Document: NUREG-0800
Document ID: 16922d4c-3f36-4add-8a31-0ec35a44f030
Document Type: srp
Title: REACTOR COOLANT SYSTEM HIGH POINT VENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070770005.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.12
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CFR Title: 

Content:
cable regulatory guides, branch technical positions, and industry standards [identify each document and describe how the applicant has implemented each]. For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. In addition, to the extent that the review is not discussed in other SER sections, the findings will summarize the staff's evaluation of the ITAAC, including design acceptance criteria, as applicable. 5.4.12-10 Revision 1 - March 2007 V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. The referenced regulations, regulatory guides, and NUREGs contain implementation schedules for conformance to parts of the method discussed in this section. VI. REFERENCES 1. 10 CFR 50.34, “Contents of Applications; Technical Information.” 2. 10 CFR 50.44, “Standards for Combustible Gas Control System in Light-Water-Cooled Power Reactors.” 3. 10 CFR 50.46, “Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors.” 4. 10 CFR 50.46a, “Acceptance Criteria for Reactor Coolant Venting Systems.” 5. 10 CFR 50.49, “Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants.” 6. 10 CFR 50.55a, “Codes and Standards.” 7. 10 CFR Part 50, Appendix A, General Design Criterion