Document: NUREG-0800
Document ID: b9958157-a0b8-4321-b294-effbf265eda5
Document Type: srp
Title: ENGINEERED SAFETY FEATURES SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070560004.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.3
CFR Part: 
CFR Title: 

Content:
to as COL license information in certain DCs) included in the referenced DC. Additionally, a COL applicant must address requirements and restrictions (e.g., interface requirements and site parameters) included in the referenced DC. Review Interfaces Other SRP sections interface with this section as follows: 1. SRP Section 7.0 describes the coordination of reviews, including the information to be reviewed and the scope required for each of the different types of applications that the staff may review. Refer to that section for information regarding how the areas of review are affected by the type of application under consideration and for a description of coordination between the organization responsible for the review of instrumentation and control systems and other organizations. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: Acceptance criteria applicable to any ESFAS and ESF control systems 1. 10 CFR 50.55a(a)(1), “Quality Standards.” 2. 10 CFR 50.55a(h), “Protection and Safety Systems,” requires compliance with IEEE Std 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations,” and the correction sheet dated January 30, 1995. For nuclear power plants with construction permits issued before January 1, 1971, the applicant/licensee may elect to comply instead with their plant specific licensing basis. 7.3-4 Revision 5 - March 2007 For nuclear power plants with construction permits issued between January 1, 1971, and May 13, 1999, the applicant/licensee may elect to comply instead with the requirements stated in IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations.” 3. 10 CFR 50. Appendix A, General Design Criterion (GDC) 1, “Quality Standards and Records.” 4. GDC 2, “Design