ML20099L530

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Forwards Page 29 to 841115 Proposed Revised Pages to Tech Specs for Renewal of License R-119.Page Inadvertently Omitted from Transmittal
ML20099L530
Person / Time
Site: 05000087
Issue date: 11/27/1984
From: Nardi A
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To: Thomas C
Office of Nuclear Reactor Regulation
References
LA-84-120, NUDOCS 8412010159
Download: ML20099L530 (2)


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\,.a/ LA 84-120 Westinghouse Water Reactor Ba 355 Pittsbur@ Pennsylvarna 15LO 0355 Electric Corporation Divisions November 27, 1984 U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Washington, D. C. 20555 Attention: Mr. Cecil 0. Thomas, Chief Standardization and Special Projects Branch Gentlemen:

Subject:

Submittal of Revised Technical Specifications for Renewal of License Number R-119 (Docket 50-87).

Reference:

Letter No. LA 84-113 from A. J. Nardi to Cecil 0. Thomas, dated November 15, 1984.

By the above referenced letter, Westinghouse submitted revised pages to the Proposed Technical Specification for renewal of License R-119 (Docket 50-87).

Page 29 inadvertently was not included in that transmittal. It is attached to this letter to complete the transmittal.

If yoe have any questions, please contact me at the above address or by telephoneon(412)374-4652.

Very truly yours, bf .

AJN/jh A. J. Nardi, Manager NES License Administration Attachment Copies Transmitted: 3 notarized & 19 conformed COMM0NWEALTil 0F , PENNSYLVANIA)

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8. Temperature coefficient of reactivity (two years).

C. Reactor power calibration (semiannually).

2. The reactor moderator-shield water quality shall be determined monthly.

Bases i

l Measurements of the above core parameters are made when a new reactor configuration or composition is assembled. Whenever the core configuration or composition is astered, the core parameters are evaluated to assure that they are within the limits of these specifications and the values analyzed in the SAR. During the initial startup test period of the reactor, measurements and determinations of the core parameters will be .

made for all standard assemblies which are to be utilized in the reactor's operational programs. Verification of these parameters are made periodically to assure that changes have not taken place.

Past experience indicates that monthly measurements of the moderator-shield water quality are adequate to comply with the requirement of specification 3.2, item 2.

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