Document: NUREG-0800
Document ID: edf4b0e7-a6b1-4168-a057-45a70ca5524d
Document Type: srp
Title: ADEQUACY OF DESIGN FEATURES AND FUNCTIONAL CAPABILITIES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1227/ML12276A112.pdf
Revision Date: 2023-06
Chapter: 19
Section ID: 19.5
CFR Part: 
CFR Title: 

Content:
IDENTIFIED AND DESCRIBED FOR WITHSTANDING AIRCRAFT IMPACTS REVIEW RESPONSIBILITIES Primary- Organization responsible for the review of fire protection Organization responsible for the review of structures Organization responsible for the review of reactor systems Secondary- Organization responsible for the review of spent fuel cooling Organization responsible for the review of balance of plant systems I. AREA OF REVIEW Title 10 of the Code of Federal Regulations (10 CFR) 50.150, the aircraft impact assessment (AIA) rule applies to the following new reactor applicants: (1) construction permit applications after July 13, 2009; (2) operating license applications for which a construction permit was issued after July 13, 2009; (3) standard design certification applications; (4) standard design certification rule renewal applications for standard design certification rules in effect on July 13, 2009, which have not been amended to comply with the AIA rule; (5) standard design approval applications; (6) combined license (COL) applications that either (a) do not reference a standard design 19-5-2 Revision 0 - April 2013 certification, standard design approval, or manufactured reactor, or (b) reference a standard design certification issued before July 13, 2009, which has not been amended to address the AIA rule; and (7) manufacturing license applications that either (a) do not reference a standard design certification or standard design approval, or (b) reference a standard design certification issued before July 13, 2009, which has not been amended to comply with the AIA rule. Using realistic analyses, applicants shall identify and incorporate into the design those design features and functional capabilities to show, with reduced use of operator action, that the reactor core remains cooled or the containment remains intact and spent fuel cooling or spent fuel pool integrity is maintained (the acceptance criteria). For some cases, when the damage could impair the ability of