ML20028G992

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Rev 2 to Core Operating Limits Rept Unit 1 Cycle 14
ML20028G992
Person / Time
Site: Prairie Island Xcel Energy icon.png
Issue date: 09/27/1990
From: Eckholt E
NORTHERN STATES POWER CO.
To:
Shared Package
ML20028G991 List:
References
NUDOCS 9010050065
Download: ML20028G992 (18)


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,-:j c PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIN7T8 REPORT g

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PRAIRIE ISLAND NUCLEAR GENERATING PIANT -

CORE OPERATING LIMITS REPORT i

1 Unit 1 - Cycle 14 Revision 2 1

This report provides the values of the limits for Unit 1 Cycle 14 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.

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Heat Flux Hot Channel Factor Limits f

Lli RTP

'Fg - 2.50

- U Z) values are provided in Figure 1.

l V(Z) values are provided in Figures 2a through 21.

- Reference Technical Specification Sections:

3.10.B.1 and 3.10.B.2 1

f

.h Jr. enthalov-Rise ' Hot Channel Factor - Limits RTP P y = 1.'"

k nut'

. enthalpy rise hot channel factor exceeds its limit in Technical z

u7 f ue on 3.10.B.1,- reduce the high neutron flux trip setpoint by 3.33% -

,,ercent that the measured' nuclear enthalpy rise hot channel factor c.

exceeu' the 3.10.B.1 limit.

y Ret'e renes Technical Specification Sections: 3.10.B.1, 3.10.B.2 and 3.10.B.3 5

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v CJrs oper: ting Lirits R: port, Wsit 1. Cy313 14 Revision 2-3,p Page 2 of 17 Linear Heat Generation Rate The.95% probability level ECCS analysis calculation utilized a peak linear heat generation rate of 14.2 kw/ft.

The Arper. dix K ECCS analysis calculation utilized a peak linear heat generation rate of 15,8 kw/f t for the Fn limit of 2.5.

s

Reference Technical Specification Section: 3.10.B 4QLTj et Difference Limits f

The axial flux difference limits are provided in Figure 3.

1 The Axial. Flux Difference target band is 15%.

Reference Technical Specification Sections: 0.10.B.4 through 3.10.B.9 l

Shutdown Rod Insertion Limits The shutdown rods shall be fully withdrawn.

Reference. Technical Specification Section: 3.10.D Control Rod Insertion Limits The control rod banks shall be limited in physical insertion as shown in Figures 4, 5 and 6.

Reference Technical Specification Sections: 3.10.D and 3.10.G Reactor Coolant Flow Limit y

The reactor coolant system flow shall be a 178,000 gpm.

Reference Technical Specification Section: 3.10.J L

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t CIra oper tina Limite Riport-Unit 1. Cycis 14 Revision 2

.i Pese 3 of 17-AM 9 2.lo /9 o Prepared By:

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Eugene %ckholt Date i

R'eviewed By:

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Thomas Breene Superintendent of Nuclear Engineering Prairie Island

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8, f M !70 to[rknderson Dat'e Manager Nuclear An lysi Approved By:

W f 27 fd Thomas M Parker

'Date' i

Manager Nuclear Support Services

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Core Operating' Limits Report.

Unit 1. Cycle 14-Revision 2 Page 4 of 17 1.2 1

(6.0.1.0)

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2 4

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10 12 Core lieight (ft)

Figure 1 Il0T CilANNEL FACTOR NORMALIZED OPERATING ENVEIMPE

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Core Operet,ing Limit.s' Report. -

s n Page S of 17 Figure 2a V(Z) ASTA FUNCTION OF~ CORE HEIGHTL UNIT 1 CYCLE 14 (5,000 MWD /MTU)-

v(z) penalty 1.14 g

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Page 6 of 17 t, -

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C:ts Oper: ting Lirits R: port Unit 1. Cycle 14 Revision 2 Page 7 of 17 Figure 2c V(Z) AS A FUNCTION OF CORE HEIGHT UNIT'l CYCLE 14 (7,000 MWD /MTU):

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V(Z) AS: A FUNCTION OF CORE HEIGHT UNIT 1 CYCLE 14 (8,000-MWD /MTU) v(z) penalty j

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Cira oper: ting Limits Rrport Unit 1. Cycis 14 Revision 2 Page 9 of 17 Figure 2e

'V(Z)- AS A FUNCTION OF CORE HEIGHT UNIT l' CYCLE 14 (10,000 MWD /MTU).

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. Figure,. 2f V(Z) AS T A FUNCTION OF CORE HEIGHT UNIT 1 CYCLE 14 (12,000. MWD /MTU) v(z) penalty 1.14 1.13 i

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