Subsequent License Renewal Documents
The license renewal documents mentioned in this section were particularly created for guidance on subsequence license renewal in the United States.
NUREG-2191, “Generic Aging Lessons for Subsequent License Renewal (GALL-SLR) Report, Volumes 1 and 2, Revision 0, 2017[edit]
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The GALL-SLR report provides the technical basis for the SRP for SLR. The report contains the staff's generic evaluation of the existing plant programs and documents the technical basis for determining where existing programs are adequate without modification and where existing programs should be augmented for the subsequent 60-to-80 year period of operation. The GALL reports also contain recommendations on specific areas for which existing programs should be augmented for license renewal.
NUREG-2192, “Standard Review Plan for Review of Subsequent License Renewal Applications for Nuclear Power Plants”, Revision 0, 2017[edit]
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The SRP-SLR assures quality and uniformity of staff reviews and presents a well-defined base from which to evaluate a licensee's application.
NEI 17-01, “Industry guidelines for Implementing the Requirements of 10 CFR Part 54 for SLR”, 2017[edit]
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This guideline is endorsed by US NRC in RG 1.188 and provides an approach for implementing the requirements of the License Renewal Rule (10 CFR Part 54) for SLR. The process outlined in this guideline is based on industry experience in implementing the Rule for initial license renewal and on the lessons learned from that industry experience that can be applied to SLR.
NEI 17-04, “Model SLR New and Significant Assessment Approach for SAMA", Revision 1, 2019[edit]
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This document provides a model approach for assessing the significance of new information of which the applicant for renewal of a nuclear power reactor operating license or extension of a combined license is aware that relates to either (1) the severe accident mitigation design alternatives (SAMDA) analysis or severe accident mitigation alternatives (SAMA) analysis documented in the US NRC’s final environmental statement that supported issuance pursuant to 10 CFR Part 50 (or Part 54) of the reactor’s initial (or renewed) operating license, or (2) the SAMDA analysis documented in the US NRC’s final environmental statement that supported issuance pursuant to 10 CFR Part 52 of the reactor’s combined license and the design certification incorporated therein by reference, if any.
EPRI 3002010401, “Long‑Term Operations: Subsequent License Renewal Electrical Handbook”, 2018[edit]
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This report provides guidance for determining the aging effects of electrical components that are in-scope for SLR and solutions for managing aging effects during the PEO. The report is a useful supplement to NEI 17-01 and the International Atomic Energy Agency’s International Generic Aging Lessons Learned report. It is also a companion to other license renewal guidelines issued by EPRI for aging management and SLR.
EPRI 3002011822, “Long‑Term Operations: Subsequent License Renewal Non‑Class 1 Mechanical Implementation Guideline and Mechanical Tools”, 2018[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 3002013084, “Long-Term Operations: Subsequent License Renewal Aging Effects for Structures and Structural Components (Structural Tools)”, 2018[edit]
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This report identifies structures and structural components subject to AMR for generic PWR and 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 |