Document: NUREG-0800
Document ID: 71b0a52a-ac0c-4c26-b0eb-708a6f5600fb
Document Type: srp
Title: FOUNDATIONS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070333.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.5
CFR Part: 
CFR Title: 

Content:
the event of an accident in one unit, an orderly shutdown and cooldown of the remaining units. The requirements of GDC 5 are imposed to ensure that the use of common structures in multiple-unit plants will not significantly affect orderly and safe shutdown and cooldown in one plant in the event of an accident in another. Loads that result during normal operation and design basis accidents are so linked in load combination equations that the resulting structural designs provide for mutual independence of shared structures. Meeting this requirement provides assurance that structures other than containment and its associated components are capable of performing their intended safety function even when they are shared by multiple nuclear power units.52 III. REVIEW PROCEDURES The reviewer selects and emphasizes material from the review procedures described below, as may be appropriate for a particular case. Deficient areas are identified by the reviewer and a request for additional information is initiated. New or unique design features that are not specifically covered in the "Standard Format...",Regulatory Guide 1.70 require a more detailed 53 review. The reviewer determines the additional information required for a meaningful review of such new or unique design features.54 1. Description of the Foundations After the type of foundation and its structural characteristics are identified, information on similar and previously licensed plants is obtained for reference. Such information, which is available in safety analysis reportsSARs and amendments of license 55 applications, enables identification of differences for the case under review. These differences require additional scrutiny and evaluation. New and unique features that have not been used in the past are examined in greater detail. The information furnished in the SAR is reviewed for sufficiency in accordance with the "Standard Format..."Regulatory Guide 1.70. A decision is then made with regard to the 56