Document: NUREG-0800
Document ID: 543267f3-bba8-4db3-95f5-8d9b48d477b7
Document Type: srp
Title: -4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1233/ML12334A360.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.3
CFR Part: 
CFR Title: 

Content:
Draft Revision 3 – June 2013 5. Verification that the applicant has identified and addressed piping connected to the RCS that is subject to thermally stratified flow, thermal striping, and/or thermal cyclic effects, for residual heat removal and emergency core cooling systems is performed under SRP Sections 5.4.7 and 6.3. 6. Review of programs for ensuring bolting and threaded fastener adequacy and integrity is performed under SRP Section 3.13. The U.S. Nuclear Regulatory Commission (NRC) staff review of the applicant’s provisions for the functional qualification and operational readiness of pumps, valves, and snubbers is performed under SRP Section 3.9.6. 7. The specific acceptance criteria and review procedures are contained in that referenced SRP section. 8. Review of stiff pipe clamp designs described in Generic Issue (GI)-89 is performed under SRP Section 3.12. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. 10 CFR 50.55a and 10 CFR Part 50, Appendix A, GDC 1 as they relate to structures and components being designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. 2. GDC 2 and 10 CFR Part 50, Appendix S, as they relate to structures and components important to safety being designed to withstand the effects of earthquakes without loss of capability to perform their safety functions. 3. GDC 4 as it relates to structures and components important to safety being designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including lost-of-coolant accidents. 4. GDC 14 as it relates to the RCPB being designed, fabricated, erected, and tested so as to have an extremely low probability of abnormal leakage, of rapidly propagating failure, and of gross rupture. 5. GDC 15 as it