ML20195D981

Describes Util Proposed Plan for Addressing Generic Ltr 82-33 Open Issues Re Spds.Current SPDS Based on Westinghouse Plant Safety Status Display Sys Using Westinghouse Software. Util Has Initiated Upgrade Project for Entire Computer Sys

ML20195D981
Person / Time
Site:	Summer
Issue date:	06/16/1988
From:	Nauman D SOUTH CAROLINA ELECTRIC & GAS CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
GL-82-33, NUDOCS 8806230266
Download: ML20195D981 (3)

Text

l th Cu lina Electric & Gas Company D n A. uman Jenkinsville. SC 29065 Nuclear Operations SCE&G " " '

June 16, 1988 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 Generic Letter 82-33 Safety Parameter Display System Gentlemen:

In a letter dated November 13, 1987, South Carolina Electric & Gas Company (SCE&G) received the NRC staff's evaluation of the Virgil C. Summer Nuclear Station Safety Parameter Display System (SPDS). The staff concluded that while some provisions of the requirements found in Generic Letter 82-33 were -

not fully satisfied by the presently installed SPOS, no serious safety I concerns were identified and continued operation was acceptable while the >

{ open issues were resolved. The purpose of this submittal is to describe the SCE&G proposed plan for addressing these open issues.

The current SCE&G SPOS is based on the Westinghouse Plant Safety Status Display (PSS0) System and utilizes software also developed by Westinghouse.

This system is a portion of the SCE&G overall Technical Support Center (TSC) j computer. Because of the many recent advancements and improvements that have 1 developed in the field of computer technology, SCE&G has initiated a j replacement upgrade project for the entire TSC computer in order to provide a '

system more capable of satisfying the NRC requirements and more fully meeting the needs of SCE&G. The new hardware which will be used (Gould Computers and Computer Products data acquisition equipment) is very similar in design and function to that used in the Virgil C. Summer Nuclear Training Center simulator; therefore, SCE&G is very familiar with, and confident in, the hardware.

l The new hardware and software is being procured to ensure NRC requirements of Supplement 1 to NUREG 0737 are satisfied. In particular, the open issues ,

identified in the NRC staff review of the current SPDS (letter from Mr. J. B.

Hopkins to Mr. D. A. Nauman dated November 13,1987) have been specifically addressed as part of the replacement / upgrade program. These issues are being addressed as follows:

1. The SPOS shall continuously display information from which the safety status of the plant can be assessed. .

The new SPDS software system requires that the status of the six critical safety functions be displayed at all times. j

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Document Control Desk June 16, 1988 Page 2 of 3

2. The SPDS shall have rapid and reliable display of the safety status of the plant.

The specification for the new system includes the requirement for a two second display response time. In addition, SCE&G expects that the system availability for the new SPDS will be greater than 99%. Adequate spare parts are being acquired with the system to prevent downtime associated with parts availability. Maintenance will be performed by SCE&G personnel further minimizing downtime necessitated by waiting for the maintenance vendor to arrive.

3. The SPDS display shall be designed to incorporate human factors principles.

The NRC identified several human factors problems regarding tha use of certain color combinations and the alarming of some values that should be expected to be at these values during normal operations (i.e., RHR flow in alarm during normal operations, since flow is not what is required in the system during normal conditions). The specifications for the new SPDS will address these type concerns such that the information displayed from the system is not misleading and human factors. considerations are utilized.

4. Problems with the validity of data on SPDS displays.

These problems are being resolved as described in item 3 above.

SCE&G currently plans to have the entire new TSC computer system operational prior to restart after the 1990 refueling outage. At that time, SCE&G would have all the deficiencies in the SPDS resolved by incorporating the new computer system. While it would be physically possible to modify the present SPDS system to address the NRC concerns, this is not considered to be the best possible solution. It is anticipated that the new system will provide greater availability, improved serviceability, and enhance expandability.

SCE&G has invested a great deal to provide a computer system that is reliable, informative, meets the NRC requirements, and has the confidence of those individuals who must utilize the system. While the current SPOS is acceptable, much more is expected from the new system when it comes online.

This implementation schedule will allow any problems to be corrected prior to declaring the system operable, thereby improving the acceptance of the system by the Operations personnel. Your cooperation in working with the SCE&G projected schedule is greatly appreciated.

If you should have any questions, please advise.

e r y yours,

. ' auman AMM/ DAN: led i

pc: See Page 3

Document Control Desk June 16, 1988 Page 3 of 3 pc: J. G. Connelly, Jr./0. W. Dixon, Jr./T. C. Nichols, Jr.

E. C. Roberts

0. S. Bradham W. A. Williams, Jr.

J. N. Grace J. J. Hayes, Jr.

General Managers C. A. Price R. B. Clary W. R. Higgins R. M. Campbell, Jr.

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

NSRC RTS(NRR 860007)

NPCF File (815.14) d

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