Document: NUREG-0800
Document ID: bf62536e-58c7-4cb0-a51f-5c5ce2c21d6b
Document Type: srp
Title: DRAFT Rev. 2 - April
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070423.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.2.9
CFR Part: 
CFR Title: 

Content:
1996 5.3.1-20 tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.116 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. This SRP section will be used by the staff when performing safety evaluations of license applications submitted by applicants pursuant to 10 CFR 50 or 10 CFR 52. Except in those 117 cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section.118 Implementation schedules for conformance to parts of the methods discussed herein are contained in the referenced regulations and regulatory guides. Acceptable repairs and 119 upgrades are described in the referenced Generic Letter for previously accepted materials and welds that do not meet NUREG-0313, Revision 2 recommendations related to material specifications and post-weld treatments for stress corrosion cracking resistant installations. NUREG-0313, Revision 2 recommendations for stress corrosion cracking resistant installations will be used by the staff for evaluation of reactor vessel attachments and appurtenences in new BWR applications.120 VI. REFERENCES 1. 10 CFR Part 50, Section 50.55a, "Codes and Standards." 121 2. 10 CFR 50.60, "Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation."122 3. 10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events."123 24. 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear