Document: NUREG-0800
Document ID: 5e3dbec9-a39f-4531-9eb9-705982190066
Document Type: srp
Title: REACTOR PRESSURE VESSEL INTERNALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1613/ML16134A059.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.5
CFR Part: 
CFR Title: 

Content:
uacy of the design fatigue curves for the reactor internals materials to account for cumulative service-related and environmental usage factor effects, and consideration of each combination of design, service, and postulated event loadings, is performed under SRP Section 3.9.3. 6. Evaluation of the adequacy of the mechanical, hydraulic, and electrical components of the control rod drive system, including the control rod drive elements, is performed under SRP Section 3.9.4. 3.9.5-5 Revision 4 – March 2017 7. Evaluation of the functional design and qualification of pumps, valves, and dynamic restraints, including the capability to withstand various vibration excitation mechanisms, is performed under SRP Section 3.9.6, “Functional Design, Qualification, and Inservice Testing Programs for Pumps, Valves, and Dynamic Restraints.” 8. Review of the adequacy of programs for assurance of integrity of bolting and threaded fasteners is performed under SRP Section 3.13, “Threaded Fasteners - ASME Code Class 1, 2, and 3.” 9. Verification of fuel system design, including fuel behavior effects on reactor core design under various normal and accident operating conditions, is performed under SRP Section 4.2, “Fuel System Design.” 10. Review of material aspects of reactor internals is performed under SRP Section 4.5.2, “Reactor Internal and Core Support Structure Materials.” The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. GDC 1 and 10 CFR 50.55a require that reactor internals be designed, fabricated, erected, tested, and inspected to quality standards commensurate with the importance of the safety functions performed. 2. GDC 2 requires that reactor internals be designed to withstand the effects of natural phenomena, such as earthquakes, combined with the effects of