Document: NUREG-0800
Document ID: 92c0723c-167f-4101-b17a-ff7f705327f0
Document Type: srp
Title: AUXILIARY AND RADWASTE AREA VENTILATION SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350560.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.4.3
CFR Part: 
CFR Title: 

Content:
esign Criterion 5, "Sharing of Structures, Systems, and Components," as related to shared systems and components important to safety. 3. General Design Criterion 60, "Control of Release of Radioactive Materials to the Environment," as related to the capability of the system to suitably control release of gaseous radioactive effluents to the environment. Accep- tance is based on meeting the guidance of Regulatory Guide 1.140, as related to design, testing, and maintenance criteria for normal ventilation exhaust system, air filtration, and adsorption units of light-water-cooled nuclear power plants, Positions C.1 and C.2. III. REVIEW PROCEDURES The 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 procedures are utilized 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 procedures for OL reviews include a determi- nation that the content and intent of the technical specifications prepared by the applicant are in agreement with the requirements for system testing, minimum performance, and surveillance developed as a result of the staff's review. The primary reviewer will coordinate this review with areas of responsibility assigned to other branches as stated in subsection I. The primary reviewer obtains and uses such inputs as required to assure that this review procedure is complete. As a result of various ARAVS designs proposed by applicants, there will be variations in system requirements. For the purpose of this SRP section, a typical system is assumed which has fully redundant subsystems, each having an identical essential (safety features) portion. For cases where there are variations from this