Document: NUREG-0800
Document ID: f0ec8180-bdec-47b1-b10f-926bce888716
Document Type: srp
Title: FUNCTIONAL DESIGN, QUALIFICATION, AND INSERVICE TESTING PROGRAMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1613/ML16134A116.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.6
CFR Part: 
CFR Title: 

Content:
view of proposed plant- specific, risk-informed changes to a licensee’s IST program. The review procedures are consistent with acceptable methods implementing a risk-informed IST program that follow RG 1.174, “An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,” and RG 1.175, “An Approach for Decisions on Plant-Specific Risk-Informed Decisionmaking: Inservice Testing.” Alternatively, an applicant may use NRC-approved risk-informed ASME Code cases referenced in RG 1.192 to construct a risk-informed approach for IST programs. Subsection ISTD, “Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants,” of the ASME OM Code incorporates alternative provisions for determining dynamic restraint visual inspection intervals and corrective actions, which the staff recommended in Generic Letter (GL) 90-09, “Alternative Requirements for Snubber Visual Inspection Intervals and Corrective Actions.” 1. Functional Design and Qualification of Pumps, Valves, and Dynamic Restraints A. For new plant applications, safety-related pump, valve, and piping designs are acceptable where they specify provisions for testing of pumps and valves at the maximum flow indicated in the plant accident analyses. B. Functional design and qualification of each safety-related pump and valve are acceptable where each pump and valve is capable of performing its intended function under the full range of fluid flow, differential pressure, electrical conditions, and temperature conditions with debris-laden coolant fluids up to and including design-basis accident conditions. ASME Standard QME-1-2007 includes provisions for the functional design and qualification of active mechanical equipment in nuclear power plants. The NRC staff has accepted the use of ASME QME-1-2007 in Revision 3 to RG 1.100 with specific conditions. C. Acceptance criteria for