ML20077D269

From kanterella
Jump to navigation Jump to search
Application for Amend to License NPF-12,transferring Item (B) & (C) of Tech Spec Surveillance Requirement 4.7.4, Svc Water Sys, to Surveillance Requirement 4.6.2.3 Item (B), Reactor Bldg Cooling Sys
ML20077D269
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 07/22/1983
From: Dixon O
SOUTH CAROLINA ELECTRIC & GAS CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20077D276 List:
References
NUDOCS 8307260461
Download: ML20077D269 (2)


Text

.

y 4

SOUTH CAROLINA ELECTRIC & GAS COMPANY POST OPPaCE 784 CoLuus!A. SOUTH CAROUNA 29218

o. w. oixoN. a..

July 22, 1983 vice pn.. o ut NUCLeAn OranATIONS Mr. Harold _R.~Denton, Director

. Office of Nuclear Reactor Regulation 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 Surveillance Requirement' Change

Dear Mr. Denton:

South Carolina Electric and Gas Company (SCE&G) hereby requests that items (b) and (c) of the Virgil'C. Summer Nuclear Station Technical Specification Surveillance Requirement 4.7.4, "Ser-vice Water System," be, transferred to' Surveillance Requirement 4.6.2.3, item'(b), " Reactor Building Cooling - System," (see

. Attachment 1).

The subject' items involve the surveillance of_a portion of the

' Service Water System that' supports only the Reactor Building Cooling Units (RBCU)(see FSAR Figures 9.2-2-and 9.2-3).

This1 portion of the system is actuated upon the receipt of a Cafety Injection signal to supply cooling water to the RBCUs:at a boosted pressure.- Because~of the present_ Technical Specifica-tion requirements, a potential component failure in the portion of the system.that is dedicated to the RBCUs necessitates declaring the entire Service Water System inoperable.

It is the opinion of SCE&G that items (b) and (c) of Technical

. Specification ~4.7.4, are more appropriately addressed under Specification 4.6.2.3 because.the intent of the Specification is~to ensure reliable operation of the RBCUs.

SCE&G has also determined that a finding of no significant hazard is justified (see Attachment 2).

t h* h 'I 8307260461 830722 PDR ADOCK 05000395 e

P pyy gp p

) I i

+

Mr. - Harold R. Denton

~ July-22, 1983 Page #2 This change has been reviewed and approved by the Plant Safety

. Review Committee and the Nuclear Safety Review Committee.

A check in the amount of Four Thousand Dollars ($4000.00) is enclosed for processing of this change.

If you have any questions, please contact us at your convenience..

Very truly yours, O. W. Di n, Jr NEC:OWD/fjc cc:

V.

C.

Summer T.

C. Nichols, Jr./O. W. Dixon, Jr.

E.

H. Crews, Jr.

E.-C.

Roberts H.

N. Cyrus J.

P. O'Reilly Group / General Managers O.

S. Bradham R.

B. Clary

)

C.

A. Price A.

R. Koon

-C.

L. Ligon (NSRC)

G. J. Braddick J.

C. Miller J.

L.

Skolds J.

B. Knotts, Jr.

H.

G.

Shealy NPCF File (Lic./Eng.)

l L-