Document: NUREG-0800
Document ID: 4ded65c2-74df-4f0b-9d0f-503a52cd155a
Document Type: srp
Title: for additional information, and the discussion in SRP Section 14.3.3.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070660522.pdf
Revision Date: 2023-06
Chapter: 14
Section ID: 14.3
CFR Part: 
CFR Title: 

Content:
stems are adequately designed. See SRP Section 14.3.3 for additional information. For the RPV, the key dimensions of the RPV system should be verified in conjunction with the basic configuration check of the system. The key dimensions of the RPV system and the acceptable variations of the key dimensions should be provided in the certified design description. Alternatively, acceptable variations and the bases for them should be provided in Tier 2. 14.3.2-10 March 2007 For component qualification, tests, analyses, or a combination of tests and analyses should be performed for seismic Category I mechanical and electrical equipment (including connected instrumentation and controls) to demonstrate that the as-built equipment and associated anchorages are qualified to withstand design basis dynamic loads without loss of safety function. These test and analyses should be performed as a part of ITAAC to verify the basic configuration of the system in which the equipment is located. See Section 14.3.3 for additional information. Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 1. Application of 10 CFR 52.47(b)(1), as it relates to ITAAC (for design certification) provides reasonable assurance that the SSCs in this area of review will operate in accordance with the design certification, the provisions of the Atomic Energy Act, and the NRC’s regulations; 2. Application of 10 CFR 52.80(a), as it relates to ITAAC (for combined licenses) provides reasonable assurance that the SSCs in this area of review have been constructed and will be operated in conformity with the combined license, the provisions of the Atomic Energy Act, and the NRC’s regulations. III. REVIEW PROCEDURES 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