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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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U.S. ATOMIC ENERGY COMMISSION
REGULATORY
GL DIRECTORATE
OF REGULATORY
STANDARDS
REGULATORY
GUIDE 5.5 STANDARD METHODS FOR CHEMICAL, MASS SPECTROMETRIC.
AND SPECTROCHEMICAL
ANALYSIS OF NUCLEAR-GRADE
URANIUM DIOXIDE POWDERS AND PELLETS
A. INTRODUCTION
Paragraph
70.22(b) of 10 CFR Part 70, "Special Nuclear Material," requires an applicant for a license to possess certain quantities of speciad nuclear material in an unsealed form to describe, among other things, his procedures for control of and accounting for such material.
This guide identifies acceptable methods for chemical, isotopic, and impurity analysis which an applicant may specify as part of his procedures for accounting for special nuclear material.
B. DISCUSSION
Committee C-26 on Fuel, Control, and Moderator Materials for Nuclear Reactor Applications of the American Society for Testing and Materials (ASTM) has developed a standard containing some methods for the analytical chemical analysis of nuclear-grade uranium dioxide powders and pellets. These methods cover the analysis for uranium content by a titrimetric and gravimetric method to be used for uranium dioxide of varying impurity levels and sample sizes, for 2101r3 IDE oxygen-uranium atomic ratio to verify stoichiometry, for verification of isotopic uranium composition, and for various impurities such as carbbn, chloride, fluoride, moisture, nitrogen, sulfur, and trace elements.
This standard was approved by the ASTM on March 3, 1972, and published in May 1972 with the designation C 696-72.' C. REGULATORY
POSITION The analytical methods for the measurement of nuclear-grade uranium dioxide powders and pellets contained in ASTM Standard C 696-72, "Standard Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets," are generally acceptable and provide an adequate basis for the assay, isotopic measurement, and impurity analysis of nuclear-grade uranium dioxide powders and pellets.
'Copies my be obtained from the Amuerean Socity for Testing and Materials, 1916 Race St., Philadelphia.
Pa. 1910
3. U EC REGULATORY
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In Onom mifdt m ~wwsuread aW haM d be sent to go @alaoSine trw Comrmnsmen's regulutions.
to dWia udmchniclua maued by the eta" in of film Cn- I ', o. U.S. Atomic Energv Comndmei.
Waduls .D.C. 20M4. wi ptll fIn M c p-oblawn or ostulted oneWesd .or to wopwid gumbnin "" Attontion:
Chiel. Public Promiinp Stoa. impns. Raillv Guid as not -akuIte for ralleliefs and tonpiim wlk "tem ir ni t rnquired Methods aMd tolitom sff met frm them f at gut in The pT1 we kmm In the lfoll, 0 tSn broa dWeaons: sh @e well km acoolibbe if tlay Would@ a basi for tm findings requniste to the .isuarm or ominuanm of a pmrm* or kc~ by thw CommissIon.
1. Pow Reactors 6. Prouct 2. Resasrch and Tes Rheactors
7. Trausportation
3 Fues mci Melteria Facilities a. Occupo:stonl t"em Pubalsted g6&s "it be rmd dl kr riod alro , y. a ippropriate, to accuol u mts 4. Enwironiental end Siting 9. Antitruat wsur comnenints o-d to reflect now or esnvarm. S. sad Plant Prtecllon
10. General