Document: NUREG-0800
Document ID: 9d63483b-6755-4ab1-bdfb-675160dd5454
Document Type: srp
Title: CONDENSATE STORAGE FACILITIES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070521.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.2.6
CFR Part: 
CFR Title: 

Content:
le:44 The technical rationale for application of the above acceptance criteria to the Condensate Storage Facilities is discussed in the following paragraphs: 1. GDC 2 requires that nuclear power plant structures, systems and components important to safety be designed to withstand the effects of seismic events and other natural phenomena without loss of capability to perform their safety functions. The subject structures, systems and components are those necessary to ensure: (1) the integrity of the reactor coolant pressure boundary; (2) the capability to shutdown the reactor and maintain it in a safe shutdown condition; or (3) the capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposures comparable to DRAFT Rev. 3 - April 1996 9.2.6-6 the guideline exposures of 10 CFR Part 100. When the plant design includes the CSF as a source of cooling water to prevent or mitigate the consequences of accidents, those portions of the CSF which provide or interface with a system that provides a means of shutting down the reactor and maintaining it in a safe shutdown condition must be capable of withstanding the effects of natural phenomena. Meeting the requirements of GDC 2 provides assurance that adequate reactor cooling will be available in the event of an accident, thus preventing offsite exposures in excess of 10 CFR Part 100. 2. GDC 5 prohibits the sharing of structures, systems and components among nuclear power plant units unless it can be shown that such sharing will not significantly impair their ability to perform their safety functions, including, in the event of an accident in one unit, an orderly shutdown and cooldown of the remaining units. The condensate storage facility provides a source of water for decay heat removal from the reactor core in those plants where the design includes this system for support to the plant in its response to an accident. Meeting the requirements of GDC 5 provides assurance that