ML20059A297
| ML20059A297 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/20/1993 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20058P968 | List: |
| References | |
| BY2C5, BY2C5-R, BY2C5-R00, NUDOCS 9310260289 | |
| Download: ML20059A297 (4) | |
Text
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ATTACHMENT 2 BY2C5 Operating Limits Report 4
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Byron Unit 2 Cycle 5 Operating Limit Report - Fxy Portion This Radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.9 of the Byron Unit 2 Nuclear Plant Technical 5pecifications.
The Fxy limits for RATED THERMAL POWER within specified core planes for Cycle 5.Mll i
be:
a: For the lower core region from greater than or equal to 0% to less than or equal to 50%:
- 1. For all core planes containing bank "D" control rods:
fy# s 2.005
- 2. For all unrodded core planes:
[y# s 1.699 b: For the upper core region from greater than 50% to less than or equal to 100%:
- 1. For all core planes containing bank "D" contrci rods:
/"## s 2.005 7
- 2. For all unrodded core planes:
l~##s1.777 7
These Fxy(z) limits were used to confirm that the heat flux hat channel factor FQ(z) will be limited to the Technical 5pecification values of:
Fo(z)s ~2.50'[K(z)] for P > 0.5 and
. y _
i Fo(z)s[s.co][K(z)] for e s o.s i
assuming the most limiting axial power distributions expected to result from the insertion and removal of Control Banks C and D during operation, including the accompanying i
variations in the axial xenon and power distributions as described in the " Power Distribution Control and Load Following Procedures" WCAP-8403, September,1974.
Therefore, these Fxy limits provide assurance that the initial conditions assumed in the LOCA analysis are met, along with the ECCS acceptance criteria of 10 CFR 50.46.
.t See the Attached Figure for the plot of Fh* pre /
vs. Axial Core Height.
BYRON UNIT 2 CYCLE 5 REV' 0 T>
FQ (Z) X P vs.
CORE HEIGHT ag FXY LIMIT ANALYSIS M
2.60_
3, g
,,,,, 2, 3,,
2.50 I
I N ?+
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( 12'8'
'3l) 2 40 A_
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x xxx xx- ^ ^x
^
pg 2.30 N
x x
x g
2.20:
x g
x g.10-?
l l
2
@ 2.00!
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x ty 1.90:.
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y 1. 00 l
l I
I y1.70 x 1. 60 :
j j
O1.50!
c5 1
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' l 40:
-- - Top Surveillance Limi t 1.30~
-- Bottom Surveillance Limii 1.20 I
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FXY Analysis Points l
x g,3g I
I 1.00!
l LOCA Limiting Envelope l
0.90:
l l
l l
l l
A:
0 1
2 3
4 5
6 7
8 9
18 11 12 BOT W TOP CORE HEIGHT (FT)
NFS/PND SY 9/02/93
i ATTACHMENT 3 References
-l 1)
Westinghouse WCAP-9272-P-A, dated October 1985; " Westinghouse Reload Safety Evaluation Methodology", (originally issued March 1978).
2)
CECO submittal, J.A. Silady to T.E. Murley dated July 13,1990; entitled
" Commonwealth Edison Company Topical Report on Benchmark of PWR Nuclear Design Methods Using The 'hoenix-P and ANC Computer Codes", NRC Docket Nos. 50-295/304,50-454/455, and 50-456/457.
3)
NRC SER on CECO's Neutronics Topical (Ref. 2) dated March 11,1991.
4)
CECO submittal, F.G. Lentine to H.R. Denton dated July 27,1983; entitled " Zion Stations Units 1 and 2, Byron Station Units 1 and 2, Braidwood Station Units 1 and 2, Commonwealth Edison Company Topical Report on Benchmark of PWR Nuclear Design Methods", NRC Docket Nos. 50-295/304, 50-454/455, and 50-456/457.
5)
NRC SER on CECO's Neutronics Topical (Ref. 4) dated December 13,1983.
6)
NRC Letter from L. N. Olshan (NRC) to T.J. Kovach (CECO), Amendment No. 36, "Use of VANTAGE 5 Fuel", dated January 31,1990.
7)
CECO submittal, S.C. Hunsader to T.E. Murley "Braidwood Stations Unit 1 and 2 Application to Facility Operating License NPF-72 and NPF-77", dated October 14,1989.
k 8)
Letter from T. Simpkin (CECO) to T. E. Murley (NRC), " Boron Dilution Protection System License Amendment Request," dated July 28,1992.
9)
Letter from J. B. Hickman (NRC) to T. J. Kovach (CECO), " Issuance of Amendments, Braidwood Technical Specification Amendment 40 and Byron Tc.nical Specification Amendment 51, to reflect changes to the current Baron 1
Dilution Analyses", dated October 5,1992.
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