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:
and prevention, and fabrication and processing of RCPB ferritic and austenitic stainless steel materials. It should be noted that ROCs 799, 800, and 805 are similar to those referenced above and have been processed in the proposed draft revision of SRP Section 5.2.3. It should also be noted that reviews of austenitic stainless steels using criteria and procedures "similar" to those of SRP Section 5.2.3 are already included in SRP Section 4.5.1. SRP Draft Section 4.5.1 Attachment A - Proposed Changes in Order of Occurrence Item Source Description DRAFT Rev. 3 - April 1996 4.5.1-12 11. Integrated Impacts 282, 303, and Added a Review Interface reflecting that portions of the 331; Potential Impacts 21391, control rod drive system which are attachments or 25342, and 25343 appurtenances of the reactor vessel are reviewed against criteria for reactor vessel materials, including criteria for reactor vessel material specifications, compatibility with environmental conditions, fracture toughness and prevention, and fabrication and processing of reactor vessel ferritic and austenitic stainless steel materials. It should be noted that Generic Letter 88-01 applies to BWR "reactor vessel attachments and appurtenances." ROCs 812, 815, and 816 are similar to those referenced above and recommend addition of Generic Letter 88-01 and NUREG-0313, Revision 2 as criteria for review of BWR reactor vessel austenitic stainless steel materials in the draft revision of SRP Section 5.3.1. 12. Potential Impacts 22224 and 25349, Added Review Interfaces reflecting review of reactor Editorial coolant chemistry specifications and controls (separately for BWRs and PWRs) as they relate to determining compatibility with control rod drive structural materials to be exposed to reactor coolant (see specific acceptance criterion II.3). 13. Current PRB names and Editorial change made to reflect current SRP Section abbreviations