Document: NUREG-0800
Document ID: 61d6c3f2-0151-4fc4-a436-71dc29b65151
Document Type: srp
Title: Revision 6 - August 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1601/ML16019A299.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
tion signals should be provided to the valve operator. 2. Visual indication in the control room of the open or closed status of the valve. 3. Bypassed and inoperable status indication in accordance to RG 1.47, “Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety System.” 4. Utilization of a safety injection signal to remove automatically (override) any bypass feature that may be provided to allow an isolation valve to be closed for short periods of time when the reactor coolant system is at pressure (in accordance with provisions of the technical specifications). C. References 1. Institute of Electrical and Electronics Engineers, IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations,” Piscataway, NJ. 2. Institute of Electrical and Electronics Engineers, IEEE Std 603-1991, “IEEE Standard BTP 7-2-3 Revision 6 – August 2016 Criteria for Safety Systems for Nuclear Power Generating Stations,” Piscataway, NJ. 3. U.S. Nuclear Regulatory Commission, “Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems,” Regulatory Guide 1.47. BTP 7-2-4 Revision 6 – August 2016 PAPERWORK REDUCTION ACT STATEMENT The information collections contained in the Standard Review Plan are covered by the requirements of 10 CFR Part 50, and were approved by the Office of Management and Budget, approval number 3150-0011. PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number. BTP 7-2-5 Revision 6 – August 2016 BTP Section 7-2 Description of Changes BTP 7-2, “Guidance on Requirements of Motor-Operated Valves in the Emergency Core Cooling System Accumulator Lines” This BTP Section affirms the technical accuracy and adequacy of the guidance previously provided in BTP Section 7-2, Revision 5, dated