ML20024F016

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Forwards Yankee Atomic Electric Co Safety Parameter Display Sys (Spds)
ML20024F016
Person / Time
Site: Yankee Rowe
Issue date: 09/01/1983
From: Kay J
YANKEE ATOMIC ELECTRIC CO.
To: Crutchfield D
Office of Nuclear Reactor Regulation
Shared Package
ML20024F017 List:
References
FYR-83-82, NUDOCS 8309080121
Download: ML20024F016 (2)


Text

Tebphone (617) 8778100 TWX 710-380u?619 YANKEE ATOMIC ELECTRIC COMPANY 2.C.2.1 y

FYR 83-82

  • YamnI'1 1971 Worcester Road, Framingham, Massachusetts 01701 es s.

September 1, 1983 United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention:

Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing

References:

(a) License No. DPR-3 (Docket No. 50-29)

(b) USNRC Generic Letter 82-33, dated December 17, 1982 (c) YAEC letter to USNRC, dated April 19, 1983 (FYR 83-44)

Subject:

Safety Parameter Display System (SPDS)

Dear Sir:

The attached report describes the Yankee SPDS, and includes descriptions of the hardware and sof tware, signal specification and alarm analysis, human factors analysis, and validation. The Yankee SPDS was installed in October, 1982 and has been operational since January, 1983. The development of the Yankee SPDS was a joint project with the Nuclear Safety Analysis Center (NSAC), operated by the Electric Power Research Institute (EPRI).

The selection of parameters, displayed on the SPDS, was based on the symptom-based critical safety function Emergency Operating Procedures and the methodology developed by NSAC for selecting safety console parameters on the basis of their relative importance to plant safety functions. The SPDS is fully integrated with the Critical Safety Function Procedures, and serves as an aid to the Shif t Supervisor; the main control board remains as the primary source of operator information.

The SPDS modifications do not involve an unreviewed safety question nor require changes to the plant Technical Specifications. Qualified safety-class isolators are installed to separate those, safety-class system inputs (process variables) from the non-safety-classified SPDS system. The attached report has been reviewed by the Nuclear Safety Audit and Review Committee.

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United States Nuclear Regulatory Commission September 1, 1983 Attention:

Mr. Dennis Crutchfield Page 2 We trust the information supplied in the attached report is satisfactory; however, if you have any questions or desire additional information, please contact us.

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Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY J. A. Kay Senior Engineer - Licensing JAK/dsm 1

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