Document: NUREG-0800
Document ID: 81a2e18b-7311-4c4e-822e-8dfe1b0ba7aa
Document Type: srp
Title: REACTOR PRESSURE VESSEL INTERNALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0702/ML070230009.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.5
CFR Part: 
CFR Title: 

Content:
RES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. These review procedures are based on the identified SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. 1. The configuration and general arrangement of all mechanical and structural internal elements covered by this SRP section are reviewed and compared to those of previously licensed similar plants. Any significant changes in design or operating conditions are noted and the applicant is asked to confirm that such changes do not affect the FIV test results required by SRP Section 3.9.2. 2. As to the design and analysis of reactor internals, a statement by the applicant that they are designed in accordance with Subsection NG of the ASME Code and SRP Section 3.9.3, "Core Support Structures," is acceptable. In lieu of such a commitment, the reviewer must determine whether the design and analysis of these components are consistent with the requirements addressed in Subsection II of this SRP section by requiring the applicant to describe the procedures and criteria for the design of these 3.9.5-8 Revision 3 - March 2007 components, including a list of the design and service stress limits for all of the applicable loading conditions. The stresses of adverse flow conditions (flow-excited vibrations and acoustic resonances) should be treated as primary stresses while satisfying the ASME Code service stress limits. 3. The reviewer verifies whether the asymmetric blowdown loadings upon reactor internals from pipe ruptures (at postulated locations not excluded in leak-before-break analyses) have been evaluated by the applicant and are accommodated in the design consistently with criteria in Subsection II.5 (Acceptance Criteria) of this SRP section. 4.