ML20058K515

Rev 0 to Praire Island Nuclear Generating Plant Core Operating Limits Rept Unit 2 - Cycle 16

ML20058K515
Person / Time
Site:	Prairie Island
Issue date:	12/08/1993
From:	NORTHERN STATES POWER CO.
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References
NUDOCS 9312150268
Download: ML20058K515 (11)

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PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT Unit 2 - Cycle 16 v

Revision 0 6

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j Note: This report is not part of the Technical Specifications.

This report is referenced in Technical Specifications.

i 9312150268 931208 I

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PRAIRIE,IS1AND NUCLEAR CENERATING PLANT I

CORE OPERATING LIMITS REPORT i

t Unit 2 - Cycle 16 Revision 0 I

This report provides the values of the limits for Unit 2 Cycle 16'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

-l applicable limits of the plant safety analysis are met.

j i

Heat Flux Hot Channel Factor Limits l

RTP 2.40 Fo K(Z) values are provided in Figure 1.

V(Z) values are provided in Figure 2.

Reference Technical Specification Sections:

3.10.B.1 and 3.10.B.2 Nuclear Enthalpy Rise Hot Channel Factor Limits j

RTP 4

l F f3 - 1.75 l

PFDH - 0.3 If the nuclear enthalpy rise hot channel factor exceeds its limit in Technical Specification 3.10.B.1, reduce reactor power and the high neutron flux trip-

,l setpoint by 3.33% for each percent that the measured nuclear enthalpy rise. hot channel factor exceeds the 3.10.B.1 limit.

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Reference Technical Specification Sections: 3.10.B.1, 3.10.B.2 and 3.10.B.3 f

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4 Core operQting Limits Report Unit 2, cycle 15 Revision 0 Page 2 of 10 l

Linear Heat Generation Rate The 95% probability level ECCS analysis calculation utilized a peak linear heat generation rate of 14.788 kw/ft.

The Appendix K ECCS analysis calculation utilized a peak linear heat f

generation rate of 15.167 kw/ft for the Fn limit of 2.40.

f Reference Technical Specification Section: 3.10.B I

i byf al Flux Difference Limits

-l The axial flux difference limits are provided in Figure 3.

The Axial Flux Difference target band is 15%.

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

f Shutdown Rod Insertion Limits The shutdown rods shall be fully withdrawn.'

Reference Technical Specifice. tion Section: 3.10.D Control Rod Insertion Limits t

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

{l Reactor Coolant Flow Limit The reactor coolant system flow shall be h 178,000 gpm.

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Reference Technical Specification Section: 3.10.J l

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l Core operating Limits Report i

Unit 2. Cycle 16 I

Revision 0 Fece 3 of 10 4

l Penalty on Fn for Small Break IDCA - K(z)

The Small and Large Break LOCA analyses performed for this cycle are valid for Fo s 2.80 and Fn s 2.40, respectively.

For this combination of Fo limits for the two LOCA analyses, the F limit for the Large Break IACA analysis is more n

limiting than the most limiting Fn used in the Small Break LOCA analysis which i

incorporates the K(z) Methodology. Therefore, no Fq penalty needs to be applied with respect to the Small Break LOCA analysis. Thus, for the.

equations in Technical Specification 3.10.B. K(z) is numerically equal to 1.

K(z) is shown graphically in Figure 1.

Transient Power Oh tribution Penalty for Fn - V(z) l i

The following data summarizes the bounding V(z) values for the middle 80% of-t the core for Prairie Island Unit 2 Cycle 16.

The V(z) penalty takes the form of straight lines connecting the data points given for each exposure range in the table below.

"z" is the core height in feet. The V(z) penalty for each i

exposure range is also shown in Figure 2.

Exposure Range GUD/MTU (z. Boundinz V(z))

i 0-2 0, 1.140 3, 1.085 9, 1.085 12, 1.115 l

2 - 14 0, 1.127 12, 1.127 14 - 19.5 0, 1.220 12, 1.220

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19.5 - 21.5 0, 1.250 12, 1.250

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t Core operating Limits Report Unit 2. Cycle 16 Eevision D Fage 4 of 10 f

ph D 2DE IV7/93 Prepared By:

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Datc ~

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Eugene $ckholt Senior Engineer Licensing and Management Issues Reviewed By:

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/2!7 77 Thomas Breene Date Superintendent of Nuclear Engineering Prairie Island Reviewed By: h. //, ON_

I1!S['73 Oley Nelson Date PWR Process Manager Fuel Resources fA/

/J /7 93 Approved By:

1. Dat'e R'oge[OAnderson Director Licensing and Management Issues

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Core Operatimig 1.1mits Report tinit 2. Cycle 16 Revision 0 Fase 5 of 10 i

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