Document: NRC Regulatory Guide
Document ID: 74c49394-8dbf-46e7-b62a-b85de93b47d8
Document Type: regulatory_guide
Title: Initial Test Programs for Water-Cooled Nuclear Power Plants + HISTORY - HISTORY 11/2012 – DG-1259 , Proposed Revision 4 11/2006 – DG-1166 , Proposed Revision 3 (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1229/ML12298A071.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.68
CFR Part: 
CFR Title: 

Content:
nstrate expected operation following a loss of power sources and in degraded modes for which the systems are designed to remain operational. Tests also should include, as appropriate, verifications of the proper functioning of Appendix A to DG-1259, Page A-2 instrumentation and controls, permissive and prohibit interlocks, and equipment protective devices of which malfunction or premature actuation may shut down or defeat the operation of systems or equipment. The ASME OM Code as incorporated by reference in 10 CFR 50.55a specifies pre-service testing and in-service testing requirements for pumps, valves, and dynamic restraints. The operational readiness of pumps, valves, and dynamic restraints needs to be demonstrated before relying on those components to perform their safety functions. Pre-service testing of pumps, valves, and dynamic restraints might be accomplished as part of the preoperational testing activities. Preoperational tests might be required by conditions in the license that the NRC has issued for nuclear power plants under construction. For example, the NRC specified license conditions for some new nuclear power plants licensed in accordance with 10 CFR Part 52 that include preoperational test requirements for pyrotechnic-actuated valves. Tests performed to satisfy license conditions are also accomplished as part of the preoperational testing activities. System vibration, expansion (in discrete temperature step increments), and restraint tests also should be conducted. This testing should include verification (by observations and measurements), as appropriate, that piping and components have adequate clearances to accommodate potential water hammer induced movements, vibrations, and expansions are acceptable for (1) Class 1, 2, and 3 systems, as defined by the ASME Boiler and Pressure Vessel Code (ASME B&PV Code) Section III (Ref. 13), (2) other high energy piping systems inside Seismic Category I structures, (3) high energy portions of systems whose