Document: NUREG-0800
Document ID: ff35052f-d051-4098-a352-1e382f87365a
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340655.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
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CFR Title: 

Content:
of mechanical components and their supports is coordinated and performed by the Mechanical Engineering Branch (MEB), as part of its primary review responsibility under SRP Section 3.9. The Mechanical Engineering Branch (MEB) will review the seismic design and quality group classification of systems and components as part of its primary review responsibility under SRP Section 3.2. The fission product removal capability of the ice condenser is evaluated by the Accident Evaluation Branch (AEB), as part of its primary review responsibility under SRP Section 6.5. The review of proposed technical specifications at the operating license stage of review, pertaining to the surveillance requirements for steam bypass area, return air fan system operability, ice condenser operability, and vacuum relief devices is performed by the Licensing Guidance Branch (LGB) as part of its primary review responsibility under SRP Section 16.0. For those areas of review identified above as being reviewed as part of the primary review responsibility of other branches, the acceptance criteria necessary for the review and their methods of application are contained in the referenced SRP section of the corresponding primary branch. II. ACCEPTANCE CRITERIA CSB acceptance criteria are based on meeting the following regulations: 1. General Design Criterion (GDC) 16, as it relates to the reactor containment and associated systems being designed to assure that containment design conditions important to safety are not exceeded for as long as postulated accident conditions require. Since the primary reactor containment is the final barrier of the defense-in-depth concept to protect against the uncontrolled release of radioactivity to the environs, preserving containment integrity under the dynamic conditions imposed by postulated loss-of-coolant accidents is essential. 2. General Design Criterion 50, as it relates to the reactor containment structure and associated heat removal system(s) being designed