Document: NUREG-0800
Document ID: 2717fe7f-71fd-4f1e-bd08-7685b24763ba
Document Type: srp
Title: Standard Review Plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff responsible for th
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0301/ML030160606.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15
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Content:
ent rates from the U.S. Government Printing Office, P.O. Box 37082, Washington, DC 20402-9328 (telephone (202)512-1800); or from the National Technical Information Service by writing NTIS at 5285 Port Royal Road, Springfield, VA 22161; (telephone (703)487-4650). Copies are available for inspection or copying for a fee from the NRC 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; fax (301)415-3548; email is PDR@NRC.GOV. 2 Single copies of regulatory guides, both active and draft, and draft NUREG documents may be obtained free of charge by writing the Reproduction and Distribution Services Section, OCIO, USNRC, Washington, DC 20555-0001, or by fax to (301)415-2289, or by email to <DISTRIBUTION@NRC.GOV>. Copies of certain guides and many other NRC documents are available electronically on the internet at NRC’s home page at <WWW.NRC.GOV> in the Reference Library. Documents are also available through the Public Electronic Reading Room (NRC’s ADAMS document system, or PERR) at the same web site. 3 Copies are available at <http://www.nea.fr/html/nsd/reports/csnirepindex.html> . 20 VII. REFERENCES 1. NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,” June 1987. (Certain updated sections are available from NRC.)1 2. USNRC, “Transient and Accident Analysis Methods,” Draft Regulatory Guide DG- 1120, October 2002.2 3. NRC Office Instruction No. LIC-101, “Licence Amendment Review Procedures,” March 27, 2002. (Electronic copies are available under ADAMS Accession Number ML020660141 in NRC’s Public Electronic Reading Room, which can be accessed through the NRC’s web site, <WWW.NRC.GOV> .) 4. B.E. Boyak et al., “Quantifying Reactor Safety Margins: Application of Code Scaling, Applicability, and Uncertainty Evaluation Methodology to a Large-Break, Loss-of-Coolant Accident,” NUREG/CR-5249,