ML20215A262

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Amended Page 81 to Proposed Tech Specs,Consisting of Proposed Change 85-13,requiring Addl Surveillance Should Plant Continue Operation W/More than Three Control Rods Taking Greater than 7 to Scram
ML20215A262
Person / Time
Site: Pilgrim
Issue date: 12/05/1986
From:
BOSTON EDISON CO.
To:
Shared Package
ML20215A142 List:
References
NUDOCS 8612110229
Download: ML20215A262 (1)


Text

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b. The control rod directional been reduced to less than three control valves for and if it has been demonstrated inoperable control rods that control rod drive mechanism shall be disarmed collet housing failure is not electrically and the control cause of an immovable control rods shall be in such rod.

positions that Specification 3.3.A.1 is met.

c. Control rod drives which are fully inserted and electrically disarmed shall not be considered inoperable.
d. Control rods with scram times greater than those permitted by Specification 3.3.C.3 are inoperable, but if they can be moved with control rod drive pressure they need not be disarmed electrically.
e. During reactor power operation, the number of inoperable control rods shall not exceed eight.

Specification 3.3.A.I must be met at all times.

f. If plant operation is continued with three (3) or more control rods with maximum scram insertion times in excess of 7.00 B. Control Rods seconds, perform the surveillance requirement of 1. The coupilng integrity shall be Section 4.3.C.2 at least verified for each withdrawn once per 60 days. control rod as follows: 1 B. Control Rods a. When the rod is withdrawn the first time subsequent to each
1. Each control rod shall be refueling outage or after coupled to its drive or maintenance, observe completely inserted and the discernible response of the control rod directional or nuclear instrumentation.

control valves disarmed However, for initial rods electrically. This requirement when response is not does not apply in the refuel discernible, subsequent condition when the reactor is exercising of these rods vented. Two control rod drives after the reactor is critical may be removed as long as shall be performed to verify Specification 3.3.A.1 is met, instrumentation response.

81 Amendment No.

8612110229 861205 3 DR ADOCK 0500