ML20095J754
| ML20095J754 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 04/27/1992 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20095J749 | List: |
| References | |
| NUDOCS 9205040128 | |
| Download: ML20095J754 (5) | |
Text
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MTAttiMBL2 M2C_4_CorJL0p enting_ LinLtLEesort w
i 9205040128 920427 PDR ADOCK-05000455 l
p PDR ZNLD/1764/5 2
.i
Byron Unit 2 Cycle 4 Operating Limit Report - Fxy Portion This Radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.9 of ine Byron Unit 2 Nuclear Plant Technical Specifications.
1 The Fxy limits for RATED THERMAL POWER within specified core planes for Cycle 4 shall 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:
RTP F
1 1.990, for Bu 1 8000 MHD/MTU xy 1 1.990, for Bu > 8000 MHD/MTV 2.
For all unrodded core planes:
RTP F
1 1.784, for Bu 1 8000 MHD/MTU xy 1 1.656, for Bu > 8000 MHD/MTU b.
For the upper core region from greater than 50% to less than.or equal to 1001.:
1.
For all planes containing bank "D" control tods:
1 F
1 1.952, for Bu 1 8000 MWD /MTU 1 1.95?
' r. c Bu > 8000 MHD/MTU 2.
For all unrodded core planes:
~
F 1 1.732, for Bu 1 8000 MHD/MTU xy 1 1.778, for Bu > 8000 MHD/MTU These Fxy(z)-limits were used to' confirm that the heat flux hot channel factor FQ(z) will be limited to the Technical Specification values of:
F (z)1[2.Jol [K(z)]
for P > 0.5 and, 9
P Fn(z)1[5.00] IK(z)]
for P 1 0.5 assuming the most limiting axial power distributions expected to resuit ft om the insertion and removal of Control Banks C and D.during operation, including the accompanying variations in-the axial xenon and power distributions as~
described in the " Power Dit;tribution Control and Load Following Procedures",
WCAP-8403,. September, 1974.
Therefore, these F limits provide assurance-thatthe.initialconditionsassumedintheLOCAknalysisaremet,alongwith x
the ECCS acceptance criteria of 10 CFR 50.46.
See Figures'l and-2 for plots of [F.PRel).vs. Axial _ Core Height.
ZNLD/1764/6
e e
' FIGURE 1 DYRON 2 CYCLE 4 Fxp LIMIT ANALYSIS - BU I 6000
=
9.68 ct. e.
- 2. so) 2.50
_~%
(
- 12. e,
- z. 31)
~
Pk 2 4g.
2 30~
4 2.28-4" -
m 2.102-I tu iR 2. 00 -
a to 1.98 U 1. 88 cc
-i iI$1.78-m x1.68:-
@ 1.58
"-1.43"
+- Top Surveillance Limi t
' 1 a
^
1'38-
}
+ Bottom Surveillance Limit
[
1.20 CAOC Analysis Points 1.10-i
.- LOCA Limi t ing Enve Iope
- 1. g o.
e N
w v
Y w
v i
0 1
2 3
4 5
6 7
8 9
10 11 12 TOP BOTTOM CORE HEIGHT (FT) c 1
v
~
FIGURE 2 DYRON 2 CYCLE 4 Fxy LIMIT ANALYEIS - BU >
6000
=
2.68 (t..i. O,
- 2. 5B) 2.56-
[
N
(
12.0*
2.31)
=
. x NA g' 4 g N
- 2. 38' 2.20 I
I tu 2.18 3-w 8 2.00; i
c' w 1.98~
m s 1.88; a
Gi1.78-f x 1. bii j
m 6 1.50 l
"- 1 4 8 -
e-Top Surveillance Limi t a
1.38-
-+ Bot tom Surveillance Limit 1.28 CAOC Analysis Points 1.13 1.00-
-*-- LOCA Limi t ing Enve l ope NNY MN4* '
q f
v v I
- M
" O k" Y v
.'O 1
2 3
4 5
6 7
8 9
10 11 12 EP 00HOM CORE ilEIGHT (FI)
l-I ATTACHBEH1,3 Refetencel I.
Westinghouse HCAP-9272-P-A, " Westinghouse Reload Safety Evaluation Methodology," dated October 1985.
2.
CECO /NFS 'opical report NFSR-0081, " Benchmark of PHR Nuclear Design Methods using the PHOENIX-P and ANC Codes," (dated July 1990) submitted for NRC review by letter from J. S11ady to T. E. Murley dated July 13, 1990.
3.
NRC SER on CECO's PHOENIX /ANC Topical 'Ref. 2) dated March il, 1991.
4.
Westinghouse topical report HCAP-11596-P-A, " Qualification of the PH0ENIX/ANC Nuclear Design System for Pressurized Hater Reactor Cores," dated September 1936.
5.
Westinghouse topical report HCAP-10965-P-A, "ANC: Westinghouse Advanced Nodal Computer C7de," dated September 1986.
e 6.
CECO submittal, R.A. Chrzanwski to T.E. Murley, " Byron Station Units 1 and 2 Application to Facility Operating License NPF-37 and NPF-66,"
dated July 31, 1989.
7.
NRC letter from L.N. 01shan to T.E. Kovach, Amendment No. 36 "Use of VANTAGE 5 Fuel," dated January 31, 1990.
t-ZNLD/1764/7
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