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| DOE-STD-6003-96
without human intervention for the period specified in the safety analysis and for as
long a period as practical following shutdown of the fusion device.
h. Unavailability of the on-site electrical power supply or the off-site power supply should
be a consideration in ensuring safety-class cooling system functions, assuming a sin-
gle failure within the cooling system. Coincident failure of off-site and on-site power
systems should not be a design consideration.
i.
Cooling system design should consider the thermal, hydraulic, and mechanical effects
of unintended operation of active components, such as valves and pump motors.
j.
Cooling system design should consider the thermal, hydraulic, and contamination
effects of cross leaks between adjacent systems, such as the primary and secondary
sides of a heat exchanger.
k. Materials properties for cooling systems should include the effects of radiation embrit-
tlement at all levels of service temperatures.
l.
Coolant system pumping should provide for coolant flow coastdown to prevent
exceeding design limits.
m. Discharge of coolant for pressure relief should be to a confinement tank that maintains
the confinement function of the coolant system.
n. The coolant system should include protection for overpressure to prevent degradation
of safety function.
o. The coolant system should include provisions for sampling to analyze coolant proper-
ties and to identify entrained radioactivity or other contaminants.
p. Use of a primary cooling system and a secondary cooling system is the recommended
design for containment of radioactivity where required by the safety analysis. Closed
heat exchangers are the recommended coupling between primary and secondary
cooling systems.
q. Multiple cooling loops are recommended for consideration as a design feature to
reduce the operational thermal-hydraulic transient associated with single-loop failure.
r.
Components and headers of systems should be designed to provide individual isola-
tion capabilities to ensure system function, control system leakage, and allow system
maintenance.
s. The use of leak-before-break may be considered in the analysis of pipe break and
pipe whip events. The methodology described in Section 3.6 of the Standard Review
Plan, NUREG-0800 is recommended.
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