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Fort Calhoun Station Technical Data BookTDB

Page 3 of 5

J

I Document Document Title Revision/Date

TDB-111.1 5.A Specific Volume vs Temperature (35°F to 200°F) R1 04-05-05

TDB-111.20 RCS Elevationsvs. LI-106, LI-199, LI-197and LIS-119 R17 04-20-05

TDB-111.22 Limitation on Power Level Increases and Rod Movements R14 04-05-05at Power

TDB-I.23.A Transient Power ASI Control Band R4 04-05-05

TDB-1l1.23.B Equilibrium Power ASI Control Band R3 04-13-05

TDB-111.24 Detector Well Temperature vs. Highest Concrete R7 04-13-05Temperature

TDB-111.26 Diesel Generator Capability Curve (4160 Volts) R4 04-13-05

TDB- 11.26.A Diesel Generator Loading Curve R13 04-13-05

TDB-111.27 Decay Heat vs. Time After Shutdown and Time to Boil R8 04-13-05Curves and Tables

TDB-111.28 Reactor Vessel Level Monitoring System (RVLMS) R5 06-01-05

TDB-111.30 Circulating Water Pump Cell and River Levels from R2 05-19-05Pressure Gauge LI-1 900

TDB-111.31 AC-10A Pump Curve R19 05-19-05

TDB-111.32 AC-10B Pump Curve R17 12-07-04

TDB-I11.33 AC-10C Pump Curve R20 05-24-05

TDB- 11.34 AC-1OD Pump Curve R22 05-19-05

TDB-111.35 Spent Fuel Pool Rack Measurements R1 05-19-05

TDB-111.36 Containment Leakage Rate Assessment R23 06-30-05

TDB-111.37A Boron Addition Rate (HZP) - SIRWT @ 1700 ppm R1 06-01-05

T1B -11.373 Boron Addition Rate (HZP) - SIRWT @ 1800 ppm R1 06-01-05

TDB-111.37C Boron Addition Rate (HZP) - SIRWT @ 1900 ppm R1 06-01-05

TDB-111.37D Boron Addition Rate (HZP) - SIRWT © 2000 ppm R1 06-01-05

le TDB-111.37E Boron Addition Rate (HZP) - BAST's @ 3.0% BA R1 06-01-05

June 30, 2005 8:16 AM

Fort Calhoun Station Technical Data BookTDB

Page 5 of 5

Document Document Title RevisionlDate

TDB-V.6 Indication of Reactor Power Based on AT R6 05-22-98a

TDB-V.9 Shutdown Margin Worksheet R35 08-08-02

TDB-V.11 Instrument Bus Loads and Failure Modes R38 04-13-05

TDB-V.12 Miscellaneous Formula Sheet R7 06-23-05

TDB-V.13 Reactor Vessel Coldown When Sweeping Steam R1 06-23-05Generators

TDB-VI Core Operating Limit Report R31 06-30-05

TDB-VII Tank Curves R8 08-12-04

TDB-VIII Equipment Operability Guidance R20 05-20-05

TDB-IX RCS Pressure and Temperature Limits Report RO 09-05-03

June 30. 2005 8:16 AM

PAGE 1 OF 19

Fort Calhoun StationUnit 1

TDB-VI

TECHNICAL DATA BOOK

CORE OPERATING LIMIT REPORT

Change No. EC 36669Reason for Change Add reference requirements consistent with Technical Specification

Amendment No. 196.Requestor Kevin HolthausPreparer Kevin HolthausIssue Date 06-30-05 3:00pm

R31

FORT CALHOUN STATIONTECHNICAL DATA BOOK

TDB-VIPAGE 2 OF 19

Fort Calhoun Station, Unit 1

Core Operating Limit Report

Due to the critical aspects of the safety analysis inputs contained in this report, changes may notbe made to this report without concurrence of the Nuclear Engineering Department.

R31

FORT CALHOUN STATION TDB-VITECHNICAL DATA BOOK PAGE 3 OF 19

TABLE OF CONTENTS

Item Description PaQe

1. INTRODUCTION.................................................................................................6

2. CORE OPERATING LIMITS ................................................... 6

3. TM/LP LIMIT ................................................... 8

4. MAXIMUM CORE INLET TEMPERATURE .................................................... 8

5. POWER DEPENDENT INSERTION LIMIT .................................................... 8

6. LINEAR HEAT RATE ........ 9...........................................9

7. EXCORE MONITORING OF LHR ..................................................... 9

8. PEAKING FACTOR LIMITS .................................................... 9

9. DNB MONITORING ................................................... 9

10. FR T AND CORE POWER LIMITATIONS . ................................................... 9

11. REFUELING BORON CONCENTRATION .................................................... 9

12. AXIAL POWER DISTRIBUTION ................................................... 10

13. SHUTDOWN MARGIN WITH Tcold > 210'F ................................................... 10

14. MOST NEGATIVE MODERATOR TEMPERATURE COEFFICIENT ................ 10

R31

FORT CALHOUN STATIONTECHNICAL DATA BOOK

TDB-VIPAGE 4 OF 19

LIST OF TABLES

Table No.

1

2

Title Page

TM/LP Coefficients ........................ 8

Refueling Boron Concentrations ....................... 9

R31

FORT CALHOUN STATIONTECHNICAL DATA BOOK

TDB-VIPAGE 5 OF 19

LIST OF FIGURES

Figure No.

1

2

3

4

5

6

7

8

9

Title Page

Thermal Margin/Low Pressure for 4 Pump Operation ....................................... 11

Power Dependent Insertion Limit ....................................... 12

Allowable Peak Linear Heat Rate vs. Burnup ............. .......................... 13

Excore Monitoring of LHR ....................................... 14

DNB Monitoring ....................................... 15

FR T and Core Power Limitations ....................................... 16

Axial Power Distribution LSSS for 4 Pump Operation ....................................... 17

Axial Power Distribution Limits for 4 Pump Operation with Incores Inoperable.. 18

Minimum Boric Acid Storage Tank Level vs. Stored Boric Acid Storage TankConcentration.................................................................................................... 19

R31

FORT CALHOUN STATION TDB-VITECHNICAL DATA BOOK PAGE 6 OF 19

CORE OPERATING LIMIT REPORT

1. INTRODUCTION

This report provides the cycle-specific limits for operation of the Fort Calhoun StationUnit 1 for Cycle 23 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 (APD)

* Shutdown Margin with TcOLD > 210'F

* Most Negative Moderator Temperature Coefficient

These limits are applicable for the duration of the cycle. For subsequent cycles the limitswill be reviewed and revised as necessary. In addition, this report includes a number ofcycle-specific coefficients used in the generation of certain reactor protective system tripsetpoints or allowable increases in radial peaking factors.

2. CORE OPERATING LIMITS

All values and limits in this TDB section apply to Cycle 23 operation. This cycle must beoperated within the bounds of these limits and all others specified in the TechnicalSpecifications.

This report has been prepared in accordance with the requirements of TechnicalSpecification 5.9.5. The list of references below are complete citations of topical reportsand include the report number, title, revision, date, and any supplements in accordancewith the basis for NRC approval of License Amendment No. 196 which eliminated thesespecific entries from Technical Specification 5.9.5. NRC approval of Amendment No. 196is consistent with the requirements of the Technical Specification Task Force, ImprovedStandard Technical Specification Change Traveler, uRevise Topical Report References inITS 5.6.5 COLR" (TSTF-363-A, Rev. 0). In accordance with this Traveler andAmendment No. 196, this information must be maintained within this TDB section.

R31

FORT CALHOUN STATION TDB-VITECHNICAL DATA BOOK PAGE 7 OF 19

The values and limits presented within this TDB section have been derived using theNRC approved methodologies listed below:

* OPPD-NA-8301, "Reload Core Analysis Methodology Overview," Rev. 8, datedAugust 2004. (TAC No. MC4304)

* OPPD-NA-8302, "Reload Core Analysis Methodology, Neutronics Design Methodsand Verification," Rev. 6, dated August 2004. (TAC No. MC4304)

* OPPD-NA-8303, "Reload Core Analysis Methodology, Transient and AccidentMethods and Verification," Rev. 6, dated August 2004. (TAC No. MC4304)

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

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

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

* ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels PWRDesign 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 forPressurized Water Reactors," October 1983.

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

* EMF-1 961 (P)(A), "Statistical Setpoint/Transient Methodology for CombustionEngineering Type Reactors," Revision 0, July 2000.

* 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 BoilingCorrelation for High Thermal Performance Fuel," March 1994.

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

* EMF-2087(P)(A), 'SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCAApplications," Revision 0, June 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 - MethodologyDescription, Volume 2- Benchmarking Results," Framatome ANP, Inc.,January 1997.

* EMF-2310(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized WaterReactors," Framatome ANP, Inc., Revision 1, May 2004.

R31

FORT CALHOUN STATIONTECHNICAL DATA BOOK

TDB-VIPAGE 8 OF 19

3. TMILP LIMIT

The TMI/LP coefficients are shown below:

Table 1 -TMILP Coefficients

Coefficient

a

13P

Value

29.6

20.63

-12372

The TM/LP setpoint is calculated by the PVAR equation, shown below and in Figure 1:

PvAR = 29.6 PF(B) Al(Y)B + 20.63TIN - 12372

PF(B) = 1.0= -0.008(B)+1.8= 1.4

A1 (Y) = -0.6666(Y1 ) + 1.000= +0.3333(Y 1) + 1.000

for B 2 100%for 50% < B < 100%for B < 50%

for Yj < 0.00for Y1 > 0.00

Where:B = High Auctioneered thermal (AT) or Nuclear Power, % of rated powerY = Axial Shape Index, asiuTIN = Core Inlet Temperature, 'FPVAR = Reactor Coolant System Pressure, psia

4. MAXIMUM CORE INLET TEMPERATURE

The maximum core inlet temperature (TIN) shall not exceed 545'F. This value includesinstrumentation uncertainty of ±2'F (Ref: FCS Calculation FC06292, 6/9/95).

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

5. POWER DEPENDENT INSERTION LIMIT

The power dependent insertion limit is defined in Figure 2.

R31

FORT CALHOUN STATIONTECHNICAL DATA BOOK

TDB-VIPAGE 9 OF 19

6. LINEAR HEAT RATE

The allowable peak linear heat rate is shown in Figure 3.

7. EXCORE MONITORING OF LHR

The allowable operation for power versus axial shape index for monitoring of LHR withexcore detectors is shown in Figure 4.

8. PEAKING FACTOR LIMITS

The maximum full power value for the integrated radial peaking factor (FRT) is 1.732.

9. DNB MONITORING

The core operating limits for monitoring of DNB are provided in Figure 5. This figureprovides the allowable power versus axial shape index for the cycle.

10. FRT AND CORE POWER LIMITATIONS

Core power limitations versus FRT are shown in Figure 6.

11. REFUELING BORON CONCENTRATION

The refueling boron concentration is required to ensure a shutdown margin of not lessthan 5% with all CEAs withdrawn. The refueling boron concentration must be at least1,900 ppm through the end of Cycle 22 operation and is valid until the beginning of corereload for Cycle 23.

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

Table 2 - Refueling Boron Concentrations

Cycle Average Burnup(MWD/MTU)

BOC

> 2,000

> 4,000

Refueling BoronConcentration (ppm)

2,141

2,014

1,900

R31

FORT CALHOUN STATION TDB-VITECHNICAL DATA BOOK PAGE 10 OF 19

12. AXIAL POWER DISTRIBUTION

The axial power trip is provided to ensure that excessive axial peaking will not cause fueldamage. The Axial Shape Index is determined from the axially split excore detectors.The setpoint functions, shown in Figure 7 ensure that neither a DNBR of less than theminimum DNBR safety limit nor a maximum linear heat rate of more than 22 kW/ft(deposited in the fuel) will exist as a consequence of axial power maldistributions.Allowances have been made for instrumentation inaccuracies and uncertaintiesassociated with the excore symmetric offset - incore axial peaking relationship. Figure 8combines the LHR LCO tent from Figure 4, the DNB LCO tent from Figure 5, and theAPD LSSS tent from Figure 7 into one figure for a visual comparison of the differentlimits.

13. SHUTDOWN MARGIN WITH Tcold > 210-F

Whenever the reactor is in hot shutdown, hot standby or power operation conditions, theshutdown margin shall be 23.6% Ak/k. With the shutdown margin <3.6% Ak/k, initiateand continue boration until the required shutdown margin is achieved.

14. MOST NEGATIVE MODERATOR TEMPERATURE COEFFICIENT

The moderator temperature coefficient (MTC) shall be more positive than-3.30 x 104 Ap/PF, including uncertainties, at rated power.

R31

FORT CALHOUN STATIONTECHNICAL DATA BOOK

TDB-VIPAGE 1 1 OF 19

590

LL

Li

w.11

0-:

UJI

H-iz

F-

z-J00

LILw00)

580

570

560

550

540

530

520

510

50060 70 80 90 100

CORE POWER (% OF RATED)

110 120

PVAR = 29.6 PF(B)A1(Y)B + 20.63TIN - 12372

PF(B) = 1.0

= -.008B+1.8

B 2 100%

50% < B < 100%

B < 50%

Al (Y) = -0.6666Y 1 + 1.000

= +0.3333Y, + 1.000

Y. < 0.00

Y. > 0.00

= 1.4

THERMAL MARGIN I LOW PRESSUREFOR 4 PUMP OPERATION

R31

FORT CALHOUN STATIONTECHNICAL DATA BOOK

TDB-VIPAGE 12 OF 19

I

z

I-

C',

Il0zU,

z0-F

M-0

CL

wC.,:

CY)

0Q(D

a-0

-126 (9

-100.8

-75.6

-50.4

-25.2

-0

-126

-100.8

-75.6

-50.4

-25.2

-0

I I ISHORT TERM

INSERTION LIMIT

7F[

. . .

I I ILONG TERM STEADY,'

INSERTION LIMIl-4-1-4-I

3TATE

..

x PDIL

PDIL or TRANSIENTINSERTION LIMIT

41

(104.5)(94.5)

(82.51

(N

0~

(D

(35.21

-126 (25.21

(13.2)

-100.8

-75.6

-50.4

-25.2

-0

-/ x. ' EMERGENCY BORATION LIMIT

12" BELOW PDIL - REFER TO AOP-3

a.

0Q(D

-126

-100.8

-75.6

-50.4

-25.2

-00 20 40 60 80

REACTOR POWER (% OF ALLOWED POWER)

100

R31

FORT CALHOUN STATIONTECHNICAL DATA BOOK

TDB-VIPAGE 13 OF 19

18

16

14

V 12

LU

w 10

IAd 8

z

J 6

4

2

I I IUNACCEPTABLE OPERATION

I I I

I I I

15.5 KW/FT

I I I

ACCEPTABLE OPERATION

0 5000 10000 15000 20000

BURNUP (MWD/MTU)

CYCLE23 ALLOWABLE PEAK LINEAR HEAT RATE FIGURECOLR VS. BURNUP 3

R31

FORT CALHOUN STATIONTECHNICAL DATA BOOK

TDB-VIPAGE 14 OF 19

110

100

90

w

3:

C)0

w0

0

0-J

LIL0I--z0wIli

80

70

60

50

40

30

20

10

0

-0.6 -OA -0.2 0.0 0.2 0.4 0.6

AXIAL SHAPE INDEX (ASIU)

CYCLE 23I. FIGURECOLR EXCORE MONITORING OF LHR I

R31

FORT CALHOUN STATIONTECHNICAL DATA BOOK

TDB-VIPAGE 15 OF 19

110

100

90

w00~

w

00

0r-J

-j

LL0

zwwa.

80

70

60

50

40

30

20

10

0

-1.0 -0.8 -0.6 -0.4 -0.2 0.0 02 0.4 0.6 0.8 1.0

AXIAL SHAPE INDEX (ASIU)

CYCLE23| DNB MONITORING FIGURECOLR | 5

R31

FORT CALHOUN STATIONTECHNICAL DATA BOOK

TDB-VIPAGE 16 OF 19

110

(1.732,100) 1 1100

w

Lu

0a.a-w0U0w

11.0-jU-

0F-zC.)w0uEL

90

80

70

60

50

\5,86(1.817,80)

40

30

20

10

0

1.70 1.75 1.80 1.85 1.90

PEAKING FACTOR

R31

FORT CALHOUN STATION TDB-VITECHNICAL DATA BOOK PAGE 17 OF 19

150

(0,140)140

130

120…_ -

110-*

w

-10 (-0.2,10) -0 -0 0 0.4,80.6 0 1.0

08

0~

z 4

11-50

AXIAL SHAPE INDEX (ASIU)

CCE23 AXIAL POWER DISTRIBUTION LSSS FIGURE.COLR FOR 4 PUMP OPERATION 7

R31

FORT CALHOUN STATION TDB-VITECHNICAL DATA BOOK PAGE 18 OF 19

150…--II-i---

140 … APD LSSS

130 ……

120…m-DNBR KW/FT

110 MONITORING…-MONITORING0 LIMIT LIMIT

o X100…M0~

L 90…

080 7

70

710----- -0. 04-0.2 -~ . . . . .

\,0

60----

U-

zWL 40--…

C-)

20…

10…

0…

-1.0 -0.8 -0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 0.8 1.0

AXIAL SHAPE INDEX (ASIU)

CYCLE 23 AXIAL POWER DISTRIBUTION LIMITS FOR 4 FIGURECOLR PUMP OPERATION WITH INCORES INOPERABLE 8

R31

FORT CALHOUN STATIONTECHNICAL DATA BOOK

TDB-VIPAGE 19 OF 19

100

90

80

I0-H

0

0z

zwl0wa--LJ

CO,

z

70

60

50 IX\LL HtN40

30

20

I

10

0

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 PPMIN SIRWT

X 1900 PPMIN SIRWT

* 2000 PPMIN SIRWT

* 2150 PPMIN SIRWT

+ 2300 PPMIN SIRWT

MINIMUM BAST LEVEL vs. STOREDBAST CONCENTRATION

R31