ML20012D917
| ML20012D917 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island |
| Issue date: | 03/22/1990 |
| From: | Eckholt E NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20012D914 | List: |
| References | |
| NUDOCS 9003290088 | |
| Download: ML20012D917 (10) | |
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT Unit 2 - Cycle 13 t
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-PRAIRIE ISLAND NUCLEAR CENERATING PLANT t
CORE OPERATING LIMITS REPORT t
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Unic 2 - Cycle 13 b
Revision 0 4
1This, report provides the values of the limits for Unit 2 Cyc?e'13 as required' by,. Technical Specification Section 6.7.A 6.
These values have been.
established using NRC approved methodology and are established such that all applicable limits of the plant safety analysis are met.
e; Heat Flux Hot Channel Factor Limits l
RTP Fo - 2'.50:
K(Z) values are provided in Figure 1.
.n V(Z) values are provided in Figure 2.
d
" Reference _ Technical Specification Sections:
3.10.B.1 and 3.10.B.2 6
Nuclear Enthalny RCse Hot Channel Factor Limits RTP F 3g - l'.70 PFDH
.0.3' If;the nuclear enthalpy rise hot channel factor exceeds 'its limit in Technical-Specification 3.10.B.1, reduce the high neutron flux trip setpoint by 3.33%
for each percent that the measured nuclear enthalpy rise hot channel factor exceeds the 3.10.B.1 limit.
Reference Technical Specification Sections: 3.10.B.1, 3.10.B.2 and 3.10.B.3 i
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' ff; Unit 2, cycle 13 Cire operstlne Ll;lts Report '
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. Linear Heat Generation' Rate
+
-i The.95t' probability level ~ECCS analysis calculation. utilized a peak linear
' heat' generation' rate-of~14.2 kw/ft.
LThe~ Appendix K ECCS analysis calculation utilized a peak linear heat
~
- generation rate of 15.8 kw/ft for the F, limit of-2.5.
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' Reference. Technical Specification Section:-3.10.P
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. Axial-Flux Difference - Limits l
g The' axial flux' difference limits'are provided in Figure 3.
H
..Th'e' Axial' Flux Difference targ't band 1s.15%.
e Reference Technical Specification-Sections: 3.10.B.4 through 3.10.B.9;
~ Shutdown Rod Insertion Limits
'The shutdown rods.shall be fully withdrawn.
4 0
Reference Technical Specification Section: 3.10.D Control Rod' Insertion Limits 3
The control rod banks =shall be limited in physical insertion.as:shovn;in "j
Figures 4, 3 and 6.
i Reference Technical' Specification Section: ~3.10.D j
u 4 Reactor Coolant Flow Limib.
r The reactor coolant system-flow shall be a 178,000 gpm.
. Reference Technical Specification Section: 3.10.J s
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Core oper: ting Ll;.its Report Unit 2, Cycl 3 13 L
Revision 0
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Reviewed By:
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Unit 2, cycle 13
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Core Height (f t) r Figure 1 HOT CHANNEL FACTOR NORMALIZED OPERATING ENVELOPE i
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10 12 Core }!eighc. (Ft) 6 Figure 2 V(2) AS A FUNCTION OF CORE HEIGHT
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