Document: NUREG-0800
Document ID: 643ab154-682e-480f-a57b-a5fd7390a34e
Document Type: srp
Title: REVIEW OF TRANSIENT AND ACCIDENT ANALYSIS METHODS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0535/ML053550265.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0.2
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CFR Title: 

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tions, NEA/CSNI/R(93)14, September 1993.6 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. 15.0.2-22 Initial Issuance - December 2005 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 System Performance,” Regulatory Guide 1.157, May 1989.2 11. W. Wulff, et al., “Uncertainty Analysis of Suppression Pool Heating During an ATWS in a BWR-5 Plant: An Application of the CSAU Methodology Using the BNL Engineering Plant Analyzer,” NUREG/CR-6200, USNRC, March 1994.4 Paperwork Reduction Act Statement The information collections contained in the Standard Review Plan are covered by the requirements of 10 CFR Part 50, which were approved by the Office of Management and Budget (OMB), approval number 3150-0011. Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement, unless the requesting document displays a currently valid OMB control number.