ML20249C703
| ML20249C703 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 05/27/1998 |
| From: | Sawyer T DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20249C702 | List: |
| References | |
| MCEI-0400-46, MCEI-0400-46-R16, MCEI-400-46, MCEI-400-46-R16, NUDOCS 9807010064 | |
| Download: ML20249C703 (21) | |
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MCEl-0400-46 Page I cf 21 7
,,, , R: vision 16 McGuire Unit 1 Cycle 13 Core Operating Limits Report May 1998 i
Duke Power Company Date Prepared By: b e M. M ov Wm 2/o,1998 Checked By:
- N.. .
26,1996 Checked By:
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% B6,If18 v {
Approved By: 4 8. ( M ///w a.7, //pf f
QA Condition 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 MIC13 Reload Safety Evaluation (calculation file: MCC-1552.08-00-0284).
I 9907010064 990624 PDR ADOCK 05000369 p PDR s
MCEl-0400-46 l ,. Page 2 of 21 Revision 16
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McGuire 1 Cycle 13 Core Operating Limits Report IMPLEMENTATION INSTRUCTIONS FOR REVISION 16 l- Revision 16 to the McGuire Unit 1 COLR contains limits specific to the McGuire Unit 1 L Cycle 13 core. The MICl3 COLR shall be implemented after no-mode is achieved and prior to the stan of fuel loading during the McGuire Unit 1 EOC-12 outage.
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", Revision 16 McGuire 1 Cycle 13 Core Operating Limits Report REVISION LOG Revision Effective Date Effective Panes COLR OriginalIssue May 24,1993 N/A M1C09 Revision 1 May 27,1993 N/A MIC09, Rev.1 Revision 2 Febmary 24,1994 N/A MIC09, Rev. 2 Revision 3 June 20,1994 N/A M1C09, Rev. 3 Revision 4 September 13,1994 N/A MIC10 Revision 5 October 18,1994 N/A MIC10, Rev. I Revision 6 October 24,1994 N/A MIC10, Rev. 2 Revision 7 June 26,1995 N/A M1C10, Rev. 3 Revision 8 November 28,1995 N/A MIC10, Rev. 4 Revision 9 December 14,1995 N/A MIC11 Revision 10 March 11,1996 N/A M1Cl l, Rev.1 Revision 11 June 24,1996 N/A M1C11, Rev. 2 Revision 12 Febmary 13,1997 N/A MICl2 Revision 13 June 13,1997 N/A MICl2, Rev.1 Revision 14 July 08,1997 N/A M ICl2, Rev. 2 Revision 15 March 12,1998 N/A MIC12, Rev. 3 Revision 16 May 27,1998 1-21 MICl3 l
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~ MCEI@00-46 Page 4 cf 21 g , Revision 16 McGuire 1 Cycle 13 Core Operating Limits Report INSERTION SHEET FOR REVISION 16 Remove pages Insert Rev.16 pages 1-21 1-21 i
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l MCEI-0400-46 i Page 5 (f 21 l R vision 16 j McGuire 1 Cycle 13 Core Operating Limits Report 1.0 Core Operating Limits Report This Core Operating Limits Repon, (COLR), for McGuire, Unit 1, Cycle 13 has been prepared in accordance with the requirements of Technical Specification 6.9.1.9.
l The Technical Specifications affected by this repon are listed below:
Tecimical Specifications Section Page 2.2.1 - Reactor Trip System Instrumentation Setpoint 2.0 6 3/4.1.1.3 - Moderator Temperature Coefficient 3.0 8 3/4.1.2.5 - Borated Water Source - Shutdown 3.1 10 3/4.1.2.6 - Borated Water Source - Operating 3.2 11 ;
3/4.1.3.5 - Shutdown Rod Insenion Limit 3.3 11 3/4.1.3.6 - Control Rod Insenion Limit 3.4 11 3/4.2.1 - Axial Flux Difference 3.5 11 3/4.2.2 - Heat Flux Hot Channel Factor 3.6 14 ,
3/4.2.3 - Nuclear Enthalpy Rise Hot Channel Factor 3.7 18 3/4.5.1.1 - Accumulators 3.8 20 3/4.5.5 - Refueling Water Storage Tank 3.9 20 3/4.9.1 - Refueling Operations - Boron Concentration 3.10 21 3/4.9.12 - Fuel Storage - Spent Fuel Storage Pool 3.11 21 l
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. Rsvision 16 McGuire 1 Cycle 13 Core Operating Limits Report 1.1 Operating Limits The cycle-specific parameter limits for the specifications listed in section 1.0 are presented in the following subsections. These limits have been developed using NRC approved methodologies specified in Technical Specification 6.9.1.9.
2.0 ' Tech Spec 2.2.1 - Reactor Trip System Instrumentation Setimints 2.0.1 Overtemperature AT Setpoint Parameter Values Parameter Value Overtemperature AT reactor trip setpoint K is 1.1978 Overtemperature AT reactor trip heatup K 2= 0.0334/0F setpoint penalty coefficient Overtemperature AT reactor trip K 3= 0.001601/ psi depressurization setpoint penalty coefficient l
Measured reactor vessel AT lead / lag time t i2 8 sec. !
constants T2s 3 sec. l l
Measured ATlag time constant 53s 2 sec. i Measured reactor vessel average temperature T4 2 28 sec. I lead / lag time constants T5 s 4 sec. !
Measure reactor vessel average temperature T6s 2 sec.
lag time constant f i(AI) " positive" breakpoint = 19.0 %Al f i(AI) " negative" breakpoint = N/A*
f i(AI) " positive" slope = 1.769 %ATo/ %AI f i(AI) " negative" slope = N/A*
l The f 1(AI) " negative" breakpoint and the f (AI) t " negative" slope are not applicable since the f t(AI) function is not required below the f 1(AI)" positive" breakpoint of 19.0% AI.
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Revision 16 McGuire 1 Cycle 13 Core Operating Limits Report !
2.0.2 O'verpower AT Setpoint Parameter Values Parameter Value Overpower AT reactor trip setpoint K4s 1.086359 Overpower AT reactor trip heatup setpoint K6= 0.001179FF penalty coefficient Measured reactor vessel AT lead / lag time t i2 8 sec. l constants T2 s 3 sec.
Measumd AT lag time constant T3 s 2 sec.
Measure reactor vessel average temperature t 6s 2 sec.
lag time constant Measure reactor vessel average temperature T7 2 5 sec.
rate-lag time constant f 2(AI) " positive" breakpoint = 35.0 %AI i
f 2(AI) " negative" breakpoint = -35.0 %AI f 2(AI) " Positive" slope = 7.0 %ATo/ %AI f 2(AI) " negative" slope = 7.0 %ATo/ %AI l
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3 . Rsvision 16 McGuire 1 Cycle 13 Core Operating Limits Report 3.0 Tech Spec 3/4.1.1.3 - Moderator Temperature Coefficient i
3.0.1 The Moderator Temperature Coefficient (MTC) Limits are:
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The MTC shall be less positive than the limits shown in Figure 1. The BOC, ARO, HZP MTC shall be less positive than 0.7E-04 AK/K/ F.
l The EOC, ARO, RTP MTC shall be less negative than -4.lE-04 AK/K/ F.
3.0.2 The MTC Surveillance Limit is:
The 300 PPM ARO, RTP MTC should be less negative than or equal to -3.2E-04 AK/K/'F.
Where: BOC stands for Beginning of Cycle EOC stands for End of Cycle ARO stands for All Rods Out
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HZP stands for Hot Zero Thermal Power l RTP stands for Rated Thermal Power !
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Rsvision 16 McGuire 1 Cycle 13 Core Operating Limits Report i
1.0 g 0.9 --
l Unacceptable Operation v
- t; 0.8 --
E !
8 0.7 '
U^
E 0.6 --
2 i 8 0.5 --
& *A 4
E $ 0.4 -- Acceptable Operation
$ et gO 0.3 --
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- $ 0.2 -- ;
i 3 0.1 -- l 0.0 l l l l l l l l l l 0 10 20 30 40 50 60 70 80 90 100 l
Percent of Rated Thermal Power Figure 1 Moderator Temperature Coefficient Versus Power level NOTE: Compliance with Technical Specification 3.1.1.3 may require rod withdrawal limits.
Refer to OP/1/A/6100/22 Unit 1 Data Book for details.
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Rtvision 16 McGuire 1 Cycle 13 Core Operating Limits Report i
3.1 - Tech Spec 3/4.1.2.5 - Borated Water Source - Shutdows 3.1.1 Volume and boron concentrations for the Boric Acid Storage System and the l Refueling Water Storage Tank (RWST) during modes 5 & 6:
Parameter Limit Boric Acid Storage System minimum contained 8,884 gallons borated water volume for LCO 3.1.2.5a 10.0% level l
Boric Acid Storage System minimum boron 7,000 ppm ,
concentration for LCO 3.1.2.5a l Boric Acid Storage System minimum water 585 gallons volume required to maintain SDM at 7,000 ppm l Refueling Water Storage Tank minimum contained 43,000 gallons borated water volume for LCO 3.1.2.5b 35 inches l- Refueling Water Storage Tank minimum boron 2,675 ppm concentration for LCO 3.1.2.5b Refueling Water Storage Tank minimum water 3,500 gaUons
- volume required to maintain SDM at 2,475 ppm i
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.,,, , Revision 16 McGuire 1 Cycle 13 Core Operating Limits Report 3.2 Tech Spec 3/4.1.2.6 - Borated Water Source - Operating 3.2.1 Volume and boron concentrations for the Boric Acid Storage System and the Refueling l Water Storage Tank (RWST) during modes 1, 2, 3, & 4:
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Parameter Limil Boric Acid Storage System minimum contained 22,520 gallons borated water volume for LCO 3.1.2.6a 39% level Boric Acid Storage System minimum boron 7,000 ppm concentration for LCO 3.1.2.6a Boric Acid Storage System minimum water 11,851 gallons volume required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum contained 96,607 gallons borated water volume for LCO 3.1.2.6b 103.6 inches Refueling Water Storage Tank minimum boron 2,675 ppm concentration for LCO 3.1.2.6b Refueling Water Storage Tank maximum boron 2,875 ppm concentration for LCO 3.5.5b Refueling Water Storage Tank minimum water 57,107 gallons volume required to maintain SDM at 2,675 ppm 3.3 Tech Spec 3/4.1.3.5 - Shutdown Rod Insertion Limit 3.3.1 The shutdown rods shall be withdrawn to at least 222 steps.
3.4 Tech Spec 3/4.1.3.6 - Control Rod Insertion Limits 3.4.1 The control rod banks shall be limited to physical insertion as shown in Figure 2.
3.5 Tech Spec 3/4.2.1 Axial Flux Difference 3.5.1 The Axial Flux Difference (AFD) Limits are provided in Figure 3.
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,';. . R: vision 16 McGuire 1 Cycle 13 Core Operating Limits Report i
1 (Fully Withdrawn min -222, max - 231) l 240 l
220 ** ** ~~ g' ' _' (29.6%,231) -
(80.0%,231) f' )
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- ~~,' ' '** ** *** *** '
7 i 200 ,z 7' 1
160 ,f ~
BdB ,1
! e' e' (100%,161) j 160 - '
h (0%,163)1 - '
Rod ' ' '
140- ,
l Insertion ' f '
! Position 120 -
' Bank C /
1 s (Steps ,
Withdrawn) g ,-
l 60 1 s 60 ,1 1
40 -" (0%,47) 1
! 20 s'
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- ' l (30%,0)
' 'l t , .
O 10 20 30 40 50 60 70 80 90 1 00 (Fullyinserted)
Relative Power (Percent)
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Control Rad Bank Insenion Limits Versus Percent Rated Thennal Power i
NOTE: Compliance with Technical Specification 3.1.1.3 may require rod withdrawal limits.
Refer to OP/1/A/6100/22 Unit 1 Data Book for details.
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,.. .- Rsvision 16 McGuire 1 Cycle 13 Core Operating Limits Report j 1
A. F. D. Limit Curve j l
enn l uv 110 -- I l (-18.100) u vv
(+10.100)
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h l Unacceptable operation l 80 -- l Unacceptable operation l h
70 --
l^cceptable %* loa.] 60 --
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i 50 -- l (+21.50)l l
% [ ( 36.50)l l o 40 --
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, g 30 -- l l s- 1 d
20 -- '
10 --
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-50 -40 -30 -20 -10 0 10 20 30 40 50 Axial Flux Difference (% Delta I)
Figure 3 Percent of Rated Thermal Power Versus Axial Flux Difference Limits 1
NOTE: Compliance with Technical Specification 3.2.2 may require more restrictive AFD l limits. Refer to OP/1/A/6100/22 Unit ! Data Book for details.
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- ., ", R vision 16 McGuire 1 Cycle 13 Core Operating Limits Report 3.6 Tech Spec 3/4.2.2 - Heat Flux Hot Channel Factor, FQ (X,Y,Z)
RTP 3.6.1 Fq = 2.50 x K(BU) 3.6.2 K(Z) and K(BU) are provided in Figures 4 and 5, respectively, for MkBW fuel.
The following parameters are required for core monitoring per the Surveillance Requirements of Specification 3/4.2.2:
D 3.6.3 [F 9(X,Y,Z)]OP = p q(X,Y,Z) x M Q (X,Y,Z)/(UMT x MT x TILT) where:
[h(X,Y,Z)]OP q = cycle dependent maximum allowable design peaking factor whi ensures that the FQ (X,Y,Z) limit will be preserved for operation within the LCO limits [ q(X,Y,Z)]OP. [F 9 (X,Y,Z)]OP includes allowances for calculational and measurement uncertainties.
g(X,Y,Z) = design power distribution Q for F . [q(X,Y,Z)is provided in Table Appendix A, for normal operating conditions and in Table 2, Appendix A for power escalation testing during initial stanup operation.
M Q(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 = 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: [F (X,Y,Z)]OP is the parameter identified as (X,Y,Z) in DPC-NE-201 I PA.
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, Ravision 16 McGuire 1 Cycle 13 Core Operating Limits Report 3.'6.4 ' [h(X,Y,Z)]RPS q = [(X,Y,Z) x (M C (X,Y,Z)/(UMT x MT x TILT))
where:
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[ q(X,Y,Z)]RPS = cycle dependent maximum allowable design peaking factor which ensures that the centerline fuel melt limit will be preserved for operation within the LCO limits. [h(X,Y,Z)]RPS ncludesi q
allowances for calculational and measurement uncertainties.
(X,Y,Z) = design power distributions for FQ. (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.
MC (X,Y,Z) = margin remaining to the CFM limit in core location X,Y,Z from the transient power distribution. MC(X,Y,Z) calculations parallel the Mo' (X,Y,Z) calculations described in DPC-NE-201 IPA, except that the LOCA limit is replaced with the CFM limit. MC(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 = Measurement Uncertainty, = 1.05.
MT= Engineering Hot Channel Factor, = 1.03. I TILT = Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02.
(TILT = 1.035)
NOTE: [h(X,Y,Z)]RPS q si the parameter identified as (X,Y,Z)in DPC-NE-2011PA, j except that MQ(X,Y,Z)is replaced by Mc(X,Y,Z).
3.6.5 KSLOPE = 0.0725 -
KSLOPE is the adjustment to the K 1value from OTAT required to compensate for each 1% that [F (X,Y,Z)]RPS exceeds its limit.
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McGuire 1 Cycle 13 Core Operating Limits Report l -
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0.90 -- (0.0,1.0) (12.0,1.0) 0.80 -
0.70 --
g 0.60 -
0.50 --
- G E0 .40 -- !
$ I 0.30 -- ;
l 0.20 --
l- 0.10 -- I l
- 0.00
- : : : : ::
! 0.0 2.0 4.0 6.0 8.0 10.0 12.0 Core Height (ft.) .
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K(Z), Normalized FQ(X,Y,Z) as a Function of Core Height for MkBW Fuel i
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- 1. . . . Revision 16 McGuire 1 Cycle 13 Core Operating Limits Report 1.000 :: : (45000,0.98)
- (0,1.0) (30000,1.0) 0.900 -
0.800 - ,
g 0.700 . (60000,0.792) 0.600 -
) 0.500 --
I 0 E .400 --
Z 0.300 --
0.200 --
0.100 -- l 0.000 : : : : : :-
0 10000 20000 30000 40000 50000 60000 Burnup (MWD /MTU)
Figure 5 K(BU), Normalized FQ(X,Y,Z) as a Function of Burnup for MkBW Fuel l
I L_--_---_----------------_-----_-- -- - - - - _ - - - - - - -- --
MCEl-0400-46 Pag 318 ef 21 '
., R: vision 16 McGuim 1 Cycle 13 Core Operating Limits Report 3.7 Tech Spec 3/4.2.3 - Nuclear Enthalpy Rise Ilot Channel Factor, FAH(X,Y,Z)
The following parameters are required for the LCO requirements of T.S. 3/4.2.3.
3.7.1 [Fm(X,Y)]LCO = MARP (X,Y) x [1.0 + (1/RRH) x (1.0 - P)]
where:
MARP(X,Y) = McGuire 1 Cycle 12 Operating Limit Maximum Allowable Radial Peaks. MARP(X,Y)) radial peaking limits, are provided in Table 7, Appendix A.
Thermal Power p , RatedThermalPower RRH is defined in section 3.7.3 The following parameters are required for core monitoring per the Surveillance requirements of T.S. 3/4.2.3.
3.7.2 [F (X,Y)]SURV = F (X,Y) x Mg(X,Y)/(UMR x TILT) where:
[F (X,Y)]SURV = cycle dependent maximum allowable design peaking factor which ensures that the Fm(X,Y) limit will be preserved for operation within the LCO limits. [F (X,Y)]SURV includes allowances for calculational and measurement uncertainty.
F (X,Y) = the design power distribution for Fg, 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 l operation.
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, Revision 16 McGuire 1 Cycle 13 Core Operating Limits Report Man (X,Y) = the margin remaining in core location X,Y relative to the Operational DNB limit in the transient power distribution.
MAH(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 incmase due to the allowed quadrant tilt ratio of 1.02. (TILT = 1.035).
NOTE: [F (X,Y)]SURV is the parameteridentified as [FAH(X,Y)] MAX in DPC-NE-2011PA.
3.7.3 RRH = 3.34 when 0.0 < P s 1.0, where:
RRH= Thermal Power reduction required to compensate for each 1% that FAH(X,Y) exceeds its limit.
3.7.4 TRH = 0.04 where:
TRH = Reduction in OTAT K setpoint 1 required !a compensate for each 1% that FAH(X,Y) exceeds its limit.
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McGuire 1 Cycle 13 Core Operating Limits Report 3.8 Tech Spec 3/4.5.1.1 - Accumulators 3.8.1 Boron concentration limits during modes 1,2, & 3:
l Parameter Limit l
l Cold Leg Accumulator minimum boron concentration for 2,475 ppm i LCO 3.5.1.1c l
Cold Leg Accumulator maximum boron concentration for 2,875 ppm LCO 3.5.1.lc l
Minimum Cold Leg Accumulator boron concentration 2,360 ppm required to ensure post-LOCA suberiticality for LCO 3.5.1.1 Action c.2)
I 3.9 Tech Spec 3/4.5.5 - Refueling Water Storage Tank l
- 3.9.1 Boron concentration limits during modes I,2,3, & 4
l l Parameter Limit l
j' Refueling Water Storage Tank minimum boron 2,675 ppm concentration for LCO 3.5.5b
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P:ge 21 of 21 q,,, Revision 16 McGuire 1 Cycle 13 Core Operating Limits Report 3.10 Tech Spec 3/4.9.1 - Refueling Operations - Boron Concentration 3.10.1 Minimum boron concentrations for the filled portions of the Reactor Coolant System and refueling canal. Applicable for mode 6 with the reactor vessel head closure bolts less than fully tensioned, or with the head removed.
Parameter Limit Refueling boron concentration for the filled portions of the 2675 ppm Reactor Coolant System and refueling canal for LCO 3.9.1.b 1
l 3.11 Tech Spec 3/4.9.12 - Fuel Storage - Spent Fuel Storage Pool 3.11.1 Minimum boron concentration limit for the spent fuel pool. Applicable when fuel is stored in the spent fuel pool.
Parameter Limit Spent fuel pool minimum boron concentration for LCO 2675 ppm 3.9.12 i
NOTE: Data contained in the Appendix to this document was generated in the McGuire 1 Cycle 13 Maneuvering Analysis calculational file, MCC-1553.05-00-0256. The McGuire Nuclear Engineering Section will control this information via computer file (s) and should be contacted if there is a need to access this information.
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