ML18152A881

Advises That Flow Tests Will Be Performed to Verify Acceptable Flow Rates to Steam Generators Prior to Returning Unit to Power,Per 880404 Telcon

ML18152A881
Person / Time
Site:	Surry
Issue date:	04/11/1988
From:	Cruden D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
88-175, NUDOCS 8804250089
Download: ML18152A881 (2)

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./ VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261

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Apri 1*_ !r, 1988 Regional Administrator Serial No.88-175 U. S. Nuclear Regulatory Commission NO/ETS:vlh R2 Region II Docket Nos. 50"280 101 Marietta Street, N. W. 50-281 Suite 2900 . License Nos. DPR-32 Atlanta, Georgia 30323 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 AUXILIARY FEEDWATER FLOW TESTING AT SHUTDOWN Following a manual reactor trip on March 27, 1988, due to failure of a vital bus inverter, a reduced fl ow condition was observed in auxiliary feedwater (AFW) fl ow to the "A"_ steam generator. Subsequent flow t_est i ng resulted in observed flow rates of 50-120 gpm. During the subsequent investigation of the auxiliary feedwater system, the motor operated valves and the check valve to "A" steam generator were opened and inspected; the flow element and cavitating venturi were inspected; and the associated pipin~ was visually inspected with a boroscope. No flow obstructions were identified.

The system was reassembled and flow testing was completed for both flow paths to each steam generator ut i 1i zing the motor driven auxiliary feedwater pump 2-FW-P-3A. Flow rates in excess of the assumed UFSAR accident analysis flow rates were establi~hed and no 0 indication of loose parts was observed. During heatup, at approximately 350 F, similar tests were performed using the 38 motor driven auxiliary feedwater pump. Normal flow rates were established and no indication of loose parts was observed. With the reactor critical at 3%

power, flow testing was again completed using the steam-driven auxiliary feedwater pump. Once again, satisfactory fl ow rates were achieved and no

• indication of loose parts was observed.

In a telephone conversation with the NRC on April 4, 1988; we summarized the above events and committed to additional flow testing of Unit 2 AFW system during the next shutdown of the unit. Flow tests will be performed to verify acceptable flow rates to the steam generators prior to returning the unit to power.

8804250089 880411 PDR ADOCK 05000280 P DCD

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If you have any further questions please do not hesitate to call.

Very truly yours,

~ruden ~-...__~~~~~~~~~~- ......

Vice President - Nuclear cc: U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Mr. Chandu P. Patel NRC Surry Project Manager Project Directorate II-2 Division of Reactor Projects - I/II