Document: NUREG-0800
Document ID: 91ccd6ba-6094-458e-842b-ff5e6b11f635
Document Type: srp
Title: INTERNALLY GENERATED MISSILES (OUTSIDE CONTAINMENT)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070370.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.5.1.1
CFR Part: 
CFR Title: 

Content:
tion of SSC important to safety from the effects of missiles is an appropriate safety consideration. Protecting those SSC that are important to safety from the effects of internally generated missiles ensures: the integrity of the reactor coolant pressure boundary; the capability to shutdown the reactor and maintain it in a shutdown condition; and the capability to prevent significant uncontrolled release of radioactivity. III. REVIEW PROCEDURES The review procedures set forth below are used during the construction permit (CP) application review to determine that the design criteria and bases and the preliminary design in applicant's preliminary safety analysis report meet the acceptance criteria given in subsection II of this SRP section. For the review of the operating license (OL) application, 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 reviews of the effects of internally generated missiles on structures are performed by SEBECGB as part of its primary responsibility for SRP Section 3.5.3. The objective in the 20 review of the reactor facility, structures, systems and componentsSSC , with regard to 21 protection requirements for internally generated missiles, is to identify the SSC that are 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 their safety category, the ASBSPLB evaluates the SSC with 22 regard to their function in achieving and maintaining a safe reactor shutdown condition or in preventing accidents or mitigating the consequences of such accidents. The single failure criterion