Document: NUREG-0800
Document ID: 2bca792d-0e88-4e2d-b437-be572ed57a48
Document Type: srp
Title: REVIEW OF TRANSIENT AND ACCIDENT ANALYSIS METHODS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0708/ML070820123.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0.2
CFR Part: 
CFR Title: 

Content:
lephone at (301) 415-4737 or (800) 397-4205, by fax at (301) 415-3548, and by email to PDR@nrc.gov. 5 Nuclear Engineering and Design is available for electronic download (by free subscription) through Science Direct, a service of the Reed Elsevier Group, at http://www.sciencedirect.com/science?_ob=JournalURL&_cdi=5756&_auth=y&_acct=C000050221&_version=1&_url Version=0&_userid=10&md5=5bc1bb0de40acc1a7b0e4129b21d809f. 6 Copies are available on the public Web site maintained by the OECD Nuclear Energy Agency, at http://www.nea.fr/html/nsd/docs/1996/csni-r1996-17.pdf. 7 Electronic copies are available on the public Web site maintained by the OECD Nuclear Energy Agency, at http://www.nea.fr/html/nsd/docs/1987/csni87-132.pdf. 15.0.2-20 March 2007 2. USNRC, “Transient and Accident Analysis Methods,” Regulatory Guide 1.203, December 2005.2 3. NRC Office Instruction No. LIC-101, “Licence Amendment Review Procedures.”3 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, USNRC, December 1989.4 5. B.E. Boyack, et al., “Quantifying Reactor Safety Margins,” six papers in Nuclear Engineering and Design, Vol. 119, No. 1, May 1990.5 6. “Compendium of ECCS Research for Realistic LOCA Analysis,” NUREG-1230, December 1988.4 7. “Separate Effects Test Matrix for Thermal-Hydraulic Code Validation,” Committee on the Safety of Nuclear Installations, NEA/CSNI/R(93)14, September 1993.6 8. “Integral Test Facility Validation Matrix for the Assessment of Thermal-Hydraulic Codes for LWR LOCA and Transients,” Committee on the Safety of Nuclear Installations, NEA/CSNI/R(96)17, July 1996. 9. “CSNI Code Validation Matrix of Thermo-Hydraulic Codes for LWR LOCA and Transients,” Committee on the Safety of Nuclear Installations, CSNI Report 132, March 1987.7 10. USNRC, “Best-Estimate Calculations of Emergency Core Cooling