ML20217Q542
| ML20217Q542 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/13/1997 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20217Q540 | List: |
| References | |
| NUDOCS 9709030191 | |
| Download: ML20217Q542 (18) | |
Text
. - _ _ _ - - -
Fort Calhoun Station Unit No.1-TDB-VI j
-TECHNICAL DATA BOOK 1
Title:
CORE OPERATING LIMIT REPORT FC48 Number: 50513
' Reason for Change: Revise refueling boron'conceritration value.
' Contact Person: M. Guinn K
+
9709030191 970825 PDR -ADOCK 050 25 ISSUED: 08-13-97 11:00 am R13-
FORT CALHOUN STATION TDB-VI
[L- TECHNICA1. DATA BOOK PROCEDURE'-
- . PAGE 1 OF 17 g--.
Fort Calhoun Station, Unit 1 Cvele 17 Core Operating Limits Rep 0d Pue 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.-
t R13-
F. ORT CALHOUN STATION TDB-Vi s- TECHNICAL DATA BOOK PROCEDURE PAGE 2 OF 17 4
TABLE OF CONTENTb lleg} Descriotion pagg 1,0 Introduction ,. 5 2.0 . Core Operailng Umits 5 3.0 _ TM/LP Umit .
6-4.0 Maximum Core inlet Temperature 6 5.0 Power Dependent insertion Umit 7 6.0 Unear Heat Rate 7 7.0 Excore Monitoring of LHR 7 Peaking Factor (FaT, F9T) Umits 8.0 7 9.0 DNB Mon!toring . 7 10.0 FnT, FnyT and Core Power Umitations 8 11.0 Refue!!ng Boron Concentratiori 8 12.0- Axlal Power Distribution 8 e
9
, ,= e .u . =-
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FORT CALHOUN STATION TDB-Vi TECHNICAL DATA BOOK PROCEDURE PAGE 3 OF 17 LIST OF TABLTS Table No. Ihlt Eage 1 TM/LP Coefficients 6 2-. Maximum Fna nd FnLimits 7 4
-s, g i
- - - = - - ' =
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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 4 OF 17 LIST OF FIGURES Figure No. Iltle P_ age 1- Thermal Margin / Low Pressure 4 Pump Operation 9 2 Power Dependent Insertion Limit 10 3 Allowable Peak Linear Heat Rate vs. Burnup 11 4 Excore Monitoring of LHR - 12 B DNB Monitoring 13 6 BASSS Allowable Power 14 T
7 Fa,FnTand Core Power Umitations 15 8 Axial Power Distribution LSSS for 4 Pump Operation . -- 16 9 Axial Power Distribution Um!ts for 4 Pump Operaton with incores Inoperable 17
. _ =
n ~ _= __
R13-
_,__m___________ - _ . - _ _ - - - - - - _ _ _
FORT CALHOUN STATION TDB-VI TECHNICAL. DATA BOOK PROCEDURE PAGE 5 OF 17 15 Cycle 17 Core Opgatina Limits Rego11 1.0 inirducilon This report provides the cycle-specific limits for operation of the Fort Calhoun Station Unit 1 for Cyclo 17 operation. It includos limits for:
1.) TM/LP LSSS 4 Pump Operation (PvAn) 2.) CoroinletTemperature (TIN) 3.) Power Dependent Insertion Limit (PDIL) 4.) Allowablo Peak Unear Heat Rate 5.) Excoro Monitoring of LHR .
0.) Planar Radial Radial Peaking n Factor (F T) l) 7.) Integrated Peaking Factor (Fn 8.) DNB Monitoring T
9.) Fn /F T9 versus Power Trade off curve 10.) Refuohng Boron Concentration 11.) Axlal Power Distribu'lon These limits are applicable for the duration of Cycle 17. 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 protectivo 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 17 operation. Cycle 17 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 Vorification" Rev. 4, dated December 1994. (TAC No. M89456)
OPPD-NA-8303, " Reload Coro Analysis Methodology, Transient and Accident Methods and Verification" Rev 04, dated January 1993. (TAC No, M85845)
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e 4 FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 6 OF 17 3.0 TM/LP Limit The TM/LP coefficients for Cycle 17 are shown below:
. Table 1 Coefficient Valut a 29.73 p 18.44 y - 11380 The TM/LP setpoint is calculated by the Pym equation, shown be!6w and in Figure 1:
Pym = 29.73 PF(B) A1(Y)B + 18.44 TIN - 11380 PF(B) = 1.0 B .P_100%
= -0.008B + 1.8 50% < B < 100%
= 1.4 B $ 50%
A1(Y) = -0.3529Ys + 1.0882 Yi s 0.25
= 0.5714Y1 + 0.857 Y$ > 0.25 Where:
B = High Auctioneered thermal (61) or Nuclear Power, % of rated power
-Y = Axial Shape Index, aslu TIN = Core inlet Temperature, F Pym = Reactor Coolant System Pressure, psla 4.0 Maximum core inlet Temperatuta ,
The maximum core inlet temperature (Ti s) for Cycle 17 shall not exceed 545'F.
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 GTATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 7 OF 17 5.0 Enw.tLDagendent insertion Limit The power dependent insertion limit is defined in Figure 2 for Cycle 17 operation.
6.0 Linear HgAtRait The a:lowable peak linea: rstq@"s. burnup for Cycle 171s 15.5 kW/ft. The allowable peak linear heat rate for Cycle 17 is shown w. i'igure 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 17 is shown in Figure 4.
8.0 Peaking Factor Limits The Cycle 17 maximum full power values for the unrodded planar radial peaking factor (FxyT) and integrated radial peaking factor (F RT) are shown in Table 2, Table 2 MAKlmum Full Power Fn andyF Limitt Peaking Factor Mmlit FnT 1.768 FxyT 1.876 9.0 DtHLManl10Ilng The Cycle 17 limits for DNB as a function of axial shape Index and core rower is shown in Figure S.
When the Better Axial Shape Selection System is operable, during Cycle 17, the core power is limited as a function of the axial shape index ac shown in Figure 6. Figure 6 will eliminate the need
. for separate LOCA and fuel performance limits to be maintained by the operators while operating with BASSS.
_. = _ _ _
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FORT CALHOUN STAllON TDB-Vi TECHNICAL DATA BOOK PROCEDURE PAGE 8 OF 17 4
10.0.EaT. F.~T and Cgte Power Limitationa Core power limitations versus FnT and FxyTare shown in Figure 7 for Cycle 17.
11.0 Befuelloa Baron Concentiallon The refueling boron concentration is required to ensure a shutdown margin of noi kss than 5%
with all CEAs withdrawn. The boron concentration requlted 1o achieve this conottion is 2: 00 ppm prior to reaching a Cycle 17 burnup of 3000 MWD /MTU. Once Cycle 17 burnup reaches 3000 MWD /MTV, the refueling boron concentration can be reduced to 1900 ppm.
12.0 Axial Power Dlatribution_
The axial power trip is provided to ensure that excessi/e axial peaking will not cause fuel damage.
The Axlal Shape Index is determined from the axially spilt excore detectors. The setpoint functions, shown in Figure 8 ensure that neither a DNBR of less than 1.18 nor a maximuin linear heat mte 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 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.
R13
)
FORT CALHOUN S(ATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 9 OF 17 590 ASI = -0.06 580 uf 570-
\ \
560 LU h \ \
2400 psla 2250 psla
\
~
s!
~
N ' 2100 psla s x o 530 0
0 -
1750 psia O
510 500 ' ' ' ' ' '
60 70 80 90 100 110 .120 BORE POWER (% OF RATED)
PVAR = 29.73PF(B)A1(Y)B + 18.44 TIN - 11380
= -- 008B + 1.8 50 .< B <100%
+' '
, y 5 5
= 1.4 B 550%
CYCLE 17 THERMAL MARGIN / LOW PRESSURE FIGURE COLR 4 PUMP OPERATION 1 R13
FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 10 OF 17 l l l l l LONG TERM STEADY STATE '****
- 100.8 INSERTION LIMIT _,
- (#5) y ,
(94.5)
, (82.5) o - 75.0 SHORT TERM '
[
\
- 126
- 50.4 INSERTION LIMIT
- ./'
PPDIL
,/
5 - 100.8 - 25.2 ,
J/
o ,
PDIL or TRANSIENT
[ " - 75.6 -0 ',
'*/,[ ' INSERTION LIMIT
)
e R .. W, -
b $ - 50.4
- E. , *j / EMERGENCY BORATION LIMIT (352) /
$ - 25.2 - 126 (25.2)
'/
12" BELOW PDil- REFER TO AOP-3 O (1s.2)
-0 - 100.8 O
o.
g E - 75.6 8
0
! - 50.4 0
b U - 126 - 25.2
- 100.8 - 0
[ - 75.6 8
b - 50.4
- 25.2
-0 0 20 40 60 80 100 REACTOR POWER (% OF ALLOWED POWER)
CYCLE 17 POWER DEPENDENT INSERTION LIMIT FIGURE COLR 2 R13 I
FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 11 OF 17
'8 i i UNACCEPTABLE OPERATION 16 15.5 KW/FT 14 ACCEPTABLE OPERATION 12
[
h 10 1
2 E 8 I
cc d
z
~3 4
0 1 0 5000 10000 15000 20000 BURNUP (MWD /MTU)
CYCLE 17 ALLOWABLE PEAK LINEAR HEAT RATE FIGURE COLR VS.BURNUP 3 R13
C TP CY EO CR O LC QWDOWZ& Ou. j_Jo3W oWW Q. O $ E HT L C N R 1E
. l I C CA _
7 1 N AL 1 2 3 4 6 7 8 9 1
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. FORT CALHObN STATION TDB-VI TECHNICAL DATA DOOK PROCEDURE PAGE 13 OF 17 110 (0.02,100) (0.15,100) m
(-0.17,90)
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Q- 20 --
10 0
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NOTE: WHEN BASSS IS OPERABLE, THIS FIGURE IS SUPERCEDED BY FIGURE 6 -
BASSS DNB ALLOWABLE POWER CYCLE 17 '
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. FORT CALHOUN STATION TDB-VI
, TECHNICAL DATA DOOK PROCEDURE PAGE 15 OF 17 110 -
FT R Exy T
100 -
- (1,708,100) r (1.876,100)
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1.75 1.80 1.85 1.90 1.95 2.00 2.05 2.10 PEAKING FACTOR CYCLE 17 FIGURE pnT, FxyT, AND CORE POWER LIMITATIONS COLR R13
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