GNRO-2002/00088, Core Operating Limits Report Revision Cycle 13 - Ldc 02104

Core Operating Limits Report Revision Cycle 13 - Ldc 02104

ML022810412
Person / Time
Site:	Grand Gulf
Issue date:	10/07/2002
From:	Bottemiller C Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2002/00088
Download: ML022810412 (33)

Text

ntergy Operations, Inc.

Waterloo Road PO.Box 756 Port Gibsor , PAS 3SlI50

.I& SO1 43.7 6299 Charles A. B o ~ e ~ ~ l l e r

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'Isin' 1icensing October 7, 2002 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention

Document Control Desk

Subject:

Core Operating Limits Report Revision Cycle 13 - LDC 02104 Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 GNRO-2002/00088 Ladies and Gentlemen:

Entergy Operations, Inc. is submitting a Revision of the Core Operating Limits Report (COLR) for Grand Gulf Nuclear Station (GGNS) (reference: Licensing Document Change LDC 02104) as required by GGNS Technical Specification 5.6.5. for Cycle 13. The analytical methods used to determine the Cycle 13 Core Operating Limits were previously approved by the NRC and are listed in GGNS Technical Specification 5.6.5. This letter does not contain any commitments. If you have any questions or require additional information, please contact Mike Larson (601) 437-6685.

Yours trulv.

Charles A. Bottemiller Manager, Plant Licensing MJL attachment: GGNS Core Operating Limits Report cc: see next page

October 7,2002 GNRO-2002/00088 Page 2 of 2 Hoeg T. L. (GGNS Senior Resident) (w/a)

Levanway D. E. (Wise Carter) (w/a)

Reynolds N. S. (w/a)

Smith L. J. (Wise Carter) (w/a)

Thomas H. L. (w/o)

U S . Nuclear Regulatory Commission ALL LETTERS ATTN: Mr. E. W. Merschoff (w/2) 61 1 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U.S. Nuclear Regulatory Commission ALL LETTERS - COURIER ATTN: Mr. David H. Jaffe, NRR/DLPM (w/2) DELIVERY (FEDEX, ETC.)

ATTN: ADDRESSEE ONLY ADDRESS ONLY - ****DO NOT ATTN: Courier Delivery Only USE FOR U.S. POSTAL SERVICE Mail Stop OWFN/iD-I ADDRESS*****

11555 Rockville Pike Rockville, MD 20852-2378

Grand Gulf Nuclear Station Core Operating Limits Report COLR Page 1 LDC 02001

CORE OPERATING LIMITS REPORT REASON FOR REVISION This Revision provides the GGNS core operating limits for Cycle 13. These limits are based on a core power of 3833 MWt.

TABLE OF CONTENTS 1.0 PURPOSE 3 2.0 SCOPE 3

3.0 REFERENCES

4-6 3.1 Background References 4 3.2 Current Cycle References 4 3.3 Methodology References 5-6 4.0 DEFINITIONS 7 5.0 GENERAL REQUIREMENTS 8-9 5.1 Average Planar Linear Heat Generation Rates 8 5.2 Minimum Critical Power Ratio 8 5.3 Linear Heat Generation Rate 8 5.4 Stability 8 5.5 Applicability 8-9 Figure(s) 1 APLHGR Operating Limits 10-13 Figure(s) 2 MCPR Operating Limits 14-20 Figure(s) 3 LHGR Operating Limits 21-26 Figure(s) 4 E1A Stability Limits 27-31 COLR Page 2 LDC 02104

CORE OPERATING LIMITS REPORT 1.0 PURPOSE On October 4, 1988, the NRC issued Generic Letter 88-16 [3.1.1] encouraging licensees to remove cycle-specific parameter limits from Technical Specifications and to place these limits in a formal report to be prepared by the licensee. As long as the parameter limits were developed with NRC-approved methodologies, the letter indicated that this would remove unnecessary burdens on licensee and NRC resources.

On October 29, 1992, Entergy Operations submitted a Proposed Amendment to the Grand Gulf Operating License requesting changes to the GGNS Technical Specifications to remove certain reactor physics parameter limits that change each fuel cycle [3.1.2].

This amendment committed to placing these operating limits in a separate Core Operating Limits Report (COLR) which is defined in Technical Specifications. This PCOL was approved by the NRC by SER dated January 21, 1993 [3.1.3].

The COLR is controlled as a License Basis Document and revised accordingly for each fuel cycle or remaining portion of a fuel cycle. This COLR reports the Cycle 13 core operating and stability limits.

2.0 SCOPE As defined in Technical Specification 1.1, the COLR is the GGNS document that provides the core operating limits for the current fuel cycle. This document is prepared in accordance with Technical Specification 5.6.5 for each reload cycle using NRC-approved analytical methods.

The Cycle 13 core operating and stability limits included in this report are:

• the Average Planar Linear Heat Generation Rate (APLHGR),

• the Minimum Critical Power Ratio (MCPR) (including EOC-RPT inoperable),

• the Linear Heat Generation Rate (LHGR) limit, and

• the E1A stability limits.

COLR Page 3 LDC 02104

CORE OPERATING LIMITS REPORT

3.0 REFERENCES

This section contains the background, cycle-specific, and methodology references used in the safety analysis of Grand Gulf Cycle 13.

3.1 Background References 3.1.1 MAEC-88/0313, Generic Letter 88-16, Removal of Cycle-Specific Parameter Limits from Technical Specifications, October 4, 1988.

3.1.2 GNRO-92-00093, Proposed Amendment to Grand Gulf Operating License, PCOL-92/07, dated October 29, 1992.

3.1.3 GNRI-93-0008, Amendment 106 to Grand Gulf Operating License, January 21, 1993.

3.2 Current Cycle References 3.2.1 GEXI 2002-00065, K.V. Walters to J.B. Lee, EMF-2759 Revision 0, Grand Gulf Nuclear Station Cycle 13 Reload Analysis, dated June 28, 2002.

3.2.2 GEXI 2000-00043, R.E. Kingston to J.B. Lee, Transmittal of GGNS LHGR/MAPLHGR Relaxation Results, dated October 23, 2000.

3.2.3 GEXI 2002-00061, K.V. Walters to J.B. Lee, EMF-2760(P) Revision 0, Grand Gulf Nuclear Station Cycle 13 Plant Transient Analysis, dated June 18, 2002.

3.2.4 GEXI 97-00035, R.E. Kingston to J.B. Lee, Utilization of Power and Flow Dependent MAPLHGR and LHGR Limits, dated June 27, 1997.

3.2.5 NEDC-32910P, Grand Gulf Nuclear Station SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis With Relaxed ECCS Parameters, dated September 1999.

3.2.6 CEO 2000-00094, Jim Head to M.D. Withrow, Revised E1A Related COLR Input, dated April 20, 2000.

3.2.7 GEXI 2002-00100, K.V. Walters to J.B. Lee, Grand Gulf Cycle 13 Operating Limits Based on a Rated Reactor Power of 3833 MWt, dated September 6, 2002.

3.2.8 GEXI 2000-00116, K.V. Walters to J.B. Lee, Technical Specification and COLR References for Grand Gulf Nuclear Station and River Bend Station, November 3, 2000.

COLR Page 4 LDC 02104

CORE OPERATING LIMITS REPORT 3.3 Methodology References 3.3.1 XN-NF-81-58(P)(A) Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.

3.3.2 XN-NF-85-67(P)(A) Revision 1, Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel, Exxon Nuclear Company, September 1986.

3.3.3 EMF-85-74(P) Revision 0 Supplement 1 (P)(A) and Supplement 2 (P)(A),

RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, Siemens Power Corporation, February 1998.

3.3.4 ANF-89-98(P)(A) Revision 1 and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, Advanced Nuclear Fuels Corporation, May 1995.

3.3.5 EMF-93-177(P)(A) and Supplement 1, Mechanical Design for BWR Fuel Channels, Siemens Power Corporation, August 1995.

3.3.6 XN-NF-80-19(P)(A) Volume 1 and Supplements 1 and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis, Exxon Nuclear Company, March 1983.

3.3.7 XN-NF-80-19(P)(A) Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads, Exxon Nuclear Company, June 1986.

3.3.8 EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-MICROBURN-B2, Siemens Power Corporation, October 1999.

3.3.9 XN-NF-80-19(P)(A) Volume 3 Revision 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, Exxon Nuclear Company, January 1987.

3.3.10 XN-NF-84-105(P)(A), Volume 1 and Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal Hydraulic Core Analysis, Exxon Nuclear Company, February 1987.

3.3.11 ANF-524(P)(A) Revision 2 and Supplements 1 and 2, ANF Critical Power Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.

3.3.12 ANF-913 (P)(A), Volume 1, Revision 1 and Volume 1 Supplements 2, 3 and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, Advanced Nuclear Fuels Corporation, August 1990.

3.3.13 XN-NF-825(P)(A) Supplement 2, BWR/6 Generic Rod Withdrawal Error Analysis, MCPRp for Plant Operation Within the Extended Operating Domain, Exxon Nuclear Company, October 1986.

3.3.14 ANF-1358(P)(A) Revision 1, The Loss of Feedwater Heating Transient in Boiling Water Reactors, Advanced Nuclear Fuels Corporation, September 1992.

3.3.15 EMF-1997(P)(A) Revision 0, ANFB-10 Critical Power Correlation, Siemens Power Corporation, July 1998.

COLR Page 5 LDC 02001

CORE OPERATING LIMITS REPORT 3.3 Methodology References (continued) 3.3.16 EMF-1997(P), Supplement 1(P)(A), Revision 0, ANFB-10 Critical Power Correlation: High Local Peaking Results, Siemens Power Corporation, July 1998.

3.3.17 EMF-2209(P)(A) Revision 1 and errata sheet, SPCB Critical Power Correlation, Siemens Power Corporation, July 2000.

3.3.18 EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporations Critical Power Correlations to Co-Resident Fuel, Siemens Power Corporation, August 2000.

3.3.19 XN-NF-80-19(P)(A), Volumes 2, 2A, 2B, and 2C, Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model, Exxon Nuclear Company, September 1982.

3.3.20 ANF-91-048(P)(A), Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR Evaluation Model, Advanced Nuclear Fuel Corporation, January 1993.

3.3.21 ANF-91-048(P)(A), Supplements 1 and 2, BWR Jet Pump Model Revision for RELAX, Siemens Power Corporation, October 1997.

3.3.22 XN-CC-33(A) Revision 1, HUXY: A Generalized Multirod Heatup Code with 10 CFR 50 Appendix K Heatup Option Users Manual, Exxon Nuclear Company, November 1975.

3.3.23 EMF-2292(P)(A) Revision 0, ATRIUM-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.

3.3.24 EMF-CC-074(P)(A) Volume 4 Revision 0, BWR Stability Analysis-Assessment of STAIF with Input from MICROBURN-B2, Siemens Power Corporation, August 2000.

3.3.25 NEDE-24011-P-A, General Electric Standard Application for Reactor Fuel (GESTAR-II)

COLR Page 6 LDC 02104

CORE OPERATING LIMITS REPORT 4.0 DEFINITIONS 4.1 Average Planar Linear Heat Generation Rate (APLHGR) - the APLHGR shall be applicable to a specific planar height and is equal to the sum of the linear heat generation rates for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle.

4.2 Average Planar Exposure - the Average Planar Exposure shall be applicable to a specific planar height and is equal to the sum of the exposure of all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle.

4.3 Critical Power Ratio (CPR) - the ratio of that power in the assembly, which is calculated by application of the fuel vendors appropriate boiling correlation, to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

4.4 Core Operating Limits Report (COLR) - The Grand Gulf Nuclear Station specific document that provides core operating limits for the current reload cycle in accordance with Technical Specification 5.6.5.

4.5 Linear Heat Generation Rate (LHGR) - the LHGR shall be the heat generation per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.

4.6 Minimum Critical Power Ratio (MCPR) - the MCPR shall be the smallest CPR which exists in the core.

4.7 MCPR Safety Limit - the minimum value of the CPR at which the fuel could be operated with the expected number of rods in boiling transition not exceeding 0.1% of the fuel rods in the core.

4.8 Aligned Drive Flow - Adjusted FCTR card input drive flow signal that accounts for actual variations in the core flow to drive flow relationship.

4.9 Monitored Region - The area of the core power and flow operating domain where the reactor may be susceptible to reactor instabilities under conditions exceeding the licensing basis of the current reactor system.

4.10 Restricted Region - The area of the core power and flow operating domain where the reactor is susceptible to reactor instabilities in the absence of restrictions on core void distributions.

4.11 Setpoint Setup - A FCTR card feature that sets the normal non-setup E1A APRM flow-biased scram and control rod block trip reference setpoints associated with the Exclusion and Restricted Regions higher to permit required reactor maneuvering in the Restricted Region when stability controls are in effect.

4.12 Middle of Cycle (MOC) - The Cycle 13 MOC Core Average Exposure (CAE) is 31,424 MWd/MTU [3.2.1].

4.13 End of Cycle (EOC) - The Cycle 13 EOC CAE is 33,184 MWd/MTU [3.2.1].

4.14 Extended End of Cycle (EEOC) - The Cycle 13 EEOC CAE is 34,023 MWd/MTU

[3.2.1].

COLR Page 7 LDC 02104

CORE OPERATING LIMITS REPORT 5.0 GENERAL REQUIREMENTS 5.1 Average Planar Linear Heat Generation Rates Consistent with Technical Specification 3.2.1, all APLHGRs for ATRIUM10 bundles shall not exceed the limits reported in Figure 1-1 as a function of exposure

[3.2.1, 3.2.7]. All APLHGRs for GE11 lattices shall not exceed the MAPLHGR limits reported in Reference 3.2.2 as a function of exposure multiplied by the smaller of either the power-dependent or flow-dependent MAPLHGR factors reported in Figures 1-3 and 1-4 [3.2.1, 3.2.7]. For each GE11 bundle type, Figures 1-2a and 1-2b report the MAPLHGR for the most limiting enriched lattice at each exposure for reference purposes.

5.2 Minimum Critical Power Ratio Consistent with Technical Specification 3.2.2, the MCPR shall be equal to or greater than the limits reported in Figure(s) 2 as functions of power, flow, and exposure

[3.2.1, 3.2.7].

Additional MCPR operating limits are provided to support operation with EOC-RPT inoperable as described in Technical Specification 3.3.4.1.

5.3 Linear Heat Generation Rate Consistent with Technical Specification 3.2.3, the LHGR for ATRIUM10 bundles shall not exceed the limits reported in Figure 3-1 as a function of exposure multiplied by the smaller of either the power-dependent or flow-dependent LHGR factors reported in Figures 3-3 and 3-5 [3.2.1, 3.2.7]. All LHGRs for GE11 lattices shall not exceed the LHGR limits reported in References 3.2.2 as a function of exposure multiplied by the smaller of either the power-dependent or flow-dependent LHGR factors reported in Figures 3-4 and 3-6 [3.2.1, 3.2.7, 3.2.4]. For each GE11 bundle type, Figures 3-2a and 3-2b reports the LHGR for the most limiting enriched lattice at each exposure for reference purposes.

5.4 Stability The stability regions and allowable values specified in Technical Specifications are reported in Figure(s) 4 [3.2.6].

5.5 Applicability The following core operating limits are applicable for operation in the Maximum Extended Operating Domain (MEOD), with Feedwater Heaters Out of Service (FHOOS), and EOC-RPT inoperable. For operation with EOC-RPT inoperable, the alternate MCPR limits described in Section 5.2 above must be implemented. Since the maximum licensed GGNS feedwater temperature reduction is 50 °F at rated power operation, an alternate set of stability limits is not required. For single-loop operation (SLO),

the following additional requirements must be satisfied.

1. A SLO MAPLHGR multiplier of 0.87 is required for ATRIUM10 fuel [3.2.1, 3.2.7]. There is no MAPLHGR multiplier required for GE11 fuel since the flow-dependent MAPLHGR and LHGR factors reported in Figures 1-4 and 3-6 at the maximum SLO core flow are less than the SLO multipliers applied in the LOCA analysis [3.2.1, 3.2.7, 3.2.5].

COLR Page 8 LDC 02104

CORE OPERATING LIMITS REPORT

2. The MCPR shall be equal to or greater than the limits determined in accordance with Section 5.2 above increased by 0.02 to account for the difference between the two-loop and single-loop MCPR safety limits for the allowable range of single-loop operation [3.2.1, 3.2.7].

COLR Page 9 LDC 02104

CORE OPERATING LIMITS REPORT 14 13 15.0, 12.5 12 MAPLHGR (kW/ft) 0.0, 12.5 11 10 9

64.0, 7.6 8

7 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 Average Planar Exposure (GWd/MTU)

Figure 1-1 Maximum Average Planar Linear Heat Generation Rate for ATRIUM-10 Note: Actual limits described in Section 5.1 COLR Page 10 LDC 02104

CORE OPERATING LIMITS REPORT 13 12 11 MAPLHGR (kW/ft) 10 9

8 7

6 5

0 10 20 30 40 50 60 Average Planar Exposure (GWd/MTU)

Figure 1-2a Maximum Average Planar Linear Heat Generation Rate for Limiting Enriched Lattice of GE Bundle Type GE11-P9SUB386-13GZ-120T-146-T Note: Actual limits described in Section 5.1 13 12 11 MAPLHGR (kW/ft) 10 9

8 7

6 5

0 10 20 30 40 50 60 Average Planar Exposure (GWd/MTU)

Figure 1-2b Maximum Average Planar Linear Heat Generation Rate for Limiting Enriched Lattice of GE Bundle Type GE11-P9SUB387-15GZ-120T-146-T Note: Actual limits described in Section 5.1 COLR Page 11 LDC 02104

CORE OPERATING LIMITS REPORT Table 1-1 MAPLHGRs for Limiting Enriched Lattices of GE11 Bundles GE Bundle Type GE Bundle Type Exposure GE11-P9SUB386- GE11-P9SUB387-(GWd/MTU) 13GZ-120T-146-T 15GZ-120T-146-T 0.00 10.86 10.71 0.22 10.93 10.77 1.10 11.03 10.85 2.20 11.16 10.96 3.31 11.29 11.07 4.41 11.42 11.18 5.51 11.53 11.30 6.61 11.63 11.42 7.72 11.73 11.54 8.82 11.83 11.66 9.92 11.93 11.79 11.02 12.03 11.91 13.78 12.10 12.02 14.66 12.10 12.03 16.53 12.10 12.05 19.29 12.01 11.93 22.05 11.87 11.74 26.79 11.62 11.39 27.56 11.57 11.34 33.07 11.14 10.94 36.05 10.81 10.58 38.58 10.53 10.28 44.09 9.86 9.57 49.60 9.18 8.86 55.12 8.52 8.16 60.63 6.81 6.69 62.14 6.18 62.48 6.18 Note: Actual limits described in Section 5.1 COLR Page 12 LDC 02104

CORE OPERATING LIMITS REPORT 1.10 71.2, 1.0 101.7, 1.0 1.00 0.90 < 50% Flow MAPFAC(p) 0.80 40.7, 0.68 0.70 25, 0.61 40.7, 0.66 0.60 0.50 25, 0.55 40.7, 0.55 0.40 > 50% Flow 0.30 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)

Figure 1-3 Cycle 13 Power-Dependent MAPLHGR Factor for GE11 BOC-EEOC Note: These factors are to be applied to the limits described in Section 5.1 1.05 70, 0.997 80, 1.00 105, 1.00 60, 0.939 0.95 70, 0.987 MAPFAC(f) 50, 0.890 40, 0.856 0.85 0.75 20, 0.704 30, 0.704 0.65 0 10 20 30 40 50 60 70 80 90 100 110 Core Flow (% rated)

Figure 1-4 Cycle 13 Flow-Dependent MAPLHGR Factor for GE11 Note: These factors are to be applied to the limits described in Section 5.1 COLR Page 13 LDC 02104

CORE OPERATING LIMITS REPORT 2.1 25, 2.02 > 50% Core Flow 2.0 1.9 25, 1.98 40.7, 1.88 1.8 40.7, 1.75 1.7 < 50% Core Flow MCPR (p) 1.6 40.7, 1.58 1.5 71.2, 1.42 1.4 1.3 71.2, 1.28 1.2 1.1 101.7, 1.19 1.0 0 10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)

Figure 2-1a Cycle 13 Power-Dependent MCPR Limit for ATRIUM-10 BOC to MOC 2.0

> 50% Core Flow 25, 1.93 1.9 40.7, 1.82 1.8 25, 1.80 1.7 1.6 40.7, 1.60 MCPR (p)

< 50% Core Flow 1.5 71.2, 1.42 40.7, 1.54 1.4 1.3 1.2 71.2, 1.26 101.7, 1.19 1.1 1.0 0 10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)

Figure 2-1b Cycle 13 Power-Dependent MCPR Limit for GE11 BOC to MOC COLR Page 14 LDC 02104

CORE OPERATING LIMITS REPORT 2.1 > 50% Core Flow 25, 2.02 2.0 25, 1.98 1.9 40.7, 1.88 1.8 40.7, 1.75 1.7 < 50% Core Flow MCPR (p) 1.6 40.7, 1.58 1.5 71.2, 1.42 1.4 1.3 1.2 71.2, 1.28 101.7, 1.19 1.1 1.0 0 10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)

Figure 2-2a Cycle 13 Power-Dependent MCPR Limit for ATRIUM-10 BOC to MOC with and EOC-RPT Inoperable 2.0 25, 1.93 > 50% Core Flow 1.9 40.7, 1.82 1.8 25, 1.80 1.7 1.6 40.7, 1.60 MCPR (p)

< 50% Core Flow 1.5 40.7, 1.54 71.2, 1.42 1.4 1.3 1.2 71.2, 1.27 101.7, 1.20 1.1 1.0 0 10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)

Figure 2-2b Cycle 13 Power-Dependent MCPR Limit for GE11 BOC to MOC with EOC-RPT Inoperable COLR Page 15 LDC 02104

CORE OPERATING LIMITS REPORT 2.1 > 50% Core Flow 25, 2.02 2.0 25, 1.98 1.9 40.7, 1.88 1.8 40.7, 1.75 1.7

< 50% Core Flow MCPR (p) 1.6 40.7, 1.58 1.5 71.2, 1.42 1.4 1.3 71.2, 1.31 1.2 101.7, 1.22 1.1 1.0 0 10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)

Figure 2-3a Cycle 13 Power-Dependent MCPR Limit for ATRIUM-10 MOC to EOC 2.0 > 50% Core Flow 25, 1.93 1.9 40.7, 1.82 1.8 25, 1.80 1.7 1.6 < 50% Core Flow 40.7, 1.60 MCPR (p) 1.5 40.7, 1.54 71.2, 1.42 1.4 1.3 71.2, 1.33 1.2 101.7, 1.24 1.1 1.0 0 10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)

Figure 2-3b Cycle 13 Power-Dependent MCPR Limit for GE11 MOC to EOC COLR Page 16 LDC 02104

CORE OPERATING LIMITS REPORT 2.1 25, 2.02

> 50% Core Flow 2.0 25, 1.98 1.9 40.7, 1.88 1.8 40.7, 1.75 1.7 < 50% Core Flow MCPR (p) 1.6 1.5 40.7, 1.58 71.2, 1.42 1.4 1.3 71.2, 1.32 1.2 101.7, 1.26 1.1 1.0 0 10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)

Figure 2-4a Cycle 13 Power-Dependent MCPR Limit for ATRIUM-10 MOC to EOC with EOC-RPT Inoperable 2.0 > 50% Core Flow 25, 1.93 1.9 40.7, 1.82 1.8 25, 1.80 1.7 1.6 40.7, 1.60 MCPR (p)

< 50% Core Flow 1.5 40.7, 1.54 71.2, 1.42 1.4 1.3 71.2, 1.33 101.7, 1.29 1.2 1.1 1.0 0 10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)

Figure 2-4b Cycle 13 Power-Dependent MCPR Limit for GE11 MOC to EOC with EOC-RPT Inoperable COLR Page 17 LDC 02104

CORE OPERATING LIMITS REPORT 2.1 25, 2.02 > 50% Core Flow 2.0 25, 1.98 1.9 40.7, 1.88 1.8 40.7, 1.75 1.7 < 50% Core Flow MCPR (p) 1.6 40.7, 1.58 1.5 71.2, 1.42 1.4 1.3 71.2, 1.34 1.2 101.7, 1.23 1.1 1.0 0 10 20 30 40 50 60 70 80 90 100 Core Power (%Rated)

Figure 2-5a Cycle 13 Power-Dependent MCPR Limit for ATRIUM-10 EOC to EEOC 2.0 > 50% Core Flow 25, 1.93 1.9 40.7, 1.82 1.8 25, 1.80 1.7 1.6 40.7, 1.60 MCPR (p)

< 50% Core Flow 1.5 40.7, 1.54 71.2, 1.42 1.4 1.3 71.2, 1.33 1.2 101.7, 1.26 1.1 1.0 0 10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)

Figure 2-5b Cycle 13 Power-Dependent MCPR Limit for GE11 EOC to EEOC COLR Page 18 LDC 02104

CORE OPERATING LIMITS REPORT 2.1 25, 2.02 > 50% Core Flow 2.0 25, 1.98 1.9 40.7, 1.88 1.8 40.7, 1.75 1.7 < 50% Core Flow MCPR (p) 1.6 40.7, 1.58 1.5 71.2, 1.42 1.4 1.3 71.2, 1.34 1.2 101.7, 1.27 1.1 1.0 0 10 20 30 40 50 60 70 80 90 100 Core Power (%Rated)

Figure 2-6a Cycle 13 Power-Dependent MCPR Limit for ATRIUM-10 EOC to EEOC with EOC-RPT Inoperable 2.0 > 50% Core Flow 25, 1.93 1.9 25, 1.80 40.7, 1.82 1.8 1.7 1.6 < 50% Core Flow MCPR (p) 40.7, 1.60 1.5 40.7, 1.54 71.2, 1.42 1.4 1.3 71.2, 1.34 101.7, 1.30 1.2 1.1 1.0 0 10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)

Figure 2-6b Cycle 13 Power-Dependent MCPR Limit for GE11 EOC to EEOC with EOC-RPT Inoperable COLR Page 19 LDC 02104

CORE OPERATING LIMITS REPORT 1.7 1.6 20, 1.59 1.5 MCPR (f) 30, 1.39 1.4 1.3 105, 1.21 1.2 75, 1.21 1.1 0 10 20 30 40 50 60 70 80 90 100 110 Core Flow (% rated)

Figure 2-7a Cycle 13 Flow-Dependent MCPR Limit for ATRIUM-10 1.7 20, 1.63 1.6 1.5 30, 1.46 MCPR (f) 1.4 1.3 105, 1.23 1.2 76, 1.23 1.1 0 10 20 30 40 50 60 70 80 90 100 110 Core Flow (% rated)

Figure 2-7b Cycle 13 Flow-Dependent MCPR Limit for GE11 COLR Page 20 LDC 02104

CORE OPERATING LIMITS REPORT 14 0, 13.4 15, 13.4 13 12 LHGR (kW/ft) 11 10 9

8 64, 7.3 7

6 0 10 20 30 40 50 60 70 Average Planar Exposure (GWd/MTU)

Figure 3-1 Maximum Linear Heat Generation Rate for ATRIUM-10 Note: Actual limits described in Section 5.3 COLR Page 21 LDC 02104

CORE OPERATING LIMITS REPORT 15 11.62, 14.4 14 0.0, 14.4 13 30.43, 12.7 12 LHGR (kW/ft) 11 10 9 55.21, 9.0 8

7 62.49, 6.4 6

0 10 20 30 40 50 60 Average Planar Exposure (GWd/MTU)

Figure 3-2a Maximum Linear Heat Generation Rate for Limiting Enriched Lattice of GE Bundle Type GE11-P9SUB386-13GZ-120T-146-T Note: Actual limits described in Section 5.3 15 11.35, 14.4 14 0.0, 14.4 30.14, 12.7 13 12 LHGR (kW/ft) 11 10 9 54.87, 9.0 8

7 62.15, 6.4 6

0 10 20 30 40 50 60 Average Planar Exposure (GWd/MTU)

Figure 3-2b Maximum Linear Heat Generation Rate for Limiting Enriched Lattice of GE Bundle Type GE11-P9SUB387-15GZ-120T-146-T Note: Actual limits described in Section 5.3 COLR Page 22 LDC 02104

CORE OPERATING LIMITS REPORT 1.10 71.2, 1.00 101.7, 1.00 1.00 71.2, 0.97 0.90 LHGRFAC(p) 0.80 40.7, 0.81 0.70 25, 0.73 0.60 0.50 0.40 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)

Figure 3-3 Cycle 13 Power-Dependent LHGR Factor for ATRIUM-10 BOC-EEOC Note: These factors to be applied to the limits as described in Section 5.3 COLR Page 23 LDC 02104

CORE OPERATING LIMITS REPORT 1.10 71.2, 1.00 101.7, 1.00 1.00 0.90 LHGRFAC(p) 0.80 < 50% Flow 40.7, 0.68 0.70 40.7, 0.66 25, 0.61 0.60 25, 0.55 40.7, 0.55 0.50

> 50% Flow 0.40 0 10 20 30 40 50 60 70 80 90 100 Power (% Rated)

Figure 3-4 Cycle 13 Power-Dependent LHGR Factor for GE11 BOC-EEOC Note: These factors to be applied to the limits described in Section 5.3 COLR Page 24 LDC 02104

CORE OPERATING LIMITS REPORT 1.05 70, 1.00 105, 1.00 0.95 LHGRFAC(f) 0.85 20, 0.78 30, 0.78 0.75 0.65 0 10 20 30 40 50 60 70 80 90 100 110 Core Flow (% rated)

Figure 3-5 Cycle 13 Flow-Dependent LHGR Factor for ATRIUM-10 Note: These factors to be applied to the limits described in Section 5.3 COLR Page 25 LDC 02104

CORE OPERATING LIMITS REPORT 1.05 70, 0.997 80, 1.00 105, 1.00 70, 0.987 0.95 LHGRFAC(f) 50, 0.890 60, 0.939 0.85 40, 0.856 0.75 20, 0.704 30, 0.704 0.65 0 10 20 30 40 50 60 70 80 90 100 Core Flow (% rated)

Figure 3-6 Cycle 13 Flow-Dependent LHGR Factor for GE11 Note: These factors to be applied to the limits described in Section 5.3 COLR Page 26 LDC 02104

CORE OPERATING LIMITS REPORT 120 110 100 90 80 MONITORED REGION 70

% RTP 60 50 40 30 20 10 0

0 10 20 30 40 50 60 70 80 90 100 110 120 TOTAL CORE FLOW (%)

Figure 4-1 Monitored Region Boundary COLR Page 27 LDC 02001

CORE OPERATING LIMITS REPORT 120 110 100 90 RESTRICTED 80 REGION 70

% RTP 60 50 40 30 20 10 0

0 10 20 30 40 50 60 70 80 90 100 110 120 ALIGNED DRIVE FLOW (%)

Figure 4-2 Restricted Region Boundary for Two-Loop Operation COLR Page 28 LDC 02001

CORE OPERATING LIMITS REPORT 120 110 100 90 80 RESTRICTED 70 REGION

% RTP 60 50 40 30 20 10 0

0 10 20 30 40 50 60 70 80 90 100 110 120 ALIGNED DRIVE FLOW (%)

Figure 4-3 Restricted Region Boundary for Single-Loop Operation COLR Page 29 LDC 02001

CORE OPERATING LIMITS REPORT 120 110 100 90 80 70

% RTP 60 50 40 30 Non-Setup (Trip Setpoint)

Non-Setup (Allowable Value) 20 Setup (Trip Setpoint)

Setup (Allowable Value) 10 0

0 10 20 30 40 50 60 70 80 90 100 110 120 ALIGNED DRIVE FLOW (%)

Figure 4-4 APRM Flow-Biased Simulated Thermal Power - High Scram Allowable Values for Two-Loop Operation COLR Page 30 LDC 02001

CORE OPERATING LIMITS REPORT 120 110 100 90 80 70

% RTP 60 50 40 30 Non-Setup (Trip Setpoint)

Non-Setup (Allowable Value) 20 Setup (Trip Setpoint)

Setup (Allowable Value) 10 0

0 10 20 30 40 50 60 70 80 90 100 110 120 ALIGNED DRIVE FLOW (%)

Figure 4-5 APRM Flow-Biased Simulated Thermal Power - High Scram Allowable Values for Single-Loop Operation COLR Page 31 LDC 02001