Document: NUREG-0800
Document ID: d8b522d4-dee5-4122-89d4-b2b45d0ca729
Document Type: srp
Title: REACTOR COOLANT PRESSURE BOUNDARY MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070420.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.3
CFR Part: 
CFR Title: 

Content:
to confine fission products, or interference with core cooling. III. REVIEW PROCEDURES The reviewer will select and emphasize material from the procedures described below, as may be appropriate for a particular case. 5.2.3-15 DRAFT Rev. 3 - April 1996 For each area of review described in subsection I of this SRP section, the following review procedures are followed: 1. Material Specifications The material specifications for each major pressure-retaining component or part used in the RCPB are compared with the acceptable specifications listed in the Code, Sections II and III, acceptable material Code Cases as identified in Regulatory Guide 1.85, staff positions on BWR materials described in Attachment A to Generic Letter 88-01, and/or the recommendations of NUREG-0313, as stated in the acceptance criteria. Exceptions 92 to the material specifications of the Code are clearly identified, and the basis evaluated. The reviewer judges the significance of the exceptions and, taking into account precedents set in earlier cases, determines the acceptability of the proposed exceptions. In those instances where the Materials Engineering BranchEMCB takes exception to the 93 use of a specific material or questions certain aspects of a specification, the applicant is advised which material is not acceptable, and for what reason. Operating experience has indicated that certain nickel-chromium-iron alloys (e.g. Inconel) are susceptible to cracking due to corrosion. Inconel 690 alloy has improved corrosion resistance in comparison to Inconel alloy 600 previously used in RCPB applications. Where nickel-chromium-iron alloys are proposed for use in the RCPB, the reviewer verifies that an acceptable technical basis is either identified (based upon demonstrated satisfactory use in similar applications) or presented by the applicant to support use of the material under the expected environmental conditions (e.g. exposure to the reactor coolant). Particular review emphasis is placed upon