Document: NUREG-0800
Document ID: e1f233ab-8592-464a-9fdc-1a20ebe416a1
Document Type: srp
Title: PRESSURE SUPPRESSION POOL AS A FISSION PRODUCT CLEANUP SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070477.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.5.5
CFR Part: 
CFR Title: 

Content:
tance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.15 6.5.5-7 DRAFT Rev. 1 - April 1996 V. IMPLEMENTATION The following guidance is provided to applicants and licensees about the 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 16 those cases in which the applicant proposes an acceptable alternative method for complying with the specified portions of the Commission's regulations, the methods described herein are to 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.17 Implementation of the acceptance criteria of subsection II and the review procedures in subsection III is as follows: (1) Operating plants and applicants for operating licenses pending at the date of issue of this SRP section need not comply with the provisions of this SRP section, but may do so voluntarily. (2) Future applicants will be reviewed according to the provisions of this SRP section. 18 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." 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 1.52, "Design, Testing, and Maintenance Criteria for Postaccident