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:
tigue Evaluation for ASME Code Class 1 Piping The acceptance criteria in Section III of the ASME Code are applicable. viii. Fatigue Evaluation of ASME Code Class 2 and 3 Piping The acceptance criteria for provided in Section III of the ASME Code are applicable. ix. Thermal Oscillations in Piping Connected to the RCS The operating experience insights contained in NRC Bulletin (BL) 88-08 and supplements are applicable for the identification and evaluation of piping systems susceptible to thermal stratification, cycling, and striping. x. Thermal Stratification The operating experience insights contained in NRC BL 79-13 and BL 88-11 are applicable for the identification and evaluation of long runs of horizontal piping susceptible to thermal stratification. xi. Safety Relief Valve Design, Installation, and Testing The acceptance criteria provided in SRP Section 3.9.3, Subsection II.2 are applicable. xii. Functional Capability The acceptance criteria provided in NUREG-1367, “Functional Capability of Piping Systems,” may be used to ensure piping functionality under level D loading conditions. Alternative criteria will be reviewed on a case by case basis. xiii. Combination of Inertial and SAM Effects The acceptance criteria provided in SRP Section 3.9.2, Subsection II.2(G) are applicable for enveloped support motion analysis. The acceptance criteria provided in NUREG-1061, Volume 4 are applicable for independent support motion analysis. xiv. OBE as a Design Load Appendix S to 10 CFR Part 50, "Earthquake Engineering Criteria for Nuclear Power Plants," allows the use of operating basis earthquake ground motion. The criteria is provided in paragraph IV.(a)(2). The detail criteria for use of such an option was provided in NUREG-1503, “Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design, Section 3.1.1.2.” 1Regulatory Guide 1.207 was issued for comment July 2006. Regulatory Guide 1.207 is being developed concurrent with