ML20083G017
| ML20083G017 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/06/1984 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8401100444 | |
| Download: ML20083G017 (2) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _
e 1
SOUTH CAROLINA ELECTRIC & GAS COMPANY Post oprice 7ee COLuws A, south CAn0 LINA 29218 O.W.OlRON.JR.
January 6, 1983 WCa PassIDENT NuCLeam OramAtoms 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 Feedwater Isolation Valve Technical Specification Justification
Dear Mr. Denton:
On November 16, 1983, South Carolina Electric and Gas Company (SCE&G) requested an amendment to the Virgil C.
Summer Nuclear Station Technical Specifications which addressed the Feedwater Isolation Valve (s).
The Staff, in a subsequent conversation with SCE&G, requested additional information for justification of the seventy-two (72) hour feedwater isolation valve inoperable time limit.
As shown in the Final Safety Analysis Report (FSAR) Figure 7.2-1, Sheet 13, the Virgil C. Summer Nuclear Station Reactor Protection System (RPS) logic dictates that on receipt of a Safety Injection (SI) or Steam Generator Hi-Hi Level signal, j
the following feedwater related actions occur:
1)
Feedwater Isolation Valve Closure 2)
Feedwater Control and Bypass Valve Closure 3)
Feedwater Pump Trip and its associated discharge valve closure 4
The steamline break events described in FSAR Sections 6.2.1.3.10.3.1, 6.2.1.3.10.3.3 and 15.4.2 take credit for feedwater isolation.
Feedwater isolation, as assumed in these analyses, can be accomplished by any one of the above three (3) feedwater related actions.
Therefore, a feedwater isolation valve inoperable time limit of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is acceptable since Feedwater Pump Trip and Feedwater Control Valve Closure provide added protection on receipt of an SI j
or Steam Generator Hi-Hi Level signal.
B401100444 840106 A
PDR ADOCK 05000395 g
f F
P.
s' Mr. Harold R.
Denton Feedwater Isolation Valve Technical Specification Justification January 6, 1984 Page #2 If there should be any questions, please contact us at your convenience.
Very truly yours, l
/ /
O. W.
D on WRM:OWD/fjc cc:
V.
C.
Summer T.
C.
Nichols, Jr./O.
W. Dixon, Jr.
E. H. Crews, Jr.
E.
C.
Roberts W. A. Williams, Jr.
D. A.
Nauman J.
P.
O'Reilly Group Managers O.
S. Bradham C. A.
Price C.
L. Ligon (NSRC)
G.
J.
Braddick D. J.
Richards NRC Resident Inspector J.
B.
Knotts, Jr.
NPCF File
.