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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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Z ~ .- r"~ , %- (U.S. NUCLEAR REGULATORY
COMMISSION
REGULATORY
Revision 1 April 1989 GUIDE OFFICE OF NUCLEAR REGULATORY
RESEARCH REGULATORY
GUIDE 3.45 (Task CE 802-5)NUCLEAR CRITICALITY
SAFETY FOR STEEL-PIPE
INTERSECTIONS
CONTAINING
AQUEOUS SOLUTIONS
OF FISSILE MATERIALS
A. INTRODUCTION
Section 70.22, "Contents of Applications," of 10 CFR Part 70, "Domestic Licensing of Special Nu-clear Material," requires that applications for a spe-cific license to own, acquire, deliver, receive, possess, use, or transfer special nuclear material contain pro-posed procedures to avoid accidental conditions of criticality.
This regulatory guide provides guidance for complying with this portion of the Commission's regu-lations by describing procedures acceptable to the NRC staff for the prevention of criticality accidents in the storage and processing of aqueous solutions of fis-sile materials in steel-pipe intersections.
Any information collection activities mentioned in this regulatory guide are contained as requirements in 10 CFR Part 70, which provides the regulatory ba-sis for this guide. The information collection require-ments in 10 CFR Part 70 have been cleared under OMB Clearance No. 3150-0009.
B. DISCUSSION
ANSI/ANS-8.9-1987, "Nuclear Criticality Safety Criteria for Steel-Pipe Intersections Containing Aque-ous Solutions of Fissile Material,"'
was prepared by Subcommittee
8, Fissionable Materials Outside Reac-tors, of the Standards Committee of the American Nuclear Society. ANSI/ANS 8.9-1987 was approved'Copies may be obtained from the American Nuclear Society, 555 N. Kensington Avenue, La Grange Park, IL 60525.by the American National Standards Institute (ANSI)on April 3, 1987.ANSI/ANS-8.9-1987 provides specifications for pipe intersections containing homogeneous aqueous solutions of fissile materials.
All dimensions are inter-preted as nominal values of schedule 10 or heavier standard steel pipe. Only single columns with inter-sections are considered in the standard.
For multiple columns or columns in the vicinity of other fissile ma-terials and the influence of environmental factors, the standard requires that experimental data or validated computational techniques be used to determine the safe configuration.
Criteria and data provided are based on criticality experiments and validated calcu-lations that are generally applicable to homogeneous aqueous solutions of fissile materials.
Specific infor-mation is included on fissile solutions containing ura-nium enriched in the 2 35U or 2 3 3 U isotope or pluto-nium and on uranium solutions having a 2 3U content not exceeding
5 weight-percent of the total uranium.C. REGULATORY
POSITION The nuclear criticality safety practices and guid-ance for calculating safe steel-pipe intersections for aqueous solutions of fissile materials contained in ANSI/ANS-8.9-1987 provide procedures generally acceptable to the NRC staff for the prevention of criticality accidents in the storage and processing of aqueous solutions of fissile materials.
USNRC REGUIATORY
GUIDES Regulatory Guides are Issued to describe and make available to the pub-lic methods 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 or postulated accidents, or to pro-vide guidance to 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 will be acceptable if they provide a basis for the findings requisite to the Issuance or continu-ance of a permit or license by the Commission.
This guide was issued after consideration of comments received from the public. Comments and suggestions for improvements in these guides are encouraged at all times, and guides will be revised, as ap-propriate, to accommodate comments and to reflect new information or experience.
Written comments may be submitted to the Regulatory Publications Branch, DFIPS, ARM, U.S. Nuclear Regulatory Commission, Washing-ton, DC 20555.The guides are Issued in the following ten broad divisions:
1. Power Reactors 2. Research and Test Reactors 3. Fuels and Materials Facilities
4. Environmental and Siting 5. Materials and Plant Protection
6. Products
7. Transportation
8. Occupational Health 9. Antitrust and Financial Review 10. General Copies of issued guides may be purchased from the Government Printing Office at the current GPO price. Information on current GPO prices may be obtained by contacting the Superintendent of Documents, U.S.Government Printing Office, Post Office Box 37082, Washington, DC 20013-70B2, telephone
(202)275-2060
or (202)275-2171.
Issued guides may also be purchased from the National Technical Infor-mation Service on a standing order basis. Details on this service may be obtained by writing NTIS, 5285 Port Royal Road, Springfield, VA 22161.
D. IMPLEMENTATION
The purpose of this section is to provide informa-tion to applicants regarding the NRC staff's plan for using this regulatory guide.These methods reflect the latest general NRC ap-proach to criticality safety in the storage and process-ing of aqueous solutions of fissile materials in steel-pipe intersections.
Therefore, except in those cases in which the applicant proposes an acceptable alterna-tive method for complying with the specified portions of the Commission's regulations, the method de-scribed here will be used in the evaluation of submit-tals for license applications submitted pursuant to 10 CFR Part 70.3.45-2 VALUE/IMPACT
STATEMENT A draft value/impact statement was published with the proposed Revision 1 to Regulatory Guide 3.45 (Task CE 802-5) when the draft guide was pub-lished for public comment in May 1988. No changes were necessary, so a separate value/impact statement for the final guide has not been prepared.
A copy of the draft value/impact statement is available for in-spection and copying for a fee at the Commission's Public Document Room at 2120 L Street NW., Wash-ington, DC, under Task CE 802-5.3.45-3 UNITED STATES NUCLEAR REGULATORY
COMMISSION
WASHINGTON, D.C. 20555 FIRST CLASS MAIL POSTAGE b FEES PAID USNRC PERMIT No. G,67 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300