Document: NUREG-0800
Document ID: d2f0cc81-920c-4065-b74b-67114ba68b0e
Document Type: srp
Title: through 7.9 of the SAR. Where exceptions are taken to the guidance provided by regulatory guides, and
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500493.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.2
CFR Part: 
CFR Title: 

Content:
ITAAC for I&C systems important to safety should be provided for each system in subsequent sections of Chapter 7 of the SAR. SECY-91-178 and SRP Section 14.3 provide guidance on conformance to 10 CFR 52.47(c). The evaluation of conformance with this requirement for I&C systems should be addressed by review of Section 7.1 through 7.9 of the SAR and the review of combined license documentation in conjunction with review of Section 14.3.5 of the SAR. Section 14.3 of the SRP describes the general acceptance criteria and review procedures for ITAAC. Section 14.3.5 describes the specific acceptance criteria and review procedures for I&C system ITAAC. The Staff review with respect to these requirements is documented in Section 14.3 of the SER. 2. 10 CFR 50 Appendix A, General Design Criteria a. Criterion 1 — Quality Standards and Records "Structures, systems, and components important to safety shall be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. Where generally recognized codes and standards are used, they shall be identified and evaluated to determine their applicability, adequacy, and sufficiency and shall be supplemented or modified as necessary to assure a quality product in keeping with the required safety function. A quality assurance program shall be established and implemented in order to provide adequate assurance that these structures, systems, and components will satisfactorily perform their safety functions. Appropriate records of the design, fabrication, erection, and testing of structures, systems, and components important to safety shall be maintained by or under the control of the nuclear power unit licensee throughout the life of the unit." Applicability — All I&C systems and components important to safety. Review Methods — Regulatory guides and endorsed codes and standards applicable to I&C systems important to safety are identified in Section 4 of this