ML20202F754

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ML20202F754
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RTR-REGGD-GENERA NUDOCS 9712090219
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{{#Wiki_filter:p# 88g 3+ t UNITC3 STATES 0 ) NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 305654001

V s,*****/g October 31,1997 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 necded 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. Occupatio'tal llealth 4. Environmental and Siting 9. Antitrust and Financial Review 5. Materials and Plant Protection

10. General (9

DrafI regulatory guides are issued for public comment in the early stages of the development of a V regulatory position.They have not received complete staff review and do not present an ofilcial NRC i 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 Regulatory guides may be withdrawn when they are superseded by the Commission's regulations, when equivalent recommendations have been incorporated in applicable approved codes and stan.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. 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 20555-0001, or by fax et (301) 415-5272. 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. Rei m's for placement on an automatic distribution list for single copies of future draft guides in spec..a Jivisions 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. 'g If you have a question on specific guides in this list, please conta Regulatory Research, U.S Nuclear Regulatory Commission, Washington, DC 20555, telephone f (301) 415-5890. I p). (a lllllll 9712090219 971031 PDR REGOD GENERAL PDR

October 31,1997 Ci U.S, NUCLEAR REGUIATORY COMMISSION s'] REGULATORY GUIDE SERIES DIVISION 1 - POWER REACTORS ACTIVE REGU1ATORY GUlDES Guide Published Number Title Rev. Month / Year 1.1 Net wsitive Suction llead for Emergency Core Cooling and Containmem Heat 11n0 Removal System Pumps (Safety Guide 1) 1.2 (Withdrawn-See 56 FR 36175,7/31/91) 1.3 Assumptions Used for Evaluulng the Potential Radiological Consequences of a 11n0 less of Coolant Accident for lloiling Water Reactors 1 06n3 2 06/74 1,4 Assumptions Used for Evaluating the Potential Radiological Consequences of a lin0 Loss of Coolant Accident for Pressurized Water Reactors 1 06n3 2 06n4 03/71 1.5 Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam Line lireak Accident for 11 oiling Water Reactors (Safety Guide 5) 1.6 Independence lletween Redundant Standby (Onsite) Power Sources and 03/71 lictween Their Distribution Systems (Safety Guide 6) 0301 1.7 Control of Combustible Gas Concentrations in Containment Following a Loss-of Coolant Accident 1 09/76 2 lin8 1.8 Qualification and Training of Personnel for Nuclear Power Plants (Draft RS 03n1 807-5, Proposed Revision 2, published 2n9; Draft RS 807-5, Second 1 09/75 Proposed Revision 2, published 9/30; Draft OL 403-5, Third Proposed 1-R 05n7 Revision 2, published 1/85; Draft DG-1012, Proposed Revision 3, published 2 04/87 9/96) Selection, Desis, Qualification, and Testing of Emergency Diesel Generator 03nt 1.9 n Units Used as Class IE Onsite Electric Power Systems at Nuclear Power Plants 1 1108 (Draft RS 802-5. Proposed Revision 3, published ll/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) 1.11 Instrument Lines Penetrating Primary Reactor Containment (Safety Guide 11) 03R1 Supplem,nt to Safety Gu!de 11, Backfitting Ccasiderations 02/72 L12 Nuclear Power Plant Instrumentation for Earthquakes (Draft MS 140-5, 03nl Proposed Revision 2, published 7/81)(DG-1016, the Second Proposed Revision 2, 1 04n4 published ll/92)(DG-1033, the Second Proposed Revision 2, published 2/95) 2 03/97 - C 1.13' Spent Fuel Storage Facility Design liasis (for Comment)(Draft CE 913-5, 03ni Proposed Revision 2, published 12/81) 1 12n5 1-Division 1

Guide Published Number Title Rev. Month / Year 1001 1.14 Reactor Coolant Pump Flywheel integrity (for Comment) 1 08D5 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 0904 3 0105 4 08n5 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) 12nl 1.20 Comprehensive Vibration.. essment Program for Reactor internals During Preoperational and initial Startup Testing 1 06/75 2 05/76 1.21 Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and 12nl Releases of Radioactive Materials in Liquid and Gaseous Efuuents from 1 06/74 Light Water Cooled Nuclear Power Plants 1.22 Periodic Testing of Protection System Actuation Functions (Safety Guid: 22) 02n2 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 4/86) 1.24 Assumptions Used for E/aluating the Potential Radiological Consequences of a 03n2 Pressurized Water Reactor Radicactive Gas Storage Tank Failure (Safety Guide 24) 1.25 Assumptions Used for Evaluating the Potential Radiological Consequences of a 03/72 Fuel llandling Accident in the Fuel llandling and Storage Facility for Boiling and Pressurized Water Reactors (Safety Guide 25) 1.26 Quality Group Classifications and Standards for Water, Steam, and 03n2 Radioactive-Waste-Containing Components of Nuclear Power Plants 1 0904 (for Comment) 2 06/75 3 02n6 1.27 Ultimate llent Sink for Nuclear Power Plants (for Comment) 03/72 1 03n4 2 01/76 1.28 Quality Assurance Program Recuirements (Design and Construction)(Draft 06/72 RS 002-5, Proposed Revision 3, published 3/81)(Draft DG-1010, 1 03n8 Proposed Revision 4, published 11/92) 2 02n9 3 08/85 1.29 SAraic Design Classification 06/72 1 08R3 2 02n6 3 09n8 Division 1 2

Guide Published fm Number Title Rev. Month / Year i \\ U l.30 Quality Assurance Requirements for the Installation, inspection, and Testing of 08/72 Instrumentation and Electric Equipment (Safety Guide 30) 1.31 Control of Ferrite Content in Stainter: Steel Weld Metal 08n2 1 06/73 2 05/77 3 04n8 1.32 Criteria for Safety Related Electric Power Systems for Nuclear Power Plants 08n2 1 03n6 2 02n7 1.33 Quality Assurance Program Requirements (Operation)(Draft RS 902 4, !!n2 Proposed Revision 3, published 899)(Draft RS 902-4. Second Proposed 1 02/77 Revision 3, puolished 11/80) 2 02n8 1.34 Control of Electroslag Weld Properties 12/72 1.35 Inservice inspectjon of Ungrouted Tendons in Prestressed Concrete Containment-02/73 (Draf t SC 810-4, Proposed Revision 3. nublished 4n9) 1 06/74 2 01/76 3 07/90 1.35.1 Determining Prestressing Forces for inspection of Prestressed Concrete 07/90 Q Containments (Draft SC 807-4 published 4/79) b 1.36 Nonmetallic Thermal Insulation for Austenitic Stainless Steel 02n3 1.37 Quality Assurance Requirements for Cleaning of Fluid Systems and Associated 03n3 Components of Water-Cooled Nuclear Power Plants 1.38 Quality Assurance Requirements for Packaging, Shipping Receiving, Storage, 03n3 and llandling of items for Water Cooled Nuclear Power Plants 1 10n6 2 05n7 1,39 Ilousekeeping Requirements for Water-Cooled Nuclear Power Plants 03/73 1 1096 2 09n7 1.40 Qualification Tests of Continuous-Duty Motors installed inside the Containment 03n3 of Water Cooled Nuclear Power Plants 1.41 Preoperational Testing of Redundant On Site Electric Power Systems To Verify 03R3 Proper lead Group Assignments 1.42 (Withdrawn-See 41 FR 11891,3/22n6) 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 05n3 n (V) Reactor Coolant Pressure Iloundary lxakage Detection Systems 05/73 1.45 1.46 (Withdrawn-See 50 FR 9732,3/11/85) 3 Dhision 1

Published Guide Number Title Rev. hionth! Year 1.47 Ilypassed and inoperable Status Indication for Nuclear Power Plant Safety 05/73 Systems 1.48 (With<trawn-See 50 FR 9732,3/11/85) 1.49 Power levels of Nuclear Power Plar ts 05/73 1 12/73 05n3 1.50 Cvitrol of Preheat Temperature for Welding of low Alloy Steel 1.51 (Withdrawn-See 40 FR 30510,7/2105) 1.52 Design, Testing, anti Maintenance Criteria for Postaccident Engineered. Safety-06/73 "cature Atmosphere Clesnup System Air Filtration and Adsorption Units of 1 0706 1ight Water-Cooled Nuclear Power Plants 2 03/78 1.53 Application of the Single Failure Criterion to Nuclear Power Plant Protection 06n3 Systems 1.54 Ouality Assurance Requirements for Protective Coatings Applied to Water Cooled 06n3 Nuclear Power Plants 1.55 (Withdrawn-Sec 46 FR 37579,7/21/81) 1.56 Maintenance of Water Purity in iloiting Water Reactors (for Comment) 06/73 1 0708 1.57 Design 1.imits and leading Combinations fo Metal Pr'.. nary Reactor 06n3 Containment System Coreponents 1.58 (Withdrawn-Sec 56 FR 36175,7/31/91) 1.59 Design llasts Floods for Nuclear Power Plants (Errata published 7/30/80) 0803 1 04D6 2 08/77 1.60 Design Response Spectra for Seismic Design of Nuclear Power Plants 10n3 1 12n3 1.61 Damping Values for Seismic Design of Nuclear Power Plants 10/73 10n3 1.62 ManualInitiation of Protective Actions 10n3 1.63 Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants (Draft EE 405-4, Proposed Revision 3, published 6/86) 1 0507 2 07/78 3 02/87 1 64 (Withdrawn-See 56 FR 36175,7/31/91) 10n3 1.65 Materials and inspections for Reactor Vessel Closure Studs 1.66 (Withdrawn-See 42 FR 54478,10/697) 1.67 (Withdrawn-See 48 FR 1910),4/27/83) Division 1 4

i Guide Published q Number Title Rev. Month / Year ,'v/ 1.68 Initial Test Programs for Water Cooled Nuclear Power Plants lin3 1 Oln7 2 08/78 1.68.1 Preoperational and Initial Startup Testing of Feedwater and Condensate 12n5 Systems for Boiling Water Reactor Power Plants 1 0197 1,68.2 initial Startup Test Program To Demonstrate Remote Shutdown Oln7 Capability for Water Cooled Nuclear Ibwer Plants 1 07R8 1.68.3 Preoperational Testing ofInstrument 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//2 Plants (LWR Edition) 1 10/72 2 09n5 3 lin8 1.71 Welder Qualification for Areas of Limited Accessibility 12/73 1.72 Spray Pond Piping Made from Fiberglass Reinforced Thermosetting Resin 12n3 1 Oln8 2 11/78 1.73 Oualification Tests of Electric Valve Operators Installed Inside the Containment Oln4 of Nuclear Power Plants 1,74 (Withdrawn-See 54 FR 38919,9/21/89) 1.75 Physical independence of Electric Systems 02n4 1 01/75 2 09n8 1.76 Design liasis Tornado for Nuclear Power Plants 04/74 1.77 Assumptions Used for Evaluating a Control Rod Ejection Accident for 05n4 Pressurized Water Reactors 1.78 Assumptions for Evaluating the liabitability of a Nuclear Power Plant Control 06n4 Room During a Postulated llazardous Chemical Release 1.79 Preoperational Testing of Emergency Core Cooling Systems for Pressurized 06D4 Water Reactors 1 09n5 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 06n4 Plants 1 Oln5 [ 1.82 Water Sources for Long Term Recirculation Cooling Following a Loss of-Coolant 06n4 \\s Accident (Draft MS 203-4, Proposed Revision 1, published S/83)(Draft 1 11/85 DG-1038, Proposed Revision 2, published 7/95) 2 05/96 5 Disision 1

Published Guide Nt"nler Title Rev, Afonth! Year 1.83 Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes 06/74 1 0705 1.84 Design and Fabrication Code Case Acceptability-ash 1E Section 111. Division I flecause this guide is frequently revised, only the current reviaion and date are listed in the appropriate columns. Prcilous revisions and their publication dates follow: 0, 6n4; 1,4/75: 2, 6n5; 3,905; 4,1In5; 5, 2n6; 6, Sn6; 7, 8n6; 8, lin6, 9, 3/77; 10, 8n7; 11,11/77; 12, 3/78; 13, 7/78; 14,11/78; 15, 5/79; 16, 5/80; 17, 12/80;I8, 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 (DG-1048, 30 10/94 Proposed Revision 31, published 5/97) 1.85 hiaterials Code Case Acceptability-AShiE Section 111, Division I liccause 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, 9D5; 4,11/75; 5, 2n6; 6, 5/76; 7, 8/76; 8,11/76; 9, 3n7; 10, 8/77; 11,1 ID7; 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. I1/82;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 (DG-1049, 30 10/94 Proposed Revision 31, published 5/97) 1.86 Termination of Operating 1.icenses for Nuclear Reactors 06/74 1.87 Guidance for Construction of Class 1 Components in filevated Temperature 06/74 Reactor < (Supplement to AShili Section 111 Code Cases 1592,1593,1594,1595, 1 06/75 and 1596) 1.88 (Withdrawn-See 56 FR 36175,7/31/91) 11/74 1.89 Environmental Qualification of Certain F acctric Equipment important to Safety for Nuclear Pow er Plants (Draf t lie V.-2, Proposed hevision 1, published 2/82) 1 06/84 1.10 Inservice Inspection of Prestressed Concrete Containment Structures with 11/74 Grouted T.ndons 1 08/77 1,91 Evaluations of Explosions Postulated To Occur on Transportation Routes Near 01/75 Nuclear Power Plants 1 02n8 12/74 1.92 Combining hiodal Responses and Spatial Components in Seismic Response Analysis 1 02/76 1.9h Availability of Electric Power Sources 12/74 1.94 Quality Assurance Requirements for installation, inspection, and Testing of 04n$ Structural Concrete and Structural Steel During the Construction Phase of 1 0406 Nuclear Power Plants (Draft RS 908-5, Proposed Revision 2, published 9n9) 1,95 Protection of Nuclear Pown Plant Control Room Operators Against an 02/75 Accidental Chlorine Release 1 01/77 1.96 Design of hiain Steam isolation Valve leakage Control Systems for lloiling 05/75 Water Reactor Nuclear Power Plants 1 06D6 1.97 Instrumentation for 1.ight-Water-Cooled Nuclear Power Plants To Assess Plant 12n5 and Environs Conditions During and Following an Accident (Errata published 1 08n7 7/81)(Draft RS 917--1, Proposed Revision 2, published 12n9) 2 12/80 3 05/83 Division 1 6

i I Guide Published Number Title Rev. Month / Year. l 1.98 Assumptions Used for Evaluating the Potential Radiological Consequences of a 03n6 i Radioactive Offgas System Failure in a Boiling Water Reactor (for Comment) [ t 1.99 Radiation Embrittlement of Reactor Vessel Materials (Draft ME 305-4, 0705 Proposed Revision 2, published 2/86) 1 WD7 2 05/88 l 1.100 Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power 03n6 j ' Plants (Draft EE 108-5, Proposed Revision 2, published 8/87) 1 08n7 i 2 06/88 1.101 ' Emergency Planning and Preparedness for Nuclear Power Reactors (Revision 1 11/75' - to this guide entitled " Emergency Plan'ning 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 i 1.102 Fhod Protection for Nuclear Power Plants 10/75 ~ l 09/76 1.103 (Withdrawn-See 46 FR 37579,7/21/81) 1.104 (Withdrawn-See 44 FR 49321,8/22n9) See NUREG-0554," Single Failure. Proof Cranes for Nuclear Power Plants." 1.105 Instrument Setpoints for Safety Related Systems (Draft IC 010-5, Proposed 1105 Revision 2, published 12/81)(Draft DO-1045, Proposed Revision 3, 1 Iln6 p>blished 10/96) 2 02/86 s 1.106 The.'nal Overload Protection for Electric Motors on Motor Operated Valves 11/75 1 03n7 1,107 Oualifications for Cement Grouting for Prestressing Tendons in Containment 11/75 i Structures 1 02n7 j 1.108 (Withdrawn-See 58 FR 41813,8/'/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 Efauents 03n6 for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix i 1 10n7 1.110 Cost-Benefit Analysis for Radwaste Systems for Light Water Cooled Nuclear 03n6 Power Reactors (for Comment) 1.111 Methods for Estimating Atmospheric Transport and Dispersion of Gaseous 03n6 Ef0uents in Routine Releases from Light Water Cooled Reactors 1 0707 f 1.112' Calculation of Releases of Radioactive Materials in Gaseous and Liquid 04n6 Ef0uents from Light Water Cooled Power Reactors, 0-R ' 05n7 1.113 Estimating Aquatic Dispersion of Efauents from Accidental and Routine - 05n6 Reactor Releases for the Purpose of implementing Appendix 1 1 04D7 h I.114 Guidance to Operators at the Controls and to Senior Operators in the Control 02n6 V Room of a Nuclear Power Unit (Draft ilF 601-4, Proposed Revision 2, 1 1106 published 12/86) 2 05/89-7 Division 1

Published Guide Number Title Rev. MontWYear 03n6 1.115 Protection Against inw Trajectory Turbine Missiles 1 07/77 0606 1.116 Quality Assurance Requirements for Installation, inspection, and Testing of 0-R 05/77 Mechanical Equiprnent and Systems 1.117 Tornado Design Classification 06D6 1 N/78 0606 1.118 Periodic Testing of Electric Power and Protection Systems (DG-1028, 1 11/77 Proposed Revision 3, published 9/94) 2 06/78 3 04/95 1.119 (Withdrawn-See 42 FR 33387,6/30n7) 1.120 Fire Protection Guidelines for Nuclear Power Plants (for Comment) 06/76 1 11/77 1.121 Ilases for Plugging Degraded PWR Steam Generator Tubes (for Comment) 08n6 1.122 Development of floor Design Response Spectra for Seismic Design of Fh>or-09n6 1 02/78 Supported Equipment or Components 1.123 (Withdrawn-See 56 FR 36175,7/31/91) 1.124 Service Limits and foading Combinations for Class 1 Linear Type Component 11/76 1 01/78 Supports 1.125 Physical Models for Design and Operation of Ilydraulic Structures and Systems 03n7 for Nuclear Power Plants 1 10n8 1.126 An Acceptab!c Model and Related Statistical Methods for the Analysis of Fuel 03n7 Densification 1 03/78 1.127 Inspection of Water Control Structures Associated with Nuclear Power Plants 04/77 1 03n8 1.128 Installation Design and Installation of Large trad Sto age llatteries for Nuclear 04/77 Power Plants 1 10/78 1.129 Maintenance, Testing, and Replacement of Large trad Storage flatteries for 04n7 Nuclear Power Plants 1 02n8 1.130 Service Limits and loading Combinat:ons for Class 1 Plate-and Shell Type 07/77 Component Supports 1 10/78 08/77 1.131 Qualification Tests of Electric Cables, Field Splices, and Connections for Light Water Cooled Nuclear Power Plants (for Comment)(Draft RS 050-2, Proposed Revision 1, published 8n9) 1.132 Site Investigations for Foundations of Nuclear Power Plants 0907 1 03n9 1.133 Loose Part Detection Program for the Primary System of Light Water-Cooled 09n7 Reactors 1 05/81 Division 1 8

Guide Puh!!shed .r] Nurnber Title Rey, hionth/ Year 1.134 hiedical Evaluation of Licensed Personnel for Nuclear Power Plants (Draft 09n7 OL 401-5, Proposed Revision 2, published ll/84)(Draft DG-1068, Proposed 1 03/79 Revision 3, published 2/97) 2 04/87 1.135 Normal Water level and Discharge at Nuclear Power Plants (for Comment) 0907 lin7 1.136 hinterials, Construction, and Testing of Concrete Containments (Articles CC-1000, -2000, and -4000 through -6000 of the " Code for Concrete 1 10n8 Reactor Vessels and Containments") (Draft SC 814-5, Proposed Revision 2, 2 06/81 published lin9) 01/78 1.137 Fuel Oil Systems for Standby Diesel Generators 1 10/79 1.138 Laboratory Investigations of Soils for Engineering Analysis and Design of 04n8 Nuclear Power Plants (for Comment) 1.139 Guidance for Residual lleat Removal (for Comment) 0508 1.140 Design, Testing, and hiaintenance Criteria for Normal Ventilation Exhaust 03/78 System Air Filtration and. Adsorption Units of Light Water Cooled Nuclear 1 10/79 Power Plants 1.141 Containment 1 solation Provisions for Fluid Systems (for Comment) 0408 O 1.142 Safety Related Concrete Structures for Nuclear Power Plants (other than 04/78 Q Reactor Vessels and Containments) 1 10/81 1.143 Design Guidance for Radioactive Waste hianagement Systems, Structures, and 07/78 Components Installed in Li;;ht Water Cooled Nuclear Power Plants 1 10/79 1.144 (Withdrawn-See 56 FR 36175,7/31/91) 1.145 Atmospheric Dispersion hiodels 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-ash 1E Section XI, Division 1 (Draft SC 721-4 published 8n9) 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 (DG-1050, Proposed Revision 12, published 5/97) 11 10/94 1.148 Functional Specification for Active Valve Assemblies in Systems important to 03/81 Safety in Nuclear Power Plants (Draft SC 704-5 published 2n9) N/81 1.149 Nuclear Power Plant Simulation Facilities for Use in Operator License Examinations (Draft RS 110-5 published 7/80)(Draft OL 402-5, Proposed 1 N/87 Revision 1, published 11/84)(Draft DG-1043, Proposed Revision 2 to 2 04/96 Regulatory Guide 1.149, published 6/95) A 1.150 Ultrasonic Testing c.'.teactor Vessel Welds During Preservice and Inservice 06/81 Examinations (Draft SC 705-4 published Sn9) 1 02/83 1.151 Instrument Censing Lines (Draft IC 126-5 published 3/82) 07/83 9 Dhision 1

Published Guide Number Title Rev. hionth/ Year 1.152 Criteria for Digital Computers in Safety Systems of Nuclear Power Plants 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-lN2, Proposed Revision 1, published 11/95) 1 06/96 01/87 1.154 Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors (Draft SI SP -4 published 1/86) 1.155 Station illackout (Draft S1501-4 published 3/86)(Issues' ne 1988, reissued 08/88 August 1988 with corrected tables) 11/87 1.156 Environmental Qualification of Connection Assemblics ir Nuclear Power Plants (Draft EE 404-4 published 5/87) 1.157 Hest Estimate Calculations of Emcrgency Core Cooling System Performance 05/89 (Draft RS 701-4 published 3/87) 1.158 Oualification of Safety Relatest fead Storage flatteries 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 (Draf t DG-1003 published 5/89) 1.160 hionitoring the Effectiveness of hiaintenance at Nuclear Power Plants 06/93 (Draft DG-1020 published ll/92)(Draft DG-1031, Proposed Revision 1, 1 01/95 published 6/94)(Draft DG-1051, Proposed Revision 2, published 8/96) 2 03/97 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 Vessels (Draft DG-1027 published 10/94) 1.163 Performance Based Containment lxak-Test Program (Draft DG-1037 09/95 published 2/95)(Errata to NEl 94-01 published 3/96) 1.164 (Not yet issued) 1.165 Identification and Characterization of Seismic Sources and Determination of 03/97 Safe Shutdown Earthquake Ground hiotion (Draft DG-1015 issued 11/92. Draft DG-1032, issued 2/95) 1.166 Pre Earthquake Planning and immediate Nuclear Power Plant Operator 03/97 Postcarthquake Actions (Draft DG-1017 issued 11/92, Draft DG-1034 issued 2/95) 03/97 1.167 Restart of a Nuclear Power Plant Shut Down by a Seismic Event (Draft DG-1018 issued 11/92, Draft DG-1035 issued 2/95) 1.168 Verification, Validation, Reviews, and Audits for Digital Computer Software 09/97 Used in Safety Systems of Nuclear Power Plants (Draft DG ~1054 issued 8/96) 1.169 Configetation hianagement Plans for Digital Computer Software Used in 09/97 Safety Systems of Nuclear Power Plants (Draft DG-1055 issued 8/96) Division 1 10

Guide Published Numlier Title lley, Month / Year 1.170 Sof tware Test Documentation for Digital Computer Software Used in Safety 09/97 Systems of Nuclear l'ower Plants (Draft DG-1056 issued 8/96) 1.171 Software Unit Testing for Digital Computer Software Used in Safety Systems 09/97 of Nuclear Power Plants (Draft DG-1057 issued 8/96) 1.172 Software itequirements Specifications for Digital Computer Software Used 09/97 in Safety Systems of Nuclear Power Plants (Draft DG-1058 issued 8/96) 1.173 Developing Soltware 1.ife Cycle Processes for Digital Computer Software Used 09/97 in Safety Systems of Nuclear Power Plants (Draft DG-1059 issued 8/96) ) J 7. i a 11 Disision 1

DIVISION I DRAIT REGULATORY GUIDES Published Task Number Title Month / Year CH 913-5 (Proposed Revision 2 to Regulatory Guide 1.13) Spent Fuel Storage Facility 12/81 Design Basis 08/89 DG-1001 Maintenance Programs for Nuclear Power Plants 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 04/91 DG-1008 Reactor Coolant Pump Seals DG-1010 (Proposed Revision 4 to Regulatory Guide 1.28) Quality Assurance Program 11/92 Requirements DG-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-1045 (Proposed Revision 3 to Regulatory Guide 1.105) Setpoints for Safety-Related 11/96 Instrumentation DG-1046 Guidelines for Reporting Reliability and Availability Information for 04/96 Risk-Significant Systems and Equipment in Nuclear Power Plants DG-IN7 Standard Format and Content for Applications To Renew Nuclear Power 08/96 Plant Operating Licenses (Supersedes DG-1009) DG-1048 (Proposed Revision 31 of Regulatory Guide 1.48) Design and Fabrication Code 05/97 Case Acceptability, ASME Section 111, Division 1 DG-1049 (Proposed Revision 31 of Regulatory Guide 1.85) Materials Code Case 05/97 Acceptability, ASME Section 111, Division 1 DG-1050 (Proposed Revision 12 of Regulatory Guide 1.147) Inservice Inspection Code 05/97 Case Acceptability, ASME Section XI, Division 1 DG-1052 Time Response Design Criteria for Safety-Related Operator Actions (supersedes 06/95 DG-1040) DG-1060 Financial Accounting Standards Board (FASB) Standards for Decommissioning 09/97 Cost Accountability DG-1061 An Approach for Using Probabilistic Risk Assessment in Risk Informed Decisions 06/97 on Plant-Specific Changes to the Current Licensing Basis DG-1062 An Approach for Plant Specific, Risk inft ned Decisionmaking: Inservice Testing 06/97 DG-1063 An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice 10/97 Inspection of Piping l Division 1 12 l

I Task Published. Number Title Month / Year j Y DO-1064 An Approach for Plant Specific, Risk inf(tmed Decisionmaking: Graded Quality 06/97 Assurance DO-1065. An Approach for Plant Specific, Risk informed Decisionmaking: Technical 06/97 Specifications l DG-1067 Decommissioning of Nuclear Power Reactors 06/97 DG-1068 (Proposed Revision 3 of Regtdatory Guide 1.134) Medical Evaluation of Licensed 02/97 Personnel at Nuclear Power Plant DG-1070 Sampling Plans Used for Dedicating Simple. Metallic / Commercial Grade items 09/97 'f for Use in Nuclear Power Plants EM 805-5 Nuclear Analyr s and Design of Concrete Radiation Shielding for Nuclear Power 02/79 Plants ES 926-4 (Second Proposed kevision I to Regulatory Guide 1.23) Meteorological 04/86 } Mmurement Program (~ Nuclear Power Plants . FP 811-4 Safety Related Permanent Dewatering Systems for Nuclear Power Plants 09n9 i IC 121-5 Respcmse Time Tnting 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 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 RS 809-5 Qualification Test for Cable Penetration Fire Stops for Use in Nuclear Power Plants 07n9 RS 902 (Second Proposed Revision 3 to Regulatory Guide 1.33) Quality Assurance Program 11/80 Requirements (Operation) RS 908-5 (Proposed Revision 2 to Regulatory Guide 1.94) Quality Assurance Requirements 09D9 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 - 09n9 Licenses and on Refueling and Startup Tests SC 708-4 (Withdrawn-See 54 FR 16030,4/20/89) ( \\ e 13 Division 1

I U.S. NUCLEAR REGULATORY COMMinSION REGULATORY GUIDE SERIES DIVISION 2 - RESEARCll AND TEST REAL TORS ACTIVE REGULATORY GUIDES Published Guide Nurnix r Title Rev. Month / Year 05D3 2.1 Shield Test Program for Evaluation of installed lilological Shielding in Research and Training Reactors 1103 2.2 Development of Technical Specifications for Experiments in Research Reactors 09n5 2.3 Quality Verification for Plate Type Uranium Aluminum Fuel Elements for Use in Research Reactors 1 07'76 07n6 2.4 Review of Experiments for Research Reactors 0-R 05/77 05n7 2.5 Quality Assurance Prt gram Requirements for Research Reactors O-R 10n7 2.6 Emergency Plai.ning for Research and Test Reactors (Draft ilF 201-4, Proposed Oln9 1 03/83 Revision 1, publisind 3/82) O l O Daision 2 14

U.S. NUCLEAR REGULATORY COMMISSION g REGULATORY GUIDE SF. PIES 4 DIVISION 3 - FUELS ANI) MATERIALS FACILITIES ACTIVE REGULATORY GUIDES Guide - Pubilshed Number Title Rev. Month / Year 3.1 Use of llorosilicate Glass Raschig Rings as a Neutron Absorber in Solutions of 01/73 Fissile Material (Draft FP 027-5, Proposed Revision 1, published $/81)(Draft 1 01/82 CE 602--1, Proissed Revision 2, published 3/87) 2 09/87 3.2 Efficiency Testing of Alt Cleaning Systems Containing Devices for Removal of Oln3 Particles 3.3 Quality Assurance Program Requirements for Fucl Reprocessing Plants and for 01/73 Plutonium Processing and Fuel Fabrication Plants 1 03n4 3.4 Nuclear Criticality Safety in Operations with Fissionable Materials at Fuels and Oln3 Materials Facilities (Draft CE 4N-4, Proposed Revision 2, published 4/85) 1 08/77 1-R 02n8 2 03/86 3.5 Standard Format and Content of License Applications for Uranium Mills (for 02n3 Comment) (Draft WM 039--1, Proposed Revision 2, published 8/81) 1 11/77 3.6 Content of Technical Specifications for Fuel Reprocessing Plants 04n3 3.7 Monitoring of Combustible Gases and Vapors in Plutonium Processing and Fuel 03/73 Fabrication Plants 3.8 Preparation of Environmental Reports for Uranium Mills 04n3 1 0908 2 10/82 3.9 Concrete Radhtion Shields 06/73 3 10 Liquid Waste Treatment System Design Guide for Plutonium Processing and I;uel 06n3 Fabrication Plants 3.11 Design, Construction, and Inspection of Embankment Retention Systems for 0603 Uranium Mills 1 03n7 2 12n7 3.11.1 Operational Inspection and Surveillance of Embankment Retention 04n9 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 p 3.13 - Guide for Acceptable Waste Storage Methods at UF Production Plants 10n3 6 3.14 Seismic Design Classification for Plutonium Processing and Fuel Fabrication 10n3 Plants 15 Division 3 w_a_a-a-----a__---w.--__--- -. - _ - - -. -

Published Guide Number Title Rev. Montit/ Year 3.15 Standard Format and Content of 1.icense Applications for Storage Only of 10/73 Unitradiated Power Reactor Fuel and Associated Radioactive Material (Draft I nt/83 Cli 219-4, Proposed itevision 1 published 8/82) 3.16 General Fire Protection Guide for Plutonium Processing and Fuel Fabrication 01/74 Plants 3.17 Ilarthquake Instrumentation for Fuel Reprocessing Plants 02/74 02/74 3.18 Confinement llatriers 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 Reptocessing Plants 3.21 Quality Assurance Requirements for Protective Coatings Applied to Fuel 03/74 Reprocessing and to Plutonium Processing and Fuel Fabrication Plants 06/74 3.22 Periodic Testing of Fuel Reprocessing Plant Protection System Actuation Fenctions 3.23 (Withdrawn-See 45 FR 71876,10/30/80) 3.24 (Withdiawn-See 46 FR 14507,2/27/81) 12/74 3.25 Standard Format and Content of Safety Analysis Reports for Uranium linrichment Facilities 3.26 Standard Format and Content of Safety Analysis Reports for Fuel Reprocessing 02/75 Plants 3.27 Nondestructive lixamination of Welds in the Liners of Concrete llatriers in Fuel 05/75 1 05/77 Reprocessing Plants 3.28 Welder Qualification for Welding in Areas of Limited Accessibility in Fuel 05/75 Repiocessing 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 Plutanium Processing and Fuel Fabrication Plants 06/75 3.30 Selection, Application, and Inspection of Protective Coatings (Paints) for Fuci O-R 05/77 Reprocessing Plants 09/75 3.31 timergency Water Supply Systems for Fuel Reprocessing Plants 0-R 05/77 3.32 General Design Guide for Ventilation Systems for Fuel Reprocessing Plants 09/75 (for Comment) 3.33 Assumptions Used fo; livaluating the Potential Radiological Consequences of 04/77 Accidental Nuclear Criticality in a Fuel Reprocessing Plant (for Comment) 3.34 Assumptivas Used for livaluating the Potential Radiological Consequences of 0-1/77 Accidental Nuclear Criticality in a Uranium Fuel Fabrication Plant 1 07/79 Division 3 16

l Gukie Published ] Number Title Rev. Month / Year "] 3.35 Assumptions Used for Evaluating the Potential Radiological Consequences of 05n7 Accidental Nuclear Criticality in a Plutonium Processing and Fuel Fabrication 1 0709 Plant 3.36 (Withdrawn-See 44 FR 6535,2/199) 3.37 Guidan x for Avoiding Intergranular Corrosion and Stress Corrosion in Austenitic 0995 Stainless Steel Comp (ments 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 Centent of License Applications for Plutonium Processing Oln6 and Fuel Fabrication Plants 3.40 Design liasis 1%xxis for Fuel Reproct c3 P! ants and for Plutonium Processing 1106 and Fuel Fabrication Plants 1 12n7 3,41 (Withdrawn-See $1 FR 11660,4/4/86) 3.42 timergency Planning for Fuel Cycle Facilities and Plants Licensed Under 10 CFR 08n7 Parts 50 and 70 1 0999 3.43 Nuclear Criticality Safety in the Storage of Fissile hiaterials 08n8 1 (Mn9 9 3.44 Standard Format and Content for the Safety Analysis Report for an Independent 12/ Y Spent Fuel Storage Installation (Water Hasin Type)(Draft CH 403-4, Proposed 1 11/80 Revision 2, published 11/86) 2 01/89 3.45 Nuclear Criticclity Safety for Steel Pipe Intersections Containing Aqueous 11/80 Solutions of Fissile hiaterials (Draft FP 925-5 published 1/80)(Draft CE 802-5, I (M/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 hiining(Draft FP 818-4 published 7/80) 3.47 Nuclear Criticality Control and c fety ofIlomogeneous Plutonium Uranium Fuel 07/81 a hiixtures 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 hionitored 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 ndard Format and Content for a License Application To Store Spent Fuel 01/82 '.ligh Ixvel Radioactive Waste (Draft FP 907-4 published 3/81) 1 09/89 aft CE 402-4, Proposed Revision 1, publis.ed 9/86) S V) 3.51 Calculational hiodels for Estimating Radiation Doses to hian from Airborne 03/82 Radioactive hiaterials Resulting from Uranium hiilling Operations (Draft Ril 802-4 pWished Sn9)(Errata published August 1982) 17 D vision 3

Published Guide Number Title Rev. Month / Year 3.52 Standard Format and Content for the llealth and Safety Sections of License 07/82 Renewal Applications for Uranium Processing and Fuel Fabrication (Draft i 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 Opuation of an 07/82 Independent Snent Fuel Storage Installation (Draft CE 037-4 published 11/81) 3.54 Spent Fuel lleat Generation in an independent Spent Fuel Storage Installation 09/84 (Draft FP 034-4 published 12/80)(cecond Draft CE 034-4 published 1/83) (DG-3010, Proposed Revision 1, published 9/97) 04/85 3.55 Standard Format and Content for the IIcahh and Safety Sections of License Renewal Applications for Uranium llexafluoride Production (Draft CE 227-4 3 published 1/84) 3.56 General Guidance for Designing, Testing, Operating, and Maintaining Emissior 05/86 Control Devices at Uranium Mills (Draft CE 309-4 published 5/85) 10/86 3.57 Administrative Pmtices for Nuclear Criticality Safety at Fuels and Materials Facilities (Draft La 501-4 published 2/86) 1 3.58 Criticality Safety for llandling, Storing, and Transporting LWR Fuel at Fuels 10/86 L and Materials Facilities (Draft CE 407-4 published 7/85)(Draft DG-30N, Proposed Revision 1, published 5/90) 3.59 Methods foi Estimating Radioactive and Toxic Airbome Source Terms for 03/87 Uranium Maling Operations (Draft WM 40"i-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) 3fI Standard Format and Content for a Topical Safety AnQais 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 MillTailings 06/89 Covers (Draft WM 503-4 published 5/87) 3.65 Standard Format and Content of Pecommissioning 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 Parts 30,40,70, and 72 (Draft DG-3002 published 1/90) 3.67 Standard Format and Content for Emergeny 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 Division 3 18

Guide I ublished p Number Title Rev. Month / Year 3.69 Topical Guidelines for the Licensing Support System (Draft DG-3009 09/96 published 7/93) 3,70 Use of Fixed Neutron Absorbers at Fuels and Materials Fac !ities (Draft DG-30ll 08/97 published 3/97) N O ( 19 Division 3

DIVISION 3 DRAIT REGULATORY GUIDES Published 'Ibsk Nctnber Title Mo ith/ 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-txvel 11/90 Waste Repository DG-3004 (Proposed Revision 1 to Regulatory Guide 't.58) Criticality Safety for llandling, 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 DG-3010 (Proposed Revision I to Regulatory Guioe 3.54) Spent Fuel lleat 09/97 Generation in an Independent Spent Fuel Storage Installation 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 u 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 Facilities WM 039-4 (Proposed Revision 2 to Regulatory Guide 3.5) Standard Format and Content of 08/81 License Applications for Uranium Mills O Division 3 20

U.S. NUCLEAR REGUIATORY COMMISSION REGUIATORY GUIDE SERIES DIVISION 4 - ENVIRONMENTAL AND SITING ACTIVE REGUIATORY GUIDES Guide Published Number Title Rev. Month / Year 4.1 Programr for Monitoring Radioactivity 19 the Environs of Nuclear Power Plants Oln3 1 04n5 4.2 - Preparation of Environmental Reports for Nuclear P3wer Stations (Proposed 0393 Supplement 1 to Regulatory Guide 4.2, DG4002, published 8/91) 1 01n5 2 0706 4.3 (Withdrawn-Sec 41 FR 53870,12/9n6) 4.4 Reporting Procedure for Mathematical Models Selected To Predict IIcated 05/74 Effluent Dispersion in Natural Water Ikidies 4.5 Measurements of Radionuclides in the Environment-Sampling and Analysis of 05n4 Plutonium in Soil 4.6 Meesurements of Radionuclides in the Environment-Strontium-89 and 05n4 Strontium-90 Analyses 4.7 General Site Suitability Criteria for Nuclear Power Stations (DG-4003, 09n4 7 Proposed Revision 2, published ll/92)(DG-4004, Second Proposed i 1In5 Revision 2, published 2/95) 4.8 Environmental Technical Specifications for Nuclear Power Plants (for Comment) 12n5 4.9 Preparation of Environmental Reports for Commercial Uranium Enrichment 12n4 Facilities 1 10n5 4.10 (Withdrawn-See 42 FR 59436,11/17/77) 4.11 Terrestrial Environmen;al 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 06n7 1 04/80 4.15 -Quality Assurance for Radiological Monitoring Programs (Normal Operations)- 12n7 Effluent Streams and the Environment 1 02n9 4.M. Monitoring and Reporting Radioactivity in Releases of Radioactive Materials in 03n8 Liquid and Gaseous Effluents fiom Nuclear Fuel Processing and Fabrication i 12/85 Plants and Uranium IIcxafluoride Production Plants (Draft CH 401-4, Proposed Revision 1, published 9/l 4ta published 8/86) 21 Division 4

Published Guide Nurnber Title Rev. Menth/ Year 4.17 Standard Format and Content of Site Characterization Plans for liigh-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) 4.18 Standard Format and Content of Environmental Reports for Near Surface 06/83 Disposal of Radioactive Waste (Draft W.I 013-4 published 4/82) 4.19 Guidance for Selecting Sites for Near-Surface Disposal of Imw Exsel Radioactive 08/88 Waste (Draft WM 408-4 published 3/87) 12/96 4.20 Constraint on Releases of Airborne Radioactive Materials to the Environment for 1.icensees other than Power Reactors (Draft DG-8016 published 12/95) O O Division 4 22

r- . DIVISION 4 DRAIT REGUIATORY GUIDES - Task. Published Number - - Tiu Month / Year DG-4002 ~ (Proposed Supplement I to Regulatory Guide 4.2) Guidance for the 08/91 Preparation of Supplemental Environmental Reports in Support of an Applicatior, To Renew a Nuclear power Station Operating License - DO-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) p .i r NJ 23 Division 4 . - - -... - ~

S. Nt' CLEAR REGUIATORY COMkSSION REGUIATORY GUIDE SERIES DIVISION 5-MATERIALS AND PIANT PROTECflON ACTIVE REGULATORY GUIDES Guide Published Number Title Rev. Month / Year 5.1 Serial Numbering of Fuel Assemblies for Light-Water-Cooled Nuclear Power 12n2 Reactors 5.2 (Withdrawn-See 44 FR 57542,10/599) 5.3 Statistical Terminology and Notation for Special Nuclear Materials Control and 02n3 Accountability 5.4 Standard Analytical Methods for the Measurement of Ur..aium Tetra 0uoride 02R3 (UF4) and Uranium llexauuoride (UF6) 5.5 Standard Methods for Chemical, Mass Spectrometric, and Spectroche.nical 02n3 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 06D3 (Draft SG 909-4, Proposed Revision 1, published 559) 1 05/80 5.8 Design Considerations for Minimizing Residual lloldup of Special Nuclear 06n3 Material in Drying und Fluidized Bed Operations 1 05/74 5.9 Guide' nes for Germanium Spectroscopy System 3 for Measurement of Special 06D3 Nuclea Material (Draft SG N2-2, Proposed Revision 2, published 7/82) 1 05/74 2 12/83 5.10 Sslection and Use of Pressure-Sensitive Seals on Containers for Onsite Storage of 07D3 Special Nuclear Material 5.11 Nondestructive Assay of Special Nuclear Mater;al Contdned in Scrap and Waste 10n3 (Draft SG 043-4, Proposed Revision I, published 11/82) 1 04/84 5.12 Generi. Use of lects in the Protection and Control of Facilities and Special lin3 Nucle r Materials 5.13 Conduct of Nuclear Material Physicil Inventories lin3 5.14 Use of Observation (Visual Surveillance) Techniques in Mate ial Access Areas 1193 (Draft SG 910-4, Proposed Revision 1, published SR9) 1 05/80 5.15 Tamper-Indicating Seals for the Protection and Control of Special Nuclear Material - 01R4 (Draft DG-5005, Propo+.o Revision 1, published 1/96) 1 03/97 5.16 (Withdrawn-See 50 FR 253M,6/18/85) 5.17 Truck identification Markings Oln4 Division 5 24

\\ l i Guide Published (3 Number Title Rev. Month / Year ) V 5.18 Limit of Error Concepts and Principles of Calculation in Nuclear Materials Oln4 Control 5.19 (Withdrawn-See 50 FR 25364,6/18/85) 5.20 Training, Equipping, and Qualifying of Guards and Watchmen 01R4 5.21 Nondestructive Uranium 235 Enrichment Assay by Gamma Ray Spectrometry 04n4 (Draft SG 044-4, Proposed Revision 1, published 6/82) 1 12/83 5.22 Assessment of the Assumption of Normahty (Employing Individual Observed 04/74 Values) 5.23 in Situ Assay of Plutonium Residual lloldup (Draft SG 045-4, Proposed 05D4 Revision 1, published 10/82) 1 02/84 5.24 Analysis and Use of Process Data for the Protection of Special Nuclear Material 06D4 5.25 Design Considerations for Minimizing Residual lloldup of Special Nuclear Material - 06n4 in Equipment for Wet hocess Operations 5.26 Selection of Material 11alance Areas and item Control Aren 06n4 1 (MD5 5.27 Special Nuclea Material Doorway Monitors 06n4 5.28 Evaluation of Shipper Receiver Ditferences in the Transfer of Special Nuclear 06/74 Materials 5.29 Nuclear Material Control Systems for Nuclear Power Plants 06D4 1 06/75 5.30 Materials Protection Contingency Measures for Uranium and Plu:9nium Fuel 06D4 Manufacturing Plants 5.31 Specially Designed Vehicle with Armed Guards for Road Shipment of Special 06/74 Nuclear Material 1 04n5 5.32 Communication with Transport Vehicles 06D4 1 05n5 5.33 Statistical Evaluation of Material Unaccounted For 06/74 5.34 Nondestructive Assay for Plutonium in Scrap Material by Spontaneous Fission 06n4 Detection (Draf SG 046-4, Proposed Revision 1, published 6/82) 1 05/84 5.35 (Withdrawn-See 42 FR 41677,8/18n7) 5.36 Recommended Practice for Dealing with Outlying Observations 06/74 5.37 in Situ Assay of Enriched Uranium Residual lloidup (Draft SG 047-4, Proposed 08n4 q Revision 1, published 8/82) 1 10/83 ) 5.38 Nondestr"ctive Assay of liigh-Enrichmer.t Uranium Fuel Plates by Gamma Ray 09n4 Spectrometry (Draft SG (M8-4, Proposed Revision 1, publisbed 8/82) 1 10/83 25 Division 5

\\ Published Guide Nrmber Title Rev. Month / Year 12n4 5.39 General Methods for the Analysis of Uranyl Nitrate Solutions for Assay, Isotopic Distribution, and impurity Determinations 5.40 (Withdrawn-See 50 FR 25364,6/18/85) 5.41 (Not issued) 5.42 Design Considerations for Minimizing Residual lloidup of Special Nuclear 01n5 Material in Equipment for Dry Process Operations 5.43 Plant Security Force Duties 01n5 5.44 Perimeter intrusion Alarm Systems (Draft SG 479-4, Proposed Revision 2, Oln5 1 06n6 published Sn9)(Dratt DG-5007, Proposed Revision 3, published 4/96) 2 05/80 3 10/97 5.45 Standard Fonnat and Content for the Special Nuclear Material Control and 12n4 Accounting Section of a Special Nuclear Material ljeense Application (Including That for a Uranium Enrichment Facility) 5.46 (Not issued) 5.47 (Withdrawn-Sec 50 FR 25364,6/18/85) 5.48 l> sign Considerations-Systems for Measuring the Mass of Liquids 02n5 5.49 Internal Transfers of Special Nuclear Material (for Comment) 03R5 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 05n5 Strategic Special Nuclear Material at Fixed Sites (Other than Nuclear Power 1 06n6 2 07/80 Plants) (DG-5004, Proposed Revision 3, published 4/94) 3 12/94 08n5 5.53 Oualification, Calibration, and Enor Estimatior Methods for Nondestructive 1 02/84 Assay (Draft SG 049-4, Proposed Revision 1, published 6/82) 5.54 Standard Format and Content of Safeguards Contingency Plans for Nuclear 03R8 Power Plants (for Comment) 03R8 5.55 Standard Format and Content of Safeguards Contingency Plans for Fuel Cycle Facilities (for Comment) 03R8 5.56 Standard Format and Content of Safeguards Contingency Plans for Transportation (for Comment) 5.57 Shipping and Receiving Control of Strategic Special Nuclear Material (Draft 06n6 1 06/80 SG 908-4, Proposed Revision 1, published 5R9) lin8 5.58 Considerations for EstablishingTraceability of Special Nuclear Material 1 02/80 Accounting Measurements Division 5 26

l l Guide Published n Number Title Rev. Month / Year 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 T:ansit 5.61 Intent and Scope of the Physical Protection Upgrade Rule Requirements for 06/80 Fixed Sites 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 Authorii.ation 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 Venicles at Nuclear Power Plants 08/94 (Draft DG-5006 issued 11/93) q 4 \\s 27 Division 5

DIVISION 5 DRAFT REGUl ATORY GUIDES Publisi.ed 'u.ler Title Month / Year SG 301-4 (Withdrawn-See 56 FR 36175,7/31/91) O 01 1 Division 5 28

U.S. NUCLEAR REGULATORY COMMISSION REGULATORY Gl>lDE SERIES DIVISION 6-PRODUCTS ACTIVE REGULATORY GUIDES Guide Published Number Title Rev. Month / Year 6.1 Leak Testing 'tadioactive Brachytherapy Sources 07/74 1 07/74 6.2 Integrity and Test Specifications for Sekcted Brachytherapy Sources 07/74 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 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 listablishing Quality Assurance Programs for the Manufacture at.d 02/95 Distribution of Scaled Sources and Devices Containing Byproduct Material (Draft DG-60)2 published 5/94) O 29 Division 8

DIVISION 6 DRAFT REGULATORY GUIDES Published Task Number Title Month! Year 11/80 TP 102-5 Safety Features of Gauges Containing Radioactive Material 9 Dhision 6 30

I U.S. NUCLEAR REGULATORY COMMISSION ] REGULATORY GUIDE SERIES J DIVISION 7 -TRANSPORTATION ACTIVE REGUIATORY GUIDES Guide Published Number Title Rev. Month / Year 06n4 7.1 Administrative Guide for Packagirrg and Transporting Radioactive Material 7.2 Packaging and Transportation of Radioactively Contaminated Biological Materials - 06n4 7.3 Procedures for Picking Up and Receiving Packages of Radioactive Material 05D5 7.4 Leakage Tests on Packages for Shipment of Radioactive Materials 06DS 06D5 7.5 Administrative Guide for Obtaining Exemptions from Certain NRC Requirements over Radioactive Material Shipments 0-R 05n7 7.6 Design Criteria for the Structural Analysis of Shipping Cask Containment Vessels 02n7 1 03n8 7.7 Administrative Guide for Verifying Compliance with Packaging P,equirements for 08D7 Shipments of Radioactive Materials (for Comment) G 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) 7.9 Standard Format and Content of Part 71 Applications for Approval of Packaging 03/79 of Type B, Large Ouantity, and Fissile Radioactive Material (Dratt 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 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) ,m j v l 31 Division 8 l

DIVISION 7 DRAFT REGUIATORY GUIDES Task Published Number Title Month /Yehr 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 Materials t O O Division 7 32

.~ REGULATORY GUIDE SERIES - DIVISION 8 - OCCUPATIONAL HEALTil ACTIVE REGULATORY GUIDES Guide - Published Number - Title Rev. Month / Year 02n3 8.1-Radiation Symbol 8.2 Guide for Administrative Practices in Radiation Monitoring 02n3 l 8.3 Film Badge Performance Criteria 02n3 8.4 Direct Reading and Indirect Reading Pocket Dosimeters 02n3 8.5 ' Criticality and Other Interior Evacuation Signals 02/73 1 03/81 05R3 8.6 Standard Test Procedure for Geiger Muller Counters 8.7 Instructions for Recording and Reporting Occupational Radiation Exposure 05n3 Data (Draft DG-8007, Proposed Revision 1, published 11/91) 1 06/92 8.8 Information Relevant to Ensuring that Occupational Radiation Exposures at. 0703 Nuclear Power Stations Will Be As Low As is Reasonably Achievable (Draft 1 09/75 Oil 507-4, Proposed Revision 4, published 3n9)(Draft OP 618-4, Second 2 03n7 Proposed Revision 4, published 5/82) 3 06/78 8.9 - Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay 09n3 Program (Draft DG-8009, Proposed Revision 1, published 12/91) 1 07/93 8.10 Operating Philosophy for Maintaining Occupational Radiation Exposures As 1.ow 04R4 As is Reasonably Achievable 1 09n5 1-R 05R7 8.11 Applications of Bioassay for Uranium 06n4 8.12. Criticality Accident Alarm Systems (Draft 011015-4, Proposed Revision 1. 12D4 published 5/80)(Draft CE 801-5, Proposed Revision 2, published 5/88) 1 01/81 2 10/88 -8.13 _ instruction Conce:ning Prenatal Radiation Exposure (Draft OP 031-4 03n5 Proposed Revision 2, published 8/81)(Draft DG-8014, Proposed Revision 3, 1 1105 published 10/94) 2 12/87 8.14 Personnel Neutron Dosimeters (Draft OH 940-4, Proposed Revision 2, 06n6 published 2/80) 1 08n7 -8.15 Acceptable Programs for Respiratory Protection. 1006 8.16 - (Not issued) 8.17 (Not issued) V 8.18 Information Relevant to Ensuring that Occupational Radiation Exposures at 12/77 Medical Institutions Will Be As Low As Reasonably Achievable - 1 10/82 33 Division 8

Guide Published Number Title Rev. Month / Year M.)9 Occupational Radiation Dose Assessment in Light-Water Reactor Power Plants-05D8 Design Stage Man-Rem Estimates 1 06D9 8.20 Applications of Bioassay for 1-125 and 1-131 04D8 1 09D9 8.21 Ilealth Physics Surveys for Byproduct Material at NRC-Licensed Processing and 05/78 1 1099 Manufacturing Plants 8.22 Bioassay at Uranium Mills (Draft OP 013-4, Proposei Revision 1, 07/78 1 08/88 published 1/87) 8.23 Radiation Safety Surveys at Medical Institutions 02n9 1 01/81 8.24 llealth Physics Surveys During Enriched Uranium-235 Processing and Fuel 11/78 Fabrication i 10/79 8.25 Air Sampling in the Workplace (Draft Oil 905--t publi<hed 10/79)(Draft 08/80 DG-8003, Proposed Revision I, published 9/91) 1 06/92 8.26 Applications of Bioassay for F'ssion and Activation Products (Draft 011714-4 09/80 published 8D9) 8.27 Radiation Protection Training for Personnel at Light-Water-Cooled Nuclear 03/81 Power Plants (Draft 011717-4 published 8/79) 8.28 Audible-Alarm Dosimeters (Draft Oli 844-4 published 8D9) 08/81 8.29 Instruction Concerning Risks from Occupational Radiation Exposure 07/81 (Draft 011902-4 published 5/80)(Draft DG-8012, Proposed Revision 1, 1 02/96 published 12/94) 8.30 llealth Physics Surveys in Uranium Mills (Draft Oil 710-4 published 8/80) 06/83 8.31 Information Relevent to Ensuring that Occupational Radiation Exposures at 05/83 Uranium Mills Will Be As Low As is Reasonably Achievable (Draft Oil 941-4 published 8/80) 8.32 Criteria for Establishing a Tritium Bioassay Program (Draft OP 713-4 07/88 published 6/83) 10/91 8.33 Ouality Management Program (Draft DG-8001 published 1/90) 8.34 Monitoring Criteria and Methods To Calculate Occupational Radiation Doses 07/92 (Draft DG-8010 published 2/92) 8.35 Planned Special Exposures (Draft DG-8008 published 12/91) 06/92 07/92 8.36 Radiation Dose to the Embryo / Fetus (Draft DG-80ll published 2/92) 8.37 ALARA Levels for Effluents from Materials Facilities (Draft DG-8013 07/93 published 10/92)(Draft DG-8016, Proposed Revision 1, published 12/95) 8.38 Cor trol of Access to liigh and Very liigh Radiation Areas of Nuclear Plants (Draft DG-8006 published 10/91) 06/03 Division 8 34

Guide Published Number Title Rev. MonthA' ear 8.39 Release of Patients Administered Radioactive Materials (Draft DG-8015 04/97 published 6/94)(Errata published 5/97) s O k 35 Division 8 1

l DIVISION 8 DRMT 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 d.13) Instruction Concerning Prenatal 10/94 Radiation Exposure Oli940-4 (Proposed Revision 2 to Regdatory 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 Proposed Revision 4 to Rcgulatory Guide 8.8)Information Relevant to 05/82 Ensuring that Occcpational Radiation Exposures at Nuclear Power Stations Will Be As Low As Is Reasonably Achievable (ALARA) OP 722-4 Qualifications for the Radiation Safety Officer in a large-Sc le Non-Fuel-Cycle 04/82 Radionuclide Program O O Division 8 36

U.S. NUCLEAR REGUIATORY COMMISSION - REGULATORY GUIDE SERIES DIVISION 9-ANTITRUST AND FINANCIAL REVIEW ACTIVE REGULATORY GUIDES Guide Published Number Title Rev. Month / Year 9.1 Regulatory Staff Position Statement on Antitru'st Matters 12/73 9.2 Information Needed by the NRC Staff in Connection wit.h its Antitrust Review 10/74 of Construction Permit Applications for Nuclear Power Plants 1 06/76 9.3 Information Needed by the AEC Regulatory Staffin 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) Gb Division 9 37 \\ l \\

l U.S. NUCLEAR REGU LATORY COMMISSION REGULNf0Ri 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 Oln5 1 07D5 2 08/75 3 05D7 4 10/81 10.2 Guidance to Academic Institutions Applying for Specific Byproduct hiaterial 03n6 Licenses of Limited Scope (Errata published 7/84) 1 12n6 10.3 Guide for the Preparation of Applications for Special Nuclear hiaterial Licenses 07D6 of Less than Critical hiass Quantities 1 Nn7 10.4 Guide for the Preparation of Applications for Licuses To Process Source hiate ial 0766 (Errata published 7/84)(Draft FC 409-4, Proposed Revision 2, published 4/85; I 03/77 2 12/87 10.5 Applications for Type A Licenses of Broad Scope (Errata published 7/84)(Draft 0906 FC 403-4, Proposed Revision 2, published 2/85)(Draft DG-0005, Second 1 12/80 Proposed Revision 2, published l'V94) 10.6 Guide for the Pre;'.iration of Applications for Use of Scaled Sources and Devices 09n6 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 Ocide for the Preparation of Applications for Licenses for Laboratory and 02n7 Industrial Use of Small Quantities of Byproduct hiaterial(Errata published 7/84) 1 08D9 10.8 Guide for the Preparation of Applications foi hiedical Use Programs (Draft 01n9 FC 415-4, Propo.,sd Revision 2, published 8/35)(Draft DG4)002, Proposed 1 10/80 Appendix X to Regulatory Guide 10.8, published 12/91)(Appendix X 2 08/87 published June 1992)(DG4)009, Prr, posed Supplement, published 3/97) 10.9 Guide for the Preparation of Applications for Licenses for the Use of Self-04/80 Contained Dry Source Storage Gamma Irradiators (Draft Oil 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 Propos:d Revision 1, published 10/84) 10.10 Guide for the I reparation of Applications for Radiation Safety Evaluation and 03/87 Registration of Devices Contaiaing Byproduct hiaterial (Draft FC 601-4 published 8/86) 10.11 Guide for the Preparation of Applications for Radiation Safety Evaluation and 06/87 Registration of Scaled Sources Containing Byproduct hiaterial (Draft FC 603-4 published 12/86) Divisica 10 38

l Guide Published Number Title Rev. Month / Year 10.12 Preparation of Petitions for Rulemaking Under 10 CFR 2.802 and Preparation 12/96 and Submission of Proposals for Regulatory Guidance Documents (Draft DG-0010 published 8/96 I i s l 39 Division 10

I DIVISION 10 DRAIT REGULATORY GUIDES Published Task hionth/ Year Number Title 01/94 DG4KX)3 Guide for the Pret.aration of Applications for Licenses for Non Self-Contained Irradiators 10/94 DG4XX)5 (Second Proposed Revision 2 to Regulatory Guide 10.5) Applications for Licenses of Broad Scope 03/97 D G 4 X)6 Guide for the Preparation of Applications for Commercial Nuclear Pharmacy Licenses (Supersedes FC 410-4) 03/97 DG4)007 Guide for the Preparation of Applications for Licenses to Authorize Distribution of Various items to Commercial Nuclear Pharmacies and hiedical Use Licensees (Supersedes FC 406-4) 05/95 DG-{XK)8 Applications for the Use of Scaled Sources in Portable Gauging Devices (Previous draft was FC 407-4) 03/97 DG4X)09 Proposed Supplement to Regulatory Guide 10.8, Revision 2," Guide for the Preparation of Applications for hiedical Use Programs" 10/84 FC 401-4 (Proposed Revision 2 to Regulatory Guide 10.6) Guide for the Preparation of Applications for the Use of Scaled Sources and Devices for Performing industrial Radiography 01/85 FC 403-4 Guide for the Preparation of Applications for Licenses for the Use of Panoramic Dry Source-Storage Irradiators, Self-Contained Wet Source-Storage Irradiators, and Panoramic Wet Source Storage Irradiators 01/85 FC 404-4 Guide for the Preparation of Applications for Licenses for the Use of Sealed Sources in Nonportable Gauging Devices FC 405 4 Guide for the Preparation of Applications for Licenses for the Use of Scaled Sources 02/85 in Gas Chromatography Devices and X-Ray Fluorescence Analyzers 02/85 FC 408-4 (Proposed Revision 2 to Regulatory Guide 10,5) Guide for the Preparation of Applications for Type A Licenses of Broad Scope (See DG41005) 06/85 FC 411-4 Guide for the Preparation of Applications for Licenses for the Use of Radioactive hiaterials in Servicing Preregistered Gauges, hicasuring Devices, and Scaled Sources Used in Such Devices FC 412-4 Guide for the Preparation of Applications for Licenses for the Use of Radioactive 06/85 hiaterials in Leak-Testing Services FC 413-4 Guide for the Preparation of Applications for Licenses for the Use of Radioactive 06/85 hinterials in Calibrating Radiation Survey and hionitoring Instrumerts 12/85 FC 414-4 Guide for the Preparation of Applications for Licenses for hiedical Teletherapy Programs (Second draft, previously issued as Thi 608-4, 3/82; Errata published 7/84) Divt ion 10 40 M

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