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NUREG-1537, Part 2 - NRC

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CHAFIE 7<br />

* The sensitivity of each sensor channel should be commensurate with the )<br />

precision and accuracy to which knowledge of the variable measured is<br />

required for the protective function.<br />

The automatic reactor runback or shutdown (scram) subsystem should be<br />

fail-safe against malfunction and electrical power failure should be as close<br />

to passive as can be reasonably achieved, should go to completion once<br />

initiated, and should go to completion within the time scale derived from<br />

applicable analyses in the SAR.<br />

* The RPS should be designed for reliable operation in the normal range of<br />

environmental conditions anticipated within the facility.<br />

* The scram operator should be able to operate the system by means of<br />

readily available switches, or by interlock activation.<br />

* The scram system should be designed to annunciate the channel initiating<br />

the action, and to require resetting to resume operation.<br />

* The scram system should be designed to maintain reactor shutdown<br />

without operator action to at least the shutdown margin as defined in<br />

Chapter 4 and the technical specifications.<br />

* The RPS function and time scale should be readily tested to ensure<br />

operability of at least minimum protection for all reactor operations.<br />

* Information about the RPS detector or sensor devices should be sufficient<br />

to verify that individual safety limits are protected by independent channels,<br />

and that LSSS and LCO settings can be established through analyses and<br />

verified experimentally.<br />

* Hardware and software for computerized systems should meet the<br />

guidelines of 7-4.3.2-1993 and RG 1.152, Revision 1, and software<br />

should meet the guidelines of ANSVANS 10.41987 applicable to nonpower<br />

reactor systems. ANSI/ANS 15.15-1978 and draft ANSIANS<br />

15.20 are useful as general guides for the design, implementation, and<br />

evaluation of I&C systems for non-power reactors and should be used<br />

where applicable.<br />

* Consult <strong>NRC</strong> Generic Letter 95-02 for I&C systems that are being<br />

upgraded to systems based on digital technology.<br />

<strong>NUREG</strong>-<strong>1537</strong>.PART2 7-12 REV 0,2/96<br />

<strong>NUREG</strong>-<strong>1537</strong>,PART2 7-12 REV 0, 2/9<br />

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