Document: NUREG-0800
Document ID: 9738c583-ac33-4836-b8f1-580dc98eb7f0
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF THE FAILURE OF SMALL LINES CARRYING
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350147.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.2
CFR Part: 
CFR Title: 

Content:
documents are made available to the public as part of the Commission's policy to Inform the nuclear Industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them is not required. The standard review plan sections are keyed to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants. Not all sections of the Standard Format have a corresponding review plan. Published standard review plans will be revised periodically, as appropriate, to accommodate comments and to reflect new informa- tion and experience. Comments and suggestions for improvement will be considered and should be sent to the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation. Washington. D.C. 205. 6. A comparison of the doses calculated by the applicant and by the staff with appropriate exposure guidelines of 10 CFR Part 100, §100.11 (Ref. 3), as stated in subsection II below. In addition, AEB will coordinate its review with other branches that interface in the overall review of the break analysis. The Reactor Systems Branch-(RSB) upon request by the AEB will confirm the value used by the applicant for the mass of coolant released in the accident and to determine if this accident will cause fuel failures. The Containment Systems Branch (CSB) upon request by the AEB, will verify that secondary containment integrity and leaktightness are maintained during the course of the accident. II. ACCEPTANCE CRITERIA The acceptance criteria for this SRP section are based on the relevant requirements of the following regulations: 1. General Design Criterion 55 (Ref. 1) as it relates to the identification of small diameter lines connected to the primary system that are exempted from the isolation requirements of GDC 55 and that are acceptable on the basis of meeting item (2) below, 2. 10 CFR Part 100, §100.11 (Ref. 3) as it relates to the