Document: NUREG-0800
Document ID: 3a8a905e-fe11-43fd-ba6c-917507daa823
Document Type: srp
Title: COMPLIANCE WITH THE CODES AND STANDARDS RULE, 10 CFR §  50.55a
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070441.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.1.1
CFR Part: 
CFR Title: 

Content:
tent that the review is not discussed in other safety evaluation report sections, the staff’s evaluation of inspections, 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.61 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 62 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.63 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulation regarding use of Codes and Standards Rule, 10 CFR Section 64 65 50.55a, and the regulatory guide. VI. REFERENCES 21 . 10 CFR Section 50.55a, "Codes and Standards Rule." 66 67 68 5.2.1.1-7 DRAFT Rev. 3 - April 1996 12 . 10 CFR Part 50, Appendix A, General Design Criterion 1, "Quality Standards and 69 Records." 43 . Regulatory Guide 1.26, "Quality Group Classifications and Standards for Water-, Steam- 70 , and Radioactive-Waste-Containing Components of Nuclear Power Plants."71 34. ASME Boiler and Pressure Vessel Code, 1980 Edition, Section III, "Nuclear Power 72 Plant Components," American Society of Mechanical Engineers (1980).73 DRAFT Rev. 3 - April 1996 5.2.1.1-8 [This Page Intentionally Left Blank] SRP Draft Section 5.2.1.1 Attachment A - Proposed Changes in Order of Occurrence 5.2.1.1-9 DRAFT Rev. 3 -