Document: NUREG-0800
Document ID: ff5838f8-986a-4d8b-a039-fb26df280426
Document Type: srp
Title: – 15.5.2
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070725.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.5.1
CFR Part: 
CFR Title: 

Content:
t Related to the Certification of the Advanced Boiling Water Reactor Design." July 1994. Section 15.2, "Trip of All Reactor Internal Pumps and Pressure Regulator Down-Scale Failure."76 10. NUREG-1462, "Final Safety Evaluation Report (FSER) Related to the Certification of the Combustion Engineering (CE) System 80+ Design." August 1994.77 112. 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."78 4. Title 10 Code of Federal Regulations, Part 50, Revised January 1, 1980.79 512. "Standard Safety Analysis Report--BWR/6," General Electric Company, April 1973. 613. "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. 714. "System 80 Standard Safety Analysis Report (CESSAR)," Combustion Engineering, Inc., August 1973. 815. "Standard Nuclear Steam System B-SAR-205," Babcock & Wilcox Company, February 1974. 916. ANSI N18.2, "Nuclear Safety Criteria for the Design of Stationary Pressurized Water 80 Reactor Plants," American National Standards Institute (1974). 1017. ANS Trial Use Standard N212, "Nuclear Safety Criteria for the Design of Stationary 81 Boiling Water Reactor Plants," American Nuclear Society (1974). 11. General Design Criterion 10, "Reactor Design." 12. General Design Criterion 15, "Reactor Coolant System Design," DRAFT Rev. 2 - April 1996 15.5.1-12 13. General Design Criterion 26, "Reactivity Control System Redundancy and Capability." 14. Regulatory Guide 1.53, "Application of the Single-Failure Criterion to Nuclear Power Plant Protection