ML20135A658
| ML20135A658 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/13/1996 |
| From: | Guinn M OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20135A648 | List: |
| References | |
| NUDOCS 9612030334 | |
| Download: ML20135A658 (18) | |
Text
. .-- . .
Fort Calhoun Station Unit No.1 9
TDB-VI TECHNICAL DATA BOOK
Title:
CORE OPERATING LIMIT REPORT FC-68 Number: 48543 Rea' son for Change:. Update for Cycle 17 Operations Contact Person: Marcus J. Guinn ISSUED: 11-13-96 2:00 am R12 9612030334 961125 PDR ADOCK 0500o285 l
P PDR j
.M e J sa -e- - a 48 a& w 0 -L- .s a a s 9-A>-- + *A -- - *a A--"a pu. -u-44+ n-J4-FORT CALHOUN STATION TDB-VI i 4
TEQHNICAL DATA BOOK PROCEDURE PAGE 1 OF 17 .
l 3 .
Fort Calhoun Station, Unit 1 i
Cycle 17 Core Operatina Limits Report l 2 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, Nuclear Engineering Department.
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FORT CALHOUN STATION -
TDB-VI l TECHNICAL DATA BOOK PROCEDURE PAGE 2 OF 17 .' i i
TABLE OF CONTENTS b
4
- llem Descriotion Paoe 4
1.0 ' Introduction 5
- 2.0 - Core Operating Limits 5 4-3.0 TM/LP Umit 6 ,
4.0 Maximum Core Inlet Temperature 6 l 5.0 Power Dependent insertion Umit 7 j
~
6.0 Linear Heat Rate 7
- l 7.0 Excore Monitoring of LHR 7 l 8.0 Peaking Factor (FRT, pyyT) Limits 7 r 9.0 DNB Monitoring 7 T
, 10.0 Fa , FxyT and Core Power Limitations 8 1 11.0 Refueling Boron Concentration 8 12.0 Axial Power Distribution 8 1
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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 3 OF 17 l LIST OF TABLES
?
Table No. Tde Page -
l I 1 TM/LP Coefficients 6 l 2 Maximum Fa and Fxy Limits 7 j ..
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e i
~
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l L -
FORT'CALHOUN STATION TDB-Vi TEQHNICAL DATA BOOK PROCEDURE PAGE 4 OF 17 .'
LIST OF FIGURES l
l Floure No. Iilla EaQR 1 Thermal Margin / Low Pressure 4 Pump Operation 9 2 Power Dependent insertion Umit 10 3 Allowable Peak Unear Heat Rate vs. Burnup
- 11 4 Excore Monitoring of'LHR 12 5 DNB Monitoring 13 6 BASSS Allowable Power 14 -
7 FaT, FxyTand Core Power Umitations 15 8 Axial Power Distribution LSSS for 4 Pump Operation 16 9 Axial Power Distribution Umits -
for 4 Pump Operation with'incores inoperable 17 R12
~ _ . _. _ -, _ _. _ _ . . _ - . - _ _ .. _ _ _ _ _ _ . . _.__..._
FORT CALHOUN STATION TDB-VI '
l_ .
TECHNICAL DATA BOOK PROCEDURE PAGE 5 OF 17 l y
) Cvelo'17 Core Operatina Limits Renort l
- j. '.
4 1.0 Introduction l 1
I This report provides the cycle-specific limits for operation of the Fort Calhoun Station Unit 1 for
' Cycle 17 operation It includes limits for:
l ,
l 1.) TM/LP LSSS 4 Pump Operation (PVAR) j 2.) CoreinletTemperature (TIN) !
3.) Power Dependent insertion Limit (PDIL) '
l 4.) Allowable Peak Unear Heat Rate
! 5.) Excore Monitoring of LHR 1 T)
~7.)6.)
~
PlanarRadial Integrated Radial Peaking Peaking FactorFactor T (Fxy(Fa )
i 8.) DNB Monitoring 9.) Fa%FxyT versus Power Trade off curve
- 10.) Refaeling Boron Concentration j - 11.) Aysal Power Distribution 3- .
These limits are applicable for the duration of Cycle 17. For subsequent cycles the limits will be l 1 d
- 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. ,
j ,
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 theTechnical SpecI i has been prepared in accordance with the requirements of Technical Specification 5.9.5. The l '
- values and limbs presented within this TDB section have been derived using the NRC approved methodologies listed below
- I i
OPPD-NA-8301, " Reload Core Analysis Methodology Overview" Rev. 6, dated December ;
{
- 1994. (l'AC No. M89455) l i
l OPPD-NA-8302," Reload Core Analysis Methodology, Neutronics Design Methods and l Verification" Rev. 4, dated December 1994. (TAC No. M89456)
OPPD-NA-8303, " Reload Core Analysis Methoc'dogy, Transient and Accident Methods and '
Verification", Fev. 04, dated Jancary 1993. (TAC No. M85845)
] ,
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FORT CALHOUN STATION TDB-Vi "
TECHNICAL DATA BOOK PROCEDURE PAGE 6 OF 17~ . l 3.0 TMILP Limit i i
~ The TM/LP coefficients for Cycle 17 are shown belovII:
l
. Table 1 Coefficient Value a 29.73 p 18.44 y - 11380 l l
The TM/LP setpoint is calculated by the PVAR equation, shown below and in Figure 1:
PVAR = 29.73 PF(B) A1(Y)B + 18.44 TIN - 11380 l PF(B) = 1.0 B 2.100%
= -0.008B + 1.8 50% < B < 100%
= 1.4 B s50% l I
A1(Y) = -0.3529Y$ + 1.0882 Y s 0.25 i i
= 0.5714Yi + 0.857 Yi > 0.25 l
\
Where:
- B" = High Auctioneered thermal (AT) or Nuclear Power, % of rated power Y . = Axlal Shape Index, aslu TIN .= CoreinletTemperature, F ,
PVAR = Reactor Coolant System Pressure, psia .
~
4.0 Maximum Core inlet Temperature The maximum core inlet temperature (TiN) for Cycle 17 shall not exceed 545'F. l )
This limit is not applicable during either a thermal power ramp in excess of 5% of rated therma j power per minute or a thermal power step greater than 10% of rated thermal power.
I R12
FORT CALHOUN STATION TDB-Vi
- TECHNICAL DATA BOOK PROCEDURE PAGE 7 OF 17 .
S.0 Power Dependent insertion Limit The power dependent insertion limit is defined in Figure 2 for Cycle 17 operation. l 6.0 Linear Heat. Rate ,
The allowable peak linear heat rate vs. burnup for Cycle 17 is 15.5 kW/ft. The allowable peak linear heat rate for Cycle 17 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 17 is shown in Figure 4. l 8.0 Peaking Factor Limits The Cycle 17 maximum full power values for the unrodded planar radial peaking factor (Fg) and l
. integrated radial peaking factor (F/) are shown in Table 2.
Table 2 ,
Maximum Full Power Fo and g F Limits Esakina Factor . Limits Ff 1.768 Fg 1.876 9.0 DNB Monitoring The Cycle 17 limits for DNB as a function of axial shape index and core poweris shown in Figure l .
5.
When the Better Axial Shape Selection System is operable, during Cycle 17, the core power is l 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 with BASSS.
R12 1
. 1
- FORT CALHOUN STATION
- TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 8 OF 17 .
10.0 FnT. p,_T and Core Power Limitations T
Core power limitations versus Fn and F T nare shown in Figure 7 for Cycle 17. [
11.0 Refueling Boron Concentration The refueling boron concentration must be maintained with a boron concentration of at leas't 2100 [
ppm in the reactor coolant system to ensure a shutdown margin of not less than 5% with all CEAs j- withdrawn.
J 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 1.18 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 inaccuracles 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.
i 1
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Y R12 l J
FORT CALHOUN STATION TDB-VI TE.CHNICAL DATA BOOK PROCEDURE PAGE 9 OF 17 .
2 590 ASI = -0.06 580 570 -
E \\
~
560 4
m x x x 2400 psia ,
y 2250 psia 540 N
- p. 2100 psia ;
1 2 _
1 5 530 s O :
O l 0 -
- W j
h 1750 psia j o -
j 510
)
l .
500 ' ' '
60 70 80 90 100 110 120 CORE POWER (% OF RATED) e PvAn = 29.73PF(B)A1(Y)B + 18.44 TIN - 11380 (B) = 1.0 B 2100%
A1(Y) = -0.3529Y: + 1.0882 Yi 5.25
= .008B + 1.8 50%<B<100% ,
= 1.4 B550%
CYCLE 17 THERMAL MARGIN / LOW PRESSURE FIGURE COLR 4 PUMP OPERATION 1 R12
FORT CALHOUN STATION TDB-VI !
TECHNICAL DATA BOOK PROCEDURE PAGE 10 OF 17 -
- 126 I I I I I LONG TERM STEADY STATE
(*'5)
'~~~~
- 100.8 INSERTION LIMIT ,-
W ,
(94.5) !
$ l ,' ,
(82.5) o - 75.6 l 8 l SHORTTERM '
\
- 126 - 50.4 l INSERTION LIMIT
, ./
PPDIL. ,
cc - 100.8 - 25.2 l
/
O l / PDIL or TRANSIENT !
h " - 75.6 -0 l
, f/,- ' INSERTION LIMIT it: -
4
$ 8 5 - 50.4
./ '
1
- ,/ / EMERGENCY BORATION LIMIT m
- 25.2 (35.2)
- 126 ps.a / / 12" BELOW PDIL - REFER TO AOP-3
-0 - 100.8 o
n.
g 2 - 75.6 o 8 O b - 50.4 6
0 - 126 - 25.2
- 100.8 - 0
[ - 75.6 8
$ - 50.4
- 25.2
-0 0 20 40 60 80 100 ,
REACTOR POWER (% OF ALLOWED POWER)
CYCLE 17 POWER DEPENDENT INSERTION LIMIT FIGURE l COLR 2 !
R12 1
j FORT CALHOUN STATION TDB-Vi TE.CHNICAL DATA BOOK PROCEDURE PAGE 11 OF 17 .
1 j
18
- UNACCEPTABLE OPERATION
! 16 1
15.5 KW/FT 1
1 14
- ACCEPTABLE OPERATION
]
12 l
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, f_ 10
! W i kE 8 !
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- 4 i
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i 0 5000 10000 15000 20000 i
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- BURNUP (MWD /MTU)
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CYCLE 17 ALLOWABLE PEAK LINEAR HEAT RATE FIGURE l COLR VS.BURNUP 3 l R12
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- FORT C'ALHOUN STATION TDB-VI j TECHNICAL DATA BOOK PROCEDURE PAGE 13 OF 17 .
110 l (0.02,100) (0.15,100) m
(-0.17,90)
/ \
(0.25,90)
! 90 O
- 0. / '
g 80 e
O >
Q 70 ,
O W (
'g 60 r O
J :
J 50
< \
4
[
(-0.5,45)
$ 40 (0.5,45) l--
Z '
W 30 O .
'tr W
E 20 10 0
- 0.6 -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 CY L DNB MONITORING COLR 5 R12
__ - _ __- . _ - - - . _ . . - . - -.. -_- -. . . - - - .- . ~ .
~
~
, FORT CALHOUN STATION TDB-VI TEQHNICAL DATA BOO
K. PROCEDURE
PAGE 14 OF 17
! 110 100 (-0.12,100) (0.15,100) g -
W / \
8" m ,
/ X s
e" O ) / N
\
- Q 70 O f i -
(-0.5,M) (0.5,%
60 i' O i
d 50
! 4
- 1.L.
j O 4o .
- F i
i Z W 30 l
i O i 'E
-W l E 20 10 0
-0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 AXIAL SHAPE INDEX (ASIU)
CY LE BASSS DNB ALLOWABLE POWER LCO 6 CO R R12
FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 15 OF 17 110 T T Fa 100 - (1.768,100) p$ (1.876,100)
\
\
\
90 (1.768,90) -- I
\
E \
m 80 3 (1.80,78) \
A 70 N \ i W % \
E \\ (1.93,65)
.h 60 (1.929,65) *%
O . '* s (2.06,55) g '
3 )
3a 50 l I
< l g 1 i O 40 l F I Z l W I O 30 i E I W I E I 20 j j I I I l l '
10 I i I
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O 1.75 1.80 1.85 1.90 1.95 2.00 2.05 2.10 ;
PEAKING FACTOR CYCLE 17 FIGURE p gT, p*T, AND CORE POWER LIMITATIONS 7 COLR R12
FORT CALHOUN STATION TDB-Vi TECHNICAL DATA BOOK PROCEDURE PAGE 16 OF 17 120 (0,112) 110 A
/\
. (. , 0) k (0.15,100) 100 '
E \
E O ** /[ \
/(
~
~
g 80 (-0.4,80) >\
(0.4,80) .
O O
Q 70 f Lu (
5 Q 60
)
J J
< 0 LL. (-0.6,50) (0.6,50)
O Z 40 Lu O
E 30 Lu D.
20 10 0 l
-0.8 - 0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 0.8 AXIAL SHAPE INDEX (ASIU)
CYCLE 17 AXIAL POWER DISTRIBUTION LSSS FIGURE COLR - FOR 4 PUMP OPERATION 8 R12
- '~ FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 17 OF 17 120 APD LSSS 110
^ -
DNBR MONITORING !
(
- f LIMIT
/
g' N )
Yv /
/
- O 8 f
[
( T
.n MONITORING 80 / ,
((
2 O
)
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S ( l \ ) \
S Q 60
/ 7
\ \
T k
J J
l 50 l
u.
O h Z 40
.m.
O E. . 30 W
Q.
20 10 l
l 0
-0.8 -0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 0.8 l l
AXIAL SHAPE INDEX (ASIU)
CYCLE 17 AXIAL POWER DISTRIBUTION LIMITS FOR 4 FIGURE COLR PUMP OPERATION WITH INCORES INOPERABLE 9 R12