ML20196G058

From kanterella
Jump to navigation Jump to search
Rev 17 to COLR Cycle 13 for McGuire Unit 1
ML20196G058
Person / Time
Site: McGuire Duke energy icon.png
Issue date: 11/06/1998
From:
DUKE POWER CO.
To:
Shared Package
ML20196G051 List:
References
MCEI-0400-06-R17, MCEI-0400-46-01, MCEI-400-46-1, MCEI-400-6-R17, NUDOCS 9812070230
Download: ML20196G058 (44)
v • d • e


Text

. __ _ . _ _ . _ __ _ _ _ _

Page I cf 22 Revision 17 McGuire Unit 1 Cycle 13 .

Core Operating Limits Report Revision 17 November 1998 .

Calculation Number: MCC-1553.05-00-0274, Rev. 2 Duke Power Company l

i Date \

Prepared By:

hf - b lf((([

Checked By: dOW & Adiduu,  !!/GM6 v

v Checked By:

h.J kl [lkt g iIl6l98

. \

i Approved By: /2f/(fe/ - /fd/fr  :

I QA Condition 1 I

1 l

l NOTE The contents of this document have been reviewed to verify that no material herein either '

directly or indirectly changes or affects the results and conclusions presented in the 10CFR50.59 MlCl3 Reload Safety Evaluation (calculation file: MCC-1552.08-004284). '

9812070230 981123 i PDR ADOCK 05000369 i P PDR i

l

. - . ~ . .-. . - - . . . - ~ . - ._ - . .. . - _-- .. - - . . . - -

MCEI-0400-46 Page 2 of 22 '

Revision 17 i

McGuire 1 Cycle 13 Core Operating Limits Report .  !

IMPLEMENTATION INSTRUCTIONS FOR REVISION 17 '

I i

Revision 17 of the McGuire Unit 1 COLR updates this mport to be compliant with the -

i Improved Technical Specifications (ITS). This revision should be implemented concurrently with this micase ofITS. i t

l l

i h

i e

l ,

l  !

I l

l i

i l

l

i. l l l l

l l  :

i i k

.- . _ . _ - . - . .. - ~ _ . .-_

t

! MCEI-0400-46 l

!- Page 3 Cf 22 '

Revision 17 -

McGuire 1 Cycle 13 Core Operating Limits Report

\

j 1

' REVISION LOG I l

i Revision Efffective Date  !

Effective Panes COLR OriginalIssue May 24,1993 N/A M1C09  !

Revision 1 May 27,1993 N/A MIC09, Rev. I  !

Revision 2 Febmary 24,1994  ?

N/A M1C09, Rev. 2  !

t Revision 3 June 20,1994  !

N/A M1C09, Rev. 3 '

Revision 4 September 13,1994 i N/A MIC10 i t

Revision 5 October 18,1994 i

! N/A MICIO, Rev. I  !

l Revision 6 - October 24,1994 i i N/A MICIO, Rev. 2 i

Revision 7 June 26,1995 ,

N/A M1CIO, Rev. 3  :

Revision 8 November 28,1995  !

N/A MIC10, Rev. 4 '

Revision 9 December 14,1995  !

N/A MICI1  :

i Revision 10 Mamh 11,1996 N/A MIC11, Rev.1 l Revision 11 June 24,1996 l

! N/A MICil, Rev. 2 '

Revision 12 Febmary 13,1997 i i

e N/A MIC12

! i Revision 13 June 13,1997 i N/A MICl2, Rev. I l l Revision 14 July 08,1997 '

N/A MIC12, Rev. 2 Revision 15 Mamh 12,1998 N/A MIC12, Rev. 3 Revision 16 May 27,1998 1-21 MICl3 Revision 17 November 6,1998 1-22 M1C13, Rev 2*

l \

  • Revision 1 of the MICl3 COLR calculation file did not requim a revision to the COLR El. 1 i l 1

I l

l

! i I

MCEI-0400-46 4

Page 4 cf 22 Revision 17 McGuire I Cycle 13 Core Operating Limits Report .

INSERTION SHEET FOR REVISION 17 Remove pages Insert Rev.17 pages .

Pages 1-21 Pages 1-22 w .

a

MCEI-0400-46 I Page 5 of 22 Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report

' 1.0 - ' Core Operating Limits Report i

This Core Operating Limits Report (COLR) has been prepared in accordance with the requirements of the Technical Specification Limiting Conditions for Operation (LCO))

l from Section 5.6.5. ,  !

t i

The Technical Specifications that reference this report are listed below:

Technical Specifications Section Page l.1 Requirements for Operational Mode 6 2.1 5 3.1.1 Shutdown Margin  !

2.2 6 3.1.3 ModeratorTemperature Coefficient )

2.3 6 3.1.5 Shutdown BankInsertion Limit i 2.4 6 3.1.6 Control BankInsertion Limit  !

! 2.5 6 '

3.2.1 Heat Flux Hot Channel Factor 2.6 9 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor  :

2.7 14 3.2.3 Axial Flux Difference  !

2.8 15 t 3.3.1 Reactor Trip System Instrumentation Setpoint 2.9 17 3.5.1 Accumulators  !

2.10 19  !

3.5.4 Refueling Water Storage Tank 2.11 19 3.7.14 Spent Fuel Pool Boron Concentration 2.12 20 3.9.1 Refueling Operations - Boron Concentration 2.13 20 I The Selected Licensee Commitments that reference this report are listed below:

I SLC Section Selected License Commitment Section Page

{

16-15.3.1.2.5 Borated Water Source-Shutdown 2.14 21 16-15.3.1.2.6 Borated Water Source-Operating )

2.15 22 -

2.0 Operating Limits 1 The cycle-specific parameter limits for the specifications listed in section 1.0 are presented in i

the following subsections. These limits have been developed using NRC approved methodologies specified in Technical Specification 5.6.5.

2.1 Requirements for Operational Mode 6 The following condition is required for operational mode 6.

l I

2.1.1 The Reactivity Condition requirement for operational mode 6 is that kerrmust be less than, or equal to 0.95. j i

r I

i

i MCEl-040046 Page 6 cf 22

! Revision 17

! McGuire I Cycle 13 Core Operating Limits Report i 2.2 , Shutdown Margin -SDM (LCO 3.1.1) 2.2.1 Shutdown margin shall be greater than 1.3% AK/K in modes 1-4.

2.2.2 Shutdown margin shall be greater than or equal to 1.0% AK/K in mode E .

i 2.3 Moderator Temperature CoefTicient - MTC (LCO 3.1.3) I

! -- 2.3.1 The Moderator Temperature Coefficient (MTC) ILO Limits are:

l  !

The MTC shall be less positive than the upper limits shown in Figure 1. The BOC,  !

ARO, HZP MTC shall be less positive than 0.7E-04 AK/K/*F.  !

i l The limit.

EOC, ARO, RTP MTC shall be less negative than the -4.lE-04 AK/K/ Flower MTC l

2.3.2 The 300 ppm MTC Surveillance Limit is:

i The measured 300 PPM ARO, equilibrium RTP MTC should be less negative than or l

equal to -3.2E-04 AK/K/ F. l 1 s t

2.3.3 The 60 PPM MTC Surveillance Limit is:  !

The 60 PPM ARO, equilibrium RTP MTC should be less negative than or equal to '

-3.85E-04 AK/K/*F.

l l

Where: . BOC = Beginning of Cycle EOC = End of Cycle ARO = All Rods Out '

HZP = Hot Zem Thermal Power RTP = Rated Thermal Power i

PPM = Parts per million (Bomn) '

2.4 Shntdown Bank Insertion Limit (LCO 3.L5) 2.4.1 Each shutdown bank shall be withdrawn to at least 222 steps.

2.5 Control Bank Insertion Limits (LCO 3.1.6) i i

l 2.5.1 Control banks shall be within the LCO insertion, sequence, and overlap limits shown in Figure 2.

I i

MCEI-040046 Page 7 of 22 Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report l

i Figure 1 Moderator Temperature Coefficient Upper Limit Versus Power Level 1.0 i

, 0.9 --

g Unacceptable Operation

  • c 0.8 --

0.7 2 0.6 -- '

5g E o 0.5 --

EE E

$ get '0.4 -- Acceptable Operation gC 0.3 --

! 0.2 --

T E 0.1 --

0.0  ;  ;  ;  ;  :  ;  ;  ;  ;

O 10 20 30 40 50 60 70 80 90 100 1 i

Percent of Rated Thermal Power '

NOTE: Compliance with Technical Specification LCO 3.1.3 may requi;e rod withdrawal limits. Refer to OP/1/A/6100/22 Unit 1 Data Book for details, l

l l

l MCEI4400-46 Pcge 8 of 22 Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report  !

l l Figure 2 Control Bank Insertion Limits Versus Percent Rated Thermal Power l l

\

i (Fully Withdrawn min - 222, max - 231) 240 (216%,231)

,p g l 220 - - -- -- - , ,, ,, ,, ,, (80.0 %,231) t '

j 200 ,

l 180 -

Bank B ,

l 160 -

' (100%.161) l Rod j (0%,163)j ,

140 - '

i insertion ,

Position 120 / Bank C - l (Steps - '

Withdrawn) l '

- /

B0 ,

60 ,' '

'/

Bank D 40 '

j (0%,47) l ,

20 l j~ (30% 0) j 0

O 10 20 30 40 50 60 70 80 90 100 (Fullyinserted)

Relative Power (Percent) 1

? l NOTE: Compliance with Technical Specification LCO 3.1.3 may require rod withdrawal limits. Refer to OP/1/A/6100/22 Unit i Data Book for details.

R l

7. . .

i MCEI-0400-46 Page 9 of 22 Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report i

2.6 Heat Flux Hot Channel Factor - FQ(X,Y,Z) (LCO 3.2.1) 2.6.1 Fn(X,Y,Z) steady-state limits are defined by the following relationships:

F *K(Z)/P for P > 0.5 Q 1 F *K(Z)/0.5 q for P s 0.5 i

whem, j

P = (Thermal Power)/(Rated Power) <

- Note: ,

The measund Fo(X,Y,Z) shall be increased by 3% to account for manufacturing tolerances and 5% to account for measurement uncertainty when comparing against the ILO limit. The manufacturing tolerance and measurement uncertainty are implicitly included in the Fq surveillance limits '

as defined in Sections 2.6.5 and 2.6.6. '

2.6.2 F = 2.50 x K(BU)

Q 2.6.3  :

K(Z) is the normalized FQ(X,Y,Z) as a function of core height for MkBW fuel and is provide:iin Figure 3.

2.6.4 K(BU) is the normalized FQ(X,Y,Z) as a function of burnup for MkBW fuel and is  !

1 provided in Figure 4. I l

The following parameters are required for core monitoring per the Surveillance Requirements of Technical Specification LCO 3.2.1:

2.6.5 F (X,Y,Z)OP = F (X,Y,Z) x Mg(X,Y,Z)/(UMT x MT x TILT) where:

F (X,Y,Z)OP = cycle dependent maximum allowable design peaking factor which ensures that the FQ(X,Y,Z) limit will be preserved for operation I:

l

_ _ _ _ _ _ _ _ - - - - - - - - - - - - - -- q MCEI4400-46 Page 10 of 22 Revision 17 McGuire 1 Cyc!e 13 Core Operating Limits Report within the LCOlimits, h(X,Y,Z)OP q includes allowances for calculational and measurement uncenainties.

(X,Y,Z) = design power distribution for 9 FQ. F (X,Y,Z) is provided in Table 1,

~

  • Appendix A, for normal operating conditions and in Table 2, Appendix A for power escalation testing during initial startup operation.

MQ(X,Y,Z) = margin remaining in core location X,Y,Z to the LOCA limit in the transient power distribution. MQ(X,Y,Z) is provided in Table 1, Appendix A for normal operating conditions and in Table 2, Appendix A for power escalation testing during initial stanup operation.

UMT = Total Peak Measurement Uncenainty, = 1.05.

MT= Engineering Hot Channel Factor, = 1.03.

TILT = Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02.

(TILT = 1.035)

NOTE: h(X,Y,Z)OP q is the parameteridentified as q (X,Y,Z) in DPC-NE-2011PA.

2.6.6 h(X,Y,Z)RPS q =

(X,Y,Z) x (MC(X,Y,Z)/(UMT x MT x TILT))

where:

h(X,Y,Z)RPS q =

cycle dependent maximum allowable design peaking factor which ensures that the centerline fuel melt (CFM) limit will be preserved for operation within the LCO limits. h(X,Y,Z)RPS q

includes allowances for calculational and measurement uncertainties.

F9(X,Y,Z) = design power distributions for FQ. F (X,Y,Z)is provided in Table 1, 9

Appendix A for normal operating conditions and in Table 2, Appendix A for power escalation testing during initial stadup operation.

\_ .. .

Page 1I of 22 f

Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report MC(X,Y,Z) = margin remaining to the CFM limit in com location X,Y,Z from the transient power distribution. CM (X,Y,Z) calculations parallel the MQ(X,Y,Z) calculations described in DPC-NE-201 IPA, except that the LOCA limit is replaced with the CFM limit. C M (X,Y,Z) is -

provided in Table 3, Appendix A for normal operating conditions and in Table 4, Appendix A for power escalation testing during initial startup operation.

UMT = Total Peak Measurement Uncertainty, = 1.05.

MT= Engineering Hot Channel Factor, = 1.03.

TILT = Factor to account for a peaking increase due to'the allowed quadrant po tilt ratio of 1.02. (TILT = 1.035).

NOTE: k('X,Y,Z)RPS is the parameteridentified as g q (X,Y,Z) in DPC-NE-2011PA, except that MQ(X,Y,Z) is replaced by MC(X,Y,Z).

2.6.7 KSLOPE = 0.0725 KSLOPE is the adjustment to1 the K value from OTAT trip setpoint mquired to compensate for each 1% that Ff (X,Y,Z) exceeds q(X,Y,Z)RPS,

_. .. . .- - . - . - - _ - _ = = - .. _ ._.

MCEI-0400-46 ...

Page 12 of 22 l Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report Figure 3 q

d K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for MkBW Fuel -

1.00  ::

0.90 - (0010)

(12.0,1.0) 0.80 --

,_., 0.70 --

ti W 0.60 --  :

1

,3 0 .50'--

a

@ 0.40 --

C Z ' O.30 -- .

0.20 --

0.10 -- i' O.00  :  :  :  :  :  :-

0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft.)

I

?

l i

I e

l-1 l

l

. - - - .- . . - . . - . ~ . _ - .- . . _ _ - - _ _ _ _ , _ - , = _ _ - .

MCEIh6 Page 13 of 22 l Revision 17 ,

McGuire 1 Cycle 13 Core Operating Limits Report Figure 4 K(BU), Normalized FQ(X,Y,Z) as a Function of Burnup for MkBW Fuel -

1.000  :: _

0.900 -- (0,1.0) (30.0,1.0)

(45.0.0.98) 0.800 --

I

$ 0.700 -- (60.0.0.792)

B g 0.600 --  ;

0 500 -- .

g 0.400 --

$ 0.300 -- l t

0.200 -- l 0.100 -- +

0.000  :  ;  ;  ; ,,

0 10 20 30 40 50 60 Burnup (GWD/MTU)

L

. Page 14 of 22  !

Revision 17 l

McGuire 1 Cycle 13 Core Operating Limits Report t

2.7 ? Nuclear Enthalpy Rise Hot Channel Factor - F AH(X,Y) (LCO 3.2.2) l

'The Fyg steady-state limits referred to in Technical Specification L! ..

the following relationship.

i l

L. i 2.7.1 F '

AH(X,Y)LCO = MARP (X,Y) x [1.0 + (1/RRH) x (1.0 - P)] i i

where:

F (X,Y)LCO is def'med as the steady-state, maximum allowed radial peak.

b MARP(X,Y) = Cycle-specific operating limit Maximum Allowable Radial Peaks.

[

MARP(X,Y) radial peaking limits are provided in Table 7, Appendix A.  !

p, Thermal Power i Rated Thermal Power RRH = 3.34 when 0.0 < P s 1.0, and i

2RH = Thermal Power reduction required to compensate for each 1% that the i

measured radial peak,F (X,Y), exceeds the limit.

The following parameters are required for core monitoring per the Surveillance requirem of Technical Specification LCO 3.2.2.  !

2.7.2 F g(X,Y)SURV = F (X,Y) x My3(X,Y)/(UMR x TILT) I i

where: '

F H(X,Y)SURV =

cycle dependent maximum allowable design peaking factor which ensures that the FAH(X,Y) limit will be preserved for operation within the LCO limits. F (X,Y)SURV includes allowances for calculational and measurement uncertainty.

- c -

,,m ,

- - -. .- .. .. . . . . - . - - . .- =

Page 15 of 22 Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report k F (X,Y) =

the design power distribution for FAH.F (X,Y)is provided in Table 5, Appendix A for normal operation and in Table 6, '

Appendix A for power escalation testing during initial startup operation.

MAH(X,Y) =

the margin remaining in core location X,Y relative to the Operational DNB limits in the transient power distribution.

M AH(X,Y) is provided in Table 5, Appendix A for normal operation and in Table 6, Appendix A for power escalation testing during initial startup operation.

UMR=

Uncertainty value for measured radial peaks, = 1.04.

TILT = .

Factor to account for a peaking increase due to the allowed quadrant tilt ratio of 1.02. (TILT = 1.035).

NOTE: F (X,Y) SURV is the parameter identified as PhAX (X,Y) in DPC-NE-201 IPA.

2.7.3 RRH = 3.34 when 0.0 < P s 1.0, i

where:

i 1

l l RRH = Thermal Power reduction required to compensate for each 1% that the measured radial peak, F (X,Y) exceeds its limit.

{

l i

2.7.4 TRH = 0.04 where:

l TRH = i l

Reduction in OTAT K setpoint 1 required to compensate for each 1% that i

the measured radial peak, F (X,Y), exceeds the linit.

2.8 Axial Flux DifTerence - AFD (LCO 3.2.3) 2.8.1 The Axial Flux Difference (AFD) Limits are provided in Figure 5.

l I

1

Page 16cf 22 R: vision 17 McGuire I Cycle 13 Ctre Operating Limits Report Figure 5 i

I Percent of Rated Thermal Power Versus Percent Axial Flux Difference Limits  :

l lL" 110 --

U l (-18.100)l .mm g ._ )

A (+10,100) l 90 --

l Unacceptable operation l 80 --

  • )

70 h .

l Unacceptable operation l l 60 -- l' W l Acceptable operation l 50 --

Ct o l (-36.50)] 40 .

l (421.50)l j 30 -- '

$ 20 --

A 10 --

n .

-50 -40 -30 -20 -10 0 10 20 30 40 50 .

Axial Flux Difference (% Delta I) l l NOTE: Compliance with Technical Specification LCO 3.2.1 may require more restrictive AFD limits. Refer to OP/1/A/6100/22 Unit i Data Book for details.

i I

I I l

I

Page 17 of 22 Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report 2.9 Reactor Trip System Instrumentation Setpoints (LCO 3.3.1) Table 3.3.1 1 2.9.1 Overtemperature AT Setpoint Parameter Values I

Parameter Value l Overtemperature AT reactor trip setpoint K 1s1.1978 Ovenemperature AT reactor trip heatup setpoint K2 = 0.0334/0F  !

penalty coefficient s

Ovenemperature AT reactor trip depressurization K3 = 0.001601/ psi setpoint penalty coefficient Time constants utilized in the lead-lag compensator tg 2 8 sec.

forAT T2 s 3 sec.

Time constant utilized in the lag compensator for AT T3 s 2 sec.

Time constants utilized in the lead-lag compensator T42 28 sec.

for T..,

T5 s 4 sec.

)i Time constant utilized in the measured T. , lag t6 s 2 sec.

compensator f 1(AI) " positive" breakpoint = 19.0 %AI f 1(AI) " negative" breakpoint = N/A*

f 1(AI) " positive" slope = 1.769 %ATo/ %Al i

f 1(AI)" negative" slope = N/A*

The f t(AI) ." negative" breakpoint and the fg(AI) " negative" slope are not applicable since the ft (Al) function is not required below the ft(AI) " positive" breakpoint of 19.0% Al.

l l

l. ,

i l

L

' a.sw-u,uu-,u

~

Page 18 cf 22 Rzvision 17

. McGuire 1 Cycle 13 Core Operating Limits Report

- 2.9.2, Overpower AT Setpoint Parameter Values Parameter Valut Overpower AT reactor trip setpoint - K4s1.086359 -

Overpower AT reactor trip heatup setpoint penalty coefficient K6= 0.001179FF Time constants utilized in the lead-lag

~

T1 2 8 sec.

compensator for AT T2s 3 sec.

2-Time constant utilized in the lag

. T3 s 2 sec.

compensator for AT

' Time constant utilized in the measured Tavs - T6s 2 sec.

lag bompensator Time constant utilized in the rate-lag T72 5 sec.

controller for T,y,

- f2 (AI) " positive" breakpoint = 35.0 %AI f 2(AI) " negative" breakpoint = -35.0 %AI f 2(AI) " Positive" slope

= 7.0 %AT/ %Al f 2(AI) " negative" slope - = 7.0 %ATg %AI

. ...~o,..,o Page 19 of 22 Revision 17 McGuire 1 Cycle 13 Core Operating Limits Report 2.10 ' Accumulators (LCO 3.5.1) 2.*0.1 Boron concentration limits during modes I and 2, and mode 3 with RCS pressure

>1000 psi: .

Parameter Limit Cold Leg Accumulator minimum boron concentration. 2,475 ppm Cold leg Accumulator maximum boron concentration. 2,875 ppm

~

2.11 Refueling Water Storage Tank - RWST (LCO 3.5.4) 2.11.1 Boron concentration limits during modes 1,2,3, and 4:

Parameter Limit Refueling Water Storage Tank minimum boron 2,675 ppm concentration.

Refueling Water Storage Tank maximum boron 2,875 ppm i concentration.

W - ,

4 ,- e Page 20 of 22

{

Revision 17

]

l McGuire 1 Cycle 13 Core Operating Limits Report  !

2.12. Spent Fuel Pool Boron Concentration (LCO 3.7.14) 2.12.1 Minimum boron concentration limit for the spent fuel pool. Applicable when fuel assemblies are stored in the spent fuel pool.

Parameter Limit l l

Spent fuel pool minimum boron concentration. '

2675 ppm 2.13 Refueling Operations - Boren Concentration (LCO 3.9.1) -

2.13.1 Minimum boron concentration limit for the filled portions of the Reactor Coolant System, refueling canal, and refueling cavity for mode 6 conditions.

Parameter Limit '

Minimum Boron concentration of the Reactor Coolant 2675 ppm t System, the refueling canal, and the refueling cavity.

1 i

, --.___..m.- _ . _ - . _ . . _ . _ . . - _ . _ = - . - . _ . . . . _

.g. .-_ _ ._.

', Page 21 cf 22 I Revision 17 McGuire I Cycle 13 Core Operating Limits Report 2.14 l Borated Water Source-Shutdown (SLC 16-15.3.1.2.5) 2.14.1' Volume and boron concentrations for the Boric Acid Storage System and the .

[ Refueling Water Storage Tank (RWST) during modes 5 & 6: -

i Parameter 1/imit .

Boric Acid Storage System minimum contained 8,884 gallons ,

borated water volume 10.0% level )

l Boric Acid Storage System minimum boron 7,000 ppm  ;

concentration Boric Acid Storage System minimum water 585 gallons

l. volume required to maintain SDM at 7,000 ppm l
t. i i

l Refueling Water Storage Tank minimum contained 43,000 gallons  !

l borated water volume 35.0 inches

  • i I

Refueling Water Storage Tank minimum boron 2,675 ppm y concentration Refueling Water Storage Tank minimum water 3,500 gallons volume required to maintain SDM at 2,675 ppm l

m I --

i 1

1 I

i e.

l 1

i i

I l

i

~~'

, mecev.+vu-.,u Page 22 of 22 Revision 17 t

l

, McGuire 1 Cycle 13 Core Operating Limits Report L .

l 2.15 Borated Water Source - Operating (SLC 16-15.3.1.2.6) 1 2.15.1 Volume and boron concentrations for the Boric Acid Storage System and the Refueling -

l Water Storage Tank (RWST) during modes 1, 2, 3, & 4:

I l Parameter Limit l

l Boric Acid Storage System minimum contained '

22,520 gallons borated water volume 39.0% level l

Boric Acid Storage System minimum boron 7,000 ppm concentration l

Boric Acid Storage System minimum water 11,851 gallons volume required to maintain SDM at 7,000 ppm l i Refueling Water Storage Tank minimum contained 96,607 gallons borated water volume  !'

103.6 inches Refueling Water Storage Tank minimum boron 2,675 ppm l

concentration Refueling Water Storage Tank maximum boron 2,875 ppm concentration l

Refueling Water Storage Tank minimum water 57,107 gallons J volume required to maintain SDM at 2,675 ppm l

I NOTE: Data contained in the Appendix to this document was generated in the McGuire 1 Cycle i 13 Maneuvering Analysis calculational file, MCC-1553.05-00-0256. The Plant Nuclear Engineering Section will control this information via computer file (s) and should be contacted if there is a need to access this infonnation.

i

-

Retrieved from "https://kanterella.com/w/index.php?title=ML20196G058&oldid=2985249"