ML20137H837

Application for Amends to Licenses NPF-2 & NPF-8,revising Note 9 of Tech Spec Table 4.3-1 to Require Clearing of Trip Signal Prior to P-9 Setpoint.Fee Paid

ML20137H837
Person / Time
Site:	Farley
Issue date:	11/22/1985
From:	Mcdonald R ALABAMA POWER CO.
To:	Varga S Office of Nuclear Reactor Regulation
Shared Package
ML20137H843	List: ML20137H837 ML20137H873
References
TAC-60287, TAC-60288, NUDOCS 8512020488
Download: ML20137H837 (3)

Text

Malung AddrOss Glabama Power Company i

600 North 18th Street Post Office Box 2641 Birmingham, Alabama 35291 Telephone 205 783-6090 R. P. Mcdonald Senior Vice President Flintndge Building Alabama Power November 22, 1985 2

Docket Nos. 50-348 50-364 4

i Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.

20555 Attention:

Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Units 1 and 2 Proposed Technical Specification Change Gentlemen:

The Farley Nuclear Plant - Units 1 and 2 are required to have a reactor trip signal generated whenever there is a turbine trip during power operation as specified in Technical Specification 3.3.1, Table 3.3-1, Item

17. The surveillance testing requirement for the trip channels is provided in Technical Specification 4.3.1.1 Table 4.3-1, Item 17 which currently requires the trip channel functional test to be performed prior to each reactor startup, if not performed in the past 7 days, by verifying that the trip channels indicate a turbine trip prior to latching the turbine and no turbine trip after latching the turbine (Table 4.3-1, Note 9). The purpose of the surveillance requirements is to verify that the channels will provide an appropriate trip signal and also to ensure that the trip clears to permit power operation and to prevent a spurious challenge of the reactor trip system when above the P-9 setpoint which is less than or equal to 50% rated thermal power.

Clarification of the specification is desirable in that the surveillance requirement is tied to the latching of the turbine and the turbine throttle valves are not typically opened until after the turbine is latched and brought up to speed and control is transferred to the governor valves.

In order to remove this apparent ambiguity, Alabama Power Company hereby requests that-Note 9 of Technical Specification Table 4.3-1 be revised to require the clearing of the trip signal prior to the P-9 setpoint k

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Mr. S. A. Varga November 22, 1985 U. S. Nuclear Regulatory Cobission Page 2 (Technical Specification 2.~2.1, Table 2.2-1, Item 20.F) which is currently i.

permitted by the Limiting Conditions of Operation. Technical Specification 3.3.1, Table 3.3-1, Item 17 (Notes 7 and #) permits escalation in power to P-9 so long as the af fected channel is placed in the tripped condition.

- This proposed change, therefore, would have no effect on the Technical Specification block of reactor trip on turbine trip below the P-9 setpoint and continues to ensure that the plant will be operated within the limits of the accident analysis.

It should be noted that a load rejection from the P-9 setpoint is addressed as a Condition 1 - Normal Operation Event in the Farley FSAR and a:; such can be accommodated with margin between any plant parameter and the value of that parameter which would require either automatic or manual protective action.. Condition I Events do not, therefore, result in more severe operational transients. Attachment I lists the changed Technical Specification pages and includes the proposed pages for Units 1 and 2.

Since the proposed Technical Specification change includes no changes which would significantly increase the probability or consequences of an accident previously evaluated, no changes which create the possibility of a new or different kind of accident from any accidents previously evaluated and no changes which would involve a significant reduction in a margin of safety, it is considered by Alabama Power Company to not involve a significant hazards consideration as defined in 10CFR50.92. This conclusion is based upon the proposed clarification permitting plant operation within the existing FSAR limitations and current Technical Specification Limiting Conditions of Operation.

The Plant Operations Review Committee has reviewed this proposed change and the Nuclear Operations Review Board will review this proposed change at a future meeting.

Pursuant to 10CFR1/0.21, the rule on License Fees, the required License Amendment Application Fee of $150.00 is enclosed.

In accordance with 10CFRSO.90, three (3) signed originals and 40 copies of this request are enclosed. A copy of this change has been sent to Mr.

Dan Turner, the Alaban;a State Designee in accordance with 10CFR50.91(b)(1).

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Mr. S. A. Varga November 22, 1985 U. S. Nuclear Regulatory Comission Page 3 If there are any questions, please advise.

4 Very truly you l

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R. P. Mcdonald RPM /CJS:ddb-D39

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cc: Mr. L. B. Long SWORN TO AND SUBSCRIBED BEFORE ME Dr. J. N. Grace i

Mr. E. A. Reeves THI DAY OF

,1985 Mr. W. H. Bradford Mr. Dan Turner VLOA d.

'8 Notary Pubp rc My Comission Expires: 9-//-f8 i

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