License Renewal Documents: Difference between revisions
en>Monica Hurley (Created page with "{{DISPLAYTITLE:License Renewal Documents}} The following documents are the most commonly used documents in the United States for license renewal. Some of the documents mentioned in this section can be used for initial license renewal as well as subsequent license renewal. ===[https://www.nrc.gov/reading-rm/doc-collections/cfr/part054/index.html 10 CFR Part 54, “Requirements for Renewal of Operating Licenses for Nuclear Power Plants”]=== LTO_Regulatory_and_Guidance...") |
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Revision as of 19:12, 4 October 2024
The following documents are the most commonly used documents in the United States for license renewal. Some of the documents mentioned in this section can be used for initial license renewal as well as subsequent license renewal.
10 CFR Part 54, “Requirements for Renewal of Operating Licenses for Nuclear Power Plants”[edit]
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This part of 10 CFR governs the issuance of renewed operating licenses and renewed combined licenses for nuclear power plants licensed pursuant to Sections 103 or 104b of the Atomic Energy Act of 1954, as amended, and Title II of the Energy Reorganization Act of 1974 (88 Stat. 1242).
RG 1.188, “Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses”, Revision 2, 2020[edit]
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This regulatory guide sets instructions for format and content of an application to renew or subsequently renew an NRC-issued operating license in accordance with 10 CFR 54. This regulatory guide endorses NEI 95-10, Rev. 6, for initial license renewal and NEI 17-01 for subsequent license renewal development of license renewal applications.
NUREG-0933, “Resolution of Generic Safety Issues", Supplement 35, 2021[edit]
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This report presents the resolution of generic safety issues related to nuclear power plants to assist in the timely and efficient allocation of NRC resources for the resolution of those safety issues that have a significant potential for reducing risk.
NUREG-1800, “Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (SRP-LR)”, Revision 2, 2010[edit]
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The (SRP-LR) provides guidance to the NRC staff reviewers in performing safety reviews of initial applications to renew nuclear power plant licenses in accordance with 10 CFR 54. The purpose of the SRP-LR is to assure the quality and uniformity of staff safety reviews. It also makes information about regulatory matters widely available and improves communication between the NRC, interested members of the public, and the nuclear power industry.
NUREG-1801, “Generic Aging Lessons Learned (GALL) Report”, Revision 2, 2010[edit]
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The GALL report contains the NRC’s generic evaluation of the existing plant programs and presents the technical basis for determining where existing programs are adequate without modification and where existing programs should be augmented for the period of extended operation (PEO) . The GALL report also contains recommendations on specific areas for which existing programs should be augmented for initial license renewal.
RIS-07-16, “Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses”, Revision 1, 2010[edit]
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The NRC issued this revised regulatory issue summary (RIS) to clarify guidance for holders of renewed licenses on implementing the requirements of 10 CFR 54.37(b), regarding newly identified systems, structures, and components (SSCs) and information required to be included in final safety analysis report (FSAR) updates. Under the revised process, the NRC evaluates each license renewal interim staff guidance (LR-ISG) to determine whether it includes SSCs subject to the provisions of 10 CFR 54.37(b), and documentation of this determination is included in the LR-ISG.
IP 71111.21N-04, “Age Related Degradation”, 2023[edit]
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The purpose of this US NRC inspection procedure (IP) is to cover age related degradation in both active and passive components, and address gaps and recommendations originally identified by the working group.
LR-ISG-2011-05, “Ongoing Review of Operating Experience”[edit]
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This LR Interim Staff Guidance (LR-ISG) revises the US NRC’s acceptance criteria and review procedures to better address the ongoing review of operating experience within the SRP-LR. This LR-ISG also better aligns NUREG-1801 with the SRP-LR by incorporating the recommendation for ongoing review of operating experience into each of the program descriptions in Chapter X, “ Time-Limited Aging Analyses Evaluation of Aging Management Programs under 10 CFR 54.21(c)(1)(iii),” and Chapter XI, “ Aging Management Programs (AMPs).” This LR-ISG also provides a framework to ensure that license renewal applicants’ operating experience review activities will adequately address operating experience concerning age-related degradation and aging management during the term of the renewed license.
NUREG-1437, “Generic Environmental Impact Statement for License Renewal of Nuclear Plants ”, Revision 1, 2013[edit]
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The purpose of the Generic Environmental Impact Statement (GEIS) report is to determine the potential environmental impacts that could occur as a result of renewing licenses of individual nuclear power plants under 10 CFR Part 54. This GEIS revision identifies 78 environmental impact issues for consideration in license renewal environmental reviews, 59 of which have been determined to be generic to all plant sites. The GEIS also discusses a range of reasonable alternatives to the proposed action (initial license renewal), which would be analyzed in detail in plant-specific supplements to the GEIS. The plant-specific supplemental information is submitted by the utility as part of a license renewal application.
NOTE: US NRC is preparing Revision 2 to this NUREG to address both initial and subsequent license renewal. This revision is expected to be published in 2024.
RG 4.2, “Preparation Of Environmental Reports for Nuclear Power Stations ”, Revision 3, 2018[edit]
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This regulatory guide (RG) provides guidance to applicants for the format and content of environmental reports (ERs) that are submitted as part of an application for a permit, license, or other authorization to site, construct, and/or operate a new nuclear power plant. This RG references “RG 4.2, Supplement 1” for guidance on license renewal applications.
RG 4.2S1, “Supplement 1 to Regulatory Guide 4.2, Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications”, Revision 1, 2013[edit]
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This RG supplement provides guidance on the format and content of an environmental report to be submitted as part of a license renewal application.
NUREG-1555, “Standard Review Plans for Environmental Reviews for Nuclear Power Plants: Environmental Standard Review Plan”, Revision 1, 2013[edit]
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This document provides guidance to the US NRC staff in implementing provisions of 10 CFR 51, "Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions" related to reactor operating license renewals.
NEI 95-10, “Industry Guideline for Implementing Requirements of 10 CFR 54 - The License Renewal Rule”, Revision 6 , 2005[edit]
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This guideline is endorsed by US NRC in RG 1.188 and provides an acceptable approach for implementing the requirements of the license renewal rule (10 CFR Part 54) for initial license renewal applications. The process outlined in this guideline is based on industry experience in implementing the license renewal rule.
NEI 14-12, “Aging Management Program Effectiveness”, Revision 1 , 2020[edit]
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This guideline provides a standard approach for the self-assessment process for periodically evaluating the effectiveness of aging management programs (AMPs) as committed to and described in the UFSAR for plants with a renewed license to ensure on-going program effectiveness and to provide documentation of information useful for subsequent license renewal (SLR) applications.
NEI 14-13, “Use of Industry Operating Experience for Age-Related Degradation and Aging Management Programs”, Revision 2, 2022[edit]
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This guideline provides additional guidance to the nuclear industry on screening and evaluation of plant specific and industry operating experience (OE) for license renewal AMPs. It also provides an industry approach for the review and sharing of OE pertaining to age-related degradation of passive, long-lived components to promote effective AMPs across the industry.
EPRI 1010639, “Non‑Class 1 Mechanical Implementation Guideline and Mechanical Tools”, Revision 4, 2006[edit]
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This report presents a set of ‘Mechanical Tools’ that utilities can use to determine which aging effects are applicable to non-Class 1 mechanical components.
EPRI 1013475, “Plant Support Engineering: License Renewal Electrical Handbook”, 2007[edit]
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This report presents a process that can be used by applicants in determining which aging effects are applicable to electrical components and how they can be managed.
EPRI 1015078, “Plant Support Engineering: Aging Effects for Structures and Structural Components (Structural Tools)”, 2007[edit]
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This report identifies structures and structural components subject to aging management review (AMR) for generic pressurized water reactor (PWR) and boiling water reactor (BWR) nuclear plants. The report also describes aging mechanisms that might impact each component.
Record of Revisions[edit]
| Number | Date | Description of Changes |
|---|---|---|
| 0 | 6/11/2024 | Initial version |