ML20214N334
| ML20214N334 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 09/09/1986 |
| From: | Tucker H DUKE POWER CO. |
| To: | Harold Denton, Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8609160246 | |
| Download: ML20214N334 (5) | |
Text
.
DUKE POWER GOMPANY P.O. box 33180 CHAmLOTrE, N.C. 28242 HALB.TUCREH TELEPHONE
@M) GNM vaca Fassumewr wCCLEAS FnGDt?Ct9UN September 9,1986 4.
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. B. J. Youngblood, Project Director PWR Project Directorate No. 4
Subject:
McGuire Nuclear Station, Unit 1 Docket No. 50-369 McGuire 1/ Cycle 4 Reload - Peaking Factor Limit Report
Dear Mr. Denton:
3 My letter of May 15,1986 (as supplemented via letters dated May 23, June 6, June 30, and July 10, 1986) submitted proposed McGuire 1/ Cycle 4 0FA reload license amendments (including the attendant radial peaking factor limit report required pursuant to Technical Spec,1fication 6.9.1.9) to Facility Operating Licenses NPF-9 and NPF-17 for McGuire Nuclear Station, Units 1 and 2, respectively. This submittal was subsequently revised / supplemented by my letters of August 4 and 12, 1986 as a result of a core redesign necessitated by fuel assembly problems discovered during the refueling outage. The revised / supplemented submittal indicated that evaluation of the unit 1/ cycle 4 core redesign had verified that the previously submitted peaking factor limit report (PFLR) remained applicable for the redesigned core cycle. Subsequently, the NRC issued the requested McGuire 1/ Cycle 4 0FA reload license amendments on August 22, 1986 (Amendment Nos. 60/41).
t j
When the core redesign was necessitated by removal of a damaged fuel assembly, Westinghouse (MNS NSSS Vendor) reevaluated the PFLR W(Z) functions and concluded i
l that the originally intended cycle 4 core design W(Z) functions were adequately I
conservative to cover the redesign core. This work and conclusion was reviewed by one of the Westinghouse designers who was later realized to have contributed to l
other phases of the overall redesign effort.
Consequently, to comply with Westinghouse internal requirements that all work be verified by someone independent j
of the particular design analysis, Westinghouse recently initiated a second review.
It was the concern of this second reviewer that a certain portion of the W(Z) curve j
may have been non-conservative near the top of the curve, and indeed upon reexamination the RAOC operation W(Z) function was determined to require a small i
increase near the top of the core.
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Mr. Harold R. Denten, Director September 9, 1986 Page Two Accordingly, please find attached new figures 1, 2, and 3 to replace the like-numbered figures in the previously submitted PFLR (reference my May 23 and June 6,1986 letters) which are the appropriate W(Z) functions for RAOC operation.
Previously submitted figures 4, 5, and 6 applicable to base load operation remain unchanged and applicable to the cycle 4 core redesign. Note that no technical specification changes (including the reload related technical specifications of license amendments 60/41) are required as a result of this PFLR revision. Since McGuire Unit 1 is currently involved in cycle 4 startup operations an exemption (in accordance with the provisions of Technical Specification 6.9.1.9) from the 60 days prior to cycle initial criticality /date the values would become effective submittal requirement will be necessary. Duke will administratively implement these new figures pending NRC review. This matter has previously been discussed in a telecon between Mr. P. B. Nardoci (Duke Power Company) and Mr. D. S. Hood of your staff on September 9, 1986.
Should there be any questions concerning this matter or if additional information is required, please advise.
Very truly yours, k
Act al B. Tucker PBN/01/ sib Attachment xc:
Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Dayne Brown, Chief Radiation Protection Branch Division of Facility Services Department of Human Resources P. O. Box 12200 Raleigh, North Carolina 27605 i
Mr. Darl Hood Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Mr. W. T. Orders Senior Resident Inspector McGuire Nuclear Station
=. - - - - -. _ -.
i i
t 1
3 i
HEIGHT 80L (FEET)
W(Z)
- O.00 1.000
- 0.20 1.000 1
0.40 1.000
- 0.60 1.000 0.80 1.000 1.00 1.000 i
1.20 1.000
=
=
1.40 1.000 i
I 1.60 1.000 1.60 j
1.80 1.543 2.00 1.514 1
2.20 1.483 1.55 2.40 1.453 w
2.60 1.423 i
2.80 1.395
,r 3.00 1.370 1*50 3.20 1.349 3.40 1.330 3.60 1.315 1.45 3.80 1.304 4.00 1.294 w
4.20 1.285 l
4.40 1.274 1.40 4.60 1.261 1
I 4.80 1.245 5.00 1.228 f
1.35 5.20 1.209 5.40 1.188
}
5.60 1.171 x
5.80 1.162 U
1.3o 6.00 1.165 7
6.20 1.171 e '
l 3
1 w
6.40 1.171 j
Z 6.60 1.170 1.25 6.80 1.168 1
7.00 1.165 7.20 1.160 7.40 1.152 a
1.20 7.60 1.142 1
7.80 1.130 8.00 1.116
'ur--
1.15 1
8.20 1.102
^
2t 8.40 1.085 u
a
^
8.60 1.076
^
'(
8.80 1.084 r
9.00 1.095 1.10 it xw 9.20 1.106 9.40 1.118 9.60 1.128 1.05 g,go g,g37 10.00 1.146 10.20 1.158
- 10.40 1.000 g -
0 2
4 6
8 to 12
- 10.80 1.000
- 11.00 1.000 BOTTOM CORE HEIGHT (FEET)
TOP 1l 20 l,ggj
- n.60
- 1. m FIGURE 1
- 11.80 1.000 McGuire Unit 1 Cycle 4 RAOC W(z) at 150 MWD /MTU Top and Botton 15% Excluded as per Tech Spec 4.2.2.26
HEIGHT MOL (FEET)
W(Z)
- O.00 1.000 O.20 1.000 O.40 1.000
- O.60 1.000
- O.80 1.000 1.00 1.000 1.20 1.000 1.40 1.000 1.60 1.000 1.40 1.80 1.271 2.00 1.256 2.20 1.241 2.40 1.225 2.60 1.210 2.80 1.196 1.35 3.00 1.191 3.20 1.193 3.40 1.198 3.60 1.205 3.80 1.212 1.30 -
4.00 1.217 gg 4.20 1.219 g
gp 4.40 1.219 n
4.60 1.217 K_
4.80 1.216 E
^
"w
^
5.00 1.215 1.25
- 'v
^
5.20 1.211 w
^
J:
5.40 1.206 x
5'.60 1.206 gvvvggy A 5.80 1.218 g
x x(
6.00 1.238 n
- 1. 20 --
6.20 1.258 gj 3
6.40 1.271 6.60 1.282 6.80 1.290 7.00 1.294 7.20 1.295 1.15 7.40 1.292 7.60 1.287 7.80 1.279 8.00 1.270 8.20 1.260 l
1.10 8.40 1.251 i
8.60 1.242 8.80 1.232 9.00 1.235 9.20 1.247 9.40 1.258 1.05 9.60 1.266 9.80 1.271 10.00 1.276 10.20 1.280
- 10.40 1.000 1 --^^^^-^^
- 10.60 1.000 3
- 10.80
- 1. M O
2 4
6 8
10 12
- 11.00 1.000
- 11.20 1.000 BOTTOM CORE HEIGHT (FEET)
TOP 11.4o 1.000
=
- 11.60 1.000 FIGURE 2 1,.80 1.000
- 12.00 1.000 McGuire Unit I Cycle 4 RAOC W(z) at 6000 MWD /MTU
- Top and Bottom 15% Excluded as per* Tech Spec 4.2.2.2G
HEIGHT EOL (FEET) w(Z) 0.00 1.000
=
- 0.20 1.000
+ 0.40 1.000
- O.60 1.000 O.80 1.000 1.00 1.000 1.20 1.000 1.40 1.000 1.60 1.000 1.80 1.225 2.00 1.218 1.40 2.20 1.210 2.40 1.203 2.60 1.197 2.80 1.190 3.00 1.181 1.35 g%
3.20 1.180 3,40 1.190 g
o 3.60 1.204 X
^
3.80 1.217 Y
4.00 1.228 Ji 4.20 1.237 1.30 JL 4.40 1.243 i
X 4.60 1.247 a
4.80 1.248 5.00 1.245 A
5.20 1.242 1.25 Z
5.40 1.250 NU 5.60 1.267
^
5.80 1.286 X
d' X
6.00 1.307 A
^
.d' 6.20 1.326 l
N N
Y w'
6.40 1.337 1.20 A
6.60 1.746 3B 6.80 1.350
?M 7.00 1.351 7.20 1.347 7.40 1.329 7.60 1.328 1.15 7.80 1.313 8.00 1.297 8.20 1.279 8.40 1.261 8.60 1.241 1.10 8.80 1.219 9.00 1.208 9.20 1.207 9.40 1.209 9.60 1.211 9.80 1.213 1.05 10.00 1.218 10.20 1.225
+ 10.40 1.000 1
- 10.60 1.000 3
- 10.80 1.000 1.________.
. it.oo 1,000
- 11.20 1.000 0
2 4
6 8
to 12
. gg,4o g,ooo
"**0
O BOTTOM TOP CORE HEIGHT (FEET)
- 11.80 1.000 i
e 12.00 1.000 FIGURE 3 McGuire Unit 1 Cycle 4 RAOC W(z) at 12000 MWD /MTU 1
- Top and Botton 15% Excluded as per Tech Spec 4.2.2.20
_ _. _ _ _ _.. _ _ - _. _ _.