Document: NUREG-0800
Document ID: 1e026b4f-5a81-43c8-9dd3-fef9bb4f9c3d
Document Type: srp
Title: INTERNALLY GENERATED MISSILES (INSIDE CONTAINMENT)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070372.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.5.1.2
CFR Part: 
CFR Title: 

Content:
nitiation of an internally generated missile is a dynamic effect and the impact of those missiles on SSC important to safety must be evaluated to ensure that the SSC important to safety are adequately protected and will be capable of performing their safety functions. Protecting those SSC that are important to safety from the adverse effects of internally generated missiles prevents failure of those systems required for safe shutdown of the reactor facility and prevents significant uncontrolled release of radioactivity. III. REVIEW PROCEDURES The review procedures below are used during the construction permit (CP) review to determine that the design criteria and bases and the preliminary design as set forth in the preliminary safety analysis report meet the acceptance criteria given in subsection II. For the review of operating license (OL) applications, the review procedures and acceptance criteria are used to verify that the initial design criteria and bases have been appropriately implemented in the final design as set forth in the final safety analysis report. The reviewer selects and emphasizes areas within the scope of this SRP section as may be appropriate in a particular case. The first objective in the review of the structures, systems, and componentsSSC, with regard to 22 protection requirements for 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 portions that are safety related, and others are classified as not needed for safety. In order to determine the safety category of the SSC, the RSBSRXB and 23 CSBSCSB upon request from the ASBSPLB , will evaluate the SSC with regard to their 24 25 function in achieving safe reactor shutdown conditions and preventing significant uncontrolled release of radioactivity or in preventing accidents or mitigating the consequences of accidents, 26 and will provide an input