ML20077G691
| ML20077G691 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/18/1991 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20077G687 | List: |
| References | |
| NUDOCS 9107020183 | |
| Download: ML20077G691 (2) | |
Text
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PROPOSED TECilNICAL SPECIFICATION CllANGES i i
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9107020183 91061G PDR ADOCK 05000313 P FDR
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. 3.5 INSTRUMENTATION SYSTEMS 3.5.1 Onorational Safety Instrumentation Applicability Applies to unit instrumentation and control systems. -
Objectives To delineate the conditions of the unit instrumentation and safety circuits necessary to assure reactor safety.
Specificat19ng 3.5.1.1 Startup and operation are not permitted unless the requirements of Table 3.5.1-1, columns 3 and 4 are met.
3.5.1.2 In the event the number of protection channels operable falls l below the limit given under Table 3.5.1-1, Columns 3 and 4, operation shall be Ifmited as specified in Column 5.
3.5.1.3 For on-line testing or in the event of a protection instrument or channel failure, a key operated channel bypass switch associated with each reactor protection channel will be used to lock the channel trip relay in the untripped state as indicated by a light. Only one channel shall be locked in this.untripped state at any one time. Only one channel bypass key shall be accessible for use in the control room.
3.5.1.4 The key operated shutdown bypass switch associated with each reactor protection channel shall not be used during reactor power operation except during channel testing. l 3.5.1.5 During startup when the intermediate range instruments come on scale, the overlap between the intermediate range and the source range instrumentation shall not be less than one decade. If the overlap is less than one decade, the flux level shall be maintained in the source range until the one decade overlap is achieved.
j 3.5.1.6 In the event that one of the trip devices in either of the sources supplying power to the control rod drive mechanisms fails in the untripped state, the power supplied to the rod drive mecheaisms through the failed trip device shall be manually removed within 30 minutes following detection. The condition will be corrected and the remaining trip devices shall be tested within eight hours following detection. If the condition is not corrected and the remaining trip devices are not tested within the eight-hour period, the reactor shall be placed in the hot shutdown condition within an additional four hours.
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Amendment No. 42 i