Recommendations on frequently encountered relief requests

Conference · Wed Jan 01 00:00:00 EST 1992

OSTI ID:7031719

Hartley, R S; Ransom, C B

This paper is based on the review of a large database of requests for relief from enservice testing (1ST) requirements for pumps and valves. From the review, the paper identifies areas where enhancements to either the relief request process or the applicable test codes can improve IST of pumps and valves. Certain types of requests occur frequently. The paper examines some frequent requests and considers possible changes to the requirements to determine if the frequent requests can be eliminated. Recommended changes and their bases will be discussed. IST of safety-related pumps and valves at commercial nuclear power plants is done according to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (the Code), Section XI. Because of the design and function of some safety systems in nuclear plants, performing Code testing of certain pumps and valves is impractical or a hardship without a compensating increase in the level of safety. Deviations from the Code are allowed by law, as reviewed and approved by the United States Nuclear Regulatory Commission (NRC), through the relief request process. Because of similarities in plant design and system function, many problems encountered in testing components are similar from plant to plant. Likewise, there are often common problems associated with test methods or equipment. Therefore, many relief requests received by the NRC from various plants are similar. Identifying and addressing the root causes for these common requests will greatly improve IST.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 7031719
• Report Number(s): EGG-M-92451; CONF-920732-7; ON: DE92019761
• Resource Relation: Conference: 2. Nuclear Regulatory Commission (NRC)/American Society of Mechanical Engineers (ASME) symposium on pump and valve testing, Washington, DC (United States), 21-23 Jul 1992
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
IN-SERVICE INSPECTION
REGULATIONS
PUMPS
VALVES
NUCLEAR POWER PLANTS
RECOMMENDATIONS
TESTING
CONTROL EQUIPMENT
EQUIPMENT
FLOW REGULATORS
INSPECTION
NUCLEAR FACILITIES
POWER PLANTS
THERMAL POWER PLANTS
220200* - Nuclear Reactor Technology- Components & Accessories
210700 - Nuclear Power Plants- Regulation & Licensing