Document: NUREG-0800
Document ID: 5b0d8000-eb22-442c-a759-c14fed5c9c67
Document Type: srp
Title: EQUIPMENT AND FLOOR DRAINAGE SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070535.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.3.3
CFR Part: 
CFR Title: 

Content:
nd nonradioactive and the inadvertent transfer of radioactive wastes to the nonradioactive portion of the system could result in radioactive releases to the environs. Acceptance is based on the system being designed to prevent the inadvertent transfer of contaminated fluids to a non-contaminated drainage system for disposal. Technical Rationale39 9.3.3-5 DRAFT Rev. 3 - April 1996 The technical rationale for application of the above acceptance criteria to the equipment and floor drainage system is discussed in the following paragraphs. 1. GDC 2 requires that SSCs important to safety be designed to withstand the effects of natural phenomena such as earthquakes, tornadoes, hurricanes, and floods without loss of capability to perform their safety functions. The safety-related functions of the EFDS have both active and passive aspects, e.g., preventing flooding by means of components such as check valves, and also providing adequate drainage capacity to accommodate unplanned water intrusion in plant areas where SSCs important to safety are located. In regard to performance of the EFDS during the SSE, both direct and indirect safety impacts are attributed to the EFDS. Direct effects to safety-related equipment due to inundation have to be averted by the EFDS by providing adequate drainage capacity. Additionally, nonsafety-related equipment has to be protected if failure of such equipment may, in a consequential manner, reduce the functional reliability of safety- related equipment to unacceptable safety levels, or if equipment would be affected, the failure of which may cause incapacitating injury to occupants of the control room or render the control room uninhabitable. Regulatory Guide 1.29 describes a methodology acceptable to the staff for identifying and classifying those features of light-water cooled nuclear power plants that should be designed to withstand the effects of the SSE. With the information provided in Regulatory Guide 1.29, safety-related plant areas