Nebraska Public Power DistrictI WWB W-WB 2 ( P 2 WAWB WAWB J where, P = a core thermal power value...

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NLS2003061June 18, 2003

U.S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, D.C. 20555

Subject Core Operating Limits Report, Cycle 22, Revision ICooper Nuclear Station, NRC Docket No. 50-298, DPR-46

Reference: Letter to U. S. Nuclear Regulatory Commission from Michael T. Coyle (NebraskaPublic Power District) dated April 4, 2003, "Core Operating Limits Report"(NLS2003042)

The purpose of this letter is to provide the Nuclear Regulatory Commission (NRC) the revised CoreOperating Limits Report (COLR) for Cooper Nuclear Station (CNS) for Cycle 22. CNS TechnicalSpecification 5.6.5.d requires that the COLR, including any midcycle revisions or supplements, beprovided to the NRC upon issuance for each reload cycle. The Cycle 22 COLR, Revision 0,Reference, contained an administrative error in that Figure 14 was referred to as Figure 18 in the firstparagraph of Section 2.5. In accordance with 10 CFR 50.4 (b) (1), we are also transmitting a copy ofthis COLR to the Regional Office and to the NRC Senior Resident Inspector.

Should you have any questions regarding this matter, please contact Paul Fleming at (402) 825-2774.

Sincerely,

Mich . yleI

/cb

Enclosure

cc: Regional Administrator w/enclosureUSNRC Region IV m

COOPERNUERSTAONP.O. Box 98 / Brownille, NE 68321-0098

Telephone: (402) 825-3811/ Fax: (402) 825-5211www.nppd.com

NLS200306 1 of 2

Senior Project Manager w/enclosureUSNRC - NRR Project Directorate IV-1

Senior Resident Inspector w/enclosureUSNRC

NPG Distribution w/o enclosure

Records w/enclosure

I ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS I

Correspondence Number: NLS2003061

The following table identifies those actions committed to by Nebraska Public Power District(NPPD) in this document. Any other actions discussed in the submittal represent intendedor planned actions by NPPD. They are described for information only and are notregulatory commitments. Please notify the NL&S Manager at Cooper Nuclear Station ofany questions regarding this document or any associated regulatory commitments.

COMMITTED DATECOMMITMENT OR OUTAGE

None

4

.9

I PROCEDURE 0.42 | REVISION 12 | PAGE 14 OF 16

COOPER NUCLEAR STATION

CORE OPERATING LIMITS REPORT

Cycle 22Revision 1

Cycle 22, Revision I-I-

Signature Page

Revision I

Stephen W. LutherPrint

Sig te

Reviewer:

RE Manager:

Paul L. BallingerPrint

Sign/D&

Jerry L. LewisPrint

g y t~~' Sigr/Date

Cycle 22, Revision 1-2 -

Preparer:

1.0 INTRODUCTION

The Core Operating Limits Report provides the limits for operation of the CooperNuclear Station for Cycle 22. It includes the limits for the Rod Block Monitor UpscaleSet Point, Average Planar Linear Heat Generation Rate (APLHGR), and MinimumCritical Power Ratio (MCPR). In addition, this COLR also contains:

- MCPR limits for an inoperable Main Turbine Bypass System(one bypass valve inoperable)

- Power to flow map defining the Stability Exclusion Region- Turbine Bypass System response time- Maximum allowable LHGR

If any of these limits is exceeded, action will be taken as defined in the TechnicalSpecifications.

The core operating limit values have been determined using the NRC-approvedmethodologies given in References 1, 2, 10, and 11 and have been established such thatall applicable plant safety analysis limits are met.

2.0 CORE OPERATING LIMITS

Cooper Nuclear Station shall operate within the bounds of the below limits/values. Theapplicable Technical Specifications are referenced in each subsection.

2.1 Rod Block Monitor Upscale Set Point

The Technical Specifications reflect a reference to Allowable Values for the RodBlock Monitor (RBM) upscale (power referenced) trip level setting, found inReference 9, are as follows:

Lowest Rated Low Trip Set Intermed Trip Set High Trip SetMCPR Limit Point (LTSP) Point (ITSP) Point (HTSP)

(LPSPSP•IPSP) (IPSP<P•HPSP) (HPSP<P)21.20 S114.0/125 S108.5/125 S104.5/12521.25 S117.0/125 S112.5/125 S107.5/12521.30 •120.0/125 S115.0/125 S110.5/125

LPSP, IPSP, and HPSP are the Low Power Set Point, Intermediate Power SetPoint, and High Power Set Point, respectively.

The trip level settings associated with this MCPR limit have been genericallycalculated and verified to bound the Rod Withdrawal Error Analysis for Cycle 22operation.

Technical Specification Reference: 3.3.2.1


2.2 Average Planar Linear Heat Generation Limits

The most limiting lattice APLHGR value (excluding natural uranium) for eachfuel bundle as a function of Planar Average Exposure, core power, and core flowis calculated by multiplying the value from Figures 1, 2, 3, 4, 5, and 6 by thesmaller of the MAPLHGR Flow Factor, MAPFACF (Figure 7) or the Power-Dependent MAPLHGR Factor, MAPFACp, (Figure 8). APLHGR valuesdetermined with the SAFER/GESTR-LOCA methodology are given inReferences 2, 3, and 5 while MAPFACF and MAPFACp were determined inReference 8.

The calculated maximum APLHGR (MAPLHGR) limits in Figures 1, 2, 3, 4, 5and 6 are conservative values bounding all fuel lattice types (excluding naturaluranium) in a given fuel bundle design. MAPLHGR limits for each individualfuel lattice design in a bundle design, as a function of axial location and averageplanar exposure, are determined based on the approved methodology referencedin Technical Specification 5.6.5 and loaded in the process computer for use incore monitoring calculations. The MAPLHGR values for these lattices, alongwith the axial location of each lattice in the bundle, are considered proprietaryinformation by General Electric and are given in Reference 3 as a function ofplanar average exposure.

The MAPLHGR limits referred to above are for two recirculation loop operations.For single loop operation, the limiting APLHGR value is multiplied by 0.77 forGE8x8 NB fuel (as can be found in Reference 5) and by 0.91 for GE14 fuel (ascan be found in Reference 5).

Technical Specification Reference: 3.2.1 and 3.4.1

2.3 Linear Heat Generation Rate Limit

The limiting power density and maximum allowable Linear Heat Generation Rate(LHGR) referred to in Technical Requirements Manual Section T 3.2.1 is thedesign LHGR. The design LHGR for fuel type GE 8x8 NB is 14.4 kW/ft asfound in Reference 12. The design LHGR for fuel type GE14 is 13.4 kW/ft asfound in Reference 13.

2.4 Minimum Critical Power Ratio Limits

The operating limit MCPR (OLMCPR) values are a function of core thermalpower, core flow, fuel bundle, scram time (), and fuel exposure. The scram time(T) is determined from CNS Procedure 10.9, Control Rod Scram Time Evaluation.The OLMCPR values are as follows:

For core thermal power 2 25 percent and <30 percent of rated power, theOLMCPR is the power dependent MCPR (MCPRp) from Figure 9.


For core thennal power 2 30 percent of rated power, the OLMCPR is the greaterof either:

The applicable flow dependent MCPR (MCPRF) determined from Figure 10, orthe appropriate scram time () dependent MCPR at rated power from Figures 11,and 12, multiplied by the applicable power dependent MCPR multiplier (Kp) fromFigure 9.

The appropriate scram time () dependent MCPR at rated power with OneTurbine Bypass Valve Unavailable is shown in Figure 13.

The system response time for the Turbine Bypass System to be at 80% of ratedbypass flow is 0.3 seconds.

For single recirculation loop operation, the OLMCPR is 0.02 greater than the tworecirculation loop operation OLMCPR.

Technical Specification References: 3.2.2, 3.4.1 and 3.7.7

2.5 Power/Flow Map

The power/flow map defining the Stability Exclusion Region can be found asFigure 14. References 5 and 6 reflect the documents describing the currentCooper Nuclear Station power/flow map. The Stability Exclusion Regionboundary is given by the equation

I WWB W-WB 2( P 2 WAWB WAWB J

where,

P = a core thermal power value on the region boundary (% of rated),W = the core flow rate corresponding to power, P, on the region boundary (% of rated),PA = core thermal power at point A (% of rated),PB = core thermal power at point B (% of rated),

WA = core flow rate at point A (% of rated), andWB = core flow rate at point B (% of rated).

Technical Specification Reference: 3.4.1

Cycle 22, Revision I-5 -

3.0 REFERENCES1. NEDE-2401 1-P-A-14-US, June 2000, General Electric StandardApplication for Reactor Fuel.

2. NEDC-32687P, Revision 1, March 1997, Cooper Nuclear Station SAFER/GESTR-LOCA Loss-of-CoolantAccident Analysis.

3. Lattice Dependent MAPLHGR Report for Cooper Nuclear Station Reload 21, Cycle 22,0000-0002-9865-MAPL, Revision 0.

4. Letter (with attachment), R.H. Buckholz (GE) to P.S. Check (NRC) dated September 5, 1980,Response to NRC Requestfor Information on ODYN Computer Model.

5. Supplemental Reload Licensing Report for Cooper Nuclear Station Reload 21, Cycle 22,0000-0002-9865-SRLR, Revision 0.

6. GE-NE-A13-00395-01, Class I, November, 1996, Application of the "Regional Exclusion withFlow-Biased APRMNeutron Flux Scram " Stability Solution (Option -D) to the Cooper NuclearStation, Licensing Topical Report.

7. Letter from James R. Hall (NRC) to G. R. Horn (NPPD) dated September 23, 1997, Approval ofSAFER/GESTAR LOCA Analysis for Cooper Nuclear Station (TAC NO. M98293)

8. GE-NE-L12-00867-12, Cooper Nuclear Station MIG Project Task 900: Transient Analysis, Revision 1,May 2000.

9. NEDC 98-024, Revision 3, May 2000, APRM- RBM Setpoint Calculation.

10. NEDO-31960-A and NEDO-31960-A Supplement 1, BWR Owner's Group Long-Term StabilitySolutions Licensing Methodology.(The approved revision at the time the reload analysis is performed.)

11. NEDE-23785-1-P-A, The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident, Volume III, Revision 1, October 1984.

12. Nuclear Design Reportfor Cooper Nuclear Station Reload, 18, J1 1-03354-03, July 1998.

13. GE-NE-L12-00867-09-02, Cooper Nuclear Station MIG Project Task 407: SAFERIGESTR-LOCAAnalysis, May 2000.

14. Letter from S. Shelton (GNF) to J.L. Lewis (NPPD) dated December 21, 2000, GE9B LHGR RelaxationforCooper Nuclear Station.

15. NEDE-31152P, GE Fuel Bundle Designs, December 1988 (As Revised)

16. NEDC-32538P-A, Determination of Limiting Cold Water Event

17. GE-NE-JI 103910-09-02P, Cooper Nuclear Station ECCS-LOCA Evaluation for Cycle 21, August 2001.

18. GE-NE-JI 103910-09-01, Cooper Nuclear Station ECCS-LOCA Evaluation for GE14, August 2001.19. NEDC-32687P, Cooper Nuclear Station SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis,

Revison 1, March 1997.

Cycle 22, Revision I-6-


Figure IMaximum Average Planar Linear Heat Generation Rate (MAPLHGR)versus Exposure with LPCI Modification and Bypass Holes Plugged,

Bundle 2610,3.93 wlo with 17GZ GE14C Fuel

10.00 20.00 30.00 40.00 50.00 60.00

Planar Average Exposure (GWdlST)

DATA COORDINATES (Reference 3)Planar Averaae Exposure

(GWDIST)0.000.201.002.003.004.005.006.007.008.009.0010.0011.0012.0013.0014.0015.0017.0020.0025.0030.0035.0040.0045.0050.0055.0057.0557.0857.4157.42

MAPLHGR(kW/ft)

9.349.439.589.7910.0010.2310.4510.6110.7410.8811.0111.1311.2311.3211.3911.4111.4211.2410.9210.399.869.378.878.357.825.864.844.834.884.87

Cycle 22, Revision 1-7-

15.00

i 12.00

y 9.00

0z 6.00-.1a-E 3.00

0.00

0.00 70.00

i


Figure 2

Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)versus Exposure with LPCI Modification and Bypass Holes Plugged,

Bundle 2568, 3.98 wJo with 16GZ GE14C Fuel

15.00 -_

1 12.00 -.

C 9.00 -w

0I 6.00--J

< 3.00-

0.000.00 10.00 20.00 30.00 40.00 50.00


DATA COORDINATES (Reference 3)Planar Averaoe Exoosure

(GWDIST)0.000.201.002.003.004.005.006.007.008.009.0010.0011.0012.0013.0014.0015.0017.0020.0025.0030.0035.0040.0045.0050.0055.0057.4757.4958.3158.32

Cycle 22, Revision I

MAPLHGR(kWtft)

9.639.649.719.8610.0310.2310.4510.6610.8711.0911.2011.2811.3611.4211.4211.4211.4211.3311.0010.439.899.398.908.387.856.074.834.834.894.88

- 8 -

60.00


Figure 3


Bundle 2472, 3.79 wlo with 17GZ GEI4C Fuel

10.00 20.00 30.00 40.00 50.00

Planar Average Exposure GWdIST)

DATA COORDINATES (Reference 3)Planar Averaae ExDosure

(GWDIST)0.000.201.002.003.004.005.006.007.008.009.0010.0011.0012.0013.0014.0015.0017.0020.0025.0030.0035.0040.0045.0050.0055.0056.2156.4856.8356.90

MAPLHGR(kW/ft)

9.259.329.459.629.809.9910.1810.3810.5210.6210.7410.8610.9611.0411.1011.1311.0410.8510.5610.109.679.258.818.317.755.524.914.934.834.83


15.00

1 12.00

- 9.00

z 6.00-Ja.< 3.00

0.000.00 60.00


Figure 4


Bundle 2380, 3.85 wlo with 14GZ GEI4B Fuel

10.00 20.00 30.00 40.00 50.00


DATA COORDINATES Reference 3)Planar Averaae Emoosure

(GWDIST)0.000.201.002.003.004.005.006.007.008.009.0010.0011.0012.0013.0014.0015.0017.0020.0025.0030.0035.0040.0045.0050.0055.0056.8656.9157.8757.93

MAEPLHG(kWlft)

9.029.119.269.499.719.9210.0510.1610.2410.3110.3810.4610.5410.6310.7410.8310.8010.6910.4610.059.649.198.698.147.516.856.596.596.636.65

Cycle 22, Revision I- 10-

15.00

I 12.00

C 9.00

( 6.00

0- 3.00

2 o.oo

0.00 60.00

I i


Figure 5


Bundle 2299, 3.50 wlo with 10GZ1 GE8X8NB Fuel

10.00 20.00 30.00 40.00 50.00

Planar Average Exposure (GWdJST)

DATA COORDINATES (Reference 3)Planar Average Eosure

(GWDIST)0.000.201.002.003.004.005.006.007.008.009.0010.0012.5015.0020.0025.0035.0045.0053.9254.00

MAPLHGR(kWlft)

11.5911.6311.7111.8411.9912.1412.2612.3912.5312.6612.8112.8512.7912.5111.7811.0810.539.515.745.75

Cycle 22, Revision I- 11 -

15.00

! 12.00

9.00

I 6.00

0- 3.00

E 0.000.00 60.00

i i

lw

I


Figure 6


Bundle 2205,3.50 wlo with 10GZ GE8X8NB Fuel

10.00 20.00 30.00 40.00 50.00

Planar Average Exposure GWdIST)

DATA COORDINATES (Reference 3)Planar Averaae ExDosure

(GWD/ST)0.000.201.002.003.004.005.006.007.008.009.0010.0012.5015.0020.0025.0035.0045.0054.0054.02

MAPLHGR(kWft)11.5911.6311.7111.8512.0012.1312.2612.3812.5212.6512.8012.8412.8112.5211.7811.0910.539.545.755.74


15.00

12.00

9.00

6.00

3.00

0.00

0-.1IL

i

Vw

0.00 60.00


Figure 7

Reference 8

Figure 3-11Cooper Nuclear Station

Flow-Dependent MAPLHGR Factor, MAPFAC(fl

102.5;% \ / /

117.) 2

MAPLHGR(f)= MAPFAC(Q * MAPUHGRstdMAPLHGRstd = Standard MAPLHGR Umits

. 7 v ~~~~~~~For Tv,o Loop Operation_MAPFAC(o - The Minimum of either

1.Oor( AFC(VWr1oo)+ BF1= % Rated Core Flow

AFand BFarefueldependentconstantsgiven _below for GE Fuels through GE14:

MadmumCore Flow

AF BF102.5 0.6784 0.48611107.0 0.6758 0.4574112.0 0.6807 0.4214

117.0 ~0.6885 0.3828

30 40 50 60 70 80 90 100 110

Core Flow (% Rated)


1.1

I

0.9

0.8

u-0.7CL07

0.6

0.5

0.4

0.3


Figure 8

Reference 8

Figure 3-9Cooper Nuclear Station

Power-Dependent MAPLHGR Factor lAPFAC(p)

0 10 20 30 40 50 60

POWER (% Rated)

Cycle 22, Revision I

70 80

- 14-

1.00

0.90

0.80

0.70

0.60

C,

L 0.50

0.40

0.30

0.20

MAPLHGR(p)= MAPFAC(p) I MAPLHGRstdMAPLHGRstd = Standard MAPLHGR LrTts

For P<25%: No Therrrmal Limits LUbnitoring REquired.l ~~~~~N irmit specified.

For 25% P < 30%MAPFAC(p)=0.53 + 0.005(P-30%)for Flow < 50%MAPFAC(p)=0.49 + 0.005(P-30%)for Flow > 50%

!g50% Flow For 30% < PMAPFAC(p) = 1.0 + 0.005224(P-100%)

_ >50% _ow

90 100


Figure 9

Reference 5

Cooper Nuclear StationPower-Dependent MCPR Limits, Kp and MCPRp

low > 5001

Flow <= 50%

Operating Limit MCPR (P) = Kp Operating Limit MCPR (100)

For Pc 25%: No Thermal Umits Monitoring RequiredNo limits specfied

For 25% c P < P(Bypass): (P(Bypass) = 30%)

K(P) = [ K(Byp) + 0.0500(30% - P)j l OLMCPR(1 00)K(Byp) = 2.24 for Flow' 50%

K(P) = [ K(Byp) + 0.0519(30% - P)l I OLMCPR(100)K(Byp) = 2.66 for Flow > 50%

For 30% c P < 45%: K(P) - 1.28 + 0.0134 (45% - P)

For45% S P < 60%: K(P)= 1.15 + 0.00867 (60% - P)

For 60% < P: K(P) = 1.0 + 0.00375 (100% - P)

p - p - p - p - p �

20 30 40 50 60 70

Power (% rated)

Cycle 22, Revision 1- 15 -

80 90 100

4.0

3.5

3.0

2.5

2.0

1.5

1.0

200

110


Figure 10

Reference 5

Cooper Nuclear StationFlow-Dependent MCPR Limits, MCPR(f)

I I I I _ _ ' _ _ ___

:orrectiod

N\

For W(C) (% Rated Core Flow) . 40%

MCPR(F) = MAX(1.22, A(F) * W(C) I 100 + B(F))

MaxFlow-117.0 A(F)=-0.644 B(F)=1.843

Max Flow = 112.0 A(F) - -0.613 B(F) = 1.780

Max Flow - 107.0 A(F) - -0.597 B(F) - 1.729

Max Flow. 102.5 A(F). -0.582 B(F) - 1.686

------ GE14 e 40% Flow

For W(C) (% Rated Core Flow) < 40% For GEXL05 only

MCPR(F) * (A(F) W(C) I 100 + B(F)) (1 + 0.0032 * (40 - W(C)))

I - - - - -

9040 50 60 70 80

Core Flow (% Rated)

100 110 120


112,

107.0%

102.5%

All Otl

GEXL05I

I.

er GEXL

K

1.8

1.7

1.6

1.5

c.a.IL

1.4

1.3

1.2

1.120 30

I I' \ &1 � I �I I I q

N ,

I


Figure II

Minimum Critical Power Ratio (MCPR) versus Tau(based on tested measured scram time as defined in

Reference 4), All Fuel

1.47 -

1.46 -

1.45 1.44 1.43 -

E 1.42 -

m 1.41-1.4 _

1.39 _1.38 _1.37 _1.36 e

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0

Tau

Exposure Range: BOC22 to EOC22-2315 MWd/MT (2100 MWd/ST) ICF



Figure 12



1.591.581.571.561.551.541.53

E 1.52a. 1.51

' 1.5E 1.49

1.481.471.461.451.441.431.42

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0

Tau

Exposure Range: EOC22-2315 MWd/MT (2100 MWd/ST) to EOC22 ICF

Cycle 22, Revision 1-18-


Figure 13



1.591.581.571.561.551.541.53

M 1.52a. 1.510 1.5E 1.49

1.481.471.461.451.441.431.42

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0

Tau

Exposure Range: BOC22 to EOC22 ICF_1TBPOOS



Fi= 14

Exclusion Region EndpointsAB

Power (% rated)77.136.8

Flow (% rated)49.732.5


Cycle 22 Stability Exclusion Region

110.000

100.000

90.000

80.000Point A

} 70.000

60.000

50.000

40.000Point B

30.000

20.000 20 30 40 50 60 70 80

Core Flow (%)

Nebraska Public Power DistrictI WWB W-WB 2 ( P 2 WAWB WAWB J where, P = a core thermal power value...

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