Recycling facility periodic safety review: Application of a methodology used for the nuclear criticality safety review of geometrically safe or favorable equipment - 14610
Creators
- 1. Areva NP, 1, rue des Herons, 78180 Montigny-le-Bretonneux (France)
- 2. Areva NC La Hague, 50444 Beaumont-Hague Cedex (France)
- 3. Areva NC, Tour Areva, 1 Place Jean Millier 92084 Paris La Defense Cedex (France)
Description
In France, for all fuel cycle facilities, the reference safety frame is continuously adapted to take into account technical developments such as changes in process and/or maintenance operations. Every ten years according to French law, the facility operator is required to launch a process of Periodic Safety Review (PSR), whose conclusions are sent to the Nuclear Safety Authority (NSA). This PSR is split in two parts: first, a review of the facility to its safety documentation and authorization, second, a safety reassessment. Actually, this PSR takes account for topics (actual aging for instance) which require several years of feedback from experience to be integrated in safety evaluations, or which cannot be done on a daily basis (documentation reorganization). It also incorporates the new regulatory safety requirements. A specific methodology was developed for the first PSR of UP3-A since the publication of the law. UP3-A is a used fuel reprocessing facility of La Hague plant. This methodology, adapted for large plants with numerous process and fissile media, is based on a two-step approach intending to focus the analysis on the real hard spots. First, 'sensitive' systems are identified. Second, a specific review is performed on these systems. After a reminder of the methodology, this paper presents the results of its application on the UP3-A scope. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 978-0-89448-723-1
- Imprint Pagination
- 10 p.
Conference
- Title
- 2015 International Conference on Nuclear Criticality Safety
- Acronym
- ICNC 2015
- Dates
- 13-17 Sep 2015
- Place
- Charlotte, NC (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 53017460
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRITICALITY; FUEL CYCLE; MAINTENANCE; RECYCLING; REPROCESSING; SAFETY ANALYSIS; SAFETY REPORTS
- Descriptors DEC
- SEPARATION PROCESSES
Optional Information
- Notes
- 7 refs.; available on CD Rom from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)