ML20210C877

Requests Meeting to Resolve Position Re Tests to Demonstrate Design Adequacy of Wiring Separation within Instrumentation & Control Protection Racks,Per 840807 Meeting

ML20210C877
Person / Time
Site:	Diablo Canyon, South Texas, 05000000
Issue date:	08/19/1975
From:	Eicheldinger C WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Rusche B Office of Nuclear Reactor Regulation
Shared Package
ML20210C503	List: ML20210C551 ML20210C605 ML20210C626 ML20210C658 ML20210C672 ML20210C677 ML20210C850 ML20210C877 ST-HL-AE-2035, Forwards Responses to Solid State Protection Sys (Ssps) Items Identified in Audit on 870128-30 & Discussion of Noise Fault Testing Performed on Ssps.Supporting Info,Including Correspondence Between PG&E & NRC Also Encl
References
NS-CE-737, NUDOCS 8705060354
Download: ML20210C877 (2)

Text

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'estinghouse Electric Corporation Power Systems anzs nneu@PmyWta1522 t

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fl' 0- SEP*t Mr. B. C. Rusche, Director -

Office of I!uclear Reactor Regulation __

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U. S. fluclear Regulatory Comission y '

Washington, D.C. 20555 L

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Dear Mr. Rusche:

k' {, .'7(i; i At the generic meeting a year ago (August 7,1974) Westinghouse addressed F NRC.(EICSB) concerns about wiring separatinn within the I and C protection

.$ racks. It was then agreed that Westinghouse perform additional tests to F

demonstrate that credible electrical faults or noise induced on control cables external to the racks could not degrade protection system perform-ance below an acceptable level. In support of the Diablo Canyon appli-

cation. Westinghouse prepared for technical review a report on tnese tests.

(" Westinghouse Protection Systems floise Tests" - December,1974). In the tests, the fluclear Instrumentation, Solid State Protection and 7100 Series 4 Process Control Systems were subjected to electrical faults and induced

. currents beyond those which could be reasonably postulated to occur.

F The results and conclusions have been accepted by the Staff and Westinghouse

. considers the tests applicable to all plants with these systems.

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• At present, assessment of the 7300 Series Process Control System design k employed in newer plants, such as North Anna, Joseph M. Farley, William B. McGuire, Catawba, includes a continuing evaluation by Westinghouse h against current criteria as well as t!RC concerns. Since these plants employ the fluclear Instrumentation and Solid State Protection Systems

[ previously tested, as described above Westinghouse has proposed additional testing to verify the 7300 Series Process Control System design only.

t In general, industry standards and llRC Regulatory Guides provide for

analyses or tests to demonstrate design adequacy. Westinghouse is in F conformance with the applicable criteria in exercising the option to test the. subject design as implemented. ,

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Rev'd Off. of D{r, of .'.*ut!ct:r Reactor

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t EICSB reviewers have asserted that this option is no longer acceptable a

for the 7300 Series Process Control System. While we strongly disagrec

! with this pos'ition, it is our desire to resolve the issue to our mutual  ;

satisfaction. Since many Westinghouse plants are affected, it is our '

' desire to meet with appropriate members of your Staff to ' discuss this .

matter generically to determine a proper resolution.

) Your prompt reply will be appreciated. .

Very truly yours, .

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nager p.Nuclear Eiche1dinger, Safety Department p J

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