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:
the adequacy of analyses justifying exclusion of certain postulated pipe ruptures from design bases in SRP Section 3.6.3 (proposed). The EMCB also reviews the adequacy of programs for 26 assuring the integrity of bolting and threaded fasteners as part of its primary review responsibility for SRP Section 3.13 (proposed).27 For those areas of review identified above as part of the primary review responsibility of other branchespart of the review under other SRP sections, the acceptance criteria necessary for the review and their methods of application are contained in the referenced SRP sections of the corresponding primary branch.28 II. ACCEPTANCE CRITERIA EMEB acceptance criteria are based on meeting the requirements of the following regulations: 29 1. General Design Criterion 1 and 10 CFR Part 50, §50.55a, as itthey relates to reactor internals, requires that the reactor internals shall be designed to quality standards 30 commensurate with the importance of the safety functions to be performed. 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 itstheir safety functions. 31 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 DRAFT Rev. 3 - April 1996 3.9.5-4 environmental conditions associated with normal operations, maintenance, testing, and postulated LOCA. Dynamic effects associated with postulated pipe ruptures may be excluded from the design basis when analyses demonstrate that the probability of fluid system piping rupture is extremely low under conditions consistent with the design basis 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