Document: NUREG-0800
Document ID: 9ff4c910-8dd7-451c-97cf-4b956e68d03e
Document Type: srp
Title: LIGHT LOAD HANDLING SYSTEM AND REFUELING CAVITY DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1331/ML13318A923.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.1.4
CFR Part: 
CFR Title: 

Content:
nts to perform safety functions. 9.1.4-4 Revision 4 - July 2014 3. GDC 61 as it relates to radioactivity release as a result of fuel damage and the avoidance of excessive personnel radiation exposure. 4. GDC 62 as it relates to prevention of criticality accidents. 5. Title 10 of the Code of Federal Regulations (10 CFR) 52.47(b)(1), which requires that a DC application contain the proposed ITAAC that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, a plant that incorporates the DC is built and will operate in accordance with the design certification, the provisions of the Atomic Energy Act (AEA), and the U.S. Nuclear Regulatory Commission (NRC) regulations. 6. 10 CFR 52.80(a), which requires that a COL application contain the proposed inspections, tests, and analyses, including those applicable to emergency planning, that the licensee shall perform, and the acceptance criteria that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, the facility has been constructed and will operate in conformity with the COL, the provisions of the AEA, and the NRC regulations. SRP Acceptance Criteria Specific SRP acceptance criteria acceptable to meet the relevant requirements of the NRC regulations identified above are as follows: 1. Acceptance for meeting the relevant aspects of GDC 2 is based on Regulatory Guide (RG) 1.29, Positions C.1 and C.2. 2. Acceptance for meeting the relevant aspects of GDC 5 is embodied within the other acceptance criteria of this document. 3. Acceptance for meeting the relevant aspects of GDC 61 is based in part on the guidelines of American National Standards Institute/American Nuclear Society (ANSI/ANS) 57.1-1992. 4. Acceptance for meeting the relevant aspects of GDC 62 is based in part on ANSI/ANS 57.1-1992. The SRP is not a substitute for the NRC