ML051940562

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Station,Technical Data Book TDB-VI, Rev. 31, Core Operating Limit Report.
ML051940562
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 06/30/2005
From:
Omaha Public Power District
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TDB-VI, Rev. 31
Download: ML051940562 (22)
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Text

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Fort Calhoun Station Technical Data Book Page 3 of 5 TDB I Document Document Title Revision/Date J

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 04-05-05 at 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 04-13-05 Temperature 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 04-13-05 Curves 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 05-19-05 Pressure 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 Book Page 5 of 5 TDB 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 06-23-05 Generators 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 Station Unit 1 TDB-VI TECHNICAL DATA BOOK CORE OPERATING LIMIT REPORT Change No. EC 36669 Reason for Change Add reference requirements consistent with Technical Specification Amendment No. 196.

Requestor Kevin Holthaus Preparer Kevin Holthaus Issue Date 06-30-05 3:00pm R31

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 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 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 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....................
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 STATION TDB-VI TECHNICAL DATA BOOK PAGE 4 OF 19 LIST OF TABLES Table No. Title Page 1 TM/LP Coefficients ........................ 8 2 Refueling Boron Concentrations ....................... 9 R31

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 5 OF 19 LIST OF FIGURES Figure No. Title Page 1 Thermal Margin/Low Pressure for 4 Pump Operation ....................................... 11 2 Power Dependent Insertion Limit ....................................... 12 3 Allowable Peak Linear Heat Rate vs. Burnup ............. .......................... 13 4 Excore Monitoring of LHR ....................................... 14 5 DNB Monitoring ....................................... 15 6 FRT and Core Power Limitations ....................................... 16 7 Axial Power Distribution LSSS for 4 Pump Operation ....................................... 17 8 Axial Power Distribution Limits for 4 Pump Operation with Incores Inoperable.. 18 9 Minimum Boric Acid Storage Tank Level vs. Stored Boric Acid Storage Tank Concentration.................................................................................................... 19 R31

FORT CALHOUN STATION TDB-VI TECHNICAL 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 Station Unit 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)
  • FRT versus Power Trade-off Curve
  • Refueling Boron Concentration
  • Axial Power Distribution (APD)
  • Most Negative Moderator Temperature Coefficient These limits are applicable for the duration of the cycle. 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. CORE OPERATING LIMITS All values and limits in this TDB section apply to Cycle 23 operation. This cycle 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 list of references below are complete citations of topical reports and include the report number, title, revision, date, and any supplements in accordance with the basis for NRC approval of License Amendment No. 196 which eliminated these specific entries from Technical Specification 5.9.5. NRC approval of Amendment No. 196 is consistent with the requirements of the Technical Specification Task Force, Improved Standard Technical Specification Change Traveler, uRevise Topical Report References in ITS 5.6.5 COLR" (TSTF-363-A, Rev. 0). In accordance with this Traveler and Amendment No. 196, this information must be maintained within this TDB section.

R31

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 7 OF 19 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. 8, dated August 2004. (TAC No. MC4304)
  • OPPD-NA-8302, "Reload Core Analysis Methodology, Neutronics Design Methods and Verification," Rev. 6, dated August 2004. (TAC No. MC4304)
  • OPPD-NA-8303, "Reload Core Analysis Methodology, Transient and Accident Methods and Verification," Rev. 6, dated August 2004. (TAC No. MC4304)
  • 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-1 961 (P)(A), "Statistical Setpoint/Transient Methodology for Combustion Engineering 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 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.
  • 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 1, May 2004.

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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 8 OF 19

3. TMILP LIMIT The TMI/LP coefficients are shown below:

Table 1 -TMILP Coefficients Coefficient Value a 29.6 20.63 13 P

-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 for B 2 100%

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

= 1.4 for B < 50%

A1 (Y) = -0.6666(Y1 ) + 1.000 for Yj < 0.00

= +0.3333(Y 1 ) + 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, 'F PVAR = Reactor Coolant System Pressure, psia

4. MAXIMUM CORE INLET TEMPERATURE The maximum core inlet temperature (TIN) shall not exceed 545'F. This value includes instrumentation 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 rated thermal power per minute or a thermal power step greater than 10% of rated thermal power.

5. POWER DEPENDENT INSERTION LIMIT The power dependent insertion limit is defined in Figure 2.

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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 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 with excore 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 figure provides 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 less than 5% with all CEAs withdrawn. The refueling boron concentration must be at least 1,900 ppm through the end of Cycle 22 operation and is valid until the beginning of core reload 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 Refueling Boron (MWD/MTU) Concentration (ppm)

BOC 2,141

> 2,000 2,014

> 4,000 1,900 R31

FORT CALHOUN STATION TDB-VI TECHNICAL 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 fuel damage. 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 the minimum 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 uncertainties associated with the excore symmetric offset - incore axial peaking relationship. Figure 8 combines the LHR LCO tent from Figure 4, the DNB LCO tent from Figure 5, and the APD LSSS tent from Figure 7 into one figure for a visual comparison of the different limits.

13. SHUTDOWN MARGIN WITH Tcold > 210-F Whenever the reactor is in hot shutdown, hot standby or power operation conditions, the shutdown margin shall be 23.6% Ak/k. With the shutdown margin <3.6% Ak/k, initiate and 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.

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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 11 OF 19 590 LL 580 Li 570 w.11 560 0-UJI 550 H

-i z 540 z

F- 530

-J 0

0 520 LIL w

0

0) 510 500 60 70 80 90 100 110 120 CORE POWER (% OF RATED)

PVAR = 29.6 PF(B)A1(Y)B + 20.63TIN - 12372 PF(B) = 1.0 B 2 100% Al (Y) = -0.6666Y 1 + 1.000 Y. < 0.00

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

= 1.4 B < 50%

THERMAL MARGIN I LOW PRESSURE FOR 4 PUMP OPERATION R31

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 12 OF 19

-126 . . .

I I I LONG TERM STEADY,' 3TATE INSERTION LIMIl (104.5)

-100.8 ..

1-4-I 41(94.5) a- -75.6 0

I I I SHORT TERM (82.51 INSERTION LIMIT x PDIL

-126 (9 -50.4 CY) 0 Q

(D

-100.8

-75.6

-25.2

-0 7F[

-/ x PDIL or TRANSIENT INSERTION LIMIT C',

-50.4 z . ' EMERGENCY BORATION LIMIT I (35.21 12" BELOW PDIL - REFER TO AOP-3 I- -25.2 -126 (25.21 Il (13.2) 0 z -0 -100.8 U, (N z 0~ -75.6 0

-F (D -50.4 0

M-CL

-126 -25.2 w: -100.8 -0 C.,

a. -75.6 Q

0 (D

-50.4

-25.2

-0 0 20 40 60 80 100 REACTOR POWER (% OF ALLOWED POWER)

R31

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 13 OF 19 18 I I I UNACCEPTABLE OPERATION 16 I I I I I I 15.5 KW/FT 14 I I I ACCEPTABLE OPERATION V 12 LU w 10 I

Ad 8 z

J 6

4 2

0 5000 10000 15000 20000 BURNUP (MWD/MTU)

CYCLE23 ALLOWABLE PEAK LINEAR HEAT RATE FIGURE COLR VS. BURNUP 3 R31

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 14 OF 19 110 100 90 w 80 70 w

0 60 3:

0 C) 0 50 0

-J 40 LIL 0

I-- 30 z

0 w 20 Ili 10 0

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

CYCLE 23I. FIGURE COLR EXCORE MONITORING OF LHR I R31

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 15 OF 19 110 100 90 80 w

0 0~ 70 w

0 60 0

0 r-J 50

-j LL 40 0

z w 30 w

a.

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)

CYCLE23l DNB MONITORING FIGURE COLR l 5 R31

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 16 OF 19 110 100 (1.732,100) 1 1 w 90 \5,86 Lu (1.817,80) 80 a.

0a-w 0 70 U

0 w 60 0

11.

-j 50 U-0 40 F-z C.) 30 w

0u EL 20 10 0

1.70 1.75 1.80 1.85 1.90 PEAKING FACTOR R31

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PAGE 17 OF 19 150 (0,140) 140 130 120_ -

110-*

w 08

-10 (-0.2,10)-0 -0 0 0.4,80.6 0 1.0 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-VI TECHNICAL DATA BOOK PAGE 18 OF 19 150--II-i---

140 APD LSSS 130 120m-DNBR KW/FT 110 MONITORING-MONITORING 0 LIMIT LIMIT o X100M 0~

L 90 0

80 7 70

\,0 60----

U-z WL 40--

C-) 710----- -0. 04-0.2 . -~ . . . .

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 FIGURE COLR PUMP OPERATION WITH INCORES INOPERABLE 8 R31

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

0 70 0

z 60 z

wl 0 50 IX\L w

a-

-LJ 40 L HtN 30 CO, 20 I

10 z

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 PPM X 1900 PPM

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