ML19098B479

Submit Preliminary Report, ISI 75-6, Inservice Inspection Program Refueling Outage No. 2, Surry Power Station Units No. 1.

ML19098B479
Person / Time
Site:	Surry
Issue date:	11/28/1975
From:	Stallings C Virginia Electric & Power Co (VEPCO)
To:	Moseley N NRC/RGN-II
References
Serial No. 796
Download: ML19098B479 (4)

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Mr. Norman C. Moseley~ Director Serial No. 796 Office of Inspection and Enforcement PO&M/JTB:cjd U. S. Nuclear Regulatory Commission Region II - Suite 818 Docket Nos. 50-280 230 Peachtree Street, No;thwest 50-281 Atlanta, Georgia 30303 License Nos. DPR-32 DPR-37

Dear Mr. Moseley:

Pursuant to Technical Specification 6.6.C for the Surry Power Station, Unit Nos. 1 and 2, the Virginia Electric and Power Company hereby submits a preliminary report,* ISI75-6, sunnnarizing the results of the inservice inspection activities conducted during Refueling Outage No. 2 of Unit No. 1.

The unit is scheduled to return to power on or about December 1, 1975.

Very truly yours, fd {.. ~II ,~/'

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. Vice President-Power Supply and Production Operations cc: Mr. Robert W. Reid, Chief Operating Reactors Branch 4 Attachment

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• I INSERVICE INSPECTION PROGRAM REFUELING OUTAGE NO. 2 SURRY POWER STATION UNIT NO. 1 NOVEMBER 25, 1975 REPORT NO. ISI 75-6 .

DOCKET NO. so-2so*

LICENSE NO. DPR-32 VIRGINIA ELECTRIC AND POWER COMPANY I

f I. IJ;,"!TRODUCTION In accordance with the requirements o-f Technical° Specification

6. 6. C, this report contains a su1!lIIlary of the preliminary re*su1 ts of the inservice inspection activities performed during Refueling Outage No. 2 of Unit No. 1 at the Surry Power Station.

II. Sill1KA.RY OF lIBSULTS

• The inservice inspections performed during the period covered by this report included the basic areas listed below:

1. Low head safety injection system piping located in valve pit (Item 7.2 of Technical Specification 4.2).

2. Steam generator tube eddy current inspections.

Low Head Safety Inje~tion System Piping iE:._Valve Pit The low head safety injection system piping. located in the valve pit was visually inspected. No significant*indications were

.noted. Arc strikes were r.emoved by grinding.

Steam Generator Tube Eddy Current Inspections Eddy current inspections of the steam generator tubes were performed in accordance with Regulatory Guide 1.83.. As a result of these inspections a.number of tubes were plugged.

The eddy current inspections and tube gauging indicate that localized tube diameter reductions have occurred in the steam generators. These reductions have been c.aused by "denting."

Because of the generic nature of "denting" it will not be discussed herein.

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• 2 Although significant "thinning" and "denting" of tubes hav~

been experienced, their integrity has been maintained and they are capable of performing their design function.

III. CONCLUSIONS The results of the inservice inspections performed verified the integrity of the systems and components examined.

Based on the results of the inservice inspection program, as summarized herein, the safety systems and components inspected have not experienced significant degradation and there is reasonable assurance that they will continue to perform their design functions.

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