Document: NUREG-0800
Document ID: 1d79b1ad-8e39-4ab1-b2e4-30556b3a5384
Document Type: srp
Title: describes the general procedures to be followed in reviewing any instrumentation and control
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500509.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.1
CFR Part: 
CFR Title: 

Content:
ing portions of the control system [insert list]. Based upon review of the completed safety analysis, the Staff finds that the requirements for these portions of the design were sufficiently detailed. Therefore, the Staff finds that the control system design satisfies the requirements of 10 CFR 52.47(a)(1)(vii). 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 control systems 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 control systems 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]. 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. Rev. 4 — June 1997 SRP 7.7-7 VI. References ANSI/IEEE Std 279-1971. "Criteria for Protection Systems for Nuclear Power Generating Stations." Regulatory Guide 1.151. "Instrument Sensing Lines." Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1983. Staff Requirements Memorandum on SECY-93-087. "Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (ALWR) Designs." July 15, 1993. Rev. 4 — June 1997 SRP 7.7-8 Table 7.7-1. Examples of Control Systems Typically Included in Section 7.7 Boiling Water Reactor Pressurized Water Reactor Nuclear boiler control and instrumentation Rod control Rod position instrumentation Neutron monitoring system Recirculation flow control system