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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)
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Watermarked - DG-5076 - Physical Protection for Part 53 - 10-13-23
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Watermarked DG-5073 - Fitness for Duty Program for Part 53 - 10-13-23
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Watermarked - DG-5078, Fatigue Management for Nuclear Power Plant Personnel -10-13-23
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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
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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
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Public Comment Resolutions on DG-1362 for RG 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities
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DG-3055, Rev 0, Regulatory Guide (RG) 3.76, Implementation of Aging Management Requirements for Spent Fuel Storage Renewals
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Regulatory Analysis for DG-3055, Rev 0, Regulatory Guide (RG) 3.76, Implementation of Aging Management Requirements for Spent Fuel Storage Renewals
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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
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Draft Regulatory Guide DG-1359, Fire Protection for Nuclear Power Plants
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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
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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
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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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12/20/72 U.S. ATOMIC ENERGY COMMISSION
REGULATORY
DIRECTORATE OF REGULATORY STANDARDS
GUIDE
REGULATORY GUIDE 5.1 SERIAL NUMBERING OF FUEL ASSEMBLIES FOR LIGHT-WATER-COOLED
NUCLEAR POWER REACTORS
A. INTRODUCTION
reprocessing in that fuel assemblies can be readily identified according to origin and irradiation history, Part 70 of the Atomic Energy Commission's thus avoiding confusion in formation of dissolver regulations requires that certain licensees establish and batches.
maintain written material control and accounting procedures which are sufficient to enable the licensee to The Fuel Assembly Identification Working Group of account for the special nuclear material (SNM) in his Subcommittee ANS-13, Fuel Assembly Criteria, has possession. In the case of SNM contained in fuel developed a standard (ANS 13.8) for fuel assembly assemblies, a system of control based on unique item identification. This standard was approved by the identification of each fuel assembly is desirable to American National Standards Institute as N18.3-1972!
achieve an acceptable level of accountability control. on May 10, 1972.
This guide describes an acceptable numbering method for item identification of fuel assemblies for Some fabricators purposely manufacture fuel light-water-cooled nuclear power reactors. assemblies that can be dismantled without any metal-cutting operation. This design feature allows
B. DISCUSSION
relatively easy substitution of fuel rods, but complicates the verification of discrete power reactor fuel items.
Power reactor fuel is relatively inaccessible while at a reactor facility. The SNM itself is securely contained within the fuel cladding. Accurate quantitative
C. REGULATORY POSITION
measurements of the SNM content of the fuel assemblies are exceedingly difficult, and as yet not feasible except 1. The provisions contained in ANSI N18.3-1972, through use of techniques requiring disassembly into "Fuel Assembly Identification," are generally acceptable individual fuel rods. The SNM content of a fuel assembly and provide an adequate numbering basis for is currently obtained by determining the SNM content in identification of individual fuel assemblies from the time each discrete item (element or rod), and then verifying of final fuel rod consolidation at the fabricator's facility the presence of such items. The principal diversion until the assembly is dissolved as an entity.
threat for SNM at the reactor consists of theft of identifiable items. Accordingly, the AEC's material 2. In the special case of fuel assemblies from which a protection inspection practices for SNM contained in fuel rod or other SNM-containing component may be completed fuel assemblies on inventory at light-water removed without the need of a metal-cutting operation, reactor facilities are based on assuring that all further identification and accounting measures in individually identifiable fuel pieces received at the addition to those required in ANSI N18.3-1972 may be facility are still on hand or have been shipped to other necessary. This determination will be made on an licensed facilities. individual case basis.
A substantial level of assurance can be provided within this context if each fuel assembly is uniquely 'Copies may be obtained from the American National identified by a number inscribed in its structure. The Standards Institute, Inc., 1430 Broadway, New York. New York unique numbering also offers an advantage at the time of 10018.
USAEC REGULATORY GUIDES Copies of published guides may be obtained by request indicating the divisions desired to the US. Atomic Energy Commission, Washington, D.C. 20545, Regulatory Guides are issued to describe and make available to the public Attention: Director of Regulatory Standards. Comments and suggestions for methods acceptable to the AEC Regulatory staff of Implementing specific parts of improvements In these guides are encouraged and should be sent to the Secretary the Commission's regulations, to delineate techniques used by the staff in of the Commission, U.S. Atomic Energy Commission, Washington, D.C. 20545.
evaluating specific 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 ere issued in the following ten broad divisions:
the guides will be acceptable if they provide a basil for the findings requisite to the Issuance or continuance of a permit or license by the Commission. 1. Power Reactors
8. Products
2. Reaeerch end Test Reactors
7. Transportation
3. Fuels and Materials Facilities 8. Occupational Health Published guides will be revised periodically, as appr.,rwate, to accommodate 4. Environmental and Siting 9. Antitrust Review comments and to reflect new information or experience. 5. Materials and Plant Protection 10. General