ML19309D422

Responds to IE Bulletin 79-13.Hot Functional Testing Scheduled for 800501 & Fuel Loading Scheduled for 801201. Operating & Emergency Operating Procedures for Main Steam Line Break & Main Feedwater Line Break Are Being Finalized

ML19309D422
Person / Time
Site:	Summer
Issue date:	03/12/1980
From:	Crews E SOUTH CAROLINA ELECTRIC & GAS CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
IEB-79-13, NUDOCS 8004100359
Download: ML19309D422 (2)

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x-Mr. James P. O'Reilly, Director ne U. S. Nuclear Regulatory Commission Region II, Suite 1217

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230 Peachtree Street, N. W.

Atlanta, GA 30303

Subject:

Virgil C. Summer Nuclear Station, Unit 1 Inspection and Enforcement Bulletin 79-13 Revision 2 - Docket No. 50-395 Nuclear Engineering File 2.8950

Dear Mr. O'Reilly:

NRC I6E Bulletin 79-13, Revision 2, revised the examination requirement for feedwater piping inside the containment.

This letter provides updated information regarding Revision 2 of this bulletin as it applies to the Virgil C. Summer Nuclear Station and replaces our response, dated September 20, 1979, on Revision 1 of this bulletin.

As a designated applicant for an operating license, item 3 of the bulletin applies to the Virgil C. Summer Nuclear Station and requires submittal of reports described in items 4, 5, and 6 of the bulletin. At this time, only item 5 requires action.

1.

Item 5(a) - Our projected schedule for beginning hot functional testing is May 1,1980, and the projected schedule for fuel loading is December 1, 1980.

Inspection required by item 1 will be performed between these two dates.

2.

Item 5(b) and (c) - Operating procedures are presently being i

finalized but are not complete at this time.

Emergency Operating Procedure (EOP-2) for a main steam line break and a main feedwater line break will have adequate coverage for symptoms of a feedwater line break inside the reactor-building so that the operator can readily recognize the accident and take immediate corrective action to limit the accident by isolating the affected feedwater line and steam generator.

For feedwater leaks inside the reactor building, the detection system for the reactor coolant system, as listed in FSAR Section 5.2.7, is also used for detection of feedwater and steam leaks.

An increased condensate drain flow in the reactor building cooling unit or a. leak detection sump level increase,1 I

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Mr. James P. O'Reilly Page 2 March 12, 1980 without an increase in radioactivity in the reactor building environment, would indicate the possible presence of a feedwater or steam leak.

Follow-up reactor building entry and investigation should locate e

the source.

Presently, SCE6G is evaluating an acoustical monitoring system by Westinghouse which may be utilized to detect and locate feedwater leaks inside the reactor building.

If evaluated favorably, this system may be placed in service at a later date.

If further information regarding hisqbulletin is required, please I

let us know.

V ry ti lly yours,

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fws, Jr.

BSM:rm CC: Office of Inspection and Enforcement Washington, DC Messrs:

V. C. Summer T. C. Nichols, Jr.

11. T. Babb M. B. Whitaker D. R. Moore A. A. Smith J. Skolds

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