Document: NUREG-0800
Document ID: 34798f4a-fe75-475a-b41f-ffb023158358
Document Type: srp
Title: 2.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070367.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.6.2.15
CFR Part: 
CFR Title: 

Content:
Evaluates the adequacy of analysis methods for seismic Category I reactor pressure vessel internals and system dynamic analysis, identification of design transients, and identification of service lifetime transient cyclic loadings to be reflected in the design and fatigue analyses of reactor pressure vessel internals, as part of its primary review responsibility for SRP Section 3.9.1.1617 3.9.5-3 DRAFT Rev. 3 - April 1996 3. Evaluates the adequacy of dynamic analyses and proposed flow-induced vibration testing for reactor pressure vessel internals as part of its primary review responsibility for SRP Section 3.9.2.18 4. Evaluates the adequacy of the design for structural integrity of the reactor pressure vessel internals, including the adequacy of design fatigue curves for reactor internals materials with respect to cumulative reactor service-related environmental and usage factor effects and consideration of each combination of design, service, and postulated event loadings, as part of its primary review responsibility for SRP Section 3.9.3.1920 5. Evaluates the adequacy of the mechanical design of the control rod drive system (CRDS), including the control rod drive elements, as part of its primary review responsibility for SRP Section 3.9.4.21 In addition, the EMEB will coordinate other branches' evaluations that interface with the 22 overall review of the reactor internals as follows: 1. The Core Performance Branch (CPB)Reactor Systems Branch (SRXB) will verify fuel 23 system design, including fuel behavior effects toon reactor core design under various 24 normal and accident operating conditions in SRP Section 4.2. 2. The Materials and Chemical Engineering Branch (MTEBEMCB) will review material 25 aspects of reactor internals in SRP Section 4.5.2. The EMCB evaluates the adequacy of analyses justifying exclusion of certain postulated pipe ruptures from design bases in SRP Section 3.6.3 (proposed). The EMCB also reviews the adequacy of programs for 26 assuring the