Document: NUREG-0800
Document ID: eae0e3f8-171e-4801-8d43-24b7ff37a525
Document Type: srp
Title: Appendix 7-A
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500522.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
ld receive a signal to close automatically whenever the primary system pressure exceeds the subsystem design pressure. 3. For those system interfaces where one check valve and one motor-operated valve are provided, the motor-operated valve should be interlocked to prevent the valve from opening whenever the primary pressure is above the subsystem design pressure, and to close automatically whenever the primary system pressure exceeds the subsystem design pressure. 4. Suitable valve position indication should be provided in the control room for the interface valves. 5. For those interfaces where the subsystem is required for emergency core cooling system operation, the above recommendations need not be implemented. System interfaces of this type should be evaluated on an individual basis. 6. The system should satisfy the requirements of the General Design Criteria and Section 50.55a(h) of 10 CFR Part 50 with regard to the protection system requirements (ANSI/IEEE Std 279, "Criteria for Protection Systems for Nuclear Power Generating Stations"). As described in Reg. Guide 1.153, "Criteria Rev. 4 — June 1997 Appendix 7-A BTP HICB-1-2 for Power, Instrumentation, and Control Portions of Safety Systems," compliance with IEEE Std 603, "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations," as modified and supplemented by the regulatory guide, is considered by the NRC staff to satisfy the provisions of ANSI/IEEE Std 279. Appendices 7.1-B and 7.1-C provide procedures for reviewing systems against ANSI/IEEE 279 and Reg. Guide 1.153. C. References ANSI/IEEE Std 279-1971. "Criteria for Protection Systems for Nuclear Power Generating Stations." IEEE Std 603-1991. "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations." Regulatory Guide 1.153. "Criteria for Power, Instrumentation, and Control Portions of Safety Systems." Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1996.