Final summary report for 1989 inservice inspection (ISI) of SRS (Savannah River Site) 100-P Reactor tank
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 1960 as a result of several degradation mechanisms, chiefly intergranular stress corrosion cracking (IGSCC) and chloride-induced transgranular cracking. IGSCC, currently the primary degradation mechanism, also occurred in the knuckle'' region (tank wall-to-bottom tube sheet transition piece) unique to C Reactor and was eventually responsible for that reactor being deactivated in 1985. A program of visual examinations of the SRS reactor tanks was initiated in 1968, which used a specially designed immersible periscope. Under that program the condition of the accessible tank welds and associated heat affected zones (HAZ) was evaluated on a five-year frequency. Prior to 1986, the scope of these inspections comprised approximately 20 percent of the accessible weld area. In late 1986 and early 1987 the scope of the inspections was expanded and a 100 percent visual inspection of accessible welds was performed of the P-, L-, and K-Reactor tanks. Supplemental dye penetrant examinations were performed in L Reactor on selected areas which showed visual indications. No evidence of cracking was detected in any of these inspections of the P-, L-, and K-Reactor tanks. 17 refs., 7 figs.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- DOE/DP
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 6975938
- Report Number(s):
- WSRC-RP-89-1311; ON: DE90009277
- Country of Publication:
- United States
- Language:
- English
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Summary report for 1990 inservice inspection (ISI) of SRS 100-L reactor tank
Summary report for 1990 inservice inspection (ISI) of SRS 100-K reactor tank
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
PRODUCTION REACTORS
TANKS
SERVICE LIFE
CAMERAS
DATA PROCESSING
FABRICATION
IMPLEMENTATION
INSPECTION
MEASURING METHODS
METALLURGY
OPTIMIZATION
PERFORMANCE TESTING
PLANNING
PROGRESS REPORT
QUALITY ASSURANCE
REACTOR CORES
REACTOR OPERATORS
REACTOR SAFETY
RELIABILITY
ROBOTS
SAVANNAH RIVER PLANT
STANDARDS
SURFACE PROPERTIES
TECHNOLOGY ASSESSMENT
TRANSDUCERS
WELDED JOINTS
CONTAINERS
DOCUMENT TYPES
JOINTS
NATIONAL ORGANIZATIONS
PERSONNEL
PROCESSING
REACTOR COMPONENTS
REACTORS
SAFETY
TESTING
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
220700 - Nuclear Reactor Technology- Plutonium & Isotope Production Reactors
360103 - Metals & Alloys- Mechanical Properties