GNRO-2011/00005, Core Operating Limits Report Cycle 18 Mid-Cycle Revision

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Core Operating Limits Report Cycle 18 Mid-Cycle Revision
ML110400123
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 02/08/2011
From: Perino C L
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2011/00005
Download: ML110400123 (29)
v • d • e


Text

..

GNRO-2011/00005 February 8, 2011 U.S.NuclearRegulatoryCommission Washington, D.C.20555 Entergy Operations, Inc.7003 Bald Hill Road PO.Box 756 Port Gibson.MS 39150 Tel 601 437 6299 Christina L.Perino Manager Licensing Attention:

Subject:

Document Control Desk Core Operating Limits Report Cycle 18 Mid-cycle Revision Grand Gulf Nuclear Station, Unit 1 Docket No.50-416 License No.NPF-29

Dear Sir or Madam:

Entergy Operations, Inc.is submitting revised pages to the Core Operating Limits Report (COLR)for Grand Gulf Nuclear Station (GGNS)(reference:

Licensing Basis Document Change Request LBDCR 10041)as required by GGNS Technical Specification 5.6.5.d for a Cycle 18 mid-cycle revision.The analytical methods used to determine the Cycle 18 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 Dennis Coulterat(601)437-6595.Sincerely, CLP/DMC

Attachment:

Grand Gulf Nuclear Station Core Operating Limits Report cc: see next page GNRO-2011/00005 Page 2 of 2 cc: NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S.Nuclear Regulatory Commission ATTN: Mr.Elmo E.Collins, Jr.(w/2)Region Administrator, Region IV 612 East Lamar Blvd, Suite 400 Arlinqton, TX 76011-4125 U.S.Nuclear Regulatory Commission ATTN: Mr.Alan Wang, NRR/ADRO/DORL (w/2)Mail Stop OWFN/8 B1 Washington, DC 20555-0001 COLR Page 1 LDC 02001

G G G r r r a a a n n n d d d G G G u u u l l l f f f N N N u u u c c c l l l e e e a a a r r r S S S t t t a a a t t t i i i o o o n n n C C C o o o r r r e e e O O O p p p e e e r r r a a a t t t i i i n n n g g g L L L i i i m m m i i i t t t s s s R R R e e e p p p o o o r r r t t t CORE OPERATING LIMITS REPORT COLR Page 2 LBDCR 09037 REASON FOR REVISION This revision provides the Cycle 18 core operating limits. These limits are based on a core power of 3898 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 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 Figure(s) 1 APLHGR Operating Limits 9-10 Figure(s) 2 MCPR Operating Limits 11-19 Figure(s) 3 LHGR Operating Limits 20-22 Figure(s) 4 E1A Stability Limits 23-27

CORE OPERATING LIMITS REPORT COLR Page 3 LBDCR 09037

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. Any revisions to the COLR must be

submitted to the NRC for information as required by Tech Spec 5.6.5 and tracked by

LCTS 29132. This COLR reports the Cycle 18 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 18 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.

CORE OPERATING LIMITS REPORT COLR Page 4 LBDCR 10041

3.0 REFERENCES

This section contains the background, cycle-specific, and methodology references

used in the safety analysis of Grand Gulf Cycle 18.

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. 3.1.4 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.

3.2 Current

Cycle References

3.2.1 ECH-NE-10-00022 Revision 2, Supplemental Reload Licensing Report for Grand Gulf Nuclear Station Reload 17 Cycle 18 , dated December 2010.

3.2.2 ECH-NE-10-00021 Revision 2, GNF2 Fuel Design Cycle-Independent Analyses for Entergy Grand Gulf Nuclear Station , dated November 2010. 3.2.3 ECH-NE-10-00023 Revision 0, Fuel Bundle Information Report for Grand Gulf Nuclear Station Reload 17 Cycle 18 , dated February 2010. 3.2.4 NEDC-32910P, Revision 1, Grand Gulf Nuclear Station SAFER/GESTR-LOCA Accident Analysis With Relaxed ECCS Parameters , dated October 1999. 3.2.5 GGNS-SA-08-00005 Revision 0, Grand Gulf Nuclear Station ATRIUM-10 ECCS-LOCA Evaluation , dated July 2008. 3.2.6 GGNS-SA-08-00006 Revision 0, Grand Gulf Nuclear Station GE14 ECCS-LOCA Evaluation , dated July 2008. 3.2.7 GGNS-SA-09-00002 Revision 1, Grand Gulf Nuclear Station GNF2 ECCS-LOCA Evaluation , dated December 2009. 3.2.8 ECH-NE-10-00026 Revision 0, GGNS Cycle 18 GESTAR Assessment , dated March 2010. 3.2.9 RA-ENO-JB1-10-057, Grand Gulf Cycle 18 Bundle GEP359/GEP559 Replacement , dated April 20, 2010. 3.2.10 ECH-NE-10-00042 Revision 0, GESTAR & Fuel Reliability Evaluations of GNF2 Spacer Issue , dated May 2010. 3.2.11 ECH-NE-10-00041 Revision 0, Entergy GNF2 Fuel Transition: Disposition of Bent Flow Wing Effects on NFI-Revision 1 , dated May 2010. 3.2.12 CEO 2000-00094, Jim Head to M.D. Withrow, "Revised E1A Related COLR Input," dated April 20, 2000.

CORE OPERATING LIMITS REPORT COLR Page 5 LDC 10041

3.3 Methodology

References

The Technical Specifications (TS) supported by each methodology reference are

provided in brackets

({ }). 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

{TS 3.2.1, TS 3.2.2, TS 3.2.3

}. 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

{TS 3.2.3}. 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

{TS 3.2.3}. 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 {TS 3.2.3}. 3.3.5 Deleted 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

{TS 3.2.1, TS 3.2.2, TS 3.2.3}. 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

{TS 3.2.1, TS 3.2.2, TS 3.2.3}. 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

{TS 3.2.2, TS 3.2.3

} . 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

{TS 3.2.2}. 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

{TS 3.2.2}. 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

{TS 3.2.2}. 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

{TS 3.2.2}. 3.3.13 XN-NF-825(P)(A) Supplement 2, "BWR/6 Generic Rod Withdrawal Error Analysis, MCPR p for Plant Operation Within the Extended Operating Domain," Exxon Nuclear Company, October 1986

{TS 3.2.2}. 3.3.14 ANF-1358(P)(A) Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005

{TS 3.2.2}.

CORE OPERATING LIMITS REPORT COLR Page 6 LDC 10041

3.3 Methodology

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

{TS 3.2.2}. 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 {TS 3.2.2}. 3.3.17 EMF-2209(P)(A) Revision 2, "SPCB Critical Power Correlation, Siemens Power Corporation," September 2003

{TS 3.2.2}. 3.3.18 EMF-2245(P)(A) Revision 0, "Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel," Siemens Power

Corporation, August 2000

{TS 3.2.2}. 3.3.19 EMF-2361 (P)(A) Revision 0, "EXEM BWR-2000 ECCS Evaluation Model,"

Framatome ANP Richland, Inc., May 2001

{TS 3.2.1}. 3.3.20 Deleted

3.3.21 Deleted 3.3.22 NEDC-33383P, Revision 1, "GEXL97 Correlation Applicable to ATRIUM-10 Fuel," June, 2008

{TS 3.2.2}. 3.3.23 EMF-2292(P)(A) Revision 0, "ATRIUM-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation," September 2000

{TS 3.2.1}. 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 {TS 3.2.4}. 3.3.25* NEDE-24011-P-A, General Electric Standard Application for Reactor Fuel (GESTAR-II)

{TS 3.2.1, TS 3.2.2, TS 3.2.3

}.

  • Note: These references are applicable when GE fuel is in the reactor.

CORE OPERATING LIMITS REPORT COLR Page 7 LBDCR 09037

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 vendor's 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 18 MOC Core Average Exposure (CAE) is 27,224 MWd/ST

[3.2.1]. 4.13 End of Cycle (EOC)

- The Cycle 18 EOC CAE is 30,075 MWd/ST

[3.2.1].

CORE OPERATING LIMITS REPORT COLR Page 8 LBDCR 10041

5.0 GENERAL

REQUIREMENTS

5.1 Average

Planar Linear Heat Generation Rates Consistent with Technical Specification 3.2.1, all APLHGRs shall not exceed the

exposure-dependent limits reported in Figures 1-1, 1-2 and 1-3 [3.2.1].

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 [3.2.1,3.2.2,3.2.11].

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 LHGRs for any GNF2 or GE14 rod

at any axial location shall not exceed the nodal exposure-dependent limits reported

in Reference 3.2.3 multiplied by the smaller of either the power-dependent or flow-

dependent LHGR factors reported in Figure s 3-2 and 3-3, respectively

[3.2.2,3.2.11].

The LHGR for ATRIUM-10 bundles shall not exceed the exposure-dependent limits

reported in Figure 3

-1 multiplied by the smaller of either the power-dependent or flow-dependent LHGR factors reported in Figure s 3-2 and 3-3, respectively

[3.2.2,3.2.11].

5.4 Stability

The stability regions and allowable values specified in Technical Specifications

are reported in Figure(s) 4 [3.2.12].

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. THE APLHGRs shall not exceed the exposure-dependent limits determined in accordance with Section 5.1 reduced by a 0.83 SLO multiplier. [3.2.1].
2. THE LHGRs shall not exceed the smaller of the exposure-dependent limits determined in accordance with Section 5.3 above or the exposure-dependent

limits reduced by a 0.83 SLO multiplier [3.2.1].

3. The MCPR shall be equal to or greater than the limits determined in accordance with Section 5.2 above increased by 0.03 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].

CORE OPERATING LIMITS REPORT COLR Page 9 LBDCR 09037 63.50, 6.6960.78, 7.5017.52, 13.780.00, 13.78 4 5 6 7 8 9 10 11 12 13 14010203040506070Average Planar Exposure (GWd/ST)MAPLHGR (kW/ft)Figure 1-1Maximum Average Planar Linear Heat generation Rate for GNF2Note: Actual Limits described in Sections 5.1 and 5.5 63.50, 5.0057.61, 8.019.14, 12.820.00, 12.82 4 5 6 7 8 9 10 11 12 13 14010203040506070Average Planar Exposure (GWd/ST)MAPLHGR (kW/ft)Figure 1-2Maximum Average Planar Linear Heat generation Rate for GE14Note: Actual Limits described in Sections 5.1 and 5.5

CORE OPERATING LIMITS REPORT COLR Page 10 LBDCR 09037

63.87, 7.321.66, 12.810.00, 12.81 4 5 6 7 8 9 10 11 12 13 14010203040506070Average Planar Exposure (GWd/MTU)MAPLHGR (kW/ft)Figure 1-3Maximum Average Planar Linear Heat generation Rate for ATRIUM-10Note: Actual Limits described in Sections 5.1 and 5.5

CORE OPERATING LIMITS REPORT COLR Page 11 LBDCR 10041 40, 2.0025, 2.1525, 2.0340, 1.5770, 1.46100, 1.3390, 1.3550, 1.5340, 1.821.01.11.21.3 1.41.51.6 1.71.81.9 2.02.12.20102030405060708090100Core Power (% Rated)MCPR(p)Figure 2-1aCycle 18 Power-Dependent MCPR Limits for GNF2BOC to MOC> 50% Core Flow

< 50% Core Flow 40, 2.0025, 2.1525, 2.0350, 1.5390, 1.31100, 1.2870, 1.4540, 1.5740, 1.821.01.11.21.3 1.41.51.61.7 1.8 1.92.02.12.20102030405060708090100Core Power (% Rated)MCPR(p)Figure 2-1bCycle 18 Power-Dependent MCPR Limits for GE14BOC to MOC > 50% Core Flow

< 50% Core Flow

CORE OPERATING LIMITS REPORT COLR Page 12 LBDCR 10041

40, 2.0025, 2.1525, 2.0350, 1.5390, 1.31100, 1.2970, 1.4540, 1.5740, 1.821.01.11.21.3 1.41.51.61.7 1.8 1.92.02.12.20102030405060708090100Core Power (% Rated)MCPR(p)Figure 2-1cCycle 18 Power-Dependent MCPR Limits for ATRIUM-10BOC to MOC > 50% Core Flow

< 50% Core Flow CORE OPERATING LIMITS REPORT COLR Page 13 LBDCR 10041 40, 2.0025, 2.1525, 2.0340, 1.5770, 1.46100, 1.3590, 1.3850, 1.5340, 1.821.01.1 1.21.31.41.5 1.61.71.81.92.02.12.20102030405060708090100Core Power (% Rated)MCPR(p)Figure 2-2aCycle 18 Power-Dependent MCPR Limits for GNF2BOC to MOC with EOC-RPT Inoperable> 50% Core Flow

< 50% Core Flow 40, 2.0025, 2.1525, 2.0350, 1.5390, 1.36100, 1.3370, 1.4540, 1.5740, 1.821.01.11.21.3 1.41.51.61.7 1.8 1.92.02.12.20102030405060708090100Core Power (% Rated)MCPR(p)Figure 2-2bCycle 18 Power-Dependent MCPR Limits for GE14BOC to MOC with EOC-RPT Inoperable> 50% Core Flow

< 50% Core Flow

CORE OPERATING LIMITS REPORT COLR Page 14 LBDCR 10041

40, 2.0025, 2.1525, 2.0350, 1.5390, 1.36100, 1.3370, 1.4540, 1.5740, 1.821.01.11.21.3 1.41.51.61.7 1.8 1.92.02.12.20102030405060708090100Core Power (% Rated)MCPR(p)Figure 2-2cCycle 18 Power-Dependent MCPR Limits for ATRIUM-10BOC to MOC with EOC-RPT Inoperable> 50% Core Flow

< 50% Core Flow

CORE OPERATING LIMITS REPORT COLR Page 15 LBDCR 10041 40, 1.8840, 1.8840, 2.02100, 1.3890, 1.4170, 1.5350, 1.5740, 1.5725, 2.1725, 2.081.01.11.21.3 1.41.51.61.7 1.8 1.92.02.12.20102030405060708090100Core Power (% Rated)MCPR(p)Figure 2-3aCycle 18 Power-Dependent MCPR Limits for GNF2MOC to EOC> 50% Core Flow

< 50% Core Flow 40, 1.8840, 1.8840, 2.02100, 1.3490, 1.3570, 1.4550, 1.5340, 1.5725, 2.1725, 2.081.01.11.21.31.41.51.61.71.81.92.02.12.20102030405060708090100Core Power (% Rated)MCPR(p)Figure 2-3bCycle 18 Power-Dependent MCPR Limits for GE14MOC to EOC> 50% Core Flow

< 50% Core Flow

CORE OPERATING LIMITS REPORT COLR Page 16 LBDCR 10041

40, 1.8840, 1.8840, 2.02100, 1.3490, 1.3570, 1.4550, 1.5340, 1.5725, 2.1725, 2.081.01.11.21.31.41.51.61.71.81.92.02.12.20102030405060708090100Core Power (% Rated)MCPR(p)Figure 2-3cCycle 18 Power-Dependent MCPR Limits for ATRIUM-10MOC to EOC> 50% Core Flow

< 50% Core Flow

CORE OPERATING LIMITS REPORT COLR Page 17 LBDCR 10041 40, 1.8840, 1.8840, 2.02100, 1.4190, 1.4570, 1.5350, 1.5740, 1.6025, 2.1725, 2.081.01.11.21.31.41.51.61.71.81.92.02.12.20102030405060708090100Core Power (% Rated)MCPR(p)Figure 2-4aCycle 18 Power-Dependent MCPR Limits for GNF2MOC to EOC with EOC-RPT Inoperable> 50% Core Flow

< 50% Core Flow 40, 1.8840, 1.8840, 2.02100, 1.3890, 1.4170, 1.4650, 1.5340, 1.5725, 2.1725, 2.081.01.11.21.31.41.51.61.71.81.92.02.12.20102030405060708090100Core Power (% Rated)MCPR(p)Figure 2-4bCycle 18 Power-Dependent MCPR Limits for GE14MOC to EOC with EOC-RPT Inoperable> 50% Core Flow

< 50% Core Flow

CORE OPERATING LIMITS REPORT COLR Page 18 LBDCR 10041

40, 1.8840, 1.8840, 2.0225, 2.0825, 2.1740, 1.5750, 1.5370, 1.4790, 1.41100, 1.381.01.11.21.31.41.51.61.71.81.92.02.12.20102030405060708090100Core Power (% Rated)MCPR(p)Figure 2-4cCycle 18 Power-Dependent MCPR Limits for ATRIUM-10MOC to EOC with EOC-RPT Inoperable> 50% Core Flow

< 50% Core Flow

CORE OPERATING LIMITS REPORT COLR Page 19 LBDCR 09037

30, 1.3120, 1.31105, 1.2090, 1.201.151.201.251.301.350102030405060708090100110Core Flow (% Rated)MCPR(f)Figure 2-5Cycle 18 Flow-Dependent MCPR Limits for GNF2, GE14 and ATRIUM-10

CORE OPERATING LIMITS REPORT COLR Page 20 LBDCR 09037

63.87, 7.3017.15, 13.400.0, 13.4 6 7 8 9 10 11 12 13 14010203040506070Pellet Exposure (GWd/ST)LHGR (kW/ft)Figure 3-1Maximum Linear Heat Generation Rate for ATRIUM-10Note: Actual limits described in Sections 5.3 and 5.5

CORE OPERATING LIMITS REPORT COLR Page 21 LBDCR 09037 0.72325, 0.690100, 1.0040, 0.87725, 0.78040, 0.87740, 1.00 0.65 0.70 0.75 0.80 0.85 0.90 0.95 1.00 1.050102030405060708090100110Power (% Rated)LHGRFAC(p)> 50% Core Flow

< 50% Core FlowFigure 3-2aCycle 18 Power-Dependent LHGR Factor BOC-MOC for GNF2, GE14, and ATRIUM-10Note: These factor to be applied to the exposure-dependent limits as descibed in Section 5.3 0.70725, 0.684100, 1.0040, 0.86425, 0.78240, 0.86440, 1.00 0.65 0.70 0.75 0.80 0.85 0.90 0.95 1.00 1.050102030405060708090100110Power (% Rated)LHGRFAC(p)> 50% Core Flow

< 50% Core FlowFigure 3-2bCycle 18 Power-Dependent LHGR Factor MOC-EOC for GNF2, GE14, and ATRIUM-10Note: These factor to be applied to the exposure-dependent limits as descibed in Section 5.3

CORE OPERATING LIMITS REPORT COLR Page 22 LBDCR 09037

30, 0.65220, 0.65271.4, 1.00105, 1.00 0.60 0.65 0.70 0.75 0.80 0.85 0.90 0.95 1.00 1.050102030405060708090100110Power (% Rated)LHGRFAC(f)

Figure 3-3Cycle 18 Flow-Dependent LHGR Factor for GNF2, GE14, and ATRIUM-10Note: These factor to be applied to the exposure-dependent limits as descibed in Section 5.3

CORE OPERATING LIMITS REPORT COLR Page 23 LBDCR 09037 0 10 20 30 40 50 60 70 80 90 100 110 1200102030405060708090100110120TOTAL CORE FLOW (%)% RTPMONITOREDREGION Figure 4-1 Monitored Region Boundary CORE OPERATING LIMITS REPORT COLR Page 24 LBDCR 09037 0 10 20 30 40 50 60 70 80 90 100 110 1200102030405060708090100110120ALIGNED DRIVE FLOW (%)

% RTPRESTRICTEDREGION Figure 4-2 Restricted Region Boundary for Two-Loop Operation CORE OPERATING LIMITS REPORT COLR Page 25 LBDCR 09037 0 10 20 30 40 50 60 70 80 90 100 110 1200102030405060708090100110120ALIGNED DRIVE FLOW (%)

% RTPRESTRICTEDREGION Figure 4-3 Restricted Region Boundary for Single-Loop Operation CORE OPERATING LIMITS REPORT COLR Page 26 LBDCR 09037 0 10 20 30 40 50 60 70 80 901001101200102030405060708090100110120ALIGNED DRIVE FLOW (%)

% RTPNon-Setup (Trip Setpoint)Non-Setup (Allowable Value)Setup (Trip Setpoint)Setup (Allowable Value)

Figure 4-4 APRM Flow-Biased Simulated Thermal Power - High Scram Allowable Values for Two-Loop Operation CORE OPERATING LIMITS REPORT COLR Page 27 LBDCR 09037 0 10 20 30 40 50 60 70 80 901001101200102030405060708090100110120ALIGNED DRIVE FLOW (%)% RTPNon-Setup (Trip Setpoint)Non-Setup (Allowable Value)Setup (Trip Setpoint)Setup (Allowable Value)

Figure 4-5 APRM Flow-Biased Simulated Thermal Power - High Scram Allowable Values for Single-Loop Operation

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