Summary report for 1990 inservice inspection (ISI) of SRS 100-L reactor tank

Technical Report · Fri Jul 12 04:00:00 EDT 1991

DOI:https://doi.org/10.2172/5559407· OSTI ID:5559407

Morrison, J M; Loibl, M W

The integrity of the SRS reactor tanks is a key factor affecting their suitability for continued service since, unlike the external piping system and components, the tanks are virtually irreplaceable. Cracking in various areas of the process water piping systems has occurred beginning in about 1960 as a result of several degradation mechanisms, chiefly intergranular stress corrosion cracking (IGSCC) and chloride-induced transgranular cracking. The primary objective of this inspection was to determine if the accessible welds and selected portions of base metal in the L Reactor tank wall contain any indications of IGSCC. This inspection included areas in and beyond the weld HAZ, extending out as far as two to three inches from the centerline of the welds, plus selected areas of base metal at the intersection of the main tank vertical and mid-girth welds. No evidence of such degradation was found in any of the areas examined. Further, additional inspections were conducted of areas that had been damaged and repaired during original fabrication, and on a sample of areas containing linear indications observed during the 1986 visual inspection of the tank. No evidence of IGSCC or other service induced degradation was detected in these areas, either. The inspection was initially planned to cover a minimum of 60% of the accessible welds, plus repair areas and a sample of the indications from the 1986 visual inspection. Direction was received from DOE while the inspection was in progress to expand the scope to cover 100% of the accessible weld areas, and the plan was adjusted accordingly. Initial setup of the tank, which prior to inspection contained Mark 60B target assemblies and nearly a full charge of Mark 22 fuel assemblies, began on October 15, 1990. The inspection was completed on April 12, 1991.

• Research Organization: Westinghouse Savannah River Co., Aiken, SC (United States)
• Sponsoring Organization: DOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 5559407
• Report Number(s): WSRC-TR-91-378; ON: DE92009960
• Country of Publication: United States
• Language: English

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
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36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
AUSTENITIC STEELS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CONTAINERS
CORROSION
CORROSION RESISTANT ALLOYS
EQUIPMENT
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HEAVY WATER MODERATED REACTORS
HIGH ALLOY STEELS
INSPECTION
INTERGRANULAR CORROSION
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
L REACTOR
MATERIALS
NATIONAL ORGANIZATIONS
NICKEL ALLOYS
PRODUCTION REACTORS
QUALITY ASSURANCE
REACTOR SAFETY
REACTORS
REMOTE VIEWING EQUIPMENT
SAFETY
SAVANNAH RIVER PLANT
SPECIAL PRODUCTION REACTORS
STAINLESS STEEL-304
STAINLESS STEELS
STEEL-CR19NI10
STEELS
STRESS CORROSION
TANKS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WELDED JOINTS