ML20077R936

Proposed Tech Spec 4.2 Re Reactivity Control

ML20077R936
Person / Time
Site:	Oyster Creek
Issue date:	08/19/1991
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20077R932	List: ML20077R924 ML20077R934 ML20077R936
References
NUDOCS 9108260238
Download: ML20077R936 (1)

Text

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,' ,4.2 REACTIVITY CONTROL hrpligahl.1111: Applies to the surveillance requirements for reactivity control.

obiective: To verify the capability for controlling reactivity.

Erggificati2D A. Following a reactor refueling when core alterations were performed, sufficient control rods shall be withdrawn to demonstrate with a margies of 0.25% A k that the core can be made suberitical at any time in the subsequen* fuel cycle with the strongest operable control rod fully withdrawn and all other operable rods fully inserted.

D. The control rod drive housing support system shall be inspected after reassembly.

C. -1. After each major ronctor refueling and prior to resuming power l

operation, all operable control rods shall be ucram time tested from the fully withdrawn position with reactor pressure above 800 psig.

2. Following each reactor scram from rated pressure, the mean 90s insertion timo shall be determined for eight selected rods. If the mean 904 insertion time of the selected control rod drives does not fall within the range of 2.4 to 3.1 seconds or the measured scram tima of any one drive for 90% insertion does not  !

fall within the range of 1.9 to 3.6 seconds, an evaluation shall [

be made to provide reasonable assurance that proper control rod  !

drive performance is maintained.  !

3. Following eny outage not initiated by a reactor scram, eight rods [

shall be scram tested with reactor pressure above 800 poig [

.provided these have not been measured in six months. . The same l criteria of 4.2.C(2) shall apply.  :

E D. Each partially or fully withdrawn control rod shall be exercised at least once each week. This test shall be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the event of power operation is continuing with two or more inoperable control rods or in the event power operation is  !

continuing with one fully or partially withdrawn rod which cannot be  !

moved and int which control rod drive mechanism damage has not been .

ruled out. The surveillance need not be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if  !

the number of inoperable rods has been reouced to less than two and if i it has been demonstrated tnat control rod drive mechanism collet housing failure is not the cause of an immovable control rod.

E. . surveillance of the standby liquid control system shall be as follows:

1. pump operebilityonce/ month j

2. Boron concentrationonce/ month l determination ,

h corrected: 12/24/84 OYSTER CREEK 4.2-1 Amendment No.: 13, 75, 144 r

- 9108260239 DR 910920 ADOCK 05000219 L PDR l' -

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