ML24261B898
| ML24261B898 | |
| Person / Time | |
|---|---|
| Issue date: | 02/15/2024 |
| From: | Aaron Armstrong NRC/NRR/DRO/IQVB |
| To: | |
| References | |
| Download: ML24261B898 (12) | |
Text
August 2021 US Nuclear Regulatory Commission (NRC)
Discussion on Regulatory Guide 1.28, QUALITY ASSURANCE PROGRAM CRITERIA (DESIGN AND CONSTRUCTION)
ASME NQA-1 EUIWG Meeting February 15, 2024 Aaron Armstrong NRR/DRO/IQVB 1
Topics
- Purpose
- Provide the international community with stronger understanding of the NRCs regulatory guide process
- Provide a discussion on the latest Regulatory Guide (RG) 1.28, Quality Assurance Program Criteria (Design and Construction),
Revision 6, endorsement of the NQA-1 2017, 2019, 2022 editions.
- Discussion on the:
The NRCs Regulatory Framework and Quality Assurance (QA)
Regulations
- The Regulatory Guide Process, and issuance of RG 1.28, Revision 6 2
Regulatory Framework Part 50
- Construction Permit
- Operating License Part 52
- Early Site Permit
- Design Certification
- Combined License 3
Quality Assurance Regulations Appendix B to Part 50 - Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants Quality assurance comprises all those planned and systematic actions necessary to provide adequate confidence that a structure, system, or component will perform satisfactorily in service.
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Regulations Appendix B to Part 50 I.
Organization II.
Quality Assurance Program III.
Design Control IV.
Procurement Document Control V.
Instructions, Procedures, and Drawings VI.
Document Control VII.
Control of Purchased Material, Equipment, and Services VIII. Identification and Control of Materials, Parts, and Components IX.
Control of Special Processes X.
Inspection XI.
Test Control XII. Control of Measuring and Test Equipment XIII.
Handling, Storage, and Shipping XIV. Inspection, Test, and Operating Status XV. Nonconforming Materials, Parts, or Components XVI. Corrective Action XVII. Quality Assurance Records XVIII.
Audits 18 Criterion comprising a QA Program 5
Regulatory Guides
- RGs describe methods acceptable to the NRC staff for implementing the regulations.
- Often QA-related RGs endorse a national standard such as:
- American Society of Mechanical Engineers (ASME)
- Institute of Electrical & Electronics Engineers (IEEE)
- American National Standards Institute (ANSI) 6
Quality Assurance Standards American Society of Mechanical Engineers (ASME)
- ASME NQA-1
- Delineates requirements for the establishment and implementation of a QA program for siting, design, construction, operation and decommissioning of nuclear facilities
- Most common QA program of licensees, A/Es, NSSSs, vendors 7
NRC Regulatory Guide Process 8
- Draft Guide 1403 (Proposed RG 1.28, Revision 6)
The NRC staff completed its review of ASME Nuclear Quality Assurance (NQA) 2017, NQA-1-2019, and NQA-1-2022, Quality Assurance Requirements for Nuclear Facility Applications, for endorsement and issued Draft Guide (DG) 1403 (Proposed Revision 6 to RG 1.28)
The staff is proposing two new regulatory positions.
1.) Etching should not be used on nickel alloys, weld areas, or sensitized areas of stainless steel.
2.) When the referenced or invoked code or standard becomes superseded or canceled, licensees or applicants need to submit their proposed alternative for NRC review and approval, as appropriate, for continued use of the code or standard or a proposed alternative.
The DG was processed through the Regulator Guide Process 9
- RG 1.28 Revision 6 was published on September 7, 2023 (ML23177A002)
Revision 6 endorses the use of the 2017, 2019, and 2022 of NQA-1 and endorses Part I & II requirements in NQA-1-2017, NQA-1-2019, and NQA-1-2022, The Regulatory Positions section of RG 1.28, Revision 6, provides the NRCs clarifications and exceptions for use of these standards.
- Majority of regulatory positions from Revision 5 still applicable in Revision 6.
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- RG 1.28 Revision 6 Continued
- New regulatory positions:
- Direct users to use Nuclear Energy Institute (NEI)14-05A, Guidelines for the Use of Accreditation in Lieu of Commercial Grade Surveys for Procurement of Laboratory Calibration and Test Services, Revision 1 (ADAMS Accession No. ML20259B731).
- Subpart 2.2 - "Etching should not be used on nickel alloys, weld areas, or sensitized areas of stainless steel.
- Subpart 5.5 - "When the referenced or invoked code or standard becomes superseded or canceled, licensees or applicants need to submit their proposed alternative for NRC review and approval, as appropriate, for continued use of the code or standard or a proposed alternative."
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Questions or Comments?
Contact Information:
Aaron Armstrong 301-415-8396 Aaron.Armstrong@nrc.gov 12