ML19322D233

Index for Divisions 1-10 Reg Guides,Power Reactors

ML19322D233
Person / Time
Site:	Crane
Issue date:	04/30/1979
From:	NRC COMMISSION (OCM)
To:
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TASK-TF, TASK-TMR NUDOCS 8002100076
Download: ML19322D233 (32)

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April 1979 s

DIVISION 1 REGULATORY GUIDES POWER REACTORS Previous issues of this table of' contents listed only the latest revision of each regulatory guide because it represented a current NRC staff position. However, some licensing commitments were based on earlier versions of a guide; therefore, this and future issues of the table of con-tents will list every version of each guide with the date it was issued. If the latest version of a guide (as of the date of this table of contents) was issued for early ecmment, this is so noted.

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Most regulatory guides contain a section headed " Implementation," which is intended to provide information to applicants and licensees regarding the NRC staff's plans for using the guide. If a guide does not contain such a section or if detailed information is needed on the staff's plans for using a regulatory guide with respect to a specific pennit or license or application therefor, requests for such information should be addressed to the appropriate licensing project manager in the Office of Nulcear Reactor Regulation or Office of Nuclear Material Safety and Safeguards.

Requests for single copies of the latest revision of a regulatory guide, the only version currently in print, should be made in writing to the U.S. Nuclear Regulatory Commission, Wash-ington, D.C. 20555, Attention: Director, Division of Technical Information and Document Con-trol. Earlier revisions may be examined at the Commission's Public Document Room,1717 H Street NW., Washington, D.C.

Regulatory guides are not copyrighted, and Commission approval is not required to reproduce them.

Issued Number Title Rev.

Year / Month 1.1 Net Positive Suction Head for Emergency Core Cooling and Contain-70/11

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.nent Heat Removal System Pumps (Safety Guide 1)

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1.2 Thermal Shock to Reactor Pressure Vessels (Safety Guide 2) 70/11 e

1.3 Assumptions Used for Evaluating the Potential Radiological Conse-70/11 quences of a Loss-of-Coolant Accident for Boiling Water Reactors 1

73/06 2

74/06 1.4 Assumptions Used for Evaluating the Potential Radiological Conse-70/11 quences of a Loss-of-Coolant Accident for Pressurized Water 1

73/06 Reactors 2

74/06 1.5 Assumptions Used for Evaluating the Potential Radiological Conse-71/03 quences of a Steam Line Break Accident for Boiling Water Reactors (Safety Guide 5) 1.6 Independence Between Redundant Standby (Onsite) Power Sources 71/03 and Between Their Distribution Systems (Safety Guide G) 1.7 Control of Combustible Gas Concentrations in Containment Following 71/03 a Loss-of-Coolant Accident 1

7G/09 2

78/11 1.8 Personnel Selection and Training 71/03 1

75/09 l-R 77/05 1.9 Selection Design, and Qualification of Diesel-Generator 71/03 Units Used as Onsite Electric Power Systems at 1

78/11 Nucl ar Power Plants (For Comment) 1.10 Mechanical (Cadweld) Splices in Reinforcing Bars of Category 1 Con- ---

71/03 crete Structures 1

73/01 1

8 0 021000 g

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Year / Month (

Issued Number Title Rev.

71/03 1.11 Instrument Lines Penetrating Primary Reactor Containment (Safety Guide 11)

Supplement to Safety Guide 11, Backfitting Considerations 72/02 71/03 1.12 Instrumentation for Earthquakes 1

74/04 71/03 1.13 Spent Fuel Storage Facility Design Basis (For Comment) 1 75/12 1.14 Reactor Coolant Pump Flywheel Integrity 71/10 (For Comment) 1 75/08 7f/10 1.15 Testing of Reinforcing Bars for Category I Concrete Structures 1

72/12 l

1.16 Reporting of Operating Information--Appendix A Technical Specifi-71/10 l

cations (For Comment) 1 73/10 2

74/09 3

75/01 4

75/08 1.17 Protection of N,uclear Power Plants Against Industrial Sabotage 71/10 1

73/06 1.18 Structural Acceptance Test for Concrete Primary Reactor Contain-71/10 ments 1

72/12 1.19 Nondestructive Examination of Primary Containment Liner Welds 71/12 (Safety Guide 19) 1 72/08 1.20 Comprehensive Vibration Assessment Program for Reactor Internals 71/12 During Preoperational and Initial Startup Testing 1

75/06 2

76/05 i

1.21 Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes 71/12 l

and Releases of Radioactive Materials in Liquid and Gaseous 1

74/06 Effluents from Light-Water-Cooled Nuclear Power Plants 1.22 Periodic Testing of Protection System Actuation Functions (Safety 72/02 Guide 22) i 1.23 Onsite Meteorological Programs (Safety Guide 23) 72/02 1.24 Assumptions Used for Evaluating the Potential Radiological Conse-72/03 quences of a Pressurized Water Reactor Radioactive Gas Storage Tank Failure (Safety Guide 24) 1.25 Assumptions Used for Evaluating the Potential Radiological Conse-72/03 quences of a Fuel llandling Accident in the Fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors (Safety Guide 25) 1.26 Quality Group Classifications and Standards for Water, Steam,

72/03 and Radioactive-Waste-Containing Components of Nuclear Power 1

74/09 Plants (For Comment) 2 75/06 3

76/02 1.27 Ultimate Heat Sink for Nuclear Power Plants 72/03

'(For Comment) 1 74/03 2

76/01 1.28 Quality Assurance Program Requirements (Design and Construction) 72/06 (For Comment) 1 78/03 2

79/02 i x

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1. k Issued Number Title Rev.

Year / Month 72/06 1.29 Seismic Design Classification 1

73/08 2

7G/02 3

78/09 72/08 1.30 Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment (Safety Guide 30) 72/08 1.31 Control of Ferrite Content in Stainless Steel Weld Metal 1

73/06 2

77/05 3

78/04 1.32 Criteria for Safety Related Electric Power Systems for Nuclear Power ---

72/08 Plants 1

76/03 2

77/02 72/11 1.33 Quality Assurance Program Requirements (Operation) 1 77/02 2

78/02 72/12 1.34 Control of Electroslag Weld Properties 73/02 1.35 Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containment Structures 1

74/06 2

76/01 73/02 1.36 Nonmetallic Thermal Insulation for Austenitic Stainless Steel

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

76/10 Plants 2

77/05 73/03 1.39 Housekeeping Requirements for Water Cooled Nuclear Power Plants 1

76/10 2

77/09 73/03 1.40 Qualification Tests of Continuous-Duty Motors Installed Inside the Containment of Water-Cooled Nuclear Power Plants 73/03 1.41 Preoperational Testing of Redundant On-Site Electric Power Systems to Verify Proper Load Group Assignments (Withdrawn-~ See 41 FR 11891, 3/22/76) 1.42 73/05 1.43 Control of Stainless Steel Weld Cladding of Low-Alloy Steel Compo-nents 73/05 1.44 Control of the Use of Sensitized Stainless Steel 73/05 1.45 Reactor. Coolant Pressure Boundary Leakage Detection Systems 73/05 1.46 Protection Against Pipe Whip inside Containment 73/05 1.47 Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems 73/05 1.48 Design Limits and Loading Combinations for Seismic Category 1 Fluid System Components

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l.49

Power Levels of Nuclear Pnwer Plants 73/05 1

73/12 3

r-l Issued Number Title Rev.

Year / Month 73/05 1.50 Control of Preheat Temperature for Welding of Low-Alloy Steel 1.51 (Withdrawn--See 40 FR 30510, 7/21/75) 73/06 1.52 Design, Testing, and Maintenance Criteria for Post Accident Engineered-Safety-Feature Atmosphere Cleanup System Air 1

76/07 Filtration and Adsorption Units of Light-Water-Cooled 2

78/03 Nuclear Power Plants 73/06 l.53 '

Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems N.

73/06 1.54 Quality Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants 73/06 1.55-Concrete Placement in Category I Structures t

73/06 j

1.56 Maintenance of Water Purity in Boiling Water Reactors (For Comment) 1 78/07 I

1.57 Design Limits and Loading Combinations for Metal Primary Reactor 73/06 Containment System Components 1.58 Qualification of Nuclear Power Plant Inspection, Examination, and 73/08 Testing Personnel 73/08 1.59 Design Basis Floods for Nuclear Power Plants 1

76/04 2

77/08

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I 1.60 Design Response Spectra for Seismic Design of Nuclear Power Plants ---

73/10 1

73/12

'l.61 Damping Values for Seismic Design of Nuclear hower Plants 73/10 73/10 1.62-Manual Initiation of Protective Actions 1.63 Electric Penetration Assemblies in Containment Structures for 73/10 Light-Water-Cooled Nuclear Power Plants 1

77/05 i

2 78/07 4

1.64 Quality Assurance Requirements for the Design of Nuclear Power 73/10 Plants 1

75/02 2

76/06 i

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

r 1.66 (Withdrawn--See 42 FR 54478,10/06/77) y 1,67 Installation of Overpressure Protection Devices 73/10 1

4 1

1,68 Initial Test Programs for Water-Cooled Reactor Power Plants 73/11 1

77/01 78/C3

.1.68.1 Preoperational and Initial Startup Testing of Feedwater and 75/12 Condensate Systems for Boiling Water Reactor Power Plants 1 77/01 l

1.68.2 ' initial Startup Test Program to Demonstrate Remote Shutdown ---

77/01 l

Capability for Water-Cooled Nuclear Power Plants 1

78/07 73/12 1.69 Concrete Radiation Shields for Nuclear Power Plants

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Issued

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. Number Title Rev.

Year / Month 72/02 1.70 Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants 1

72/10 2

75/09 3

78/11 h

73/12 1.71 Welder Qualification for Areas of Limited Accessibility i

73/12 i

1.72 Spray Pond Piping Made from Fiberglass-Reinforced Thermosetting p

Resin 1

78/01 2

78/11 74/01 1.73 Qualification Tests of Electric Valve Operators installed Inside the Containment of Nuclear Power Plants 74/02

- 1.74 Quality Assurance Terms and Definitions

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1.'75 Physical Independence of Electric Systems 74/02 i

1 75/01 2

78/09 7

1.76 Design Basis Tornado for Nuclear Power Plants 74/04 7

1.77 Assumptions Used for Evaluating a Control Rod Ejection Accident 74/05

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for Pressurized Water Reactors 74/06 1.78 Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated liazardous Chemical Release

[ 1.79 Preoperational Testing of Emergency Core Cooling Systems for Pres-74/06

, (3 surized Water Reactors 1

75/09

\\N ] 1.80 Preoperational Testing of Instrument Air Systems 74/06 74/06 T 1.81 Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants 1

75/01 7

h 3

• 1.82 Sumps for Emergency Core Cooling and Containment Spray Systems 74/06 3 1.83 Inservice Inspection of Pressurized Water Reactor Steam Generator 74/06 Tubes 1

75/07-

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%1.84 -

Design and-Fabrication Code Case Acceptability--

y/,y ASME Section III, Division 1 2

75/06 3

75/09 4

75/11 5

76/02 6

76/05 7

76/08 8

76/11 9

77/03 10 77/08 11 77/11 12 78/03 13 78/07 14 78/11 I

j 1.85 Materials Code Case Acceptability--ASME Section 74/06 III, Division 1 1

75/04 2

75/06 3

75/09 4

75/11 5

76/02 6

76/05 i

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Issued

. Number Title Rev.

Year / Month 7

76/08 8

76/11 9

77/03 10 77/08 11 77/11 12 78/03 13 78/07 14 78/11

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1.86 Termination of Operating Licenses for Nuclear Reactors 74/06 74/06 1.87 Cuidance for Construction of Class 1 Components in Elevated-Temperature Reactors (Supplement to ASME Section III Code 1

75/06 Cases 1592,1593,1594,1595, and 1596)

's 74/08 1.88 Collection,' Storage, and Maintenance of Nuclear Power Plant Quality

. Assurance Records 1

75/12 2

76/10 h 1.B9 Qualification of Class IE Equipment for Nuclear Power Plants 74/11

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74/11 1.90 Inservice Inspection of Prestressed Concrete Containment Structures h

with Grouted Tendons 1

77/08 g/h1.91 Evaluations of Explosions Postulated to Occu. on Transportation 75/01 Routes Near Nuclear Power Plants (For Comment) 1 78/02 j d l.92 Combining Modal Responses and Spatial Components in Seismic Re-74/12 sponse Analysis 1

76/02 h 1.93 Availability of Electric Power Sources 74/12 y/

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

76/04 Construction Phase of Nuclear Power Plants 3 1.95 Protection of Nuclear Power Plant Control Room Operators Against an --

75/02 Accidental Chlorine Release 1

17761 Ob IA 1.96 Design of Main Steam Isolation Valve Leakage Control Systems for 75/05 Boiling Water Reactor Nuclear Power Plants 1

76/06

. /[ 3 1.97 Instrumentation for Light-Water-Cooled Nuclear Power Plants To 75/12 Assess Plant Conditions During and Following an Accident 1

77/08 1.98 Assumptions Used for Evaluating the Potential Radiological Conse-76/03 quences of a Radioactive Offgas System Failure in a Boiling Water Reactor (For Comment)

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Effects of Residual Elements on Predicted Radiation Damage to Reac 75/07 tor Vessel Materials 1

77/04 1.100 Seismic Qualification of Electric Equipment for Nuclear Power Plants 76/03 1

77/08 jcl 101 Emergency Planning for Nuclear Power Plants '

75/11 1

77/03 l

h1.102 Flood Protection for Nuclear Power Plants -

75/10 1

76/09 1.103 Post-Tensioned Prestressing Systems for Concrete Reactor Vessels 75/11 and Containments 1

76/10 6

Issued Number Title Rev.

Year / Month 1.104 Overhead Crane liandling Systems. for Nuc! car Power Plants (For 76/02 C/

Comment) h105 Instrument Setpoints 7

75/11 1.106 Thermal Overload Proteth for Electric Motors on Motor-Operated Valves 1

77/03 1.107 Qualifications for Cement Grouting for Prestressing Tendons in Con-75/11 tainment Structures

.1 77/02 fl.108 Periodic Testing of Diesel Generator Units Used as Onsite Electric 76/08

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Power Systems at Nuclear Power Plants 1

77/08 1.109 Calculation of Annual Doses to Man from Routine Releases of Reactor 76/03 Effluents for the Purpose of Evaluating Compliance with 10 CFR 1

77/10 Part 50 Appendix 1.

1.110 Cost-Benefit Analysis for Radwaste Systems for Light-Water-Cooled 76/03 Nuclear Power Reactors (For Comment) 7 1.111 Methods for Estimating Atmospheric Transport and Dispersion of 76/03 h8 Gaseous Effluents in Routine Releases from Light-Water-Cooled 1

77/07 Reactors 1.112 Calculation of Releases of Radioactive Materials in Gaseous and 76/04 Liquid Effluents from Light-Water-Cooled Power Reactors O-R 77/05 ph1.113 Estimating Aquatic Dispersion of Effluents from Accidental and

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76/05 Routine Reactor Releases for the Purpose of Implementing Appen-1 77/04 r

dix I t

fPI.114 Guidance on Being Operator at the Controls of a Nuclear Power Plant ---

76/02 1

76/11 1.115 Protection Against Low-Trajectory Turbine Missiles 76/03 1

77/07 1

1.116 Quality Assurance Requirements for Installation, inspection, and 76/06 17 Testing of Mechanical Equipment, and Systems O-R 77/05 1.117 Tornado Design Classification 76/06 1

78/04 h.118 Periodic Testing of Electric Power and Protection Systems 76/06 1

77/11 2

78/06 1.1 (Withdrawn--See 42 FR 33387. 6/30/77) 1.126 Fire Protection Guidelines for Nuclear Power Plants (For Comment) 76/06 1

77/11 1.121 Bases for Plugging Degraded PWR Steam Generator Tubes (For 76/08 Comment) 1.122 Development of Floor Design Response Spectra for Seismic Design of 76/09 Floor-Supported Equipment or Components 1

78/02 1.123 Quality Assurance Requirements for Control of Procurement of items 76/10 and Services for Nuclear Power Plants 1

77/07 1

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Issued

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Number Title Rev.

Year / Month (

76/11

.124 Service Limits and Loading Combinations for Class 1 Linear Type 1

78/01 Component Supports 77/03 411 5

Physical Models for Design and Operation of Hydraulic Structures and Systems for Nuclear Power Plants 1

78/10 77/03 1.126 An Acceptable Model and Related Statistical Methods for the Analysis of Fuel Densification 1

78/03 hl.127 Inspection of Water-Control Structures Associated with Nuclear Power ---

77/04 Plants 1

78/03

(" 4 [ 1.128 Installation Design and Installation of Large Lead Storage Batteries 77/04 for Nuclear Power Plants 1

78/JO I 1.129 Maintenance, Testing, and Replacement of Large Lead Storage Bat-77/04 teries for Nuclear Power Plants 1

78/02 77/07 1.130 Service Limits and Loading Combinations for Class 1 Plate-and-Shell-Type Component Supports 1

78/10 77/08 1.131 Qualification Tests of Electric Cables, Field Splices, and Connec-tions for Light-Water-Cocied Nuclear Power Plants (For Comment) 77/09 1.132 Site Investigations for Foundations of Nuclear Power Plants 1

79/03 77/09 1.133 Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors (For Comment) 77/09 r

1.134 Medical Certification and Monitoring of Personnel Requiring Operator Licenses 1

79/03 77/09 1.135 Normal. Water Level and Discharge at Nuclear Power Plants (For Conment) 77/11 1.136 Material for Concrete Containments 1

78/10 78/01 1.137 Fuel-Oil Systems for Standby Dissel Generators (For Comment) 78/04 1.138 Laboratory Investigations of Soils for Engineering Analysis and Design of Nuclear Power Plants (For Comment) 78/05 1.139 Guidance for Residual Heat Removal (For Comment) 78/03 1.140 Design, Testing, and Maintenance Criteria for Nonnal Ventilation Exhaust System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants (For Comment) 1.141 Containment Isolation hovisions for Fluid Systems (For Comment) 78/04 78/04 1.142 Safety-Related Concrete Structures for Nuclear Power Plants (Other Than Reactor Vessels and Containments) (For Comment) 78/07 1.143 Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants (For Comment) l.144 Auditing of Quality Assurance Programs for Nuclear 79/01 Power Plants (For Comment) 8

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April 1979 DIVISION 1 - POWER REACTORS DRAFT REGULATORY GUIDES Task Issued Number Title Year / Month EM 805-5 Nuclear Analysis and Design of Concrete 79/02 Radiation Shielding for Nuclear Power Plants RS 810-5 Qualification of Quality Assurance Program 79/02 Audit Personnel for Nuclear Power Plants SC 704-5 Functional Specification for Safety-Related 79/02 Valve Assemblies in Nuclear Power Plants SC 807-4 Determining Prestressing Forces for Inspection 79/04 (Proposed of Prestressed Concrete Containments-R.G.1.35.1) 1

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April 1979 DIVISION 1.- POWER REACTORS PROPOSED REVISIONS TO REGULATORY GUIDES Proposed.

Issued Task:& R.G.

Numbers Title Revision Year / Month RS 807-5 Personnel Selection and Training 2

79/02 1.8 c.

SC 810-4 Inservice Inspection of Ungrouted 3

79/04 1.35 Tendons in Prestressed Concrete Containments i

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April 1979 b

U.S. NUCLEAR REGULATORY COMMISSION

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REGULATORY GUIDE SERIES DIVISION 2 - RESEARCH AND TEST REACTORS TABLE OF CONTENTS This table of contents lists every revision of each regulatory guide in Division 2 with the dete it was issued. If the latest version of a guide (as of the date of this table of contents) was issued for early comment, this is so noted.

Division 2, one of ten broad divisions in which regulatory guides are issued, contains those guides that were developed for research and test reactors. There may also be some guides issued in other divisions that would be of interest to those whose primary concern is in the area of research and test reactors. Accordingly, this issue of the table of contents includes, for the first time, a listing of regulatory guides issued in the other divisions that the NRC staff has identified as possibly of interest to recipients of Divisfor. 2 guides.

This listing will be updated from time to time, and suggestions for additions to it are encouraged.

Most regulatory guides contain a section headed " Implementation" that is intended to provide information to applicants and licensees regarding the NRC staff's plans for using the guide. If a guide does not contain such a section or if detailed information is needed on the staff's plans for using a regulatory guide with respect to a specific permit or license or appli '

cation therefor, requests for such information should be addressed to the appropriate licensing-project manager in the Office of Nuclear Reactor Regulation or Office of Nuclear Material Safety and Safeguards.

At an approp te point in the development of a new regulatory guide or a proposed revision to an existing guide, the guide and the associated value/ impact statement are issued in draft form to involve the public in the early stages of the development of a regulatory position. These drafts have not received complete staff review and, do not represent an official NRC. staff position. They are temporarily identified by their task number and issued to the same distribution list that is used for published guides in each division. Lists of these drafts will be included in future issues of the table of contents.

All regulatory guides, including draft guides, proposed revisions, and all published revisions, may be examined at the Commission's Public Document Room at 1717 H Street NW., Washington,

D.C.

Requests for single copies of draft _ guides, proposed revisions, and the latest revision of published guides, the only version currently in print, should be made in writing to the U.S. Nuclear Regulatory Commission, Washin gton, D.C. 20555, Attention: Director, Division of Technical Infonnation and Document Control. Regulatory guides are not copyrighted and Commission approval is not required to reproduce them.

Regulatory Guides issued Number Title Rev.

Year / Month 2.1 Shield Test Program for Evaluation of Installed Biological Shielding 73/05 in Research and Training Reactors 2.2 Development of Technical Specifications for Experiments in Research 73/11 Reactors 2.3 Quality Verification for Plate-Type Uranium-Aluminum Fuel Elements 75/09 for Use h1 Research Reacters 1

76/07 2.4 Review of Experiments for Research Reactors 76/07

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O-R 77/05

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1

Issued Number Title Rev.

Year / Month 2.5 Quality Assurance Program Requirements for Research Reactors 77/05 O-R 77/10 2.6 Emergency Planning for Research Reactors (For Comment) 79/01 f

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'm May 1979 DIVISION 3 REGULATORY GUIDES r.

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FUELS AND MATERI ALS FACILITIES TABLE OF CONTENTS Previous issues of this = table of contents listed only.the latest revision of each regulatory guide because it represented a current NRC staff position. However, some licensing commit-ments were based on earlier versions of a guide; therefore, this and future issues of the table of contents will list every version of each guide with the date it was issued, If the latest version of a guide (as of the date of this table of contents) was issued for early comment, this is so noted.

Most regulatory guides contain a section headed " Implementation," which is intended to provide infor. ation to applicants and licensees regarding the NRC staff's plans for using the guide. If a guide does not contain such a section or if detailed information is needed on the staff's plans for using a regulatory guide with respect to a specific permit or license or appli-cation therefor, requests for such information should be addressed to the appropriate licensing project manager in the Office of Nuclear Reactor Regulation or Office of Nuclear Material Safety and Safeguards.

Requests for single copies of the latest revision of a regulatory guide, the only version currently in print, should be made in writing to the U.S. Nuclear Regulatory Commission, Director, Division of Technic 1 Information and Document Washington, D.C. 20555, Attention:

Control. Earlier revisions may be examined at the Commission's Public Document Room,1717 H Street NW., Washington, D.C.

Regulatory guides are not copyrighted, and Commission approval 4

- is not required to reproduce them.

Issued l

Rev. Year / Month k

Number Title 1

73/01-3.1 Use of Borosilicate-Glass Raschig Rings as a Neutron Absorber in Solutions of Fissile Material f

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

3.3 Quality Assurance Program Re luirements for Fuel Reprocessing Plants ---

73/01 and for Plutonium Processing and Fuel Fabrication I'lants 1

74/03 3.4 Nucle r Criticality Safety in Operations with Fissionable Materials 73/01 1

77/08 Out.ide Reactors 1-R 78/02 73/02 3.5 Standard Format and Content of License Applications for Uranium 1

77/11 Mills (For Comment) 3.6 Content of Technical Specifications for Fuel Reprocessing Plants 73/04

)

73/03 3.7 Monitoring of Combustible Cases and Vapors in Plutonium Processing and Fuel Fabrication Plants 3.8 Preparation of Environmental Reports for Uranium Mills (For 73/04 1

78/09 Comment) 9

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Issued Number Title Rev. Year / Month 3.9 Concrete Radiation Shields 73/06 7

3.10 Liquid Waste Treatment System Design Guide for Plutonium Processing ---

73/06 and Fuel Fabrication Plants 3.11 Design, Construction, and Inspecton of Embankment Retes,n 73/06 Systems for Uranium Mills 1

77/03 2

77/12 3.11.1 Operationel Inspection and Surveillance of Embank-79/04 ment Retention Systems for Uranium Mill Tailings (For Comment) 3.12 General Design Guide for Ventilation Systems of Plutonium Processing ---

73/08

. and Fuel Fabrication Plants 3.13 Guide for Acceptable Waste Storage Methods at UF Produedon Plants ---

73/10 6

73/10 3.14 Seismic Design Classification for Plutonium Processing and Fuel Fabrication Plants 3.15 Standard Fonnat and Content of License Applications for Storage 73/10 Only of Unirradiated Reactor Fuel and Associated Radioactive Material 74/01

/'

3.16 General Fire Protection Guide for Plutonium Processing and Fuel Fabrication Pla'nts t

74/02 3.17 Earthquake Instrumentation for Fuel Reprocessing Plants 74/02 3.18 Confinement Barriers and Systems for Fuel Reprocessing Plants 3.19 Reporting of Operating Information for Fuel Reprocessing Plants 74/02 74/02 3L Process Offgas Systems for Fuel Reprocessing Plants 74/03 23.21 Quality Assurance Requirements for Protective Coatings Applied to Fuel Reprocessing and to Plutonium Processing and Fuel Fabrication Plants 3.22 Periodic Testing of Fuel Reprocessing Plant Protection System 74/06 Actuation Functions i

3.23 Stabilization of Uranium-Thorium Milling Waste Retention Systems 74/11 s --

3.24 Guidance on the Licet.se Application Siting, Design, and Plant Pro- ---

74/12

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tection for an Independent Spent Fuel Storage Installation w

w

Issued Number Title Rev. Year / Month f-(

74/12 3.25 Standard Fonnat and Content of Safety Analysis Reports for U*

ium s\\-

Enrichment Facilities 75/02 3.26 Standard Format and Content of Safety Analysis Reports for Fuel Reprocessing Plants 75/05 3.27 Nondestructive Examination of Welds in the Liners of Concrete Barriers in Fuel Reprocessing Plants 1

77/05 75/05 3.28 Welder Qualification for Welding in Areas of Limited Accessibility in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants 3.29 Preheat and Interpass Temperature Control for the Welding of Low-75/05 Alfoy Steel for Use in Fuel Reprocessing Plants and in Plutonium Processing and Fuel Fabrication Plants 75/06 3.30 Selection, Application, z.ad Inspection of Protective Coatings (Paints) for Fuel Reprocessing Plants O-R 77/05 75/09 3.31 Emergency Water Supply Systems for Fuel Reprocessing Plants O-R 77/05 75/09 3.32 General Design Guide for Ventilation Systems for Fuel Reprocessing Systems (For Comment) 77/04 3.33 Assumptions Used for Evaluating the Potential Radiological Conse-s quences of Accidental Nuclear Criticality in a Fuel Reprocessing Plant (For Comment) 77/04 3.34 Assumptions Used for Evaluating the Potential Radiological Conse-quences of Accidental Nuclear C.-iticality in a Uranium Fuel Fabrication Plant (For Comment) 3.35 Assumptions Used for Evaluating the Potential Radiological Conse-77/05 quences of Accidental Nuclear Criticality in a Plutonium Process-ing and Fuel Fabrication Plant- (For Comment) 3.3s

.(Withdrawn -- See 44 FR 6535 02/01/79) 3.37 Guidance for Avoiding Intergranular Corrosion and Stress Corrosion ---

75/09 in Austenitic Stainless Steel Components of Fuel Reprocessing Plants (For Comment) 3.38 General Fire Protection Guide for Fuel Reprocessing Plants (For 76/06 Comment) 3.39 Standard Format and Content of License Applications for Plutonium 76/01 Processing and Fuel Fabrication Plants 3,40 Design Basis Floods for Fuel Reprocessing Plants and for Plutonium 76/11 Processing and Fuel Fabrication Plants 1

77/12 3

l

Issued e

Number Title Rev. Year / Month

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76/06 3.41 Validation of Calculational Methods for Nuclear Criticality Safety 7j 1

77/05 77/08 3.42 Emergency Planning for Fuel Cycle Facilities and Plants Licensed Under 10 CFR Parts 50 and 70 (For Comment) 1 78/08 3.43 Nuclear Criticality Safety in the Storage of Fissile Materials 1~,

79/04 78/12 3.44 Standard Format and Content for the Safety Analysis Report To Be Included in a License Application for the Storage of Spent Fuel in an Independent i

Spent Fuel Storage Installation (Water-Basin Type) i.

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Draft Regulatory Guides Task Issued fiumber Title Year / Month RH 802-4 Calculational Models for Estimating Radiation Doses 79/05 to Man From Airborne Radioactive Materials Resulting From Uranium Milling Operations

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May 1979

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DIVISION 4 HEGlfl.ATOHY GUIDES ENVih0NMENTAI AND SITING TABl.E OF CONTENTS Previcus issues of this table of contents listed only the latest revision of each regulatory guide because it represented a current NRC staff position. Ilowever, some licensing commit-ments were based on earlier versions of a guide; therefore, this and future issues of the table of contents will list every version of each guide with the date it was issued. If the latest version of a guide (as of the date of this table of contents) was issued for early comment, this is so noted.

Most regulatory guides contain a section headed " Implementation," which is intended to provide information to applicants and licensees regarding the NRC staff's plans for using the guide. If a guide does not contain such a secton or if detailed information is needed on the staff's plans for using a regulatory guide with respect to a specific permit or license or appli-cation therefor, requests for such information should t c addressed to the appropriate licensing project manager in the Office of Nuclear Reactor Regulation or Office of Nuclear Material Safety and Safeguards.

Requests for single copies of the latest revision of a regulatory guide, the only version currently in print, should be made in writing to the U.S. Nuclear Regulatory Commission, Washington. D.C 20555. Attention: Director, Division of Technical Information and Document Con t rol. Earlier revisions may be examined at the Ccemission's Public Document Room,1717 H Street, NW., Washington, D.C.

Regulatory guides are not copyrighted, and Commission approval is not required to reproduce them.

Issued Number Title Rev.

Year / Month 4.1 Programs for Monitoring Radioactivity in the Environs of Nuclear 73/01 Power Plants (For Comment) 1 75/04 4.2 Preparation of Environmental Reports for Nuclear Power Stations 71/02 1

75/01 2

76/07 4.3 (WITilDR AWN--See 41 FR 53870,12/09/76) 4.4 Reporting Procedure for Mathematical Models selected to Predict 74/05 lleated Effluent Dispersion in Natural Water Bodies 4.5 Measurements of Radionuclides in the Environment--Sampling and 71/05 Analysis of Plutonium in Soil

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4.0 Measurements of Radionuclides in the Environment---Strontium-89 74/05 and Strontium-90 Analyses o

4.7 General Site Suitability Criteria for Nuclear Power Sthtions 74/09 1

75/11 4.8 Environmental Technical Specifications for Nuclear Power Plants 75/12 (For Comment) 1.9 Preparation of Environmental Reports for Commercial Uranium 74/12 Enrichment Facilities 1

75/10 l

e

d issued Number Title Rev.

Year / Month

- 4.10 (WITIIDRAWN--See 42 FR 59436,; 11/17/77) 4.11 Terrestrial Environmental Studies for Nuclear Power Stations 76/07 1

77/08 4.12 (Not yet published) i

- 4.13 Performance, Testing, and Procedural Specifications for Thermo-76/11 luminescence Dosimetry: Environmental Applications 1

77/07 77/06

.4.14 Measuring, Evaluating, and Reporting Radioactivity in Releases of Radioactive Materials in Liquid and Airborne Effluents from Uranium Mills (For Comment)

, s 4.15 Quality Assurance for Radiological Monitoring Programs (Normal 77/12 i

Operations)--Effluent Streams and the Environment 1

79/02 4.16 Measuring, Evaluating, and Reporting Radioactivity in Releases 78/03 of Radioactive Materials in Liquid and Airborne Effluents from Nuclear Fuel Processing and Fabrication Plants (For Comment) e i

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l Proposed Revisions to Regulatory Guides R.G. and Task Proposed Issued Numbers Title Revision Year / Month 5.7 (SG 909-4)

Entry / Exit Cor.crol to Protected Areas, Vital 1

79/05 Areas, and Material Access Areas 5.14 Use of Observation (Visual Surveillance) Techniques 1

79/05 (SG 910-4) in Material Access Areas F

5.44 Perimeter Intrusion Alarm Systems 2

79/05 (SG 479-4) 5.57 Shipping and Receiving Control of Strategic Special 1

79/05 (SG 908-4)

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DIVISION 5 REGULATORY GUIDES MATERIALS AND PLANT PROTECTION TABLE OF CONTENTS Previous issues of this table of contents listed only the latest revision of each regulatory guide because it represented a current NRC staff position. However, some licensing commit-ments were based on earlier versions of a guide; therefore, this and future issues of the table of contents will lit t every version of each guide with the date it was issued. If the latest version of a guide t, ' of the date of this table of contents) was issued for early comment, this is so noted.

Most regulatory guides contain a section headed " Implementation," which is intended to provide infomation to applicants and licensees regarding the NRC staff's plans for using the guide. If a guide does_ not contain such a section or if detailed information is needed on the.

staff's plans for using a regulatory guide '<ith respect to a specific pemit or license or appli-cation therefor, requests for such infomition should be addressed to the appropriate licensing project manager in the Office of Nuclear Reactor Regulation or Office of Nuclear Material Safety and Safeguards.

Requests for single copies of the latest revision of a regulatory guide, the only version currently fa print, should be made in writing to the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Director, Division of Technical. Information and Document Control. Earlier revisions may be examined at the Commission's Public Document Room,1717 H Street NW., Washington, D.C.

Regulatory guides are not copyrighted, and Commission approval is not required to reproduce them.

Number Issued Title Rev. Year / Month f.

5.1 Serial Numbering of Fuel Assemblies for Light-Water-Cooled Nuclear 72/12 s

Power Reactors 5.2 Classification of Unitradiated Plutonis s and Us anium Scrap 72/12 5.3 Statistical Terminology and Notation for Special Nuclear Materials 73/02 Control and Accountability 5.4 Standard Analytical Methods for the Measurement of Uranium Tetra-73/02 fluoride (UF ) and Uranium Hexafluoride (UF )

4 6

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5.5 Standard Methods for Chemical, Mass Spectrometric, and Spectro-73/02 chemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets 5.6 Standard Methods for Chemical, Mass Spectrometric, and Spectro-73/05 chemical Analysis of Nuclear-Grade Plutonium Dioxide Powders and Pellets and Nuclear-Grade Mixed Oxides ([U,Pu]O )

2 5.7 Control of Personnel Access to Protected Areas, Vital Areas, and 73/0G l

Material Access Areas 5.8 Design Considerations for Minimizing Residual Holdup of Special 73/06 Nuclear Material in Drying and Fluidized Bed Operations 1

74/05 5.9 Specifications of Ge(Li) Spectroscopy Systems for Material Protec-73/06 tion Measurements--Part I: Data Acquisition Systems 1

74/05

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Year / Month Title Number 73/07 Selection and Use of Pressure-Sensitive Seals on Containers for On-

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5.10 site Storage of Special Nuclear Material 73/10 Nondestructive Assay of Special Nuclear Material Contained in Scrap 5.11 and Waste 73/11 General Use of Locks in the Protection and Control of Facilities and 5.12 Special Nuclear Materials 73/11 Conduct of Nuclear Material Physical Inventories 5.13 73/11 Visual Surveillance of Individuals in Material Access Areas 5.14 74/01 Security Seals for the Protection and Control of Special Nuclear 5.15 Material 74/01 Standard Methods for Chemical, Mass Spectrometric, Spectrochemical, -~

1 75/05 5.16 Nuclear, and Radiochemical Analysis of Nuclear-Grade Plutonium Nitrate Solutions and Plutonium Metal (For Comment) 74/01 5.17 Truck Identification Markings 74/01 Limit of Error Concepts and Principles of Calculation in Nuclear 5.18 Materials Control 74/01 Methods for the Accountability of Plutonium Nitrate Solutions 5.19 74/01 Training, Equipping, and Qualifying of Guards and Watchmen 5.20 74/04 Nondestructive Uranium-235 Enrichment Assay by Gamma-Ray

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5.21 Spectrometry 74/04

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Assessment of the Assumption of Normality (Employing Individual 5.22 Observed Values) 74/05 e

5.23 In Situ Assay of Plutonium Kasidual Holdup 74/06 Analysis and Use of Process Data for the Protection of Special 5.24 Nuclear Material 74/06 Design Considerations for Minimi2i; s..esidual Holdup of Syecial 5.25 Nuclear Material in Equipment for Wet Process Operations 74/06 Selection of Material Balance Areas and Item Control Areas 1

75/04 1

5.26 74/06 5.27 Special Nuclear Material Doorway Monitors 74/06 Evaluation of Shipper-Receiver Differences in the Transfer of Special --

5.28 Nuclear Materials 74/06 Nuclear Material Control Systems for Nuclear Power Plants 1

75/06 5.29 74/06 Materials Protection Contingency Measures for Uranium and Plutonium ---

5.30 Fuel Manufacturing Plants 74/06 Specially Designed Vehicle With Armed Guards for Road Shipment of 1

75/04 5.31 Special Nuclear Material 74/06

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Communication With Transport Vehicles 1

75/05 5.32 74/06 Statistical Evaluation of Material Unaccounted For l

5.33 2

Issued Number Title Rev.

Year / Month 5.34 Nondestructive Assay for Plutonium in Scrap Material by Spontaneous ---

74/06 d

Fission Detection 5.35 (Withdrawn -- See 42 FR 41677, 8/18/77) 74/06 5.36 Recommended Practice for Dealing With Outlying Observations 74/08 5.37 In Situ Assay of Enriched Uranium Residual Holdup 74/09 5.38 Nondestructive Assay of High-Enrichment Uranium Fuel Plates by Gamma-Ray Spectrometry 74/12 5.39 General Methods for the Analysis of Uranyl Nitrate Solutions for Assay, Isotopic Distribution, and Impurity Deteminations 74/12 5.40 Methods for the Accountability of Plutonium Dioxide Powder 5.41 (Not issued) 5.42 Design Considerations for Minimizing Residual Holdup of Special 75/01 Nuclear Material in Equipment for Dry Process Operation 75/01 5.43 Plant Security."orce Duties 5.44 Perimeter Intrusion Alarm Systems 75/01 1

76/06 5.45 Standard ForTnat and Content for the Special Nuclear Material Control ---

74/12 and Accounting Section of a Special Nuclear Material License Application (including That for a Uranium Enrichment Facility) f 5.46 (Not issued)

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5.47 Control and Accountability of Plutonium in Waste Material 75/02 75/02 5.48 Design Considerations--Systems for Measuring the Mass of Liquids 75/03 i

5.49 Internal Transfers of Special Nuclear Material (For Comment) 5.50 (Not issued) 5.51 Management Review of Nuclear Material Control and AccouAting Sys- ---

75/06 tems (For Comment) 5.52 Standard Format and Content for the Physical Protection Section of 75/05 a License Application (for Facilities Other Than Nuclear Power 1

76/06 Plants)(For Comment)

Revisions (For 60-Day Comment) to Chapter 4, " Security Organiza-tion," and Chapter 18, " Security Personnel," of Regulatory Guide 5.52, Revision 1 (For Comment) were issued July 1978.

5.53 Qualification, Calibration, and Error Estimation Methods for Non-75/08 destructive Assay (For Comment) 5.54 Standard Fonnat and Content of Safeguards Contingen y Plans for 78/03 Nuclear Power Plants (For Commenti 78/03 5.55 Standard Format and Content of Safeg iards Continger :y Piri.s (or Fuel Cycle Facilities (For Comment) 5.56 Standard Format and Content of Safeguards Contingency. 'sn:, for 78/03 Transportation (For Comment) i 4

3

Issued Numbir Titla Rev. Year / Month 5.57 Shipping and Receiving Control of Special Nuclear Material (For 76/06 f

Comment) 5.58 Considerations for Establishing Traceability of SNM Accounting

~8/11 Measurements (For Comment)

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May 1979 U.S. NUCLEAR REGULATORY CO>DilSSION i

REGULATORY GUIDE SERIES DIVISION 6 - PRODUCTS TABLE OF CONTENTS [

Previous issues of this table of contents listed only the latest revision of each regulatory guide in Division 6 because it represented a current NRC staff position. However, some licensing commitments were based on earlier versions of a guide; therefore, this tsnd future issues of the table of contents will list every version of each guide in Division 6 with the date it was issued. If the latest version 'of a guide (as of the date of this table of contents) was issued for early comment, this is so noted.

Division 6, one of ten broad divisions in which regulatory guides are issued, contains those guides that were developed to provide guidance in the area of products. There may also be some guides issued in otner divisions that would be of interest to those whose primary concern is in the area of products. Accordingly, this issue of the table of contents includes, for the first time, a listing of regulatory guides issued in the other divisions that the NRC staff has identified as possibly of interest to recipients of Division 6 guides. This listing will be updated from time to time, and sugge stions for additions to it are encouraged.

Most regulatory guides contain a section headed " Implementation" that is intended to provide information to applicants and licensees regarding the NRC staff's plans for using the guide. If a guide does not contain such a section or if detailed information is needed on the staff's plans for using a regulatory guide with respect to a specific permit or license or appli-cation therefor, requests for such information should be addressed to the appropriate licensing project manager in the Office of Nuclear Reactor Regulation or Office of Nuclear Material Safety and Safeguards.

At an appropriate point in the development of a new regulatory guide or a proposed revision

(-

to an existing guide, the guide and the associated value/ impact statement are issued in draft form to involve the public in the early stages of the development of a regulatory position.

These drafts have not received complete staff review and do not represent an official NRC staff position. They are temporarily identified by their task number and issued to the same distribu-tion list that is used for published guides in each division. Lists of these drafts will be included in future issues of the table of contents.

All regulatory guides, including draft guides, proposed revisions, and all published revisions, may be examined at the Commission's Public Document Room at 1717 H Street NW., Washington, D.C.

Requests for single copies of draft guides, proposed revisions, and the latest revision of published guides, the only version currently in print, should be made in writing to the U.S.

Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Director, Division of Technical Information and Document Control. Regulatory guides are not copyrighted and Commission approval is not required to reproduce them.

Regulatorv Guides issued Number Title Rev.

Year / Month a

e 6.1 Leak Testing Radioactive Brachytherapy Sources 74/02 1

74/07 3

6.2 Integrity and Test Specifications for Selected Brachytherapy 74/02 Sources 74/07 74/03 6.3 Design, Construction, and Use of Radioisotopic Power Generators for Certain Land and Sea Applications 1

..e

Issued Numbzr Title Rev.

Year / Month 6.4 Classification of Containment Properties of Radioactive 74/03 Sources Contained in Certain Devices To Be Distributed.

1 75/05 for Use Under General License 6.5 General Safety Sandard for Installations Using Nonmedical 74/06 S,ealed Gamma-Ray Sources 6.6 Acceptance Sampling Procedures for Exempted and Generally 74/06 Licensed items Containing Byproduct Material 6.7 Preparation of an Environmental Report To Support a Rule 75/10 Making Petition Seeking an Exemption for a Radionuclide-1 76/06 Containing Product 6.8 Identification Plaque for Irretrievable Well-Logging Sources 78/10 (For Comment) r C

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March 1979 DItISI0tl 7 - TRAt1SPORTATION TABLE OF C0t1 TENTS Regulatory Guides Issued Number Title Rev.

Year / Month 7.1 Administrative Guide for Packaging and 74/06 Transporting Radioactive Material 7.2 Packaging and Transportation of Radioactively 74/06 Contaminated Biological Materials 7.3 Procedures for Picking Up and Receiving 75/05 Packages of Radioactive Material (For Comment) 7.4 Leakage Tests on Packages for Shipment of 75/06 Radioactive Materials (For Comment) 7.5 Administrative Guide for Obtaining Exemptions 75/06 From Certain NRC Requirements Over 0-R 77/05 Radioactive Material Shipments

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7.6 Design Criteria for the Structural Analysis 77/02 of Shipping Cask Containment Vessels 1

78/03 7.7 Administrative Guide for Verifying Compliance 77/08 With Packaging Requirements for Shipments of Radioactive Materials (For Comment) 7.8 Load Combinations for the Structural Analysis 77/05 of Shipping Casks 7.9 Standard Fonnat and Content of Part 71

'79/03 Applications for Approval of Packaging of Type B, Large Quantity, and Fissile Radioactive Material (For Comment)

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April 1979

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U.S. NUCLEAR REGULATORY COMMISSION n

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w4 OFFICE OF STANDARDS DEVELOPMENT DIVISION 8 REGULATORY GUIDES OCCUPATIONAL HEALTH TABLE OF CONTENTS Previous issues of this table of contents listed only the latest revision,of each regulatory guide because it represented a current NRC staff position. However, some licensing commitments were based on earlier versions of a guide; therefore, this and future issues of the table of contents will list every version of each guide with the date it was issued. If the latest version of a guide (as of the date of this table of contents) was issued for early comment, this is so noted.

51ost regulatory guides contain a section headed " Implementation," which is intended to provide information to applicants and licensees regarding the NRC staff's plans for using the guide. If a guide does not contain such a section or if detailed information is needed on the staff's plans for using a regulatory guide with respect to a specific permit or license or application therefor, requests for such information should be addressed to the appropriate licensing project manager in the Office of Nuclear Reactor Regulation or Office of Nuclear Staterial Safety and Safeguards.

Number Title Rev.

Issued 8.1 Radiation Symbol 2/2/73 8.2 G L.id e for Administrative Practices in Radiation

(

Nfonitoring 2/2/73 8.3 Film Badge Performance Criteria 2/2/73 2

8.4 Direct-Reading and Indirect-Reading Pocket Dosimeters 2/26/73 8.5 Immediate Evacuation Signal 2/16/73 8.6 Standard Test Procedure for Geiger-N1uller Counters 5/73 8.7 Occupational Radiation Exposure Records Systems 5/73 8.8 Information Relevant to Ensuring That Occupational 7/73 Radiation Exposures at Nuclear Power Stations Will Be 1

9/75 As Low As Is Reasonably Achievable 2

3/77 3

6/78 8.9 Acceptable Concepts, 51odels, Equations, and 9/73 Assumptions for a Bioassay Program 8.10 Operating Philosophy for N1aintaining Occupational 4/74 Radiation Exposures As Low As Is Reasonably 1

9/75 Achievable 1-R 5/77 8.11 Applications of Bioassay for Uranium 6/74 8.12 Criticality Accident Alarm Systems 12/74 8.13 Instruction Concerning Prenatal Radiation Exposure 3/75

\\

1 11/75

Number ~

Title

Rev, Issued 8.14 Personnel Neutron Dosimeters 6/76 I

8/77 8.15 Acceptable Programs for Respiratory Protection 10/76

_ Not yet publishel; 8.16

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9.17 (Not yet published) 8.18 Information Relevant to Ensuring That Occupational 12/77 Radiation Exposures at NiedicalInstitutions Will Be As Low As Reasonably Achievable (For Comment) 8.19 Occupational Radiation Dose Assessment in Light-Water 5/78 Reactor Power Plants-Design Stage 51an-Rem Estimates (For Comment) 8.20 Applications of Bioassay for I-125 and 1-131 (For 4/78 Comment) 8.21 Health Physics Surveys for Byproduct Staterial at 5/78 NRC-Licen Processing and 51anufacturing Plants (For Commc.,

8.22 Bioassay at Uranium hiills (For Comment) 7/78 2/79 8.23 Radiation Safety Surveys at Medical Institutions (For Cor.unent) 8.24 Health Physics Surveys During Enriched 11/78

[

Uranium-235 Processing and Fuel.

(

Fabrication (For Comment) a 4

2

April 1979 DIVISION 8 - OCCUPATIONAL HEALTH PROPOSED REVISIONS TO REGULATORY GUIDES Task and R.G.

Proposed Issued Numbers Title Revision Year / Month OH 507-4 Information Relevant to Ensuring That 4

79/03

-8.8 Occupational Radiation Exposures at Nuclear Power Stations Will Be As low As Is Reasonably Achievable j

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October 1978 Ci DIVISION 9 REGULATORY GUIDES ANTITRUST AND FINANCIAL REVIEW TABLE OF CONTENTS Number Title 9.1 Regulatory Staff Position Statement on Antitrust Matters (12/73) 9.2 Information Needed by the NRC Staff in Connection with Its

- s Antitrust Review of Construction Permit Applications for Nuclear Power Plants (Revision 1, 6/76) 9.3 Information Needed by the AEC Regulatory Staff in Connection with Its Antitrust Review of Operating Licen'se Applications for Nuclear Power Plants (10/74) 9.4 Suggested Format for Cash Flow Statements Submitted as Guarantees of Payment of Retrospective Premiums (9/78)

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January 1979

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DIVISION 10 REGULATORY GUIDES GENERAL TABLE OF CONTENTS Number Title 10.1 Compilation of Reporting Requirements for Persons Subject to NRC Regulations (Revision 3, 5/77) 10.2 Guidance to Academic Institutions Applying for Specific Byproddet.

Material Licenses (Revision 1, 12/76) 10.3 Guide for the Preparation of Applications for Special Nuclear Matt rial Licenses of Less Than Critical Mass Quantities (Rev. 1, 5/77) 10.4 Guide for the Preparation of Applications for Licenses to Process Source Material (Revision 1, 3/77) 10.5 Guide for the Preparation of Applications for Type A Licenses of Broad Scope for Byproduct Material (9/76) 10.6 Guide for the Preparation of Applications for Use of Sealed Sources and Devices for the Performance of Industrial Radiography (9/76) 10.7 Guide for the Preparation of Applications for Licenses for Laboratory Use of Small Quantities of Byproduct M terial (2/77) a 10.8 Guide for the Preparation of Applications for Medical Programs (For

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March 1979 f

DIVISION 10 - GENERAL Draft Regulatory Guides l

Task Issued

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Number Title Year / Month OH 706-4 Guide for Preparation of Applications 79/02 for the Use of Gamma Irradiators

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