Document: NUREG-0800
Document ID: dc63e8aa-2a74-4078-9e19-9a26ed1b4d8c
Document Type: srp
Title: Revision 6 – July 2012
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1105/ML110550791.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
nd every possible sequence of device states are tested and all outputs are verified for every case (100% tested). What constitutes "sufficient diversity” should be evaluated on a case-by-case basis, considering diversity attributes and attribute criteria that preclude or limit certain types of CCF. Diversity attributes and associated attribute criteria, and a process for evaluating the application may provide more objective guidance in answering, “What is sufficient diversity?”. 2. Information to be Reviewed The information to be reviewed is the D3 assessment conducted by the applicant. If the D3 assessment indicates the need for a diverse means to accomplish a protective safety function, then the diverse means should be evaluated, including any HFE analysis associated with manual operator actions as a diverse means. 3. Acceptance Criteria 3.1 Specific Acceptance Criteria The D3 assessment submitted by the applicant should demonstrate compliance with the NRC position on D3 described above. To reach a conclusion of acceptability, the following conclusions should be reached and supported by summation of the results of the analyses and the diverse means provided. Since the acceptance criteria address confirmation that AOOs and Revision 6 – July 2012 BTP 7-19-14 postulated accidents are mitigated in the presence of CCF, the focus of the D3 analyses should be on the protection systems. Other systems important to safety become involved only to the extent that they are credited as providing diverse functions to protect against CCF in the protection systems. (1) For each anticipated operational occurrence in the design basis occurring in conjunction with each single postulated CCF, the plant response calculated using realistic assumptions should not result in radiation release exceeding 10 percent of the applicable siting dose guideline values or violation of the integrity of the primary coolant pressure boundary. The applicant should (1) demonstrate that sufficient