ML20116B690
| ML20116B690 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 07/10/1996 |
| From: | Guinn M OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20116B689 | List: |
| References | |
| NUDOCS 9607300206 | |
| Download: ML20116B690 (19) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
o LIC-96-0100
, Attachment OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION UNIT NO. 1 CORE OPERATING LIMITS REPORT (COLR)
REVISION 10 R
k 9607000206 PDR 960722 "
P ADOCK 05000285 PDR g ~~
' ' ~ ~ '
Fort Calhoun Station Unit No.1 TDB-VI TECHNICAL DATA BOOK
Title:
CORE OPERATING LIMIT REPORT FC-68 Number: 47774 Reason for Change: Update Figure 4 (Excore Monitoring of LMR) and Figure 7 (F/,
FJ and Core Power Limitations) to reflect LMR LCO reanalysis to support plant operation above 90% power.
Contact Person: Marcus J. Guinn ISSUED: 07-10-96 4:00 pm R10
FORT CALHOUN STATION TDB-VI i
i TECHNICAL DATA BOOK PROCEDURE PAGE 1 OF 17 i
Fort Calhoun Station, Unit 1 l
Cvels 16 Core Operatina Limits Report l
l 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 Production Engineering Division.
l Nuclear Engineering Departrnent.
l
[
t I
i I
l 4
R10
FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 2 OF 17 i 1
TABLE OF CONTENTS l
llCm Descriotion EaQR 1.0 Introduction 5 2.0 Core Operating 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 l 8.0 Peaking Factor (FR T, p,y T) Umits 7 l
9.0 DNB Monitoring 7 10.0 T T ,
Fa,Fxy and Core Power Umitations 8 l 11.0 Refueling Boron Concentration 8 12.0 )
Axial Power Distribution 8 l
l R10
- . - - . - . . . . . . . . . ... .. - =-.. ...- - . . . . - .
l l
FORT CALHOUN STATION TDB-VI l .
TECHNICAL DATA BOOK PROCEDURE PAGE 3 OF 17 i
LIST OF TABLES i
l Table No. Illlt EaQA l
1 TM/LP Coefficients 6 2 Maximum Fa and Fxy Umits 7 l
1 i
l l
l l
l l
l l
- l. R10
r i l l l 1 l
l .
FORT CALHOUN STATION TDB-VI {
l .
TECHNICAL DATA BOOK PROCEDURE PAGE 4 OF 17 I i
l LIST OF FIGURES l
Fiaure No. Iilla Page 1 Thermal Margin / Low Pressure 1 4 Pump Operation 9 l 2 Power Dependent insertion Limit 10 ,
3 Allowable Peak Linear Heat Rate i vs. Bumup 11 l
4 Excore Monitoring of LHR 12 1 5 DNB Monitoring 13 6 BASSS Allowable Power 14 7 FsT, p Tand Core Power Umitations 15 7A FRT,F and Core Power Umitations l Wh n ICI System is Inoperable 16 ,
I 8 Axial Power Distribution LSSS
! for 4 Pump Operation 17 l
l I
l l
l 4
I R10
FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 5 OF 17
[ Cvels 16 Core Operatina Limits Report j
l 1.0 Introduction This report provides the cycle-specific limits for operation of the Fort Calhoun Station Unit 1 for.
Cycle 16 operation. It includes limits for:
1.) TM/LP LSSS 4 Pump Operation (PVAR) 2.) Core inlet Temperature (T is)
- 3.)' Power Dependent insertion Limit (PDIL) l 4.) Allowable Peak Linear Heat Rate 5.)' Excore Monitoring of LHR i T 6.) Planar Radial Peaking Factor (Fxy ) T 7.) Integrated Radial Peaking Factor (Fn )
! 8.) DNB Monitoring T T 9.) Fa /Fxy versus Power Trade off curve 10.) Refueling Boron Concentration 11.) Axial Power Distribution r
I These limits are applicable for the duration of Cycle 16. For subsequent cycles the limits will be l~ 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 Onoratina Limits All values and limits in this TDB section apply to Cycle 16 operation. Cycle 16 must be operated within the bounds of these limits and all others specified in the Technical Specifications. This report l has been prepared in accordance with the requirements of Technical Specification 5.9.5. The i values and limits presented within this TDB section have been derived using the NRC approved l methodologies listed below:
1
! 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)
[
i OPPD-NA-8303, " Reload Core Analysis Methodology, Transient and Accident Methods and Verification", Rev. 04, dated January 1993. (TAC No. M85845) l R10
FORT CALHOUN STATION TOB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 6 OF 17 2
i 3.0 TM/LP Limit 4
The TM/LP coefficients for Cycle 16 are shown below:
Table 1 Coefficient Value a 29.73 s 18.44 y - 11470
- The TM/LP setpoint is calculated by the PVAR equation, shown below and in Figure 1:
PVAR = 29.73 PF(B) A1(Y)B + 18.44Ti n - 11470 I
PF(B) = 1.0 B 2100%
= -0.008B + 1.8 50% < B < 100%
= 1.4 8 s 50%
A1(Y) = -C.3529Yi + 1.0882 Y, s 0.25
= 0.5714Y 3 + 0.857 Yi > 0.25 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 4.0 Maximum Core inlet Temoerature The maximum core inlet temperature (TIN) for Cycle 16 shall not exceed 545'F.
This ilmit is not applicable during either a thermal power ramp in excess of 5% of rated thermal j
power per minute or a thermal power step greater than 10% of rated thermal power. j R10
FORT CALHOUN STATION TDB-VI l
TECHNICAL DATA BOOK PROCEDURE PAGE 7 OF 17 l
l 5.0 Power Denendent insertion Limit The power dependent insertion limit is defined in Figure 2 for Cycle 16 operation.
l l
6.0 Linear Heat Rate The allowable peak linear heat rate vs. burnup for Cycle 16 is 15.5 kW/ft. The allowable peak linear heat rate for Cycle 16 is shown in Figure 3.
7.0 Excore Monitorina of LHR The allowable operation for power versus axial shape index for monitoring of LHR with excore 4
, detectors for Cycle 16 is shown in Figure 4.
6.0 Peakina Factor Limits The Cycle 16 maximum full power values for the unrodded planar radial peaking factor (FxyT ) and integrated radial peaking factor (FaT) are shown in Table 2.
Table 2 Mmvimum Full Power Fo and 7F Limits Peakina Factor Limits fatT 1.77 Fxy 1.86 9.0 DNB Monitorina l The Cycle 16 limits for DNB as a function of axial shape index and core power is shown in Figure
- 5.
l
( When the Better Axial Shape Selection System is operable, during Cycle 16, the core power is limited as a function of the axial shape index as 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 l with BASSS. l 1
1 i
R10
1 FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 8 OF 17 l
l 10.0 FJ. F yT and Core Power Limitations Core power limitations versus Fa7 and FxyT are shown in Figure 7 for Cycle 16. If the ICI System is declared inoperable, Figure 7 will be superceded by Figure 7A. l l
l 11.0 Refuelina Boron Concentration l
The refueling boron concentration must be maintained with a boron concentration of at least 2000 ppm in the reactor coolant system to ensure a shutdown margin of not less than 5% with all CEAs withdrawn.
12.0 Axial Power Distribution ,
i The axial power trip is provided to ensure that excessive axial peaking will not cause fuel damage.
l 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 1.18 nor a maximum linear heat rate J 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 i associated with the excore symmetric offset - incore axial peaking relationship. !
l r
I R10
FORT CALHOUN STATION TOB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 9 OF 17 l .
590 i
ASI = -0.D6 580 '
g LL LLI 570 560 A \
LLS CL _
\
2250 psia
! p 550 '
W
$ \ ' 2100 psia
! E 540 g w .
Z -
5 o 530 o ~ N 1750 psia l
CC 520 O
O .
510 500 ' ' '
l 60 70 80 90 100 110 120 l
l CORE POWER (% OF RATED)
PVAR = 29.73PF(B)A1(Y)B + 18.44 TIN - 11470 PF(B) = 1.0 B 2100%
= .008B + 1.8 50%<B <100%
- = 1.4 B $ 50%
4 l A1(Y) = -0.3529Y i + 1.0882 Yi 1 25
= 0.5714Y + 0.857 Yi >.25 I
.i 1.
CYCLE 16 THERMAL MARGIN / LOW PRESSURE FIGURE COLR 4 PUMP OPERATION 1 R10
FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 10 OF 17 I
, - 126
'~~'~
l - 100.8 LC'NG TIERM STEADVSTATE ,
INSERTfDN UMIT ,
o - 75.6 l ,
c I ,
- 126 - 50.4 INSERTIOPlUMr' , < '
$ - 100.8 - 25.2 l
$ I '
, PDIL or TRANSIE.NT b:
3:
M
- 75.6 -0 ! ,', ' '/,
, r INSE RTIOff UMir
$ o ,-
b - 50.4 ,- ,
EMERC,ENCY BORATION UMIT 95.2) ./ (12"IlELOVf PDIL - RE :ER TO AOF -3)
- 25.2 - 126 (25.2)
G -0 - 100.8 O
n.
! $ E - 75.6 O @
0" m 0 0 - 50.4
<C W
U
- 126 - 25.2 l - 100.8 - 0 i
[ - 75.6 i 8 b - 50.4
- 25.2 l
-0 0 20 40 60 80 100 REACTOR POWER (% OF ALLOWED POWER) 1 CYCLE 16 POWER DEPENDENT INSERTION LIMil FIGURE COLR 2 R10
l FORT CALHOUN STATION TOB-Vi TECHNICAL DATA BOOK PROCEDURE PAGE 11 OF 17 l
18 UNACCEPTABLE OPERATION 16 15.5 KW/FT 14 A CCEPTABLE OPERATION 12 l
10
! E m
)
4 = a k
=
I k
m 6
E a
4 0
0 5000 10000 15000 20000 BURNUP (MWD /MTU)
CYCLE 16 ALLOWABLE PEAK LINEAR HEAT RATE FIGURE COLR VS.BURNUP 3 R10
l
- l FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 12 OF 17 NOTE: Rodded operation is prohibited above 90% of Rated Thermal Power
( .12,100) (.05,100) :
100 ;7;; g j7 ms,w
)
a: , 1 e seesec l l 90 '14 801 ' L14-901
.26 ,80)[ (.26,80) 80 a
O l' (1.
! W 70 l E l O
O 60 O l g ,
3 O 50 a
J
<C E 40 O
1 Z
W 30 O
E W
Q. 20
, 10 0
.4 .2 0 .2 .4 AXIAL SHAPE INDEX (ASIU)
\
l l
CYCLE 16 FIGURE COLR EXCORE MONITORING OF LHR 4 R10
p--..-.--.. -- . . .
FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 13 OF 17 110 ,
i
~^ ' ' " ' I' ' *' ' "'
100 l
l 90 E
W g 80 .
O )
O.
70 f W
( .25 65) (0.:ts,ss)
O O 60 0
W g 50 0a J 40
<C IL O 30 W
Z 20 i
E i W
Q. 10 6
0
.4 .2 0 .2 .4 AXIAL SHAPE INDEX (ASIU)
NOTE: WHEN BASSS IS OPERABLE THIS FIGURE IS SUPERCEDED BY FIGURE 6 - BASSS DNB ALLOWABLE POWER DNB MONITORING FIGURE COLR R10
1 FORT CALHOUN STATION TDB-VI
, TECHNICAL DATA BOOK PROCEDURE PAGE 14 OF 17 110
!' i
( .12.100) (.12,100) 100 i
90 l K
= !
/
f \
g 80 o
O. l
(-o.28,65[ }(0.28,65)
O O 60 O '
W g 50 oi J 40 LL.
o ao I-Z W 20 O
K W
(1. 10 0
.4 .2 0 .2 .4 AXIAL SHAPE INDEX (ASIU)
IG COLR BASSS DNB ALLOWABLE POWER LCO 6 R10
. FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 15 OF 17 110
" *Y 100 1 (1.86,90)
E 90 1.lJ N g (1.77, 90) 80 N N g
W N (1.929,75) (2.055,75 [
E 70 I O l O
- O 60 W :
l N
! O 50
> J i
J i 4 IL 40
- O
! H Z 30 W
- 0 2 E 20 W
Q.
4 10 0
1.75 1.80 1.85 1.90 1.95 2.00 2.05 2.10 PEAKING FACTOR CYCLE 16 FIGURE COLR FaT, FxyT , and Core Power Limitations 7 a10
.m FORT CALHOUN STATION TDB-VI
, TECHNICAL DATA BOOK PROCEDURE PAGE 16 OF 17 NOTE: Rodded operation is prohibited above 90% of Rated Thermal Power 110 100 1
E (1.86,94 90 W N g (1.77, 90)
O 80 x N ( .92, 80)
W N (1.929,75) (2.055,755 E 70 O
U 1 l O 60 l W N
O 50 J
4 u,, 40 0
z 30 W
O E 20 W
l G-10 0
1.75 1.80 1.85 1.90 1.95 2.00 2.05 2.10 l PEAKING FACTOR i
i CYCLE 16 T T, and Core Power Limitations FIGUR ~
COLR Fn When , p$he ICI System is inoperable 7A R10
1
. FORT CALHOUN STATION TDB-VI
, TECHNICAL DATA BOOK PROCEDURE PAGE 17 OF 17 120
. (0.0, 112) 110 ^ i 100 ( '18 00) (*15 '100) l C
W I g 90 2 /y )\
m 80 II O
O 70
-0.3, tLS) ;0.3, 65 g 60 O l 3 50 u
O 40 H
Z W 30 0
E W
CL. 20 10 l
0 l
.4 -2 . 0 .2 .4 AXIAL SHAPE INDEX (ASIU) ,
CYCLE 16 Axial Power Distribution LSSS FIGURE COLR for 4 Pump Operation 8 aio