Document: NUREG-0800
Document ID: 90914152-fc84-4413-a5f5-aa75efd21205
Document Type: srp
Title: TURBINE MISSILES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0636/ML063600395.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.5.1.3
CFR Part: 
CFR Title: 

Content:
t requirements of the following Commission regulations: 1. The NRC acceptance criteria is based on meeting the relevant requirements of General Design Criteria (GDC) 4, as it relates to SSCs important to safety being appropriately protected against environmental and dynamic effects, including the effects of missiles, that may result from equipment failure. Failure of large steam turbines in the main turbine generator has the potential to eject high-energy missiles that can produce such 3.5.1.3-3 Revision 3 - March 2007 damage. The staff's overall safety objective is to ensure that SSCs important to safety are adequately protected from the effects of turbine missiles. Accordingly, consideration should be given to safety-related systems (i.e., those SSCs necessary to perform required safety functions). The specific criteria necessary to meet the relevant requirements of GDC 4 to reduce the probability of turbine missile generation are as follows: A. The integrity of the reactor coolant pressure boundary; B. The capability to shut down and maintain the reactor in a safe condition; and C. The capability to prevent accidents that could result in potential offsite exposures, which represent a significant fraction of the guideline exposures specified in 10 CFR Part 100, "Reactor Site Criteria." Examples of safety-related systems that should be protected are described in the Appendix to Regulatory Guide (RG) 1.117, “Tornado Design Classification.” 2. 10 CFR 52.47(b)(1), which requires that a DC application contain the proposed inspections, tests, analyses, and acceptance criteria (ITAAC) that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, a plant that incorporates the design certification is built and will operate in accordance with the design certification, the provisions of the Atomic Energy Act, and the NRC's regulations; 3. 10 CFR 52.80(a), which requires that