ML20053D721

Forwards Westinghouse Transmitting SAR for Deletion of Reactor Trip Following Turbine Trip Below 50% Power.Review Requested Against NUREG-0737,Item II.K.3.10 Concerns

ML20053D721
Person / Time
Site:	Beaver Valley
Issue date:	05/27/1982
From:	Carey J DUQUESNE LIGHT CO.
To:	Varga S Office of Nuclear Reactor Regulation
Shared Package
ML20053D722	List: ML20053D721 ML20053D726
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.10, TASK-TM TAC-11011, TAC-45471, NUDOCS 8206070249
Download: ML20053D721 (4)

Text

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'Af Telephone (412) 4%6000 Nuclear DMalon P.O. Box 4 Shippingport, PA 15077M4 May 27, 1982 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attn:

Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Washington, DC 20555

Reference:

Beaver Valley Power Stat'on, Unit No. 1 Docket Ni. 50-334, License No. DPR-66 NUREG-07:' 7; item II.K.3.10 Centlemen:

Reference A:

Varga to Carey letter dated February 7, 1981 Reference B:

Varga to Carey letter dated November 18, 1981 The above two referenced letters requested the analysis required by NUREC-0737, item 11.K.3.10, Proposed Anticipatory Trip Modification.

The position statement of II.K.3.10 requests that it be shown that the probability of a small-break loss-of-coolant accident resulting from a stuck-upen power-operated relief valve is substantially unaffected by the proposed anticipatory trip modification.

Our letter of October 27, 1978 requested a Technical Specification change and provided a Safety Analysis Report for the deletion of reactor trip following turbine trip below 50 percent power. Recent conversation between the NRC and my staff have indicated that the above mentioned Safety Analysis Report (SAR) was not reviewed to determine if the position state-ment of 11.K.3.10 was satisified. We are therefore providing an additional copy of the SAR for review against NUREG-0737 concerns.

If you have any questions, please contact my office.

Very tr ly yours, J. J. Carey Vice President, Nuclear OY s

s206070249 020527 PDR ADOCK 05000334 s /

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4 Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 NUREG-0737; item II.K.3.10 Page 2 cc:

Mr. William J. Ross, Licensing Project Manager United States Nuclear Regulatory Commission Division of Licensing kashington, DC 20555 Mr. W. M. Troskoski, Resident Inspector United States Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 United States Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 i

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WeStingh0USe Water Reactor wearsmice onnse Electric Corporation Divisions Ba 2m Pinsturgh Pernsylvania 15230 May 4, 1978 RPFP-78-6 Mr. J. A. Werling, Station Superintendent Duquesne Light Company Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077

Dear Mr. Werling:

Duquesne Light Company Beaver Valley Power Station Unit No.1 Deletion of Reactor Trip following Turbine Trip below 50 percent power Safety Analysis Report

/

The attached report presents the results of the analysis done to support deletion of reactor trip following turbine trip below 50 percent power at Beaver Valley Power Station Unit No.1.

The report concludes that reactor trip on turbine trip may be deleted below 50 percent power without presenting a hazard to the integrity of the RCS or main steam system.

In addition, the results of analyses to support deletion of reactor trip on turbine trip below 70 percent power are presented.

The results show that with respect to core integrity, reactor trip on turbine trip can be deleted below 70 percent power.

However, Duquesne Light Company must verify that Beaver Valley Unit No.1 has the condenser capacity to accept a 70 percent load rejection, otherwise the Reactor Protection System would trip the reactor.

The report includes the following information:

1.

Transient results and a general discussion of the assumptions made in l

the analyses.

2.

Proposed changes to the Precautions Limitations and Setpoints document consistent with recommended setpoint.

3.

Proposed changes to the Beaver Valley Power Station Unit 1 Standard Technical Specifications consistent with recommended setpoint.

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b May 4, 1978 RPFP-78-6 If there are any further questions relative to the attached report, please feel free to contact me.

j Sincerely,

.\\

cg J. D. Woodward, Manager Eastern Service Region JDW/jm attachment cc:

G. W. Moore amusumannum H. P. Williams H. A. Van Wassen A. R. D'Amico R. C. Schopper R. F. Burski R. E. Martin B. Sandrock

• F. W. Knowles

• Without Attachment l

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