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NUREG-1537, Part 2 - NRC

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CHAFIER 7<br />

* The control console, display instruments, and equipment should be readily ><br />

testable and capable of being accurately calibrated.<br />

* The designed range of operation of each device should be sufficient for the<br />

expected range of variation of monitored variables under conditions of<br />

operation.<br />

When required by the safety analysis, the control console instruments and<br />

equipment should be designed to assume a safe state on loss of electrical<br />

power or should have a reliable source of emergency power sufficient to<br />

sustain operation of specific devices.<br />

* The bases for technical specifications, including surveillance tests and<br />

intervals for control console devices, should be discussed in this section of<br />

the SAR<br />

* The outputs and display devices showing reactor nuclear status should be<br />

readily observable by the operator while positioned at the reactor control<br />

and manual protection systems.<br />

* Control, safety, and transient rod position indication and limit lights should<br />

be displayed on the console and should be readily accessible and<br />

understandable to the reactor operator.<br />

* Other controls and displays of important parameters that the operator<br />

should monitor to keep parameters within a limiting value, and those which<br />

can affect the reactivity of the core should be readily accessible and<br />

understandable to the reactor operator.<br />

* Annunciators or alarms on the control console should clearly show the<br />

status of systems such as operating systems, interlocks, experiment<br />

installations, pneumatic rabbit insertions, ESF initiation, radiation fields and<br />

concentration, and confinement or containment status.<br />

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

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

should meet the guidelines of ANSIIANS 10.4-1987 that apply to nonpower<br />

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

15.20 are general guides for the design, implementation, and evaluation of<br />

I&C systems for non-power reactors and should be used where applicable.<br />

The reviewer should consult Generic Letter 95-02 for guidance on I&C<br />

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

<strong>NUREG</strong>-<strong>1537</strong>, PART2 7-18 REV 0, 2/96

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