Document: NUREG-0800
Document ID: 78c093cc-6cc4-4fac-aea2-087f774d42c3
Document Type: srp
Title: CONTROL ROD DRIVE STRUCTURAL MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070414.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.5.1
CFR Part: 
CFR Title: 

Content:
cant has met the guidelines of Regulatory Guide 1.85 by usingused materials of construction that are approved for use to in accordance with the acceptable ASME code cases described in Regulatory Guide 1.85 or that have otherwise been demonstrated acceptable for the application.57 In addition, the controls imposed upon the austenitic stainless steel of the mechanisms conform to the recommendations of Regulatory Guide 1.31, "Control of Ferrite Content in Stainless Steel Weld Metal," Regulatory Guide 1.37, regulatory position C.5, and 58 Regulatory Guide 1.44, "Control of the Use of Sensitized Stainless Steel.," and the related criteria described in SRP Section 5.2.3, "Reactor Coolant Pressure Boundary Materials." All materials selected for application in the control rod drive mechanism 59 component are or will be in conformance with the applicable code case listed in Regulatory Guide 1.85, "Code Case Applicability ASME Section III Materials." 60 Fabrication and heat treatment practices performed in accordance with these recommendations provide added assurance that stress corrosion cracking will not occur during the design life of the component. The compatibility of all materials used in the control rod system in contact with the reactor coolant satisfies the criteria of Articles NB-2160 and NB-3120 of Section III, Division 1 of the Code. Both martensitic and 61 precipitation-hardening stainless steels have been given tempering or aging treatments in accordance with staff positions. Cleaning and cleanliness control are in accordance with ANSI Standard N 45.2.1-1973, "Cleaning of Fluid Systems and Associated Components During Construction Phase of Nuclear Power Plants," and Regulatory Guide 1.37, 62 "Quality Assurance Requirements for Cleaning Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants."63 For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report