ML20003F672

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Forwards Revision to Preoperational Test Program Modifying RCS Flow Measurement Test by Use of Elbow Tap Differential Pressure Instrumentation Which Provides Data for Full Flow Rate Calculation.Inclusion in FSAR by Amend 69 Indicated
ML20003F672
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 04/17/1981
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: Schwencer A
Office of Nuclear Reactor Regulation
References
NUDOCS 8104230332
Download: ML20003F672 (2)


Text

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TENNESSEE VALLEY AUTHORITY CH ATTANCOGA TENNESSEE 37401 400 Chestnut Street Tower II 4 ( f. r' [h April 17, 1981, h' ( I 'i()

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6'" C Director of Nuclear Reactor Regulation

'\\'b Attention:

Mr. A. Schwencer, Chief 9

Licensing Branch No. 2 Division of Licensing iNj l as U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Schwencer:

In the Matter of

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Docket No. 50-328 Tennessee Valley Authority

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Enclosed for your review is a revision to the Sequoyah Nuclear Plant (SNP) unit 2 preoperational test program.

The mactor coolant system (RCS) flow measurement test has been modified by the use of elbow tap differential pressure (d/p) instrumentation. This instrumentation will provide data for the calculation of the full flow reactor coolant flow rate. This test is completed after fuel loading.

This mvision will be incorporated into Table 14.1-1 of the SNP Final Safety Analysis Report by Amendment 69.

Very truly yours, TENNESSEE VALLEY AUTHORITY

'f h { % l d M. Mills, Manager Nuclear Regulation and Safety Sworn to and subscribed bpfore me thip/

day of T d d 1981

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'),o D %, n,c L '.,. c <.LL-kr, Notary Public

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My Co m.ission Expires N 3

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ENCLOSURE SEQUOYAH NUCLEAR PLANT UNIT 2 REVISED PREOPERATIONAL IEST RCS FLOW MEASUREMENT Test Prerequisites The RCS c:ust be in the hot shutdown mode with the reactor core in place.

All RC pumps must be operable. All instrumentation (including special instrumentation) is calibrated and available.

Test Objectives, Summary of Testing, and Acceptance Criteria Test objective is to obtain data for calculation of the ft:11 flow reactor coolent ficw rate as derived from the installed elbow tap differential pressure (d/p) instrumentation before initial criticality. The reactor coolant system design flow rate will be verified before escalation above 50 percent power using plant calorimetric data Acceptance criterion is that the flow rate must meet er exceed the funct!.onal design requirements specified in FSAR section 5.1.

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