ML20235U302
| ML20235U302 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 03/02/1989 |
| From: | Chrzanowski R COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8903090137 | |
| Download: ML20235U302 (7) | |
Text
_ _ _ - _ _ _ _
i e
_ Commonwanith Edison O
One First National Plaza, Chicago, Illinois Q'
Address Reply to: Post Office Box 767 Chicago, tilinois 60690 March 2,,
1989 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 l'
Attn: Document Control Desk
Subject:
Byron Station Units 1 and 2 l
Braidwood Station Units 1 and 2 Operating Limits Report l
1@C DoIkat Nos. 50-45.4/455 and 50-456/457
Reference:
December 12, 1988, letter, from R.A. Chrzanowski to T.E. Murley
Dear Dr. Murley:
The referenced letter contair;ed the Byron and Braidwood application for amendment to Facility Operating Licenses NPF-37, NPF-66, NPF-72 and
'NPF-77 for Technical Specification 4.2.2.2.e for the Fxy limits. The proposed amendment deleted the fixed Fxy limit and replaced it with a requirement to submit an Operating Limit Report. The attachments to this letter provide the Operating Limits Reports for By on Units'l and 2.
Braidwood Units 1 and 2 Operating Limits Reports will be submitted following the first refueling outage for each unit.
Please direct any questions on this matter to this office.
Very truly yours, f W-GNGUh
/
R.A. Chrzanowski Nuclear Licensing Administrator
/sc1:0046V:1 cc Resident Inspector-Byron Resident inspector-Braidwood S. Sands-NRR L. Oishan-NRR l
Region III Office M.C. Parker-IDNS I \\
i 890309013/ 890302 ADOCK03OOg'f PDR P
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ATTACHMENT A
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BYRON UNIT 1 CYCLE 3
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~ OPERATING LIMITS REPORT'- Fxy PORTION l
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- c Byron Unit 1 Cycle 3 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 1 Nuclear Plant Technical Specifications.
The Fxy limits for RATED THERMAL POWER within specified core planes for Cycle 3 shall be:
a.
For the lower core region from greater than or equal to 0% to less than or equal to 50%:
1.
FQ}P less than or equal to 1.85 for all core planes containing bank "D" control rods, and 2.
Fj}P less than or equal to 1.61 for all unrodded core planes.
b.
For the upper core region from greater than 50% to less than or equal to 100%:
1.
FQJP less than or equal to 1.85 for all core planes containing bank "D" control rods, and 1.
FQyP less than or equal to 1.64 for all unrodded core planes.
These Fxy(z) limits were used to confirm that the heat flux hnt channel factor F0(z) will be limited to the Technical Specification values of:
Fg(z)1[2.32] [K(z)]
for P > 0.5 and, P
F (z)1[4.64] [K(z)]
for P 1 0.5 Q
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 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.
See Figure 1 for a plot of [Ff.PRel] vs. Axial Core Height.
ID:9365N/18
igure Maximum TPower versus Axia eig1.
l During Norma
- ore:) era. ion 2'(0 l6.0, 2.32 2.30
- =-
(
N
' "- 0.2 146?
2.20
,,,,1-s q j
2.10 2.00 i
= 1.90 E1.80 E1.70
$1.60 21.50
$1.40 1.30,
1.20 1.10 1.00 O.90 0
1 2
3 4
5 6
7 8
9 10 11 12 80T10ll COREHEIGHTlfI?
TOP i
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L___------------------
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i ATTACHMENT B l
s BYRON UNIT 2 CYCLE 2 i
OPERATING LIMITS' REPORT - Fxy PORTION l
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- l 7
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I Byron Unit 2 Cycle 2 Limit Report - Fxy Portion 4
This Radial Peaking Factor Limit is provided in accordance with Paragraph 6.9.1.9 of the Byron Unit 2 Nuclear Plant Technical Specifications.
The Fxy limits for RATED THERMAL POWER within specified core planes for l
Cycle 2 shall be:
a.
For the lower core region from greater than or equal to 0% to less than or equal to 50%:
1.
F]JP less than or equal to 1.85 for all core planes containing bank "0" control rods, and 2.
FjjP less than or equal to 1.61 for all unrodded core planes.
b.
For the upper core region from greater than 50% to less than or equal to 100%:
j 1.
Fj}P less than or equal to 1.85 for all core planes
{
containing bank "D" control rods, and pl}nes.FQ P less than or equal to 1.64 for all unrodded core 1.
3 a
~
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[2.32] [K(z)]
for P > 0.5 and, Q
P Fg(z)1[4.64] [K(z)]
for P 1 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-8403, September,1974.
Therefore, these F limits provide assurance xy that the initial conditions assumed in the LOCA analysis are met, along with the ECCS acceptance criteria of 10 CFR 50.46.
See figure 1 for a plot of [Ff PRel] vs. Axial Core Height.
A-1 ID:8536N/76 t
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M0Ximum T *3 0W0fV0fSUSAxi0
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JUflA{g10fm0 C0fB
)ef0.iOA 2'40 l
6.0, 2.32 2.30=
s II 2 0c2146' 220 gg i
1,1 1
2.10
,1 g
g 3
1.90
= 1.80
=
=
=
m 51.10
$1.60 21.50
~
E1.40 1.30 1.20 1.10 1.00 0.90 0
1 2
3 4
5 6
7 8
9 10 11 12 80TI0ll COREWElGHT[fT' TOP A-2