Document: NUREG-0800
Document ID: 15a004f9-6c99-4bc0-a858-efeaea553e8e
Document Type: srp
Title: REACTOR COOLANT SYSTEM HIGH POINT VENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070440.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.12
CFR Part: 
CFR Title: 

Content:
ry guides, branch technical positions, and industry standards [identify each document and describe how the applicant has implemented each]. DRAFT Rev. 1 - April 1996 5.4.12-10 For design certification reviews, the findings will also summarize, to the extent that the review 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.71 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans 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 72 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.73 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulations, regulatory guides and NUREGs. 74 VI. REFERENCES 75 1. 10 CFR 50.34, "Contents of Applications."76 2. 10 CFR 50.44, "Standards for Combustible Gas Control System in Light-Water-Cooled Power Reactors."77 31. 10 CFR Part 50, 50.46, "Acceptance Criteria for Emergency Core Cooling Systems 78 for Light Water Nuclear Power Reactors." 79 4. 10 CFR 50.49, "Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants."80 52. 10 CFR Part 50, 50.55a, "Codes and Standards." 81 63. 10 CFR Part 50, Appendix A, General Design Criterion 1,