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CLASSIFICATION OF THE MGR UNCANISTERED SNF DISPOSAL CONTAINER
Author(s) -
J.A. Ziegler
Publication year - 1999
Language(s) - English
Resource type - Reports
DOI - 10.2172/860264
Subject(s) - quality assurance , container (type theory) , spent nuclear fuel , environmental science , waste management , engineering , computer science , operations management , mechanical engineering , external quality assessment
The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) uncanistered spent nuclear fuel (SNF) disposal container system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998)

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