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Category:Regulatory Guide
MONTHYEARML24038A3102024-04-30030 April 2024
Rev 1 Dedication of Commercial-Grade Items for Use in Nuclear Power Plants
ML23263A9972024-02-0202 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
ML23286A2512024-02-0202 February 2024
Watermarked DG-5073 - Fitness for Duty Program for Part 53 - 10-13-23
ML23286A2682024-02-0202 February 2024
Watermarked - DG-5074 - Access Authorization - Econcurrence Version Clean (02-03-23)
ML23286A2862024-02-0202 February 2024
Watermarked - DG-5078, Fatigue Management for Nuclear Power Plant Personnel -10-13-23
ML23286A2822024-02-0202 February 2024
Watermarked - DG-5076 - Physical Protection for Part 53 - 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
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
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
ML21006A3372021-04-0101 April 2021
Regulatory Analysis - DG 1381 - Control of Heavy Loads for Nuclear Facilities
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
ML21083A2892021-02-28028 February 2021
Draft for Acrs Review
ML21048A4482021-02-17017 February 2021
Rev. 2
ML21011A2312021-01-31031 January 2021
Rev 4 (Draft for ACRS Fc Review on 2-3-21)
ML20120A6312021-01-31031 January 2021
Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 20, (DG-1367)
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)
ML21012A1972021-01-12012 January 2021
a Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion, RG 1.208, Revision 0
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
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
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
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
ML20282A2982020-12-0404 December 2020
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
ML20231A8352020-11-30030 November 2020
Draft Regulatory Guide DG-1359, Fire Protection for Nuclear Power Plants
ML20231A8562020-11-30030 November 2020
Draft Regulatory Guide DG-1360, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water 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.
2024-04-30
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3/16/73 U.S. ATOMIC ENERGY COMMISSION
REGULATORY GUI DE
,-"
- DIRECTORATE OF REGULATORY STANDARDS
REGULATORY GUIDE 1.41 PREOPERATIONAL TESTING OF REDUNDANT ON-SITE ELECTRIC POWER
SYSTEMS TO VERIFY PROPER LOAD GROUP ASSIGNMENTS
A. INTRODUCTION
in one load group from causing the loss of equipment in another load group." The independence among General Design Criterion 1, "Quality Standards aiAd redundant on-site power sources and their load groups Records," of Appendix A to 10 CFR Part 50, "Genei .al should be such that the successful operation of any Desigu' Criteria for Nuclear Power Plants," requires th at power source and its load group is in no way affected by structires, systems, and components important to safety the partial or complete failure of any other power source be tested to quality standards commensurate with t]he and its load group.
importance of the safety functions to be performe d.
Criterion Xl, "Test Control," of Appendix B to 10 CF'R Since the reliability of an on-site power system of Part 50, "Quality Assurance Criteria for Nuclear Pow er the kind discussed in this guide is predicated on the Plants and Fuel Reprocessing Plants," requires that a te.st existence of this independence, a suitable preoperational program be established to assure that all testing requiri-d test to detect any lack of independence should be to demonstrate that structures, systems, ajid performed. As a minimum, a suitable test should assure components will perform satisfactorily in service is that each redundant on-site power source and its load identified and performed. For on-site emergency pow er group can function without any dependence upon any systems designed in accordance with Regulatory Guid es other redundant load group or portion thereof.
1.6 and 1.32 (Safety Guides 6 and 32) this gui4de describes an acceptable method of complying with tlhe Commission's regulations with respect to verifying tl lie
C. REGULATORY POSITION
proper assignments of redundant load groups to tihe related on-site power sources. The Advisory Committ,De As part of the initial preoperational testing program, on Reactor Safeguards has been consulted concerniinig and also after major modifications or repairs to a this guide and has concurred in the Regulatory positio n. facility, those on-site electric power systems designed in accordance with Regulatory Guides 1.6 and 1.32 (Safety
B. DISCUSSION
Guides 6 and 32) should be tested as follows to verify the existence of independence among redundant on-site An on-site electric power system designed in power sources and their load groups.
accordance with Regulatory Guides 1.6 and 1.32 (Safeity 1. The plant electric power distribution system, Guides 6 and 32) will consist of redundant pow er not necessarily including the switchyard and the startup sources and load groups that are independent of eac:h and auxiliary transformers, should be isolated from the other. Such a design will conform to the provisions 4of off-site transmission network. Preferably, this isolation Section 5.2.2(5) of IEEE Std 308-1971.' Secticin should be effected by direct actuation of the
5.2.2(5) states: "Auxiliary devices that are required I.0 undervoltage-sensing relays within the on-site system.
operate dependent equipment shall be supplied from a 2. Under the conditions of C.1. above, the on-site related bus section to prevent the loss of electric powier electric power system should be functionally tested successively in the various possible combinations of I IEEE Std 308-1971, "Criteria for Class IE Electric Systeins power sources and load groups with all d-c and on-site for Nuclear Power Generating Stations." Copies may be obtain ed a-c power sources for one load group at a time from the Institute of Electrical and Electronics Enginee rs, completely disconnected. Each test should include United Engineering Center, 345 East 47th Street, New Yoi *k, injection of simulated accident signals, startup of the N.Y. 10017.
USAEC REGULATORY GUIDES Copies of published guides nmy be obtained by request indicating the divisions desired to the US. Atomic Energy Commission, Washington, D.C. 20645, Regulatory Guides ar issued to describe and make available to the public Attention: Director of Regulatory Stendards. Comments and sUggestions for methods amccptable to the AEC Regulatory staff of implementing specific parts of Improvements in thee guides "a encouraged end should be sent to the Secretary the Commission's regulations, to delineate techniques used by the staff in of the Commission. US. Atomic Energy Commission, Washington, D.C. 20645,
"evluating spedfic 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 are issued in the following tan broad divisions:
the guides will be acceptable if they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the Commission. 1. Power Reactors
6. Products
2. Research and Test Reactors
7. Transportation
3. Fuels and Materials Facilities 8. Occupalional Health Pullo*ed guides will be revised periodically, asappropriate, to accommodate 4. Environmental and Siting 9. Antitrust Review coronst and to reflect new information or experience. 5. Materials and Plant Protection 1
0. General
on-site power source(s) and load group(s) under test, result from improper assignment of loads, e.g., the lack sequencing of loads, and the functional performance of of forced cooling of a vital device.
the loads. Each test should be of sufficient duration to 3. During each test, the d-c and on-site a-c buses achieve stable operating conditions and thus permit the and related loads not under test should be monitored to onset and detection of adverse conditions which could verify absence of voltage at these buses and loads.
1.41-2