Document: NUREG-0800
Document ID: f58c1aee-14cf-4909-b99e-6a9548723b23
Document Type: srp
Title: ASME CODE CLASS 1, 2, AND 3 PIPING SYSTEMS, PIPING COMPONENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1233/ML12334A376.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.12
CFR Part: 
CFR Title: 

Content:
te compliance with applicable code limits. In addition, the applicant should describe a monitoring program to verify that the extent of thermal stratification, thermal striping, and piping deflections remain consistent with the design and results in no adverse consequences.. 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 Section 2 “Staff Recommendations on Response Combinations” of NUREG-1061, Volume 4 are applicable for independent support motion analysis. 3.12-11 Draft Revision 1 - June 2013 xiv. Operating Basis Earthquake as a Design Load In SECY-93-087, “Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (ALWR) Designs,” dated April 2, 1993, the staff discussed eliminating the operating-basis earthquake (OBE) from the design bases when the OBE is established at less than or equal to one third of the safe-shutdown earthquake (SSE). In the associated Staff Requirements Memorandum (SRM) dated July 21, 1993, the Commission approved the staff’s recommendations associated with eliminating the OBE in piping and support analyses. An example of the implementation of this Commission policy is provided in NUREG-1503, “Final Safety Evaluation Report Related to the Certification of the Advanced Boiling Water Reactor Design,” Section 3.1.1.2. Appendix S to 10 CFR Part 50, “Earthquake Engineering Criteria for Nuclear Power Plants,” first issued in 1996