Document: NUREG-0800
Document ID: 40fd3df4-ccf2-4533-a724-bcd94c5aec2b
Document Type: srp
Title: of the SAR.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550076.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.3
CFR Part: 
CFR Title: 

Content:
identified acceptance criteria and guidelines satisfies the applicable requirements of 10 CFR 50.55a(a)(1) and GDC 1 with respect to the design, fabrication, erection, and testing to quality standards commensurate with the importance of the safety functions to be performed. 3. For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. 7.1-10 Revision 5 - March 2007 4. Note: The following conclusion is applicable to all applications. The conclusions noted above for the I&C systems important to safety are applicable to all portions of the systems except for the following, for which acceptance is based on prior NRC review and approval as noted [list applicable system or topics and identify references]. 5. In addition, to the extent that the review is not discussed in other SER sections, the findings will summarize the staff's evaluation of the ITAAC, including design acceptance criteria, as applicable. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. IEEE Std. 279-1971, "Criteria for Protection Systems for Nuclear Power Generating Stations." 2. IEEE Std. 603-1991, "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations." 3. IEEE Std. 7-4.3.2-2003, "IEEE Standard Criteria for Digital Computers in Safety