ML19350B946

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Notifies That Description of Conformance of Subcooling Monitor to Reg Guide 1.97 Will Include Assessment of Core Exit Thermocouples Using Attachment 1 to Item II.F.2 in NUREG-0737
ML19350B946
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
Issue date: 03/18/1981
From: Parker W
DUKE POWER CO.
To: Harold Denton, Youngblood B
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM NUDOCS 8103240455
Download: ML19350B946 (2)


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.*'"'"[.*[j,2l Mr. Harold R. Denton, Director I:~,c Office of Nuclear Reactor Regulation

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Attention:

B. J. Youngblood, Chief L]

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Licensing Projects Branch No. 1

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Re: McGuire Nuclear Station D'

Docket Nos. 50-369, 50-370 N

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Dear Mr. Denton:

In our respons'e to Item'II.F.2 in my letter of March 9, 1981, it was stated that a description of the conformance of the Subcooling Monitor to R.G. 1.97 would be submitted by April 23, 1981 along with the overall description of compliance with R.G. 1.97.- This description will include an assessment of.

-the core exit thermocouples using Attachment.1 to Item II.F.2 in IUREG-0737.

With regard to Item II.K.3 (C.3.10 and C.3.12) a plant specific transient analysis was not performed in selecting the power level belowwhich a PORV would not be actuated upon trip of the turbine. Rather the results of the analysis for Farley Unit 2 were used. This analysis supported a setpoint of 50% power.for Farley. Farley is a three loop plant, therefore it has a higher power ~ density per loop than McGuire which is a four loop plant. Thus the Farley. analysis is conservative compared to.McGuire for the purpose of selecting a reactor trip setpoint upon turbine trip.

As part of the power ascension testing, a test will be performed to verify-the response of the plant to a turbine trip at 1% below the F-11 setpoint (nominally 47% of full power). Primary reactor coolant and secondary system parameters will be monitored during the transient using existing plant in-

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strumentation. Acceptance criteria will include: Reactor does not trip and pressurizer power operated relief valves do not open. Appropriate test ab-stracts-in the McGuire FSAR will be revised to reflect these revised acceptance criteria at a future date.

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Mr. Harold R. Denton, Director March IS, 1981 Page 2 If there are any questions regarding either of these matters, please advise.

Very truly yours, b

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Willian 0. Parker, J GAC:pw cc:

T. J. Donat Senior Resident Inspector McGuire Nuclear Station

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