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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 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. 2024-04-30
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Z ~ .- r"~ , %- (U.S. NUCLEAR REGULATORY COMMISSIONREGULATORYRevision 1April 1989GUIDEOFFICE OF NUCLEAR REGULATORY RESEARCHREGULATORY GUIDE 3.45(Task CE 802-5)NUCLEAR CRITICALITY SAFETY FOR STEEL-PIPE INTERSECTIONS CONTAININGAQUEOUS SOLUTIONS OF FISSILE MATERIALS
A. INTRODUCTION
Section 70.22, "Contents of Applications," of10 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 ofcriticality. This regulatory guide provides guidance forcomplying with this portion of the Commission's regu-lations by describing procedures acceptable to theNRC staff for the prevention of criticality accidents inthe storage and processing of aqueous solutions of fis-sile materials in steel-pipe intersections.Any information collection activities mentionedin this regulatory guide are contained as requirementsin 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 underOMB Clearance No. 3150-0009.
B. DISCUSSION
ANSI/ANS-8.9-1987, "Nuclear Criticality SafetyCriteria for Steel-Pipe Intersections Containing Aque-ous Solutions of Fissile Material,"' was prepared bySubcommittee 8, Fissionable Materials Outside Reac-tors, of the Standards Committee of the AmericanNuclear 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 forpipe intersections containing homogeneous aqueoussolutions of fissile materials. All dimensions are inter-preted as nominal values of schedule 10 or heavierstandard steel pipe. Only single columns with inter-sections are considered in the standard. For multiplecolumns or columns in the vicinity of other fissile ma-terials and the influence of environmental factors, thestandard requires that experimental data or validatedcomputational techniques be used to determine thesafe configuration. Criteria and data provided arebased on criticality experiments and validated calcu-lations that are generally applicable to homogeneousaqueous solutions of fissile materials. Specific infor-mation is included on fissile solutions containing ura-nium enriched in the 235U or 233U isotope or pluto-nium and on uranium solutions having a 23U contentnot 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 foraqueous solutions of fissile materials contained inANSI/ANS-8.9-1987 provide procedures generallyacceptable to the NRC staff for the prevention ofcriticality accidents in the storage and processing ofaqueous solutions of fissile materials.USNRC REGUIATORY GUIDESRegulatory Guides are Issued to describe and make available to the pub-lic methods acceptable to the NRC staff of implementing specific partsof the Commission's regulations, to delineate techniques used by thestaff in evaluating specific problems or postulated accidents, or to pro-vide guidance to applicants. Regulatory Guides are not substitutes forregulations, and compliance with them is not required. Methods andsolutions different from those set out in the guides will be acceptable ifthey 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 fromthe public. Comments and suggestions for improvements in theseguides are encouraged at all times, and guides will be revised, as ap-propriate, to accommodate comments and to reflect new information orexperience.Written comments may be submitted to the Regulatory PublicationsBranch, DFIPS, ARM, U.S. Nuclear Regulatory Commission, Washing-ton, DC 20555.The guides are Issued in the following ten broad divisions:1. Power Reactors2. Research and Test Reactors3. Fuels and Materials Facilities4. Environmental and Siting5. Materials and Plant Protection6. Products7. Transportation8. Occupational Health9. Antitrust and Financial Review10. GeneralCopies of issued guides may be purchased from the Government PrintingOffice at the current GPO price. Information on current GPO prices maybe obtained by contacting the Superintendent of Documents, U.S.Government Printing Office, Post Office Box 37082, Washington, DC20013-70B2, 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 beobtained by writing NTIS, 5285 Port Royal Road, Springfield, VA 2216
D. IMPLEMENTATION
The purpose of this section is to provide informa-tion to applicants regarding the NRC staff's plan forusing 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 inwhich the applicant proposes an acceptable alterna-tive method for complying with the specified portionsof the Commission's regulations, the method de-scribed here will be used in the evaluation of submit-tals for license applications submitted pursuant to10 CFR Part 70.3.45-2 VALUE/IMPACT STATEMENTA draft value/impact statement was publishedwith the proposed Revision 1 to Regulatory Guide3.45 (Task CE 802-5) when the draft guide was pub-lished for public comment in May 1988. No changeswere necessary, so a separate value/impact statementfor the final guide has not been prepared. A copy ofthe draft value/impact statement is available for in-spection and copying for a fee at the Commission'sPublic Document Room at 2120 L Street NW., Wash-ington, DC, under Task CE 802-5.3.45-3 UNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, D.C. 20555FIRST CLASS MAILPOSTAGE b FEES PAIDUSNRCPERMIT No. G,67OFFICIAL BUSINESSPENALTY FOR PRIVATE USE, $300