Document: NUREG-0800
Document ID: 042bc5c0-5de0-44b4-9599-6c131e20eb7a
Document Type: srp
Title: FUNCTIONAL DESIGN OF CONTROL ROD DRIVE SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070413.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.6
CFR Part: 
CFR Title: 

Content:
nt has met the requirements of GDC 4 with respect to the design of the system against the adverse effects of missiles hazards inside the containment, pipe whipping and jets caused by broken pipes, and adverse environmental conditions DRAFT Rev. 2 - April 1996 4.6-10 resulting from high and moderate energy pipe breaks during normal plant operations, anticipated operations occurrences, and accident conditions.71 21. The applicant has met the requirements of General Design Criterion 23 by demonstrating the ability to insert the control rods upon any failure of the drive mechanism or any induced failure by an outside force (such as loss of electric power, instrumentation air, fire, radiation, extreme heat, pressure, cold, water, steam, etc.). 32. The applicant has met the requirements of General Design Criterion 25 by assuring that no fuel design limits are exceeded for any single malfunction or rod withdrawal accident. 43. The applicant has met the requirement of General Design Criterion 26 by demonstrating the ability to control reactivity changes to assure that, under normal operation and anticipated operational occurrences with the appropriate margin for malfunction (such as stuck rods), no fuel design limits are exceeded and the reactor can be maintained subcritical under cold conditions. 54. The applicant has met the requirements of General Design Criterion 27 by demonstrating the ability to reliably control reactivity changes under accident conditions to assure that no fuel design limits are exceeded and the reactor can be maintained subcritical under cold conditions. 65. The applicant has met the requirements of General Design Criterion 28 by demonstrating the ability to reliably control the amount and rate of reactivity change to assure that no reactivity accident will damage the reactor coolant pressure boundary or disturb the core or the core's appurtenances such as to impair coolant flow. The postulated reactivity accidents include rod ejection, rod drop,