ML20094H006
| ML20094H006 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 11/08/1995 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20094H005 | List: |
| References | |
| NUDOCS 9511130297 | |
| Download: ML20094H006 (6) | |
Text
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t ENCLOSURE i
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Braidwood Nuclear Power Station Unit 1 Cycle 6 Operating Limits Report i
9511130297.951108 PDR ADOCK 05000456 P
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NDIT No.
9500M NUCLEAR FUEL SERVICES DEPARTMENT l
Rev. No.
o NUCLEAR DESIGN INFORMATION TRANSMITTAL Page 2 or6 Braidwood Unit ! Cycle 6 Operatine Limit Report - Fxv Portion i
i This Radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.9 of the Braidwood Unit 1 Nuclear Plant Technical Specifications.
The Fxy limits for RATED THERMAL POWER within specified core planes for Cycle 6 shall be:
For the lower core region from greater than or equal to 0% to less than a:
er equalto 50%:
- 1. For a!! core planes containing bank "D" control rods:
i Fn"* s 2.840
- 2. For all unrodded core planes:
F,""s 1.750 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" control rods:
i F,"" s 2.059
- 2. For all unrodded core planes:
Fn""s 1.830 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:
Fo(z) s f2,501[K(z)]
for P > 0.5 and, P
Fo(z) s [5.00][K(z)}
for P s 0.5 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 and the ECCS acceptance criteria of 10 CFR 50.46 are met.
See the Attached Figure for the plot of [ Fo(z) x P,,} vs. Axial Core Height.
l NDIT No.
950036 NUCLEAR TL'EL SERVICES DEPARTMENT Rev. No.
0 NUCLEAR DESIGN INFORMATION TRANSMITTAL
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Page 3 or6 Braidwood Unit 1 Cycle 6 Operatine Limit Report - MTC Portion The Moderator Temperature Coefficient (MTC) limits are:
a:
- 1. The BOUARO/HZP-MTC shall be less positive than +1.5 x 10 ~5ok/k/*F.
- 2. The EOUARO/RTP-MTC shall be less negative than -4.1 x 10 " Ak/k/*F.
b:
The MTC surveillance limit is:
The 300 pfm/ARO/RTP-MTC should be less negative than or equal to J
-3.2 x 10 Ak/k/*F.
i where:
BOL stands for Beginning of Cycle Life ARO stands for All Rods Out i
HZP stands for Hot Zero Thermal Power i
EOL stands for End of Cycle Life RTP stands for Rated Thermal Power
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NDIT No.
950036 4
NUCLEAR IUEL SERVICES DEPARTMENT Rev. No.
O NUCLEAR DESIGN INFORMATION TRANSMITTAL Page 4 of6 BRAIDWOOD UNIT 1 CYCLE 6 s
FXY LIMIT EVALUATION i
Summary of Fq vs. Core Height Fq SPIL Core Height (feet!
Max Fq x P LIMIT O.25038 0.59034 2.5 0.62594 2.0588 2.5 0.87632 2.4738 2.5 1.1267 2.5 2.5 1.3771 2.4659 2.5 2.5 1.6275 2.4878' @Mripa#
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0 NDTT No.
95o036 NUCLEAR FUEL SFRVICES DEPARTMENT Rev. No.
O NUCLEAR DESIGN INTORAtATION TRANSMr!TAL Page iso r
BRAIDWOOD UNIT 1 CYCLE 6 FXY LIMIT EVALUATION (Cont.)
Suminary of Fq vs. Core Height Fq SPIL l
Core Height (feet)
Max Fe x P UMIT
$!@?M5%$101@ WW*MF;gjht9 g;)bggy!Pt37.6.8 BSCGX$n9.8899 42?!qMRg2:3639 A
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10.391 2.3521 2.361 10.641 2.2045 2.353 10.891 2.1217 2.3451 11.142 1.9821 2.3372 11.392 1.609 2.3292 11.768 0.595 2.3174 Shaded asta shows surveillance region.
j Unshaded area (top and bottom 15%) is ignored for this surveillance.
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s NDirNa 950036 e
NUCLEAR F1JEL SERVICES DEPARTMENT Rev. Na o
NUCLEAR DESIGN INFORMATION TRANSMirTAL Page 6 o(6 Braidwood Unit 1 Cycle 6 FQ(Z)x P versus Core Height ca.o.2.so)
,,,gog (12 0,2 it) e s *-
=
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2.2000 e:
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e 2.0000 1.8000 1.6000 l
a Fxy Umst Analysis Points LOCA Umiting Envelope
,,,ogg
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- Bottom Survemance Umit 1.2000
+ Top Survedance Umit a
1.0000 l
l 0.8000
=
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0.4000 l
0.2000 i
0.0000
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1 2
3 4
5 6
7 8
9 to 11 12 i
CORE HEIGHT (FT)
TOP SOTTOM 4
d 4