Document: NUREG-0800
Document ID: fafcb45b-b0e5-49ad-9a69-0de2e8975189
Document Type: srp
Title: describes the general procedures to be followed in reviewing any I&C system. Section 7.5
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500506.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.1
CFR Part: 
CFR Title: 

Content:
ese features has been demonstrated; interdependent effects among the safety features are acceptable; sufficient data exist to assess the analytical tools used for safety analysis; and the scope of the design is complete except for site-specific elements. Therefore, the Staff finds that the information systems important to safety satisfy the requirements of 10 CFR 52.47(b)(2)(i). Based upon an initial review of the scope and content of the material submitted by the applicant, and completed review with respect to the technical items above, the Staff finds that the application contained appropriate detail about the information systems important to safety design to satisfy the requirements of 10 CFR 52.47(a)(2). Note: the following conclusion is applicable to all applications. The conclusions noted above for the information systems important to safety are applicable to all portions of the systems except for the following, for which acceptance is based upon prior NRC review and approval as noted. [List applicable system or topics and identify references.] Rev. 4 — June 1997 SRP 7.5-11 V. Implementation Except in those cases in which the applicant/licensee proposes an acceptable alternative method for complying with specified portions of the NRC's regulations, the method described herein will be used by the NRC staff in its evaluation of conformance with NRC regulations. VI. References ANSI/IEEE Std 279-1971. "Criteria for Protection Systems for Nuclear Power Generating Stations." Draft Regulatory Guide DG-1045. Proposed Revision 3 to Regulatory Guide 1.105, "Instrument Setpoints for Safety Systems." Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1997. IEEE Std 603-1991. "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations." NUREG-0737 Supplement 1. "Clarification of TMI Action Plan Requirements — Requirements for Emergency Response Capability." January 1983. Regulatory Guide 1.151. "Instrument Sensing Lines."