Document: NUREG-0800
Document ID: f97c1bda-c2f0-4f1d-9a3d-cdbc1080dbac
Document Type: srp
Title: Revision 3 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070710423.pdf
Revision Date: 2023-06
Chapter: 8
Section ID: 8
CFR Part: 
CFR Title: 

Content:
issue. BTP 8-1-2 Revision 3 - March 2007 B. BRANCH TECHNICAL POSITION To meet the intent of IEEE Std. 279, the design of the MOIV system should incorporate the following features for safety injection tanks: 1. Automatic opening of the valves when either primary coolant system pressure exceeds a preselected value (to be specified in the technical specifications) or a safety injection signal is present. Both primary coolant system pressure and safety injection 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. An audible and visual alarm, independent of item 2, above, that is actuated by a sensor on the valve when the valve is not in the fully open position. 4. Use 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). Conformance with the relevant criteria for operating bypasses described in IEEE Std. 603, as endorsed in RG 1.153, constitutes an acceptable alternative approach. It should be noted that BTP 8-4 may also be applied to these isolation valves and should be used, when applicable, in conjunction with this Branch Technical Position. It should also be noted that IEEE Std. 1290 provides information on motor-operated valve protection, control, and testing. C. REFERENCES 1. Regulatory Guide 1.153, “Criteria for Power, Instrumentation, and Control Portions of Safety Systems.” 2. BTP 8-4, “Application of the Single Failure Criterion to Manually Controlled Electrically Operated Valves.” 3. Arkansas 1, Unit 1, Safety Evaluation Report, January 23, 1973. 4. IEEE Std. 603-1991, “Criteria for Safety Systems for Nuclear Power Generating Stations.” 5. IEEE Std. 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations.” 6.