Document: NUREG-0800
Document ID: b8e96856-10d6-4a01-99ff-6618d335e774
Document Type: srp
Title: 15.3.2.-4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550010.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.1
CFR Part: 
CFR Title: 

Content:
Revision 2 - March 2007 4. 10 CFR 50, Appendix A, GDC 17 as to onsite and offsite electric power systems so structures, systems, and components (SSCs) important to safety function during normal operation, including AOOs. The safety function for each power system (assuming the other system is not functioning) must be to provide sufficient capacity and capability so SAFDLs and design conditions of the reactor coolant pressure boundary are not exceeded during AOOs. 5. 10 CFR 50, Appendix A, GDC 26 as to the reliable control of reactivity changes so SAFDLs are not exceeded, including during AOOs. This control is accomplished by accounting for appropriate margin for malfunctions (e.g., stuck rods). SRP Acceptance Criteria Specific SRP acceptance criteria acceptable to meet the relevant requirements of the NRC’s regulations identified above are as follows for the review described in this SRP section. The SRP is not a substitute for the NRC’s regulations, and compliance with it is not required. However, an applicant is required to identify differences between the design features, analytical techniques, and procedural measures proposed for its facility and the SRP acceptance criteria and evaluate how the proposed alternatives to the SRP acceptance criteria provide acceptable methods of compliance with the NRC regulations. The basic objectives of the review of loss of forced reactor coolant flow transients are to identify the most limiting transients and to verify whether, for the most limiting transients, the plant response to the loss of flow transients satisfies fuel damage and system pressure criteria. The following specific criteria are necessary to meet the regulatory requirements for incidents of moderate frequency: 1. Pressure in the reactor coolant and main steam systems should be maintained below 110 percent of the design values. 2. Fuel-cladding integrity must be maintained by the minimum DNBR remaining above the 95 percent probability/95 percent confidence