Document: NUREG-0800
Document ID: 422f3de0-8599-4095-ba95-7882c43c82b9
Document Type: srp
Title: -
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1602/ML16029A367.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.2.1
CFR Part: 
CFR Title: 

Content:
leakage, rapidly propagating failure, and gross rupture is extremely low and (2) the RCPB design conditions are not exceeded during any condition of normal operation, including anticipated operational occurrences, consistent with the requirements of GDC 14 and 15. Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: The steam generators serve as the boundary between the primary and secondary sides of a pressurized-water reactor. As a result, they serve both as the RCPB and as the containment. Primary leakage into the secondary system could lead to the direct release of radioactivity to the environment. The steam generators are also relied on to perform safety functions such as removing decay heat (emergency core cooling) or supplying steam to engineered safety feature pumps. The components of the steam generator are divided into two classes. Class 1 includes material for those parts exposed to the primary (reactor) coolant, and Class 2 includes materials for parts exposed to the secondary coolant. Some plants elect to classify the pressure boundary portion of the steam generator that is exposed to secondary coolant (i.e., the SSPB) as Class 1. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. 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. 1. Selection, Processing, Testing, and Inspection of Materials The reviewer examines the materials selected and their specifications, as given in the safety analysis report (SAR) for Class 1 and Class 2 components of the steam generators, to determine