Document: NUREG-0800
Document ID: 2adccc8f-d828-4baf-b696-6ee4f776837b
Document Type: srp
Title: REACTOR INTERNAL AND CORE SUPPORT MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070416.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.5.2
CFR Part: 
CFR Title: 

Content:
e materials will not deteriorate in service. Acceptable heat treatment temperatures are aging at 565 C - 595 C (1050 F - 1100 F) for Type 17-4 PH and tempering at 565 C (1050 F) for Type 410 stainless 43 44 steel. Other materials shall have similar appropriate heat treat and fabrication controls in accordance with strength and compatibility requirements. Technical Rationale45 The technical rationale for application of the above acceptance criteria to the reactor internals and core support structures materials is discussed in the following paragraph: GDC 1 and 10 CFR 50.55a require that structures, systems, and components (SSCs) be designed, fabricated, erected, constructed, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed. 10 CFR 50.55a also incorporates by reference the applicable editions and addenda of the ASME Boiler and Pressure Vessel Code. The reactor internals and core support structures include SSCs that perform safety functions and/or whose failure could affect the performance of safety functions by other SSCs. These safety functions include reactivity monitoring and control, core cooling, and fission product confinement (within both the fuel cladding and the primary reactor coolant system). Application of 10 CFR 50.55a and GDC 1 to the materials of construction provides assurance that established standard practices of proven or demonstrated effectiveness for selecting materials, fabrication, and testing/inspection of SSCs are used to achieve a high likelihood that these safety functions will be performed. III. REVIEW PROCEDURES The reviewer will select and emphasize material from the procedures described below, as may be appropriate for a particular case. For the areas of review described in subsection I of this SRP section, the review procedures isare as follows:46 1. Material Specifications The list of the materials of construction of the components offor the reactor internals that are