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NUREG-1537, Part 2 - NRC

NUREG-1537, Part 2 - NRC

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EraNEm SArFEY FEATuRES<br />

* The ECCS is designed and technical specification requirements and<br />

procedures exist for periodic surveillance and testing to ensure its<br />

operability and availability.<br />

* The design of the ECCS is adequate for operation at the required flow rate<br />

and time interval as determined by the accident analysis. The design also<br />

considered the availability of normal electrical power and coolant sources<br />

and provided for alternative sources, if necessary.<br />

* The functioning of the ECCS as designed reasonably ensures that a LOCA<br />

at the reactor facility would not subject the public, the environment, or the<br />

facility staff to unacceptable radiological exposure.<br />

6.3 References<br />

American National Standards Institute/American Nuclear Society,<br />

ANSI/ANS 15.7, 'Research Reactor Site Evaluation," 1977.<br />

Atomic Safety and Licensing Appeal Board, In the Matter of Trustees of Columbia<br />

University in the City of New York, May 18, 1972.<br />

REV 0,2196 6-13 STtwu REVIEW PLAN<br />

REV 0, 296 6-13 STANDARD REViEwPLAN

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