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Category:Regulatory Guide
MONTHYEARML23263A9972024-02-0202 February 2024
Watermarked - DG-5072 - Rev 0 of RG 5.90 - Guidance for Alternative Physical Security Requirements for Small Modular Reactors and Non-Light-Water Reactors
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Watermarked - DG-5074 - Access Authorization - Econcurrence Version Clean (02-03-23)
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Watermarked DG-5073 - Fitness for Duty Program for Part 53 - 10-13-23
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Draft Regulatory Guide DG-1404, Revision 1 (RG 1.253 Rev 0) Guidance on Ticap for Non-LWRs
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DG-1374 RG 1.152 Rev 4 Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants
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DG-4027, Draft Regulatory Guide 4.2 Supplement 1, Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications, Revision 2
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
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Watermark for ACRS Fc Meeting RG 1.9 Rev 5
ML21006A3352021-04-0101 April 2021
DG 1381 for Rev 0 of RG 1.244 - Control of Heavy Loads for Nuclear Facilities
ML20168A8832021-04-0101 April 2021
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
ML20120A6292021-01-31031 January 2021
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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ASME Code Cases Not Approved for Use, Revision 7 (DG-1369)
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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)
ML21012A1972021-01-12012 January 2021
a Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion, RG 1.208, Revision 0
Regulatory Guide 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities2020-12-31031 December 2020
Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities
ML20183A4232020-12-31031 December 2020
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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Public Comment Resolutions on DG-1362 for RG 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities
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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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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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Draft Regulation Guide DG-1288: Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspections of Piping
ML20231A8562020-11-30030 November 2020
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)
ML20154K5842020-09-17017 September 2020
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
Regulatory Guide 1.2362020-07-30030 July 2020
Draft for ACRS Review
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Response to Comments for RG 1.236 for ACRS
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Memo to OCA - for Revision 1 of Regulatory Guide 8.39, Release of Patients Administered Radioactive Material
ML20099F0262020-04-0707 April 2020
Public Comment Resolution Table for DG 1341 (Regulatory Guide (RG) 1.188, Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses, Rev. 2
ML19206A4892020-02-0606 February 2020
Draft Regulatory Guide DG-1287, an Approach for Plant-Specific, risk-Informed Decisionmaking: Technical Specifications
ML19116A0772019-08-31031 August 2019
Draft Regulatory Guide DG-5040, Urine Specimen Collection and Test Results Review Under 10 CFR Part 26, Fitness for Duty Programs.
ML19203A0892019-07-31031 July 2019
Assessment of the Continued Adequacy of Revision 2 of Regulatory Guide 1.99 - Technical Letter Report
2024-02-02
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Revision O-R
U.S. NUCLEAR REGULATORY COMMISSION May 1977 REGULATORY GUIDE (This guide reissued OFFICE OF STANDARDS DEVELOPMENT
October 1977)
REGULATORY GUIDE 2.5 QUALITY ASSURANCE PROGRAM REQUIREMENTS FOR RESEARCH REACTORS
A. INTRODUCTION
C. REGULATORY POSITION
Paragraph (a)(7) of §50.34, "Contents of Applica The general requirements for establishing and ex tions: Technical Information." of 10 CFR Part 50. ecuting a quality assurance program for the design,
"Licensing of Production and Utilization Facilities." construction. testing, modification, and maintenance requires that each applicant for a construction permit of research reactors that are included in ANSI N402 to build a production or utilization facility include in 1976. "Quality Assurance Program Requirements for its preliminary safety analysis report a description of Research Reactors,"' provide an acceptable method the quality assurance program to be applied to the for compl~ing Aith the program requirements of 10
design and construction of the structures, systems. CtR ý,50.34.
and components of the facility. Paragraph (b)(6)(ii)
D. IMPLEMENTATION
of §50.34 requires that each applicant for a license to operate a facility include in the final safety analysis The purpose of this section is to provide informa report a description of the managerial and ad tion to applicants regarding the NRC staffs plans for ministrative controls to be used to assure safe opera using this regulatory guide.
tion. This guide describes a method acceptable to the NRC staff of complying with the Commission's Except in those cases in which the applicant regulations with regard to overall quality assurance proposes an acceptable alternative method for com program requirements for research reactors. plying with specified portions of the Commission's regulations. the method described herein will be used in the evaluation of submittals in connection with ap
.
B. DISCUSSION
plications for operating licenses, construction per mits, or proposed amendments thereto docketed after January 16, 1978, unless this guide is revised as a Work Group ANS-15.8 of Subcommittee ANS-15, result of suggestions from the public or additional Research Reactors, of the American Nuclear Society staff review.
Standards Committee has developed a standard that describes a quality assurance program for use in If an applicant wishes to use this regulatory guide research reactors. The standard was approved by the in developing submittals for applications docketed on American National Standards Committee N17, or before January 16, 1978, the pertinent portions of Research Reactors. It was subsequently approved the application will be evaluated on the basis of this and designated ANSI N402-1976 by the American guide.
National Standards Institute (ANSI) on August 19, ICopies may be obtained from the American Nuclear Society,
1976.
555 North Kensington Avenue, LaGrafige Park, Illinois 60525.
USNRC REGULATORY GUIDES Comments should be sent to the Secretary of the Commission, US. Nuclear Regu latory Commission, Washington, D.C. 20555, Attention: Docketing and Service Regulatory Guides are issued to describe and make available to the public methods Branch.
acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evaluating specific problems The guides are issued in the following ten broad divisions or postulated accidents, or to provide guidance to applicants. Regulatory Guides are not substitutes for regulations, and compliance with them is not required. 1. Power Reactors 6. Products Methods and solutions different from those set out in the guides will be accept- 2. Research and Test Reactors 7- Transportation able if they provide a basis for the findings requisite to the issuance or continuance 3. Fuels and Materials Facilities 8. Occupational Health of a permit or license by the Commission. 4. Environmental and Siting
9. Antitrust Review
5. Materials and Plant Protection 10. General Comments and suggestions for improvements in these guides are encouraged at all times, and guides will be revised, as appropriate, to accommodate commentsand to Requests for single copies of issued guides lwhich may be reproducedl or for place reflect new information or experience. However, the staff's consideration of com- ment on an automatic distribution list for single copies of future guides in specific ments received during the initial public comment period for this guide has resulted divisions should be made in writing to the US. Nuclear Regulatory Commission, in the determination that there is no need for a revision at this time. Washington, D.C. 20555. Attention: Director, Division of Document Control.
This guide is being reissued with the words
"For Comment" deleted. The staff's consideration of comments received during the initial public comment period has resulted in the determination that there is no need for a revision at this time.
Consequently, no changes have been made in the text of the guide.
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