ML20116A873: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:- . _ _ .
{{#Wiki_filter:-
Wolf Creek Cycle 7                                       Rev. O Wolf Creek Generating Station cycle 7 CORE OPERATING LIMITS REPORT October 12, 1992 Prepared by:
Wolf Creek Cycle 7 Rev. O Wolf Creek Generating Station cycle 7 CORE OPERATING LIMITS REPORT October 12, 1992 Prepared by:
D. T. Gournelos                 J. T. Blair Reviewed by:
D.
E. W. Jackson Approved by:
T.
Terry J. Garrett Manager, Nuclear Analysis Page 1 of 18 9210300191 DR       921028 ADOCK 05000482 PDR
Gournelos J.
T. Blair Reviewed by:
E.
W. Jackson Approved by:
Terry J. Garrett Manager, Nuclear Analysis Page 1 of 18 9210300191 921028 DR ADOCK 05000482 PDR


Wolf Creek Cycle 7                                       Rev. 0 1.0 CORE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT (COLR) for Wolf Creek Generating Station Cycle 7 has been prepared in accordance with the requirements of Technical Specification 6.9.1.9.
Wolf Creek Cycle 7 Rev. 0 1.0 CORE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT (COLR) for Wolf Creek Generating Station Cycle 7 has been prepared in accordance with the requirements of Technical Specification 6.9.1.9.
The core operating limits that are included in the COLR affect the following Technical Specifications:
The core operating limits that are included in the COLR affect the following Technical Specifications:
2.1.1   Safety Limits - Reactor Core 3.1.1.3 Moderator Temperature Coefficient (MTC)
2.1.1 Safety Limits - Reactor Core 3.1.1.3 Moderator Temperature Coefficient (MTC)
BOL and EOL limits 3.1.3.5 Shutdown Rod Insertion Limit 3.1.3.6 Control Rod Insertion Limits 3.2.1   Axial Flux Difference (AFD) 3.2.2   Heat Flux Hot Channel Factor - FQ(X,Y,Z) 3.2.3   Nuclear Enthalpy Rise Hot Channel Factor - FAH(X,Y) 3.2.5.c   Ree.ctor Coolant System (RCS) Flow Rate 3.9.1.b   Refueling Boron Concentration i
BOL and EOL limits 3.1.3.5 Shutdown Rod Insertion Limit 3.1.3.6 Control Rod Insertion Limits 3.2.1 Axial Flux Difference (AFD) 3.2.2 Heat Flux Hot Channel Factor - FQ(X,Y,Z) 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor - FAH(X,Y) 3.2.5.c Ree.ctor Coolant System (RCS) Flow Rate 3.9.1.b Refueling Boron Concentration i
Page 2 of 18
Page 2 of 18


Wolf Creek Cycle 7                                         Rev. 0 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the subsections below:
Wolf Creek Cycle 7 Rev. 0 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the subsections below:
2.1 Safety Limits - Reactor Core (Tech spec 2.1.1)
2.1 Safety Limits - Reactor Core (Tech spec 2.1.1)
The combination of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant tempergture (Tavg) shall not exceed the limits shown in Figure 1   for four loop operation.
The combination of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant tempergture (Tavg) shall not exceed the limits shown in Figure 1 for four loop operation.
* The curves on Figure 1 are based on DNB Correlation             : WRB-2 DNBR design limit           : 1.17 Safety Analysis limit DNBR : 1.80 Design Fag                 : 1.65 Page 3 of 18 i
The curves on Figure 1 are based on DNB Correlation
: WRB-2 DNBR design limit
: 1.17 Safety Analysis limit DNBR : 1.80 Design Fag
: 1.65 Page 3 of 18 i
o
o


Wolf Creek Cycle 7                                                                                         Rev. 0 680                                           i
Wolf Creek Cycle 7 Rev. 0 680 i
                          , _ _ _              t                             _ _y_           ,
t
i                              L               l     !
_ _y_
p       q       ;
L l
660   -                                                                ---
i p
                                                                                        !      -1       j UNACCEPTABLEq
q j
                                                                                .__ OPERATION           :
660
l                                                                   l       l l
-1 UNACCEPTABLEq
1 3_
.__ OPERATION l
l                ,
l l
O
l l
_ _ _ . ' _ 2400    _ 7SIA      i __ _
3_
                                                ;                            y--               !      y LL         _.__}         wi= .2000 PSIA                                       '
1 O
                                                                                                !    __L I
_ _ _. ' _ _2400 SIA i __ _
h 620                       l                                                   f               h     4         -
7 y--
                                                                                                                          ~
y LL
2250 PSIA       -- > I                 ~~i
_.__}
$                j                                       i                       t-q-                 i g ggg           i                     I               7                   T         T         N     r 190 PSIA                       '
wi=.2000 PSIA
I 4                        -,-
__L h 620 l
g
f h
                                                !                              }
4 I
i l
2250 PSIA -- > I
j M 580                       !                            +
~~i
o                          !
~
_ ._ f
j i
                                                                  ,          a yb 560                                 ACCEPTABLE                                 ,              j OPERATION                           -
t-q-
i                  l                       l\\ _
i g ggg i
l                             I                   i           i       i                       i \\,
I 7
540                                                               j                   ;                              y   '
T T
i           i       i        l               i
N r
                                                +
190 PSIA I
l     l     1                      i
}
          ''''    ''''        ''''      ''' !    '    ''''l''''                   ' '''      '' ''' ''        '''
l g
520 O.0     0.1     0.2         0.3     0.4     0.5       0.6         0.7     0.8-   0.9     1.0       1.1     1.2 FRACTION OF RATED THERMAL POWER Figure 1 REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION Page 4 of 18
i j
4 M 580
+
_._ f yb o
a 560 ACCEPTABLE j
OPERATION i
l l\\\\ _
l I
i i
i i \\\\,
540 j
y i
i i
l i
l l
i
''''l''''
+
1 520 O.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8-0.9 1.0 1.1 1.2 FRACTION OF RATED THERMAL POWER Figure 1 REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION Page 4 of 18


t Wolf Creek Cycle 7                                       Rev. 0 2.2 Moderator Temperature Coefficient (MTC)
t Wolf Creek Cycle 7 Rev. 0 2.2 Moderator Temperature Coefficient (MTC)
(Tech Spec 3.1.1.3)
(Tech Spec 3.1.1.3)
(a) The BOL MTC limit is shown in Figure 2.
(a) The BOL MTC limit is shown in Figure 2.
Line 81: Line 106:
l l
l l


  - _ - , -_.                __ _      ~ . . . _ . . .
~... _...
Wolf' Creek Cycle- T Rev. 0:
Wolf' Creek Cycle-T Rev. 0:
FIGURE 2                                                                                             .
FIGURE 2 Moderator Temperature Coefficient vs Power Level 1
Moderator Temperature Coefficient vs Power Level                                                                                                                 1 MTC (pcm/deg. F)                                                                                                                       ARO at BOL-8 i
MTC (pcm/deg. F)
ARO at BOL-8 i
UNACCEPTABLE OPERATION 6.0, 70%
UNACCEPTABLE OPERATION 6.0, 70%
6 i
6 i
ACCEPTABLE OPERATION 4   - - - - - - - - - - - -              - - - - - - - - -            - - - - - - - -                - - - - - -            ------*--
ACCEPTABLE OPERATION 4
2
2
                                                                                                                                                                    \i
\\i
                                                                                                                                                                        \,?
\\,
0 l                   0       -10           20           30           40;             50               60               70             80               9 0 ---       100-i
?
                                              % of Rated Thermal Power l
0 l
I                                                                       Page 6 of 18 y,-d-                                                                                             y                   %~w
0
-10 20 30 40; 50 60 70 80 9 0 ---
100-i
% of Rated Thermal Power l
I Page 6 of 18 y,-d-m--
y m
W
-F T-v
-7rrr-e-we t y
w
%~w


Wolf Creek Cycle 7                                         Rev. 0-2.3 Shutdown Rod T.nse_rtion Limit (Tech Spec 3.1.3.5)
Wolf Creek Cycle 7 Rev.
0-2.3 Shutdown Rod T.nse_rtion Limit (Tech Spec 3.1.3.5)
The shutdown rods shall be fully withdrawn, as defined in Figure 3.
The shutdown rods shall be fully withdrawn, as defined in Figure 3.
2.4 Control Rod Insertion Limits (Tech Spec 3.1.3.6)
2.4 Control Rod Insertion Limits (Tech Spec 3.1.3.6)
Line 104: Line 141:
l l
l l


uti creer, cycle ;                                                                                           Pev, u l
l uti creer, cycle ;
I (FULLY WITHDRAWN0 )
Pev, u I
0 (FULLY WITHDRAWN )
122 %
122 %
                                                      ** "                                          /izs.iw' zzl t                                                / (7s.7%'az23.__
/izs.iw' zzl
                                                                                                /                                                         /
/ (7s.7%'az23.__
too
t
                                                                                              /                                                        ,/
/
g) r BANK B                                                   g
/
                                                                                                                                                      ')
/
g               )                                                                 )
,/
l                                                             }
too r
                                                                /l(o% tal) 2
) BANK B
                                                                                                                                /
')
iso                                                                                                      (loo %Istp l                                                f I40
g g
                                                                                                              /                                                         ,
)
                                                                                                                                                                          /
)
BANK C
g l
                                                            =                                          ,
}
                                                                                                        /   1
/
                                                                                                                                                                    /
/l iso (o% tal)
                                                                                                      )                                                         )
(loo %Istp 2l f
A f
/
f l%
/
So                           '
I40 BANK C
                                                                                            /                                                          /
/
                                                                                    /                                                                / BANK 0 so                                                                       ,
/
                                                                  /                                                               /
1
                                                                ' (o% 44) f
=
                                                                                                                              /
)
                                                                                                                        )
)
f f
A l%
/
/
So
/
/ BANK 0 so
/
/
' (o% 44)
/
f
)
f 20
f 20
                                                                                                          /
/
g                              (30.2%o)/
(30.2%o)/
o                             to           40                                     so           so           10 0 (FULLY INSERTED)
g o
FIGURE               3 ROD BANK INSERTION LIMIT VERSUS THERMAL POWER-FOUR LOOP OPERATION
to 40 so so 10 0 (FULLY INSERTED)
                                                                + Fully Withdrown shall be the condition where control rods are at a position within the interval of h 222 and :s 231 steps withdrawn.
FIGURE 3
ROD BANK INSERTION LIMIT VERSUS THERMAL POWER-FOUR LOOP OPERATION
+ Fully Withdrown shall be the condition where control rods are at a position within the interval of h 222 and :s 231 steps withdrawn.
Page 8 of 18
Page 8 of 18


Wolf Creek Cycle 7                                   pey, o 2.5 Axial Flux Difference (AFD)
Wolf Creek Cycle 7 pey, o 2.5 Axial Flux Difference (AFD)
(Tech Spec 3.2,1)
(Tech Spec 3.2,1)
The indicated Axial Flux Difference (AFD) allowed operational space is defined by Figure 4.
The indicated Axial Flux Difference (AFD) allowed operational space is defined by Figure 4.
Line 148: Line 201:
l
l


Wolf Creek Cycle               7_.
Wolf Creek Cycle 7_.
Rev, 0 110
Rev, 0 110
( 15.100)                     (6,100) 100   -
( 15.100)
UNACCEPTABLE                                               UNACCEPTABLE OPERATlON                                                 OPERATION
(6,100) 100 UNACCEPTABLE UNACCEPTABLE OPERATlON OPERATION
                                          ~
~
90 -
90 -
i d   80    -
i d
o.
o.
N iE
80 N
.                              O r
iE O
                                $ 70         -
r
B g                                            ACCF.PTABLE
$ 70 B
                                            ~
ACCF.PTABLE g
OPERATION 60     -
~
50       -
OPERATION 60 50 (24,50)-
(24,50)-
(. 2 6,5 0)
(. 2 6,5 0)
I       '      '      '      '    '      !    '      !    '
I 40 30 20 10 0
40 30                 20             10           0           10           20                   30
10 20 30
                                                                              . FLUX DIFFERENCE (DELTA 1) %
. FLUX DIFFERENCE (DELTA 1) %
Figure 4 WOLF CREEK UNIT 1 AXIAL FLUX OlFFERENCE AS A FUNCTION OF RATED THERMAL POWER Page 10 of '"
Figure 4 WOLF CREEK UNIT 1 AXIAL FLUX OlFFERENCE AS A FUNCTION OF RATED THERMAL POWER Page 10 of '"
6
6


Wolf creek Cycle 7                                         Rev..0 2.6 Heat Flux Hot Channel Factor - PgiX,Y.Z)
Rev..0 Wolf creek Cycle 7 2.6 Heat Flux Hot Channel Factor - PgiX,Y.Z)
(Tech Spec 3.2.2) y RTP FQ MA(X,Y,Z) 1 --------
(Tech Spec 3.2.2)
* K(Z)             for P > 0.5 P
RTP y
p RTP FgMA(X,Y,Z) 5 --------
MA(X,Y,Z) 1 --------
* K(Z)               for 1 0.5 0.5 THERMAL POWER where,   P     = ------------------ ,
* K(Z) for P > 0.5 FQ P
RATED THERMAL POWER FqRTP , the Fq at RATED THERMAL POWER
RTP p
                        = 2.50, and K(Z) is defined in Figure 5.
FgMA(X,Y,Z) 5 --------
* K(Z) for 1 0.5 0.5 THERMAL POWER
: where, P
= ------------------,
RATED THERMAL POWER FqRTP, the Fq at RATED THERMAL POWER
= 2.50, and K(Z) is defined in Figure 5.
(Tech Spec 4.2.2....d)
(Tech Spec 4.2.2....d)
See Appendix A for:
See Appendix A for:
: 1.  (Fg(X,Y,Z)) NOM
(Fg(X,Y,Z)) NOM 1.
[Fgb(X,Y,Z))OP and (Fgb(X,Y,Z))RPS e
(Fg (X,Y,Z))RPS b
: 2. Op Mar NSLOPE and Op Mar PSLOPE
[Fg (X,Y,Z))OP b
: 3. RPS Mar NSLOPE and RPS Mar PSLOPE.
and 2.
Op Mar NSLOPE and Op Mar PSLOPE e
3.
RPS Mar NSLOPE and RPS Mar PSLOPE.
i Page 11 of 18 l
i Page 11 of 18 l


                  .                  ,            I                       ,
I
        , nnO4Y nXan* N                                     ,$*    0 2
, nnO4Y nXan* N 0
                        -                              1 o
2 1
t T
o t
H G
T HG I
I E
EH ER O
H                                              '
C 8
E                _
F O
R O
N 5
C                                                 8 F
O
O N                                                                 5 O                                                         )       2 I
)
T                                              '    )     Z 009 C                                                   T F
2 IT
0(     1 1 0 N
)
5 UF                                                '
Z 009 C
T 0(
1 0
: 5. K 1
N F
5 U
(
(
T 5. K e A H 2 r   S                                                6I G =
T F
E u
H 2
g  A                                                    H i
e A G
    )
6I r
Z E T )ft F                                                         R
=
S E
u A g
H T
)f t
)Z E
i Q (n F
R
(
(
F                                                   O Q F o (n
O F
C D                                                          it E                                                           a Z                                                            0 0 0, I
F o D
L A
C it E
p062 E       1 M                                                 4 R
a I
O N                                              '
0 0 0, Z
    )
p062 LA E
1 M
4 R
ON
)
Z.
Z.
(
(
K 2
K 2
O 2       j 8       6     4     2   O 1             0       0     0     O G_ota onC$2EOZh uf       Y mu$ w 0m *
O 2
8 6
4 2
O j
1 0
0 0
O a onC$2EOZh Y G_ot uf mu$ w 0m *


      * ^ ^ ' '-                        -      -      . . - . --      -.
* ^ ^ '
l l
l 1
l 1
Wolf Creek. cycle 7                                             Rev. 0 2.7 Nuclear Enthalov Rise Hot Channel Factor - F 4g(X,Y)
Rev. 0 Wolf Creek. cycle 7 2.7 Nuclear Enthalov Rise Hot Channel Factor - F g(X,Y) 4 (Tech Spec 3.2.3)
(Tech Spec 3.2.3)
FAH(X,Y) shall be limited oy the relationship F49RM(X,Y) $ FAHRL(X,Y).
FAH(X,Y) shall be limited oy the relationship F49RM(X,Y) $ FAHRL(X,Y).
See Appendix A for array FAHRL (X,Y).
L See Appendix A for array FAHR (X,Y).
(ACTION a, b)
(ACTION a, b)
See Appendix A for RRH.
See Appendix A for RRH.
Line 233: Line 313:
Page 13 of-18
Page 13 of-18


i Wolf Creek Cycle 7                                       Rev. O Definition of FAHR Limit:
i Wolf Creek Cycle 7 Rev. O Definition of FAHR Limit:
FAH (X,Y)               1 FAHRL(X,Y) = ---------------------------------- * -------
FAH (X,Y) 1 FAHRL(X,Y)
MAPD(hD(X,Y), AXD(X,Y)) / AXD(X,Y)   MH(X,Y) where, FanD (X,Y) = Design FAH for the assembly at location (X,Y),
= ---------------------------------- * -------
MAP D     =TgedesignMaxgmumAllowablePeakat h (X,Y) and AX (X,Y),
MAPD(hD(X,Y), AXD(X,Y)) / AXD(X,Y)
h D(X,Y)   = Axial location of the design axial power peak at (X,Y),
MH(X,Y)
AXU(X,Y)   = The ratio of the peak to average axial power at (X,Y) for the design power distribution, and MH(X,Y)   = Minimum available margin ratio at (X,Y).
: where, D
Fan (X,Y) = Design FAH for the assembly at location (X,Y),
D
=TgedesignMaxgmumAllowablePeakat MAP h (X,Y) and AX (X,Y),
D h (X,Y)
= Axial location of the design axial power peak at (X,Y),
AXU(X,Y)
= The ratio of the peak to average axial power at (X,Y) for the design power distribution, and MH(X,Y)
= Minimum available margin ratio at (X,Y).
Measuren nt:
Measuren nt:
FAH (X,Y)
FAH (X,Y)
FAHRM(X,Y) = ----------------------------------
FAHRM(X,Y)
MAP                              M M (hM (X,Y), AXM(X,Y)) / AX_(X,Y) where, FAH (X,Y) = Measured FAH for the assembly at location (X,Y),
= ----------------------------------
MAPM      = The Magimum' Allowable Peak at hM(X,Y) and AX (X,Y),
M M
h M(X,Y)   = Axial location of the-measured axial power peak,-and AXM(X,Y)   = The ratio _of the peak to average axial power at (X,Y) for the-measured power distribution.
M MAP (h (X,Y), AXM(X,Y)) / AX_(X,Y)
: where, FAH (X,Y) = Measured FAH for the assembly at location (X,Y),
MAP
= The Magimum' Allowable Peak at hM(X,Y)
M and AX (X,Y),
M h (X,Y)
= Axial location of the-measured axial power peak,-and AXM(X,Y)
= The ratio _of the peak to average axial power at (X,Y) for the-measured power distribution.
Page 14 of 18
Page 14 of 18


Wolf Creek Cycle 7                                         Rev. o 2.8 Reactor Coolant System (RCS) Flow Ralg (Tech Spec 3.2.5.c)
Wolf Creek Cycle 7 Rev. o 2.8 Reactor Coolant System (RCS) Flow Ralg (Tech Spec 3.2.5.c)
The measured Reactor Coolant System (RCS) total flow rgte shall be maintained greater than or equal to 38.4 x 10 GPM for four loop operation. The indicated flow shall be used for the measured flow without adjustment for measurement uncertainty. The limit includes the 2.5%
The measured Reactor Coolant System (RCS) total flow rgte shall be maintained greater than or equal to 38.4 x 10 GPM for four loop operation. The indicated flow shall be used for the measured flow without adjustment for measurement uncertainty. The limit includes the 2.5%
measurement uncertainty for flow.
measurement uncertainty for flow.
i Page 15 of 18
i Page 15 of 18


Wolf Creek Cycle 7                                     Rev. 0 2.9 Refuelina Boron concentration (Tech Spec 3.9.1.b)
Wolf Creek Cycle 7 Rev. 0 2.9 Refuelina Boron concentration (Tech Spec 3.9.1.b)
The refueling boron concentration shall be greater than er squal to 2300 PPM.
The refueling boron concentration shall be greater than er squal to 2300 PPM.
Page 16 of 18
Page 16 of 18


Wolf Creek Cycle 7                                       Rev. O APPENDIX A (Reference 1)
Wolf Creek Cycle 7 Rev. O APPENDIX A (Reference 1)
A. Input relating to Specification 4.2.2.2.d:
A.
: 1.  [Fg(X,Y,Z)) NOM   : Nominal design peakin' (Fgb(X,Y,Z))OP   : Operational design peaking limit, and (Fgb(X,Y,Z))RPS   : Reactor Protection Setpoint (RPS) design peaking limit.
Input relating to Specification 4.2.2.2.d:
[Fg(X,Y,Z)) NOM
: Nominal design peakin' 1.
(Fg (X,Y,Z))OP b
: Operational design peaking limit, and (Fg (X,Y,Z))RPS b
: Reactor Protection Setpoint (RPS) design peaking limit.
These are a large number of large arrays. They are issued in a controlled report which will be submitted to the NRC on request.
These are a large number of large arrays. They are issued in a controlled report which will be submitted to the NRC on request.
The design peaking limits include all uncertainties.
The design peaking limits include all uncertainties.
: 2. Op Mar NSLOPE = 1.5% / % margin-Op Mar PSLOPE = 2.0% / % margin
2.
: 3. RPS Mar NSLOPE = 1.32% / % margin RPS Mar PSLOPE = 2.82% / % margin l
Op Mar NSLOPE
l Ref. 1: Core Operating Limit Methodology for Westinghouse-Designed PWRs, BAW-10163P-A, June 1989.
= 1.5% / % margin-Op Mar PSLOPE
= 2.0% / % margin 3.
RPS Mar NSLOPE = 1.32% / % margin RPS Mar PSLOPE = 2.82% / % margin l
l Ref. 1: Core Operating Limit Methodology for Westinghouse-Designed PWRs, BAW-10163P-A, June 1989.
Page 17 of 18
Page 17 of 18
\
\\


Wolf Creek Cycle 7                                         Rev. O APPENDIX A (Cont'd)
Wolf Creek Cycle 7 Rev. O APPENDIX A (Cont'd)
B. Input relating to Specification 3.2.3:
B.
: 1. FAHRT(X,Y)     : The maximum allowaole radial peak ratio These are a large number of large arrays. They are issued in a controlled report which will be submitted to the NRC on request.
Input relating to Specification 3.2.3:
1.
FAHRT(X,Y)
: The maximum allowaole radial peak ratio These are a large number of large arrays. They are issued in a controlled report which will be submitted to the NRC on request.
The design peaking limits include all uncertainties.
The design peaking limits include all uncertainties.
: 2. RRH = 3.33
2.
: 3. TRH = 0.038 C. Input relating to Specification 4.2.3.2.b:
RRH = 3.33 3.
i
TRH = 0.038 C.
: 1. FAHRNOM(X,Y)   : Nominal design radial peak ratio These are a large number of large arrays. They are         ,
Input relating to Specification 4.2.3.2.b:
issued in a controlled report which will be submitted       '
i 1.
to the NRC on request.
FAHRNOM(X,Y)
I I
: Nominal design radial peak ratio These are a large number of large arrays. They are issued in a controlled report which will be submitted to the NRC on request.
l Page 18 of 18
Page 18 of 18
_ .      .-          __}}
__}}

Latest revision as of 22:59, 12 December 2024

Cycle 7 Core Operating Limits Rept, Rev 0
ML20116A873
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 10/12/1992
From: Garrett T, Gournelos D, Jackson E
WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20116A856 List:
References
NUDOCS 9210300191
Download: ML20116A873 (18)
v • d • e


Text

-

Wolf Creek Cycle 7 Rev. O Wolf Creek Generating Station cycle 7 CORE OPERATING LIMITS REPORT October 12, 1992 Prepared by:

D.

T.

Gournelos J.

T. Blair Reviewed by:

E.

W. Jackson Approved by:

Terry J. Garrett Manager, Nuclear Analysis Page 1 of 18 9210300191 921028 DR ADOCK 05000482 PDR

Wolf Creek Cycle 7 Rev. 0 1.0 CORE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT (COLR) for Wolf Creek Generating Station Cycle 7 has been prepared in accordance with the requirements of Technical Specification 6.9.1.9.

The core operating limits that are included in the COLR affect the following Technical Specifications:

2.1.1 Safety Limits - Reactor Core 3.1.1.3 Moderator Temperature Coefficient (MTC)

BOL and EOL limits 3.1.3.5 Shutdown Rod Insertion Limit 3.1.3.6 Control Rod Insertion Limits 3.2.1 Axial Flux Difference (AFD) 3.2.2 Heat Flux Hot Channel Factor - FQ(X,Y,Z) 3.2.3 Nuclear Enthalpy Rise Hot Channel Factor - FAH(X,Y) 3.2.5.c Ree.ctor Coolant System (RCS) Flow Rate 3.9.1.b Refueling Boron Concentration i

Page 2 of 18

Wolf Creek Cycle 7 Rev. 0 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the subsections below:

2.1 Safety Limits - Reactor Core (Tech spec 2.1.1)

The combination of THERMAL POWER, pressurizer pressure, and the highest operating loop coolant tempergture (Tavg) shall not exceed the limits shown in Figure 1 for four loop operation.

The curves on Figure 1 are based on DNB Correlation

WRB-2 DNBR design limit
1.17 Safety Analysis limit DNBR : 1.80 Design Fag
1.65 Page 3 of 18 i

o

Wolf Creek Cycle 7 Rev. 0 680 i

t

_ _y_

L l

i p

q j

660

-1 UNACCEPTABLEq

.__ OPERATION l

l l

l l

3_

1 O

_ _ _. ' _ _2400 SIA i __ _

7 y--

y LL

_.__}

wi=.2000 PSIA

__L h 620 l

f h

4 I

2250 PSIA -- > I

~~i

~

j i

t-q-

i g ggg i

I 7

T T

N r

190 PSIA I

}

l g

i j

4 M 580

+

_._ f yb o

a 560 ACCEPTABLE j

OPERATION i

l l\\\\ _

l I

i i

i i \\\\,

540 j

y i

i i

l i

l l

i

'l'

+

1 520 O.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8-0.9 1.0 1.1 1.2 FRACTION OF RATED THERMAL POWER Figure 1 REACTOR CORE SAFETY LIMIT - FOUR LOOPS IN OPERATION Page 4 of 18

t Wolf Creek Cycle 7 Rev. 0 2.2 Moderator Temperature Coefficient (MTC)

(Tech Spec 3.1.1.3)

(a) The BOL MTC limit is shown in Figure 2.

(b) The EOL MTC limit is -4; pcm/deg F.

(Tech Spec 4.1.1.3)

The 300 PPM MTC Surveillance Limit is -32 pcm/deg F.

I l

l l

l Page 5 of 18 l

l l

~... _...

Wolf' Creek Cycle-T Rev. 0:

FIGURE 2 Moderator Temperature Coefficient vs Power Level 1

MTC (pcm/deg. F)

ARO at BOL-8 i

UNACCEPTABLE OPERATION 6.0, 70%

6 i

ACCEPTABLE OPERATION 4

2

\\i

\\,

?

0 l

0

-10 20 30 40; 50 60 70 80 9 0 ---

100-i

% of Rated Thermal Power l

I Page 6 of 18 y,-d-m--

y m

W

-F T-v

-7rrr-e-we t y

w

%~w

Wolf Creek Cycle 7 Rev.

0-2.3 Shutdown Rod T.nse_rtion Limit (Tech Spec 3.1.3.5)

The shutdown rods shall be fully withdrawn, as defined in Figure 3.

2.4 Control Rod Insertion Limits (Tech Spec 3.1.3.6)

The Control Bank Insertion Limits are specified in Figure 3.

I i

Page 7 of 18 l

{

l l

l uti creer, cycle ;

Pev, u I

0 (FULLY WITHDRAWN )

122 %

/izs.iw' zzl

/ (7s.7%'az23.__

t

/

/

/

,/

too r

) BANK B

')

g g

)

)

g l

}

/

/l iso (o% tal)

(loo %Istp 2l f

/

/

I40 BANK C

/

/

1

=

)

)

f f

A l%

/

/

So

/

/ BANK 0 so

/

/

' (o% 44)

/

f

)

f 20

/

(30.2%o)/

g o

to 40 so so 10 0 (FULLY INSERTED)

FIGURE 3

ROD BANK INSERTION LIMIT VERSUS THERMAL POWER-FOUR LOOP OPERATION

+ Fully Withdrown shall be the condition where control rods are at a position within the interval of h 222 and :s 231 steps withdrawn.

Page 8 of 18

Wolf Creek Cycle 7 pey, o 2.5 Axial Flux Difference (AFD)

(Tech Spec 3.2,1)

The indicated Axial Flux Difference (AFD) allowed operational space is defined by Figure 4.

Page 9 of 18 l

l

Wolf Creek Cycle 7_.

Rev, 0 110

( 15.100)

(6,100) 100 UNACCEPTABLE UNACCEPTABLE OPERATlON OPERATION

~

90 -

i d

o.

80 N

iE O

r

$ 70 B

ACCF.PTABLE g

~

OPERATION 60 50 (24,50)-

(. 2 6,5 0)

I 40 30 20 10 0

10 20 30

. FLUX DIFFERENCE (DELTA 1) %

Figure 4 WOLF CREEK UNIT 1 AXIAL FLUX OlFFERENCE AS A FUNCTION OF RATED THERMAL POWER Page 10 of '"

6

Rev..0 Wolf creek Cycle 7 2.6 Heat Flux Hot Channel Factor - PgiX,Y.Z)

(Tech Spec 3.2.2)

RTP y

MA(X,Y,Z) 1 --------

  • K(Z) for P > 0.5 FQ P

RTP p

FgMA(X,Y,Z) 5 --------

  • K(Z) for 1 0.5 0.5 THERMAL POWER
where, P

= ------------------,

RATED THERMAL POWER FqRTP, the Fq at RATED THERMAL POWER

= 2.50, and K(Z) is defined in Figure 5.

(Tech Spec 4.2.2....d)

See Appendix A for:

(Fg(X,Y,Z)) NOM 1.

(Fg (X,Y,Z))RPS b

[Fg (X,Y,Z))OP b

and 2.

Op Mar NSLOPE and Op Mar PSLOPE e

3.

RPS Mar NSLOPE and RPS Mar PSLOPE.

i Page 11 of 18 l

I

, nnO4Y nXan* N 0

2 1

o t

T HG I

EH ER O

C 8

F O

N 5

O

)

2 IT

)

Z 009 C

T 0(

1 0

5. K 1

N F

5 U

(

T F

H 2

e A G

6I r

=

S E

u A g

H T

)f t

)Z E

i Q (n F

R

(

O F

F o D

C it E

a I

0 0 0, Z

p062 LA E

1 M

4 R

ON

)

Z.

(

K 2

O 2

8 6

4 2

O j

1 0

0 0

O a onC$2EOZh Y G_ot uf mu$ w 0m *

  • ^ ^ '

l 1

Rev. 0 Wolf Creek. cycle 7 2.7 Nuclear Enthalov Rise Hot Channel Factor - F g(X,Y) 4 (Tech Spec 3.2.3)

FAH(X,Y) shall be limited oy the relationship F49RM(X,Y) $ FAHRL(X,Y).

L See Appendix A for array FAHR (X,Y).

(ACTION a, b)

See Appendix A for RRH.

(ACTION c)

See Appendix A for TRH.

(Tech Spec 4.2.3.2.b)

See Appendix A for array FAHRNOM(X,Y).

Page 13 of-18

i Wolf Creek Cycle 7 Rev. O Definition of FAHR Limit:

FAH (X,Y) 1 FAHRL(X,Y)

= ---------------------------------- * -------

MAPD(hD(X,Y), AXD(X,Y)) / AXD(X,Y)

MH(X,Y)

where, D

Fan (X,Y) = Design FAH for the assembly at location (X,Y),

D

=TgedesignMaxgmumAllowablePeakat MAP h (X,Y) and AX (X,Y),

D h (X,Y)

= Axial location of the design axial power peak at (X,Y),

AXU(X,Y)

= The ratio of the peak to average axial power at (X,Y) for the design power distribution, and MH(X,Y)

= Minimum available margin ratio at (X,Y).

Measuren nt:

FAH (X,Y)

FAHRM(X,Y)

= ----------------------------------

M M

M MAP (h (X,Y), AXM(X,Y)) / AX_(X,Y)

where, FAH (X,Y) = Measured FAH for the assembly at location (X,Y),

MAP

= The Magimum' Allowable Peak at hM(X,Y)

M and AX (X,Y),

M h (X,Y)

= Axial location of the-measured axial power peak,-and AXM(X,Y)

= The ratio _of the peak to average axial power at (X,Y) for the-measured power distribution.

Page 14 of 18

Wolf Creek Cycle 7 Rev. o 2.8 Reactor Coolant System (RCS) Flow Ralg (Tech Spec 3.2.5.c)

The measured Reactor Coolant System (RCS) total flow rgte shall be maintained greater than or equal to 38.4 x 10 GPM for four loop operation. The indicated flow shall be used for the measured flow without adjustment for measurement uncertainty. The limit includes the 2.5%

measurement uncertainty for flow.

i Page 15 of 18

Wolf Creek Cycle 7 Rev. 0 2.9 Refuelina Boron concentration (Tech Spec 3.9.1.b)

The refueling boron concentration shall be greater than er squal to 2300 PPM.

Page 16 of 18

Wolf Creek Cycle 7 Rev. O APPENDIX A (Reference 1)

A.

Input relating to Specification 4.2.2.2.d:

[Fg(X,Y,Z)) NOM

Nominal design peakin' 1.

(Fg (X,Y,Z))OP b

Operational design peaking limit, and (Fg (X,Y,Z))RPS b
Reactor Protection Setpoint (RPS) design peaking limit.

These are a large number of large arrays. They are issued in a controlled report which will be submitted to the NRC on request.

The design peaking limits include all uncertainties.

2.

Op Mar NSLOPE

= 1.5% / % margin-Op Mar PSLOPE

= 2.0% / % margin 3.

RPS Mar NSLOPE = 1.32% / % margin RPS Mar PSLOPE = 2.82% / % margin l

l Ref. 1: Core Operating Limit Methodology for Westinghouse-Designed PWRs, BAW-10163P-A, June 1989.

Page 17 of 18

\\

Wolf Creek Cycle 7 Rev. O APPENDIX A (Cont'd)

B.

Input relating to Specification 3.2.3:

1.

FAHRT(X,Y)

The maximum allowaole radial peak ratio These are a large number of large arrays. They are issued in a controlled report which will be submitted to the NRC on request.

The design peaking limits include all uncertainties.

2.

RRH = 3.33 3.

TRH = 0.038 C.

Input relating to Specification 4.2.3.2.b:

i 1.

FAHRNOM(X,Y)

Nominal design radial peak ratio These are a large number of large arrays. They are issued in a controlled report which will be submitted to the NRC on request.

Page 18 of 18

__

Retrieved from "https://kanterella.com/w/index.php?title=ML20116A873&oldid=4287674"