Document: NUREG-0800
Document ID: 9415dfca-08ff-4096-a9d7-071357523a23
Document Type: srp
Title: 6
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350142.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.5.1
CFR Part: 
CFR Title: 

Content:
5Rev. 1 - July 1981 4. The applicant has met the requirements of GDC 26 with respect to the capability of the reactivity control system to provide adequate control of reactivity during this event while including appropriate margins for stuck rods since the specified acceptable fuel design limits were not exceeded. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. Except in those 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. 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. Title 10 Code of Federal Regulations, Part 50, Revised January 1, 1980. S. "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. 8. "Standard Nuclear Steam System B-SAR-205," Babcock & Wilcox Company, February 1974. 9.