Document: NUREG-0800
Document ID: 4a46b35d-2e81-4517-9716-154b19f57049
Document Type: srp
Title: REACTOR COOLANT PRESSURE BOUNDARY MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190006.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.3
CFR Part: 
CFR Title: 

Content:
cifications listed in the Code, Sections II, Part D, acceptable material Code Cases as identified in Regulatory Guide 1.84, staff positions on BWR materials described in Attachment A to Generic Letter 88-01, and/or the recommendations of NUREG-0313, Revision 2, as stated in the acceptance criteria. Exceptions to the material specifications of the Code 5.2.3-15 Revision 3 - March 2007 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 primary reviewer takes exception to the 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. Alloy 600 and associated weld materials, Alloy 82 and 182) are susceptible to stress corrosion cracking as documented in NUREG-1823 and NRC Generic Letter 97-01. The NRC Order EA-03-009 was issued to provide interim inspection requirements for reactor pressure vessel heads (including penetration nozzles) at pressurized water reactors. Alloy 690 and associated weld materials Alloy 52 and 152 have improved corrosion resistance in comparison to Alloy 600 used in PWR RCPB applications. Where nickel- chromium-iron alloys are proposed for use in the PWR RCPB, use of Alloy 690 materials is preferred. If use of Alloy 600 materials is proposed, 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). In addition the reviewer verifies that acceptable augmented inspection requirements have been proposed based on operating experience and service