ML20236G983

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Proposed Tech Specs,Incorporating New Requirement That Each Operable Control Rod Be Subjected to Scram Time Test After Reactor Shutdown Greater than 120 Days
ML20236G983
Person / Time
Site: Pilgrim
Issue date: 07/24/1987
From:
BOSTON EDISON CO.
To:
Shared Package
ML20236G837 List:
References
NUDOCS 8708050020
Download: ML20236G983 (1)


Text

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~ LIMITING CONDITION FOR OPERATION SURVEILLANCE RE0(IIREMENT

'353.B Control Rodi 4.3.B Control Rodl

4. Control rods shall not be
4. Prior to control rod. with-withdrawn for startup or drawal for startup or refueling unless at least two during refueling, verify source range channels have an that at least two source observed count rate equal to range channels have an or greater than three counts observed _ count rate of at per second.

least three counts per second.

5. During operation with limiting
5. When a limiting control rod control rod patterns, as pattern exists, an.instru-determined by the Reactor ment functional test of the Engineer, either:

RBM shall be performed prior to withdrawal of the

'a. Both RBM channels shall be designated rod (s) and operable: or daily thereafter.

b. Control rod withdrawal shall i

be blocked:

or

c. The operating power level shall be limited so that the

'MCPR will remain above the Safety Limit MPCR assuming a single error that results in t

complete withdrawal of any single operable control rod.

C. Scram Insertion Times Scram Insertion Times

1. The average scram insertion
1. Following each refueling time, based on the deenergi-outage, or after a zation of the scram pilot valve reactor shutdown that solenoids as time zero,of all is greater than 120 days, operable control rods in the each operable control reactor power operation condi-rod shall be subjected tion shall be no greater than:

to scram time tests from the fully withdrawn

% Inserted Average Scram position.

If testing is From Fully Insertion not accomplished with the Hithdrawn Times (set) nuclear system pressure above 950 psig, the 10

.55 measured scram insertion 30 1.275 time shall be extrapolated 50 2.00 to reactor pressures above 90 3.50 950 psig using previously determined correlations.

Testing of all operable control rods shall be com-pleted prior to exceeding 40% rated thermal power.

i Amendment No.

83 8708050020 870724 PDR ADOCK 05000293 p

PDR

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