Document: NUREG-0800
Document ID: 694a6d46-6a73-4dcf-afa8-2ea3a4a0181a
Document Type: srp
Title: REACTOR PRESSURE VESSEL INTERNALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340641.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.5
CFR Part: 
CFR Title: 

Content:
uires that the reactor internals shall be designed to quality standards commensurate with the importance of the safety functions to be performed. 3.9.5-2 Rev. 2 - July 1981 2. General Design Criterion 2, as it relates to reactor internals, requires that the reactor internals shall be designed to withstand the effects of earthquakes without loss of capability to perform its safety functions. 3. General Design Criterion 4, as it relates to reactor internals, requires that reactor internals shall be designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operations, maintenance, testing, and postulated LOCA. 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. 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 MG of the ASME Code are presented in SRP Section 3.9.3 (Ref. 7). 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. 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-U22). d. Deformation limits for reactor internals should be established by the applicant and presented in his safety analysis report. The basis for these limits should be included. The stresses associated with these dis- placements should not exceed the specified limits.