ML19332G114

Reformats 890721 Application for Amend to License NPF-12, Revising Tech Specs 2.2.1 & 3.3.2 Re Reactor Trip Sys Instrumentation Setpoints & Esfas,Respectively.Util Requests Change to Support Next Refueling Outage

ML19332G114
Person / Time
Site:	Summer
Issue date:	12/11/1989
From:	Bradham O SOUTH CAROLINA ELECTRIC & GAS CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19332G115	List: ML19332G114 ML19332G119
References
NUDOCS 8912200180
Download: ML19332G114 (3)

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[ ,. South Carolma Electric & GIs Company ~ Om S. radham

.f Jenkinsville, Sc 29065 Nuclear Operations ,

, (803) 345-4040 L

. SCE&G r u .-,. .

December 11, 1989

i Document Control Desk.

U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Virgil C. Summer Nuclear Station Docket No. 50/395 ,

Operating License No. NPF-12 Technical Specifications Change Request - RTD Bypass Elimination 4

Gentlemen:.

South Carolina Electric & Gas Company (SCE&G) requests a revision to the Technical Specifications for the. Virgil'C. Summer Nuclear Station. The proposed change revises certain setpoints and allowable values ~in Specification 2.2.1 " Reactor Trip System Instrumentation Setpoints" and Specification 3.3.2 " Engineered Safety Feature Actuation System (ESFAS)

Instrumentation". associated with the replacement of the RTD bypass manifold with fast response RTDs in thermowells.  !

This letter reformats the previous submittal dated July 21, 1989 to comply with new guidance received from Mr. Jack Hayes, NRC Project Manager. Please note that the.WCAPs (WCAP- 12189 and WCAP-12190) referenced in this letter l were provided in the previous July 21, 1989 submittal. The request is contained in the following attachments: i Attachment 1 - The Technical Specification pages with the requested changes indicated. I Attachment 2 - Description of amendment request and supporting safety evaluation.

Attachment'3 - Description of amendment request and supporting no significant hazards determination.

SCE&G'would like to utilize the proposed change to support its next refueling outage activities. It.is therefore requested that the NRC review and approve this change by February'1, 1990.

.These changes have been reviewed by the Plant Safety Review Committee and the Nuclear Safety Review Committee.

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Ii 8912200100 891211 O PDR .ADOCK 0S000395 rs J830

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.'. Document Control Desk

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'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, a  :"

0. S. Bradham

-DCH/OSB:lbs

. Attachments-c:. D. A. Nauman/0. W. Dixon, Jr./T. C. Nichols, Jr.

E. C. Roberts

'W. A. Williams,.Jr.

S. D. Ebneter J. J. Hayes, Jr.

General Managers -

C. A. Price 1 lR. B. Clary K. E. Nodland J.-C. Snelson R.'L. Prevatte H. G. Shealy J. B. Knotts, Jr.

.NSRC NPCF RTS':(TSP'890009)

File (813.20)

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ATTACHMENT 1 Technical Specification Pages with Changes Indicated Pigg Specification Chance Description -

2-5 2.2.1 Changes values of "S," "Z," and Allowable Values 2-9 2.2.1 Changes value in Note 2 2-10: .2.2.1 Changes value in Note 4 3/4 3-27 3.3.2 Changes values of "S," "Z," Trip Setpoint and Allowable Values 3/4 3-28b 3.3.2 Changes values of "S," "Z," Trip Setpoint and Allowable Values l

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