Document: NUREG-0800
Document ID: 87477809-7581-4701-b6f2-91410029e1c8
Document Type: srp
Title: MAIN STEAM SUPPLY SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0703/ML070380206.pdf
Revision Date: 2023-06
Chapter: 10
Section ID: 10.3
CFR Part: 
CFR Title: 

Content:
ia. 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. The NRC staff uses the procedures below during a construction permit (CP) review to determine whether the design criteria and bases and the preliminary design in the preliminary safety analysis report (SAR) meet the acceptance criteria in Subsection II of this SRP section. For review of operating license (OL) applications, the procedures verify that the initial design criteria and bases have been appropriately implemented in the final design in the final SAR. The procedures for OL applications include a determination that the content and intent of the applicant’s technical specifications agree with the requirements for system testing, minimum performance, and surveillance, developed as a result of the technical specification review, as indicated in Subsection I of this SRP section. 10.3-9 Revision 4 - March 2007 The review procedures below are written for typical MSSSs for both direct- and indirect-cycle plants. The reviewer will select and emphasize material from this SRP section, as appropriate for a particular case. 1. Significant differences distinguish the design of the MSSS for an indirect-cycle (PWR) plant from that for a direct-cycle (BWR) plant. Furthermore, different portions of the MSSS are safety related in different plant designs, although the safety functions of the system are much the same in all PWR and BWR plants. The first step in the review of the MSSS is to determine those portions that are designed to perform a safety function. For this purpose, a system evaluation determines the components and subsystems necessary for achieving safe reactor shutdown under all conditions or for performing accident prevention or mitigation functions. 2. The reviewer determines that essential (safety-related) portions of