ML20116A873
| ML20116A873 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| 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) | |
Text
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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
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i p
q j
660
-1 UNACCEPTABLEq
.__ OPERATION l
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_ _ _. ' _ _2400 SIA i __ _
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OPERATION i
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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)
(a) The BOL MTC limit is shown in Figure 2.
(b) The EOL MTC limit is -4; pcm/deg F.
The 300 PPM MTC Surveillance Limit is -32 pcm/deg F.
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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
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0 l
0
-10 20 30 40; 50 60 70 80 9 0 ---
100-i
% of Rated Thermal Power l
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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.
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Page 7 of 18 l
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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
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Wolf Creek Cycle 7_.
Rev, 0 110
( 15.100)
(6,100) 100 UNACCEPTABLE UNACCEPTABLE OPERATlON OPERATION
~
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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)
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
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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.
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
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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
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