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Category:Regulatory Guide
MONTHYEARML22264A1092024-10-30030 October 2024
DG-5078 - Fatigue Management for Nuclear Power Plant Personnel at Commercial Nuclear Plants Licensed Under 10 CFR Part 53
ML22257A1732024-10-30030 October 2024
DG-1413 - Technology-Inclusive Identification of Licensing Events for Commercial Nuclear Plants
ML22203A1312024-10-30030 October 2024
DG-5076 - Guidance for Technology-Inclusive Requirements for Physical Protection of Licensed Activities at Commercial Nuclear Plants
ML22200A0372024-10-30030 October 2024
DG-5073 - Fitness-For-Duty Programs for Commercial Nuclear Plants and Manufacturing Facilities Licensed Under 10 CFR Part 53
ML22199A2572024-10-30030 October 2024
DG-5075 - Establishing Cybersecurity Programs for Commercial Nuclear Plants Licensed Under 10 CFR Part 53
ML22199A2462024-10-30030 October 2024
DG-5074 - Access Authorization Program for Commercial Nuclear Plants
ML23291A2982024-02-29029 February 2024
DG-1422 (RG 1.245 Rev 1) Preparing Probabilistic Fracture Mechanics (Pfm) Submittals
ML23072A0452024-01-31031 January 2024
Watermarked - RG 1.235 Revision 0 - Emergency Planning for Decommissioning Nuclear Power Reactors (02-14-24)
ML23248A3432023-08-31031 August 2023
Draft Regulatory Guide DG-1404, Rev. 1, Guidance for a Technology-Inclusive Content-Of-Application Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications,
ML23102A0322023-05-17017 May 2023
Rev 2 Periodic Review
ML22196A0652023-01-31031 January 2023
DG 1408 ASME Code Cases Not Approved for Use (RG 1.193 Rev 8)
ML22196A0632023-01-31031 January 2023
Draft Regulatory Guide DG 1407, Operation and Maintenance Code Case Acceptability, ASME OM Code (RG 1.192 Rev 5)
ML22195A2842023-01-31031 January 2023
Draft Regulatory Guide DG 1406, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1 (RG 1.147 Rev 21)
ML22195A2822023-01-31031 January 2023
DG 1405 - Design, Fabrication, and Materials Code Case Acceptability, ASME Section III (RG 1.84 Rev 40)
ML22101A2632023-01-30030 January 2023
Rev 2 Acceptability of ASME Code Section III Division 5 High Temperature Reactors
ML22221A2202022-10-0505 October 2022
Rev 0, Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Production and Utilization Facilities
ML22223A1592022-08-12012 August 2022
Draft Regulatory Guide 1.250, Rev. 0, Dedication of Commercial-Grade Digital Instrumentation & Control Item for Use in Nuclear Power Plants (for ACRS on 9-7-22)
ML22066B2752022-05-31031 May 2022
Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation
ML21288A1152022-01-31031 January 2022
Draft Regulatory Guide DG-1393, RG 1.248 Rev. 0, Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations
Regulatory Guide 1.1922021-12-31031 December 2021
Operation and Maintenance Code Case Acceptability, ASME OM Code
Regulatory Guide 1.1472021-12-17017 December 2021
0, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1
Regulatory Guide 1.842021-12-17017 December 2021
9, Design, Fabrication, and Materials Code Case Acceptability, ASME Section III
Regulatory Guide 1.1932021-12-17017 December 2021
ASME Code Cases Not Approved for Use
ML21288A5652021-11-0909 November 2021
ACRS Version DG-1393 (RG 1.248 Rev. 0) (Advance Copy for ACRS Use)
ML20356A1272021-03-31031 March 2021
Regulatory Guide RG 1.240, Fresh and Spent Fuel Pool Criticality Analyses
ML21068A4042021-03-12012 March 2021
RG 1.102. Transmittal Memo Periodic Review 2021
ML20301A1702021-02-17017 February 2021
Transmittal Memo to OCA for Revision 4 of RG 1.136, Design Limits, Loading Combinations, Materials, Construction and Testing of Concrete Containments
ML20339A5582021-02-0303 February 2021
DG-1304 for Rev 0 of RG 1.243, Safety-Related Steel Structures and Steel-Plate Composite (Sc) Walls for Other than Reactor Vessels and Containments
ML20339A5592021-02-0303 February 2021
Regulatory Analysis for DG-1304 for Rev 0 of RG 1.243, Safety-Related Steel Structures and Steel-Plate Composite (Sc) Walls for Other than Reactor Vessels and Containments
ML21033B0912021-02-0202 February 2021
Draft for ACRS Meeting 3-3-21: Regulatory Guide - RG 1.240 Rev.0 for Fresh and Spent Fuel Pool Criticality Analyses
ML20301A1672021-02-0101 February 2021
Regulatory Guide (RG) 1.136, Rev 4, Design Limits, Loading Combinations, Materials, Construction and Testing of Concrete Containments
Regulatory Guide 1.1772021-01-0404 January 2021
(DG-1287) an Approach for Plant-Specific, Risk Informed Decisionmaking: Technical Specifications
ML21033B0832020-10-23023 October 2020
Draft for ACRS Meeting 3-3-21: Public Comment Resolution Table for DG-1373
ML20078K9202020-08-31031 August 2020
DG-1370 Proposed Revision 1 of Regulatory Guide (RG) 1.191, Fire Protection Program for Nuclear Power Plants During Decommissioning
ML20142A4892020-08-31031 August 2020
DG-1351 Rev 1 - Licensee Actions to Address Nonconservative Technical Specifications_FY20
ML20164A2142020-08-0404 August 2020
FRN for 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
ML20125A7322020-07-0101 July 2020
FRN for RG 1.187-Rev 2 - Guidance for Implementation of 10 CFR 50.59, Changes, Tests and Experiments
Regulatory Guide 1.1872020-06-30030 June 2020
Rev. 2, Guidance for Implementation of 10 CFR 50.59, Changes, Tests and Experiments
ML20055F4902020-06-30030 June 2020
Reg Guide 1.236 - Pressurized-Water Reactor Control Rod Ejection and Boiling-Water Reactor Control Rod Drop Accidents
ML20055F4892020-06-10010 June 2020
Pressurized-Water Reactor Control Rod Ejection and Boiling-Water Reactor Control Rod. Response to Public Comments - 2nd Comment Period
ML20141L6132020-05-31031 May 2020
Reg Guide 1.142 Rev 3 - Safety Related Structures for Nuclear Power Plants (Other than Reactor Vessels and Containments)
ML19156A1292020-02-29029 February 2020
Regulatory Guide (Rg) 1.151, Revision 2 Instrument Sensing Lines
ML19266A6192020-02-21021 February 2020
Response to Public Comments on DG-1337
ML14161A6212020-02-12012 February 2020
DG-3036 Standard Format and Content of License Applications for Storage Only of Unirradiated Power Reactor Fuel and Associated Radioactive Material
ML20022A2142020-01-22022 January 2020
Draft Regulatory Guide DG-1364, Volcanic Hazards. Draft for ACRS Public Meeting 1-22-20
ML19175A0442019-12-19019 December 2019
Regulatory Guide (Rg) 1.180, Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems
ML19213A3452019-09-30030 September 2019
Draft Regulatory Guide DG-1341, Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses
ML19141A2142019-08-16016 August 2019
Regulatory Guide Periodic Review
ML18312A2422019-04-30030 April 2019
Draft Regulatory Guide DG-1353, Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water
ML18114A2262018-08-31031 August 2018
Draft Regulatory Guide DG-1343, (Rg 1.192 Rev 3), Operation and Maintenance Code Case Acceptability, ASME OM Code
2024-02-29
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Bases for withdrawal of Regulatory Guide 1.37, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants (1) What regulation(s) did the Regulatory Guide support?
RG 1.37 provides guidance on meeting the requirements of Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities.
(2) What was the purpose of the Regulatory Guide?
RG 1.37 provided guidance to licensees and their vendors on cleaning and cleanness controls of fluid systems and associated components for nuclear power plants during manufacturing, construction, repairs, and modifications.
(3) How was the Regulatory Guide used?
RG 1.37 was used to assist licensees and their vendors in meeting the requirements in Appendix B to 10 CFR Part 50, in regards to quality assurance requirements for cleaning of fluid systems and associated components. Regulatory Guide (RG) 1.37 was initially published in March 1973 and revised in March 2007. The initial issuance of RG 1.37 endorsed American National Standards Institute Standard N45.2.1-1973, Cleaning of Fluid Systems and Associated Components during Construction Phase of Nuclear Power Plants with six regulatory positions. RG 1.37, Revision 1, endorsed American Society of Mechanical Engineers NQA-1-1994, Part II, Subpart 2.1, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components for Nuclear Power Plants, with three regulatory positions.
The staff issued RG 1.37, which endorsed an industry consensus standard, to provide licensees with a method acceptable to the NRC staff to meet quality assurance requirements.
(4) Why is the Regulatory Guide no longer needed?
The NRC issued RG 1.28, Quality Assurance Program Criteria (Design and Construction), Revision 4 in June 2010, which endorses NQA-1-2008 and the NQA-1a-2009 Addenda, Parts I and II. NQA-1-2008 and NQA-1a-2009 Addenda Part II incorporate the requirements and regulatory positions contained in RG 1.37, Revision 1. Additionally, RG 1.33, Quality Assurance Program Requirements (Operation),
was issued in June 2013, which endorses ANSI/ANS 3.2-2012. ANSI/ANS 3.2-2012, Section 1.2, Purpose, requires implementation of the applicable sections of NQA-1-2008 and NQA-1a-2009 during the operational phase of power plant operation. Any update to RG 1.37 to endorse NQA-1-2008 and NQA-1a-2009, Part II, Subpart 2.1 would be redundant since the standards are already endorsed in RG 1.28, Revision 4 and in RG 1.33 Revision 3.
Regulatory Guide 1.37 endorsed ASME NQA-1-1994 with 3 regulatory positions. The regulatory positions are no longer need for the following reasons:
- Position 1, Referenced Documents, is no longer required because the paragraph has been deleted in ASME NQA-1-2009 and subsequent revisions.
- The requirements of Position 2, Water quality, are included in Section 304.1 of ASME NQA 2009 and subsequent revisions.
- The requirements of Position 3, Precautions, are included in Section 304.1 of ASME NQA 2009 and subsequent revisions.
(5) What guidance is available once the Regulatory Guide is withdrawn?
The NRC staffs regulatory guidance for quality assurance requirements for cleaning of fluid systems and associated components can be found in RG 1.28, Revision 4, Quality Assurance Program Criteria (Design and Construction), which endorsed NQA-1-2008 and NQA-1a-2009 Addenda, Parts I and II.
Additionally, RG 1.33, Quality Assurance Program Requirements (Operation), endorses ANSI/ANS 3.2-2012. ANSI/ANS 3.2-2012, Section 1.2, Purpose, requires implementation of the applicable sections of NQA-1-2008 and NQA-1a-2009 during the operational phase of power plant operation.
(6) Is the Regulatory Guide referenced in other documents and what are the ripple effects on these documents if it is withdrawn?
RG 1.37 is briefly discussed or referenced in the following sections of NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition:
- 5.3.1, Reactor Vessel Materials,
- 6.1.1, Engineered Safety Features Materials,
- 10.3.6, Steam and Feedwater System Materials,
- 14.2, Initial Plant Test Program - Design Certification and New License Applicants, and
- 17.5, Quality Assurance Program Description - Design Certification, Early Site Permit and New License Applicants.
RG 1.37 is briefly discussed or referenced in the following inspection procedures (IPs):
- IMC 1245, Appendix C2, Reactor Engineering Inspector Technical Proficiency Training and Qualification Journal
- IP 49063, Piping - Work Observation There are no ripple effects of withdrawing this RG. The impact of not revising the above documents at this time will be minimal because applications referencing this RG will be limited. The industry is mature and fluid cleaning practices/procedures for most utilities are well established. Any user who desires to use RG 1.37 directly or indirectly (via a related reference) will ascertain that it has been withdrawn and the linked bases for withdrawal will direct the user to RG 1.28, Revision 4 and RG 1.33, Revision 3. The staff intends to update references in NUREG-0800 and inspection procedures to RG 1.28, Revision 4 during the next updates to these documents.
(7) What is the basis for believing that no guidance similar to that in the Regulatory Guide will ever be needed?
The guidance remains valid and has been incorporated into RG 1.28 and RG 1.33. Any updates to this guidance would be evaluated as needed, particularly any changes to NQA-1, Parts I and II that warrant limitations or conditions.
(8) Will generic guidance still be needed?
Guidance for complying with quality assurance criteria for cleaning of fluid systems and associated components is still needed. The staff has endorsed updated guidance in Revision 4 of RG 1.28. Updated 2
guidance for cleanliness of fluid systems is ensured through the continued staff participation on consensus standards.
(9) What is the rationale for withdrawing this Regulatory Guide instead of revising it?
RG 1.37 contains the endorsement of outdated guidance. Updated guidance has been endorsed in Revision 4 of RG 1.28, which was issued in June 2010.
(10) Do other agencies rely upon the Regulatory Guide, e.g., the Agreement States, National Aeronautical and Space Administration, Department of Energy?
The staff is unaware of any other agency that uses or relies on the guidance in RG 1.37.
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