GNRO-2008/00070, Cycle 17 Update to the Core Operating Limits Report (COLR)

Cycle 17 Update to the Core Operating Limits Report (COLR)

ML083030084
Person / Time
Site:	Grand Gulf
Issue date:	10/28/2008
From:	Larson M Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2008/00070
Download: ML083030084 (25)

Text

-===-Entergy GNRO-2008/00070 October 28, 2008 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Entergy Operations, Inc.

PO Box 756 Port Gibson, MS 39150 Tel 601 437 2800

Subject:

Cycle 17 Update to the Core Operating Limits Report (COLR)

Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29

Dear Sir or Madam:

Attached is the Cycle 17 update to the Grand Gulf Nuclear Station Core Operating Limits Report (COLR).

This letter does not contain any commitments.

Yours truly, Michael J.

arson Acting-Manager Licensing MJLlJEO attachment:

cc:

Cycle 17 Update to the GGNS COLR (See Next Page)

GNRO-2008/00070 Page 2 cc:

NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U. S. Nuclear Regulatory Commission ATIN: Mr, Elmo E. Collins (w/2)

Regional Administrator, Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U. S. Nuclear Regulatory Commission ATIN: Mr. Carl F. Lyon, NRR/DOLR (w/2)

ATTN: ADDRESSEE ONLY ATIN: Courier Delivery Only Mail Stop OWFN/8 81 11555 Rockville Pike Rockville, MD 20852-2378

Attachment to GNRO-2008/00070 CYCLE 17 UPDATE TO THE GRAND GULF NUCLEAR STATION (COLR)

Grand Gulf Nuclear Station Core operating Limits Report COLR page 1 LDC 02001

CORE OPERATING LIMITS REPORT REASON FOR REVISION This reV1Slon provides the Cycle 17 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 Averaae 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 ADD1i cabil i ty 8

Figure(s) 1 APLHGR Operating Limits 9

Figure(s) 2 MCPR Operating Limits 10-14 Figure(s) 3 LHGR Operating Limits 15-17 Figure(s) 4 EIA Stability Limits 18-22 COLR Page 2 LDC 08029

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.

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 17 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 17 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 ElA stability limits.

COLR Page 3 LDC 08029

CORE OPERATING LIMITS REPORT

3.0 REFERENCES

This section contains the background, cycle-specific, and methodology references I used in the safety analysis of Grand Gulf Cycle 17.

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-08-00029 Revision 1, 2JJJwJemeu.:tgL.R~.9jt(LJ,.icen?JlliLRportfQLGr<imi Gulf Nuclear Station Reload 16 Cycle 17, dated October 2008.

3.2.2 ECH-NE-08-00031 Revision 1, GE14 Fuel Design Cycle-Independent Analyses fo r:::...J:-'J!~I:.m-:_J:iran d~iLlJli_Nl!c 1~_gLSta.tiPJJ, dated October 2008.

3.2.3 ECH-NE-08-00030 Revision 1, Fuel Bundle Infor~ation Report for Grand Gulf Nuclear Station Reload 16 Cycle 17, dated October 2008.

3.2.4 NEDC-32910P, Revision 1, Grand Gulf Nuclear Station SAFER/GESTR-LOCA Accident AnalY2is With

~~laxed__~CCS Parameters, dated October 1999.

3.2.5 GGNS-SA-08-00005 Revision 0, Grand Gulf Nuclear Station ATRIUM-I0 ECCS-bOCA EvaluatiQrr, dated July 2008.

3.2.6 GGNS-SA-08-00006 Revi si on 0, fd.C<iDd Gylf Nuclg_ar._21ation GE14 ECCS-:.bOCA Evaluation, dated July 2008.

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

COLR Page 4 LDC 08029

CORE OPERATING LIMITS REPORT 3.3 Methodology References The Technical Specifications provided in brackets.

(TS) supported by each methodology reference are I 3.3.1 3.3.2 3.3.3 3.3.4 3.3.5 3.3.6 3.3.7 3.3.8 3.3.9 3.3.10 3.3.11 3.3.12 3.3.13 3.3.14 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 3.2.3J.

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 J.

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 3.2.3J.

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].

Deleted 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].

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].

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 3.2.3J 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].

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].

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 3.2.2J.

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].

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 [TS 3.2.2].

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

COLR Page 5 LOC 07011

CORE OPERATING LIMITS REPORT 3.3 Methodology References (continued) 3.3.15 3.3.16 3.3.17 3.3.18 3.3.19 3.3.20 3.3.21 3.3.22 3.3.23 3.3.24 3.3.25*

• Note:

EMF-1997(P)(A) Revision 0, "ANFB-10 Critical Power Correlation," Siemens Power Corporation, July 1998 [TS 3.2.2].

EMF-1997(P), Supplement l(P) (A), Revision 0, "ANFB-10 Critical Power Correlation: High Local Peaking Results, Siemens Power Corporation," July 1998 [TS 3.2.2].

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

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].

EMF-2361 (P)(A) Revision 0, "EXEM BWR-2000 ECCS Evaluation Model,"

Framatome ANP Richland, Inc., May 2001 [TS 3.2.1].

Deleted Deleted NEDC-33383P, Revision 1, "GEXL97 Correlation Applicable to ATRIUtvl-10 Fuel," June, 2008 [TS 3.2.2J.

EMF-2292(P)(A) Revision 0, "ATRIUM-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation," September 2000 [TS 3.2.1].

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].

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].

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

COLR Page 6 LDC 08029

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 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" ElA 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 17 MOC Core Average Exposure (CAE) is 26,019 MWdjST [3.2.1].

4.13 End of Cycle (EOC) - The Cycle 17 EOC CAE is 29,750 MWd/ST [3.2.1].

COLR Page 7 LDC 08029

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 shall not exceed the exposure-dependent limits reported in Figures 1-1 and 1-2 [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].

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 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 Figures 3-2a and 3-3, respectively [3.2.2J.

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 Figures 3-2b and 3-3, respectively [3.2.2J.

5.4 Stability The stability regions and allowable values specified in Technical Specifications are reported in Figure(s) 4 [3.2.7].

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 of 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 multiplier on LHGR and MAPLHGR of 0.83 is required [3.2.1].

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].

COLR Page 8 LDC 08029

70 63.5,5.0 60 50 20

~+-~~~..",..1-1~~~~_+I**..*L,~'~~-+~

30 40

~-'-'-':""'=-=';;;

--Ia:1..:9.14, 12.82 13 0.00,12.82 12 11

=- 10

~C 9

It

(!)

r 8*

.....I Q.<

E 7

6 5

4 1

0 10 Average Planar Exposure (GWdlST)

Figure 1-1 Maximum Average Planar Linear Heat generation Rate for GE14 Note: Actual Limits described In Sections 5.1 and 5.5 13 0.00,12.81 12 11

~ 10I 9

It

(!)

r 8

.....I Q.<

E 7

6 5

4

~L_.~_-'-------+~,",- __

0 10 20 21.66, 12.81

+_.

f'..L~.~~-+-~

30 40 50 Average Planar Exposure (GWd/ST) 60 63.87,7.3 70 Figure 1-2 Maximum Average Planar Linear Heat generation Rate for ATRIUM-10 Note: Actual Limits described In Sections 5.1 and 5.5 COLR Page 9 LDC 08029

2.1 25,2.03 90, 1.23 100,1.21

~. ~+.~

.+

I

+

I 20 30 40 50 60 70 80 90 100 25,1.93

. 50% Core Flow 2.0 1.3 1.9 1.2 1.8 1.1 1.7

~ 1.6 D.

~ 1.5 1.4 1.0 +-~--+--~--+-~

o 10 Core Power (% Rated)

Figure 2-1a Cycle 17 Power-Dependent MCPR Limits for GE14 aOCto MOC 2.1 2.0 1.9 1.8 1.7

~ 1.6 D.

~ 1.5 1.4 1.3 1.2 100,1.21 1.1 100 90 80 70 60 50 40 30 20 10 1.0 +-~--+-~--+--~-'--~--+-~-'--~--t-~-+-~--t--~-+--~--i o

Core Power (% Rated)

Figure 2-1b Cycle 17 Power-Dependent MCPR Limits for ATRIUM-10 aOCto MOC COLR Page 10 LDC 08029

2.1 2.0 1.9 1.8 1.7

~ 1.6 0.!i 1.5 1.4 1.3 1.2 25,2.03 25,1.93

50% Core Flow 90,1.24 100,1.23 1.1 100 90 80 70 60 50 40 30 20 10 1.0 +-~_-+----'_-+-_~-i-_~-+_~---'r-~_+-~_+-~_-+-_~-+-_~--J o

Core Power (% Rated)

Figure 2-2a Cycle 17 Power-Dependent MCPR Limits for GE14 BOC to MOC with EOC-RPT Inoperable 2.1 2.0 1.9 1.8 1.7

~ 1.6 0.!i 1.5 1.4.

1.3 1.2

> 50% Core Flow 90, 1.25 100,1.23 1.1 100 90 80 70 60 50 40 30 20 10 1.0 +-~--+--~-+-~-+-~--+--~-+--~~-~-+-~--+--~--+-~-

o Core Power (% Rated)

Figure 2-2b Cycle 17 Power-Dependent MCPR Limits for ATRIUM-10 BOC to MOC with EOC-RPT Inoperable COLR Page 11 LDC 08029

2.1

~

2.0 f 1.9.

1.8 +

Ir 1.7t

~ 1.6 r D..

~ 1.5t 1

1.4 1.3 +

1.2f 1.1+

f 25,2.10 25,2.02

> 50% Core Flow 40,1.93 40,1.81 40, 1.61 ~--::+::-:::::---_-l70, 1.53 50,1.58 100, 1.32 1.0 +!-~-II--~-+I-~-+-I -~--+-~-+-I -~--+I-~-+-~--jl-~-+I

-~---jl o

10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)

Figure 2-3a Cycle 17 Power-Dependent MCPR Limits for GE14 MOCto EOC 100,1.33

___ 7.0, 1.51 50,1.57 25,2.06 25, 1.98 2.1 T 2.0 +

1.9j 1.8,

Ie 1.7 '

~ 1.6 t D.. t o

15*L

IE i

14 i f

1.3 i r

1.2 T 1.1 +

1.0 +t-~-+---L--+-~~-+-I-~---jl-~-+I---I+--~-+I---+--~--+I-~---jl

° 10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)

Figure 2*3b Cycle 17 Power-Dependent MCPR Limits for ATRIUM-10 MOC to EOC COLR Page 12 LDC 08029

CORE OPERATING LIMITS REPORT 2.1 2.0 1.9 1.8 1.7

~ 1.6 a..

~ 1.5 1.4 25,2.10 25,2.02

> 50% Core Flow 1.3 100,1.39 1.2 1.1 100 90 80 70 60 50 40 30 20 10 1.0 +-~--+-~-.... +._-~-+--~-

.+.~-~--i-~--j

.....,._-+-~--+--_..

_.+--~-j o

Core Power (% Rated)

Figure 2-4a Cycle 17 Power*Dependent MCPR Limits for GE14 MOC to EOC with EOC*RPT Inoperable 100,1.40

> 50% Core Flow 25,2.06 25, 1.98

. 50% Core Flow 2.1 1

1 1.8,

i' 1.7+

~ 1.6t a..

~ 1.5 +

1.4 t I

~::1 1.1.+

1.0.r-~-+--~-+I-~--tl-~---i~-+-~-+I-~--il-~-+-I-~-+-~-I o

10 20 30 40 50 60 70 80 90 100 Core Power (% Rated)

Figure 2-4b Cycle 17 Power*Dependent MCPR Limits for ATRIUM*10 MOC to EOC with EOC*RPT Inoperable COLR Page 13 LDC 08029

CORE OPERATING LIMITS REPORT 1.35 T

~

I 20,1.30 30,1.30 1.30+

f t

£t I

a. 125 1

u

IE 105,1.21

~

120 1

1.15 L~---+...

I f**

...+

0 10 20 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Figure 2-5 Cycle 17 Flow-Dependent MCPR Limits for GE14 and ATRIUM-10 COLR Page 14 LDC 08029

CORE OPERATING LIMITS REPORT 70 63.87,7.30 60 50 20

__-+-_~_m. -+

I 30 40 Pellet Exposure (GWd/ST)

._-------.....17.15, 13.40 14 0.0, 13.4 13 12 11

~

~ 10 0::

Cl

c oJ 9

8 7

6 0

10 Figure 3-1 Maximum Linear Heat Generation Rate for ATRIUM-10 Note: Actual limits described in Sections 5.3 and 5.5 COLR Page 15 LDC 08029

CORE OPERATING LIMITS REPORT 40,0.780 110 100 100.1.0 90 80 70 60 50 40 30 50.1.0 20

25. 0.767 - ---.........

10

> 50% Core Flow

'~f--L-~~-+--,~J_,--l-,~,+_,L......L........

I 1

1.05 1.00 0.95 Q:

c:r Lf 0.90 0::

Cl

t:

...I 0.85 0.80 0.75 0

Power (% Rated)

Figure 3-2a Cycle 17 Power-Dependent LHGR Factor BOC-EOC for GE14 Note: These factor to be applied to the exposure-dependent limits as desclbed In Section 5.3 1.05 50.1.0 100. 1.0 1.00 0.95 Q:

c:r< 0.90 LL.

0::

Cl

t:

...I 0.85 25.0.854 0.80 40.0.782 0.75 o

10 25,0.761 20 30 40 50 60 70 80 90 100 110 Power (% Rated)

Figure 3*2b Cycle 17 Power-Dependent LHGR Factor BOC-EOC for ATRIUM-10 Note: These factor to be applied to the exposure-dependent limits as desclbed In Section 5.3 COLR Page 16 LDC 08029

CORE OPERATING LIMITS REPORT 1.05 60,1.0 0.95 0.75 -

20.0,0.748 30.0,0.748 105,1.0 0.65 -~---+-~-

o 10

-t~,-,---------L I

I

~.-_..._.._j I

+----"

-'------+

20 30 40 50 60 70 80 90 100 110 Core Flow (% Rated)

Figure 3*3 Cycle 17 Flow-Dependent LHGR Factor for GE14 and ATRIUM-10 Note: These factor to be applied to the exposure-dependent limits as descibed In Section 5.3 COLR Page 17 LDC 08029

CORE OPERATING LIMITS REPORT 120 110 100 90 80 40 50 60 70 TOTAL CORE FLOW (%)

Figure 4-1 Monitored Region Boundary 30 MONITORED REGION 20 10 120 110 100 90 80 70 Q.I-0:::

60

~

0 50 40 30 20 10 0

0 COLR Page 18 LDC 08029

CORE OPERATING LIMITS REPORT 120 110 100 90 80 40 30 50 60 70 ALIGNED DRIVE FLOW (%)

Figure 4-2 Restricted Region Boundary for Two-Loop Operation 20 RESTRICTED REGION 10 120 110 100 90 80 70.

Q.

~

60

~

0 50 40 30 20 10 0

0 COlR Page 19 LDC 08029

CORE OPERATING LIMITS REPORT RESTRICTED REGION 120 110 100 90 80 40 30 50 60 70 ALIGNED DRIVE FLOW (%)

Figure 4-3 Restricted Region Boundary for Single-Loop Operation 20 10 120 110 100 90 80 70 Q.

I-0:::

60

~..

50 40 30 20 10 0

0 COLR Page 20 LDC 08029

CORE OPERATING LIMITS REPORT 120 110 100 90 80 l~-~-~-~.~-:::~-:-:-:~:~-;-:-:-~:-w :b-e-~-:~~~':~~~~e~)-!

i Setup (Trip Setpoint) 1- - - Setup (Allowable Value) 70 60 50 40 30 20 10

/

I..

120 110 100 90 80 70 P-<

E-<

60 p:;

0\\° 50 40 30 20 10 0

0 ALIGNED DRIVE FLOW

(%)

Figure 4-4 APRM Flow-Biased Simulated Thermal Power - High Scram Allowable Values for Two-loop Operation COlR Page 21 LDC 08029

CORE OPERATING LIMITS REPORT 120 110 100 90 80 70 P-<

~

60 0\\° 50 40 30 20 10 o

I I

I, I

I,.

i---** Non-Se t-~p-(T~Tps~i: p 0 i-~t-)-**

--..=-=-Non-Setup (Allowable Value)

---

Setup (Trip Setpoint) 1- - - Setup (Allowable Value) o 10 20 30 40 50 60 70 ALIGNED DRIVE FLOW

(%)

80 90 100 110 120 Figure 4-5 APRM Flow-Biased Simulated Thermal Power - High Scram Allowable Values for Single-Loop Operation COLR Page 22 LDC 08029