Document: NUREG-0800
Document ID: 73a7c7ff-f0ac-467b-ba1d-0fb71e328868
Document Type: srp
Title: examines this margin to ensure that specified acceptable fuel design limits are not
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070705.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.2
CFR Part: 
CFR Title: 

Content:
ill be used by the staff when performing safety evaluations of license applications submitted by applicants pursuant to 10 CFR 50 or 10 CFR 52. Except in those 77 cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described 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.78 VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 10, "Reactor Design." 2. 10 CFR Part 50, Appendix A, General Design Criterion 15, "Reactor Coolant." 3. 10 CFR Part 50, Appendix A, General Design Criterion 17, “Electric Power Systems.”79 34. 10 CFR Part 50, Appendix A, General Design Criterion 26, "Reactivity Control System Redundancy and Capability." 45. Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants." 56. ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Power Plant Components," Article NB-7000, "Protection Against Overpressure," American Society of Mechanical Engineers. 15.3.1-11 DRAFT Rev. 2 - April 1996 67. "Standard Safety Analysis Report - BWR/6," General Electric Company, April 1973. 78. "Reference Safety Analysis Report - RESAR-3," Westinghouse Nuclear Energy Systems, November 1973. "Reference Safety Analysis Report - RESAR-41," Westinghouse Nuclear Energy Systems, October 1976. 89. "System 80 Standard Safety Analysis Report (CESSAR)," Combustion Engineering, Inc., August 1973. 910. "Standard Nuclear Steam System B-SAR-205," Babcock & Wilcox Company, February 1976. 110. ANSI N18.2, "Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants," American National Standards Institute (1974). 121. ANS Trial Use Standard N212, "Nuclear Safety Criteria for the Design of Stationary Boiling