ML20012D917

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Rev 0 to Core Operating Limits Rept Unit 2 - Cycle 13
ML20012D917
Person / Time
Site: Prairie Island  Xcel Energy icon.png
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:

A 3// f/ 4'O Steve Schaefer f

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Superintendent of Nuclear Engineering Prairie Island b 6f//pyt.-

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b i-Reviewed By:

a Mana[ger foge Anderson' Da6e Nuclear nal is

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Approved By:

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Manager Nuclear Support Services 4

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Cste operating LI::Its Report I

Unit 2, cycle 13

.j tevision 0 Pope 4 of 9

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10 12 i

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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