Document: NUREG-0800
Document ID: 848ab24d-ac9b-4ec5-85ff-099e13b769c3
Document Type: srp
Title: CONTAINMENT SPRAY AS A FISSION PRODUCT CLEANUP SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0601/ML060150001.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.5.2
CFR Part: 
CFR Title: 

Content:
certification and combined license 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 the ITAAC, and as applicable, design acceptance criteria (DAC), interface | requirements, and combined license action items relevant to this SRP section. | V. IMPLEMENTATION The following guidance is for applicants and licensees concerning the staff’s plans for using this SRP section. The staff will use this SRP section in performing safety evaluations of design certifications and | license applications submitted by applicants pursuant to 10 CFR Parts 50 or 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 docketed 6 months or more | after the date of issuance of this SRP section. | VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 41, “Containment Atmosphere Cleanup.” 2. 10 CFR Part 50, Appendix A, General Design Criterion 42, “Inspection of Containment Atmosphere Cleanup Systems.” 6.5.2-15 Rev. 3 - December 2005 3. 10 CFR Part 50, Appendix A, General Design Criterion 43, “Testing of Containment Atmosphere Cleanup Systems.” 4. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.3, “Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Boiling Water Reactors.” 5. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.4, “Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Pressurized Water Reactors.” 6. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.183, “Alternate Radiological | Source Terms for Design Basis Accidents at Nuclear Power Reactors.”