ML20058D225

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RTR-REGGD-GENERA NUDOCS 9312030101
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tU M /s E NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555

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November 1,1993 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-y 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.

Er vironmental and Siting 9.

Antitrust and Financial Review O

5.

Materials and Plant Protection

10. General Draft regulatory guides are issued for public comment in the early stages of the development of a 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Regulatory guides may be withdrawn when they are superseded by the Commission's regulations, when equivalent recommendations have been inco porated in applicable approved codes and stan-dards, or when changes in methods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 aher any prior or existing licensing commitments based on its use.

The latest version of active guides may be purchased from the Government Printing Office at the current GPO price. Information on current GPO prices may be obtained by contacting the Superin-tendent of Documents, U.S. Government Printing Office, P.O. Box 37082, Washington, DC 20013-7082, telephone (202) 512-2249 or (202) 512-2171. Active guides may also be purchased from the National Technical Information Service on a standing order basis. Details on this service i

may be obtained by writing NTIS, 5285 Port Royal Road, Springfield, VA 22161.

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Requests for smgle copies of draft guides (which may be reproduced) or for placement on an auto-matic distribution list for single copies of future draft guides in specific divisions should be made in writing to the U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention: Distribu-tion 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) 492-3519.

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GENERAL oI I

t November 1,1993 1

U.S. NUCLEAR REGULATORY COMMISSION

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REGULATORY GUIDE SERIES f

DIVISION 1 - POWER REACTORS e

ACTIVE REGULATORY GUIDES Guide Published Number Title Rev.

Month / Year 1.1 Net Positive Suction Head for Emergency Core Cooling and Containment Heat 11/70 Removal System Pumps (Safety Guide 1) i

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1.2 (Withdrawn-See 56 FR 36175, 7/31/91) d 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)

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1.6 Independence Between 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 f

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) 2 04/87 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 Plants 1

11/78 (Draft RS 802-5, Proposed Revision 3, published 11/88) (Draft DG-1021, 2

12/79 Second Proposed Revision 3, published 4/92) 3 07/93-1.10 (Withdrawn-See 46 FR 37579, 7/21/81) t 1.11 Instrument Lines Penetrating Primary Reactor Containment (Safety Guide 11) 03/71 i

V Supplement to Safety Guide 11, Backfitting Considerations 02/72

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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

' (r 1.14 Reactor Coolant Pump Flywheel Integrity (for Comment) 10/71 i

1 08/75 1

Division 1

Guide Published Number Title Rev.

Month / Year 1.15

' hdrawn-Su 16 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) 1.20 Comprehensive Vibration Assessment Program for Reactor Internals During 12/71 g

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

^

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, published 4/S6) 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) 1.25 Assumptions Used for Evaluating the Potential Radiological Consequences of a 03/72 Fuel Handling Accident in the Fuel Handling and Storage Facihty for Boiling and Pressurized Water Reactors (Safety Guide 25) 1.26 Ouality 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

02/7.6 1.27 Ultimate lleat Sink for Nuclear Power Plants (for Comment) 03/72 1

03/74 2

01/76 1.28 Ouahty Assurance Program Requirements (Design and Construct'on) (Dreft 06/72 RS 002-5, Proposed Revision 3, published 3/81) (Draft DG-10'0, 1

03/78 Proposed Revision 4, published 11/92) 2 02/79 3

08/85

^

1.29 Seismic Design Classification 06/72 1

08/73 2

02/76 3

09/78 1.30 Ouality Assurance Requirements for the Installation Inspection, and Testing of 08/72 Instrumentation and Electric Equipment (Safety Guide 30) 2 Division 1

Guide Published Number Title Rev.

Month / Year b

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 i

' 1.35 Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments 02/73 l

(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) j

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1.36 Nonmetallic Thermal Insulation for Austenitic Stainless Steel 02/73 l

t Quality Assurance Requirements for Cleaning of Fluid Systems and Associated 03/73 1.37 Components of Water-Cooled Nuclear Power Plants 1.38 Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, 03/73 and llandling of items for Water-Cooled Nuclear Power Plants 1

10/76 l

2 05/77 i

i 1.39 Ilousekeeping Requirements for Water-Cooled Nuclear Power Plants 03/73 1

10/76 2

'09/77 i

l I

1.40 Qualification Tests of Continuous-Duty Motors Installed inside the Containment 03/73 of Water Cooled Nuclear Power Plants 4

I 1.41 Preoperational Testing of Redundant On-Site Electric Power Systems To Verify 03/73 l

s Proper Load Group Assignments i

i I

1.42 (Withdrawn-See 41 FR 11891, 3/22/76) l l

1.43 Control of Stainless Steel Weld Cladding of Low-Alloy Steel Components 05/73 l

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1.44 Control of the Use of Sensitized Stainless Steel 05/73 1

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1.45 Reactor Couant Pressure Boundary Leakage Detection Systems 05/73 l

1 1.46 (Withdrawn-See 50 FR 9732, 3/11/85) 2 1.47 Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety 05/73 Systems t

t j

1.48 (Withdrawn-See 50 FR 9732. 3/11/85) l I

3 Division 1 l

l 1

i Guide Published Number Title Rev.

Month / Year 1.49 Power Levels of Nuclear Power Plants 05/73 1

12/73 1.50 Control of Preheat Temperature for Welding of Low-Alloy Steel 05/73 1.51 (Withdrawn-See 40 FR 30510, 7/21/75) l l

1.52 Design, Testing, and Maintenance Criteria for Postaccident Engineered-Safety-06/73 Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of 1

07/76 Light-Water-Cooled Nuclear Power Plants 2

03/78 j

1.53 Application of the Single-Failure Criterion to Nuclear Power Plant Protection 06/73 Systems

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1.54 Quality Assarance Requirements for Protective Coatings Applied to Water-Cooled 06/73 Nuclear Power Plants

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1.55 (Withdrawn-See 46 FR 37579, 7/21/81) t j

1.56 Maintenance of Water Purity in Boiling Water Reactors (for Comment) 06/73 l

1 07/78 l

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) l t

l 1.59 Design Basis Floods for Nuclear Power Plants (Errata published 7/30/80) 08/73 d

1 04/76

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2 08/77 l

l 1.60 Design Response Spectra for Seismic Design of Nuclear Power Plants 10/73 1

12/73 6

i 1.61 Damping Values for Seismic Design of Nuclear Power Plants 10/73 I

i 10/73

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1.62 Manual Initiation of Protective Actions d

1.63 Electric Penetration Assemblies in Containment Structures for Nuclear Power 10/73 i

Plants (Draft EE 405-4, Proposed Revision 3. published 6/86) 1 05/77 2

07/78 j

3 02/87 1

l l

1.64 (Withdrawn-See 56 FR 36175, 7/31/91) i l

i 1.65 Materials and Inspections for Reactor Vessel Closure Studs 10/73 f

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1.66 (Withdrawn-See 42 FR 54478,10/6/77) l 4

1.67 (Withdrawn-See 48 FR 19101, 4/27/83) s b

1.68 Initial Test Programs for Water-Cooled Nuclear Power Plants 11/73 i

1 01/77 2

08/78 i

i 1.68.1 Preoperational and Imtial Startup Testing of Feedwater and Condensate 12/75 j

Systems for Boiling Water Reactor Power Plants 1

01/77 i

l j

4 Division 1 l

9 4

Published Guide Number Title Rev.

Month / Year O

1.68.2 Initial Startup Test Program To Demonstrate Remote Shutdown 01/77 Capability for Water-Cooled Nuclear Power Plants 1

07/78 1.68.3 Preoperational Testing of Instmment 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 i

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 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.

f 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 Fo!!owing a Loss-of-Coolant 06/74

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j Accident (Draft MS 203-4, Proposed Revision 1, published 5/83) 1 11/85 1.83 Insersice Inspection of Pressurized Water Reactor Steam Generator Tubes 06/74 1

07/75 1.84 Design and Fabrication Code Case Acceptability-ASME Section Ill, 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: 11, 9/83; 22, 7/84; 23, 9/85; 24, 6/86; 25, 5/88; 26, 7/89; 27, 11/90: 28, 4/92.

29 07/93 5

Disision 1

h i

c Guide Published Number Title Rev.

Month / Year l

1.85 Meterials Code Case Acceptabihty-ASME Section Ill, Division 1 Because this gt.ide is frequently revised, only the current revision and date are l

hsted m 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, i

5/79; 16, $/50; 17,12/S0; 18, 8/81; 19, 4/82: 20,11/62: 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 07/93 j

1.86 Termination of Operating Licenses for Nuclear Reactors 06/74

1. 8 ~7 Guidance for Construction of Class 1 Components in Elevated-Temperature 06/74 Reactors (Supplement to ASME Section 111 Code Cases 1592, 1593, 1594, 1595, 1

06/75 and 1596) 1.88 (Withdrawn-See 56 FR 36175, 7/31/91)

I 1.89 Environmental Quahfication of Certain Electric Equipment Important to Safety 11/74 for Nuclear Power Plants (Draft EE 042-2. Proposed Revision 1, published 2/82) 1 06/84 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 I

i Nuclear Power Plants 1

02/78 i

I 1.92 Combining Modal Responses and Spatial Components in Seismic Response 12/74 Analysis 1

02/76 l

1.93 Availability of Electric Power Sources 12/74 l

1.94 Quahty Assurance Requirements for Installation, Inspection, and Testing of 04/75 Structural Concrete and Structural Steel During the Construction Phase of 1

04/76 2

Nuclear Power Plants (Draft RS 908-5. Proposed Revision 2, published 9/79) 1.95 Protection of Nuclear Power Plant Control Room Operators Against an 02/75 l

Accidental Chlorine Release 1

01/77 1.96 Design of Main Steam Isolation Valve Leakage Control Systems for Boiling 05/75 i

Water Reactor Nuclear Power Plants 1

06/76 i

l 1.97 Instrumentation for Light-Water-Cooled Nuclear Power Plants To Assess Plant 12/75 i

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 1.95 Assumptions Used for Evaluating the Potential Radiological Consequences of a 03/76 i

Radioactive Offgas System Failure in a Boiling Water Reactor (for Comment) 1.99 Radianon Embrittlement of Reactor Vessel Materials (Draft ME 305-4, 07/75 Proposed Revision 2, published 2/S6) 1 04/77 2

05/88 1.100 Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power 03/76 q

Plants (Draft EE 105-5, Proposed Revision 2 published S/87) 1 08/77 06/88

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1.101 Tmergency Planning and Preparedness for Nuclear Power Reactors (Revision 1 11/75 j

to this guide entitled " Emergency Planning for Nuclear Power Plants" was 1

C3/77 i

j withdrawn-see 45 FR 69610,10/21/80.) (Draft DG-1022, Proposed 2

10/81 j

Revision 3, punished 2/92) 3 08/92 j

l 6

Division 1 b

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Guide Published j

Number Title Rev.. Month / Year 1.102 Flood Protection for Nuclear Power Plants 10/75 1

1 09/76 1.103 (Withdrawn-See 46 FR 37579, 7/21/81) i j

1.104 (Withdrawn-See 44 FR 49321, 8/22/79) See NUREG-0554, " Single-Failure-i Proof Cranes for Nuclear Power Plants."

1.105 Instrument Setpoints for Safety-Related Systems (Draft IC 010-5. Proposed 11/75 Revision 2, published 12/81) 1 11/76' 2

02/86 k

j 1.106 Thermal Overload Protection for Electric Motors on Motor-Operated Valves 11/75 f

1 03/77

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1.107 Qualifications for Cement Grouting for Prestressing Tendons in Containment 11/75 l

i Structures 1

02/77 l

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1.108 (Withdrawn-See 58 CFR 41813, 8/5/93) (Periodic Testing of Diesel Generator j

Units Used as Onsite Electric Power Systems at Nuclear Power Plants) b i

1.109 Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents 03/76 l

for the Purpose of Evaluating Compliance with 10 CFR Part 50. Appendix 1 1

10/77 i

1.110 Cost-Benefit Analysis for Radwaste Svstems for Light-Water-Cooled Nuclear 03/76 i

Power Reactors (for Comment) i-7 i

i

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1.111 Methods for Estimating Atmospheric Transport and Dispersion of Gaseous 03/76 l

Effluents in Routine Releases from Light-Water-Cooled Reactors 1

07/77 j

f 1.112 Calculation of Releases of Radioactive Materials in Gaseous and Liquid 04/76 l

Effluents from Light-Water-Cooled Power Reactors O-R 05/77 1.113 Estimating Aquatic Dispersion of Effluents from Accidental and Routine 05/76 i

Reactor Releases for the Purpose of implementing Appendix I 1

04/77 j

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 i

i published 12/86) 2 05/89 1.115 Protection Against Low-Trajectory Turbine Missiles 03/76 1

07/77' i

l 1.116 Ouality Assurance Requirements for Installation, Inspection, and Testing of 06/76 l

Mechanical Equipment and Systems 0-R 05/77 I

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1.117 Tornado Design Classification 06/76 l

V 1

04/78 1.118 Periodic Testing of Electric Power and Protection Systems 06/76 l

l 1

11/77 I

2 06/78 i

i 1.119 (Withdrawn-See 42 FR 33387, 6/30/77) 1 i

j 1.120 Fire Protection Guidelines for Nuclear Power Plants (for Comment) 06/76 1

11/77 l

j 1.121 Bases for Plugging Degraded PWR Steam Generator Tubes (for Comment) 08/76 j-7 Division 1 l

1 1

4

i 1

J l

1 i

Guide Published l

Number Title Rev.

Month / Year 1.122 Development of Floor Design Response Spectra for Seismic Design of Floor-09/76 Supported Equipment or Components 1

02/78 l

1.123 (Withdrawn-See 56 FR 36175, 7/31/91) i 1.124 Service Limits and Loading Combinations for Class 1 Linear-Type Component 11/76 Supports 1

01/78 l

1.125 Physical Models for Design and Operation of Hydraulic Structures and Systems 03/77 3

for Nuclear Power Plants 1

10/78 1

1 1.126 An Acceptable Model and Related Statistical Methods for the Analysis of Fuel 03/77 l

Densification 1

03/78 l

1.127 Inspection of Water-Control Structures Associated with Nuclear Power Plants 04/77 i

1 03/78 1

l 1.128 Installation Design and Installation of Large Lead Storage Batteries for Nuclear 04/77 j

Power Plants 1

10/78 j

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 i

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 pubhshed 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 l

1.135 Normal Water Level and Discharge at Nuclear Power Plants (for Comment) 09/77 1 136 Matenals, Construction, and Testing of Concrete Containments (Articles 11/77 CC-1000 -2000, and -4000 through -6000 of the Code for Concrete 1

10/78 l

Reactor Vessels and Containments") (Draft SC 814-5, Proposed Revision 2.

2 06/81

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published 11/79) 01/78 I

2.137 Fuel-Oil Systems for Standby Diesel Generators 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 i

Sptem Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear 1

10/79 Power Plants 8

Division 1 i

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l l

r Guide Published l

Number Title R ev.

Month / Year 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 t

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 l

1.144 (Withdrawn-See 56 FR 36175, 7/31/91)

I 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 l

1.146 (Withdrawn-See 56 FR 36175, 7/31/91) l

's 1.147 Inservice Inspection Code Case Acceptability-ASME Section X1, Division 1 10 07/93

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(Draft SC 721-4 published 8/79) Previous revisions and their publication dates i

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;

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8, 11/90; 9, 4/92.

i 1.148 Functional Specification for Active Valve Assemblies in Systems important to 03/81 l

Safety in Nuclear Power Plants (Draft SC 704-5 published 2/79)

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i 1.149 Nuclear Power Plant Simulation Facilities for Use in Operator License 04/81 l

Examinations (Draft RS 110-5 published 7/80) (Draft OL 402-5, Proposed 1

04/87 t

Revision 1, published 11/84) 1.150 Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice 06/81 Examinations (Draft SC 705-4 published 5/79) 1 02/83

[

l 1.151 Instrument Sensing Lines (Draft IC 126-5 published 3/82) 07/83 1.152 Criteria for Programmable Digital Computer System Software in Safety-Related 11/85 i

Systems of Nuclear Power Plants (Draft IC 127-5 published 3/83)

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1.153 Criteria for Power. Instrumentation, and Control Portions of Safety Systems 12/85-

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(Draft IC 609-5 published 12/82) 1 l.

1.154 Format and Content of Plant-Specific Pressurized Thermal Shock Safety 01/87 i

Analysis Reports for Pressurized Water Reactors (Draft SI 502-4 published 1/86) 08/88 1.155 Station Blackout (Draft SI 501-4 published 3/86) (Issued June 1988, reissued August 1988 with corrected tables) l 1.156 Environmental Qualification of Connection Assemblies for Nuclear Power Plants 11/87 i

(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) i 1.159 Assuring the Availability of Funds for Decommissioning Nuclear Reactors 08/90 (Draft DG-1003 published 5/89) l 1.160 Monitoring the Effectiveness of Maintenance at Nuclear Power Plants 06/93-I (Draft DG-1020 published 11/92) i 9

Division 1

DIVISION 1 1

DRAFT REGULATORY GUIDES Task Published i

Number 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 Programs for Nuclear Power Plants 08/89 DG-1005 Standard Format and Content for Decommissioning Plans for Nuclear Reactors 09/89 i

DG-1006 Records Important for Decommissioning of Nuclear Reactors 09/89

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DG-1008 Reactor Coolant Pump Seals 04/91 4

DG-1009 Standard Format and Content of Technical Information for Applications To 12/90 1

Renew Nuclear Power Plant Operating Licenses DG-1010 (Proposed Revision 4 to Regulatory Guide 1.28) Quahty Assurance Program 11/92 Requirements DG-1015 ldentification and Characterization of Seismic Sources, Deterministic Source 11/92

)

Earthquakes, and Ground Motion DG-1016 (Second Proposed Revision 2 to Regulatory Guide 1.12, previously issued as MS 140-5) 11/92

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Nuclear Power Plant Instrumentation for Earthquakes t

l DG-1017 Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator 11/92 Postearthquake Actions DG-1018 Restart of a Nuclear Power Plant Shut Down by a Seismic Event 11/92 DG-1023 Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy l

Less than 50 Ft-lb 09/93 l

DG-1025 Calculational and Dosimetry Methods for Determining Pressure 09/93 Vessel Neutron Fluence EM 805-5 Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power 02/79 i

l Plants ES 926-4 (Second Proposed Revision 1 to Regulatory Guide 1.23) Meteorological Measurement 04/86 l

Program for Nuclear Power Plants FP S11-4 Safety Related Permanent Dewatering Systems for Nuclear Power Plants 09/79 f

l IC 121-5 Response-Time Testing of Protection System Instrument Channels 01/82 i

i IC 131-5 Installation of Transducers 03/82

~

I l

MS 021-5 Containment System Leakage Testing 10/86 j

MS 901-4 Identification of Valves for loclusion in Inservice Testing Programs 11/81 l

RS 050-2 (Proposed Revision I 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 I

i i

10 Division 1 1

I

I Task Published Number Title Month / Year RS S09-5 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, Soils, and Foundations During the Construction Phase of Nuclear Power Plants SC 521-4 LWR Core Reloads; Guidance on Applications for Amendments to Operating 09/79 Licenses and on Refueling and Stanup Tests 1-l SC 70S-4 (Withdrawn-See 54 FA 16030, 4/20/89) l-4 e

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11 Division ' 1

U.S. NUCLEAR REGULATORY COMMISSION REGULATORY GUIDE SERIES 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 Us.

09/75 in Research Reactors 1

07/76 t,

2.4 Review of Experiments for Resaarch Reactors 07/76 O-R 05/77 2.5 Quahty 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 0

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O' I

e 12 Division 2

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.U.S. NUCLEAR REGULATORY COMMISSION REGULATORY GUIDE SERIES

(

i

\\

DIVISION 3 - FUELS AND MATERIALS FACILITIES ACTIVE REGULATORY GUIDES Guide Published l

Number Title R ev.

Month / Year 3.1 Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of 01/73 i

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 j

i 3.2 Efficiency Testing of Air-Cleaning Systems Containing Devices for Removal of 01/73 l

Particles l

3.3 Quality Assurance Program Requirements for Fuel Reprecessing Plants and for 01/73 Plutonium Processmg and Fuel Fabrication Plants 1

03/74 j

t 3.4,," Nuclear Criticality Safety in Operations with Fissionable Materials at Fuels and 01/73 l

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 i

f 3.6 Content of Technical Specifications for Fuel Reprocessing Plants 04/73 J

t 3.7 Monitoring of Combustible Gases and Vapors in Plutonium Processing and Fuel 03/73 Fabrication Plants 3.S Preparation of Environmental Reports for Uranium Mi"s 04/73 l

1 09/78 I

2 10/82-1 3.9 Concrete Radiation Shields 06/73 3.10 Liquid Waste Treatment System Design Guide for Plutonium Processing and Fuel 06/73 Fabrication Plants

[

4 t

3,11 Design, Construction, and Inspection of Embankment Retention Systems for 06/73 j

Uranium Mills 1

03/77 4

2 12/77 l

l 3.11.1 Operational Inspection and Surveillance of Embankment Retention 04/79 Systems for Uranium Mill Tailings 1

10/80 1i 3.12 General Design Guide for Ventilation Systems of Plutonium Processing and Fuel 08/73 Fabrication Plants f

10/73 3.13 Guide for Acceptable Waste Storage Methods at UF8 Production Plants -

I 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 Unirradiated Power Reactor Fuel and Associated Radioactive Material (Draft 1

04/83

'}

CE 219-4, Proposed Revision 1, published 8/82)

[-t i

13 Division 3

-(

d

i Guide Published Number Title Rev.

Month / Year 3.15 General Fire Protection Guide for Plutonium Processing and Fuel Fabrication 01/74 Plants 3.17 Earthquake Instrumentation for Fuel Reprocessing Plants 02/74 3.! S Confinement Barriers and Systems for Fuel Reprocessing Plants 02/74 i

j 3.19 Reporting of Operating Information for Fuel Reprocessing Plants 02/74 I

3.20 Process Offgas Systems for Fuel Reprocessing Plants 02/74 l

3.21 Quahty Assurance Requirements for Protective Coatings Applied to Fuel 03/74 Reprocessing and to Plutonium Processing and Fuel Fabrication Plants

)

i 3.22 Periodic Testing of Fuel Reprocessing Plant Protection System Actuation 06/74 j

Functions

]

3.23 (Withdrawn-See 45 FR 71876,10/30/80) 3.24 (Withdrawn-See 46 FR 14507, 2/27/81) 1 3.25 Standard Format and Content of Safety Analysis Reports for Uranium 12/74 j

Enrichment Facilities 3.26 Standard Format and Content of Safety Analysis Reports for Fuel Reprccessing 02/75 1

Plants i

j 3.27 Nondestructise Examination of Welds in the Liners of Concrete Barriers in Fuel 05/75 Reprocessing Plants 1

05/77 a

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 1

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, Apphcation, 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 j

0-R 05/77 3.32 General Design Guide for Ventilation Systems for Fuel Reprocessing Plants 09/75 1

(for Comment) l 3.33 Assumptions Used for Evaluating the Potential Radiological Consequences of 04/77 Accidental Nuclear Criticality in a Fuel Reprocessing P' ant (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 e

3.35 Assumptions Used for Evaluating the Potential Radiological Consequences of 05/77 j

Accidental Nuclear Criticality in a Plutonium Processing and Fuel Fabrication 1

07/79 j

Plant

]

l 3.36 (Withdrawn-See 44 FR 6535, 2/1/79) 1 14 Division 3

I l

Published Guide 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) 06/76 339 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 Plutoniurn Processing 11/76 and Fuel Fabrication Plants 1

12/77 3.41 (Withdrawn-See 51 FR 11660, 4/4/86) 3.42 Emerp.ency Planning for Fuel Cycle Facilities and Plants Licensed Under 10 CFR 08/77 Parts 50 and 70 1

09/79 J

3.43 Nuclear Criticality Safety in the Storage of Fissile Materials 08/78 1

04/79 l

3.44 Standard 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 Revision 2, published 11/86) 2 01/89 3.45 Nuclear Crincality Safety for Steel-Pipe Intersections Containing Aqueous 11/80 Solutions of Fissile Materials (Draft FP 925-5 published 1/80) (Draft CE S02-5, 1

04/89 Proposed Revision 1, put. 'shed 5/88) 3.46 Standard Format and Content of License Applications, including Environmental 06/S2 Report, for In Situ Cranium 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/S0) 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 Inde,endent Spent Fuel Storage Installation (Water-Basin Type) 12/81 (Draft FP B06-6 published 1/81) 3.50 Standard Format and Content for a License Application To Store Spent Fuel 01/82 and IIigh-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 03/52 Radioactive Materials Resulting from Uranium Milling Operations (Draft s

R11 802-4 published 5/79) (Errata published August 1982) 3.52 Standard Format and Content for the Health and Safety Sections of License 07/52 Renewal Appbcations for Uranium Processing and Fuel Fabrication (Draft 1

11/86 l

FP 716-4 published 10/80) (Draft CE 308-4, Proposed Revision 1, published

[

7/85) 3.53 Apphcabihty of Existing Regulatory Guides to the Design and Operation of an 07/82 Independent Spent Fuel Storare Installation (Draft CE 037-4 published 11/81) 3.54 Spent Fuel IIcat Generation in an Independent Spent Fuel Storage Installation 09/84 (Draft FP 034-4 pubbshed 12/S0) (Second Draft CE 034-4 pubbshed 1/83) 15 Division 3

l l

Guide Published l

Number Title Rev.

Month / Year 1

3.55 Standard Iormat and Content 'or the Health and Safety Sections of License 04/85 l

Renewal Apphcations for Uran.um llexafluoride Production (Draft CE 227-4 j

pubbshed 1/h4) 3.56 General Guidance for Designing Testing, Operating, and Maintaining Emission 05/86 l

Control Deuces at Uranium Mails (Draft CE 309-4 pubbshed 5/f 5) 3.57 Adrmnistrain'e Practices for Nuclear Criticahty Safety at Fuels and Matenals 10/86 Facilities (Draf t CE 501-4 pubbshed 2/86) 1 l

3.58 Criticahty Safety for Handhng Storing, and Transporting LWR Fuel at Fuels 10/86 1

and Matenals Facihties (Draft CE 407-4 published 7/85) (Draft DG-3004, j

Proposed Resision 1, pubbshed 5/90) 3.59 Methods for Esumating Radioactive and Toxic Airborne Source Terms for 03/87 Uranium Milbng Operations (Draft WM 407-4 pubbshed 4/86) 3.60 Design of an Independent Spent Fuel Storage Installation (Dry Storage) (Draft 03/87 CE 410-4 published 11/85) l 3.61 Standard Format and Content for a Topical Safety Analysis Repon for a Spent 02/89 Fuel Dry Storage Cask (Draft Cl! 306-4 pubhshed 4/86) 3.62 Standard Format and Content for the Safety Analysis Report for Onsite Storage 02/89 of Spent Fue! Storage Casks (Draft CE 301-4 pubbshed 4/86) 3.63 Ons:te Meteorological Measurement Program for Uranium Recosery Facilitics-03/F8 Data Acqumtion and Reporting fDraft ES 401-4 published 9/85) 3.64 Calculanon of Radon Flux Attenuation by Earthen Uranium Mill Tailings 06/89 j

Covers (Draf t WM 503-4 pubbshed 5/87) j 3.05 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 Fmancial Assurance Mechanisms Required for 06/90 Decommissioning Under 10 CFR Parts 30, 40, 70, and 72 (Draft DG-3002 l

pubbsbed 1/90) 3.67 Standard Format and Content for Emergency Plans for Fuel Cycle and Materials 01/92 i

f acihties (Draf t DG-3005 pubbshed 9/90) i 1

5 l

I 16 Division 3 a

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DIVISION 3 DRAIT REGULATORY GUIDES Task Published Number Title Month / Year i

4

\\

l DG-3001 Records Important for Decommissioning for Licensees Under 10 CFR Parts 30, 07/89 40, 70, and 72 i

DG-3003 Format and Content for the License Application for the High-Level 11/90 Waste Repositar, l~

DG-3004 (Proposed Revision 1 to Regulatory Guide 3.58) Criticality Safety for Handling, 05/90 Storing, and Transponing LWR Fuel at Fuels and Materials Facilities i

DG-3006 Standard Format and Content for Fire Protection Sections of License 04/93 Applications for Fuel Cycle Facilities DG-3008 Nuclear Criticahty Safety Training 01/93 DG-3009 Topical Guidelines for the Licensing Support System 07/93 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 liF 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 i

Facilities WM 039-4 (Proposed Revision 2 to Regulatory Guide 3.5) Standard Format and Content of 08/81 License Applications fe Uranium Mills J

.~

17 Division 3

U.S. NUCLEAll ItEGUIATOltY COMMISSION ItEGUIATOltY GUIDE SEltIES DIVISION 4 - ICNVIItONMENTAL 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 I to Regulatory Guide 4.2 DG-4002, pubbshed S/91) 1 01/75 2

07/76 4.3 (Withdrawn-See 41 FR 53870,12/9/76) 4.4 Reponing Procedure for Mathem tical Models Selected To Predict lleated 05/74 Effluent Dispersion in Natural Water Bodies 4.5 Measurements of Radionuclides in the Environment-Sampling and Analysis of 05/74 Plutonium in Soit 4.6 Measurements of Radionuclides in the Environment-Strontium-89 and 05/74 Strontium-90 Analyses 4.7 General Site Suitability Criteria for Nuclear Power Stations (DG-4003, 09/74

~

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 Environmen:al 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 07/7f 1

08/77 4.12 (Not published) 4.13 Performance, Testing, and Procedural Specifications for Thermoluminescence 11/76 Dosimetry: Environmental Apphcations 1

07/77 4.14 Radiological Effluent and Environmental Monitoring at Uranium Mills 06/77 1

04/80 4.15 Ouahty 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 hadioactive Materiais in 03/78

(

Liquid and Gaseous Ef fluents from Nuclear Fuel Processing and Fabrication 1

12/85 Plants and Uranium liexafluoride Production Plants (Draft CE 401-4, Proposed Revision 1, published 9/84) (Errata pubbshed 8/86) l 4.17 Standard Format and Content of Site Characterization Plans for Iligh-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) 16 Division 4

Published Guide Number Title Rev.

Month / Year 4.18 Standard Format and Content of Environmental Reports for Near-Surface 06/83 i

Disposal of Radioactive Waste (Draft WM 013-4 published 4/82) j 08/88 4.19 Guidance for Selecting Sites for Near-Surface Disposal of Low-Level Radioactive Waste (Draft WM 408-4 published 3/87) 1 s

1 I

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l 19 Division 4 -

l DIVISION 4

]

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 i

Application To Renew a Nuclear Power Station Operating License

~

DG-4003 (Proposed Revision 2 to Regulatory Guide 4.7) General Site Suitability 11/92 Criteria for Nuclear Power Stations O

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U.S. NUCLEAR REGULATORY COMMISSION REGULATORY GUIDE SERIES J

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 e

5.2 (Withdrawn-See 44 FR 57542,10/5/79) 1.3 Statistical Terminology and Notation for Special Nuclear Materials Control and 02/73 J

Accountability 5.4 Standard Analytical Methods for the Measurement of Uranium Tetrafluoride 02/73 (UF ) and Uranium Hexafluoride (UFe) 4 5.5 Standard Methods for Chemical, Mass Spectrometric, and Spectrochemical 02/73 I

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 l

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 1

l 5.10 Selection and Use of Piessure-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 Cor. trol of Facilities and Special 11/73 Nuclear Materials 5.13 Conduct of Nuclear Material Physical Inventories 11/73 5.14 Use of Observe. 2 (Visual e.aneillance) Techniques in Material Access Areas 11/73 4

(Draft SG 910-.1, Proposed Revision 1, published 5/79) 1 05/60 5.15 Security Seals for the Protection and Control of Special Nuclear Material.

01/74 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) 21 Division 5

- -.... ~ -.

~.. -. =.

. = -

l t

j Guide Published i

Number Title Rev.

Month / Year 5.20 Trainmg, Equipping, and Quahfying of Guards and Watchmc')

01/74 5.21 Nondestructive Uratuum-235 Ennchment Assay by Gamma Ray Spectrometry 04/74 j

(Draft SG 044-4, Proposed Revision 1, pubinhed 6/62) 1 12/83 j

5.22 Assessment of the Assumption of Normality (Employing Individual Observed 04/74 Values) t 5.23 In Situ Assay of Plutonium Residual lloldup (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 ' Special Nuclear Material 06/74

]

5.25 Design Considerations for Minimizing Residual IIoldup of Special Nuclear Material -

06/74 in Equipment for Wet Process Operations l

5.26 Selection of Material Balance Areas and Item Control Areas 06/74 l

1 04/75 t

5.27 Special Nuclear Material Doorway Monitors 06/74 5.28 Evaluation of Shipper-Receiver Ddferences in the Transfer of Special Nuclear 06/74 I

l Materials 5.29 Nuclear Matenal Connot Systems for Nuclear Power Plants 06/74 l

1 06/75 5.30 Materials Protection Contingency Measures for Uranium and Piutonium Fuel 06/74 Manufacturing Plants i

5.31 Specially Designed Vehicle with Armed Guards for Road Shipment of Special 06/74 i

l Nuclear Material 1

04/75

~

l' 5.32 Commumcation with Transport Vehicles 06/74 I

1 05/75 l

5.33 Statistical Evaluation of Material Unaccounted For 06/74 5.34 Nondestructise Assay for Plutonium in Scra;, 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, S/18/77) 5.36 Recommended Practice for Dealing with Outlying Observations 06/74 5.37 In Situ Assay of Enriched Uranium Residual IIoldup (Draft SG 047-4, Proposed 08/74 Revision 1, published 8/82) 1 10/83 f

~

5.38 Nondestructive Assay of liigh-Enrichment Uranium Fuel Plates by Gamma Ray 09/74 f

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) 22 Division 5 1

1 i

Guide Published Number Title Rev.

Month / Year

(

5.42 Design Considerations for Minimizing Residual lloldup 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 Systems (Draft SG 479-4, Proposed Revision 2, 01/75 published.5/79) 1 06/76 2

05/80 5.45 Standard Format and Content for the Special Nuclear Material Control and 12/74 l

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 Managemera Review of Nuclear Material Control and Accounting Systems (for 06/75 l

Comment) 5.52 Standard Format and Content of a Licensee Physical Protection Plan for 05/75 l

l Strategic Special Nuclear Material at Fixed Sites (Other than Nuclear Power 1

06/76 l

Plants) 2 07/80 1

1 5.53 Qualification Cahbration, and Error Estimation Methods for Nondestructive 08/75 l

Assay (Draft SG 049-4, Proposed Revision 1, published 6/82) 1 02/84 1

5.54 Standard Format and Content of Safeguards Contingency Plans for Nuclear 03/7' Power Plants (for Comment) l 5.55 Standard Format and Content of Safeguards Contingency Plans for Fuel Cycle 03/78 Facilities (for Comment) l l

5.56 Standard Format and Content of Safeguards Contingency Plans for 03/78 l

Transportation (for Comment) 06/76 5.57 Shipping and Receiving Control of Strategic Special Nuclear Material (Draft 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 4

5.59 Standard Format and Content for a Licensee Physical Security Plan for the

.01/80 l

Protection of Special Neckar Material of Moderate or Low Strategic 1

02/83 Signihcance (Draft MP 711-4 published 7/79) (Draft SG 229-4, Proposed Revision 1, published 9/82)

F 5.60 Standard Format and Content of a Licensee Physical Protection Plan for Strategic -

04/80 Special Nuclear Material in Transit 06/80 5.61 Intent and Scope of the Physical Protection Upgrade Rule Requirements for Fixed Sites 23 Division 5

Guide Published Number Title Rev.

Month / Year 5.62 Reporting of Safeguards Events (Draft SG 901-4 pubhshed 10/79) (Draft 02/81 SG 901-4, Proposed Revision 1, published 10/85) 1 11/87 5.63 Physical Protection for Trar ent Shipments (Draft SG 126-4 published 9/81) 07/82 5.64 (Not issued) l 5.65 Vital Area Access Controls, Protection of Physical Security Equipment, and 09/66 Key and Lock Controls (Draft SG 302-4 published 1/85) 5.66 Access Authorization Program for Nuclear Power Plants 06/91 I

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I DIVISION 5 l

DRAFT REGULATORY GUIDES Task Published Number Title Month / Year l

DG-5002 Material Control and Accounting for Uranium Enrichment Facilities 02/91 Authorized To Produce Special Nuclear Material of Low Strategic Significance SG 301-4 (Withdrawn-See 56 FR 36175, 7/31/91) l a

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U.S. NUCLEAR REGULATORY COMMISSION REGULATORY GUIDE SERIES 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 Cenain 03/74 Land and Sea Applicadons 6.4 Classification of Containment Properties of Sealed 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 f

6.6 Acceptance Sampling Procedures for Exempted and Generally Licensed items 06/74 i

Containing Byproduct Material 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 I

6.8 Identification Plaque for Irretrievable Well-Logging Sources (for Comment) 10/78 i

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-s DIVISION 6 DRAFT REGULATORY GUIDES Task Published Numlier Title Month / Year TP 102-5 Safety Features of Gauges Containing Radioactive Material 11/80 l

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U.S. NUCLEAR REGULATORY COMMISSION REGULATORY GUIDE SERIES 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 Crneria for the Structural Analysis of Shipping Cask Containment Vessels 02/77 1

03/78 7.7 Admimstrative 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 Matenal (Draft MS 527-4, Proposed Revision 1, published 7/87) (Draft MS 1

03/89 804-4, Second Proposed Revision 1, published 9/88) 7.9 Standard Format and Content of Part 71 Applications for Approval of Packaging 03/79 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 Ba.ce Material for Ferritic Steel Shipping Cask 06/91 Containment Vessels with a Maximum Wall Thickness of 4 Inches (0.1 m)

(Draf t 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 Containment 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)

(Draft DG-7002 published 7/89)

O 28 Division 7

DIVISION 7 DRAI'r REGULATORY GUIDES Task Published Number Title Month / Year I

FC 416-4 (Proposed Revision 2 to Regulatory Guide 7.9) Standard Format and Content of 05/86 I

I 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 Materials O

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29 Division 7

U.S. NUCLEAR REGULATORY COMMISSION REGULATORY GUIDE SERIES SS DIVISION 8 - OCCUPATIONAL HEALTH ACTIVE REGULATORY GUIDES Guide Published Number Title Rev.

Month / Year 8.1 Radiation Symbol 02/73 8.2 Guide for Administrative Practices in Radiation Monitoring 02/73 8.3 Film Badge Performance Criteria 02/73 8.4 Direct-Reading and Indirect-Reading Pocket Dosimeters 02/73 8.5 Criticality and Other Imerior Evacuation Signals 02/73 1

03/81 8.6 Standard Test Procedure for Geiger-Muller Counters 05/73 8.7 Instructions for Recording and Reponing Occupational Radiation Exposure 05/73 Data (Draft DG-8007. Proposed Revision 1, published 11/91) 1 06/92 8.8 Information Relevant to Ensuring that Occupational Radiation Exposures at 07/73 Nuclear Power Stations Will Be As Low As is Reasonably Achievable (Draft 1

09/75 Oli 507-4 Proposed Revision 4. published 3/79) (Draft OP 618-4, Second 2

03/77 Proposed Revision 4, published 5/82) 3 06/78 8.9 Acceptable Concepts, Models. Equations, and Mumptions for a Bioassay 09/73 Program (Draft DG-8009, Proposed Revision 1, published 12/91) 1 07/93 8.10 Operating Philosophy for Maintaining Occupational Radiation Exposures As Low 04/74 As Is Reasonably Achievable 1

09/75 1-R 05/77 8.11 Applications of Bioassay for Uranium 06/74 S.12 Criticality Accident Alarm Systems (Draft OH 015-4, Proposed Revision 1 12/74 published 5/80) (Draft CE 801-5, Proposed Revision 2, published 5/88) 1 01/81 2

10/88 8.13 Instruction Concerning Prenatal Radiation Exposure (Draft OP 031-4, Proposed 03/75 Revision 2, published 8/81) 1 11/75 2

12/87 8.14 Personnel Neutron Dosimeters (Draft OH 940-4 Proposed Revision 2 06/76 published 2/80) 1 08/77 i

S.15 Acceptable Programs for Respiratory Protection 10/76 8.16 (Not nued) 8.17 (Not issued) 8.18 Information Relevant to Ensuring that Occupational Radiation Exposures at 12/77 Medical Institutions Will Be As Low As Reasonably Achicvable 1

10/82 8.19 Occupational Radiation Dose Assessment in Light-Water Reactor Power Plants-05/78 Design Stage Man-Rem Estimates 1

06/79 30 Division 8

Gulde Published Number Title Rev.

Month / Year 8.20 Applications of Bioassay ior I-125 and 1-131 04/78 1

09/79 8.21 Ilealth Physics Surveis for Byproduct Material at NRC-Licensed Processing and 05/78 Manufacturing Plants 1

10/79 8.22 Bioassay at U2anium Mills (Draft OP 013-4, Proposed Revision 1 07/78 published 1/87) 1 08/88 8.23 Radiation Safety Surveys at Medical Institutions 02/79 l

1 01!81 8.24 Health Physics Surveys During Enriched Uranium-235 Processing and Fuel 11/78 Fabrication 1

10/79 e

8.25 Air Sampling in the Workplace (Draft 011 905-4 published 10/79) (Draft 08/80-DG-8003. Proposed Revision 1, published 9/91) 1 06/92 8.26 Applications of Bioassay for Fission and Activation Products (Draft Oli 714-4 09/80 -

published 8/79) 8.27 Radiation Protection Training for Personnel at Light-Water-Cooled Nuclear 03/S1 Power Plants (Draft Oil 717-4 published 8/79) 8.28 Audible-Alarm Dosimeters (Draft Oli 804-4 published 8/79) 08/81 8.29 Instruction Concerning Risks from Occupational Radiation Exposure (Draft 07/81 Oli 902-4 published 5/80) 8.30 licalth Physics Surveys in Uranium Mills (Draft 011 710-4 published 8/80) 06/83 l

8.31 Information Relevent to Ensuring that Occupational Radiation Exposures at 05/83 Uranium Mills Will Be As Low As Is Reasonably Achievable (Draft OH 941-4 published 8/80) 8.32 Criteria for Establishing a Tritium Bioassay Program (Draft OP 713-4 07/88-published 6/83) 8.33 Ouality Management Program (Draft DG-8001 published 1/90) 10/91 07/92 8.34 Monitoring Criteria and Methods To Calculate Occupational Radiation Doses (Draft DG-8010 published 2/92) 8.35 Planned Special Exposures (Draft DG-8008 published 12/91) 06/92 8.36 Radiation Dose to the Embryo / Fetus (Draft DG-8011 published 2/92) 07/92 e-8.37 ALARA. Levels for Effluents from Materials Facilities (Draft DG-8013 07/93 d

published 10/92) 8.38 Control of Access to.Iligh and Very liigh Radiation Areas of Nuclear Plants 06/93 (Draft DG-8006 published 10/91) 31 Division 8

4 DIVISION 8 DRAFT REGULATORY GUIDES I

i Published Task Number Titic Month / Year DG-8004 Radiation Protection Programs for Nuclear Power Plants 10/91 4

J

' DG-5005 Withdrawn-See 58 FR 17628, 4/5/93 (Assessing External Radiation Doses from i

Airborne Radioactive Materials) t l

OH 940-4 (Proposed Revision 2 to Regulatory Guide 8.14) Personnel Neutron Dosimeters 02/80 i

OP 032-5 Test and Calibration of Radiation Protection Instrumentation 09/S4 OP 212-4 Radiation Protection Training for Personnel Employed in Medical Facilities 01/84 OP 616-4 (Second Proposed 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)

  • f OP 722-4 Qualifications for the Radiation Safety Officer in a Large-Scale Non-Fuel-Cycle 04/82

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32 Division 8 1

U.S. NUCLEAR REGULATORY COMMISSION REGULATORY GUIDE SERIES DIVISION 9 - ANTITRUST AND FINANCIAL REVIEW ACTIVE REGULATORY GUIDES C uide Published Number Title Rev.

Month / Year 9.1 Regulatory Staff Position Statement on Antitrust Matte s 12/73 9.2 Information Needed by the NRC Staff in Connection with its Antitrust Review 10/74 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 9.4 Suggested Format for Cash Flow Statements Submitted as Guarantees of 09/78

=

Payment of Retrospective Premiums (for Comment)

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l 33 Division 9

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 Applications f or 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 FC 408-4, Proposed Revision 2, published 2/85) 1 12/80 10.6 Guide for the Preparation of Applications for Use of Sealed Sources and Devices 09/76 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, published 10/84) 10.7 Guide for the Preparation of Applications for Licenses for Laboratory and 02/77 Industrial Use of Small Quantities of Byproduct Material (Errata published 7/84) 1 08/79 10.8 Guide for the Preparation of Applications for Medical Use Programs (Draft 01/79 FC 415-4, Proposed Revision 2, published 8/85) (Draft DG-0002, Proposed 1

10/80 Appendix X to Regulatory Guide 10.8, published 12/91) (Appendix X 2

08/87 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 published 8/86)

  • e 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)

O 34 Division 10 l

I

l DIVISION 10 DRAFT REGULATORY GUIDES Task Published Number Title Month / Year i

FC 401-4 (Proposed Revision 2 to Regulatory Guide 10.6) Guide for the Preparation of 10/84 Applications for the Use of Sealed Sources and Devices for Performing Industrial Radiography FC 403-4 Guide for the Preparation of Applications for Licenses for the Use of Panoramic Dry 01/85 l

Source-Storage irradiators. Self-Contained Wet Source-Storage Irradiators, and Panoramic Wet Source Storage Irradiators e

FC 404-4 Guide for the Preparation of Applications for Licenses for the Use of Scaled Sources 01/85 in Nonportable Gauging Devices l

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 I

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 407-4 Guide for the Preparation of Applications for Licenses for the Use of Sealed Sources 01/85

[

in Portable Gauging Devices 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 FC 410-4 Guide for the Preparation of Applications for Nuclear Pharmacy Licenses 08/85 t

I 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 i

FC 412-4 Guide for the Preparation of Applications for Licenr.es for the Use of Radioactive 06/85

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Materials in Leak Testing Services j

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 j

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) l

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