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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
ML23286A2682024-02-0202 February 2024
Watermarked - DG-5074 - Access Authorization - Econcurrence Version Clean (02-03-23)
ML23286A2822024-02-0202 February 2024
Watermarked - DG-5076 - Physical Protection for Part 53 - 10-13-23
ML23286A2512024-02-0202 February 2024
Watermarked DG-5073 - Fitness for Duty Program for Part 53 - 10-13-23
ML23286A2862024-02-0202 February 2024
Watermarked - DG-5078, Fatigue Management for Nuclear Power Plant Personnel -10-13-23
ML23286A2782024-02-0202 February 2024
Watermarked - DG-5075 - Cyber Security 10-13-23
ML23194A1942023-08-31031 August 2023
Draft Regulatory Guide DG-1404, Revision 1 (RG 1.253 Rev 0) Guidance on Ticap for Non-LWRs
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
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
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
Rev 5 Final Watermarked for ACRS
ML21092A1512021-05-0505 May 2021
Rev. 4 ACRS Version
ML21092A1342021-05-0505 May 2021
Rev. 2 ACRS Version
ML21181A2492021-04-30030 April 2021
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
ML21006A3372021-04-0101 April 2021
Regulatory Analysis - DG 1381 - Control of Heavy Loads for Nuclear Facilities
ML21083A2892021-02-28028 February 2021
Draft for Acrs Review
ML21048A4482021-02-17017 February 2021
Rev. 2
ML20120A6292021-01-31031 January 2021
Operation and Maintenance Code Case Acceptability, ASME OM Code, Revision 4, (DG-1368)
ML20120A6332021-01-31031 January 2021
Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, Revision 39, (DG-1366)
ML20120A6272021-01-31031 January 2021
ASME Code Cases Not Approved for Use, Revision 7 (DG-1369)
ML20120A6312021-01-31031 January 2021
Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 20, (DG-1367)
ML21011A2312021-01-31031 January 2021
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
ML20238B8732020-12-29029 December 2020
Public Comment Resolutions on DG-1362 for RG 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities
ML20282A2982020-12-0404 December 2020
DG-3055, Rev 0, Regulatory Guide (RG) 3.76, Implementation of Aging Management Requirements for Spent Fuel Storage Renewals
ML20282A2992020-12-0404 December 2020
Regulatory Analysis for DG-3055, Rev 0, Regulatory Guide (RG) 3.76, Implementation of Aging Management Requirements for Spent Fuel Storage Renewals
ML20210M0472020-12-0101 December 2020
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
ML20231A8352020-11-30030 November 2020
Draft Regulatory Guide DG-1359, Fire Protection for Nuclear Power Plants
ML20307A0462020-11-0202 November 2020
Draft for ACRS Public Meeting, RG 1.200, R3, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities
ML20210M0442020-10-28028 October 2020
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
ML20182A7882020-08-31031 August 2020
DG 1373 for RG 1.240 - Fresh and Spent Fuel Pool Criticality Analyses
ML20055G8232020-08-0707 August 2020
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
ML20119A6142020-04-28028 April 2020
Response to Comments for RG 1.236 for ACRS
ML20105A4672020-04-14014 April 2020
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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Text
Revision I
+,* . E*0*'March 1981 0,tof U.S. NUCLEAR REGULATORY COMMISSION REGULATORY GUIDE OFFICE OF STANDARDS DEVELOPMENT REGULATORY GUIDE 8.5 CRITICALITY AND OTHER INTERIOR EVACUATION SIGNALS A. INTRODUCTION conception, installation, and operation. A description of typical characteristics for an evacuation signal and the Section 70.24, "Criticality Accident Requirements," of signal generator that were included as requirements in the 10 CFR Part 70, "Domestic Licensing of Special Nuclear body of USASI N2.3-1967 have been placed in Appendix B Material." requires criticality detection and alarm systems to ANSI/ANS N2.3-1979 simply asan example of compliance in any area containing special nuclear material when the with the standard.
licensee is authorized to possess such special nuclear mate rial in excess of certain specified amounts. This guide defines the characteristics of an audible signal acceptable to the C. REGULATORY POSITION NRC staff for use where prompt, complete evacuation is required to prevent serious injury from radiation exposure. The characteristics of an immediate evacuation signal described in ANSI/ANS N2.3-1979, "Immediate Evacua B. DISCUSSION tion Signal for Use in Industrial Installations," are gen erally acceptable to the NRC staff for use wherever such ANSI/ANS N2.3-1979,1 "Immediate Evacuation Signal a system may be needed or required except that the mini for Use in Industrial Installations," which is a revision of mum duration of the signal should be sufficient to ensure USASI N2.3-1967, was approved by the American National evacuation and permit implementation of access control.
Standards Institute (ANSI) on September 13, 1979. The standard defines the characteristics of an immediate evacua tion signal system. D. IMPLEMENTATION Whereas USASI N2.3-1 967 specified the characteristics of The purpose of this section is to provide information to a unique audible signal for evacuation of the area potentially applicants and licensees regarding the NRC staff's plan for affected by the consequences of a nuclear criticality acci using this regulatory guide. This guide reflects practices dent. ANSI/ANS N 2.3-1979 presents the recognized desirable currently acceptable to the NRC staff. Except in those characteristics of signal systems and good practices in their cases in which the applicant or licensee proposes accept able alternative practices or methods for complying with specified portions of the Commission's regulations, the The substantial number of changes in this revision has made it practices or methods described herein will be used as a impractical to indicate them with lines in the margin.
basis for evaluating applications for licenses to possess ICopies may be obtained from the American Nuclear Society. special nuclear material in quantities subject to §70.24 5SS North Kensington Avenue, LaGrange Park, Illinois 60525. of 10 CFR Part 70.
USNRC REGULATORY GUIDES Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Regulatory Guides are issued to describe and make available to the Attention: Docketing and Service Branch.
public methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate tech The guides are issued in the following ten broad divisions:
niques used by the staff in evaluating specific problems or postu lated accidents, or to provide guidance to applicants. Regulatory 1. Power Reactors 6. Products Guides are not substitutes for regulations, and cor-pliance with 2. Research and Test Reactors 7. Transportation them is not required. Methods and solutions different from those set 3. Fuels and Materials Facilities 8. Occupational Hearth out in the guides will be acceptable if they provide a basis for the 4. Environmental and Siting 9. Antitrust and Financial Review findings requisite to the issuance or continuance of a permit or 5. Materials and Plant Protection 10. General license by the Commission.
Copies of issued guides may be purchased at the current Government Comments and suggestions for improvements in these guides are Printing Office price. A subscription service for future guides in spe encouraged at all times, and guides will be revised, as approp:iate, cific divisions is available through the Government Printing Office.
to accommodate comments and to reflect new information or Information on the subscription service and current GPO prices may experience. This guide was revised as a result of substantive com be obtained by writing the U.S. Nuclear Regulatory Commission, ments received from the public and additional staff review. Washington, D.C. 20555, Attention: Publications Sales Manager.
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