Industry current and future plans for implementation of proposed revision of 10 CFR Part 50, Appendix J, Containment Leak Rate Testing
Creators
Description
The Nuclear Regulatory Commission (NRC) has proposed revision of the Containment leak rate testing requirements as specified in 10 CRF Part 50, Appendix J, Leakage Rate Testing of Containments of Light-Water Cooled Nuclear Power Plants, as described in documents released to the NRC Public Document Room on January 10, 1992. It is the authors understanding that this proposed revision of Appendix J reflects the staff disposition of public comments that is in process of review by the Commissioners. The industry has maintained a continuing dialogue with the NRC through public forums such as interactions of the boiling water reactor nuclear steam supply systems Owners Group, the ANS 56.8 Committee, Containment Leak Rate Test Work Shops and, since 1991, as a generic issue through Nuclear Management and Resources Council/NRC meetings. This dialogue has positively contributed to a communication and understanding of methods and issues that can facilitate containment leak rate testing. The industry's review of the proposed Appendix J revision indicates that resolution of certain aspects of the revision could further reduce contamination, exposure and unnecessary use of resources without any reduction in the health and safety of the public
Additional details
Publishing Information
- Imprint Title
- Proceedings of the fifth workshop on containment integrity
- Imprint Pagination
- 646 p.
- Journal Page Range
- p. 579-582.
- Report number
- NUREG/CP--0120
Conference
- Title
- 5. workshop on containment integrity for nuclear power plants.
- Dates
- 12-14 May 1992.
- Place
- Washington, DC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24027169
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT SYSTEMS; DOCUMENTATION; FISSION PRODUCT RELEASE; IMPLEMENTATION; LEAK TESTING; LEAKS; PIPES; PWR TYPE REACTORS; REACTOR INSTRUMENTATION; REACTOR SAFETY; RELIABILITY; REPORTING REQUIREMENTS; STANDARDIZATION; US NRC
- Descriptors DEC
- CONTAINMENT; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTORS; SAFETY; TESTING; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- SAND--92-0173; CONF-920541--.