Document: NUREG-0800
Document ID: b0a0e95d-3418-480e-a2d1-2c8c449e797c
Document Type: srp
Title: Draft Revision 6 – August 2015
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159A540.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
valve operators should 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, as discussed in GL 87- 12 and GL 88-17. 6. The system should satisfy the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(h), “Protection and Safety Systems,” of 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” Appendix A, “General BTP 7-1-3 Draft Revision 6 – August 2015 Design Criteria for Nuclear Plants.” 10 CFR 50.55a(h) requires compliance with the Institute of Electrical and Electronics Engineers (IEEE) Standard (Std) 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Station,” and the correction sheet dated January 30, 1995. For nuclear power plants with construction permits issued before January 1, 1971, the applicant or licensee may elect to comply instead with their plant-specific licensing basis. For nuclear power plants with construction permits issued between January 1, 1971 and May 13, 1999, the applicant or licensee may elect to comply instead with the requirements stated in IEEE Std 279- 1971, “Criteria for Protection Systems for Nuclear Power Generating Stations.” SRP, Appendix 7.1-B provides procedures for reviewing systems against IEEE