ML20249C565

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Rev 16 to TDB-VI, COLR for Fort Calhoun Station,Unit 1, Updating Cycle 18 Boron Concentration on Page 8 of 17
ML20249C565
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 03/30/1998
From: Guinn M
OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20249C561 List:
References
TDB-VI, TDB-VI-R16, NUDOCS 9806300338
Download: ML20249C565 (18)


Text

__. _ - _ _____ _ ___ __

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O . .. 1 Fort Calhoun Station Unit No.1 TDB-VI L

TECHNICAL DATA BOOK

Title:

CORE OPERATING LIMIT REPORT O

FC-68 Number: 50579-Reason for Change: Update for Cycle 18 boron concentration on page 8 of 17.

,l ' Contact Person: M. Guinn O

ISSUED: :03-30-98 3:40 pm R16 c ,

P- 4

FORT CALHOUN STATION TDB-Vi TECHNICAL DATA BOOK PROCEDURE PAGE 1 OF 17 0 . .

Fort Calhoun Station, Unit 1 Cycle 17 Core Ooerating 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.

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FORT CALHOUN STATION TDB-Vi TECHNICAL DATA BOOK PROCEDURE PAGE 2 OF 17 0 . .

TABLE OF CONTENTS

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llem Description Eag.e 1.0 Introduction 5 2.0 Core Operating Limits 5 3.0 TM/LP Umit 6 4.0 Maximum Core inlet Temperature 6 5.0 Power Dependent Ir.sertion Limit 7 6.0 Linear Heat Rate 7 7.0 Excore Monitoc:ng of LHR 7 8.0 Peaking Factor (F RT, ExyT) Limits 7 9.0 DNB Monitoring 7 10.0 T 8 Fn , FxyT and Core Power Limitations 11.0 Refueling Boron Concentration 8 12.0 Axial Power Distribution 8 O

O R16

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 3 OF 17 O . .

LIST OE TABLES Table No. Il1[g g 1

1 TM/LP Coefficients 6 I 2 Maximum FRand Fxy Limits 7 i

O R16

FORT CALHOUN STATION TDB-VI j TECHNICAL DATA BOOK PROCEDURE PAGE 4 OF 17

. . i LIST OF FIGURES l

l Floure No, Iltle Eage  !

1 Thermal Margin / Low Pressure 4 Pump Operation 9 l 2 Power Dependent Insertion Umit 10 l 3 Allowable Peak Linear Heat Rate I vs. Burnup 11 4 Excore Monitoring of LHR 12  ;

5 DNB Monitoring 13 6 BASSS Allowable Power 14 7 FaT, FxyT and Core Power Limitations 15  ;

8 Axial Power Distribution LSSS for 4 Pump Operation 16 .

)

9 Axial Power Distribution Umits ,

for 4 Pump Operation with incores inoperable 17

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4 i

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R16 O-___-___-___-___-___--_____

FORT CALHOUN STATION TDB-VI I TECHNICAL DATA BOOK PROCEDURE PAGE 5 OF 17 Cycle 17 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 17 operation. It includes limits for:

1.) TM/LP LSSS 4 Pump Operation (PVAP)  :

2.) CoreInletTemperature (Tm)  !

3.) Power Dependent insertion Limit (PDlL) 4.) Allowable Peak Linear Heat Rate 5.) Excore Monitoring of LHR T

6.) Planar Radial 7.) Integrated Peaking Radial Peaking Factor Factor (FR (Fxy ) I) 8.) DNB Monitoring T

9.) Fa /pxyT versus Power Trade off curve

'10.) Refueling Boron Concentration f~

. 11.) Axial Power Distribution i t l 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 protective system trip setpoints or allowable l I

increases in radial peaking factors.

2.0 Gnte Operating Limita 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 l- Verification" Rev. 4, dated December 1994. (TAC No. M89456) ,

OPPD-NA-8303, " Reload Core Analysis Methodology, Transient and Accident Methods and Verification", Rev. 04, dated January 1993. (TAC No. M85845) l i

R16

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 6 OF 17 0 . .

3.0 TM/LP Limit l

The TM/LP coefficients for Cycle 17 are shown below: l Table 1 Coefficient Valug a 29.73 p 18.44 y - 11380 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 s - 11380 PF(B) = 1.0 B A 100%

= -0.008B + 1.8 50% < B < 100%

~N = 1.4 B$50%

(O A1(Y) = -0.3529Yt + 1.0882 Y s 0.25 3

= 0.5714Y1 + 0.857 Yi > 0.25 l Where:

B = High Auctioneered thermal (AT) or Nuclear Power, % of rated power Y = Axial Shape Index, asiu TIN = Core inlet Temperature, F j PVAR = Reactor Coolant System Pressure, psia 4.0 Maximum Core inlet Temperature The maximum core inlet temperature (T IN ) for Cycle 17 shall not exceed 540* F. This value includes instrumentation uncertainty of *2*F (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 themal power step greater than 10% of rated thermal power,

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1 l

I FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 7 OF 17

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5.0 Power D.spendent insertion Limit I

i The power dependent insertion limit is defined in Figure 2 for Cycle 17 operation.' )

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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 l

The allowable operation for power versus axial shape index for monitoring of LHR with excore l l detectors for Cycle 17 is shown in Figure 4. i 8.0 Peaking Factor Limits rm  ;

U The Cycle 17 maximum full power values for the unrodded planar radial peaking factor (FnT) and integrated radial peaking factor (FnT) are shown in Table 2.

Table 2 Maximum Full Power Fo and yF Limits Peakina Factor Limlig T 1.717 Fn FyT 1.821 9.0 p_ND Monitoring t

The Cycle 17 !imits for DNB as a function of axial shape index and core power is shown in Figure 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

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for separate LOCA and fuel performance limits to be maintained by the operators while operating

(b' with BASSS.

R16

l FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 8 OF 17  :

i . .

10.0 FoT. FgT and Core Power Limitations Core power limitations versus FRT and F n T are shown in Figure 7 for Cycle 17.

I 11.0 Refueling Boron Concentration l l

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 17 operation and is valid until the beginning of core reload for Cycle 18.

Listed below are the refueling boron concentration values for Cycle 18 operations:

Cycle 18 Average Burnup Refueling Boron Concentration (MWD /MTU) (ppm) l l BOC 2,100 l

> 500 2,000 2 4,000 1,900 12.0 blal Power Distribution O

The axial power trip is provided to ensure that excessive axial peaking will not cause fuel damage, i 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 l maldistributions. Allowances have been made forinstrumentation inaccuracies and uncertainties l associated with the excore symmetric offset - incore axial peaking relationship. Figure 9 l combines the LHR LCO tent from Figure 4, the DNB LCO tent from F!gure 5, and the APD LSSS l tent from Figure 8 into one figure for a visual comparison of the different limits, l 1

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FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 9 OF 17 l

O 590 ASI = -0.06 580 570 '

E \ \ i m

560 x x x 2400 psia

p. 550 y 2250 psia

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[  % ' 2100 psia

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530 0 1 0 -

l m i h 1750 psia l 0 -

510

' ' ' ' I 500 ' '

60 70 80 90 100 110 120 CORE POWER (% OF RATED)

PVAR = 29.73PF(3)A1(Y)B + 18.44Tm - 11380 PF(B) =10 B 2.100%

A1(Y) = -0.3529Y i+ 1.088'e Yi s.25 l = .008B + 1.8 50%<B<100%

= 0.5714Y: + 0.857 Yi >.25

= 1.4 B $50%

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l . CYCLE 17 THERMAL MARGIN / LOW PRESSURE FIGURii COLR 4 PUMP OPERATION 1 R16

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 10 OF 17

- 126 I i i i i l l LONG TERM STEADY STATE l - 100.8 INSERTION LIMIT ,'

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/ EMERGENCY BORATION LIMIT 12" BELOW PDIL - REFER TO AOP-3 m

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REACTOR POWER (% OF ALLOWED POWER)

O CYCLE 17 POWER DEPENDENT INSERTION LIMIT FIGU9E COLR 2 R16

FORT CALHOUN STATION TDB-Vi TECHNICAL DATA BOOK PROCEDURE PAGE 11 OF 17 O - -

'8 i i i UNACCEPTABLE OPERATION 16 15.5 KW/FT 14 ACCEPTABLE OPERATION 12 L

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O CYCLE 17 ALLOWABLE PEAK LINEAR HEAT RATE FIGURE COLR VS.BURNUP 3 R16

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Operation Prohibited 90 -

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CY LE EXCORE MONITORING OF LHR CO R R16

FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 13 OF 17 110 (0.02,100) (0.15,100) 100 r E

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NOTE: WHEN BASSS IS OPERABLE, THIS FIGURE IS SUPERCEDED BY FIGURE 6 -

.O BASSS DNB ALLOWABLE POWER CYCLE 17 '

DNB MONITORING 5

. COLR R16 ,

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s FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 14 OF 17

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BASSS DNB ALLOWABLE POWER LCO 6 COLR l R16

4 FORT CALHOUN STATION TDB-VI )

TECHNICAL DATA BOOK PROCEDURE PAGE 15 OF 17 0 ."

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FIGURE mcj;e'7 , Fa T, FxyT, AND CORE POWER LIMITATIONS c ,

R16

9 FORT CALHOUN STATION TDB-VI TECHNICAL DATA BOOK PROCEDURE PAGE 16 OF 17 0 .

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CYCLE 17 AXIAL POWER DISTRIBUTION LSSS FIGURE COLR FOR 4 PUMP OPERATION 8 R16

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CYCLE 17 AX1AL POWER DISTRIBUTION LIMITS FOR 4 FIG l COLR PUMP OPERATION WITH INCORES INOPERABLE R16

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l Fort Calhoun Station Unit No.1 1

L TDB-VI l

TECHNICAL DATA BOOK

Title:

CORE OPERATING LIMIT REPORT l

l l

O

! FC-68 Number: 50580 l

l Reason for Change: Update for Cycle 18 operations.

l Contact Person: _M. Guinn L

o ISSUED: 04-22-98 4:00 am R17 l-4 l 8