Published 1996 | Version v1
Report Restricted

Recent NRC research activities addressing valve and pump issues

Creators

Description

The mission of the U.S. Nuclear Regulatory Commission (NRC) is to ensure the safe design, construction, and operation of commercial nuclear power plants and other facilities in the U.S.A. One of the main roles that the Office of Nuclear Regulatory Research (RES) plays in achieving the NRC mission is to plan, recommend, and implement research programs that address safety and technical issues deemed important by the NRC. The results of the research activities provide the bases for developing NRC positions or decisions on these issues. Also, RES performs confirmatory research for developing the basis to evaluate industry responses and positions on various regulatory requirements. This presentation summarizes some recent RES supported research activities that have addressed safety and technical issues related to valves and pumps. These activities include the efforts on determining valve and motor-operator responses under dynamic loads and pressure locking events, evaluation of monitoring equipment, and methods for detecting and trending aging of check valves and pumps. The role that RES is expected to play in future years to fulfill the NRC mission is also discussed

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Additional details

Publishing Information

Imprint Title
Proceedings of the 4th NRC/ASME symposium on valve and pump testing
Imprint Pagination
719 p.
Journal Page Range
p. 7.
Report number
NUREG/CP--0152

Conference

Title
4. NRC/ASME symposium on valve and pump testing in nuclear power plants.
Dates
15-18 Jul 1996.
Place
Washington, DC (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28013949
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AGING; DYNAMIC LOADS; NUCLEAR POWER PLANTS; PRESSURIZATION; PUMPS; REACTOR SAFETY; TESTING; US NRC; VALVES
Descriptors DEC
CONTROL EQUIPMENT; EQUIPMENT; FLOW REGULATORS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; THERMAL POWER PLANTS; US ORGANIZATIONS

Optional Information

Secondary number(s)
CONF-9607103--.