ML19317D735

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Responds to AEC 730307 Request for Review of Control Circuits & safety-related Equipment.Analysis Concludes That Disabling of One Component Does Not Render Redundant Components Inoperable
ML19317D735
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 05/03/1973
From: Thies A
DUKE POWER CO.
To: Schwencer A
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 7912100503
Download: ML19317D735 (1)


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Oconee Nuclear Station Docket Nos. 50-269, -270, and -287

Dear Mr. Schwencer:

Please reference your letter of March 7, 1973 which requests that we perform a review of all control circuits and safety-related equipment to assure that disabling of one component does not through incorporation in other interlocking or sequencing controls render other components inoperable.

Duke Power Design Engineering and Babcock & Wilcox have performed the requested analysis and have determined that the disabling of one com-ponent does not render other redundant components inoperable. All modes of test, operation, and failure were considered in the analyses. Systems l

that were reviewed in the analysis were the Reactor Protective System, Nuclear Instrumentation, Engineered Safeguards Protective System, Control Rod Drive System, Emergency Power Systems, and Emergency Power Switching Logic Systems.

We have also reviewed our station procedures to ensure that they will require that whenever a safety-related system or component is removed from service, the redundant system or component is functionally tested before or immediately after the system or component is removed from service. Our review indicates that our procedures are adequate in this respect.

Sincerely, A. C. Thies ACT:vr

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