Document: NUREG-0800
Document ID: 504a24fe-9056-495a-8541-0e278016ce80
Document Type: srp
Title: in that offsite AC power remains available to operate the station
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0703/ML070300702.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.6
CFR Part: 
CFR Title: 

Content:
d consequences of the transients. A. The sequence of events described in the SAR (or DCD) analysis is reviewed by the organization responsible for reactor systems in consultation with the organization responsible for instrumentation and control. The reactor systems reviewer concentrates on the assumptions for the reactor protection system, the engineered safety systems, and required operator actions to secure and maintain the reactor in a safe condition. B. The organization responsible for reactor systems reviews the analytical methods for whether all mathematical models and computer codes have been reviewed and accepted by the staff. If a referenced analytical method or code has not been reviewed, the reviewer requests a generic evaluation of the new analytical model or code by the appropriate code review organization. C. The results of the analyses are reviewed for whether predicted values of pertinent system parameters are within expected ranges for the type and class of reactor under review. The predicted results of the transient analyses then are reviewed for whether the consequences meet the acceptance criteria of subsection II of this SRP section. D. The organization responsible for reactor systems reviews the values of all parameters in the analytical models, including the initial conditions of the core and systems. In addition, this organization reviews core physics, fuel design, and core thermal-hydraulics data in the SAR (or DCD) analysis as part of its primary review responsibility for SAR sections corresponding to SRP Sections 4.2 through 4.4. Finally, the organization responsible for reactor systems reviews SAR (or DCD) Section 5.2.2 for adequacy of the overpressure protection of the reactor coolant pressure boundary (RCPB). 7. COL Action Items and Certification Requirements and Restrictions. For a DC application, the review will also address COL action items and requirements and restrictions (e.g., interface requirements and site parameters). For a