Document: NRC Regulatory Guide
Document ID: acab976c-e936-49be-8c59-865767973599
Document Type: regulatory_guide
Title: Guidance for a Technology-Inclusive Content of Application Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2319/ML23194A194.pdf
Revision Date: 2023-09
Chapter: 
Section ID: RG-1.253
CFR Part: 
CFR Title: 

Content:
y through Friday, except Federal holidays. Publications from the Nuclear Energy Institute (NEI) are available at their Web site: http://www.nei.org/ or by contacting the headquarters at Nuclear Energy Institute, 1776 I Street NW, Washington DC 20006-3708; telephone: 202-739-800; fax 202-785-4019. Copies of American Society of Mechanical Engineers (ASME) standards may be purchased from ASME, Two Park Avenue, New York, NY 10016-5990; telephone (800) 843-2763. Purchase information is available through the ASME Web-based store at http://www.asme.org/Codes/Publications/. DG-1404, Revision 1, App. B, Page 21 B-10 NRC, “Policy Statement on the Regulation of Advanced Reactors,” Federal Register, Vol. 73, No. 199, October 14, 2008, pp. 60612–60616 (73 FR 60612). B-11 NRC, “Safety Goals for Operations of Nuclear Power Plants; Policy Statement; Republication,” Federal Register, Vol. 51, No. 162, August 21, 1986, pp. 30028-30033 (51 FR 30028). B-12 NRC, “Severe Reactor Accidents Regarding Future Designs and Existing Plants,” Federal Register, Vol. 50, No. 153, August 8, 1985, pp. 32138-32150 (50 FR 32138). B-13 NRC, “Use of Probabilistic Risk Assessment Methods in Nuclear Regulatory Activities,” Federal Register, Vol. 60, No. 158, August 16, 1995, pp. 42622-42629 (60 FR 42622). B-14 NRC, DANU-ISG-2022-07, “Risk-Informed Inservice Inspection/Inservice Testing Programs for Non-LWRs,” Washington, DC, May 2023. (ML22048B549) B-15 ASME, Boiler and Pressure Vessel Code, Section XI, “Rules for Inservice Inspection of Nuclear Power Plant Components,” Division 2, “Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants,” 2019 Edition, New York, NY, July 1, 2019. B-16 NRC, RG 1.246, “Acceptability of ASME Code, Section XI, Division 2, “Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Powers Plants”, for Non- Light-Water Reactors,” Washington, DC. B-17 NRC, DANU-ISG-2022-08,