Review of containment examination and testing requirements
Conference
·
OSTI ID:5505506
At the present time, the ASME Code Section XI, Division 1, Subsection IWE, requirements for metal containment inservice inspection are not specifically referenced in the Nuclear Regulatory Commission (NRC) Regulations. A review of Subsection IWE is being performed by the Idaho National Engineering Laboratory (INEL) to assist the NRC in evaluating the acceptability of incorporating this Subsection into the NRC Regulations. The impact of Subsection IWE requirement changes compared with the present containment inservice inspection (ISI) requirements contained in Appendix J of the NRC Regulations is discussed. In addition, INEL recommendations for improvements/changes in containment ISI requirements are presented for consideration by personnel of code/standards committees and the NRC staff. For example, quantification of requirements for leak testing of localized areas in pressure boundaries is needed. Paragraph IWE-1221(b) calls out ''testing for leak tightness using a gas medium test such as a Halide Detector test.'' The sensitivity required and acceptance criteria for this test should be specified. Both a bubble solution test and a helium mass spectrometer test are ''gas medium tests'', but their sensitivities could vary by a factor of 10/sup 6/. Development of training programs and qualification requirements for personnel who conduct the Appendix J containment leakage tests are also recommended.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5505506
- Report Number(s):
- EGG-M-31485; CONF-860507-7; ON: TI86011043
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
CONTAINMENT
CONTAINMENT SYSTEMS
ENGINEERED SAFETY SYSTEMS
IN-SERVICE INSPECTION
INSPECTION
LEAKS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
RECOMMENDATIONS
TESTING
THERMAL POWER PLANTS
220200* -- Nuclear Reactor Technology-- Components & Accessories
CONTAINMENT
CONTAINMENT SYSTEMS
ENGINEERED SAFETY SYSTEMS
IN-SERVICE INSPECTION
INSPECTION
LEAKS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
RECOMMENDATIONS
TESTING
THERMAL POWER PLANTS