LIC-02-0058, Core Operating Limits Report, Revision 26
| ML021410176 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/03/2002 |
| From: | Ridenoure R Omaha Public Power District |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LIC-02-0058 | |
| Download: ML021410176 (21) | |
Text
Omaha Public Power District 444 South 16th Street Mall Omaha NE 68102-2247 May 3, 2002 LIC-02-0058 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Reference:
SUBJECT:
Docket No. 50-285 Transmittal of Fort Calhoun Station (FCS) Core Operating Limit Report (COLR) Revision 26 Pursuant to FCS Unit No. 1 Technical Specification 5.9.5.c, Omaha Public Power District is transmitting Revision 26 (dated May 1, 2002) of the FCS COLR. The COLR was revised to update the boron concentration to allow loading of the core for Cycle 21 and incorporate Technical Specification Amendment 203.
Please contact me if you have any questions.
Sincerely, Operations
Attachment:
TDB-VI - Technical Data Book - Core Operating Limit Report - Revision 26 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)
Employment with Equal Opportunity
Fort Calhoun Station Unit No. 1 TDB-VI TECHNICAL DATA BOOK
Title:
CORE OPERATING LIMIT REPORT FC-68 Number:
Reason for Change:
Requestor:
Preparer:
EC 29854 To update the boron concentration to allow loading of the core for Cycle 21 and include three additional references from Technical Specification Amendment No. 203 Thomas Heng Thomas Heng ISSUED: 05-01-02 3:00 pm R26
FORT CALHOUN STATION TECHNICAL DATA BOOK PROCEDURE TDB-VI PAGE 1 OF 19 Fort Calhoun Station, Unit I Cycle 20 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.
R26
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 R26
FORT CALHOUN STATION TECHNICAL DATA BOOK PROCEDURE TDB-VI PAGE 3 OF 19 LIST OF TABLES Table No.
Title 1
TM/LP Coefficients 2
Refueling Boron Concentrations Pagqe 7
9 R26
FORT CALHOUN STATION TECHNICAL DATA BOOK PROCEDURE TDB-VI PAGE 4 OF 19 LIST OF FIGURES Figure No.
Title 1
Thermal Margin/Low Pressure for 4 Pump Operation 2
Power Dependent Insertion Limit 3
Allowable Peak Linear Heat Rate vs. Burnup 4
Excore Monitoring of LHR 5
DNB Monitoring 6
BASSS Allowable Power 7
FRT and Core Power Limitations 8
Axial Power Distribution LSSS for 4 Pump Operation 9
Axial Power Distribution Limits for 4 Pump Operation with Incores Inoperable 10 Minimum Boric Acid Storage Tank Level vs.
Stored Boric Acid Storage Tank Concentration Page 10 11 12 13 14 15 16 17 18 19 R26
FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 5 OF 19 Cycle 20 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 20 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 20. 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 20 operation. Cycle 20 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)
R26
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 Bumup," 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 Setpoint/Transient Methodology for Combi~stion 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 TECHNICAL DATA BOOK PROCEDURE TDB-VI PAGE 7 OF 19 3.0 TM/LP Limit The TM/LP coefficients for Cycle 20 are shown below:
Table 1 TMILP Coefficients Coefficient a
13 Value 29.6 20.63 Y
-12372 The TM/LP setpoint is calculated by the PVAR equation, shown below and in Figure 1:
PVAR= 29.6 PF(B) AI(Y)B + 20.63TIN - 12372 PF(B)
= 1.0
= -0.008(B)+1.8
= 1.4 Al (Y)
= -0.6666(Y1) + 1.000
= +0.3333(Y1) + 1.000 for B >_ 100%
for 50% < B < 100%
for B < 50%
for Y1 *< 0.00 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 20 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.
R26
FORT CALHOUN STATION TECHNICAL DATA BOOK PROCEDURE TDB-VI PAGE 8 OF 19 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 20 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 20 is shown in Figure 4.
8.0 Peaking Factor Limits The Cycle 20 maximum full power value for the integrated radial peaking factor (FRT) is 1.732.
An additional dotted line exists on Figure 7 to allow operation in the presence of a hot leg flow streaming event with less than a 6% power difference between actual power and AT power indication.
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 20 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 20, 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 20.
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FORT CALHOUN STATION TECHNICAL DATA BOOK PROCEDURE TDB-VI 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 (MWD/MTU)
> 2,000
>4,000 Refueling Boron Concentration 2,155 2,023 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 TcoId > 210 OF Whenever the reactor is in hot shutdown, hot standby or power operation conditions, the shutdown margin shall be _4.0% Ak/k. With the shutdown margin <4.0% 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 0F, including uncertainties, at rated power.
R26 I I
FORT CALHOUN STATION TECHNICAL DATA BOOK PROCEDURE LL LLJ I
z 0
0 I
w 0
0 TDB-VI PAGE 10 OF 19 80 90 100 CORE POWER (% OF RATED)
PVAR = 29.6 PF(B)AI(Y)B + 20.63TIN - 12372 PF(B) = 1.0
= -.008B+1.8
= 1.4 B > 100%
50% < B < 100%
B < 50%
A1(Y) = -0.6666Y1 + 1.000
= +0.3333Y1 + 1.000 THERMAL MARGIN I LOW PRESSURE FOR 4 PUMP OPERATION 590 580 570 560 550 540 530 520 510 500 S.....
- 2150 psia
- 4.
4 4
.4 1-60 70 110 120 Y, < 0.00 Y, > 0.00 I
FIGURE I
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FORT CALHOUN STATION TECHNICAL DATA BOOK PROCEDURE z
w z
CO z
0 0
IL
- 0.
0 Q
C-,
03 0
(9.
T 0
-126
-100.8
-75.6
-50.4
-25.2 0
0
(.9 0
(9
-126
-100.8
-75.6
-50.4
-25.2
-0
-126
-100.8
-75.6
-50.4
-25.2
-0
-126
-100.8
-75.6
-50.4
-25.2
-0 (35.2)
(25.2)
(13.2) 0 TDB-VI PAGE 11 OF 19 LONG TERM STEADY STATE INSERTION LIMIT I
I __~
I__
I I__
SHR ERM INSERTION LIMIT PPDIL PDIL or TRANSIENT INSERTION LIMIT I
I I
EMERGENCY DURATION LIMIT 12" BELOW PDIL-REFER TO AOP-3 (104.5)
(94.5)
(82.5) 20 40 60 80 100 REACTOR POWER (% OF ALLOWED POWER)
R26 E
FORT CALHOUN STATION TECHNICAL DATA BOOK PROCEDURE 0
18 16 14 5000 10000 15000 TDB-VI PAGE 12 OF 19 20000 BURNUP (MWD/MTU)
CYCLE 20 ALLOWABLE PEAK LINEAR HEAT RATE FIGURE COLR VS. BURNUP 3
R26 UNACCEPTABLE OPERATION 15.5 KW/FT ACCEPTABLE OPERATION p
LL I
w z
12 10 8
6 4
0 t
I.
I I
I
FORT CALHOUN STATION TECHNICAL DATA BOOK PROCEDURE 110 100 90 w
0 (
w 0
0 w
0
-JJ 0
I z
w ILl 0
a--
80 70 60 50 40 30 20 10 0
-0.6
-0.4
-0.2 0.0 0.2 TDB-VI PAGE 13 OF 19 0.4 0.6 AXIAL SHAPE INDEX (ASIU)
CYCLE 20 EXCORE MONITORING OF LHR COLR 4
R26
FORT CALHOUN STATION TECHNICAL DATA BOOK PROCEDURE 110 100 w
- 0.
(U 0
-J
..J R:
0 L
z
- a.
O 0
wU 0,
90 80 70 60 50 40 30 20 10 0
-0.6 TDB-VI PAGE 14 OF 19
(-0.12,100)
(0.15,100)
(-0.5,64)
(0.5,64)
-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 DN13 MONITORING FIGURE 5
R26
FORT CALHOUN STATION TECHNICAL DATA BOOK PROCEDURE 110 100 90 w
0~
CL w
0 0 0
0
-J
-J 0
I-.
z w
w M
80 70 60 50 40 30 20 10 0
-0.6
-0.4
-0.2 TDB-VI PAGE 15 OF 19 0.0 0.2 0.4 0.6 AXIAL SHAPE INDEX (ASIU)
R26
FORT CALHOUN STATION TECHNICAL DATA BOOK PROCEDURE 110 100 90 ILl 0
0 a
0 W
o U.1
- a.
0 I-0*
Iz.
80 70 60 50 40 30 20 10 0
1.60 1.65 TDB-VI PAGE 16 OF 19 1.70 1.75 1.80 1.85 PEAKING FACTOR FRT Limit with no hot leg flow streaming event in progress FRT Limit if a hot leg flow streaming event is in progress with differences between actual power and AT power indication of less than 6% power CYCLE 20 COLR I FRT AND CORE POWER LIMITATIONS (1.628,100)
(1.732,100)
,(Q 1.659,86) 1.765,86)
(* 1.708,80)
\\
- Z
,(11.817,80)
"1~~
I I__________
______________________ ____________________________________I_
I FIGURE 7
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FORT CALHOUN STATION TECHNICAL DATA BOOK PROCEDURE 120 110 100 90 w
LU 0
0 (1.
w 0
.,J LL 0
L Z:
z w
0u wl 80 70 60 50 40 30 20 10 0
-0.8
-0.6
-0.4
-0.2 0.0 0.2 0.4 TDB-VI PAGE 17 OF 19 0.6 0.8 AXIAL SHAPE INDEX (ASIU)
AXIAL POWER DISTRIBUTION LSSS FOR 4 PUMP OPERATION R26
FORT CALHOUN STATION TECHNICAL DATA BOOK PROCEDURE 120 110 100 90 w
0 wL 0
IL
-J LL w
0 I-U a
uj 80 70 60 50 40 30 20 10 0
TDB-VI PAGE 18 OF 19 APD LSSS DNBR MONITORING LIMIT KWIFT MONITORING
/ !
-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 R26 i
i
- i i
i i
i i
i i
i i
i i
i
FORT CALHOUN STATION TECHNICAL DATA BOOK PROCEDURE 100 90 0
z z
w 0(
-J w
UJ
-J I
(/)
z<
80 70 60 50 40 30 20 10 0
TDB-VI PAGE 19 OF 19 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 IN SIRWT X 1900 PPM IN SIRWT
"+2300 PPM IN SIRWT MINIMUM BAST LEVEL vs. STORED BAST CONCENTRATION R26