Document: NUREG-0800
Document ID: 9ef26e18-47a9-41fc-84a0-1b3184d69ad4
Document Type: srp
Title: SITE PROXIMITY MISSILES (EXCEPT AIRCRAFT)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070377.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.5.1.5
CFR Part: 
CFR Title: 

Content:
ss of those given in 10 CFR Part 100 will not be exceeded. The remaining safety-related structures, systems, and componentsSSC , although 28 vulnerable to the potential effects of identified missiles, have a sufficiently low probability (within the criteria given in SRP Section 2.2.3) of unacceptable damage (on the basis of considerations such as low strike probability, or adequate separation and redundancy) such that the risk of public exposure is low and in conformance with 10 CFR Part 100, §100.10. For design certification 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 inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.29 V. IMPLEMENTATION The following is intended to provide 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 30 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.31 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides. VI. REFERENCES 1. Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants."32 1. 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and Dynamic Effects Design