ML20058D030
| ML20058D030 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/21/1982 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| REF-SSINS-6820, REF-SSINS-SSINS-6 IEB-80-04, IEB-80-4, TAC-46826, NUDOCS 8207270011 | |
| Download: ML20058D030 (2) | |
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Teiepnon. aia 45e4000 Nuclear Dwisdn P.O. Box 4 July 21, 1982 smppinsport. PA isona 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 j
Reference:
Beaver Valley Power Station, Unit No. L l
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Docket No. 50-334, License No. DPR-66 Franklin Research Center Technical Evaluation of IE Bulletin 80-04 " Analysis of a PWR Steam Line Break with Continued AFW Addition" Centlemen:
Your telex to K. D. Grada of Duquesne Light Company, requested that we " provide an evaluation of the potential for damage to the AFW Pumps due to operation at runout flow for 30 minutes."
In your letter dated February 7, 1981 (page 17), you requested that we " confirm that the Beaver Valley AFW system can provide the required flow for a feed-line rupture and for the steamline break inside containment without operator intervention for 10 minutes. We tested a motor driven A"W Pump for that period to qualify the pumps on that basis, af ter which time it is assumed that operator intervention terminates the transient.
Our test data indicated that all vital parameters, specifically pump vibration, discharge pressure, flow and oil temperature remained stable during the test period. The pump capacity was also within the acceptable range of its head curve. The maximum steady state motor current did not exceed 42 amps and the overcurrent trip is set at 60 amps. On this basis, we would expect that the pump and motor would be capable of performing under those conditions for 30 minute period.
Our evaluation, based on the test data generated during the 10 minute run, is adequate for concluding that an AFW Pump would not be damaged by operating at runout flow for 30 minutes and a substantial basis for testing the equipment under those conditions has not been presented.
Very tru
- yours, J. J. Carey Vice President, Nuclear
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@207270011 820721 PDR ADOCK 05000334 P
Beaver Valley Power Station, Unit No. I Docket No. 50-334, License No. DPR-66 5
Franklin Research Center Technical Evaluation of IE Bulletin 80-04 " Analysis of a PWR Steam Line Break with continued AFW Addition" Page 2 cc:
Mr. W. M. Troskoski, 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