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DOE-STD-1183-2004
c. Describe the requirements the contractor must perform to maintain the safety basis.
d. Discuss the purpose and determine the hazard categorization of an operating nuclear
facility.
e. Describe the exclusions types for radionuclides associated with hazard categorization
determination.
f.
Describe the differences between initial and final hazard categorizations and where these
designations occur in the DSA development process.
21. Nuclear safety specialists shall demonstrate a familiarity level knowledge of
Department of Energy (DOE) Order 420.1A, Facility Safety, DOE G 420.1-1, Nonreactor
Nuclear Safety Design Criteria and Explosive Safety Criteria Guide for use with DOE O
420.1 Facility Safety and DOE-STD-1020, Natural Phenomena Hazards Design and
Evaluation Criteria for Department of Energy Facilities, with respect to its impact on
Department nuclear safety.
Supporting Knowledge and/or Skills
a. Discuss the purpose and policy associated with DOE Order 420.1A, Facility Safety.
b. Discuss the role of Department nuclear safety specialists with respect to the implementation
of the requirements of DOE Order 420.1A, Facility Safety.
c. Discuss the Department policy and objectives with respect to safety-class and safety-
significant criteria.
d. Discuss the facility and activity applicability of DOE Order 420.1A, with respect to
implementation associated with the design of nuclear facilities.
e. Identify and discuss the use of DOE standards for seismic safety.
f.
Define PC-1, PC-2, PC-3 and PC-4 and its relationship to nuclear facility design and the
DSA.
g. Discuss aspects of fire protection, fire hazards analysis and its relationship to nuclear
facility design and the DSA.
h. Identify and discuss the strengths and weaknesses of methods utilized to analyze the
initiation and propagation of fires, and of their potential release of hazardous materials.
i.
Identify and discuss the methods used to determine the seismic hazard level to be used in
design.
j.
Identify and discuss the methods used to assess the structural response of structures and
determine whether safety systems may be expected to remain functional following an
earthquake of postulated intensity.
k. Identify the methods for evaluating the tolerance of structures and systems for natural
phenomenon.
22. Nuclear safety spe cialists shall demonstrate a working level knowledge of the
Technical Safety Requirements as described in 10 CFR 830.205, Technical Safety
16


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