Document: NUREG-0800
Document ID: 843fa920-b1b6-4712-bc03-1c4072c6b4f6
Document Type: srp
Title: through 7.9 reference these BTPs.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550074.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.2
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CFR Title: 

Content:
cance of a given system or aspect of a system's design under review. Probabilistic risk assessments (PRAs), such as those conducted under the Individual Plant Evaluation Program or required as part of applications under 10 CFR 52, "Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants," provide information that may prove helpful in determining the appropriate level of review. Regulatory Guide 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," provides specific guidance on the review of license amendment applications supported by risk information. SRP Chapter 19 provides additional guidance on reviewing applications supported by risk information. The scope of review should be coordinated with other review organizations, as discussed in subsection V below. The review should include consideration of material that is formally submitted for the docket and material that is available for audit at the applicant's site. Reviewers should be familiar with all sections of the SAR that have a bearing on the I&C systems under review. The following SAR chapters are typically relevant to the review of I&C systems. SAR Chapter Description 1 For familiarization with the general operation of the plant, both safety and non-safety aspects. 2 For familiarization with environmental conditions and natural phenomena hazards that could affect I&C systems. 3 Section 3.1. For exceptions to criteria applicable to I&C systems, and for structures suitable for housing this equipment. Sections 3.10 and 3.11. For an understanding of the seismic and environmental qualification program for I&C components. SAR Chapter Description 7.0-6 Revision 5 - March 2007 4, 5 For an understanding of the reactor and the reactor coolant system and its interconnections with the engineered safety feature (ESF) systems. 6 For the design bases, design features, and functional performance