ML20049H553

Provides Info on Item II.K.3.5 Re Automatic Trip of Reactor Coolant Pumps During Loca,Per NUREG-0737 Requirements. Status Submitted in Has Not Changed

ML20049H553
Person / Time
Site:	Beaver Valley
Issue date:	02/24/1982
From:	Carey J DUQUESNE LIGHT CO.
To:	Varga S Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.05, TASK-TM TAC-45392, NUDOCS 8203030289
Download: ML20049H553 (2)

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February 24, 1982

/D D

Director of Nuclear Reactor Regulation fg United States Nuclear Regulatory Commission fp.

Attn:

Mr. Steven A. Varga, Chief N

N%g) c Operating Reactors Branch No. 1 p

Division of Licensing NASg fgr A -S Washington, DC 20555 i

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Reference:

Beaver Valley Power Station, Unit No. 1 A

Docket No. 50-334, License No. DPR-66 Q/

NUREG 0737; II.K.3.5

/k Gentlemen:

In accordance with the requirements of NUREG-0737, we are providing information for item II.K.3.5, Automatic Trip of Reactor Coolant Pumps During Loss-of-Coolant Accident. The implementation schedule required modifications to be complete by March 1, 1982.

Our previous submittal on this subject, dated July 1,1981, provided the status-as of that time, and since then the status has not changed.

The following is a summary stating our current position as documented through ciorrespondence between the Westinghouse Owners Group and the NRC.

)

Westinghouse (in support of the Westinghouse Owners Group) has performed an analysis of delayed reactor coolant pump trip during small-break LOCAs.

This analysis is documented in " ANALYSIS OF DELAYED REACTOR COOLANT PUMP TRIP DURING SMALL LOSS OF COOLANT ACCIDENTS FOR WESTINGHOUSE NUCLEAR STEAM SUPPLY SYSTEMS,"

WCAP-9584 (PROPRIETARY) AND WCAP-9585 (NON-PROPRIETARY), AUGUST 1979.

In addition, Westinghouse '(again in support of the Westinghouse Owners Group) has performed test predictions of LOFT Experiments L3-1 and L3-6.

The results of these pre-dictions are documented in the following:

A)

LETTER OG-49, DATED MARCH 23, 1982, R. W. JURGENSEN (CHAIRMAN, WESTINGHOUSE OWNERS GROUP) TO D. F. ROSS, JR. (NRC).

B)

LETTER OG-50, DATED MARCH 23, 1981, R. W. JURGENSEN (CHAIRMAN, WESTINGHOUSE OWNERS GROUP) TO D. F. ROSS, JR. (NRC).

C)

LETTER OG-60, DATED JUNE 15, 1981, R. W. JURGENSEN (CHAIRMAN, WESTINGHOUSE OWNERS GROUP) TO P. S. CHECK (NRC).

Based on:

1) the Westinghouse analysis, 2) the excellent prediction of the LOFT Experiment L3-6 results using the Westinghouse analytical model, and

3) Westinghouse simulator data related to operator response time, the Westinghouse and Duquesne Light Company position is that automatic reactor coolant pump trip is not necessary since sufficient time is available for manual tripping of the pumps.

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Beaver l' alley Power Station Cocket No. 50-334, License No. DPR-66 NUREG 0737; II.K.3.5 Page 2 Our understanding of the schedule for final resolution of this issue 1

is:

A)

Once the NRC formally approves the Westinghouse model, a three-month study period will ensue during which the Westinghouse Owners Group will attempt to demonstrate compliance with some NRC acceptance criteria for manual RCP trip. The NRC acceptance criteria will accompany their formal approval of the Westinghouse models.

B)

If, at the end of the three-month period, the Westinghouse Owners Group cannot show compliance with the acceptance criteria, the NRC will formally notify utilities that they must submit an automatic RCP trip design.

Very truly yours, J. J. Carey Vice President, Nuclear cc:

Mr. D. A. Beckman, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 t

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