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:
al phenomena such as the safe- shutdown earthquake, the probable maximum flood, and the tornado missiles, is performed under SRP Sections 3.3.1, 3.3.2, 3.5.3, 3.7.1 through 3.7.4, 3.8.4, and 3.8.5. 7. Verification of the adequacy of the design, installation, inspection, and testing of all electrical systems (sensing, control, and power) required for proper operation is performed under SRP Section 7.1 and Appendix 7-A and SRP Section 8.3.1. 8. The evaluation of potential sources of internal flooding and, where applicable, determination that SSCs are adequately protected against the effects of internal flooding or can otherwise function in the event of such flooding, are performed under SRP Section 3.4.1. The evaluation of potential sources of internally generated missiles and, where applicable, determination that SSCs are adequately protected against the effects of such missiles are performed under SRP Sections 3.5.1.1 and 3.5.1.2. The verification of the adequacy of specified environments and service conditions for equipment qualification as they relate to the locations of affected equipment and the overall demonstration that systems and components are qualified to perform their function are performed under SRP Section 3.11. 9. Reviews of fire protection, technical specifications, and quality assurance and maintenance are performed under SRP Sections 9.5.1 and Chapters 16 and 17, respectively. 10. Review of the seismic qualification of Category I instrumentation and electrical equipment and the environmental qualification of electrical and mechanical equipment is performed under SRP Sections 3.10 and 3.11, respectively. 11. Review of the RFCS is performed under SRP Section 7.7. Review of reactor thermal- hydraulic systems in pressurized-water reactors is performed under 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