ML20211P644

From kanterella
Jump to navigation Jump to search
Submits Followup to Telcon Re Current Normal Operation of Reactor Bldg Cooling Units (Rbcus) & as-modified Environ Qualification of Rbcu Isolation Valves Described in 870120 Tech Spec Change Request.Listed IE Info Notice Inapplicable
ML20211P644
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 02/24/1987
From: Nauman D
SOUTH CAROLINA ELECTRIC & GAS CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
IEIN-87-008, IEIN-87-8, NUDOCS 8703020406
Download: ML20211P644 (2)


Text

-_-

10 CFR50.36 e

gggna Electric & Gas Company n A.

n m

29218 Nuc! ear Operations SCE&G

~

February 24, 1987 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Virgil C. Summer Nuclear Station Docket N0. 50/395 Operating License No. NPF-12 Reactor Building Cooling System

Dear Mr. Denton:

This letter is being submitted as a followup to a telephone conversation held between Jon Hopkins (USNRC), Hal Donnelly and Gil Williams of South Carolina Electric & Gas Company. Mr. Hopkins asked about the current normal operation of the Reactor Building Cooling Units (RBCUs) and the as-modified environmental qualification of the RBCU isolation valves (XVG-3109A,B,C,0-SW) that were described in the Technical Specification change request letter dated January 20, 1987.

Mr. Hopkins was informed that for normal operation, three out of four RBCU's are in operation and the fourth RBCU's discharge isolation valve is shut.

This method of operation will continue to be used after the modification.

Currently, these discharge valves are passive and receive an SI signal to open; therefore, operating procedures are set up to ensure that the RBCUs which are selected to run during an accident, have open discharge valves during normal operation.

The planned modification will make these valves active and the operators will be environmentally qualified to the requirements for active Class 1E Limitorque operators inside containment at Virgil C. Summer Nuclear Station.

Mr. Hopkins also asked if IEN 87-08, " Degraded Motor Leads in Limitorque D_G Motor Operator," would have any effect on the valve operators being modified.

Because the motor operators at the Virgil C. Summer Nuclear Station are &Q, this IEN is not applicable.

y 3b tr

\\ ' \\. Nauman W

.A HID/ DAN:jez c:

Page 2 I

00 4t

)$

8703020406 870224 PDR ADOCK 05000395 P

PDR

.O e

Mr. Harald R. Denton February 24, 1987 Page 2 c:

0. W. Dixon, Jr./T. C. Nichols, Jr.

E. C. Roberts

0. S. Bradham J. G. Connelly, Jr.

D. R. Moore W. A. Williams, Jr.

J. N. Grace Group Managers W. R. Baehr C. A. Price C. L. Ligon (NSRC)

R. M. Campbell, Jr.

K. E. Nodland R. A. Stough G. O. Percival R. L. Prevatte J. B. Knotts, Jr.

H. G. Shealy NPCF File 4

l I

~.. -.. - -.. -.., -, - _.. _. _ _.. -. -

- -. _. -....