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Core Operating Limits Report for Prairie Island, Unit 1 Cycle 21, Revision 2 and Unit 2 Cycle 21, Revision 1
	ML023100558
Person / Time
Site:	Prairie Island
Issue date:	10/29/2002
From:	Nazar M; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML023100558 (52)
	v • d • e

SComitted to 10VrP Mano K. Nazar Site Vice President.

Prairie Island Nuclear Generating Plant

Nuclear Management Company, LLC 1717 Wakonade Dr. East a Welch MN 55089 October 29, 2002 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC:20555

, PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 Ucense No. DPR-42 Docket No. 50-306 Ucense No. DPR-60 Core Operating Limits Report for Prairie Island Unit I Cycle 21, Revision 2 and Unit 2 Cycle.21 Revision I The attached revisions to the Core Operating Limits Reports for Prairie Island Unit 1 Cycle 21, Revision 2 and Unit 2 Cycle 21, Revision 1, are provided in accordance with the requirements of Technical Specification Section 5.6.5.d. The limits specified in the attached Core Operating Limits Reports have been established using NRC approved methodologies.

The Unit I Core Operating Limits Report has been revised to support License Amendment 158 changes, including revision of all references to Technical Specifications, revision of Fa symbols and addition of the following features:

"* Table 4, FoA Factor

"* Isothermal Temperature Coefficient limits

"* RCS Pressure and Temperature - Departure from Nucleate Boiling limits

"* Refueling Boron Concentrations.

The Unit 2 Core Operating Umits Report has been revised to support License Amendment 149 changes which comprised the same changes as those identified above for Unit 1. Revision I to the Unit 2 Core Operating Limits Report also includes an additional V(z) curve to give greater Fo margin between 13.0 and 16.0 GWd/MTU.

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NUCLEAR MANAGEMENT COMPANY USNRC October'29, 2002 Page 2 of 2 The Nuclear Management Company has not made new or revised existing Nuclear Regulatory Commission commitments in this letter or the attachments. Please contact Dale Vincent (651-388-1121) if you have any questions related to these reports.

Mano K. Nazar Site Vice Presi ent Prairie Island uclear Generating Plant c:

Regional Administrator - Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC James Bernstein, State of Minnesota Attachments:

Core Operating Limits Report - Unit I Cycle 21, Revision 2 Core Operating Limits Report - Unit 2 Cycle 21, Revision I

44 PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 1 - CYCLE 21 REVISION 2 Note: This report is not part of the Technical Specifications This report is referenced in the Technical Specifications L- ý

Core operating Limits Report Unit 1, Cycle 21 Revision 2 PRAIRIE ISLAND NUCLEAR GENERATING PLANT CORE OPERATING LIMITS REPORT UNIT 1-CYCLE 21 REVISION 2 This report provides the values of the limits for Unit 1 Cycle 21 as required by Technical Specification Section 5.6.5. These values have been established using NRC approved methodology and are established such that all applicable limits of the plant safety analysis are met.

Heat Flux Hot Channel Factor (FQ(Z)) Limits The Heat Flux Hot Channel Factor, FQ(Z), shall be limited by the following relationships:

FQ(Z) < CFQ K(Z) for P > 0.5

-P FQ(Z) < CFQ K(Z) for P < 0.5

0.5 Where

CFQ = 2.40, K(z) values are provided in Figure 1.

p = THERMAL POWER RTP FQ (Z) is approximated by F I (Z) and F ' (Z). Thus, both F * (Z) and F ' (Z) must meet the preceding limits on FQ (Z).

F'(Z) = F' (Z)*(1.0815)

Where:

F Q (Z) is the measured value from the incore flux map NOTE: If the two most recent FQ(Z) evaluations show an increase in the expression maximum over z L

(Z) it is required to meet the FQ (Z) limit with the last F *' (Z) increased by the appropriate factor F ' specified Table 4, or to evaluate FQ (Z) each 7 EFPD.

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Core operating Limits Report Unit 1, Cycle 21 Revision 2 F' (Z) = F'(Z)

V(Z)

Where:

V(Z) values are provided in Figures 2a through 2f and Table I and Table 2.

If either F' (Z) or F w (Z) exceeds the limit, reduce thermal power and the Power Range Neutron Flux-High trip setpoints by 1% for each percent the limit is exceeded.

Reference Technical Specification section: 3.2.1 Nuclear Enthalpy Rise Hot Channel Factor (F^AN) Limits FAHN

1.04 < FART' * [1 + PFDH * (1 -P)]

Where:

FAHRT= 1.77 PFDH = 0.3 P = Thermal Power / RTP If FAHN exceeds the limit, reduce thermal power to < 50% and reduce the Power Range Neutron Flux-High trip setpoints to *55%.

Reference Technical Specification section: 3.2.2 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 generation rate of 15.167 kW/ft for the FQ limit of 2.40.

Reference Technical Specification sections: 3.2.1 and 3.2.2.

Isothermal Temperature Coefficient (1TC)

ITC Upper limit (with all rods at withdrawal limits):

a.

5 pcm]iF for power levels

70% RTP; and

b. 0 pcm/IF for power levels > 70% RTP JTC Lower limit:

a. -32.7 pcm/IF Reference Technical Specification section: 3.1.3.

RCS Pressure, Temperature, and Flow - Departure from Nucleate Boiling (DNB) Limits Pressurizer pressure limit = 2205 psig RCS average temperature limit = 564°F RCS total flow rate limit = 178,000 gpm Reference Technical Specification section: 3.4.1.

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Core operating Limits Report Unit 1, Cycle 21 Revision 2 Axial Flux Difference Limits The axial flux difference limits are provided in Figure 3.

The axial flux difference target band is +/-5% when using figures 2a through 2e and Table

1. The axial flux difference target band is +5% when' equal to or above 90% power and +

10% below 90% power when using figure 2f and Table 2.

Reference Technical Specification sections: 3.2.3.

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

Reference Technical Specification section:3.1.5.

Control Rod Insertion Limits The control rod banks shall be limited in physical insertion as shown in Figures 4, 5, and

6.

The control rod banks withdrawal sequence shall be Bank A, Bank B, Bank C, and finally Bank D.

The control rod banks shall be withdrawn in 100 step overlap.

Reference Technical Specification sections: 3.1.6.

Shutdown Margin Requirements Minimum Shutdown Margin requirements are shown in Table 3.

Reference Technical Specification sections: 3.1.1 and 3.1.8.

Refueling Boron Concentrations The boron concentration of the reactor coolant system and the refueling cavity shall be sufficient to ensure that the more restrictive of the following conditions is met:

a) Kerr -< 0.95 b) 2000 ppm c) The Shutdown Margin specified in Table 3 Reference Technical Specification sections: 3.9.1.

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Core operating Limits Report Unit 1, Cycle 21 Revision 2 Penalty on Fn for Small Break LOCA - K(z)

The small and large break LOCA analyses performed for this cycle are valid for FQ <2.80 and FQ

< 2.40, respectively. The FQ limit for the large break LOCA analysis is more limiting than the FQ limit for the small break LOCA analysis. The small break LOCA analysis incorporates the K(z) methodology. However, since the small break LOCA is less limiting than the large break LOCA, no K(z) penalty needs to be applied to calculations of most limiting FQ values. Thus for the equation in Technical Specification Bases B3.2.1, K(z) is equal to 1. K(z) is shown graphically in Figure 1.

Transient Power Distribution Penalty for Fo - V(z)

Table I summarizes the bounding V(z) values for the middle 80% of the core for Prairie Island unit 1, cycle 21 with an operating band of+ 5% AL. The V(z) penalty takes the form of straight lines connecting data points determined as a function of core height. A particular V(z) curve is valid over a given exposure range and equilibrium axial offset range as noted in Table 1. The V(z) penalty for each exposure and axial offset range is shown graphically in Figures 2a - 2e.

An alternate two tier V(z) curve is presented in Table 2 and figure 2f. The operating band is

+5% Al at or above 90% power, and + 10% Al below 90% power. This figure is valid over all exposure ranges.

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