Document: NUREG-0800
Document ID: 25cb3efc-9642-430d-a72f-52decd59b34f
Document Type: srp
Title: INTRODUCTION - TRANSIENT AND ACCIDENT ANALYSES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070710376.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0
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CFR Title: 

Content:
capability of the reactor coolant makeup system. MCPR safety limit This limit ensures that during normal operation and during AOOs, at least 99.9 percent of the fuel rods in the core do not experience transition boiling. minimum critical power ratio (MCPR) The smallest CPR that exists in the core for each class of fuel. overpressurization The condition that occurs when pressure exceeds the design pressure of the component of interest by more than 10 percent, in accordance with the ASME Code. postulated accidents Unanticipated conditions of operation (i.e., not expected to occur during the life of the nuclear power unit). Postulated accidents are also known as Condition IV events. protection system The protection system shall be designed (1) to initiate automatically the operation of appropriate systems including the reactivity control systems, to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences and (2) to sense accident conditions and to initiate the operation of systems and components important to safety. (GDC 20) single failure An occurrence that results in a component’s loss of capability to perform its intended safety functions. VII. REFERENCES 1. Appendix A to 10 CFR Part 50, “General Design Criteria for Nuclear Plants.” 2. Regulatory Guide 1.70, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants.” 3. Regulatory Guide 1.206, “Combined License Applications for Nuclear Power Plants (LWR Edition).” 4. ANS 51.1, “Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants” (replaces ANSI N18.2), 1983 (withdrawn in 1998). 5. ANSI/ANS-52.1-1978, “Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants” (withdrawn in 1998). 15.0-16 Revision 3 - March 2007 6. 10 CFR 50.62, “Requirements for Reduction of Risk from Anticipated Transients Without Scram (ATWS) Events for Light-Water Cooled Nuclear