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Category:Regulatory Guide
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Rev 1 Dedication of Commercial-Grade Items for Use in Nuclear Power Plants
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Watermarked DG-5073 - Fitness for Duty Program for Part 53 - 10-13-23
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ML23194A1942023-08-31031 August 2023
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ML22165A0722023-02-28028 February 2023
DG-4027, Draft Regulatory Guide 4.2 Supplement 1, Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications, Revision 2
ML23012A2422023-02-28028 February 2023
DG-1374 RG 1.152 Rev 4 Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants
ML23018A2932023-02-16016 February 2023
Draft Regulatory Guide DG-1418 (RG 1.212 Rev 2), Sizing Large Lead-Acid Storage Batteries. (ACRS Copy)
Regulatory Guide 5.892022-11-0101 November 2022
Rev.0, Fitness-for-Duty Programs for Commercial Power Reactor and Category I Special Nuclear Material Licensees
ML22067A0142022-03-31031 March 2022
Rev 3 ACRS Spent Fuel Heat Generation in an ISFSI
ML22048B8222022-02-18018 February 2022
DG-1389 (ACRS Version for 3-16-22 Meeting) - Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors
ML22040A0822021-10-30030 October 2021
Document to Support ACRS Subcommittee Meeting - Redline RG 1.57, Rev 3, Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components
ML21167A3512021-06-0101 June 2021
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Rev. 4 ACRS Version
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Rev. 2 ACRS Version
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Watermark for ACRS Fc Meeting RG 1.9 Rev 5
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DG 1381 for Rev 0 of RG 1.244 - Control of Heavy Loads for Nuclear Facilities
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DG-1371, Proposed Rev 6 of RG 1.26, Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants
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Regulatory Analysis - DG 1381 - Control of Heavy Loads for Nuclear Facilities
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Draft for Acrs Review
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Rev. 2
ML20120A6312021-01-31031 January 2021
Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 20, (DG-1367)
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Rev 4 (Draft for ACRS Fc Review on 2-3-21)
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ASME Code Cases Not Approved for Use, Revision 7 (DG-1369)
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Operation and Maintenance Code Case Acceptability, ASME OM Code, Revision 4, (DG-1368)
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Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, Revision 39, (DG-1366)
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A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion, RG 1.208, Revision 0
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Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities
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Draft Regulatory Guide DG-1361 (Proposed Rev. 2 to Reg. Guide 1.89), Environmental Qualification of Certain Electrical Equipment Important to Safety for Nuclear Power Plants
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Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities
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Public Comment Resolutions on DG-1362 for RG 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities
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Regulatory Analysis for DG-3055, Rev 0, Regulatory Guide (RG) 3.76, Implementation of Aging Management Requirements for Spent Fuel Storage Renewals
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DG-3055, Rev 0, Regulatory Guide (RG) 3.76, Implementation of Aging Management Requirements for Spent Fuel Storage Renewals
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Draft Regulation Guide DG-1288: Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspections of Piping
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Draft Regulatory Guide DG-1360, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants
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Draft Regulatory Guide DG-1359, Fire Protection for Nuclear Power Plants
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Draft for ACRS Public Meeting, RG 1.200, R3, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities
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Regulatory Analysis: Draft Regulatory Guide DG-1288 - an Approach for Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspection of Piping (Proposed Revision 2 of Regulatory Guide 1.178, Dated September 2003)
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Results of Periodic Review of Regulatory Guide (RG) 1.78
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DG 1373 for RG 1.240 - Fresh and Spent Fuel Pool Criticality Analyses
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DG 1363 for Proposed Rev 4 to Regulatory Guide (RG) 1.105 - Setpoints for Safety-Related Instrumentation
Regulatory Guide 3.152020-07-31031 July 2020
Regulatory Guide 3.15. Rev 2, Standard Format and Content of License Applications for Receipt and Storage of Unirradiated Power Reactor Fuel and Associated Radioactive Material at a Nuclear Power Plant
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Reg Guide 7.4 New Reg Analysis-Leakage Tests on Package for Shipment of Radioactive Material
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Regulatory Guide (RG) 1.188, Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses. Revision 2
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Response to Comments for RG 1.236 for ACRS
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2024-04-30
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June 1973 U.S. ATOMIC ENERGY COMMISSION
N REGULATORYDIRECTORATE OF REGULATORY STANDARDS
GUIIDE
REGULATORY GUIDE 1.54 QUALITY ASSURANCE REQUIREMENTS FOR PROTECTIVE COATINGS
APPLIED TO WATER-COOLED NUCLEAR POWER PLANTS
A. INTRODUCTION
Coatings Applied to Nuclear Facilities,"' for protective coatings applied to ferritic steels, aluminum, stainless Appendix B to 10 CFR Part 50, "Quality Assurance steel, zinc-coated (galvanized) steel, concrete, or masonry Criteria for Nuclear Power Plants and Fuel Reprocessing surfaces of water-cooled nuclear power plants are Plants," establishes overall quality assurance program generally acceptable and provide an adequate basis for requirements for the design, fabrication, construction, complying with the pertinent quality assurance and operation of safety-related nuclear power plant requirements of Appendix B to 10 CFR Part 50 subject structures, systems, and components. This guide to the following:
describes an acceptable method of complying with the Commission's quality assurance requirements with 1. ANSI N101.4-1972 should be used in conjunction regard to protective coatings applied to ferritic steels, with ANSI N45.2-1971, "Quality Assurance Program aluminum, stainless steel, zinc-coated (galvanized) steel, Requirements for Nuclear Power Plants." 2 concrete, or 'Masonry surfaces of water-cooled nuclear power plants. The Advisory Committee on Reactor 2. Subdivision 2.7 of ANSI N101.4-1972 states that Safeguards has been consulted concerning this guide and when references are made to other standards, these has concurred in the regulatory position. references shall imply the most recent or current editions of the referenced standard
s. The specific
B. DISCUSSION
applicability or acceptability of referenced standards will be covered separately in other regulatory guides, where Subcommittee N101.5.7 of the American National appropriate.
Standards Institute (ANSI) Standards Committee NIO1, Atomic Industry Facility Design, Construction, and 3. Subdivision 1.1.2 of ANSI N101.4-1972 states that Operation Criteria, under the sponsorship of the quality assurance, as covered by this standard, comprises American Institute of Chemical-Engineers, has developed all those planned and systematic actions necessary to a standard which includes quality assurance provide specified documentation and adequate requirements for protective coatings applied to ferritic confidence that shop or field coating work for nuclear steels, aluminum, stainless steel, zinc-coated (galvanized) facilities will perform satisfactorily in service. This steel, concrete, or masonry surfaces of nuclear facilities. statement should not be interpreted as implying that the This standard was approved by the American National end product of quality assurance actions is the Standards Committee N1O0 and its Secretariat. It was production of specified documentation. The term subsequently approved and designated N101.4-1972 by the American National Standards Institute on November 28, 1972. 'Copies may be obtained from the American Institute of Chemical Engineers, 345 East 47th Street, New York, N.Y.
C. REGULATORY POSITION
10017.
'Copies may be obtained from the American Society of The requirements and guidelines included in ANSI Mechanical Engineers, United Engineering Center, 345 East 47th N 10 1.4-1972, "Quality Assurance for Protective Street, New York, N.Y. 10017.
USAEC REGULATORY GUIDES Copies of published guides may be obtained by request Indicating the divisions desired to the US. Atomic Energy Commission. Washington, D.C. 20545, Regulatory Guides are issued to describe and make available to the public Attention: Director of Regulatory Standards. Comments end suggestions for methods acceptable to the AEC Regulatory staff of implementing specific parts of Improvements In these guides re encouraged and should be sent to the Secretary the Cornmmssion's regulations, to delineate techniques used by the staff in of the Commission. U.S. Atomic Energy Commission. Washington, D.C. 20545, evluating specific problems or postulated accidents, or to provide guidance to Attention: Chief, Public Proceedings Staff.
applicants. Regulatory Guides are not substitutes for regulations and compliance with them is not required. Methods and solutions different from those set out in The guides ae issued in the following ten broad divisions:
the guides will be acceptable if they provide a besis for the findings requisite to the issuance or continuance of a permit or license by the Commission. 1. Power Reactors
6. Products
7. Research and Test Reactors
7. Transportation
3. Fuels arid Materials Facilities &. Occupational Health Published guides will be revised periodically, asappropriate, to accommodate 4. Environmental and Siting 9. Antitrust Review comments and to reflect new information or experience. 5. Materials and Plant Protection 1
0. General
"quality assurance" as used in ANSI N1OI.4-1972 materials used with stainless steel should not be should be considered to comprise all those planned and compounded from or treated with chemical compounds systematic actions necessary to provide adequate containing elements that could contribute to corrosion, confidence that shop or field coating work for nuclear intergranular cracking, or stress corrosion cracking.
facilities will perform satisfactorily in service. In this Examples of such chemical compounds are those connection it is emphasized that records and documents containing chlorides, fluorides, lead, zinc, copper, sulfur, listed in Subdivisions 7.4 through 7.8, and included in or mercury where such elements are leachable or where the standard, are suggested forms only. Alternate they could be released by breakdown of the chemical documentation consistent with the requirements of compounds under expected environmental conditions Appendix B to 10 CFR Part 50 is also considered (e.g., by radiation). This limitation is not intended to acceptable. prohibit the use of trichlorotrifluoroethane which meets the requirements of Military Specification
4. Sections 3 and 4 of ANSI N101.4-1972 delineate MiL-C-81302b for cleaning or degreasing of austenitic quality assurance requirements for coating materials and stainless steel provided adequate removal is assured prior surface preparation of substrates. Coatings and, cleaning to painting.
1.54-2