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:
pable 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 have a combined capability, in conjunction with poison addition by the emergency core cooling system to reliably control reactivity changes to assure that under postulated accident conditions the capability to cool the core is maintained. 6. GDC 28, as it relates to reactivity limits such that reactivity control systems shall be designed with appropriate limits on the potential amount and rate of reactivity increase to assure that the effects of postulated reactivity accidents can neither result in damage to the reactor coolant boundary nor disturb the core and its supports structures to impair significant capability to cool the core. 4.6-5 Revision 2 - March 2007 7. GDC 29, as it relates to protecting system against anticipated operational occurrences such that the design of the protection and reactor control systems should assure an extremely high probability of accomplishing their safety functions in the event of anticipated operational occurrences. 8. 10 CFR 50.62(c)(3), as it relates to those requirements that impact the CRDS functional design. Specifically for BWRs, the alternate rod injection system must be diverse and independent (from the reactor trip system) and must have redundant scram air header exhaust valves. 9. 10 CFR 52.47(b)(1), which requires that a DC application contain the proposed inspections, tests, analyses, and acceptance criteria (ITAAC) that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, a plant that incorporates the design certification is built and will operate in accordance with the design certification, the provisions of the Atomic Energy Act, and the NRC's regulations; 10. 10 CFR 52.80(a), which requires that a COL application