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:
ge, it is not required for shutdown.) In addition, RSBSRXB reviews the operation of the RFCS to confirm that a malfunction or failure 19 of the system will not degrade the capabilities of plant safety systems or lead to plant conditions more severe than those considered in the accident analyses (e.g., by determining the effects of a failure of the system following a loss-of-coolant accident or steam line break). The RSBSRXB reviews the results of the most limiting transient 20 from a malfunction of the RFCS as part of its primary review responsibility for SRP Section 15.4.5. 2. As part of its primary review responsibility for SRP Section 4.3, the Core Performance Branch (CPB)SRXB verifies the reactivity control requirements. 21 22 3. Other reactivity control systems are reviewed by the SRXB as follows: The Auxiliary 23 Systems Branch (ASB)SRXB reviews the standby liquid control system (BWRs) as part 24 of its primary review responsibility for SRP Section 9.3.5. The Reactor Systems Branch (RSB)SRXB reviews the safety injection system as part of its primary review 25 responsibility for SRP Section 6.3. In addition, ASBSRXB will coordinate other branches' evaluations that interface with the 26 27 overall review of the control rod system as follows:.28 1. The Instrumentation and Controls Systems Branch (ICSBHICB) verifies the results of 29 failure modes and effects analyses to assure that a single failure occurring in the control rod system, or an operator error, will not result in the loss of capability for safe shutdown as part of its primary review responsibility for SRP Section 7.2. 2. The Mechanical Engineering Branch (EMEB) verifies the adequacy of the control rod 30 drive mechanisms to perform its mechanical function (e.g., rod insertion and withdrawal, scram operation and time) and to maintain the reactor coolant pressure boundary as part of its primary review responsibility for SRP Section 3.9.4. The EMEB verifies that the 31 design and requirements, as