Application of quality assurance program to safety related aging equipment or components
Creators
Description
This paper addresses how quality assurance programs and their criteria are applied to safety related and aging equipment or components used in commercial nuclear plant applications. The QA Programs referred to are 10CFR50 Appendix B and EPRI NP-5652. The QA programs as applicable are applied to equipment/component aging qualification, preventive maintenance, surveillance testing and procurement engineering. The intent of this paper is not the technical issues, methods and research of aging. The paper addresses QA program's application to age-related equipment or components in safety related applications. Quality Assurance Program 10CFR50 Appendix B applies to all safety related aging components or equipment related to the qualification program and associated preventive maintenance and surveillance testing programs. Quality Assurance involvement with procurement engineering for age-related commercial grade items supports EPRI NP-5652 and assures that the dedicated OGI is equal to the item purchased as a basic component to 10CFR50 Appendix B requirements
Additional details
Publishing Information
- Publisher
- PennWell Conferences and Exhibitions Co.
- Imprint Place
- Houston, TX (United States)
- Imprint Title
- POWER-GEN '90 conference papers: Volume 7 (Fossil plant performance availability and improvement) and Volume 8 (Nuclear power issues)
- Imprint Pagination
- 294 p.
- Journal Page Range
- p. 1319-1335.
Conference
- Title
- 3rd international power generation industries conference and exhibition.
- Acronym
- Power-Gen '90
- Dates
- 4-6 Dec 1990.
- Place
- Orlando, FL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24019579
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; BWR TYPE REACTORS; MAINTENANCE; MANAGEMENT; PERFORMANCE TESTING; PROCUREMENT; PWR TYPE REACTORS; QUALITY ASSURANCE; RADIATION EFFECTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY; SERVICE LIFE; SPECIFICATIONS
- Descriptors DEC
- BUSINESS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; LIFETIME; POWER REACTORS; REACTORS; SAFETY; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-901223--.