ML20059C675

Application for Amend to License NPF-12,changing Tech Spec 3/4.4.5 to Allow Alternative to Plugging or Sleeving of Tubes W/Degradation in Tubesheet Area.Ltr Reformats 880801 Submittal

ML20059C675
Person / Time
Site:	Summer
Issue date:	08/30/1990
From:	Bradham O SOUTH CAROLINA ELECTRIC & GAS CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20059C678	List: ML20059C675 ML20059C681
References
NUDOCS 9009050257
Download: ML20059C675 (3)

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August 30, 1990 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D. C. 20555

Subject:

Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Technical Specification Change Request for Steam Generator L*

Criteria Gentlemen:

South Carolina Electric & Gas Company (SCELG) hereby requests a revision to the Technical Specifications for the Virgil C. Summer Nuclear Station (VCSNS). The proposed change revises the surveillance requirements of Technical Specification 3/4.4.5, " Steam Generators," to allow for an

. alternative to plugging or sleeving of tubes with degradation in the tubesheet area. This alternate method is designated the L* criteria. This letter reformats the previous submittal dated August 1, 1988, to comply with guidance received from Mr. Jack Hayes, NRC Project Manager. Also, thr; technical specification change request has been amended.to provide additional conservatism over the Westinghouse L* criteria to allow fa dem^nstre.ble.

implementation. In addition, information on implementation of the L*

criteria (e.g., eddy current testing techniques) is provir.ed. Please note that the WCAP's referenced in this submittal (WCAP-11857 and WCAP-11858) were provided in the August 1, 1988 letter.

The change request is contained in the following attachments:

Attachment 1 -

The Technical Specification pages with the requested changes indicated.

Attachment 2 - A description of the amendment request and supporting safety evaluation.

Att'tchment 3 - A description of the amendment request and associated no significant hazards evaluation.

Attachment 4 -

A discussion of eddy current testing techniques to be used to implement L*.

9009050257 900830 5 PDR ADOCK 0500 P

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D'ocument Control Desk August 30, 1990 Page 2 of 2 SCE&G requests that the NRC process this change request in an expeditious manner, such that, upon approval it can be utilized at the next refueling outage which is scheduled for September, 1991. SCE&G is available to meet with NRC personnel to discuss the technical details associated with the analysis and implementation of L*.

This proposed Technical Specification change has been reviewed and approved by the Plant Safety Review Committee and Nuclear Safety Review Committee.

I declare that the statements and matters set forth herein are true and correct to the best of my knowledge, information and belief.

Should you have any questions, please call at your convenience.

Very truly yours.

(N et

0. S. Bradham ARR/OSB: led Attachments c: O. W. Dixon, Jr./1. C. Nichols, Jr.

E. C. Roberts R. V. Tanner S. D. Ebneter J. J. Hayes, Jr.

Genert.1 Managers C. A. Price R. J. Waselus K. E. Nodland J. C. Snelson R. L. Prevatte J. B. Knotts, Jr.

H. G. Shealy A. M. Monroe R. E. Kelso A. R. Rice HSRC NPCF RTS (TSP 880015)

File (813.20) i

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ATTACllMENT 1  ;

Marked Up Technical Specificat?nn Pages Eaag SDecification Chance Description 3/4 4-12 4.4.5.2.c Adds the requirement to inspect all tubes which have had the L*

criteria applied.

3/4 4-14 4.4.5.4.a.6 Adds an exemption to the tube plugging or repair limit for L*-

tubes.

3/4 4-15 4.4.5.4.a.15 Adds a new item, 4.4.5.4.a.15, which d2 fines the L* distance.

4.4.5.4.a.16 Adds a new item, 4.4.5.4.a.16 -

which defines an L* tube.

l- 4.4.5.5.d Adds the requirement to report ,

the results of inspections of L* tubes.

B 3/4 4-3 Bases 3/4.4.5 Adds a statement that plugging is not required for tubes meeting the L* criteria.

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