ML19206B341

Forwards Lists of NRC Regulations & Reg Guides Classified as Category a & B

ML19206B341
Person / Time
Site:	Crane
Issue date:	04/12/1979
From:	Arlotto G NRC OFFICE OF STANDARDS DEVELOPMENT
To:	Minogue R NRC OFFICE OF STANDARDS DEVELOPMENT
References
NUDOCS 7905090228
Download: ML19206B341 (10)

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WNQ APR 1 ~o 1973 MEMORA!:DU;1 FOR: Robert B. Minogue, Director Office of Standards Developnent FRO.'t :

Guy A. Arlotto, Director Divisior of Engineering Standards SUDJECT:

NRC REGULATIONS A':D RECUllsTORY CUI:'ES Enclosed, as you instructed at today's cceting, are lists of URC regulations and Regulatory Cuides that are classified as Category "A" and Category "B".

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I Guy A. Arlotto, Director Division of Engineering S'.andards l

Office of Standards Development cr:

Ray G. Smith, SD:DD i

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DISTRIBUTION:

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NRC REGULATI0'lS Category A 10 CFR 50.44 Standards for Combustible Gas Control Systems in Light Water Cooled Power Reactors 10 CFR 50.46 Acceptance Criteria for Energency Core Cooling Systems for Light Water Nuclear Power Reactors 10 CFR 30, Appendix K ECCS Evaluation Models 10 CFR 55 Operators' Licenses 10 CFR 100 Reactor Site Criteria L4

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J NRC REGULATIONS Category B 10 CFR 21 Reporting of Defects and Noncompliance 10 CFR 50.55a Codes and Standards 10 CFR 50, Appendix A General Design Criteria for Nuclear Power Plants 10 CFR 50, Appendix B Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants 10 CFR 50, Appendix E Emergency Plans for Production and Utilization Facilities 10 CFR 50, Appendix G Fractur? Toughness Requirements 10 CFR 50, Appendix H Reactor Vessel Material Surveillance Program Requirements 10 CFR 50, Appendix J Primary Reactor Containment Leakage Testing for Mater-Cooled Power Reactors Proposed Amendments to Parts 11, 50 cnd 70 - Clearance Rule i o.'ts 19 and 20 Control of Radiation Doses to Transient Workers (Proposed)

Parts 20, 30, 40, 50 and 70 Ocrupational ALARA Rule Change (Proposed) 24 338 i

i REGULATORY GUIDES i

i Category A 1

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.\\ssumpticns Used for Evaluating the Potentiol Radic! weal Conse-quences of a Loss of-Coc! ant Accident for Boing Water Reactors 1.4 Assumptions Used for Evaluating the Potential Radiological Conse-quences of a Loss-of-Coolant Accident for Pressurced Water Reactor s 1.5 Assumptior ~ Used for Evaluatmg the Potential Radiological Conse-quences of a Steam Line Break Accident for Bothng Water Reactors (Safety Guide 5) 1.7 Control of Ccmbustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident 1.8 Personac! Selection and Training i

1.21 Measuring, Evaluating, and Reportint-Radi, activity in Solid Wastes and Releascs cf Itad:oac:ree Aternis m Liquid and Ga cous Effluents from Lt;,ht.Mer-C aled Nuclear Power Plants 1.23 Onsite Meteorological Programs (Safety Guide 23) 1.33 Quality Assurance Program Requirements (Operation) 1.40 Quahfication Tests of Ccntinuous-Duty Sictors Installed Inside the Containment cf Water-CN!c : ';uclear Power Plants 1.47 Bypassed and Inoperable Status Indicati:n for Nuclear Power Plant Safety Sy:,tems 1.52 Design, Testing, and Maintenance Criteria for Post Accident Engineered-Safet,-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Lignt-Oter-cooled Nuclear Power Plants 1.57 Design Linits and Loading Cembmations for Metal Pcimary Reactor Containment System Components 1.73 Qualification Tests 07 Electric "alse Operators Installed Inside the Containment of Nuc! car Power Plants 1.89 Qualification cf Class IE Equipment for Nuc: car Power Plants 1.97 Instrumentation for Light-hater-Cooled ',uclear Power Plants To Assess Plant Conditions Durmg and Fel!av.mg an Accident 1.111 Emergency Planning for Nuclear Power Plants 1.114 Guidance on Being Operator at the Controls cf a Nuc! car Power Plant 1.131 Qua!aication Tests of Electri-Cables. Field Splices and Ccnnec-tiens for Light ':atcr-Locied Nuclear Power Plants (r.

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REGULATORY GUIDES l

Category A

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1.139 Cuidance for Residual Heat Rcmoval (For t.

it) 1.140 Design, Testing, and Maintenance Criteria for Nomal Ventilation Exhau:t System Air Filtranon and Adsorption Units of Light-Water-Cocled Nuclear Power Plants (For Cumment) 1.141 Containment I:,olation Provisions for Fluid Systems (For Coir. ment) 1.143 Design Guidance for Radioactive Waste Manaamcat Systems, Structures, and Ccmponents Installed in Li.;ht-Water-Cooled Nuclear Power Plants (For Ccmment)

Criteria for EIcetric, Instrumentation. and Control Portions of Safety Systems Qualification of E!ectric Mcdules for Nuclear Power Plants Atmospheric Dispersion Models for Potential Accitat Consequence Assessments at Nuclear Power Plan'.s Recommendation for In Service Testing of Valves which Perform Safety Functions in LWR's.

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Under Development REGULATORY GUIDES Category A 4.1 Programs for ffonitoring Radioactivity in the Environs of Nuclear Power Plants 4.6 Measurement of Radionuclides in the Environment - Strontium-89 and Strontium 90 Analyses 4.7 General Site Suitability Criteria for Nuclear Power Stations Bioassay Fission and Corrosion Products 7 li

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L 't Under Development REGULATORY GUIDES Category B 1.1 Net Positive Suction Head f.'r Emergency Ccre Cooling and Contain-ment lleat Remo"11 Syston Pumps (Safety Gu:de 1) 1.2 Thenna! Shock to Peactor Pressure Vessels (oafety Guide 2) 1.6 Independtnce Between Redundant Standby 2nsite) Power Sources and betwcen The:r Distribution Systems (Safety Guide 6) 1.11 Instrument Lines Penetrating Primary Reactor Containment (Safety Guide 11)

Supplement to Safety Guide 11, Backfitting Consideraticns 1.13 Sptnt Fuel Storage Facility Design Basis (For Comment) 1.16 Reporting of Operating Information-- Appendix A Technical Specifi-cations (For Comment) 1.17 Protection of N,uclcar Power Plants Against Industrial Sabotage 1.19 Nondestructive Examinatien of Primary Centainment Liner Welds (Safety Guide 19) 1.22 Periodic Testing cf Protection System Actuation Functions (Safety Guide 22) 1.24 Assumptions Used for Evaluating the Pctential Radiological Conse-quences of a Pressur: zed Water Reactor Radioactive Gas Storage Tank Failure (Safety Guide 2-4) 1.25 Assumpticns Used for Evaluating the Pctential Radiological Conse-quences of a Fuel Handling Accident in the Fuel Handlmg and Storage Facihty for Boing and Pressurtzed Water Reacto s (Safety Guide 25) 1.2G Quality Group Classtricatiens and Standards for Water. Stea;n,

and Radioactive-Waste-Containing Components cf Nuclear Power Plants (For Ccmment) 1.28 Quality Assur ace Program Requirements (Design and Construction)

(For Comment) 1.32 Criteria for Safety-Relatad Electric Power Systems for Nuclear Power Plants 1.45 Reactor Coolant Pressure Roundary Leakage Detection Systems 1.53 Application of the Sing'e-Failure Criteriem to Nuclear Power Plart Protection S"3tems 1.58 Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel Oh f.\\ f-o

REGULATORY GUIDES.

i Category B i

1.61 Quality Assurance Requirements for the Design of Nuclear Power Plants 1.67 Installation of Overpressure Protection Devices 1,68 Initial Test Programs for Water-Cooled Reactor Power Plants 1.70 Standard Format and Centent of Safety Analysis Reports for Nuclear Power Plants 1.'75 Physical Independence of Electric Systems 1,79 Preoperational Testing of Emergency Core Cooling Systems for Pres-

. s' surized Water Reactors 1.80 Preoperational Testing of Instrument Air Systems 1.81 Shared Errergency and Chutdown Electric Systems for Multi-Unit Nuclear Power Plants 1.82 Sumps for Emergency Core Cooling and Contatnment Spray Systems 1.83 Inservice Inspection cf Pressurized Water Reactor Steam Generator Tubes 1.88 Couection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Record.

1.90 Inservice inspection of Prestressed Concrete Containmen: Structures with Grouted Tendons 1.93 Availability of Electric Pov.er Sources 1.9G Design of Ma:n Steam Isolation Valve I.eakage Ccatrol Systems for Bothng Water Rcactor Nuclear Power Plants 1.98 Assu:nptiuns Used for Evaluating the Potential Radiclogical Conse-quences of a Radioactive Offgas System Fatlure in a Buthng Water Reactor (Far Comment) 1.105 Instrument Setpoints 1.10G Thermal Overload Prota h Mr Electric Motors on Motor-Operated Valves 1.107 Quall'ications for Cement Grouting for Prestressing Tendons in Con-tainment Structures l.118 Periodic Testing of Flectric Power ind Protection Systems 1.120 Fire Protection Guidelines fcr Nuclear Pcwer Plants (For C mmer.)

1.121 Bases for Hugging Degraded PWil 5tcam G< nerator Tubes (For Commen t )

1.13G Material for Concrete Containments 1.142 Safety-itelated Concrete Structures fer Nuclear Power Plants (Other Than Reactor Vessels and Contatnments) (For Ccmment) d 'k 2 2

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REGULATCRY GUID_ES I

Catecury '.

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DIVISION 1 - POWER REACTORS

' DRAFT REGULATORY GUIDES SC 704-5 Functional Specification for Safety-Related Valve Assemblies in Nuclear Powe. Plants I

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DIVISION 1 REGULATORY Gl' IDES UNDER DEVELOPMENT POWER REACTORS Single-Failure Criteria for Light-Water Reactor Plants Fluid Systems Pressurized Water Reactor and Boiling Water Reactor Cuntainment Spray Design Criteria e

Design and Construction Deficiency Reportirg Requirements Lightning Protection for Nuclear Power Plants Applicaticr. cf Torque Switches in Motor Operated Valves Important to Safety Guidance for Content of Licensing Applications for Light-Water Reactor Reload Fuel Requirements for Quahtication Tests and Production Tests for Piping and Equipment Snutateers 6

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RECULATORY GUIDES Categorv B 2.6 Energency Planning for Research Reactors 4.2 Preparation of Environmental Reports for Nuclear Power Stations 4.8 Environmental Technical Specifications for Nuclear Power Plants 5.54 Standard Format and Content of Safeguards Contingency Plans for Nuclear Power Plants 8.8 I n fo rv z : ion Relevant to Ensuring tha t Occupational Radiction Expo:ure a t fluclear Power S +.ations will he as low as is Reasonably Achievable Alarming Pocket Dosimeters 7#(-)

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Under Development