Document: NUREG-0800
Document ID: 67e3fd64-e6a4-4522-b90f-4184c2f5b357
Document Type: srp
Title: FUNCTIONAL DESIGN OF CONTROL ROD DRIVE SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070540139.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.6
CFR Part: 
CFR Title: 

Content:
nder SRP Section 9.3.4. 4.6-4 Revision 2 - March 2007 12. For new BWR plant applicants, the CRDS (control rod drive pump) may be included in the systematic assessment of shutdown risks as an alternate feature that can provide core inventory makeup in the event of a loss of normal decay heat removal. The shutdown risk assessment reviews are performed under SRP Chapter 19. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. GDC 4 found in Appendix A to 10 CFR Part 50, as it relates to the structures, systems, and components important to safety that shall be designed to accommodate the effects of and to compatible with the environmental conditions during normal plant operation as well as during postulated accidents. 2. GDC 23, as it relates to the protection system failure modes such that the system shall fail into a safe state or into a state demonstrated to be acceptable on some other defined basis if conditions such as disconnection of system, loss of energy, or postulated adverse environment are experienced. 3. GDC 25, as it relates to the fuel design such that the specified limits are not exceeded for any single malfunction of the reactivity control system. 4. GDC 26, as it relates to the reactivity control system redundancy and capability such that two independent reactivity control systems of different design principles shall be provided and capable of reliably controlling reactivity changes under conditions of normal operation, including anticipated operational occurrences to assure acceptable fuel design limits are not exceeded. In addition, one of the systems must be capable of holding the reactor core subcritical under cold conditions. 5. GDC 27, as it relates to the combined reactivity control systems capability such that the reactivity control system design shall