ML20207T361
| ML20207T361 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 03/06/1987 |
| From: | Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8703230479 | |
| Download: ML20207T361 (5) | |
Text
sggn. Ei.ctric a ca. company ogng-n Columbia 29218 Nuclear Operations SCE&G
~~
March 6, 1987 4
5
- .z co Dr. J. Nelson Grace Regional Administrator E
U. S. Nuclear Regulatory Commission o
Region II, Suite 2900
~
101 Marietta Street N.W.
Atlanta, Georgia 30323
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Radial Peaking Factor Limit Report
Dear Dr. Grace:
In accordance with Paragraph 6.9.1.11 of the Virgil C. Summer Nuclear Station Technical Specifications, South Carolina Electric & Gas Company (SCE&G) hereby submits the required Cycle 4 Radial Peaking Factor Limit Report.
RTP The Fxy limits for RATED THERMAL POWER (Fxy ) within specified core planes for Cycle 4 shall be; RTP 1)
Fxy less than or equal to 1.71 for all core planes containing bank "D"
control rods; 2)
For all unrodded core planes:
RTP a)
Fxy less than or equal to 1.69 up to and including core elevations of 3.5 feet.
RTP b)
Fxy less than or equal to 1.74 for core elevations between 3.5 feet and 7.0 feet.
RTP c)
Fxy less than or equal to 1.69 for all core elevations above and including 7.0 feet.
l fg32 DOM 05000395 870306 P
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s ZEo /
Dr. J. Nels:n Gr c0 March 6, 1987 Page 2 of 3 These Fxy(z) limits are used to confirm that the heat flux hot channt factor
-FQ(Z) will be limited to the Technical Specifications values of:
FQ(Z) s [2.251 [K(Z)]'for P > 0.5 and, P
FQ(Z) 5 [4.50] [K(Z)] for P $ 0.5; assuming the most limiting axial power distributions expected to result from the insertion and removal of control banks "C" and "0" during operation, including the accompanying variations in the axial xenon and power distributions as described in the " Power Distribution Control and Load Following Procedures." WCAP-8385, September 1974. Therefore, these Fxy limits provide assurance that the initial conditions assumed in the LOCA analysis are met and the ECCS acceptance criteria limits of 2200*F are not exceeded.
T Please find enclosed as Figures 1 and 2 graphs of Fg x pre 1 versus axial core h9ght based on calculated and surveillance limit Fxy's. All calculated 1
FQ x pre 1 for the Cycle 4 core meet the 2.25 x K(z) LOCA envelope (shown by solid line) for the standard fuel with substantial margin. The NRR staff has requested that these graphs be included in this submittal. The Cycle 4 design precludes the Vantage 5 demonstration assemblies from being more limiting than the standard design fuel assemblies during normal and transient conditions.
If you should have any questions, please advise.
Very ruly 6urs, (A.
e aum n RBW/ DAN:jez Attachments c:
Page 3 j
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Dr. J.' Nelson Grace
' March 6, 1987
.Page 3 of 3 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.
Group Managers W. R. Baehr C. A. Price-W. T. Frady C. L. Ligon (NSRC)
R. M. Campbell, Jr.
K. E. Nodland R. A. Stough G. O. Percival R. L. Prevatte J. B. Knotts, Jr.
I&E Washington Chief. Core Performance Branch NPCF File l
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FIGURE 1 MAXIMUM F x P Rel NORMAL OPERATION; BASED ON CALCULATED F
's xy 2.4 2.3 X X X X X
Xv 2
^XX X^
X X XXXX X
X X
X 1.s X
X E
1.s m
M w er 1,4 1.2 X
0.8 0
2 4
8 8
10 12 CORE HEIGHT (Feet)
FIGURE 2 MAXIMUM F x P VERSUS AXIAL CORE HEIGHT DURING Rel NORMAL OPERATION; BASED ON SURVEILLANCE LIMIT F
's xy 2.4 N
X xX 2CXXXX)X X
X X XX X X XX X X XX'<X v
2 X
1.8 X
X T
f
\\
s er X
1.4 1.2 l
1 l
0.8 i
0 2
4 8
8 10 12 l
i CORE HEIGHT (Feet) l
. _ _ _ _ _. _,,.... _ _..