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Title: Acceptance criteria for reactor coolant pumps and valves

Each of the six primary coolant loop systems of the Savannah River Site (SRS) production reactors contains one reactor coolant pump, one PUMP suction side motor operated valve, and other smaller valves. The pumps me double suction, double volute, and radially split type pumps. The valves are different size shutoff and control valves rated from ANSI B16.5 construction class 150 to class 300. The reactor coolant system components, also known as the process water system (PWS), are classified as nuclear Safety Class I components. These components were constructed in the 1950`s in accordance with the then prevailing industry practices. No uniform construction codes were used for design and analysis of these components. However, no pressure boundary failures or bolting failures have ever been recorded throughout their operating history. Over the years, the in-service inspection (ISI) was limited to visual inspection of the pressure boundaries, and surface and volumetric examination of the pressure retaining bolts. Efforts are now underway to implement ISI requirements similar to the ASME Section XI requirements for pumps and valves. This report discusses the new ISI requirements which also call for volumetric examination of the pump casing and valve body welds.
Authors:
; ;
Publication Date:
OSTI Identifier:
10159788
Report Number(s):
WSRC-MS--93-182; CONF-930702--19
ON: DE93012758; TRN: 93:015207
DOE Contract Number:
AC09-89SR18035
Resource Type:
Conference
Resource Relation:
Conference: 1993 American Society of Mechanical Engineers (ASME) pressure vessel and piping conference,Denver, CO (United States),25-29 Jul 1993; Other Information: PBD: [1993]
Research Org:
Westinghouse Savannah River Co., Aiken, SC (United States)
Sponsoring Org:
USDOE, Washington, DC (United States)
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; PRODUCTION REACTORS; PUMPS; VALVES; SPECIFICATIONS; SAVANNAH RIVER PLANT; FAILURES; INSPECTION; WELDED JOINTS; REACTOR COOLING SYSTEMS; FASTENERS; FRACTURE MECHANICS; CRACKS 220600; 220200; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS; COMPONENTS AND ACCESSORIES