ML20101A097
| ML20101A097 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 11/28/1984 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19274C469 | List: |
| References | |
| NUDOCS 8412180123 | |
| Download: ML20101A097 (5) | |
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"o SOUTH CAROLINA ELECTRIC Sc GAS COMPANY Post orrica 7e4 COLUMetA. SOUTH CAROUN A 29218
. O. W. DixON, Jm.
vice g.===~r November 28, 1984 NUCLEAR Ort ATIONS Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission L
Washington, D.C. 20555
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Facility Operating License NPF-12 g
Radial' Peaking Factor Limit i
Dear Mr..Denton:
REFERENCES 1.
. Letter dated September 28, 1984 from O. W. Dixon, Jr.
f3CEEG) to J. P.
O' Reilly (NRC)
[
2.
Letter dated November 19, 1984 from E. G. Adensam (NRC) i.
to O. W. Dixon, Jr. (SCEEG) estinghouse Reload Safety Evaluation Methodology" "W
3.
'(WCAP-9272), March, 1978 In' Reference 1 we provided the radial peaking factor limit. report
-for Cycle 2 in accordance with Paragraph 6.9.1.14 of the Virgil C. Summer Nuclear Station Technical Specifications.
Reference'2 requested additional information in the form of a
' plotted graph of predicted Fg x P el versus axial core R
- height. - The requested graph is attached as Figure 1 of ; it shows the predicted envelope of maximum values of Fo x P el for the core and'the limit.
All points meet R
j j;
the Ilmit of 2.32 x K(z) with substantial margin.
Reference 2 also requested additional information concerning the L
.four VANTAGE 5 demonstration assemblies to be loaded in Cycle 2.
L In summary,.the demonstration assemblies have all the VANTAGE 5 features:
L 1.
~ Axial B?ankets
-2.
Integral Fuel Burnable Absorber 3.
- Intermediata Flow Mixer Grids 4.
' Increased Burnup Capability Of f
]
5.
Reconstitutable Top Nozzle
[
d N
perman Sy 1
a f
Mr. Harold R.
Denton November 28, 1984 Page 92 The reload core design places these assemblies into core location B-7, G-14, J-2, and P-9.
This loading ensures that they will not become lead assemblies during normal operation or result in more limiting conditions during transient events than analyzed'for the Westinghouse scandard 17x17 design fuel assemblies.
SCEEG performed an -internal review of the Westinghouse Reload.
Safety. Evaluation for Cycle 2 and concluded that the analyses were performed in accordance with the bounding reload safety o
methodology'as outlined in Reference 3.
Additionally, SCE&G has
-verified.that the Cycle 2 design precludes the four VANTAGE 5 demonstration assemblies from becoming more limiting than the standard design assemblies during both normal operation and transient conditions.
Figures l' and 2 _show beginning and end.of
. cycle radial power distributions which confirm that both assembly
. average _and peak pin powers in the VANTAGE 5 assemblies are well below the maximum values in the core throughout the cycle.
f-Comparing Figures 1 and'2 of Attachment 1 shows that Fg for the l
VANTAGE 5 demonstration assemblies is at least 0.04 lower than Fg 'for the standard fuel at all axial locations.
.The reload safety evaluation demonstrated that technical specification changes are not required for operation of Virgil C.
Summer Nuclear Station Cycle 2.
It was additionally concluded that the introduction of VANTAGE 5 demonstration fuel assemblies into Cycle 2 met all requirements of 10CFR50.59; No technical
~-specification changes are involved and no unreviewed safety questions result.
n
-Your' expeditious review of 'the enclosed material is requested as Cycle 2-initial criticality is currently scheduled for
' December 6,,1984.
This submittal contains proprietary information of Westinghouse Electric Corporation.
In conformance with the_ requirements of 10CFR-Section '2.7 90, ' as amended, of the Commission's regulations,
-an application for withholding from public disclosure and an affidavit will be forwarded along with a proprietary class 3
_ version of the submittal under separate cover.
The affidavit
' sets forth~ the basis on which the information may be ' withheld from public disclosure by the Commission.
- Accordingly, it is respectfully requested that the information
- which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10CFR Section 2.790 of the-
. Commission's regulations.
Correspondence with respect to the
. proprietary aspects of.this application for withholding or the supporting-Westinghouse affidavit should reference CAWO84-104 and r
. _.,.~
2.
- u..
Mr. Harold R.'Denton-November 28, 1984 Page #3 should ' be addressed to R.
A. Wiesemann, Manager of Regulatory and LegislativelAffairs,. Westinghouse' Electric Corporation, Post Of fice Box 355, ~Pittsburgh, Pennsylvania ~ 15230.
I$:you.have;any further questions on this matter, please contact us at'your convenience.'
very truly our c /*
,/
O. W. Dixon, N
OWD/gj
Attachment:
cc:
V. C.
Summer C.
A. Price T.
C. Nichols, Jr./O. W. Dixon, Jr.
C. L. Ligon (NSRC)
E.. H. Crews, Jr.
K. E. Nodland E. C. Roberts R. A.
Stough W. A.
Williams, Jr.
~ G.
Percival D. A.
Nauman C. W. Hehl
.J.
P.
O'Reilly J.
B.. Knotts, Jr.
Group Managers NPCF O.
S.
Bradham File a,
,,.....,...., -,, ~.
FIGURE 1 CYCLE 2 ASSEMBLYWISE POWER AND BURNUP AT 0
MWD /MTU, HFP,.ARO, NO XENON AVERAGE ASSEMBLY POWER. PEAK ASSEMBLY POWER AND AVERAGE ASSEMBLY SURNUP DISTRIBUTION 1.042 1.295 1.072 1.211 1.344 1.252
.851 484 1
1.093 1.391 1.134 1.328 1.415 1.384
.988
.750 14121 7954 18988 14289 0
7307 18646 11455 1.254 1.091 1.258 1.112 1.075 1.054 1.142
.377 2
1.359 1.156 1.357 1.185 1.144 1.117 1.359
.665 11047 18889 0
18506 18690 19284 O
16901 1.073 1.2b7 1.102 1.261 1.209 1.241 1.035 3
1.132 1.356 1.163 1.380 1.295 1.36d 1.379 18790 0
18780 10469 15481
.9148 O
1.229 1.113 1.260 1.051 1.150 1.044
.516 4
1.338 1.185 1.379 1.119 1.318 1.328 1.009
~
12895 16506 1046*d 18409 O
O 15285 1.339 1.067 1.2CO 1.142
.810
.361 5
1.415 1.143 1.200 1.309 1.003
.661 0
18690 15d0' O
13592 17189 1.189 1.028 1.111 0 1.029
.356 6
1.348 1.090 1.347-1.311
.649 11694 19284 9146 0
17189
.881 1.000 1.010
.506 7
.972 1.323 1.314
.991 18683 0
0 15285
.479
.366 8
.741
.454 11455 16901 l
l l
i
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l e
l i
i
FIGURE 2 CYCLE 2 ASSEMBLYWISE POWER AND BURNUP AT 9660 MWD /MTU, HFP, ARO, EQUILIBRIUM XENON AVERAGE ASSEMBLY POWER. PEAK ASSEMBLY POWER APC AVERAGE ASSEMBLY BURNUP DISTRIBU7 ION
.994 1.212 1.058 1.153 1.315 1.164
.860
.562 1
1.048 1.275 1.122 1.237 1.372 1.267
.977
.822 23931 20004 29265 25667 12790 18902 26972 16573 1.181 1.066 1.317 1.071 1.024
.990 1.089 428 2
1.247 1.151 1.380 1.144 1.098 1.059 1.243
.579 22764 29286 12430 27023 28782 29073 10668 20809 1.059 1.317 1.075 1.189 1.143 1.146
.962 3
1.122 1.380 1.154 1.287 1.227 1.257 1.230 29077 12425 29263 22219 26725 20497 9474 1.168 1.073 1.190 1.061 1.265 1.108
.554 4
1.252 1.146 1.287 1.126 1.354 1.315
.948 1
24425 27045 22226 28575 11595 10302 20411 l
1.314 1.024 1.144 1.263
.936 463 5
1.373 1.099 1.228 1.354 1.104
.740 i
12771 28759 26725 11575 22045 21190 1.122
.995 1.150 1.108 461 6
1.238 1.053 1.259 1.315
.736
~22825 29069 20513 10286 21165 l
.872 1.112
.977
.556 7
.CSO 1.273 1.245
.951 27045 11897 9575 20421 l
.566 439 8
.825
.715 l
16597 20883 l
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