LIC-02-0072, Omaha Public Power District Transmittal of Fort Calhoun Station (FCS) Core Operating Limit Report (COLR) Revision 27

Omaha Public Power District Transmittal of Fort Calhoun Station (FCS) Core Operating Limit Report (COLR) Revision 27

ML021650492
Person / Time
Site:	Fort Calhoun
Issue date:	05/31/2002
From:	Ridenoure R Omaha Public Power District
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LIC-02-0072
Download: ML021650492 (21)

Text

Omaha Public Power District 444 South 16th Street Mall Omaha NE 68102-2247 May 31, 2002 LIC-02-0072 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Reference:

Docket No. 50-285

SUBJECT:

Transmittal of Fort Calhoun Station (FCS) Core Operating Limit Report (COLR) Revision 27 Pursuant to FCS Unit No. 1 Technical Specification 5.9.5.c, Omaha Public Power District is transmitting Revision 27 (dated May 20, 2002) of the FCS COLR. The COLR was revised to incorporate the Cycle 21 specific update.

Please contact me if you have any questions.

Attachment:

TDB-VI - Technical Data Book - Core Operating Limit Report - Revision 27 c: E. W. Merschoff, NRC Regional Administrator, Region IV A. B. Wang, NRC Project Manager W. C. Walker, NRC Senior Resident Inspector Winston & Strawn (w/o attachments) k'ý- C)t Employment with Equal Opportunity 4171

WP8 Fort Calhoun Station Unit No. 1 TDB-VI TECHNICAL DATA BOOK

Title:

CORE OPERATING LIMIT REPORT FC-68 Number: EC 30066 Reason for Change: Update for Cycle 21.

Requestor: Thomas Heng Preparer: Mathew Panicker ISSUED: 05-20-02 1515 R27

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 1 OF 19 Fort Calhoun Station, Unit I Cycle 21 Core Operating Limits Report Due to the critical aspects of the safety analysis inputs contained in this report, changes may not be made to this report without concurrence of the Nuclear Engineering Department.

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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 2 OF 19 TABLE OF CONTENTS Item Description Page 1.0 Introduction 5 2.0 Core Operating Limits 5 3.0 TM/LP Limit 7 4.0 Maximum Core Inlet Temperature 7 5.0 Power Dependent Insertion Limit 8 6.0 Linear Heat Rate 8 7.0 Excore Monitoring of LHR 8 "8.0 Peaking Factor (FRT) Limits 8 9.0 DNB Monitoring 8 10.0 FRT and Core Power Limitations 8 11.0 Refueling Boron Concentration 9 12.0 Axial Power Distribution 9 13.0 Shutdown Margin With TcOLD > 210 OF 9 14.0 Most Negative Moderator Temperature 9 Coefficient R27

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 3OF 19 LIST OF TABLES Table No. Title Page 1 TM/LP Coefficients 7 2 Refueling Boron Concentrations 9 R27

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 4 OF 19 LIST OF FIGURES Figure No. Title Page 1 Thermal Margin/Low Pressure for 4 Pump 10 Operation 2 Power Dependent Insertion Limit 11 3 Allowable Peak Linear Heat Rate vs. Burnup 12 4 Excore Monitoring of LHR 13 5 DNB Monitoring 14 6 BASSS Allowable Power 15 7 FRT and Core Power Limitations 16 8 Axial Power Distribution LSSS for 4 Pump 17 Operation 9 Axial Power Distribution Limits for 4 Pump 18 Operation with Incores Inoperable 10 Minimum Boric Acid Storage Tank Level vs. 19 Stored Boric Acid Storage Tank Concentration R27

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 5 OF 19 Cycle 21 Core Operating Limits Report 1.0 Introduction This report provides the cycle-specific limits for operation of the Fort Calhoun Station Unit 1 for Cycle 21 operation. It includes limits for:

• TM/LP LSSS for 4 Pump Operation (PVAR)

• Core Inlet Temperature (TIN)

• Power Dependent Insertion Limit (PDIL)

• Allowable Peak Linear Heat Rate

• Excore Monitoring of LHR

• Integrated Radial Peaking Factor (FRT)

• DNB Monitoring

• FRT versus Power Trade-off Curve

• Refueling Boron Concentration

• Axial Power Distribution

• Shutdown Margin With TcOLD > 210 OF

- Most Negative Moderator Temperature Coefficient These limits are applicable for the duration of Cycle 21. For subsequent cycles the limits will be reviewed and revised as necessary. In addition, this report includes a number of cycle-specific coefficients used in the generation of certain reactor protective system trip setpoints or allowable increases in radial peaking factors.

2.0 Core Operating Limits All values and limits in this TDB section apply to Cycle 21 operation. Cycle 21 must be operated within the bounds of these limits and all others specified in the Technical Specifications. This report has been prepared in accordance with the requirements of Technical Specification 5.9.5. The values and limits presented within this TDB section have been derived using the NRC approved methodologies listed below:

"* OPPD-NA-8301, "Reload Core Analysis Methodology Overview," Rev. 6, dated December 1994. (TAC No. M89455)

"* OPPD-NA-8302, "Reload Core Analysis Methodology, Neutronics Design Methods and Verification," Rev. 4, dated December 1994. (TAC No.

M89456)

"* OPPD-NA-8303, "Reload Core Analysis Methodology, Transient and Accident Methods and Verification," Rev. 4, dated January 1993. (TAC No.

M85845)

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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 6 OF 19

"* XN-75-32(P)(A) Supplements 1, 2, 3, & 4, "Computational Procedure for Evaluating Fuel Rod Bowing," October 1983.

"* XN-NF-82-06(P)(A) and Supplements 2, 4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Revision 1, October 1986.

"* XN-NF-85-92(P)(A), "Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination and Thermal Conductivity Results," August 1985.

"* ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Burnups of 62 GWd/MTU,"

December 1991.

"* EMF-92-116(P)(A), "Generic Mechanical Design Criteria for PWR Fuel Designs," Revision 0, February 1999.

"* XN-NF-78-44(P)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," October 1983.

"* XN-NF-82-21(P)(A), "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Revision 1, September 1983.

"* EMF-1961(P)(A), "Statistical SetpointlTransient Methodology for Combustion Engineering Type Reactors," Revision 0, July 2000.

"* XN-NF-621(P)(A), "Exxon Nuclear DNB Correlation for PWR Fuel Designs," Revision 1, September 1983.

"* ANF-89-151(P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events," Revision 0, May 1992.

"* EMF-92-153(P)(A) and Supplement 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," March 1994.

"* XN-NF-82-49(P)(A), Supplement 1, "Exxon Nuclear Company Evaluation Model Revised EXEM PWR Small Break Model," Revision 1, December 1994.

"* EMF-2087(P)(A), "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Revision 0, June 1999.

"* ANF-84-73 Appendix B (P)(A), "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation, Revision 5, July 1990.

"* EMF-84-093(P)(A), "Steam Line Break Methodology for PWRs," Siemens Power Corporation, Revision 1, February 1999.

"* EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based,"

Framatome ANP, Inc., Revision 0, March 2001.

" EMF-96-029(P)(A) Volume 1, EMF-96-029(P)(A) Volume 2, EMF-96-029(P)(A)

Attachment, "Reactor Analysis System for PWRs, Volume 1 - Methodology Description, Volume 2 - Benchmarking Results," Framatome ANP, Inc., January 1997.

" EMF-2310(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors, " Framatome ANP, Inc., Revision 0, May 2001.

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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 7 OF 19 3.0 TM/LP Limit The TM/LP coefficients for Cycle 21 are shown below: I Table I TM/LP Coefficients Coefficient Value 29.6 20.63 Y -12372 The TM/LP setpoint is calculated by the PVAR equation, shown below and in Figure 1:

PWR= 29.6 PF(B) AI(Y)B + 20.63TIN - 12372 PF(B) = 1.0 for B _Ž100%

= -0.008(B)+1.8 for 50% < B < 100%

= 1.4 for B5<50%

Al (Y) = -0.6666(Y1 ) + 1.000 for Y1 < 0.00

= +0.3333(Y1 ) + 1.000 for Y1 > 0.00 Where:

B = High Auctioneered thermal (AT) or Nuclear Power, % of rated power Y = Axial Shape Index, asiu TIN = Core Inlet Temperature, OF PVAR = Reactor Coolant System Pressure, psia 4.0 Maximum Core Inlet Temperature The maximum core inlet temperature (TIN) for Cycle 21 shall not exceed 545 OF. This value includes instrumentation uncertainty of +/-2 OF (Ref: FCS Calculation FC06292, 6/9/95).

This limit is not applicable during either a thermal power ramp in excess of 5% of rated thermal power per minute or a thermal power step greater than 10% of rated thermal power.

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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 8OF19 5.0 Power Dependent Insertion Limit The power dependent insertion limit is defined in Figure 2.

6.0 Linear Heat Rate The allowable peak linear heat rate for Cycle 21 is shown in Figure 3.

7.0 Excore Monitoring of LHR The allowable operation for power versus axial shape index for monitoring of LHR with excore detectors for Cycle 21 is shown in Figure 4.

8.0 Peaking Factor Limits The Cycle 21 maximum full power value for the integrated radial peaking factor (FRT) is 1.732. I 9.0 DNB Monitoring The core operating limits for monitoring of DNB are provided in Figures 5 and 6. These figures provide the allowable power versus axial shape index for Cycle 21 operation. When the Better Axial Shape Selection System (BASSS) is operable, the limits in Figure 6 apply. If BASSS becomes inoperable, the limits in Figure 5 apply. Note that for Cycle 21, the DNB limits are identical whether BASSS is operable or inoperable.

10.0 F.RT and Core Power Limitations Core power limitations versus FRT are shown in Figure 7 for Cycle 21.

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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 9 OF 19 11.0 Refueling Boron Concentration The refueling boron concentration is required to ensure a shutdown margin of not less than 5%

with all CEAs withdrawn. The refueling boron concentration must be at least 1,900 ppm through the end of Cycle 20 operation and is valid until the beginning of core reload for Cycle 21.

Listed below in Table 2 are the refueling boron concentration values for Cycle 21 operations:

Table 2 Refueling Boron Concentrations Cycle 21 Average Burnup Refueling Boron Concentration (MWD/MTU)

BOC 2,155

> 2,000 2,023

>4,000 1,900 12.0 Axial Power Distribution The axial power trip is provided to ensure that excessive axial peaking will not cause fuel damage. The Axial Shape Index is determined from the axially split excore detectors. The setpoint functions, shown in Figure 8 ensure that neither a DNBR of less than the minimum DNBR safety limit nor a maximum linear heat rate of more than 22kW/ft (deposited in the fuel) will exist as a consequence of axial power maldistributions. Allowances have been made for instrumentation inaccuracies and uncertainties associated with the excore symmetric offset incore axial peaking relationship. Figure 9 combines the LHR LCO tent from Figure 4, the DNB LCO tent from Figure 5, and the APD LSSS tent from Figure 8 into one figure for a visual comparison of the different limits.

13.0 Shutdown Margin With TcOW > 210 OF Whenever the reactor is in hot shutdown, hot standby or power operation conditions, the shutdown margin shall be _>3.6% Ak/k. With the shutdown margin <3.6% Ak/k, initiate and continue boration until the required shutdown margin is achieved.

14.0 Most Negative Moderator Temperature Coefficient The moderator temperature coefficient (MTC) shall be more positive than -3.05 x 10 4 ApI/F, including uncertainties, at rated power.

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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 10 OF 19 590 U 580 Ld 570 560 w

550 w

540 z

530 0

520 U~J 0

u) 510 500 60 70 80 90 100 110 120 CORE POWER (% OF RATED)

PVAR = 29.6 PF(B)AI(Y)B + 20.63TIN - 12372 PF(B) = 1.0 BŽ 100% AI(Y) = -0.6666Y1 + 1.000 Y, < 0.00

= -.008B+1.8 50% < B < 100% = +0.3333Y, + 1.000 Y, > 0.00

= 1.4 B<*50%

THERMAL MARGIN / LOW PRESSURE FOR 4 PUMP OPERATION R27

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 11OF19 R27

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 12 OF 19 18 I I I UNACCEPTABLE OPERATION 16 15.5 KWIFT 14 I-L ACCEPTABLE OPERATION U

12 10

._1 w 8 I

6 4 4. t I

& I a 0

0 5000 10000 15000 20000 BURNUP (MWD/MTU)

CYCLE 21 ALLOWABLE PEAK LINEAR HEAT RATE FIGURE COLR VS. BURNUP 3 R27

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 13 OF 19 110

(-0.12,100) (0.08,100) 100 90 w 80 0

I 70 LU w

0 60 0

0 50

(-0.5,50) (0.6,50)

LJ 0 40 I-zw 30 wu 0

L) 20 10 0

-0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 AXIAL SHAPE INDEX (ASIU)

R27

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 14 OF 19 110

(-0.12,100) (0.15,100) 100 / -

w 0

90 0J w

(. 80

(-/,4 (.,4 70 w

0

-J 60

-3 50 ILL 0 40 z

w 30 w

I-20 10 0

-0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 AXIAL SHAPE INDEX (ASIU)

NOTE: WHEN BASSS IS OPERABLE, THIS FIGURE IS SUPERCEDED BY FIGURE 6 BASSS DNB ALLOWABLE POWER CYCLE 21 DNB MONITORING FIGURE COLR 5 R27

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 15 OF 19 110

(-0.12,100) (0.15,100) 100 w 90 0 ( 6 (,

80 w.IM 0 70

-. 5,4 (0.5,64)*

0 cm) wJ 60 0-- !

50 0 40 I-z w

LLI 0 30 w

20 10 0

-0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 AXIAL SHAPE INDEX (ASIU)

R27

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 16 OF 19 110 100 90 80 (LU 0

w C-. 70 0n*

U 0 60 0.J 50

-J z

0 40 Z

0LI 30 w

20 10 0

1.70 1.75 1.80 1.85 1.90 PEAKING FACTOR R27

TECHNICAL DATA BOOK PROCEDURE PAGE 17 OF 19 150 (0,140) 140 /\

130 -------------

120 110 LU o 1oo (-0.27,100) . - (0.27,100) 0L LUI w 90 0

80 (-.4,80)----------------(0.4,8) 70 0

-j 60 LL.

oI 50 -065)----------- (06,50) z wU 40 UJ 30 a.

20 10 0

-0.8 -0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 0.8 AXIAL SHAPE INDEX (ASIU)

,LE 21 AXIAL POWER DISTRIBUTION LSSS FIGUI OLR FOR 4 PUMP OPERATION 8 R27

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 18 OF 19 150

- *PD LSSS 140 130 120 DNBRKWIFT DNBR MONITORING 110 MONITORINGLIMIT 0

100 LIM/IT' 90 0

C.) 80 70 LU 0

0

-J 60 I

.j LI 50 --- --- -- -- -- - -

z 40 LU 30

(.

20 10 0

-0.8 -0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 0.8 AXIAL SHAPE INDEX (ASIU)

AXIAL POWER DISTRIBUTION LIMITS FOR 4 PUMP OPERATION WITH INCORES INOPERABLE R27

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 19 OF 19 100 90 80 0z 70 I

60 0

w r*

(0 w 50 a

-J 40 x N M 30 w

-. I 20 z

10 flt 2.5 2.7 2.9 3.1 3.3 3.5 3.7 3.9 4.1 4.3 4.5 STORED BAST CONCENTRATION (WT % BORIC ACID)

A 1800 F'PM X 1900 PPM *2000 PPM N 2150 PPM +2300 PPM IN SIR .WT IN SIRWT IN SIRWT IN SIRWT IN SIRWT CYCLE 21 MINIMUM BAST LEVEL vs. STORED FIGURE COLR BAST CONCENTRATION 10 R27