Document: NUREG-0800
Document ID: 34798f4a-fe75-475a-b41f-ffb023158358
Document Type: srp
Title: 2.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070367.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.6.2.15
CFR Part: 
CFR Title: 

Content:
for the piping.32 4. General Design Criteria 10, as it relates to reactor internals, requires that reactor internals shall be designed with adequate margins to assure specified acceptable fuel design limits are not exceeded during anticipated normal operational occurrences.appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.33 Specific criteria necessary to meet the relevant requirements of the regulations identified above are as follows: a. Requirements for loads, loading combinations, and limits applicable to those portions of reactor internals constructed to Subsection NG of the ASME Code are presented in SRP Section 3.9.3 (Ref. 7) . 34 b. The design and construction of the core support structures should conform to the requirements of Subsection NG, "Core Support Structures," of the ASME Code (Ref. 5) , and SRP Section 3.9.3. 35 c. The design criteria, loading conditions, and analyses that provide the basis for the design of reactor internals other than the core support structures should meet the guidelines of NG-3000 and be constructed so as not to adversely affect the integrity of the core support structures (NG-1122). d. Deformation limits for reactor internals should be established by the applicant and presented in histhe safety analysis report. The basis for these limits should be included. 36 The stresses associated with these displacements should not exceed the specified limits. The requirements for dynamic analysis of these components are discussed in SRP Section 3.9.2. e. The reactor internals should be designed to accommodate asymmetric blowdown loads due to postulated pipe ruptures. The applicant's evaluation of such loads should demonstrate that the loads do not exceed the limits imposed by the applicable codes and standards. Where double-ended guillotine break of reactor coolant piping is postulated, criteria