Document: NUREG-0800
Document ID: 93a26deb-9fac-4f56-a0c6-8addc960a55b
Document Type: srp
Title: ASME CODE CLASS 1, 2, AND 3 PIPING SYSTEMS, PIPING COMPONENTS AND
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0700/ML070040002.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.12
CFR Part: 
CFR Title: 

Content:
items (referred to as COL license information in certain DCs) included in the referenced DC. Additionally, a COL applicant must address requirements and restrictions (e.g., interface requirements and site parameters) included in the referenced DC. Review Interfaces Other SRP sections interface with this section as follows: 1. Evaluation Seismic System Analysis is performed under SRP Sectin 3.7.2. 2. Evaluation of the seismic cyclic ground input loading and the seismic cyclic loading used for fatigue analysis for components and supports is performed under SRP Section 3.7.3. 3. Evaluation of the seismic design loading for seismic Category I structures is performed under SRP Sections 3.8.1-3.8.5. 3.12-5 March 2007 4. Verification of the adequacy of the computer programs used in the analyses is performed under SRP Section 3.9.1. 5 Verification of the dynamic testing and analysis of systems, components, and equipment is performed under SRP Section 3.9.2. 6. Evaluation of the adequacy of the design of ASME Code, Class 1, 2, and 3 components, component supports, and core support structures is performed under SRP Section 3.9.3. 7. Evaluation of the design criteria for pressure-relieving devices, operability of pumps, and valves that have an active function during and after a faulted plant condition is performed under SRP Section 3.10. 8. Verification of the adequacy of the program for the integrity of bolting and threaded fasteners is performed under SRP Section 3.13. 9. Verification of the Compliance with the Codes and Standards Rule 10 CFR 50.55a is performed under SRP Section 5.2.1. 10. Evaluation of the number and size of valves specified for the Reactor Coolant Pressure Boundary (RCPB) and their pressure-relieving capacity is performed under SRP Section 5.2.2. 11. Evaluation of the design of systems and components that interface with the Reactor Coolant System (RCS) with regard to ISLOCA is performed under SRP Sections 5.4.7 and 6.3. 12. Evaluation of the process used