Document: NUREG-0800
Document ID: 8a69e211-8100-413b-aa05-61dd44b10160
Document Type: srp
Title: REVIEW RESPONSIBILITIES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350115.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.4
CFR Part: 
CFR Title: 

Content:
en met since the maximum pressure within the reactor coolant and main steam systems did not exceed 110% of the design pressures. 4. The applicant has met the requirements of GDC 26 with respect to the capability of the reactivity control system to provide adequate con- trol of reactivity during this event while including appropriate margins for stuck rods since the specified acceptable fuel design limits were not exceeded. 5. The applicant has met the requirements of II.E.5.1 and II.E.5.2 by properly accounting for all design modifications in the analysis that has been made as a result of resolution of this item. 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. 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,"West nghouse 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