Document: NUREG-0800
Document ID: 42f941d3-4815-4bc5-bf81-f2dab04a7aa7
Document Type: srp
Title: SECONDARY CONTAINMENT FUNCTIONAL DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070459.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.3
CFR Part: 
CFR Title: 

Content:
s intended to provided 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 64 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.65 6.2.3-11 DRAFT Rev. 3 - April 1996 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides. VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and MissileDynamic Effects Design Bases." 66 2. 10 CFR Part 50, Appendix A, General Design Criterion 16, "Containment Design." 3. 10 CFR Part 50, Appendix A, General Design Criterion 43, "Testing of Containment Atmosphere Cleanup Systems." 4. 10 CFR Part 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water- Cooled Power Reactors."67 5. Regulatory Guide 1.52, "Design, Testing, and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants."68 56. Branch Technical Position CSB 6-3, "Determination of Bypass Leakage Paths in Dual 69 Containment Plants," attached to this SRP section. 67. Branch Technical Position CSB 6-1, "Minimum Containment Pressure Model for PWR 70 ECCS Performance Evaluation," attached to SRP Section 6.2.1.5. 8. NUREG/CR-0255 (TREE-1279), "CONTEMPT-LT/028: A Computer Code for Predicting Containment Pressure-Temperature Response to a Loss-of-Coolant Accident," EG&G Idaho, Inc. for the U.S. Nuclear Regulatory Commission,