Document: NUREG-0800
Document ID: 2c1e60ee-a3b4-4f26-8ebd-56dc7a8435b6
Document Type: srp
Title: THREADED FASTENERS ! ASME CODE CLASS 1, 2, AND
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550058.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.13
CFR Part: 
CFR Title: 

Content:
s to avoid contamination that could lead to SCC conform to the recommendations of RG 1.37. These controls satisfy the requirements of 10 CFR 50, Appendix B, Criterion XIII with respect to controls for cleaning of materials and components. 3.13-13 March 2007 6. The staff concludes that the applicant’s preservice and inservice program for threaded fasteners is acceptable and meets the criteria of ASME Code, Section XI and the requirements of 10 CFR 50.55a. For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. In addition, to the extent that the review is not discussed in other SER sections, the findings will summarize the staff's evaluation of the ITAAC, including design acceptance criteria, as applicable. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. ASME Boiler and Pressure Vessel Code, Sections II, III, and XI, 2001 Edition, American Society of Mechanical Engineers. 2. Regulatory Guide 1.37, “Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants,” March 1973. 3. Regulatory Guide 1.65, “Materials and Inspections for Reactor Vessel Closure Studs,” October 1973. 4. Regulatory Guide 1.84, “Design, Fabrication, and Materials Code Case