CLASSIFICATION OF THE MGR NAVAL SPENT NUCLEAR FUEL DISPOSAL CONTAINER | Zendy

J.A. Ziegler | Zendy

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CLASSIFICATION OF THE MGR NAVAL SPENT NUCLEAR FUEL DISPOSAL CONTAINER

Author(s) -

J.A. Ziegler

Publication year - 1999

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/860261

Subject(s) - quality assurance , container (type theory) , spent nuclear fuel , environmental science , waste management , nuclear fuel , engineering , nuclear engineering , 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) naval spent nuclear fuel 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 (YMF 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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