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CNEl-0400-25 Page 1 of 302 Rev.I Catawba Unit 2 Cycle 6 Core Operating Limits Report April 1994 Duke Power Company DATE PREPARED BY:          '/ #~ / M l b [a.a n                    4 -/ 'l -W CilECKED BY:              m (2r      4      ( L4_            M-/M-7j/
  ~a APPROVED BY:            /
E~/f'fV 5
QA CONDITION 1 NOTE This document does not contain information that affects the results and conclusions presented in the C2C6 Rcload Report, Safety Analysis.
9404220219 940414 DR- ADOCK 05000414 PDR
 
4 -
            ~
Catawba 2 Cycle 6 Core Operating 1,imits Report  CNE!4MCD-25
      ,                                                                      Page 2 0f 302 Rev.1-INSERTION SIIEET Remove                                  Insert pages 1-17, rev. O                      pages 1-16,17A,17B, 17C, rev.1
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't t-
 
Catawba 2 Cycle 6 Core Operating Limits Report    CNB14M(Mb25 Page 3 of 302 Rev.l REVISION LOG Revision                Effective Date              Comment Original Issue            15 February 1993            C2C6 COLR Revision 1                14 April 1994            C2C6 COLR rev.
4
 
a Catawba 2 Cycle 6 Core Operating Limits Report              CNEl-MCD-25 Page 4 of 302 Rev I 1.0 Core Operating Limits Report This Core Operating Limits Report (COLR) for Catawba Unit 2, Cycle 6 has been prepared in accordance with the requirements of Technical Specification 6.9.1.9.
The Technical Specifications affected by this report are listed below:
2.2.1-      Reactor Trip System Instrumentation Setpoints 3/4.1.1.3    Moderator Temperature Coefficient 3/4.1.2.5    Borated Water Source - Shutdown 3/4.1.2.6    Borated Water Source - Operating 3/4.1.3.5    Shutdown Rod Insertion Limit 3/4.1.3.6    Control Rod Insertion Limit 3/4.2.1      Axial Flux Difference 3/4.2.2      Ileat Flux liot Channel Factor 3/4.2.3      Nuclear Enthalpy Rise Hot Channel Factor 3/4.3.3.11  Boron Dilution Mitigation System 3/4.5.1      Accumulators 3/4.5.4      Refueling Water Storage Tank 3/4.9.2      Instrumentation s-
    - . ~ , ,                                                                                  *              '-" ''
 
                                                                                              .      . _=
s Catawha 2 Cycle 6 Core Operating Limits Report              CNEIMMb25 Page 5 of 302 Rev.1 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 Heactor Trip System Instrumentation Setpoints (Specification 2.2.1) 2.1    Overtemperature AT Setpoint Parameter Values Parameter                            Value Overtemperature AT reactor trip setpoint                K i = 1.1953 Overtemperature AT reactor trip heatup setpoint        K 2= 0.03163/oF penalty coefficient Overtemperature AT reactor trip depressurization        K 3= 0.001414/ psi setpoint penalty coefficient Measured reactor vessel ATlead/ lag time                t i= 12 sec.,
constants                                              T2 = 3 sec.
Measured ATlag time constant                            13 = 0 sec.
Measured reactor vessel average temperature            T4 = 22 sec.,
lead / lag time constants                              i s= 4 sec.
  ?
    )                  Measured reactor vessel average temperature lag        t 6= 0 sec.
time constant f i(Al) " positive" breakpoint                          = 3.0% Al f i(Al) " negative" breakpoint                        = -39.9% Al f i(AI) " positive" slope                              = 2.316% ATd % Al f i(AI) " negative" slope                              = 3.910% ATg % Al
 
Catawba 2 Cycle 6 Core Operating Limits Report      CNEI-0400-25 Pagc 6 of 302 Rev.I 2.2 Overpower AT Setpoint Parameter Values Parameter                      Value Overpower AT reactor trip setpoint                K4= 1.0819 Overpower AT reactor trip heatup setpoint penalty K6= 0.001291/oF coefficient (for T > 590.8 oF)
Overpower AT reactor trip heatup setpoint penalty K6 = 0.0/oF coefficient (for T s 590.8 oF)
Measured reactor vessel ATlead/ lag time          t i= 12 sec.,
constants                                        t 2= 3 sec.
Measured ATlag time constant                      13 = 0 sec.
Measured reactor vessel average temperature lag  T6 = 0 sec.
time constant                                                                          ;
l Measured reactor vessel average temperature rate- 17 = 10 sec.
lag time constant f 2(AI) " Positive" breakpoint                    = 35.0% Al                        J f 2(AI) " negative" breakpoint                    = -35.0% AI f 2(AI) " positive" slope                        = 7.0% ATg % AI                      j
    !            f2(Al) " negative" slope                          = 7.0% ATg % AI I
I I
:        .                                                                                                I Catawba 2 Cycle 6 Core Operating Limits Report            CNEl-G4GD-25 Page 7 of 302 Rev.I 3.0 Moderator Temperature Coefficient (Speciucation 3/4.1.1.3) 3.0.1  The Moderator Temperature Coefficient (MTC) Limits are:
The MTC shall be less positive than the limits shown in Figure 1. The BOC, ARO, li7P MTC shall be less positive that 0.7
* 104 AK/K/'F.
The EOC, ARO, RTP MTC shall be less negative that -4.l* 104 AK/K/'F.
3.0.2 For the MTC Surveillance Limit:
                        'T he 300 PPM /ARO/RTP MTC should be less negative than or equal to -3.2
* 104 AK/Kf'F.
Where:    HOC stands for Beginning of Cycle EOC stands for End of Cycle ARO stands for All Rods Out IIZP stands for Hot Zero (Thermal) Power RTP stands for Rated Thermal Power s
  )
l
 
Catawba 2 Cycle 6 Core Operating Limits Report                CNE14MCD-25      !
Page 8 of 302    l Itev. I  j i
I 0.9 -
og.    .
Unacceptable Operation C  0.7 1
29 0.6
            .5 g 0.5 s' O'4 Acceptable Operation g0.3-0.2 -  -
0.1 -
0        l  l      ;      ;      l            l      l      l 0    10  20    30      40    50      60    70    80    90    100 Percent ofitated Thermal Power i
' j                                              Figure 1 4
Moderator Temperature Coefficient Versus Percent of Rated Thermal Power                -!
l I
i 1
l i
 
Cntawha 2 Cycle 6 Core Operating Limits Report        CNiil-04525 Page 9 of 302 Itev 1 3.1 llorated Water Source - Shutdown lopecification 3/4.1.2.5) 3.1.1  Volume and boron concentrations for the Boric Acid Storage System and the Refueling Water Storage Tank (RWST) during modes 5 & 6:
Parameter                    Ljiinil Doric Acid Storage System minimum boron            7,000 ppm concentration for LCO 3.1.2.5a Boric Acid Storage System minimum contained        12,000 gallons water volume for LCO 3.1.2.5a Boric Acid Storage System minimum water volume 585 gallons required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum baron        2,000 ppm concentration for LCO 3.1.2.5b Refueling Water Storage Tank minimum contained 45,000 gallons                    .l water volume for LCO 3.1.2.5b                                                      l Refueling Water Storag- Tank minimum water        3,500 gallons volume required to maintain SDM at 2,000 ppm l
l
                                                                                                ~l i,
i 1
                                                                                                  ~
 
l Catawba 2 Cycle 6 Core Operating Limits Report              CNEl-0400-25 '  l Page 10of 302    ;
Rev.I 1
3.2 llorated Wnter Source Operating (Specification 3/4.1.2.6) 3.2.1  Volume and boron concentrations for the Boric Acid Storage System and the Refueling Water Storage Tank (RWST) during modes 1,2,3, & 4:
Parameter                      Limil Boric Acid Storage System minimum boron              7,000 ppm concentration for LCO 3.1.2.6a Boric Acid Storage System minimum contained          22,000 gallons water volume for LCO 3.1.2.6a Boric Acid Storage System minimum water volume 9,851 gallons required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum boron            2,000 ppm concentration for LCO 3.1.2.6b Refueling Water Storage Tank minimum contained 363,513 gallons water volume for LCO 3.1.2.6b Refueling Water Storage Tank minimum water            57,107 gallons volume required to maintain SDM at 2,000 ppm 3.3 Shutdown Rod Insertion Limit (Specification 3/4.1.3.5) 3.3.1  The shutdown rods shall be withdrawn to at least 222 steps.
        .'[
3.4 Control Rod Insertion Limits (Specification 3/4.1.3.6) 3.4.1 The control rod banks . hall be limited to physical insertion as shown in Figure 2.
3.5 Axial Flux Difference (Specification 3/4.2.1) 3.5.1  The Axial Flux Difference (AFD) Limits are provided in Figure 3.
f
 
Catawba 2 Cycle 6 Core Operating Limits Report                                        CNEl-0400 25 Page 11 of 302 Itev.1 Fully Withdrawn (29.IE 230)                                                    (79.6% 230)
(Maximum = 230)\
220 -r---------            - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Fully Withdrawn 200 .                                (Minimum = 222)
                                "^      "
9* 180 -  -
(100 % 161) 160 --(OE 163)
G 140 --
ef2                                        IIANK C 7 120 e
[100--
e 7 80 -    -
U                                                                      llA N K D 0
L 60 --                                                                                                            1 l
40 -_ (OE 47)                                                                                                  l l
                                                                                                                              ~
20 --
Fully inserted (30 % 0) 0      '
l l
                                                                                                    ;A '    ;
0      10    20    30          40        50        60          70        80      90    100          i l
Percent of Itated Thermal Power                                                      1 4
i                                                    Figure 2
  )
Control Rod Bank Insertion Limits Versus Percent of Rated Thermal Power                                            j
 
Catawba 2 Cycle 6 Cure Operating Limits Report                                    CNE14MCD-25 Page 12 Of 302 Rev.1
( 20,100)                        (410,100)
Unaccattable Operation                              ,,
                                                                            ~~
Unaccepuble Operation 70 --
g                            Acceptable Operation S                                                      g,o .-
d                                                      so .    .
( M.50)                                                      (+21.50) 3                                                      40 --
1 30 ..
20 --
I 4
10 --
e        e          i          e                    e      i        i          I                  l
                                  .        .          .          .                    .      i        i          i                  ,
40        -40          30      -20          10          0        10    20        30        40        50 Antal Hus thfference (% Delta 1) l Figure 3 Percent of Rated Thermal Power Versus Axial Flux Difference Limits
    's                                                                                                                                .
i i
 
_      _-    m.  .
Catawba 2 Cycle 6 Core Operating Limits Report                  CNE14M0(b25 Page 13 of 302 Rey,1 3.6 Ileat Flux IInt Channel Factor, F (X,Y,Z)
Q        (Specification 3/4.2.2) 3.6.1    I I[ = 2.32 3.6.2 K(Z) is provided in Figure 4 for Mark-BW fuel.
3.6.3 K(Z) is provided in Figure 5 for OFA fuel.
The following parameters are required for the Surveillance Requirements of T.S. 3/4.2.2:
FO(X,Y,Z)
* Mg(X,Y,Z)                                                    j 3.6.4  ((g(X,Y,Z)]OP =            *
* LT where:  [Fh(X,Y,Z))OP    =    cycle dependent maximum allowable design peaking factor which ensures that the 9F (X,Y,7) limit will be preserved for operation within the LCO limits. [Fj(X,Y,Z)jm' includes allowances for calculational and measurement uncertainties.
F (X,Y,Z)          =  the design power distribution for Fn.        (X,Y,Z) is provided in Table 2 for normal operation and Table 2A for power escalation testing during initial startup.                                          l l
Mg(X,Y,Z)        =  the margin remaining in core location X,Y,Z to            ,
the LOCA limit in the transient power                    j
. .,                                                  distribution. Mn(X,Y,Z) is provided in Table 3            ;
j                                                for normal operation and Table 3A for power              l 3                                                escalation testing during initial startup.
UMT              =  Measurement Uncertainty, = 1.05.
1 MT                =  Engineering Ilot Channel Factor, = 1.03.                  l TILT              =    Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02, = 1.035.              I l
NOTE: [I (X,Y,Z)]OP E
q          is the parameter identified as Ng        (X,Y,Z)in DPC-NE 2011PA. l 1
l l
 
                                          -. .              .        .      .                    ..        .~
l Catawba 2 Cycle 6 Core Operating Limits Report              CNEl-0400-25 Page 14 of 302 Rev.I    j
                                                                                                                        .i i
Fh(X,Y,Z)
* MC(X,Y,Z)                                                  )
3.6.5 IfE (X,Y,Z)lRPS =
n                            UMT
* MT
* TILT where:            [F (X,Y,Z))RPS  =    cycle dependent maximum allowable design peaking factor which ensures that the centerline fuel melt limit will be preserved for all operation.
[Fq(X,Y,Z)]RPS        includes    allowances      for calculational and measurement uncertainties.            -
                                                                                                                          )
I((X,Y,7-)      =    the design power distributions for Fq. ((X,Y,Z).
is provided in Table 2 for nomial operation and Table 2A for power escalation testing during initial startup.
Mc(X,Y,Z)        =    the margin remaining to the CFM limit in core location X,Y,Z from the transient power distribution. M c(X,Y,Z) calculations parallel the
                                                              .Mn(X,Y,Z) calculations described in DPC-NE-201 IPA, except that the LOCA limit is replaced with the CFM limit. M c(X,Y,Z) is provided in Table 4 for normal operation and Table 4A for power escalation testing during initial startup.
UMT              =    Measurement Uncertainty, = 1.05.
MT              =    Engineering Hot Channel Factor, = 1.03.
  's
  ',                                    TILT            =    Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02, = 1.035.
NOTE: ((q(X,Y,Z)]RPS is similar to the parameter identified(X,Y,Z)                  as [q in DPC-NE-2011PA except that MC (X,Y,Z) replaces Mg(X,Y,Z).
3.6.6    KSLOPE = adjustment to the K ivalue from OTAT required to compensate for each 1% that ((g(X,Y,Z)]nPS  exceeds it limit, = 0.0725 e % -
                        ,.,,rv.,- ig -.
 
            .                                                                                                        i Catawba 2 Cycle 6 Core Operating Limits Report                  CNElet00-25 Fage 15 0f 302 Rev.1 I
1.2
                          .l(0,0.1.00)                                    (8.0,1.00)
L 1                                                                      (l0.8,0.94) i 0.8  -                                                                                          !
E w
0.6    -                                                                  (12.0,0.647)I I
0.4  -
0.2  -
o                , , i    i 0        1      2    3  4      5      6    7      8    9    10      11    12 Core lleight (ft)
    ),                                                    Figure 4 4
K(Z), Nortnalized F (X,Y,Z) as a Function of Core licight for MkBW Fuel Q
 
Calawba 2 Cycle 6 Core Operating Limits Iteport                  CNEl-(M00 25
      <                                                                                        Fage 16of 302 11ev. I 1.2 (0.0,1.00)                        (6.0.1.00) 1                                                                    (l0.8,0.94) 0.8  -
8x 0.6  -                                                                  (12.0.0.647) 0.4  -
0.2  -
0 0        1    2      3    4      5      6    -7      8      9  10      11    12 Core lleight (ft)
  )
  ),                                                    Figure 5 a
K(Z), Normalized F (X,Y,Z) as a Function of Core Height for OFA Fuel Q
l
 
Catawba 2 Cycle 6 Core Operating Limits Report                CNEI4MCD-25
      .                                                                                  Page 17A of 302 Rev.1 3.7 Nuclear Enthalpy Rise Ilot Channel Factor, FAgg(X,Y,Z)(Specification 3/4.2.3)
The following parameters are required for the LCO Requirements of T.S. 3/4.2.3:
                                                                                  ~
1 3.7.1  [F[,(X, Y)]'" = MARP (X,Y)
* 1.0 + RRil * (1.0 - P) where:    M ARP(X,Y) = Catawba 2 Cycle 6 Operating Limit Maximum Allowable Radial Peaks. (M ARP(X,Y)) is provided in Tabic 1.
Thermal Power p
* Rated Thermal Power RRIl      is defined in section 3.7.3 The following parameters are required for the Surveillance Requirements of T.S. 3/4.2.3:
3.7.2  [Fi,(X,Y)]SURV = FM,(X,Y)x Mm(X,Y)
UMR xTILT where: [ F[i(X, Y)]''"Y  =    cycle dependent maximum allowable design peaking factor which ensures that the FAli(X,Y) limit will be preserved for operation within the LCO limits.
[ fin (X, Y)]5"*V includes allowances for calculational and measurement uncertainties.
F",(X,Y) = the design power distribution for Fall. Fj,(X, Y) is provided in Table 5 for normal operation and Table 5A for power escalation testing during initial startup.
(
  )                              Mall (X,Y) = the margin remaining in core location X,Y to the
                                                                                ~
Operational DNB limit - in the transient power distribution. Mall (X,Y) is provided in Table 6 for normal operation and Table 6A for power escalation testing during initial startup.
UMR = Uncertainty value for measured radial peaks, = 1.04.
TILT = Peaking penalty that accounts for allowable quadrant power tilt ratio of 1.02, = 1.035.
NOTE: [F[,(X,Y)]''"V is the pararneter identified as Fif(X,Y) in DPC-NE-20llPA.
 
Catawba 2 Cycle 6 Core Operating Limits Report          CNEl oWO 25 Page 1711of 302 Rev.1 3.7.3    RRIi = Thermal Power reduction required to compensate for each l'/c that FAi g(X,Y) exceeds its limit, = 3.34.
3.7.4    TRIi = Reduction in OTAT K setpoint 1        required to compensate for each 1% that FAij(X,Y) exceeds its limit, = 0.04 3.8 lloron Dilution Mitigation System (Specification 3/4.3.3.11) 3.H.1  Reactor Water Makeup Pump flowrate limits:
Applicable Mode                      Limit Mode 3 or 4                          s 150 gpm Mode 5                              s70gpm 3.9 Accumulators (Specification 3/4.5.1) 3.9.1  Baron concentration limits during modes 1,2 and 3:
brameter                              Limits Cold Leg Accumulator minimum baron                    1,900 ppm concentration for LCO 3.5.lc Cold Leg Accumulator maximum boron                    2,100 ppm concentration for LCO 3.5.lc                                                      .
o Minimum Cold Leg Accumulator boron                    1,800 ppm
    !                  concentration required to ensure post-LOCA suberiticality 3.10        Refueling Water Storage Tank (Specification 3/4.5.4) 3.10.1 Boron concentration limits during modes 1,2,3 and 4:
Parameter                            Limits Refueling Water Storage Tank minimum baron            2,000 ppm concentration for LCO 3.5.4b Refueling Water Storage rank maximum baron            2,100 ppm concentration for LCO 3.5.4b
 
4 Catawlia 2 Cycle 6 Core Operating Limits Report  CNE!-N00-25        -
Page 17C of 302    :
Rey,1 3.11        Instrumentation (Specification 3/4.9.2) 1 3.11.1 Reactor Makeup Water Pump Flowrate Limit:                                    l Applicable Mode                  Lim.Its Mode 6                          s 70 gpm o
S
                                  -.                                -                        -. .}}

Revision as of 18:38, 30 March 2020

Rev 1 to CNEI-0400-25, Catawba Unit 2 Cycle 6 Colr.
ML20065M058
Person / Time
Site: Catawba Duke Energy icon.png
Issue date: 04/14/1994
From: Clark R, Hager N, St Clain R
DUKE POWER CO.
To:
Shared Package
ML20065M057 List:
References
CNEI-0400-25, CNEI-0400-25-R01, CNEI-400-25, CNEI-400-25-R1, NUDOCS 9404220218
Download: ML20065M058 (19)
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