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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
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Watermarked DG-5073 - Fitness for Duty Program for Part 53 - 10-13-23
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Watermarked - DG-5074 - Access Authorization - Econcurrence Version Clean (02-03-23)
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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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May 1973 U.S. ATOMIC ENERGY COMMISSION
REGU LATORY GUIDE
DIRECTORATE OF REGULATORY STANDARDS
REGULATORY GUIDE 2.1 SHIELD TEST PROGRAM FOR
EVALUATION OF INSTALLED BIOLOGICAL SHIELDING
IN RESEARCH AND TRAINING REACTORS
A. INTRODUCTION
installed biological shielding in research and training reactors subject to the following:
Subdivision (bX6) (iii) of section 50.34, "Contents
1. Section 3.2.4 of ANSI 18.9-1972 defines accessible of applications: technical information," of 10 CFR Part areas, controlled areas, and unlimited access areag.
50, "Licensing of Production and Utilization Facilities,"
Section 3.2.5 defines Maximum Permissible Dose rate.
requires an applicant for a license to include in his final Nothing in these paragraphs should imply that exposures safety analysis report plans for preoperational testing need not be controlled to the requirements of 10 CFR
and initial operation. This regulatory guide describes a Part 20, "Standards for Protection Against Radiation."
shield test program that is generally acceptable for evaluation of installed biological shielding in research 2. Section 5.2 of ANSI 18.9-1972 states that and training reactors.
procedures for implementing the minimum shield test program shall be prepared. These procedures should be
B. DISCUSSION
designed so that exposures to personnel performing the Subcominittee ANS 6, Shielding, of the American test program are as low as practicable. These procedures Nuclear Society Standards Committee has developed a should also be designed so that safety hazards to standard that describes an operational shield test personnel performing the shield test program are program which may be used in evaluating the iilstalled properly identified. For example, gas ;nonitoring should biological shielding in research and training reactors. be required where gases or vapors could affect the This standard was approved by the American National accessibility of an area.
Standards Committee Ni 8, Nuclear Design Criteria, and its Secretarial. It was subsequently approved and 3. Section 6 of ANSI N18.9-1972 specifies tests that designated ANSI N18.9-1972 by the American National should be conducted for evaluation of installed Standards Institute (ANSI) on September 15, 1972. biological shielding. This section further specifies use of survey meters when conducting the required test
s. The
C. REGULATORY POSITION
shield test program should also include provisions for gamma and neutron film mapping of critical areas where The requirements and guidelines contained in ANSI
personnel exposure may occur due to streaming, cracks, N18.9-1972, "Program for Testing Biological Shielding or gaps in the shielding too small to detect by survey meters, e.g.. areas in the vicinity of beam holes, in Nuclear Reactor Plants,"' approved September 15.
irradiation ports, or shielding areas directly aligned with
1972, are generally acceptable and. with due the core.
consideration for the unique characteristics of each research and training reactor, provide an adequate basis
4. Section 9 of ANSI N18.9-1972 states that for conducting a shield test program during instruments used in carrying out the minimum shield preoperational and startup testing for evaluation of test program shall have been calibrated prior to use in the test program and immediately after each survey. The
'Copies may be obtained from American Nuclear Society, shield test program should also include provisions for
244 East Ogden Avenue, Hinsdale, Illinois 60521.
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 end 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. US. Atomic Energy Commission. Washington. D.C. 20645, evaluating specific problems or postulated accidents, or to provide guidance to Attention. Chief, Public Proceedings Staff.
applicants. Regulatory Guides are not substitutes for regula.ions and compliance with them is not required. Methods and solutions different from those set out in The guides are issued in the following ten broad divisions:
the guides will be acceptable if they provide a basis for the findings requisite to 6. Products the iwuance or continuance of a permit or license by the Commissio
n.
1. Power Reactors
2. Research and Test Reactors
7. Transportation
3. Fuels and Materials Facilities
8. Occupational Health
4. Environmental and Siting 8. Antitrust Review Published guides will be revised periodically. as appropriate, to accommodate
5. Materials and Plant Protection 10. General comments and to reflect new information or experience
calibrating #1 radiation survey monitors (both portable these requirements, a survey instrument's range should and installed) aainsl a source emitting radiation of be consistent with the actual dose range expected. For approximrnly the tane type and intensity as that measurements conducted while a reactortis operating in eipected to be neasured during the survey. the pulsed mode, appropriate instrumentation, such as film packets, which will properly respond to and
5. Seitions 9.2 and 9.3 of ANSI 18.9.1972 provide measure radiation during the pulsed mode of operation requirements for survey instruments. In addition to should be provided.
2.1-2