Document: NUREG-0800
Document ID: 61ddad5b-f914-4192-b39f-6f00ffa2e3c5
Document Type: srp
Title: REACTOR INTERNAL AND CORE SUPPORT STRUCTURE MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190005.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.5.2
CFR Part: 
CFR Title: 

Content:
nhibitors) as it relates to corrosion control and compatibility with materials to be exposed to reactor coolant is performed under SRP Sections 5.4.8 “Reactor Water Cleanup System (BWR)” and 9.3.4 “Chemical and Volume Control System (PWR).” 4. The review of the adequacy of design fatigue curves for reactor internals and core support structures materials with respect to cumulative reactor service-related environmental and usage factor effects and consideration of each combination of loadings is performed under SRP Sections 3.9.1, “Special Topics for Mechanical Components,” and 3.9.3, “ASME Code Class 1, 2, and 3 Components, Component Supports, and Core Support Structures.” 5. The review of the reactor internals and core support structures with respect to their mechanical design adequacy to withstand design and service loading combinations is performed under SRP Section 3.9.5, “Reactor Pressure Vessel Internals.” 6. The review of the plant design, including the selection of materials to minimize activation products, to verify that occupational radiation exposures will be as low as is reasonably achievable (ALARA) is performed under SRP Section 12.1, “Assuring That Occupational Radiation Exposures Are As Low As Is Reasonably Achievable.” The specific acceptance criteria and review procedures are contained in the reference SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 4.5.2-4 Revision 3 - March 2007 The design, fabrication, and testing of the materials used in the reactor internals and core support structures are reviewed and evaluated to meet codes and standards commensurate with the safety functions to be performed such that the relevant requirements of 10 CFR 50.55a and GDC 1 are met. 1. 10 CFR 50.55a, "Codes and Standards,” which requires that SSCs shall be designed, fabricated, erected, constructed, tested, and inspected to