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
CFR Part: 
CFR Title: 

Content:
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 1989.1 5. B.E. Boyack et al., “Quantifying Reactor Safety Margins,” six papers in Nuclear Engineering and Design, Vol. 119, No. 1, May 1990. 6. “Compendium of ECCS Research for Realistic LOCA Analysis,” NUREG-1230, December 1988.1 7. “Separate Effects Test Matrix for Thermal-Hydraulic Code Validation,” Committee on the Safety of Nuclear Installations, NEA/CSNI/R(93)14, September 1993.3 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 1987.3 10. USNRC, “Best-Estimate Calculations of Emergency Core Cooling System Performance,” Regulatory Guide 1.157, May 1989.2 21 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 1994.1