ML20086S473

Ro:On 740725 & 26,liquid Release Occurred Which Exceeded 4% of Tech Spec Limit.Steam Generator Leakage Being Continuously Monitored & Will Be Repaired During 741015 Refueling Shutdown

ML20086S473
Person / Time
Site:	Surry
Issue date:	08/26/1974
From:	Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20086S454	List: ML20086S449 ML20086S462 ML20086S473
References
253, NUDOCS 8403020370
Download: ML20086S473 (2)

Text

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O O Vinoi x i A Etnernic Axu Pownic Gmti Axy Hicunoxu.Vinoix A u O u UI August 26, 1974 ,

Mr. Norman C. Moseley, Director Serial No. 253 Directorate of Regulatory Operations P06M/JTB:clu United States Atomic Energy Commission Region II - Suite 818 Docket No. 50-280 230 Peachtree Street, Northuest License No. DPR-32 Atlanta, Georgia 30303

Dear Mr. Moseley:

Pursuant to Technical Specification 6.6.B.3 for the Surry Power Station, Unit Nos. 1 and 2, the Virginia Electric and Power Company hereby reports a liquid release which exceeded four (4) per cent of the limit established in Technical Specification 3.11.A.1; i.e. the limit contained in Appendix B, 10 CFR 20, for unrestricted a.rens. The release occurred during the forty-cight (48) hour period of July 25 through 26, 1974, and has continued to date.

For the period reported, the controlled release rate of radioactive effluents f rom the station was such that tlie concentration of radionuclides leaving the circulating water discharge canal was 5.4 per cent of the limit contained in Technical Specification 3.11.A.1. The release consisted of batch releases from the liquid waste disposal system and the blowdown of .

Unit Nos. 1 and 2 steam generators. The limit was exceeded because of the high activit.y of the blowdown. This activity was due to a primary to secondary tube Icak in Unit No. 1 "A" stcan generator. For the forty-eight (48) hour period, the total liquid By activity released was 9.43 x 10'+

pCi or 5.4 per cent of the limit established in Appendix B, 10 CFR 20, for unrestricted areas.

The steat generator leakage is being continuously monitored and will be repaired at the refueling shutdown scheduled for October 15, 1974. In the interim, every effort will be made to minimize the amount of radioactive liquid releases commensurate with the necessity to maintain proper water chemistry in the steam generator during normal unit operation.

Because of the necessity to continuously release the steam generator blowdown and other liquid waste, it is most probable that we will continue to exceed four (4) per cent of the limits of Technical Specification - 3.11.A.1 until the steam generator tube leak is repaired during the re-fueling scheduled for October 15, 1974. Uc do not expect that any limit contained in Technical Specification 3.11 will be violated as a result of our continued operation, and in the event any specification limit is 8403020370 741216 PDR ADOCK 05000290 .

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Mr. Norman C. Moscicy, Director Page 2 approached, we will immediately initate appropriate action. Based on the gradua! rate of increase in steam generator activity, it is estimated that at no time will it be necessary to exceed 10 per cent of the limits established in Appendix B, 10 CFR 20, for unrestricted area.

For the purpose of reporting, we request that this report be considered as fulfillment of the requirements of Technical Specification 6.6.B.3, until we are able to repair the leak during the refueling outage. This will significantly reduce the number of reports which both Vepco and the AEC will have to process. Of course, we will continue to keep you notified of any significant changes and, for record purposes, will submit the necessary release data with our regular Semiannual Operating Report.

The release is significantly less than the limits established in Appendix B, 10 CFR 20, for unrestricted areas; therefore, there is no hazard to the health or safety of the general public.

Very truly yours, u ., ' ~ . .. \

G '. jp f. ) ^I )L'C a s

C. M. Stallings Vice President-Power Supply and Production Operations cc: Mr. K. R. Coller, Assistant Director for Operating Reactors 1

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