Document: NUREG-0800
Document ID: aa1c1ded-ea20-4e56-972b-84806f488df7
Document Type: srp
Title: RELIABILITY ASSURANCE PROGRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1235/ML12354A592.pdf
Revision Date: 2023-06
Chapter: 17
Section ID: 17.4
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of RAP, the different stages of RAP, and the RAP information to be included in an application for new reactor and provides guidance for developing an effective RAP. The acceptance criteria and review process presented in this SRP section is developed primarily from the guidance contained in SECY-95-132. The acceptance criteria for the methodology that is used to identify the RAP SSCs is developed from guidance in SECY-95-132 and SRP Section 19.0. III. REVIEW PROCEDURES The staff will select material from the procedures described below, as may be appropriate for a particular case. For review of a DC or COL application, the staff should use the following procedures to verify that the RAP set forth in the application meets the acceptance criteria identified in Subsection II of this SRP section. For review of a COL application, the scope of the review is dependent on whether the COL applicant references a DC. These review procedures are based on the identified SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II of this SRP section. The staff should verify that the RAP set forth in the application meets the acceptance criteria identified in Subsection II of this SRP section. The staff should also consider the appropriateness of the identified COL action items. The staff may identify additional COL action items; however, to ensure these COL action items are addressed during a COL application, they should be added to the DCD. The staff should document any NRC audits or inspections performed in audit/inspection reports so that they may be referenced in the staff's Safety Evaluation Report (SER). For additional information, the staff should consider the information provided in Section 17.4 of previous SERs for advanced reactors. Through the review of information