Published July 1994 | Version v1
Report Restricted

Enhancements to the Idaho National Engineering Laboratory motor-operated valve assessment software

Description

In January 1991, the U.S. Nuclear Regulatory Commission (USNRC) commenced Part 1 inspections to review licensee's motor-operated valve (MOV) programs that were developed to address Generic Letter 89-10, open-quotes Safety-Related Motor-Operated Valve Testing and Surveillanceclose quotes. In support, of this effort, the Isolation Valve Assessment (IVA) software, Version 3.10, was developed by the Idaho National Engineering Laboratory (INEL) to enable rapid in-depth review of MOV sizing and torque switch setting calculations. In 1994, the USNRC commenced Part 2 inspections, which involve a more in-depth review of MOV in situ testing relative to design-basis assumptions. The purpose of this paper is to describe the latest INEL and industry research that has been incorporated into Version 4.00 of the IVA software to support the latest round of inspections. Major improvements include (a) using dynamic and static test results to determine MOV performance parameters and validate design-basis engineering assumptions, (b) determining the stem/stem-nut coefficient of friction using new research-based techniques, (c) adding the ability to evaluate globe valves, and (d) incorporating new methods to account for the effects of high ambient temperature on the output torque of alternating current (ac) motors

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Additional details

Publishing Information

Imprint Title
Proceedings of the Third NRC/ASME Symposium on Valve and Pump Testing. Session 1A--Session 2C: Volume 1
Imprint Pagination
532 p.
Journal Page Range
p. 143-158.
Report number
NUREG/CP--0137-Vol.1

Conference

Title
3. ASME/NRC symposium on valve and pump testing.
Dates
18-21 Jul 1994.
Place
Washington, DC (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
26033552
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DESIGN; NUCLEAR POWER PLANTS; REACTOR COMPONENTS; RELIABILITY; TESTING; VALVES
Descriptors DEC
CONTROL EQUIPMENT; EQUIPMENT; FLOW REGULATORS; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Contract/Grant/Project number
Contract AC07-76ID01570
Secondary number(s)
CONF-940774--Vol.1.