Document: NUREG-0800
Document ID: 77e928bd-5fcf-425f-b8c0-85215a64682f
Document Type: srp
Title: INTERNALLY-GENERATED MISSILES (INSIDE CONTAINMENT)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0703/ML070380167.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.5.1.2
CFR Part: 
CFR Title: 

Content:
is SRP section is discussed in the following paragraphs: 1. 10 CFR Part 50, Appendix A, GDC 4 establishes requirements for the ability of SSCs important to safety to be protected from dynamic effects, including the effects of internally-generated missiles. Equipment inside the containment like pressurized components, high-energy piping, and rotating equipment all have a potential for generating credible missiles. An internally-generated missile has a dynamic effect and its impact on SSCs important to safety must be evaluated to ensure that they are protected adequately and will be capable of performing their safety functions. Protecting SSCs important to safety from the adverse effects of internally-generated missiles prevents both failure of systems required for safe shutdown of the reactor facility and significant uncontrolled release of radioactivity. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. These review procedures are based on the identified SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. 3.5.1.2-5 Revision 3 - March 2007 The review procedures below are used during the review to determine whether the design criteria and bases and the design in the SAR meets the acceptance criteria in subsection II of this SRP section. 1. The first objective in the review of SSCs requiring protection against internally-generated missiles is to determine whether the equipment is needed to perform a safety function. Some structures and systems are designed as safety-related in their entirety, others have safety-related portions, and others are not needed for safety. To determine the safety category, the SSCs are evaluated for their functions in achieving safe reactor