Document: NUREG-0800
Document ID: bcc615f1-3f65-4757-994f-88cc8fe800d5
Document Type: srp
Title: should still be met.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070473.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.5.1
CFR Part: 
CFR Title: 

Content:
rtions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. Implementation of the acceptance criteria in 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 revision 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. 42 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.43 VI. REFERENCES DRAFT Rev. 3 - April 1996 6.5.2-16 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." 64. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.3, "Assumptions Used for 44 Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Boiling Water Reactors." 75. 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. NUREG-1465 (draft for comment), "Accident Source Terms for Light- Water Nuclear Power Plants," June 1992.45 7. J. J. DiNunno, F. D. Anderson, R. E. Baker, and R. L. Waterfield, "Calculation of Distance Factors for Power and Test Reactor Sites," TID-14844, USAEC, March 23, 1962.46 138. A. K. Postma, R. R. Sherry, and P. S. Tam, Technological Bases for Models of Spray Washout of Airborne Contaminants in Containment Vessel, U.S. Nuclear Regulatory Commission Report, NUREG/CR-0009, October 1978. 179. J. T. Bell, D. O. Campbell,