Fuel -
05/75 Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants 3.29 Preheat and Interpass Temperature Control for the Welding of Low-Alloy Steel -
05/75 for Use in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants 3.30 Selection, Application, and Inspection of Protective Coatings (Paints) for Fuel -
06/75 Reprocessing Plants O-R 05/77 3.31 Emergency Water Supply Systems for Fuel Reprocessing Plants -
09/75 O-R 05/77 3.32 General Design Guioe for Ventilation Systems for Fuel Reprocessing Plants -
09/75 (for Comment) 3.33 Assumptions Used for Evaluating the Potential Radiological Consequences of -
04/77 Accidental Nuclear Criticality in a Fuel Reprocessing Plant (for Comment) 3.34 Assumptions Used for Evaluating the Potential Radiological Consequences of -
04/77 Accidental Nuclear Criticality in a Uranium Fuel Fabrication Plant 1 07/79 l 3.35 Assumptions Used for Evaluating the Potential Radiological Consequences of -
05/77 Accidental Nuclear Criticality in a Plutonium Processing and Fuel Fabrication D
3.36 Piant 1 07/79 (Withdrawn-See 44 FR 6535, 2/1/79) - -
15 Division 3
Gulds Published Number Title Rev. Month / Year 3.37 Guidance for Avoiding Intergranular Corrosion and Stress Corrosion in Austenitic - 09/75 Stainless Steel Components of Fuel Reprocessing Plants (for Comment) 3.38 General Fire Protection Guide for Fuel Reprocessing Plants (for Comment) -
06/76 3.39 Standard Format and Content of License Applications for Plutonium Processing -
01/76 and Fuel Fabrication Plants 3.40 Design Basis Floods for Fuel Reprocessing Plants and for Plutonium Processing -
11/76 and Fuel Fabrication Plants 1 12/77 3.41 (Withdrawn-See 51 FR 11660, 4/4/86) - -
3.42 Emergency Planning for Fuel Cycle Facilities and Plants Licensed Under 10 CFR -
08/77 Parts 50 and 70 1 09/79 3.43 Nuclear Criticality Safety in the Storage of Fissile Materials -
08/78 1 04/79 ;
3.44 Emdard Format and Content for the Safety Analysis Report for an Independent -
12/78 Spent Fuel Storage Installation (Water-Basin Type) (Draft CE 403-4, Proposed 1 11/80 i Revision 2, published 11/86) 2 01/89 3.45 Nuclear Criticality Safety for Steel-Pipe Intersections Containing Aqueous -
11/80 Solutions of Fissile Materials (Draft FP 925-5 published 1/80) (Draft CE 802-5, 1 04/89 Proposed Revision 1, published 5/88) 3.46 Standard Format and Content of License Applications, Including Environmental -
06/82 Reports, for In Situ Uranium Solution Mining (Draft FP 818-4 published 7/80) 3.47 Nuclear Criticality Control and Safety of Homogeneous Plutonium-Uranium Fuel -
07/81 Mixtures Outside Reactors (Draft FP 026-5 published 12/80) 3.48 Standard Format and Content for the Safety Analysis Report for an Independent -
10/81 Spent Fuel Storage Installation or Monitored Retrievable Storage Installation 1 08/89 (Dry Storage) (Draft FP 029-4 published 12/80) (Draft CE 406-4, Proposed Revision 1, published 10/86) 3.49 Design of an Independent Spent Fuel Storage Installation (Water-Basin Type) -
12/81 (Draft FP 806-6 published 1/81) 3.50 Standard Format and Content for a License Application To Store Spent Fuel -
01/82 and High-Level Radioactive Waste (Draft FP 907-4 published 3/81) 1 09/89 (Draft CE 402-4, Proposed Revision 1, published 9/86) 3.51 Calculational Models for Estimating Radiation Doses to Man from Airborne -
03/82 Radioactive Materials Resulting from Uranium Milling Operations (Draft RH 802-4 published 5/79) (Errata published August 1982) 3.52 Standard Format and Content for the Health and Safety Sections of License -
07/82 l Renewal Applications for Uranium Processing and Fuel Fabrication (Draft 1 11/86 FP 716-4 published 10/80) (Draft CE 308-4, Proposed Revision 1, published 7/85) 3.53 Applicability of Existing Regulatory Guides to the Design and Operation of an -
07/82 Independent Spent Fuel Storage Installation (Draft CE 037-4 published 11/81) 3.54 Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation -
09/84 (Draft FP 034-4 published 12/80) (Second Draft CE 034-4 published 1/83)
Division 3 16
Guide Published Number Title Rev. Month / Year 3.55 Standard Format and Content Mr the Health and Safety Sections of License -
04/85 Renewal Applications for Uran'.um Hexalluoride Production (Draft CE 227-4 published 1/84) 3.56 General Guidance for Designing, Testing, Operating, and Maintaining Emission -
05/86 Control Devices at Uranium Mills (Draft CE 309-4 pu'olished 5/85) 3.57 Administrative Practices for Nuclear Criticality Safety at Fuels and Materials -
10/86 Facilities (Draft CE 501-4 published 2/86) 3.58 Criticality Safety for Handling, Storing, and Transporting LWR Fuel at Fuels -
10/86 and Materials Facilities (Draft CE 407-4 published 7/85) (Draft DG-3004, Proposed Revision 1, published 5/90) 3.59 Methods for Estimating Radioactive and Toxic Airborne Source Terms for -
03/87 Uranium Milling Operations (Draft WM 407-4 published 4/86) 3.60 Design of an Independent Spent Fuel Storage Installation (Dry Storage) (Draft -
03/87 CE 410-4 published 11/85) 3.61 Standari Format and Content for a Topical Safety Analysis Report for a Spent -
02/89 Fuel Dry Storage Cask (Draft CE 306-4 published 4/86) 3.62 Standard Format and Content for the Safety Analysis Report for Onsite Storage -
02/89 of Spent Fuel Storage Casks (Draft CE 301-4 published 4/86) 3.63 Onsite Meteorological Measurement Program for Uranium Recovery Facilities- -
03/88 Data Acquisition and Reporting (Draft ES 401-4 published 9/85) 3.64 Calculation of Radon Flux Attenuation by Earthen Uranium Mill Tailings -
06/89 Covers (Draft WM 503-4 published 5/87) 3.65 Standard Format and Content of Decommissioning Plans for Licensees -
08/89 Under 10 CFR Parts 30, 40, and 70 (Draft CE 304-4 published 12/85) 3.66 Standard Format and Content of Financial Assurance Mechanisms Required for -
06/90 Decommissioning Under 10 CFR Pans 30, 40, 70, and 72 (Draft DG-3002 published 1/90) 3.67 Standard Format and Content for Emergency Plans for Fuel Cycle and Materials -
01/92 Facilities (Draft DG-3005 published 9/90) 3.68 Nuclear Criticality Safety Training (Draft DG-3008 published 1/93) -
04/94 3.69 Topical Guidelines for the Licensing Support System (Draft DG-3009 -
09/96 published 7/93) l l
17 Division 3
DIVISION 3 DRAFT REGULATORY GUIDES Task Published Number Title Month / Year DG-3001 Records important for Decommissioning for Licensees Under 10 CFR Parts 30, 07/89 40, 70, and 72 DG-3003 Format and Content for the License Application for the liigh Level 11/90 Waste Repository DG-3004 (Proposed Revision 1 to Regulatory Guide 3.58) Criticality Safety for IIandling, 05/90 Storing, and Transporting LWR Fuel at Fuels and Materials Facilities DG-3006 Standard Format and Content for Fire Protection Sections of License 04/93 Applications for Fuel Cycle Facilities ES 114-4 Guidelines for Ground-Water Monitoring at In Situ Uranium Solution Mines 06/83 ES 115-4 Guidelines for Modeling Ground-Water Transport of Radioactive and Nonradioactive 05/83 Contaminants at Tailings Disposal Sites HF 608-4 Training and Certification of Independent Spent Fuel Storage Installation Operators 03/82 MS 146-4 Design, Installation, and Inspection of Seepage Control Liners at Uranium Recovery 11/82 Facilities WM 039-4 (Proposed Revision 2 to Regulatory Guide 3.5) Standard Format and Content of 08/81 License Applications for Uranium Mills I
9 Division 3 18
U.S. NUCLEAR REGULATORY COMMISSION REGULATORY GLIDE SERIES DIVISION 4 - ENVIRONMENTAL AND SITING ACTIVE REGULATORY GUIDES Guide Published Number Title Rev. Month / Year 4.1 Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants -
01/73 1 04/75 4.2 Preparation of Environmental Reports for Nuclear Power Stations (Proposed -
03/73 Supplement 1 to Regulatory Guide 4.2, DG-4002, published 8/91) 1 01/75 2 07/76 4.3 (Withdrawn-See 41 FR 53870,12/9/76) - -
4.4 Reporting Procedure for Mathematical Models Selected To Predict Heated -
05/74 Effluent Dispersion in Natural Water Bodies 4.5 Measurements of Radionuclides in the Environment-Sampling and Analysis of -
05/74 Plutonium in Soil 4.6 Measurements of Radionuclides in the Enviranment-Strontium-89 and -
05/74 Strontium-90 Analyses l 4.7 General Site Suitability Criteria for Nuclear Power Stations (DG-4003, -
09/74 I Proposed Revision 2, published 11/92) 1 11/75 4.8 Environmental Technical Specifications for Nuclear Power Plants (for Comment) -
12/75 4.9 Preparation of Environmental Reports for Commercial Uranium Enrichment -
12/74 Facilities 1 10/75 4.10 (Withdrawn-See 42 FR 59436,11/17/77) - -
4.11 Terrestrial Environmental Studies for Nuclear Power Stations -
07/76 1 08/77 4.12 (Not published) - -
4.13 Performance, Testing, and Procedural Specifications for Thermoluminescence -
11/76 Dosimetry: Environmental Applications 1 07/77 4.14 Radiological Effluent and Environmental Monitoring at Uranium Mills -
06/77 1 04/80 4.15 Quality Assurance for Radiological Monitoring Programs (Normal Operations)- -
12/77 Effluent Streams and the Environment 1 02/79 4.16 Monitoring and Reporting Radioactivity in Releases of Radioactive Materials in -
03/78 Liquid and Gaseous Effluents from Nuclear Fuel Processing and Fabrication 1 12/85 Plants and Uranium Hexafluoride Production Plants (Draft CE 401-4, Proposed Revision 1, published 9/84) (Errata published 8/86) l 4.17 Standard Format and Content of Site Characterization Plans for High-Level- -
07/82 Waste Geologic Repositories (Draft GS 027-4 published 4/81) (Draft 1 03/87 WM 404-4, Proposed Revision 1, published 2/85) 19 Division 4
Guide Published -
Number Title R ev. Month / Year 4.18 Standard Format and Content of Environmental Reports for Near-Surface -
06/83 Disposal of Radioactive Waste (Draft WM 013-4 published 4/82) 4.19 Guidance for Selecting Sites for Near-Surface Disposal of Low-Level Radioactive -
08/88 Waste (Draft WM 408-4 published 3/87) e O
Division 4 20
DIVISION 4 I DRAFT REGULATORY GUIDES Task Published Number Title Month / Year DG-4002 (Proposed Supplement 1 to Regulatory Guide 4.2) Guidance for the 08/91 Preparation of Supplemental Environmental Reports in Support of an Application To Renew a Nuclear Power Station Operating License DG-4004 (Proposed Revision 2 to Regulatory Guide 4.7) General Site Suitability 02/95 Criteria for Nuclear Power Stations (Issued as DG-4003,11/92)
I 21 Division 4
o l
U.S. NUCLEAR REGULATORY COMMISSION i REGULATORY GUIDE SERIES DIVISION 5 - MATERIALS AND PLANT PROTECTION ACTIVE REGULATORY GUIDES Guide Published Number Title Rev. Month / Year 5.1 Serial Numbering of Fuel Assemblies for Light-Water-Cooled Nuclear Power -
12/72 Reactors 5.2 (Withdrawn-See 44 FR 57542,10/5/79) - -
5.3 Statistical Terminology and Notation for Special Nuclear Materials Control and -
02/73 Accountability 5.4 Standard Analytical Methods for the Measurement of Uranium Tetrafluoride -
02/73 (UF4) and Uranium Hexafluoride (UFe) 5.5 Standard Methods for Chemical, Mass Spectrometric, and Spectrochemical -
02/73 Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets 5.6 (Withdrawn-See 50 FR 25364, 6/18/85) - -
5.7 Entry / Exit Control for Protected Areas, Vital Areas, and Material Access areas -
06/73 (Draft SG 909-4, Proposed Revision 1, published 5/79) 1 05/80 5.8 Design Considerations for Minimizing Residual Holdup of Special Nuclear -
06/73 Material in Drying and Fluidized Bed Operations 1 05/74 5.9 Guidelines for Germanium Spectroscopy Systems for Measurement of Special -
06/73 Nuclear Material (Draft SG 042-2, Proposed Revision 2, published 7/82) 1 05/74 2 12/83 5.10 Selection and Use of Pressure-Sensitive Seals on Containers for Onsite Storage of -
07/73 Special Nuclear Material 5.11 Nondestructive Assay of Special Nuclear Material Contained in Scrap and Waste -
10/73 (Draft SG 043-4, Proposed Revision 1, published 11/82) 1 04/84 5.12 General Use of Locks in the Protection and Control of Facilities and Special -
11/73 Nuclear Materials 5.13 Conduct of Nuclear Material Physical Inventories -
11/73 5.14 Use of Observation (Visual Surveillance) Techniques in Material Access Areas -
11/73 (Draft SG 910-4, Proposed Revision 1, published 5/79) 1 05/80 5.15 Security Seals for the Protection and Control of Special Nuclear Material (Draft -
01/74 DG-5005, Proposed Revision 1, published 1/96) 5.16 (Withdrawn-See 50 FR 25364, 6/18/85) - -
5.17 Truck Identification Markings -
01/74 5.18 Limit of Error Concepts and Principles of Calculation in Nuclear Materials -
01/74 Control 5.19 (Withdrawn-See 50 FR 25364, 6/18/85) - -
Division 5 22
Guide Published Number Title Rev. Month / Year I
5.20 Training, Equipping, and Qualifying of Guards and Watchmen -
01/74 5.21 Nondestructive Uranium-235 Enrichment Assay by Gamma Ray Spectrometry -
04/74 (Draft SG 044-4, Proposed Revision 1, published 6/82) 1 12/83 5.22 Assessment of the Assumption of Normality (Employing Individual Observed -
04/74 Values) 5.23 In Situ Assay of Plutonium Residual Holdup (Draft SG 045-4, Proposed -
05/74 Revision 1, published 10/82) 1 02/84 5.24 Analysis and Use of Process Data for the Protection of Special Nuclear Material -
06/74 5.25 Design Considerations for Minimizing Residual Holdup of Special Nuclear Material - 06/74 in Equipment for Wet Process Operations 5.26 Selection of Material Balance Areas and Item Control Areas -
06/74 1 04/75 5.27 Special Nuclear Material Doorway Monitors -
06/74 5.28 Evaluation of Shipper-Receiver Differences in the Transfer of Special Nuclear -
06/74 Materials 5.29 Nuclear Material Control Systems for Nuclear Power Plants -
06/74 1 06/75 I 5.30 Materials Protection Contingency Measures for Uranium and Plutonium Fuel -
06/74 Manufacturing Plants 5.31 Specishy Designed Vehicle with Armed Guards for Road Shipment of Special -
06/74 Nuclear Material 1 04/75 5.32 Communication with Transport Vehicles -
06/74 1 05/75 5.33 Statistical Evaluation of Material Unaccounted For -
06/74 5.34 Nondestructive Assay for Plutonium in Scrap Material by Spontaneous Fission -
06/74 Detection (Draft SG 046-4, Proposed Revision 1, published 6/82) 1 05/84 5.35 (Withdrawn-See 42 FR 41677, 8/18/77) - -
5.36 Recommended Practice for Dealing with Outlying Observations -
06/74 5.37 In Situ Assay of Enriched Uranium Residual Holdup (Draft SG 047-4, Proposed -
08/74 Revision 1, published 8/82) 1 10/83 5.38 Nondestructive Assay of High-Enrichment Uranium Fuel Plates by Gamma Ray -
09/74 Spectrometry (Draft SG 048-4, Proposed Revision 1, published 8/82) 1 10/83 5.39 General Methods for the Analysis of Uranyl Nitrate Solutions for Assay, Isotopic -
12/74 Distribution, and Impurity Determinations 5.40 (Withdrawn-See 50 FR 25364, 6/18/85) - -
5.41 (Not issued) - -
23 Division 5
Guide Published Number Title Rev. Month / Year 5.42 Design Considerations for Minimizing Residual lioldup of Special Nuclear - 01/75 Material in Equipment for Dry Process Operations 5.43 Plant Security Force Duties -
01/75 5.44 Perimeter Intrusion Alarm Systeins (Draft SG 479-4, Proposed Revision 2, -
01/75 published 5/79)(Draft DG-5007. Proposed Revision 3, published 4/96) 1 06/76 2 05/80 5.45 Standard Format and Content for the Special Nuclear Material Control and -
12/74 Accounting Section of a Special Nuclear Material License Application (Including That for a Uranium Enrichment Facility) 5.46 (Not issued) - -
5.47 (Withdrawn-See 50 FR 25364, 6/18/85) - -
5.48 Design Considerations-Systems for Measuring the Mass of Liquids -
02/75 5.49 Internal Transfers of Special Nuclear Material (for Comment) -
03/75 5.50 (Not issued) - -
5.51 Management Review of Nuclear Material Control and Accounting Systems (for -
06/75 Comment) 5.52 Standard Format and Content'of a Licensee Physical Protection Plan for -
05/75 Strategic Special Nuclear Material at Fixed Sites (Other than Nuclear Power 1 06/76 Plants) (DG-5004, Proposed Revision 3, published 4/94) 2 07/80 l 3 12/94 5.53 Qualification, Calibration, and Error Estimation Methods for Nondestructive -
08/75 Assay (Draft SG 049-4, Proposed Revision 1, published 6/82) 1 02/84 5.54 Standard Format and Content of Safeguards Contingency Plans for Nuclear -
03/78 Power Plants (for Comment) 5.55 Standard Format and Content of Safeguards Contingency Plans for Fuel Cycle -
03/78 Facilities (for Comment) 5.56 Standard Format and Content of Safeguards Contingency Plans for -
03/78 Transportation (for Comment) 5.57 Shipping and Receiving Control of Strategic Special Nuclear Material (Draft -
06/76 SG 908-4, Proposed Revision 1, published 5/79) 1 06/80 5.58 Considerations for Establishing Traceability of Special Nuclear Material -
11/78 Accounting Measurements 1 02/80 5.59 Standard Format and Content for a Licensee Physical Security Plan for the -
01/80 Protection of Special Nuclear Material of Moderate or Low Strategic 1 02/83 Significance (Draft MP 711-4 published 7/79) (Draft SG 229-4, Proposed Revision 1, published 9/82) 5.60 Standard Format and Content of a Licensee Physical Protection Plan for Strategic - 04/80 Special Nuclear Material in Transit 5.61 Intent and Scope of the Physical Protection Upgrade Rule Requirements for -
06/80 Fixed Sites Division 5 24
Gulde Published l Number Title Rev. Month / Year I
5.62 Reporting of Safeguards Events (Draft SG 901-4 published 10/79) (Draft -
02/81 SG 901-4, Proposed Revision 1, published 10/85) 1 11/87 5.63 Physical Protection for Transient Shipments (Draft SG 126-4 published 9/81) -
07/82 5.64 (Not issued) - -
5.65 Vital Area Access Controls, Protection of Physical Security Equipment, and -
09/86 Key and Lock Controls (Draft SG 302-4 published 1/85) 5.66 Access Authorization Program for Nuclear Power Plants -
06/91 5.67 Material Control and Accounting for Uranium Enrichment Facilities -
12/93 Authorized To Produce Special Nuclear Material of Low Strategic Significance (Draft DG-5002 published 2/91) 5.68 Protection Against Malevolent Use of Vehicles at Nuclear Power Plants -
08/94 (Draft DG-5006 issued 11/93)
I 25 Disision 5
DIVISION 5 DRAFT REGULATORY GUIDES Task Nurnber Published Title Month / Year SG 301-4 (Withdrawn-See 56 FR 36175, 7/31/91) -
DG-5005 (Proposed Revision 1 to Regulatory Guide 5.15) Tamper-Indicating 01/96 Seals for the Protection and Control of Special Nuclear Material DG-5007 (Proposed Revision 3 to Regulatory Guide 5.44) Perimeter 04/96 Intrusion Alarm Systerns l
9 j Division 5 26
U.S. NUCLEAR REGULATORY COMMISSION REGUIATORY GUIDE SERIES I
DIVISION 6 - PRODUCTS ACTIVE REGULATORY GUIDES Guide Published Number Title Rev. Month / Year 6.1 Leak Testing Radioactive Brachytherapy Sources -
02/74 1 07/74 6.2 Integrity and Test Specifications for Selected Brachytherapy Sources -
02/74 1 07/74 6.3 Design, Construction, and Use of Radioisotopic Power Generators for Certain -
03/74 Land and Sea Applications 6.4 Classification of Containment Properties of Scaled Radioactive Sources -
03/74 1 05/75 2 08/80 6.5 General Safety Standard for Installations Using Nonmedical Sealed Gamma- -
06/74 Ray Sources 6.6 Acceptance Sampling Procedures for Exempted and Generally Licensed Items -
06/74 Containing Byproduct Material l 6.7 Preparation of an Environmental Report To Support a Rule Making Petition -
10/75 Seeking an Exemption for a Radionuclide-Containing Product 1 06/76 6.8 Identification Plaque for Irretrievable Well-Logging Sources (for Comment) -
10/78 6.9 Establishing Quality Assurance Programs for the Manufacture and -
02/95 Distribution of Scaled Sources and Devices Containing Byproduct Material (Draft DG-6002 published S/94) 27 Division 8
DIVISION 6 DRAFT REGULATORY GUIDES Task Published Number Title Month / Year l
TP 102-5 Safety Features of Gauges Containing Radioactive Material 11/80
)
i l
i e
l d
3 1
l
! O Division 6 28 e
I U.S. NUCLEAR REGULATORY COMMISSION REGULATORY GUIDE SERIES I
DIVISION 7 - TRANSPORTATION ACTIVE REGULATORY GUIDES Guide Published Number Title Rev. Month / Year 7.1 Administrative Guide for Packaging and Transporting Radioactive Material -
06/74 7.2 Packaging and Transportation of Radioactively Contaminated Biological Materials -
06/74 7.3 Procedures for Picking Up and Receiving Packages of Radioactive Material -
05/75 7.4 Leakage Tests on Packages for Shipment of Radioactive Materials -
06/75 7.5 Administrative Guide for Obtaining Exemptions from Certain NRC Requirements -
06/75 over Radioactive Material Shipments O-R 05/77 7.6 Design Criteria for the Structural Analysis of Shipping Cask Containment Vessels -
02/77 1 03/78 7.7 Administrative Guide for Verifying Compliance with Packaging Requirements for -
08/77 Shipments of Radioactive Materials (for Comment) 7.8 Load Combinations for the Structural Analysis of Shipping Casks for Radioactive -
05/77 Material (Draft MS 527-4, Proposed Revision 1, published 7/87) (Draft MS 1 03/89 804-4, Second Proposed Revision 1, published 9/88) v ,
7.9 Standard Format and Content of Part 71 Applications for Approval of Packaging -
03/79 l of Type B, Large Quantity, and Fissile Radioactive Material (Draft FC 416-4, 1 01/80 Proposed Revision 2, published 5/86) 7.10 Establishing Quality Assurance Programs for Packaging Used in the Transport of -
01/83 Radioactive Material (Combined Draft TP 019-4, published 6/81, and Draft 1 06/86 TP 020-4, published 3/81) 7.11 Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask -
06/91 Containment Vessels with a Maximum Wall Thickness of 4 Inches (0.1 m)
(Draft MS 144-4 published 6/83) (Draft DG-7001 published 7/89) 7.12 Fracture Toughness Criteria of Base Material for Ferritic Steel Shipping Cask -
06/91 Contalmnent Vessels with a Wall Thickness Greater than 4 Inches (0.1 m)
But Not Exceeding 12 Inches (0.3 m) (Draft MS 501-4 published 6/86) l (Draft DG-7002 published 7/89)
I 29 Division 8
DIVISION 7 DRAFT REGULATORY GUIDES Task Published Number Title Month / Year FC 416-4 (Proposed Revision 2 to Regulatory Guide 7.9) Standard Format and Content of 05/86 Part 71 Applications for Approval of Packaging for Radioactive Material TP 914-4 Measurement of Radiation Levels on Surfaces of Packages of Radioactive 12/79 l Materials l
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Division 7 30
REGULATORY GUIDE SERIES DIVISION 8 - OCCUPATIONAL HEALTH ACTIVE REGULATORY GUIDES Guide Number Title Published Rev. Morith/ Year 8.1 Radiation Symbol 8.2 02/73 Guide for Administrative Practices in Radiation Monitoring -
8.3 02/73 Film Badge Performance Criteria 8.4 02/73 Direct-Reading and Indirect Reading Pocket Dosimeters 8.5 02/73 Criticality and Other Interior Evacuation Signals 02/73 8.6 1 03/81 Standard Test Procedure for Geiger-Muller Counters 8.7 05/73 Instructions for Recording and Reporting Occupational Radiation Exposure Data (Draft DG-8007, Proposed Revision 1, published 11/91) 05/73 8.8 1 06/92 Information Relevant to Ensuring that Occupational Radiation Exposures at -
Nuclear Power Stations Will Be As Low As Is Reasonably Achievable1 (Draft 07/73 OH 507-4, Proposed Revision 4, published 3/79) (Draft OP 618-4, Second 09/75 Proposed Revision 4, published 5/82) 2 03/77 3 06/78 8.9 Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay -
Program (Draft DG-8009, Proposed Revision 1, published 12/91) 09/73 8.10 1
07/93 Operating As Is Reasonably Philosophy for Achievable Maintaining Occupational Radiation Exposures As Low 04/74 1 09/75 1-R 05/77 8.11 Applications of Bioassay for Uranium 8.12 06/74 Criticality Accident Alarm Systems (Draft OH 015-4, Proposed Revision 1, -
published 5/80) (Draft CE 801-5 Proposed Revision 2, published 5/88)1 12/74 01/81 2 10/88 8.13 Instruction Concerning Prenatal Radiation Exposure (Draft OP 031-4 -
Proposed published Revision 2, published 8/81) (Draft DG-8014, Proposed Revision 10/94) 3,03/75 1 11/75 2 12/87 8.14 Personnel published Neutron Dosimeters (Draft OH 940-4, Proposed Revision 2, 2/80) -
06/76 8.15 1 08/77 Acceptable Programs for Respiratory Protection 8.16 10/76 (Not issued) 8.17 (Not issued) 8.18 Information Relevant to Ensuring that Occupational Radiation Exposures at -
Medical Institutions Will Be As Low As Reasonably Achievable 12/77 8.19 1 10/82 Occupational Radiation Dose Assessment in Light-Water Reactor Power Plants-Design Stage Man-Rem Estimates -
05/78 1 06/79 31 Division 8
Published Guide Title Rev. Month / Year Number
- 04/78 8.20 Applications of Bioassay for I-125 and 1-131 1 09/79
- 05/78 8.21 Health Physics Surveys for Byproduct Material at NRC-Licensed Processing and 1 10/79 Manufacturing Plants
- 07/78 8.22 Bioassay at Uranium Mills (Draft OP 013-4, Proposed Revision 1, 1 08/88 published 1/87)
- 02/79 8.23 Radiation Safety Surveys at Medical Institutions 1 01/81
- 11/78 8.24 Health Physics Surveys During Enriched Uranium-235 Processing and Fuel 1 10/79 Fabrication
- 08/80 8.25 Air Sampling in the Workplace (Draft OH 905-4 published 10/79) (Draft 1 06/92 DG-8003, Proposed Revision 1, published 9/91)
- 09/80 8.26 Applications of Bioassay for Fission and Activation Products (Draft OH 714-4 published 8/79)
- 03/81 8.27 Radiation Protection Training for Personnel at Light-Water-Cooled Nuclear Power Plants (Draft OH 717-4 published 8/79)
- 08/81 8.28 Audible Alarm Dosimeters (Draft OH 804-4 published 8/79)
- 07/81 8.29 Instruction Concerning Risks from Occupational Radiation Exposure 02/96 1
(Draft OH 902-4 published 5/80) (Draft DG-8012, Proposed Revision 1, published 12/94)
- 06/83 8.30 Health Physics Surveys in Uranium Mills (Draft OH 710-4 published 8/80)
- 05/83 8.31 Information Relevent to Ensuring that Occupational Radiation Exposures at Uranium Mills Will Be As Low As Is Reasonably Achievable (Draft OH 941-4 published 8/80)
- 07/88 8.32 Criteria for Establishing a Tritium Bioassay Program (Draft OP 713-4 published 6/83)
- 10/91 8.33 Ouality Management Program (Draft DG-8001 published 1/90)
- 07/92 8.34 Monitoring Criteria and Methods To Calculate Occupational Radiation Doses (Draft DG-8010 published 2/92)
- 06/92 8.35 Planned Special Exposures (Draft DG-8008 published 12/91)
- 07/92 8.36 Radiation Dose to the Embryo / Fetus (Draft DG-8011 published 2/92)
- 07/93 8.37 ALARA Levels for Effluents from Materials Facilities (Draft DG-8013 published 10/92) (Draft DG-8016 Proposed Revision 1, published 12/95) 8.38 Control of Access to High and Very High Radiation Areas of Nuclear Plants - 06/93 (Draft DG-8006 published 10/91)
O 32 Division 8
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DIVISION 8 DRAFT REGULATORY GUIDES Task Published Number Title Month / Year DG-8004 Radiation Protection Programs for Nuclear Power Plants 10/91 DG-8005 Withdrawn-See 58 FR 17628, 4/5/93 (Assessing External Radiation Doses from Airborne Radioactive Materials)
DG-8014 (Proposed Revision 3 to Regulatory Guide 8.13) Instruction Concerning Prenatal 10/94 Radiation Exposure DG-8015 Release of Patients Administered Radioactive Materials 06/94 DG-8016 (Proposed Revision 1 to Regulatory Guide 8.37) Constraints for Air Effluents 12/95 for Licensees Other Than Power Reactors OH 940-4 (Proposed Revision 2 to Regulatory Guide 8.14) Personnel Neutron Dosimeters 02/80 OP 032-5 Test and Calibration of Radiation Protection Instrumentation 09/84 OP 212-4 Radiation Protection Training for Personnel Employed in Medical Facilities 01/84 ,
OP 618-4 (Second Preposed Revision 4 to Regulatory Guide 8.8) Information Relevant to 05/82 Ensuring that Occupational Radiation Exposures at Nuclear Power Stations Will Be As Low As is Reasonably Achievable (ALARA)
Qualifications for the Radiation Safety Officer in a Large-Scale Non-Fuel-Cycle 04/82 D OP 722-4 Radionuclide Program i
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U.S. NUCLEAR REGULATORY COMMISSION REGULATORY GUIDE SERIES DIVISION 9 - ANTITRUST AND FINANCIAL REVIEW I
ACTIVE REGULATORY GUIDES Guide Number Published Title Rev. Month / Year 9.1 Regulatory Staff Position Statement on Antitrust Matters -
12/73 9.2 Information Needed by the NRC Staff in Connection with Its Antitrust Review -
10/74 l of Construction Permit Applications for Nuclear Power Plants 1 06/76 !
9.3 Information Needed by the AEC Regulatory Staff in Connection with its -
10/74 ;
Antitrust Review of Operating License Applications for Nuclear Power Plants 1 9.4 Suggested Format for Cash Flow Statements Submitted as Guarantees of -
09/78 i Payment of Retrospective Premiums (for Comment) 9 4
9 Division 9 34
U.S. NUCLEAR REGULATORY COMMISSION REGULATORY GUIDE SERIES DIVISION 10 - GENERAL ACTIVE REGULATORY GUIDES Guide Published Number Title Rev. Month / Year 10.1 Compilation of Reporting Requirements for Persons Subject to NRC Regulations -
01/75 1 07/75 2 08/75 3 05/77 4 10/81 10.2 Guidance to Academic Institutions Applying for Specific Byproduct Material -
03/76 Licenses of Limited Scope (Errata published 7/84) 1 12/76 10.3 Guide for the Preparation of Applicttions for Special Nuclear Material Licenses -
07/76 of Less than Critical Mass Quantities 1 04/77 10.4 Guide for the Preparation of Applications for Licenses To Process Source Material - 07/76 (Errata published 7/84) (Draft FC 409-4, Proposed Revision 2, published 4/85) 1 03/77 2 12/87 10.5 Applications for Type A Licenses of Broad Scope (Errata published 7/84) (Draft -
09/76 D FC 408-4, Proposed Revision 2, published 2/85) (Draft DG-0005, Second Proposed Revision 2, published 10/94) 1 12/80 I
10.6 Guide for the Preparation of Applications for Use of Sealed Sources and Devices -
09/76 i for Performing Industrial Radiography (Draft TP 602-4, Proposed Revision 1, 1 12/81 published 6/80) (Errata published 7/84) (Draft FC 401-4, Proposed Revision 2, I published 10/84) I 10.7 Guide for the Preparation of Applications for Licenses for Laboratory and -
02/77 l Industrial Use of Small Qur.ntities of Byproduct Material (Errata published 7/84) 1 08/79 1 10.8 Guide for the Preparation of Applications for Medical Use Programs (Draft -
01/79 l FC 415-4, Proposed Revision 2, published 8/85) (Draft DG-0002, Proposed 1 10/80 i Appendix X to Regulatory Guide 10.8, published 12/91) (Appendix X 2 08/87 l published June 1992) 10.9 Guide for the Preparation of Applications for Licenses for the Use of Self- -
04/80 Contained Dry Source Storage Gamma Irradiators (Draft OH 706-4 published 1 12/88 2/79) (Draft OP 706-4, Proposed Revision 1, published 4/82) (Errata published 7/84) (Draft FC 402--4, Second Proposed Revision 1, published 10/84) 10.10 Guide for the Preparation of Applications for Radiation Safety Evaluation and -
03/87 Registration of Devices Containing Byproduct Material (Draft FC 601-4 l
published 8/86) 10.11 Guide for the Preparation of Applications for Radiation Safety Evaluation and -
06/87 Registration of Sealed Sources Containing Byproduct Material (Draft FC 603-4 published 12/86)
- 35 Division 10
DIVISION 10 DRAlT REGULATORY GUIDES Task Published Number Title Month / Year DG-0003 Guide for the Preparation of Applications for Licenses for Non-Self-Contained 01/94 Irradiators DG-0005 (Second Proposed Revision 2 to Regulatory Guide 10.5) Applications for 10/94 Licenses of Broad Scope DG-0008 Applications for the Use of Sealed Sources in Portable Gauging Devices 05/95 l (Previous draft was FC 407-4)
DG-0010 Preparation of Petitions for Rulemaking Under 10 CFR 2.802 and Preparation 08/96 and Submission of Proposals for Regulatory Guidance Docurnents FC 40'.-4 (Proposed Revision 2 to Regulatory Guide 10.6) Guide for the Preparation of 10/84 l Applications for the Use of Sealed Sources and Devices for Performing Industrial l Radiography FC 403-4 Guide for the Preparation of Applications for Licenses for the Use of Panoramic Dry 01/85 Source-Storage Irradiators, Self-Contained Wet Source-Storage Irradiators, and Panoramic Wet Source-Storage Irradiators l
FC 404-4 Guide for the Preparation of Applications for Licenses for the Use of Sealed Sources 01/85 in Nonportable Gauging Devices FC 405-4 Guide for the Preparation of Applications for Licenses for the Use of Sealed Sources 02/85 in Gas Chromatography Devices and X-Ray Fluorescence Analyzers FC 406-4 Guide for the Preparation of Applications for Licenses and Approvals To Authorize 02/85 Distribution of Various items to Group Medical Licensees FC 408-4 (Proposed Revision 2 to Regulatory Guide 10,5) Guide for the Preparation of 02/85 Applications for Type A Licenses of Broad Scope (See DG-0005)
FC 410-4 Guide for the Preparation of Applications for Nuclear Pharmacy Licenses 08/85 FC 411-4 Guide for the Preparation of Applications for Licenses for the Use of Radioactive 06/85 Materials in Servicing Preregistered Gauges, Measuring Devices, and Sealed Sources Used in Such Devices FC 412-4 Guide for the Preparation of Applications for Licenses for the Use of Radioactive 06/85 Materials in Leak-Testing Services FC 413-4 Guide for the Preparation of Applications for Licenses for the Use of Radioactive 06/85 Materials in Calibrating Radiation Survey and Monitoring Instruments FC 414-4 Guide for the Preparation of Applications for Licenses for Medical Teletherapy 12/85 Programs (Second draft, previously issued as TM 608-4, 3/82; Errata published 7/84) 9 Division 10 36
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