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{{Adams
#REDIRECT [[LIC-06-0121, Transmittal of Fort Calhoun, Unit 1, Core Operating Limit Report (Colr), Revision 32]]
| number = ML062980548
| issue date = 10/24/2006
| title = Transmittal of Fort Calhoun, Unit 1, Core Operating Limit Report (Colr), Revision 32
| author name = Faulhaber H J
| author affiliation = Omaha Public Power District
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000285
| license number = DPR-040
| contact person =
| case reference number = LIC-06-0121
| document type = Fuel Cycle Reload Report, Letter
| page count = 20
}}
 
=Text=
{{#Wiki_filter:Omathi Publ~c Power Dfsfstnct 444 South 16th Street Mall Omahu NE 68102-2247 October 24,2006 LIC-06-0 12 1 U. S. Nuclear Regulatory Commissjoil Attn: Document Control Desk Washington.
DC: 20555
 
==Reference:==
 
Docket No. 59-285
 
==SUBJECT:==
Transmittal of Fort Calhoun Station Unit No. 1 (FCS) Core Operating Limit Report (COLR), Revision 32 Pursuant to FCS Technical Specification 5.9.5.q Revision 32 of the FCS COLR is enclosed.
Rcvision 32, issued on October 17, 2006, is updated for Cycle 24 operation.
If you have any questions, please contact Susan Baughn at (402) 533-721 5. Sincerely, &83& . J. F~U aber Division Manager Nuclear Engineering
 
==Enclosure:==
 
TDB-VI - Technical Data Book - Core Operating Limit Report - Revision 32 Employment with Equal Opportunity PAGE 1 OF 19 Fort Calhoun Station Unit 1 TDB-VI TECHNICAL DATA BOOK CORE OPERATING LIMIT REPORT Change No. Reason for Change Requestor Preparer Issue Date EC 38634 Update for Cycle 24 operation.
Julie Falter Daniel A Hochstein 10-17-06 3:00 pm FORT CALHOUN STATION TECHNICAL DATA BOOK TDB-VI PAGEZOF 19 Fort Calhoun Station, Unit I Core Operatins 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.
FORT CALHOUN STATION TECHNICAL DATA 800K TDB-VI PAGE 3 OF 19 TABLE OF CONTENTS & Description Page INTRODUCTION
.................................................................................................
6 CORE OPERATING LIMITS ..............................................................................
6 TMltP LIMIT .......................................................................................................
8 MAXIMUM CORE INLET TEMPERATURE
........................................................
8 POWER DEPENDENT INSERTION LIMIT .........................................................
8 LINEAR HEAT RATE ..........................................................................................
9 EXCORE MONITORING OF LHR ....................................................................
9 ................................................................................
PEAKING FACTOR LIMITS 9 DNB MONITORING
..................................................................................
9 .............................................................
F~~ AND CORE POWER LIMITATIONS 9 REFUELING BORON CONCENTRATION
.........................................................
9 AXIAL POWER DISTRIBUTION
.............................
.. ..................................
10 SHUTDOWN MARGIN WITH Tmld > 21 O°F ......................................................
10 MOST NEGATIVE MODERATOR TEMPERATURE COEFFICIENT
................
10 FORT CALHOUN STATION TECHNICAL DATA BOOK LIST OF TABLES TDB-VI PAGE 4 OF 19 TableNo. Pa~e ..............................................................................................
I TMlLP Coefficients 3 .........................................................................
2 Refueling Boron Concentrations 9
FORT CALHOUN STATION TECHNICAL DATA BOOK Fiqure No. Title TDB-VI PAGE 5 OF 19 LIST OF FIGURES Thermal MarginlLow 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 T FR and Core Power Limitations
.... .. .. .. .. .. .... ....... .... ... ... ..... . .. . ..... ,, ,. . . 16 Axial Power Distribution LSSS for 4 Pump Operation
.....,. .. .. ... .... .., ... . . . . IT Axial Power Distribution Limits for 4 Pump Operation with lncores Inoperable..
18 Minimum Boric Acid Storage Tank Level vs. Stored Boric Acid Storage Tank Concentration
.. .. . . . . . . . . .. . . . . . . . .
.. . . . . . . . . . . . . . ... . .. . . . . . . . . . . . . . . . . .. ... . . . . . . . . . . . . . . .. .. .. , . . . . . . . . -. . ... . 19 FORT CALHOUN STATION TECHNICAL DATA BOOK TDB-VI PAGE 6 OF 19 CORE OPERATING LIMIT REPORT INTRODUCTION This report provides the cycle-specific limits for operation of the Fort Calhoun Station Unit 1 for Cycle 24 operation.
It includes limits for:
I TMlLP LSSS for 4 Pump Operation (PVA~) Core Inlet Temperature (TIN) Power Dependent Insertion Limit (PDIL) Integrated Radial Peaking Factor (F~~) DNB Monitoring FR~ versus Power Trade-off Curve Refueling Boron Concentration
+ Axial Power Distribution (APD) Shutdown Margin with TcoLD > 21OVF 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.
CORE OPERATING LIMITS All values and limits in this TDB section apply to Cycle 24 operation.
This cycle must be I 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, titte, 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, "Revise 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.
FORT CALHOUN STATION TECHNICAL DATA BOOK TDB-VI PAGE7OF 19 The values and limits presented within this TDB section have been derived using the NRC approved methodologies listed below: OPPO-NA-8301, "Reload Core Analysis Methodology Qverview," Revision 8, dated 1 August 2004. (TAC No. MC4304) OPPD-NA-8302, "Reload Core Analysis Methodology, Neutronics Design Methods and Verification," Revision 6, dated August 2004. (TAC No. MC4304) I OPPD-NA-8303, "Reload Core Analysis Methodology, Transient and Accident Methods and Verification," Revision 7, dated August 2005. (TAC No. MC4304) I 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 DioxidelGadolinia Irradiation Examination and Thermal Conductivity Results," August 1985. ANF-88-133(P)(A) and Supplement 1, "Qualif cation of Advanced Nuclear Fuels PWR Design Methodology for Rod Burnups of 62 GWdlMTU," December 1991. EMF 1 16(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. EM F-1961 (P)(A). "Statistical Setpoinnransient Methodology for Combustion Engineering Type Reactors," Revision 0, July 2000. AN F-89-75 I (P)(A), "AN F-RELAP Methodology for Pressurized Water Reactors:
Analysis of Non-LOCA Chapter 15 Events," Revision 0, May 1992, EMF-92-153(P)(A), "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Revision 1, January 2005. 1 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), "SEMIPWR-98:
ECCS Evaluation Model for PWR LBLOCA Applications," Revision 0, June 1999. EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model, S-RELAPS Based," Revision 0, March 2001. I EM F-96-029(P)(A)
Volume 1, EM F-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," January 1997. I EMF-231 O(P)(A), "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," Revision 1, May 2004. I FORT CALHOUN STATION TECHNICAL DATA BOOK TDB-VI PAGE 8 OF 19 3. TMlLP LlMlT The TMlLP coefficients are shown below: Table 1 -TMILP Coefficients Coefficient a P Y Value 29.6 20.63 -1 2372 The TMlLP setpoint is calculated by the PVA~ equation, shown below and in Figure 1: PF(8) = 1.0 for B 2 100% = -0.008(B)+
1.8 for 50% < 0 < 100% = 1.4 for B 5 50% A1 (Y) = -O.6666(Y1)
+ 1.000 for Y1 s 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 TnIN = 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&deg;F. This value includes instrumentation uncertainty of G0F (Ref: FCS Calculation FC06292, 619195). 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.
FORT CALHOUN STATION TECHNICAL DATA BOOK TBB-VI 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 (F~~) 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. F~~ AND CORE POWER LIMITATIONS Core power limitations versus FR~ are shown in Figure 6. I 1 REFUELING BORON CONCENTRATION The refueling boron concentration is required to ensure a shutdown margin of not less than 5% with all CEAs withdrawn.
The refueting boron concentration must be at least 1,900 ppm through the end of Cycle 23 operation and is valid until the beginning of core reload for Cycle 24. Listed below in Table 2 are the refueling boron concentration values for Cycle 24 operations:
Table 2 - Refueling Boron Concentrations Cycle Average Burnup Refueling Boron IMWDjMTUl Concentration (ppm) BOG 2,141 2 2,000 2,014 2 4,000 1,900 FORT CALHOUN STATION TECHNICAL DATA BOOK TDB-VI 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 kWlft (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 LC0 tent from Figure 4, the DNB LC0 tent from Figure 5, and the APD LSSS tent from Figure 7 into one figure for a visual comparison of the different limits. Whenever the reactor is in hot shutdown, hot standby or power operation conditions, the shutdown margin shall be 23.6% Aklk. With the shutdown margin ~3.6% Aklk, 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 to4 ~pl"F, including uncertainties, at rated power.
FORT CALHOUN STATION TECHNICAL DATA BOOK TDB-VI PAGE 11 OF 19 590 LL 580 ui w 570 5 560 (L I ill 550 + ul 4 540 + Z 4 530 0 0 520 z 0 0 510 500 60 70 80 90 100 110 120 CORE POWER (Oh OF RATED) PVAR = 29.6 PF(B)AI(Y)B
+ 20.63TIN - 12372 PF{B) = 1 .O B 2 100% A1 (Y) = -0.6666Y 1 + 1.000 Y, 10.00 = -.008B+1.8 50% r B < 100% = +0.3333Yj
+ 1.000 Y1 > 0.00 = 1.4 B < 50% FIGURE I CYCLE 24 COLR THERMAL MARGIN 1 LOW PRESSURE FOR 4 PUMP OPERATION FORT CALHOUN STATION TECHNICAL DATA BOOK TDB-VI PAGE 12 OF 19 I LONG TERM STEADY STATE INSERTION LIMIT .. - - - C I INSERTION LIMIT , r' EMERGENCY BORATION LlMlT 12" BELOW PDlL - REFER TO AOP-3 1 26 100.8 1104 51 194.5) 182.51 5 135 2) 25.2 126 (25 2) 11 3.21 100.8 CO Z 0 P P 3 126 P 100.8 75.6 w U 50.4 25.2 0 0 2 0 4 0 6 0 8 0 10 0 REACTOR POWER (% OF ALLOWED POWER) CYCLE 24 COLR POWER DEPENDENT INSERTION LIMIT FIGURE 2 3RT CALHOUN STATION ECHNICAL DATA BOOK TDB-VI PAGE 13 OF 19 5000 I0000 15000 BURNUP (MWDIMTU)
UNACCEPTABLE OPERATION 15.5 KWIFT ACCEPTABLE OPERATION FIGURE 3 CYCLE 24 COLR ALLOWABLE PEAK LINEAR HEAT RATE VS. BURNUP FORT CALHOUN STATION TECHNICAL DATA BOOK TDB-VI PAGE 14 OF 19 110 100 w 80 w W m 0 e W fY 60 0 0 a 50 5 Sm A 4 LL 30 0 + $ 20 0 10 e 0 0.8 0.6 4.4 -0.2 0.0 0.2 0.4 0.6 0.8 AXIAL SHAPE INDEX (ASIU) CYCLE 24 COLR EXCORE MONITORING OF LHR FIGURE 4 FORT CALHOUN STATION TECHNICAL DATA BOOK TDB-VI PAGE 15 OF 19 110 I00 90 w 80 5 g 70 W w 0 0 60 P 5 0 50 4 J 4 % I- Z E w UJ L rn 10 0 10 a8 as a a2 ao a2 0.4 as a8 1.0 AXIAL SHAPE INDEX (ASIU) CYCLE 24 COLR DNB MONITORING FIGURE 5 FORT CALHOUN STATION TECHNICAL DATA BOOK TDB-VI PAGE 16 OF 19 110 100 K 90 $ O 80 e W w 0 70 0 0 60 0 4 50 4 LL O 40 + Z W 30 PL W e 20 10 0 1.70 1.75 1.80 I .85 1.90 PEAKING FACTOR FIGURE 6 CYCLE 24 COLR F~~ AND CORE POWER LlMlTATlONS FORT CALHOUN STATION TECHNICAL DATA BOOK TDB-V1 PAGE 17 OF 19 150 140 t30 120 w 110 5 100 0 n W 90 z 0 0 80 a 5 70 0 A 60 a LL 0 50 I- z W 40 0 [IL W 30 e 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 24 COLR AXIAL POWER DISTRIBUTION LSSS FOR 4 PUMP OPERATION FIGURE 7 FORT CALHOUN STATION TECHNICAL DATA BOOK TDB-VI PAGE 18 OF 19 MONITORING KWlFT MONITORING LIMIT 150 140 130 120 pI 110 I 0 100 e 90 0 8, a 5 70 0 J 60 Q: b 50 I- z W 40 0 w W n 30 20 I0 0 1.0 -0.8 0 -0.4 -0.2 0.0 0.2 0.4 0.6 0.8 1.0 AXIAL SHAPE INDEX (ASIU) CYCLE 24 COLR AXIAL POWER DISTRIBUTION LIMITS FOR 4 PUMP OPERATION WITH INCORES INOPERABLE FIGURE 8 FORT CALHOUN STATION TECHNICAL DATA BOOK TDB-VI PAGE 19 OF 19 100 90 80 ti 0 2 0 5 z 60 I t- 2 50 0 PI W e - 40 4 W > 30 b # Q m 20 E - 3 4 3 10 Z s 0 I -- 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 + 2000 PPM . 2150 PPM + 2300 PPM IN SIRW IN SlRWT IN SIRWT IN SIRW IN SIRW CYCLE 24 COLR MINIMUM BAST LEVEL vs. STORED BAST CONCENTRATION FIGURE 9}}

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