Document: NUREG-0800
Document ID: 7b7303eb-a3a7-433b-8301-fcaba03194ea
Document Type: srp
Title: - 15.1.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070676.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.1
CFR Part: 
CFR Title: 

Content:
bed herein will be used by the staff in its evaluation of conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section.66 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides and NUREGS. VI. REFERENCES 1. Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants." 2. ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Power Plant Components." Article NB-7000, "Protection against Overpressure," American Society of Mechanical Engineers. 3. Standard Review Plan Section 4.2, "Fuel System Design." 4. 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities." 5. "Standard Safety Analysis Report - BWR/6," General Electric Company, April 1973. 6. "Reference Safety Analysis Report - RESAR-3,"Westinghouse Nuclear Energy Systems, November 1973; and "Reference Safety Analysis Report - RESAR-41," Westinghouse Nuclear Energy Systems, December 1973. "Reference Safety Analysis Report - RESAR-3S," Westinghouse Nuclear Energy Systems, July 1975; and "Reference Safety Analysis Report - RESAR-414," Westinghouse Nuclear Energy Systems, October 1976. 7. "System 80 Standard Safety Analysis Report (CESSAR)," Combustion Engineering, Inc., August 1973. The previously approved ODYN and REDY codes have been modified by GE for use ** in the analysis of limiting transients on the standard design Advanced Boiling Water Reactor (ABWR). These modified codes, ODYNA and REDYA, were reviewed by the NRC staff and have been approved for design analysis of the ABWR. DRAFT Rev. 2 - April 1996 15.1.1-12 8. "Standard Nuclear Steam System B-SAR-205," Babcock & Wilcox Company, February 1974. 9. General Design Criterion 10, "Reactor Design." 10. General Design Criterion 15, "Reactor Coolant System Design." 11. General Design Criterion 20,