ML20247K201

From kanterella
Jump to navigation Jump to search
Application for Amend to License NPF-12,revising Tech Spec Sections 3.8.1.1 & 3.8.1.2 Re Ac Sources & Bases Section Re Ac Sources,Dc Sources & Onsite Power Distribution Sys to Correct Deficiency on Min Fuel Oil Storage Vol
ML20247K201
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 07/21/1989
From: Bradham O
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20247K205 List:
References
NUDOCS 8907310479
Download: ML20247K201 (3)


Text

- _ _ _,__

th rotina Ettetric & G:s CompIny iSD dhrm Jenkinsville. SC 29065 Nuclear operations l

(803) 345 4040 l

SCE&G July 21.-1989' l

l l

. 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 - A. C. Sources Gentlemen:

South Carolina Electric & Gas Company (SCE&G) hereby. requests an amendment to-Technical Specifications Sections 3.8.1.1 and 3.8.1.2, "A. C. Sources," and j

Bases Section 3/4.8.1, 3/4.8.2 and 3/4.8.3,="A. C. Sources, D. C. Sources.and-Onsite Power Distribution Systems."

On April 28, 1989, SCE&G identified a discrepancy in the requirements for the volume of stored diesel fuel oil between the current design basis calculation and Technical Specification Sections 3.8.1.1.b.2 and 3.8.1.2.b.2.

The design basis calculations determined that the minimum required fuel oil storage volume for each diesel should be 47,100 gallons while in Modes 1-4 and-33,200 gallons while in Modes 5 and 6.

The current Technical Specification limits-are 42,500 gallons (Modes 1-4) and 30,000 gallons (Modes 5 and 6).

This event was reported to the Commission on May 26, 1989 in Licensee Event Report (LER) 50/395 89-009. The submittal of this Technical. Specifications change request satisfies Corrective Actions 1 and 2 of the LER.-

The marked up pages for the proposed amendments are provided in Attachment 1.-

The proposed no significant hazards evaluation is provided in Attachment 2.-

This request has been reviewed and approved by both the Plant Safety Review Committee and the Nuclear Safety Review Committee.

AMI 8907310479 890721 3

1 PDR ADOCK 05000395 g

P._

PDC h

l.

.(

Docun *' *ni.ral Desk July 21 7

Page 2 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.

O. S.-Bradham MDB/0SB: led 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 /R. M. Campbell, Jr.

R. B. Clary K. E. Nodland J. C. Snelson G. O. Percival R. L. Prevatte J. B. Knotts, Jr.

H. G. Shealy M. D. Blue NSRC RTS (TSP 890011)

NPCF File (813.20) 4 I

I 1

The Secretary of the Commission July 21, 1989 Contents Section Page 3.8.1.1 3/4 8-1 3.8.1.2 3/4 8-8 Bases 3/4.8.1, 3/4.8.2 and 3/4.8.3 8 3/4 8-1 l

l l

i 1

_ _ _ _ _ _ _ _ _ _ _ _ _.