Document: NUREG-0800
Document ID: 9c7116dd-39cd-47a9-b121-dce6f51adc77
Document Type: srp
Title: SUBCOMPARTMENT ANALYSIS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070620009.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.1.2
CFR Part: 
CFR Title: 

Content:
s (referred to as COL license information in certain DCs) included in the referenced DC. Additionally, a COL applicant must address requirements and restrictions (e.g., interface requirements and site parameters) included in the referenced DC. Review Interfaces Other SRP sections interface with this section as follows: 1. Review of the various types and aspects of the containment design are identified in SRP Section 6.2.1. 2. Review of the break locations and dynamic effects of postulated pipe ruptures and the mechanical design of movable and stationary devices provided for vent flow control in containment subcompartments is performed under SRP Section 3.6.2. 6.2.1.2-3 Revision 3 - March 2007 3. Review of those applications that propose to exclude dynamic effects of pipe ruptures, including localized pressurization effects and loads on component supports, is performed under SRP Section 3.6.3. 4. Review of the structural design of movable and stationary devices provided for vent flow control in containment subcompartments is performed under SRP Section 3.8.3. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. General Design Criterion (GDC) 4, as it relates to the design of containment internal compartments to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant accidents. The containment internal compartments shall be appropriately protected against dynamic effects, including the effects of missiles, pipe whipping, and discharging fluids, that may result from equipment failures and from events and conditions outside the nuclear power unit. 2. GDC 50, as it relates to the design of the containment internal compartments to ensure that the