ML20203F527
| ML20203F527 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 09/23/1997 |
| From: | Blair J, Flannigan R, Kennamore P WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20203F516 | List: |
| References | |
| NUDOCS 9712170403 | |
| Download: ML20203F527 (14) | |
Text
- - _ _
WdPLF CREEK Wolf Creek Generating Station
~ 4-Core Operat g Limits Report NUCLEAR OPERATING CORPORATION
)
f WOLF CREEK GENERATING STATION CYCLE 10 CORE OPERATING LIMITS REPORT Revision 0 i
Septernber 23,1997 Prepared by:
ch po4ff.Sidir Reviewed by:
Pete Kennamore l. [auw$mv Approved by:
z, R. D. Flarinighn
[/
bho82 AD P
PDR Page 1 of 14 i
Wolf Creek Generating Station Cycle 10 v
Core Opera g Limits Report NUCLEAR OPERATING CORPORATION 1,0 CORE OPERATING LIMITS REPORT The CORE OPERATING LIMITS REPORT (COLR) for Wolf Creek Generating Station Cycle 10 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:
3.1.1.3.b Moderator Temperature Coefficient (MTC) EOL Limit 3.1.3.5 Shutdown Rod Insertion Limit 3.1.3.6 Control Rod Insertion Limit 3.2.1 Axial Flux Difference (AFD) 3.2.2 Heat Flux Hot Channel Factor F (2) g 3.2.3 Nuclear Enthalpy Rbe Hot Channel Factor F,"n 3.9.1.b Refueling Boron Concentration Page 2 of 14
Wolf Creek Generating Station o
Cycle 10 Core Operati g Limits Report NUCLEAR OPERATING CORPORATION 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 Moderator Temperature Coefficient (MTC) EOL Limit (Toch Spoc 3.1.1.3.b)
The EOL MTC shall be less negative than 50 pern/deg F.
(Toch Spec 4.1.1.3.b)
The 300 PPM MTC Surveillance Limit is 41 pcm/deg F (all rods withdrawn, Rated Thermal Power condition).
Page 3 of 14
Wolf Creek Generating Station o
Cycle 10 Core Opera g Liinits Report DCLEAR OPERATNG COaK) RATION 2.2 Shutdown Rod Insertion Limit (Tech Spec 3.1.3.5)
The shutdown rods shall be fully withdiawn, as defined in Figure 1.
2.3 Control Rod Insertion Limits (Tech Spec 3.1.3.6)
The Control Bank Insertion Limits are specified in Figuro 1 Page 4 of 14
WoH Creek Generating Station l
Cycle 10 Core Operating Limits Rwport l
UCLEAR OPERATWO CORPORATION Revision 0 (rutLY MTNOMAWN )
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RATED THERMAL POWER (Pe. ;ent)
FIGURE 1 ROD BANK INSERTION LIMIT VERSUS THERMAL POWER.FOUR LOOP OPERATION r.. tty withdrewn shait be the conaittori where control rods are si a position wtihin the intervat i 2H2 ands 231 steps withdrewn.
Page 5 of 14
Wolf Creek Generating Station-i Cyclo 10 1
CWe yrs m'
W UCLEAR OPERATING CORPORATION p
0 2.4 Axial Flux Difference (AFD)
The Indicated Axlal Flux Difference (AFD) allowed operational space is i
defined by Figure 2.
J G
i i
Page 6 of 14
Wolf Crook Generating Strtion i
Cycle 10 Core Operating Limits Report 4
Nm NNeme Revision 0 110 es. w>
(i.im) 100 EE" "mnIEw" W
o p
90 R-A.
T E.
80 D
T
).
Acet m ou f 70
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mm M
l A
l L.
p 60 0
l W
E R
(M.80) 0 4,80) i i
i 30 20 10 0
10 20 30 FLUX DIFFERENCE (DELTA l} %
l RGURE2 WOLF CREEA AXIAL FLUX DIFFERENCE LIMITS AS A PUNCTION OF RATED THERMAL P
l l
Page 7 of 14
Wolf Creek Generating Station Cycle 10 Core Operati g Limits Report UCLEAR OPERATING CORPORATION 2.5 Heat Flux Hot Channel Factor Fo(2)
F" F (Z)s 'p 'K(Z),
for P > 0.5 o
F" F,(Z)5 05
- K(Z),
rPs0.5 TIIERMA1. POWER d ere, P
=
RATED TilERMAL POWtiR,
Fare the F,(Z) Limit at RATED THERMAL POWER (RTP)
=
a 2.50, and
=
K(Z) is defined in Figure 3.
Ff(Z)s
- (K(Z)] for P > 0.5 Fj" p
Fj"' (K(Z))
Ff(Z) s (W(Z)] [0.5] '
Ratio of the Fo from normal operation transients to the Fo at W(Z)
=
steady state conditions Page 8 of 14
Wolf Creek Generating Station Cycle 10 Coro Opera Ing m1ts Repod NL' CLEAR OPERATING CORPORATION p
9
- (Tech Spec 4.2.2.2.e.1)
With measurements indicating maximum
' F,"(Z)'
g(z),
wer z has increased since the previous determir'ilon of F7(Z),
Ff(Z) shall be nereased over that specified in 4.2.2.2.c by an appropriate factor, the F, Penalty Factor.
See Appendix A for.
1.
W(Z) 1.
F, Penalty Factor Page 9 of 14
Wolf Creek Generating Station Cycle 10 Core Operating Limits Report NUCLEAR OPERADNQ CORPORADON
- Revision 0 FIGURE 3 K(Z)-NORMALIZED PEAKING FACTOR VS. CORE HEIGHT 1.2 4
0 1
1 4
I i
t, g
xo, o
2
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FOT=2.50 g
o 0.2 - " " " " " " ! " " " " " " " - " " " ' " " ': " " ' " " " "i " "
twvenaa n rm 0.0 1.0 g
6.0 1.0 12.0 0.925 i
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i 0
2 4
6 8
10 12 C'
46 HEIGHT (FT) l I
Page 10 of 14 1
'*w
Wolf Creek Generating Station c
Cycle 10 m OpemtIng Umits Repod OCLEAR OPERATING CORPORATION Revision 0 4
2.6 Nuclear Enthalov Rise Hot Channel Feetor F5 (Tech Spec 3.2.?)
FL shall be limited by the following relationsh!p:
F5 s F$"(l.0 + PF,(1.0- P))
- Where, F7
= The F5 limit at RATED THERMAL POWER (RTP) 1.59
=
PF,
= the power factor multiplier for F5
= 0.3 TIIERMAL POWER P
=
RATED TiiERMAL POWER F"n = Measured values of FL obtained by using the movable incore 3
detectors to obtain P. power distribution map. The measured values of P& shall be used since an uncertainty of 4% for incore measurement of l
FL has been inciaded in the above limit.
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f Page 11 of 14 l
l
Wolf Creek Generating Station Cycle 10 Core Opera g Limits Report NUCLEAR O'ERATING CORPORATION 2.7 Refuelino Boron Concentration
('.:h Spec 3.9.1.b)
'lhe refueling boron concentration shail be greater than or equal to 2300 PPM.
Page 12 of 14
Wolf Creek Generating Station Cycle 10 e
Core Operatin Lim ta Report NUCLEAR OPERATING OvRPORATION 4
APPENDIX A A.
Input relating to Specification 4.2.2.2.c:
F,(Z)'"" '"""
W(Z)= 7 (7),
g,,
Thew values are issead 51 a controlled report which will be provided on requert.
Input relating to Specification 4.2.2.2.e.1 Cycle Bumup Ff(Z) Penalty Factor 0
2.00 21000 2.00 Note: All cycle bumups outside of the above table shall use a 2% penalty factor for com )l lance with 4.2.2.2.e Surveillance Requirement.
Linear Interpo ation should be used for intertnediate cycle bumups.
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l Pago 13 of 14
Wolf Creek Generating Station Cycle 10 Core Operati g Limits Report NUCLEAR OPERATING CORPORKnON 1
i Technical Soecification BASES 3/4.2.5 Cycle 10 Safety Analysis DNB Umit 1.76 WRB 2 Desi9.: Limit DNBR 1.23 i
4 i
1 j
Page 14 of 14
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