Document: NUREG-0800
Document ID: 145ec0f9-012b-4669-9627-ed1b1d0cce95
Document Type: srp
Title: THERMAL AND HYDRAULIC DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070412.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
CFR Part: 
CFR Title: 

Content:
w is not discussed in other safety evaluation report sections, the staff's evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.101 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plan for using this SRP section. This SRP section will 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 102 cases 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.103 The provisions of specific criterion II.10 apply to reviews for all new BWR applications.104 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides and, NUREGs, and Generic Letters . 105 VI. REFERENCES 1. 10 CFR 50.34(f), "Additional TMI-related requirements," paragraph 10 CFR 50.34(f)(2)(xviii).106 2. 10 CFR 50.62, "Requirements for Reduction of Risk from Anticipated Transients Without Scram (ATWS) events for light-water-cooled nuclear power plants."107 DRAFT Rev. 2 - April 1996 4.4-14 13. 10 CFR Part 50, Appendix A, General Design Criterion 10, "Reactor Design." 108 4. 10 CFR Part 50, Appendix A, General Design Criterion 12, "Suppression of Reactor Power Oscillations."109 155. Regulatory Guide No. 1.68, "Preoperational and Initial Startup Test Programs for Water-Cooled Nuclear Power Reactors Plants."110 166. Regulatory Guide 1.133, "Loose Parts Detection Program for the