ML20070C279
| ML20070C279 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 06/24/1994 |
| From: | Bonneau C, Paustian H, Wegener D NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20070C275 | List: |
| References | |
| NUDOCS 9407050175 | |
| Download: ML20070C279 (6) | |
Text
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1 MONTICELLO NUCLEAR GENERATING PLANT Core Operating Limits Report For Cycle 16 Revision 2 Note: This report is not part of the Technical Specifications. This report is referenced in Technical Specifications.
l 9407050175 940627 PDR ADOCK 05000263 i P PDR '
Monticello Nuclear Generating Plant Page 1 of 8 )
Core Operating Limits Report For Cycle 16 Revision 2 This report provides the values of the limits for Cycle 16 as required by Technical Specification Section 6.7.A.7. These values have been established using NRC approved methodology and are established such that all applicable limits of the plant safety analysis are met.
Rodj!qck Monitor Ooerability Reauirements The MCPR limit associated with the Rod Block Monitor operability is:
if thermal power < 90% of rated and MCPR < 1.72 or if thermal power a 90% of rated and MCPR < 1.55.
Reference Technical Specification Section: 3.2.C.2.a Rod Block Monitor Uoscale Trio Setooints low Trip Setpoint (LTSP) s 120/125 of full scale intermediate Trip Setpoint (ITSP) s 115/125 of full scale High Trip Setpoint (HTSP) s 110/125 of full scale (These values are unchanged from the Cycle 15 trip setpoints)
Reference Technical Specification Sections: Table 3.2.3 Item 4.a, Table 3.2.3' Note 8.
Maximum Averaae Linear Heat Generation Rate as a function of Exposure When hand calculations are required, the Maximum Average Linear Heat Generation Rate (MAPLHGR) for each fuel bundle design as a function of average planer exposure shall not exceed the limiting lattice (excluding natural uranium) provided in Table 1 (based on straight line interpolation between data points) multiplied by the smaller of the two MAPFAC factors determined from Figures 1 and 2.
The MAPLHGR limits in Table 1 are conservative values bounding all the fuellattice types (excluding natural uranium) in a given fuel bundle design and are intended only for use in hand calculations as described in Technical Specification 3.11.A Channel bow effet.ts are included in the bounding MAPLHGR values below. MAPLHGR limits for each individual fuel lattice design in a bundle design, with appropriate channel bow adjustments are loaded in the process computer and are used in core monitoring calculations.
Reference Technical Specification Section: 3.1 1. A.
1 l
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Maximum Linear Heat Generation Rate as a Function of Exposure
. Table 1 Maximum A'verage Planar Heat Generation Rate vs. Exposure MAPLHGR for Each Fuel Type (kW/ft)
Exposure Fuel (MWD /STU) HXB324-n BD319B NDB312A NDB313A HXB324- HXB324- o 10GZ 11GZ 10GZ1 8E OO 200 9.52 9.43 9.60 9.28 10.36 9.51 a R-1,000 9.61 9.52 9.52 9.39 10.47 9.71 E E:
5,000 10.17 10.20 10.20 10.21 11.55 10.37 5 2 10,000 10.71 11.05 11.05 11.19 12.95 10.75 g { g; 15,000 10.49 10.96 10.88 11.01 12.97 10.60 s. -. E 20,000 10.16 10.45 10.37 10.38 12.22 10.04 25,000 30,000 9.83 8.96 9.86 9.26 9.77 9.18 9.79 9.26 11.52 10.90 9.53 9.07 6'((
g og 35,000 8.10 8.67 8.67 8.75 10.28 8.62 Q&
40,000 7.24 8.07 8.07 8.18 9.61 8.12 RS 45,000 6.32 7.48 7.56 7.63 8.94 7.62 23 50,000 -
4.93 4.93 5.52 6.45 5.51 Q.E i $
i Note: For two recirculation loop operation. For single loop operation multiply these values by 0.85.
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Monticello Nuclear Generating Plant Page 3 of 8 l' Core Operating Limits Report For Cycle 16 Revision 2 Linear Heat Generation Rate The Linear Heat Generation Rates (LHGR) are: f Table 2 LHGR for Each Fuel Type (kW/ft)
BD3198 NDB312A NDB313A HXB324- HXB324- HXB324-10GZ 11GZ 10G7.1 14.4 14.4 14.4 14.4 14.4 14.4 m
Reference Technical Specification Section: 3.1 1. B.
Minimum Critical Power Ratio The minimum Critical Power Ratio (MCPR) limit shall be determined as follows:
If thermal power > 45%, then the MCPR limit is the greater of:
1.35
- K, (K, from Figure 3) or the MCPR(F) from figure 4.
If thermal power s 45%, then the MCPR limit is obtained from figure 3.
Reference Technical Specification Section: 3.1 1. C.
f2yyer-Flow Ooerating Mao The Power Flow Operating Map based on analysis used to support Cycle 16 is shown in Figure 5.
Prepared By: [
Harold Paustian MW 0/Softh Date Sr. Nuclear Engineer Monticello M _ ymc, - J d t-fg_
Reviewed By: _. Daniel Wegener Date Superintendent Nuclear Engineering Monticello Reviewed By: w ,-m/ft4L _p[N!f/
Clif ;
d Bonneho'[ Ddte /
B\ R Process Manager Fuel sources /Nuclea Analysis and Design Reviewed By: jff [ h I [
t er O Anderson ate Director Licensing and Management issues ,
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._ CORE FLOW L 50%
Q L_ OR t %
O_ 25'
' <s ca o O 5' 5 FCP P < 25% NO THERMAL LIMITS REQUIRED Z CORE FLON > .50%
$ 0.6 - - - . .#.._
NO UMITS SPECIFIED e 9 9.
O $-L'E, m
Lt. FOR 45% > P 2 25%: [em c) e 90 D o T
y "
MAPFAC p =
0.796 + 0.0030 (P - 45) $$
o g-6 0.4 -- - - - - - ,------- - - - - '
FOR CORE FLOW s 50%
'c a.
y MAPFACp = 0.666 + 0.0030 (P - 45) M2 m g FOR CORE FLOW > 50% nF ".
_a O D FOR P > 45%
< 0.2 -- - + +-------..
2 MAPFAC p =
1.0 + 0.002325 (P - 100)
P = POWER (% RATED)
' ' ' i 0.0 20 30 40 50 60 70 80 90 100 ;y o
O POWER (% RATED) >
?
c2 Figure 1: MAPFAC, Limits
1 1 I I I I i t
100% Power MAX FLCW = 107%
MAPMULT O 94 . 1 - _ 4sx power uAx v. tow = ii4x
^
0.9 - ,
9 O
u.
/ 8g MAPFACr = M!N! MUM (MFRPDg . MAPMULTr ) Og I R$
h MAPMULT ' = 1.0 FOR FLOW > 80% $.=
$ c5
= 0.94 FOR FLOW s 80% Z cr 0.8 -
- m r--
O MFRPDF= MINIMUM (1_O, nF + b) < j'. o a>
9, w EGR O F = COPE FLOW (% RATED) b AND n. b ARE $[O CONSTANTS GfvEN BELOW: N3g )
3 -
3 0.7 -
+ . - . . - . . . uA>aMuu
?[5!
R l
' / CORE FLOW
@ (% RATED) n b Q3 L
3 hk 107.0 0.006753 9.4574 -.
1 G e 0.6 - -
- MAPMULTr = 0.94 6ETWEEN SO% AND 90%
CORE FLOW IF RATED MCPR UMIT (MCPR(100)) < 1.28 i ' i 0.5 i 30 40 50 60 70 80 90 100 110 ?
'8 '
CORE FLOW (% RATED) m 9.
Figure 2: MAPFAC, Limits
- 2.6 , i ; i FOR P : 250 NO THERMAL LIMITS MONITORING 2.4 -
D CORE FLOW > S0%
a 2.2 -
FoR 45% > P > 25% @
O' eg O_ TICPR p = 1.749 + 0.014 (45 - P) oo 2 2.0 -
FOR CCRE FLOW 5 50% .
TICPRp= 1.979 + 0.023 (45 - P) Eo=
FOR CORE FLOW > 50% *Z CORE FLOW s 50%
ICC P = POWER (% RATED) $:a
- 3. h.
1.6 -
STC S e
. FOR 65% > P > 45% NEg ,
(
1,4 _ _ . . . . . i. . . _ .i. . . . . . .
K g= 1.07 + 0.0035 (85 - P) ;n$.
E5c FOR P 2 85% O y i
a.
Kp = 1.0 + 0.00467 (100 - P) $k M P = POWER (% RATED) b 1.2 - - + -
-+~--
i i ' i i i i 1.0 20 30 40 45 50 60 70 60 90 100 2 cn POWER (% RATED)
E Figure 3: Power Dependent MCPR Limits 1
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Figure 5 Monticello Nuclear Generating Plant Power-Flow Operating Map for Cycle 16 (Rev 2)
- [ Operation NOT allowed in the
/ shaded areas.
Roted y -
Power hf ,' ,-
'** e g 1500- _
) ,
f -
/
r ( ..- H*
Q 2, '25 ~; ,
$ , . - / ,
52
- SCRAM REGlott: $! ,
1000 ~ SCRAM required _ }
u in the i a[O o double-hatched . Ty;
- ..jN }
Legend Nga c re a. gj AXCLUSION REGIOt4: '
g ,,,,,,, ci,,,i o,io, ay e 750-- m;gpFj trnrnedIate exis O 20x ev_-ss e~d _ ?E
'C Jji[ required in the G sox rump 3..J,
.;jji;is ' f doited area. g ,oog p,,ts,,,, y I O "" '" "" -
500--
7p?. Rod Line X erAu nog _si.3uin g V !?o l a.! N a_.__.__.
/ + aose.4un.
250- j O stix n.4 ua. _ _
,e /e o ui..... r...,
e 2.., se. 2.... m_i, yy,
/
O !m.=M ca. 9.x .
Total Core now (MLb/Hr) Roted Flow e CD k
CD
_ _ _ - - _ _ _ _ _ _ _ _ . _ _ _ _ _ _ - _ - _ - _ _ _ _ - - _ _ _ _ _ _ . _