ML20099C929

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Forwards Response to NRC 841031 Request for Info Re Safety Parameter Display Sys Electrical Isolation Device Compliance W/Environ & Seismic Qualifications Which Were Basis for Licensing of Plant
ML20099C929
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 11/13/1984
From: Mcdonald R
ALABAMA POWER CO.
To: Varga S
Office of Nuclear Reactor Regulation
References
TAC-51088, TAC-51089, NUDOCS 8411200121
Download: ML20099C929 (2)


Text

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'.Malling Address ..

- Alabama Power Company p 4' 600 North 13h Street '

- Post Office Box 2641 -

Birmingham. Alabama 35291 ^

- Telephone 205 7_83-6090 .

R. P. Mcdonald Senior Vice President -

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1 November 13.-1984 Docket Nos.~50-348 -

50-364 Director, Nuclear Reactor Regulation

-U. S. Nuclear l Regulatory Commission Washingte . D.-.C.- 20555 Attention: Mr. S. A. Varga -

Joseph M. Farley Nuclear Plant - Units'1 and 2.

SPDS Electrical-Isolation Device Qualifications Gentlemen:

On October 31,1984,'a telephone conversation was held between the NRC Staff and Alabama Power Company personnel regarding the SPDS ..

electrical isolation device qualifications. During this conversation the NRC . Staff requested .that Alabama Power Company address the electrical isolation device compliance with the environmental and seismic qualifications which were the basis for the licensing of the Farley Nuclear Plant. The response to this request is attached.

If there are any questions, please advise.

Yours truly, R. P. Mc90nald n RPM /JLO:bdh-D16 Attachment cc:. Mr. L. B. Long-Mr. . J. P. 0' Reilly .

Mr. 'E. A. Reeves

..Mr. W. H. Bradford' ,

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SPDS . Iso 1'ation Device Qualification' s g.. .

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NRC Request: Provide a commitment' that' the isolation devices comply 1

- ~ with the-environmental. qualifications)(10 CFR 50.49)l and-

.the; seismic; qualifications which were the-basis ~ for: .

C plant. licensing. -

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APCo-Response:1: All' analog SPDS input" signals orginating.from existing ,

. Class IE: instrumentation loops are designed to be _ ,

. provided with Westinghouse' 7300 system isolatton. devices located in the-Westinghouse 7300 process control and-instrumentation system cabinets. The Westinghouse 7300 -

cabinets are . located:in a mild environment and are . .

4 excluded from the scope of 10CFR50.49. :The Westinghouse .

seismic qualification of the'7300 cabinets is documented in WCAP-7817 Supplement 4-and complies
with the
requirements.of IEEE 344-1971 which is the licen' sing 1 basis for the' Farley Nuclear Plant.

The existing core. exit thermocouple (CET) analog si.gnals.- ~

, are not designed and installed as Class' IE-

instrumentation loops. To comply with the :R.G.1.97 .

Category 1 variable design criteria, the CET-cabling _and s

, signal processing will be upgraded. The isolation and

-interface criteria for R.G.'1.97 Category 1= variables will be followed in _ designing the method of acquiring the SPDS CET input signals from the'CET.R.G. l.97. -

instrumentation loops. -This isolation ~ and interface

- criteria.is described in Alabama Power-~ Company's R.G.

1.97 Compliance Reports dated June-29,1984 for-Unit l' and March 30,'1984 for Unit 2.  :

The CET SPDS signal isolation devices will be qualified.

.to-the' requirements of IEEE 344-1975 and will be located F in a mild environment. Supporting sei smic ' qualification documentation will be available after procurement of the' upgraded inadequate core cooling monitoring system.

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