NLS2003042, Core Operating Limits Report for Cooper Nuclear Station

Core Operating Limits Report for Cooper Nuclear Station

ML031050424
Person / Time
Site:	Cooper
Issue date:	04/04/2003
From:	Coyle M Nebraska Public Power District (NPPD)
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NLS2003042
Download: ML031050424 (23)

Text

I Nebraska Public Power District Always there when you need us NLS2003042 April 4, 2003 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Core Operating Limits Report Cooper Nuclear Station NRC Docket No. 50-298, DPR-46 The purpose of this letter is to provide the Nuclear Regulatory Commission (NRC) the Core Operating Limits Report (COLR) for Cooper Nuclear Station (CNS) for Cycle 22. CNS Technical Specification 5.6.5 requires that core operating limits be documented in the COLR and provided to the NRC upon issuance for each reload cycle for changes to the following cycle specific parameters:

I. The Average Planar Linear Heat Generation Rate (APLHGR)

2. The Minimum Critical Power Ratio (MCPR)

3. The Rod Block Monitor Upscale Allowable Values

4. The power/flow map defining the Stability Exclusion Region For Cycle 22 operations, changes have been made to the operating limits for APLHGR, MCPR, and the power/flow map defining the Stability Exclusion Region. Consequently, the COLR has been updated and it is being submitted as an enclosure. In accordance with 10 CFR 50.4 (b) (1),

we are also transmitting a copy of this COLR to the Regional Office and to the NRC Senior Resident Inspector.

COOPER NUCLEAR STATION P 0 Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811/ Fax: (402) 825-5211 www nppd com

NLS2003042 Page 2 of 2 Should you have any questions regarding this matter, please contact Paul Fleming at (402) 825-2774.

Sincerely, Site Vice President

/cb Enclosure cc: Regional Administrator w/enclosure USNRC Region IV Senior Project Manager w/enclosure USNRC - NRR Project Directorate IV-I Senior Resident Inspector w/enclosure USNRC NPG Distribution w/o enclosure Records w/enclosure

COOPER NUCLEAR STATION CORE OPERATING LIMITS REPORT Cycle 22 Revision 0 Cycle 22, Revision 0

-I-

Signature Page Revision 0 Preparer: Stephen W. Luther Print Sign/Date / / /

Reviewer: Paul L. Ballinger Print Sign/DLL RE Manager: Jerry L. Lewis Print Wign!lke Cycle 22, Revision 0

1.0 INTRODUCTION

The Core Operating Limits Report provides the limits for operation of the Cooper Nuclear Station for Cycle 22. It includes the limits for the Rod Block Monitor Upscale Set Point, Average Planar Linear Heat Generation Rate (APLHGR), and Minimum Critical 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 Technical Specifications.

The core operating limit values have been determined using the NRC-approved methodologies given in References 1, 2, 10, and 11 and have been established such that all 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. The applicable 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 Rod Block Monitor (RBM) upscale (power referenced) trip level setting, found in Reference 9, are as follows:

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

(LPSP*P*IPSP) (IPSP<P*HPSP) (HPSP<P) 21.20 <114.0/125 <108.5/125 <104.5/125

Ž1.25 *117.0/125 *112.5/125 *107.5/125 21.30 *120.0/125 *115.0/125 *110.5/125 LPSP, IPSP, and HPSP are the Low Power Set Point, Intermediate Power Set Point, and High Power Set Point, respectively.

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

Technical Specification

Reference:

3.3.2.1 Cycle 22, Revision 0 2.2 Average Planar Linear Heat Generation Limits The most limiting lattice APLHGR value (excluding natural uranium) for each fuel bundle as a function of Planar Average Exposure, core power, and core flow is calculated by multiplying the value from Figures 1, 2, 3, 4, 5, and 6 by the smaller of the MAPLHGR Flow Factor, MAPFACF (Figure 7) or the Power-Dependent MAPLHGR Factor, MAPFACp, (Figure 8). APLHGR values determined with the SAFER/GESTR-LOCA methodology are given in References 2, 3, and 5 while MAPFACF and MAPFACp were determined in Reference 8.

The calculated maximum APLHGR (MAPLHGR) limits in Figures 1, 2, 3, 4, 5 and 6 are conservative values bounding all fuel lattice types (excluding natural uranium) in a given fuel bundle design. MAPLHGR limits for each individual fuel lattice design in a bundle design, as a function of axial location and average planar exposure, are determined based on the approved methodology referenced in Technical Specification 5.6.5 and loaded in the process computer for use in core monitoring calculations. The MAPLHGR values for these lattices, along with the axial location of each lattice in the bundle, are considered proprietary information by General Electric and are given in Reference 3 as a function of planar 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 for GE8x8 NB fuel (as can be found in Reference 5) and by 0.91 for GE14 fuel (as can 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 the design LHGR. The design LHGR for fuel type GE 8x8 NB is 14.4 kW/ft as found in Reference 12. The design LHGR for fuel type GE14 is 13.4 kW/ft as found in Reference 13.

2.4 Minimum Critical Power Ratio Limits The operating limit MCPR (OLMCPR) values are a function of core thermal power, core flow, fuel bundle, scram time (r), 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 > 25 percent and <30 percent of rated power, the OLMCPR is the power dependent MCPR (MCPRp) from Figure 9.

Cycle 22, Revision 0 For core thermal power 2 30 percent of rated power, the OLMCPR is the greater of either:

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

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

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

For single recirculation loop operation, the OLMCPR is 0.02 greater than the two recirculation 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 as Figure 18. References 5 and 6 reflect the documents describing the current Cooper Nuclear Station power/flow map. The Stability Exclusion Region boundary is given by the equation I 2W-)VW ( W-JWB 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), and WB = core flow rate at point B (% of rated).

Technical Specification

Reference:

3.4.1 Cycle 22, Revision 0

3.0 REFERENCES

1. NEDE-2401 I-P-A-14-US, June 2000, GeneralElectric StandardApplicationforReactor Fuel.

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

3. Lattice Dependent MAPLHGR Reportfor CooperNuclear 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 Request for Information on ODYN Computer Model.

5. Supplemental ReloadLicensing Reportfor Cooper Nuclear Station Reload 21, Cycle 22, 0000-0002-9865-SRLR, Revision 0.

6. GE-NE-A 13-00395-01, Class 1, November, 1996, Application of the "Regional Exclusion with Flow-BiasedAPRMNeutronFlux Scram" Stability Solution (Option l-D) to the CooperNuclear Station, Licensing Topical Report.

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

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

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

10. NEDO-3 1960-A and NEDO-3 1960-A Supplement 1, BWYR Owner's Group Long-Term Stability Solutions 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 ], October 1984.

12. Nuclear Design Reportfor Cooper Nuclear Station Reload, 18, J 11-03354-03, July 1998.

13. GE-NE-L 12-00867-09-02, Cooper Nuclear Station MIG Project Task 407: SAFER/GESTR-LOCA Analysis, May 2000.

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

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

16. NEDC-32538P-A, DeterminationofLimiting Cold Water Event

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

18. GE-NE-J1 103910-09-01, CooperNuclear Station ECCS-LOCA Evaluationfor GEI4, August 2001.

19. NEDC-32687P, Cooper Nuclear Station SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis, Revison 1, March 1997.

Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure I Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, Bundle 2610, 3.93 w/o with 17GZ GE14C Fuel 15 00 1 12.00 - - -

9.00 i,

= 600

-j a-

< 300 0.00 0.00 10.00 20 00 30.00 40 00 50.00 60.00 70.00 Planar Average Exposure (GWdIST)

DATA COORDINATES (Reference 3)

PlanarAverage Exposure MAPLHGR (GWD/ST) (kW/ft) 000 934 020 9.43 1 00 9.58 200 9.79 3 00 1000 400 10.23 500 1045 600 10 61 700 1074 800 1088 900 11 01 1000 1113 11 00 11.23 1200 1132 1300 1139 1400 11.41 1500 1142 17 00 11.24 20 00 1092 25 00 1039 3000 9.86 3500 9.37 4000 8 87 4500 8 35 5000 7.82 55 00 5.86 57 05 484 57.08 483 57.41 488 57.42 4 87 Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 2 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, Bundle 2568, 3.98 wlo with 16GZ GE14C Fuel 15.00 g 12.00 I 4

- 9.00 _

= 6 00 .I

-j 0E 4 3 00 000 _-

0.00 10.00 20.00 30 00 40.00 50.00 60 00 Planar Average Exposure (GWd/ST)

DATA COORDINATES (Reference 3)

Planar Average Exposure MAPLHGR (GWDIST) (kW/fR) 000 9.63 020 9.64 1.00 9.71 2.00 986 3.00 1003 4 00 1023 5.00 1045 600 10 66 7.00 1087 8.00 I1 09 9.00 11.20 10.00 1128 11.00 1136 1200 1142 1300 11.42 1400 11 42 1500 11 42 1700 11 33 2000 I1 00 2500 1043 30 00 989 35.00 939 40.00 890 45.00 838 5000 7 85 55 00 607 57 47 4 83 57.49 4 83 5831 4 89 58.32 4 88 Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 3 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, Bundle 2472, 3.79 w/o with 17GZ GEi4C Fuel 15.00

` 12.00 9S

• 9.00

= 6.00

-E a-

<' 3.00 0.00 _-

0 00 10.00 20.00 30 00 40 00 50.00 60.00 Planar Average Exposure (GWd/ST)

DATA COORDINATES Reference 3)

Planar Average Exmosure MAPLHGR (GWD/ST) (kW/ft) 000 925 020 932 1 00 9.45 2.00 962 3.00 980 4 00 999 5.00 10 18 600 10 38 7.00 1052 8 00 1062 9 00 1074 10 00 1086 11 00 1096 1200 11 04 1300 1110 1400 1113 1500 11 04 1700 1085 2000 1056 2500 1010 30.00 967 3500 925 4000 8 81 45 00 831 5000 775 5500 5 52 5621 4 91 56.48 493 56 83 4.83 56.90 483 Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 4 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, Bundle 2380, 3.85 wlo with 14GZ GE14B Fuel 15.00 -_

12.00 -_

9.00 4 -

0 . pp 6.00 -

-j

a. 3.00 0.00 - Ii 0.00 10.00 20.00 30.00 40.00 50.00 60.00 Planar Average Exposure (GWd/ST)

DATA COORDINATES (Reference 3)

Planar Average Exposure MAPLHGR (GWD/ST) (kW/ft) 000 902 020 911 1 00 926 2 00 949 300 971 4 00 992 500 10.05 600 10.16 700 1024 800 10.31 900 10 38 1000 1046 11 00 1054 1200 1063 1300 1074 1400 10 83 1500 1080 17.00 1069 20 00 1046 25 00 1005 3000 964 35.00 919 40.00 869 45.00 814 50.00 751 5500 685 56 86 6 59 56.91 659 57.87 663 57.93 6 65 Cycle 22, Revision 0

-.10-

CORE OPERATING LIMITS REPORT Figure 5 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, Bundle 2299, 3.50 w/o with I0GZ1 GE8X8NB Fuel

_ 15.00 8 12.00 a

9.00 I 6.00

0. 3.00 E 0.00 . . .I 0.00 10.00 20.00 30.00 40.00 50.00 60.00 Planar Average Exposure (GWd/ST)

DATA COORDINATES (Reference 3)

Planar Average Exposure MAPLHGR (GWD/ST) (kW/ft) 000 1159 020 11 63 1.00 1171 2 00 11 84 300 1199 4.00 12 14 5 00 1226 600 12 39 700 1253 800 1266 900 12.81 1000 1285 1250 1279 1500 12 51 2000 11 78 25 00 11 08 3500 1053 4500 951 5392 5 74 5400 5 75 Cycle 22, Revision 0

-I -

CORE OPERATING LIMITS REPORT Figure 6 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Exposure with LPCI Modification and Bypass Holes Plugged, Bundle 2205, 3.50 wlo with IOGZ GE8X8NB Fuel 4 C Afn

-I U.UU -

12.00 A, * ^*- + +

I 6.00 -

-j 0M 3.00 0.00 I I 0.c1o 10.00 20.00 30.00 40.00 50.00 60.00 Planar Average Exposure (GWdIST)

DATA COORDINATES (Reference 3)

Planar Average Exosure MAPLHGR (GWDIST) (kW/ft) 0 00 11.59 0.20 11.63 1 00 11.71 200 11.85 3 00 12.00 4 00 12.13 5 00 12.26 600 12.38 700 12.52 8 00 12.65 9 00 12.80 1000 12.84 1250 12.81 1500 12.52 2000 11.78 2500 11.09 3500 10.53 4500 954 5400 5 75 5402 5 74 Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 7 Reference 8 Figure 3-11 Cooper Nuclear Station ndent MAPLHGR Factor, l' 1.1 1

0.9 08 ML U-

a. 0.7 m

06 05 04 03 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 8 Reference 8 Figure 3-9 Cooper Nuclear Station Power-Dependent MAPLHGR Factor MAPFAC(p) 1.00 0.90 0 80 tp)= MAPFACp) MALHGRstd 0.70 MPLHGRstd = Standard MAFPLHGR Lints For P<25%- No Thermal Lints rAonitoring Required

. No fimts s pecif ied 0.60 a- For 25% < P < 30%

0~ MAPFAC(p)=0 53 + 0.005(RL30%)for Flow < 50%

MAPFAC(p)=0 49 + 0.005(P-30%)for Flow > 50%

LL 0.50 <50% Fo For 30% < P MAPFAC(p) = 1 0 + 0.005224(P-100%)

0 40 0 30 020 0 10 20 30 40 50 60 70 80 90 100 POWER (% Rated)

Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 9 Reference 5 Cooper Nuclear Station Power-Dependent MCPR Limits, Kp and MCPRp 4.0 Operating Limit MCPR (P) = Kp ' Operating Limit MCPR (100)

For P< 25%- No Thermal Limits Monitoring Required 3.5 II No limits specified I

I For 25% < P < P(Bypass) (P(Bypass) = 30%)

I I

I K(P) = [K(Byp) + 0 0500(30% - P)] / OLMCPR(100)

I I K(Byp) = 2.24 for Flow < 50%

a I

I K(P) = [ K(Byp) + 0 0519(30% - P)] I OLMCPR(100) 3.0 I I K(Byp) = 2 66 for Flow > 50%

I low > 500/c For 30% < P < 45%: K(P) = 1 28 + 0 0134 (45% - P)

For 45% <P <60% K(P)= 1.15+000867(60% - P)

I For 60% <P. K(P) = 1 0 + 0 00375 (100% - P)

L 2.5 I

I a

I I

- I - - I - I I 200 I Flow <= 50%

I I

I I

2.0 II I

I I

I I

I I

I I

1.5 I I

II 1.0 20 30 40 50 60 70 80 90 100 110 Power (% rated)

Cycle 22, Revision 0

- 15-

CORE OPERATING LIMITS REPORT Figure 10 Reference 5 Cooper Nuclear Station Flow-Dependent MCPR Limits, MCPR(Q) 1.8 I I I I 'I '

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

MCPR(F) = MAX(1.22, A(F) - W(C) /100 + B(F))

GEXL05 'orrectiorj Max Flow = 117 0 A(F) = -0 644 B(F) = 1 843 1.7 -

Max Flow =1120 A(F) = -0613 B(F) 1.780 117.0%

112.0% \ Max Flow = 107.0 A(F) = -0 597 B(F) = 1.729 107.0%1R Max Flow = 102 5 A(F) = -0 582 B(F) = 1 686 16 ----- = GE14 < 40% Flow 102.5% For W(C) (% Rated Core Flow) < 40% For GEXL05 only MCPR(F) = (A(F)' W(C) /100 + B(F))' (1 + 0 0032 ' (40 - W(C)))

1.5 w K I s._

i '1z S1 a-U All OtU er GEXL

'N\ \

1.4 F 4. _ __I 1

I_ _ _ 1 _ _ 4_ _ _

13 N

I

\K\11 12 I I I I- 4 - +

1.1 I I . . i 20 30 40 50 60 70 80 90 100 110 120 Core Flow (% Rated)

Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure I I 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 -_

t 1.42 --

0 1.41 -_

1.4 -_

1.39 -

1.38 1.37 -

1.36 -

0.0 0.1 0.2 0.3 0.4 0.5 06 0.7 0.8 0.9 1.0 Tau Exposure Range BOC22 to EOC22-2315 MWd/MT (2100 MWd/ST) ICF Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 12 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured scram time as defined in Reference 4), All Fuel 1.59 -

1.58 -

1.57 -

1.56 -

1.55 _

1.54 --

1.53 -

1.52 -

a- 1.51 -

C. 1.5 -

1.49 -

1.48 -

1.47 -

1.46-1.45 -

1.44 _

1.43 -

1.42 -

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 08 0.9 1.0 Tau Exposure Range: EOC22-2315 MWd/MT (2100 MWd/ST) to EOC22 ICF Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 13 Minimum Critical Power Ratio (MCPR) versus Tau (based on tested measured scram time as defined in Reference 4), All Fuel 1.59 1.58 1.57 1.56 1.55 1.54 1.53 a 1.52 IL 1.51

. 1.5 5 1.49 1.48 1.47 1.46 1.45 1.44 1.43 1.42 00 0.1 0.2 0.3 0.4 0.5 06 0.7 0.8 0.9 1.0 Tau Exposure Range BOC22 to EOC22 ICF_1TBPOOS Cycle 22, Revision 0 CORE OPERATING LIMITS REPORT Figure 14 Cycle 22 Stability Exclusion Region 110 000 100 000 X

90 000 80 000 Point A 70 000 -

60.000 -

50 000 -

40000 -

Point B 30 000 -

20 000 -

0 3 40 50 60 70 80 Core Flow (%)

Exclusion Region Endpoints Power (% rated) Flow (% rated)

A 77.1 49.7 B 36.8 32.5 Cycle 22, Revision 0 I ATTACHMENT 3 LIST OF REGULATORY COMMITMENTS Correspondence Number: NLS2003042 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 intended or planned actions by NPPD. They are described for information only and are not regulatory commitments. Please notify the NL&S Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.

COMMITTED DATE COMMITMENT OR OUTAGE None 4-4-

4-1-

4-4-

PROCEDURE 0.42 l REVISION 12 l PAGE 14 OF 16