ML23222A182
| ML23222A182 | |
| Person / Time | |
|---|---|
| Issue date: | 12/01/2023 |
| From: | Darrell Murdock NRC/RES/DE/CIB |
| To: | |
| Shared Package | |
| ML23139A210 | List: |
| References | |
| RG-1.030, Rev 3 DG-1419 | |
| Download: ML23222A182 (9) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION DRAFT REGULATORY GUIDE DG-1419 Proposed Revision 1 to Regulatory Guide 1.30 Issue Date: December 2023 Technical Lead: Darrell Murdock INSTALLATION, INSPECTION, AND TESTING FOR CLASS 1E POWER, INSTRUMENTATION, AND CONTROL EQUIPMENT AT PRODUCTION AND UTILIZATION FACILITIES A. INTRODUCTION Purpose This regulatory guide (RG) describes an approach that is acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) to meet the regulatory requirements for installation, inspection, and testing for Class 1E power, instrumentation, and control equipment at production and utilization facilities. It endorses, with a clarification, Institute of Electrical and Electronics Engineers (IEEE) Standard (Std) 336-2020, IEEE Recommended Practice for Installation, Inspection, and Testing for Class 1E Power, Instrumentation, and Control Equipment at Nuclear Facilities (Ref. 1).
Applicability This RG applies to nuclear power reactor applicants and licensees subject to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing of Production and Utilization Facilities (Ref. 2), and 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants (Ref. 3). With respect to 10 CFR Part 50, this RG applies to applicants for and holders of a license, as defined in 10 CFR 50.2. With respect to 10 CFR Part 52, this RG applies to applicants for and holders of licenses, as defined in 10 CFR 52.1, standard design certifications, and standard design approvals.
Applicable Regulations
- 10 CFR Part 50 provides regulations for licensing production and utilization facilities.
o 10 CFR 50.65, Requirements for monitoring the effectiveness of maintenance at nuclear power plants, requires that each holder of an operating license for a nuclear power plant under 10 CFR Part 50 and each holder of a combined license under 10 CFR Part 52 (after the Commission makes the finding under 10 CFR 52.103(g)) monitor the performance or condition of structures, systems, and components (SSCs) against licensee-established goals, in a manner sufficient to provide reasonable assurance that these SSCs are capable of fulfilling their intended functions. 10 CFR 50.65 requires these goals to be established This RG is being issued in draft form to involve the public in the development of regulatory guidance in this area. It has not received final staff review or approval and does not represent an NRC final staff position. Public comments are being solicited on this DG and its associated regulatory analysis. Comments should be accompanied by appropriate supporting data. Comments may be submitted through the Federal rulemaking Web site, http://www.regulations.gov, by searching for draft regulatory guide DG-1419. Alternatively, comments may be submitted to the Office of Administration, Mailstop: TWFN 7A-06M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, ATTN:
Program Management, Announcements and Editing Staff. Comments must be submitted by the date indicated in the Federal Register notice.
Electronic copies of this DG, previous versions of DGs, and other recently issued guides are available through the NRCs public Web site under the Regulatory Guides document collection of the NRC Library at https://nrc.gov/reading-rm/doc-collections/reg-guides/index.html. The DG is also available through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under Accession No. ML23222A182. The regulatory analysis may be found in ADAMS under Accession No. ML23235A321.
commensurate with safety and, where practical, take into account industrywide operating experience. 10 CFR 50.65 also states that appropriate corrective action will be taken when the performance or condition of an SSC does not meet established goals. For a nuclear power plant for which the licensee has submitted the certifications specified in 10 CFR 50.82(a)(1) or 10 CFR 52.110(a)(1), as applicable, 10 CFR 50.65 only applies to the extent that the licensee monitor the performance or condition of all SSCs associated with the storage, control, and maintenance of spent nuclear fuel in a safe condition, in a manner sufficient to provide reasonable assurance that these SSCs are capable of fulfilling their intended functions.
o The general design criteria (GDC) in Appendix A, General Design Criteria for Nuclear Power Plants, to 10 CFR Part 50 establish minimum requirements for the principal design criteria for water-cooled nuclear power plants similar in design and location to plants for which construction permits have been issued by the Commission. The GDC are also considered to be generally applicable to other types of nuclear power units and are intended to provide guidance in establishing the principal design criteria for such other units. The following GDC is related to quality assurance (QA):
o GDC 1, Quality standards and records, requires, in part, that SSCs important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed.
o Nuclear power plants and fuel reprocessing plants include SSCs that prevent or mitigate the consequences of postulated accidents that could cause undue risk to public health and safety.
Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50 establishes QA requirements for the design, manufacture, construction, and operation of those SSCs. The pertinent requirements of Appendix B to 10 CFR Part 50 apply to all activities affecting the safety-related functions of those SSCs.
- 10 CFR Part 52.79(a) requires that an application for a combined license contain a final safety analysis report that describes the facility, presents the design bases and the limits on its operation, and presents a safety analysis of the structures, systems, and components of the facility as a whole.
o 10 CFR 52.79(a)(10) requires that SSCs important to safety in a nuclear power plant be designed to accommodate the effects of environmental conditions and that design control measures, such as testing, be used to check the adequacy of the design.
o 10 CFR 52.79(a)(15) requires an application for a combined license to contain a final safety analysis report that describes the program and its implementation for monitoring the effectiveness of maintenance necessary to meet the requirements of 10 CFR 50.65.
Related Guidance
- RG 1.160, Monitoring the Effectiveness of Maintenance at Nuclear Power Plants (Ref. 4),
provides general guidelines for complying with 10 CFR 50.65(a)(1).
- NUREG-1537, Parts 1 and 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, issued February 1996 (Ref. 5), contains format and content DG 1419, Page 2
guidance for non-power reactor applicants and licensees, as well as a standard review plan and acceptance criteria for NRC staff.
- Final Interim Staff Guidance Augmenting NUREG-1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, Parts 1 and 2, for Licensing Radioisotope Production Facilities and Aqueous Homogeneous Reactors, issued October 2012 (Ref. 6), updates and expands the content of NUREG-1537 Part 1 and Part 2, and contains format and content guidance for non-power aqueous homogeneous reactor and radioisotope production facility applicants and licensees, as well as a standard review plan and acceptance criteria for the NRC staff.
- Endorsement of Appendix A to Oak Ridge National Laboratory Report, Proposed Guidance For Preparing and Reviewing a Molten Salt Non-Power Reactor Application, as Guidance for Preparing Applications for the Licensing of Non-Power Liquid Fueled Molten Salt Reactors, dated November 18, 2020 (Ref. 7), endorses, with clarifications, Proposed Guidance for Preparing and Reviewing a Molten Salt Non-Power Reactor Application (ORNL/TM-2020/1478), issued July 2020 (Ref. 8), to support the review of non-power molten salt reactors.
Purpose of Regulatory Guides The NRC issues RGs to describe methods that are acceptable to the staff for implementing specific parts of the agencys regulations, to explain techniques that the staff uses in evaluating specific issues or postulated events, and to describe information that the staff needs in its review of applications for permits and licenses. Regulatory guides are not NRC regulations and compliance with them is not required.
Methods and solutions that differ from those set forth in RGs are acceptable if supported by a basis for the issuance or continuance of a permit or license by the Commission.
Paperwork Reduction Act This RG provides voluntary guidance for implementing the mandatory information collections in 10 CFR Parts 50 and 52 that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et.
seq.). These information collections were approved by the Office of Management and Budget (OMB),
under control numbers 3150-0011 and 3150-0151, respectively. Send comments regarding this information collection to the FOIA, Library, and Information Collections Branch ((T6-A10M), U.S.
Nuclear Regulatory Commission, Washington, DC 20555 0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the OMB reviewer at: OMB Office of Information and Regulatory Affairs, (3150-0011 and 3150-0151), Attn: Desk Officer for the Nuclear Regulatory Commission, 725 17th Street, NW, Washington, DC, 20503; e-mail: oira_submissions@omb.eop.gov.
Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid OMB control number.
DG 1419, Page 3
B. DISCUSSION Reason for Revision This RG is being revised to endorse IEEE Std 336-2020. IEEE Std. 336-2020 provides an acceptable method for installation, inspection, and testing of Class 1E power, instrumentation, and control equipment and systems at production and utilization facilities. The staff determined that the revised IEEE standard, subject to the clarification described in Section C, supports applications for new licenses, design certifications, standard design approvals, and license amendments. This RG also removes all QA requirements from Safety Guide 30, Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment, dated August 11, 1972 (also known as RG 1.30, Rev. 0) (Ref. 9) and addresses the requirements of a QA program for design and construction in RG 1.28, Revision 6, Quality Assurance Program Criteria (Design and Construction), (Ref. 10) and for operation in RG 1.33, Revision 3, Quality Assurance Program Requirements (Operation), (Ref. 11).
Background
Several decades of experience in the nuclear industry have prompted many updates to standard quality programs, such as the elimination of prescriptive requirements and of duplicate criteria. This revision to RG 1.30 removes all QA requirements from Safety Guide 30 (RG 1.30, Rev. 0) and addresses the requirements of a QA program for design and construction in RG 1.28, and for operation in RG 1.33.
RG 1.28 finds the requirements included in NQA-1b-2011 Addenda to ASME NQA-1-2008, ASME NQA-1-2012, and ASME NQA-1-2015 acceptable for use given stated exceptions identified in the staff regulatory guidance section. RG 1.33 finds the requirements included in ANSI/ANS 3.2-2012 acceptable for use given stated exceptions identified in the staff regulatory guidance section.
The Nuclear Power Engineering Committee prepared IEEE Std 336-2020, and the IEEE Standards Board approved it September 24, 2020. The revised IEEE Std 336-2010 incorporates new technologies and industry best practices and provides more detailed guidance on specific topics.
The purpose of the recommended practice in IEEE Std. 336-2020 is to identify the activities, instructions, and attributes that should be considered in the process of installing, inspecting, and testing during new construction, modification, and maintenance for Class 1E power, instrumentation, and control equipment at production and utilization facilities. Topics covered include equipment specifications, installation requirements, inspection and testing procedures, and documentation requirements. The recommended practice also emphasizes the importance of maintaining proper documentation throughout the installation, inspection, and testing process and provides guidance on the types of documentation that should be generated and maintained. This recommended practice does not apply to periodic surveillance testing.
In addition, IEEE Std 336-2020 includes new guidance on the training and qualification requirements for personnel performing the verification of the recommended practices.
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Consideration of International Standards The International Atomic Energy Agency (IAEA) works with member states and other partners to promote the safe, secure, and peaceful use of nuclear technologies. The IAEA develops Safety Requirements and Safety Guides for protecting people and the environment from the harmful effects of ionizing radiation. This system of safety fundamentals, safety requirements, safety guides, and other relevant reports, reflects an international perspective on what constitutes a high level of safety. To inform its development of this RG, the NRC staff considered IAEA Safety Requirements and Safety Guides pursuant to the Commissions International Policy Statement (Ref. 12) and Management Directive and Handbook 6.6, Regulatory Guides (Ref. 13). The NRC staff did not identify any IAEA Safety Requirements or Guides with information related to the topic of this RG.
Documents Discussed in Staff Regulatory Guidance This RG endorses, in part, the use of one or more codes or standards developed by external organizations and other third-party guidance documents. These codes, standards and third-party guidance documents may contain references to other codes, standards, or third-party guidance documents (secondary references). If a secondary reference has itself been incorporated by reference into NRC regulations as a requirement, then licensees and applicants must comply with that standard as set forth in the regulation. If the secondary reference has been endorsed in a RG as an acceptable approach for meeting an NRC requirement, then the standard constitutes a method acceptable to the NRC staff for meeting that regulatory requirement as described in the specific RG. If the secondary reference has neither been incorporated by reference into NRC regulations nor endorsed in a RG, then the secondary reference is neither a legally-binding requirement nor a generic NRC approved acceptable approach for meeting an NRC requirement. However, licensees and applicants may consider and use the information in the secondary reference, if appropriately justified, consistent with current regulatory practice, and consistent with applicable NRC requirements.
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C. STAFF REGULATORY GUIDANCE
- 1. The NRC staff considers conformance with the recommended practice in IEEE Std 336-2020 for installation, inspection, and testing for Class 1E power, instrumentation, and control equipment at production and utilization facilities an acceptable method for complying with the NRCs regulations for the construction or modification of electrical and instrumentation systems at production and utilization facilities, subject to the following clarification:
- a. The below paragraph in Clause 4.1, General, of IEEE Std 336-2020 states the following:
During the initial construction phase and performance of modifications, this recommended practice should be used in conjunction with applicable portions of ANSI/ASME NQA-1.
During the operations phase, this recommended practice should be used with the applicable portions of ANSI/ANS-3.2 and ANSI/ASME NQA-1.
This paragraph should be replaced with:
During the initial construction phase and performance of modifications, this recommended practice should be used in conjunction with the guidance in RG 1.28 (Revision 6), which endorses NQA-1b-2011, NQA-1-2012, and NQA-1-2015 with exceptions and clarifications.
During the operations phase, this recommended practice should be used in conjunction with the guidance in RG 1.33 (Revision 3), which endorses ANSI/ANS 3.2-2012 with clarifications.
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D. IMPLEMENTATION The NRC staff may use this regulatory guide as a reference in its regulatory processes, such as licensing, inspection, or enforcement. However, the NRC staff does not intend to use the guidance in this regulatory guide to support NRC staff actions in a manner that would constitute backfitting as that term is defined in 10 CFR 50.109, Backfitting, and as described in NRC Management Directive 8.4, Management of Backfitting, Forward Fitting, Issue Finality, and Information Requests (Ref. 14), nor does the NRC staff intend to use the guidance to affect the issue finality of an approval under 10 CFR Part 52, Licenses, Certifications, and Approvals for Nuclear Power Plants. The staff also does not intend to use the guidance to support NRC staff actions in a manner that constitutes forward fitting as that term is defined and described in Management Directive 8.4. If a licensee believes that the NRC is using this regulatory guide in a manner inconsistent with the discussion in this Implementation section, then the licensee may file a backfitting or forward fitting appeal with the NRC in accordance with the process in Management Directive 8.4.
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REFERENCES 1
- 1. Institute of Electrical and Electronics Engineers (IEEE), Std. 336-2020, IEEE Recommended Practice for Installation, Inspection and Testing for Class 1E Power, Instrumentation, and Control Equipment at Nuclear Facilities, Piscataway, New Jersey. 2
- 2. U.S. Code of Federal Regulations (CFR), Domestic Licensing of Production and Utilization Facilities, Part 50, Chapter I, Title 10, Energy.
- 3. CFR, Licenses, Certifications, and Approvals for Nuclear Power Plants, Part 52, Chapter I, Title 10, Energy.
- 4. U.S. Nuclear Regulatory Commission (NRC), Regulatory Guide (RG) 1.160, Monitoring the Effectiveness of Maintenance at Nuclear Power Plants, Washington, DC.
- 5. NRC, NUREG-1537, Parts 1 and 2, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, Washington, DC, February 1996. (Agencywide Document and Access Management System (ADAMS) Numbers ML12156A069 and ML12156A075, respectively)
- 6. NRC, Final Interim Staff Guidance Augmenting NUREG-1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors, Parts 1 and 2, for Licensing Radioisotope Production Facilities and Aqueous Homogenous Reactors, Washington, DC, October 2012. (ML12156A053)
- 7. NRC, Endorsement of Appendix A to Oak Ridge National Laboratory Report, Proposed Guidance for Preparing and Reviewing a Molten Salt Non-Power Reactor Application, Washington, DC, November 18, 2020. (ML20251A008)
- 8. Oak Ridge National Laboratory, ORNL/TM-2020/1478, Proposed Guidance for Preparing and Reviewing a Molten Salt Non-Power Reactor Application, Washington, DC, July 2020.
- 9. NRC, Safety Guide 30, Quality Assurance Requirements for the Installation, Inspection and Testing of Instrumentation and Electric Equipment, Washington, DC, August 11, 1972.
- 10. NRC, RG 1.28, Revision 6, Quality Assurance Program Criteria (Design and Construction),
Washington, DC, September 2023. (ML23177A002) 1 Publicly available NRC published documents are available electronically through the NRC Library on the NRCs public website at http://www.nrc.gov/reading-rm/doc-collections/ and through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html. For problems with ADAMS, contact the Public Document Room staff at 301-415-4737 or (800) 397-4209, or email pdr.resource@nrc.gov. The NRC Public Document Room (PDR), where you may also examine and order copies of publicly available documents, is open by appointment. To make an appointment to visit the PDR, please send an email to PDR.Resource@nrc.gov or call 1-800-397-4209 or 301-415-4737, between 8 a.m. and 4 p.m. eastern time (ET), Monday through Friday, except Federal holidays.
2 Copies of Institute of Electrical and Electronics Engineers (IEEE) documents may be purchased from the Institute of Electrical and Electronics Engineers Service Center, 445 Hoes Lane, PO Box 1331, Piscataway, NJ 08855 or through the IEEEs public Web site at http://www.ieee.org/publications_standards/index.html.
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- 11. NRC, RG 1.33, Revision 3, Quality Assurance Program Requirements (Operation),
Washington, DC, June 2013. (ML13109A458)
- 12. NRC, Nuclear Regulatory Commission International Policy Statement, Federal Register, Vol. 79, No. 132, pp. 39415-39418, July 10, 2014.
- 13. NRC, Management Directive 6.6, Regulatory Guides, Washington, DC.
- 14. NRC, Management Directive 8.4, Management of Backfitting, Forward Fitting, Issue Finality, and Information Requests, Washington, DC, September 20, 2019.
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