ML20101S667

Forwards Proprietary & Nonproprietary Westinghouse Rept, Design Process of Farley Status Tree Monitoring Sys Display & Nonproprietary Safety Analysis Background.... Proprietary Rept Withheld (Ref 10CFR2.790)

ML20101S667
Person / Time
Site:	Farley
Issue date:	01/31/1985
From:	Mcdonald R ALABAMA POWER CO.
To:	Varga S Office of Nuclear Reactor Regulation
Shared Package
ML19269A987	List: ML20101S667 ML20101S676 ML20101S684
References
RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8502050580
Download: ML20101S667 (2)

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_ Alabama Power Company PR0PRIETARY 600 North 18th Street MATERIAL TRANSMITTED HEREWlTH "Br*i ha A ab a 35291 CONTAINS 2.700 INFORMATION Telephone 205 7834090 R. P. Mcdonald ML;**2%d!"' Alabama Power

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January 31, 1985 Docket Nos. 50-348 50-364 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 Safety Parameter Display System (SPDS)

Safety Analysis Background'and Human

-Factors Criteria Gentiemen:-

By letter dated April 4,1984, the NRC Staff provided comments on

.the Alabama Power Company SPDS Safety Analysis dated November 30, 1983.

Alabama Power Company responded to the NRC Staff comments by letter dated May 11, 1984. In this letter, Alabama Power Company comitted to provide the NRC Staff with a description of'the human factors review results for the Farley SPDS design. The purpose of this description was to identify .the human factors criteria incorporated into the SPDS design to ensure that the displayed information is readily perceived, easily

- comprehended, and is not misleading .to the SPDS users. Attachment 1 Design Process of the Farley Status' Tree Monitoring System Displays,

.provides this description.

In the May'11, 1984 letter, Alabama Power Company also committed to provide a listing of the critical safety functions, an identification of

-SPDS ' parameters used to satisfy each critical safety function, and a discussion of how each parameter'and setpoint satisfies its critical *

. safety function requirements. It was stated that the basis for the

. selection of the Farley critical safety functions and the relationship of these functions to the functional criteria in NUREG-0737 -Supplement I would be provided. Attachment 2, Safety Analysis Background for Farley g

' Units 1 and 2,-contains this basis.

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Mr. S. A. Varga January 31, 1985 U. .S. Nuclear Regulatory Comission Page 2 Attachment 1 contains Westinghouse proprietary information. In conformance with the requirements of 10CFR Section 2.790 of the Comission's regulations, a Westinghouse affidavit is enclosed. It is requested that the Westinghouse proprietary information be withheld from public disclosure by the Commission.

Correspondence with respect to the proprietary aspects of the Westinghcuse affidavit should reference CAW-84109, and be directed to R. A. Wiesemann, Manager, Licensing Programs, Westinghouse Electric Corporation.

If there are any quastions, please advise.

Yours very tr ,

R. P. Mcdonald RPM /JLO:bdy-D6 Attachments Enclosure cc: Mr. L. B. Long Mr. J. P. O' Reilly Mr. E. A. Reeves Mr. W. H. Bradford l