Document: NRC Regulatory Guide
Document ID: 70415715-297f-4d60-841c-514b0372a131
Document Type: regulatory_guide
Title: 02/2017 (Rev. 5)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1608/ML16082A501.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.26
CFR Part: 
CFR Title: 

Content:
ry on the NRC’s public Web site at http://www.nrc.gov/reading-rm/doc-collections/. The documents can also be viewed on-line for free or printed for a fee in the NRC’s Public Document Room (PDR) at 11555 Rockville Pike, Rockville, MD; the mailing address is USNRC PDR, Washington, DC 20555; telephone (301) 415-4737 or (800) 397-4209; fax (301) 415 3548; and e-mail pdr.resource@nrc.gov. 10 Copies of ASME standards may be purchased from ASME, Two Park Avenue, New York, New York 10016-5990; Telephone (800) 843-2763. Purchase information is available through the ASME Web site store at http://www.asme.org/Codes/Publications/. 11 All Federal Register notices listed herein were issued by the U.S. Nuclear Regulatory Commission. Copies are available for inspection or copying for a fee from the NRC’s Public Document Room at 11555 Rockville Pike, Rockville, MD; the PDR’s mailing address is USNRC PDR, Washington, DC 20555; telephone (301) 415-4737 or (800) 397-4209; email PDR@nrc.gov. 12 Copies of ANSI standards may be purchased from ANSI, 1819 L Street, NW., Washington, DC 20036, on their Web site at http://webstore.ansi.org/; telephone (202) 293-8020; fax (202) 293-9287; or e-mail storemanager@ansi.org. RG 1.26, Rev. 5, Page 13 10. Nuclear Energy Institute (NEI) 00-04, “10 CFR 50.69 SSC Categorization Guideline,” Washington, DC, July 2005.13 11. International Atomic Energy Agency (IAEA) SSG-30, “Safety Classification of Structures, Systems, and Components in Nuclear Power Plants,” Vienna, Austria, 2014.14 12. NRC, RG 1.3, “Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Boiling-Water Reactors,” Washington, DC. 13. NRC, RG 1.4, “Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Pressurized-Water Reactors,” Washington, DC. 14. ASME Boiler and Pressure Vessel Code, Section VIII, Division 1, “Rules for Construction of Pressure Vessels,” New