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NUREG-1537, Part 2 - NRC

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TEcHnICAL SpEcmcAnoms<br />

* The staff has evaluated the applicant's (or licensee's) technical<br />

specifications in this licensing action. These technical specifications<br />

define certain features, characteristics, and conditions governing the<br />

operation of the (insert none) facility and are explicitly included in<br />

the (renewal) license as Appendix A. The staff has reviewed the<br />

format and contents of the technical specifications using the<br />

guidance of ANSI/ANS 15.1-1990, 'Development of Technical<br />

Specifications for Research Reactors," and <strong>NUREG</strong>-<strong>1537</strong> (<strong>Part</strong> 1),<br />

'Guidance for Preparing and Reviewing Applications for the<br />

Licensing of Non-Power Reactors: Format and Content,"<br />

February 1996.<br />

The staff finds the technical specifications acceptable and concludes<br />

that normal plant operation within the limits of the technical<br />

specifications will not result in offaite radiation exposures in excess<br />

of 10 CFR <strong>Part</strong> 20 guidelines and reasonably ensures that the<br />

facility will function as analyzed in the safety analysis report.<br />

Furthermore, adherence to the technical specifications will limit the<br />

likelihood of malfunctions and mitigate the consequences to the<br />

public of off-normal or accident events.<br />

References<br />

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

ANSYIANS 15.1, "The Development of Technical Specifications for Research<br />

Reactors," ANS, LaGrange Park, Illinois, 1990.<br />

U.S. Nuclear Regulatory Commission, <strong>NUREG</strong>-<strong>1537</strong> (<strong>Part</strong> 1), "Guidelines for<br />

Preparing and Reviewing Applications for the Licensing of Non-Power Reactors:<br />

Format and Content," Februazy 1996.<br />

REV 0,2/96 14-3 STANrD REVIEW PLAN<br />

REV 0, 2/96 14-3 STANDARD REvEFw PLAN

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