ML20073F700
| ML20073F700 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 09/22/1994 |
| From: | Bonneau C, Pribyl D, Wegener D NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20073F699 | List: |
| References | |
| NUDOCS 9410030205 | |
| Download: ML20073F700 (8) | |
Text
_
i 1
MONTICELLO NUCLEAR GENERATING PLANT i
Core Operating Limits Report for Cycle 17 Revision 0 i
t i
j Prepared By:
k 6!TT Date '
D.J. Pribyl C,,J Engineer 11, Fuel Resources Reviewed By:
. M MP + -
9-1F-9Y l
D.G. Wegener /
Date Superintendent of Nuclear Engineering, Monticello i
Reviewed By:
_ #. 44_,
_4, (4 8-m-9[///#/'/
C.A. Bonneau Date Proces Mana Fu esources s,
Q Reviewed By:
- ///sE
-@o. RoA
.225eo+ 9/
l R'. O. Anderson Director, Licensing an[d Management issues Date l
l 9410030205 940926 PDR ADDCK 05000263 Page1 of 8
.P PDR
~
This report provides the values of the limits for Cycle 17 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.
Rod Block Monitor Operability Reauirements l
The MCPR limit associated with the Rod Block Monitor operability is:
if thermal power < 90% of rated and MCPR < 1.70 or if thermal power 2 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 Sctpoint (ITSP) s 115/125 of full scale High Trip Setpoint (HTSP) s 110/125 of full scale Reference Technical Specification Sections: Table 3.2.3 Item 4.a Table 3.2.3 Note 8.
Minimum Critical Power Ratio The Minimum Critical Power Ratio (MCPR) limit shall be determined as follows:
If thermal power > 45%, then the MCPR is the greater of:
1.35
- Kp (Ke from Figure 3) or MCPRr from Figure 4.
If thermal power s 45%, then the MCPR limit is obtained from Figure 3.
Reference Technical Specification Section: 3.11.C.
Power-Flow Operatina Mao The Power-Flow Operating Map based on analysis to support Cycle 17 is shown in Figure 5.
t Acoroved Analytical Methods NEDE-24011-P-A Rev 11
" General Electric Standard Application for Reactor Fuel" NSPNAD-8608-A Rev 2
" Reload Safety Evaluation Methods for Application to the Monticello Nuclear Generating Plant" NSPNAD-8609-A Rev1
" Qualification of Reactor Physics Methods for Application to Monticello" ANF-91-048 (P) (A) Rev 0
" Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors-EXEM BWR Evaluation Model," Siemens Power Corporation Page 2 of 8
)
4 9
. Maximum Averaoe Linear Heat Generation Rate as a function of exposure When hand calculations are required, the Maximum Average Linear Heat Generation Rate (MAPLHGR) l for each fuel bundle design as a function of average p!Pner 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 fuel lattice 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.
No channel bow effects are included in the bounding MAPLHGR values below because there are no reused channels. MAPLHGR limits for each individual fuel lattice design in a bundle design as a function of axial location and average planar exposure, with appropriate channel bow adjustments (no channel bow effects for Cycle 17), are determined based on the approved methodology referenced in Monticello Technical Specification 6.7.A.7.b and loaded in the process computer for use in core monitoring calculations.
The SPC 9x9-IX Qualification Fuel Assemblies (QFAs) will be monitored to the GE10 DXB333-10GZ MAPLHGR and LHGR limits to protect the steady state LHGR limit of the QFAs. When hand calculations are required, the D\\B333-10GZ MAPLHGR and LHGR limits can be used to calculate the appropriate limits for the QFAs.
Reference Technical Specification Section 3.11.A.
Table 1 MAPLHGR for each fueltype (kW/ft) i Exposure Fuel MWD /STU NBD NBD HXB324-HXB324-HXB324-DXB333-DXB324-312A 313A 10GZ 11GZ 10GZ1 10GZ 11GZ 200 11.1 11.3 10.92 10.36 11.19 11.64 10.71 1000 11.2 11.2 11.05 10.C 11.42 11.70 10.82 5000 12.0 12.0 12.01 11.55 12.20 12.30 11.78 10000 13.0 13.0 13.17 12.95 12.65 12.88 13.17 15000 12.9 12.8 12.95 12.97 12.47 12.65 12.88 20000 12.3 12.2 12.21 12.22 11.81 11.97 12.25 25000 11.6 11.5 11.52 11.52 11.21 11.31 11.60 30000 10.9 10.8 10.90 10.90 10.67 10.67 10.95 35000 10.2 10.2 10.29 10.28 10.14 10.02 10.30 40000 9.5 9.5 9.63 9.61 9.55 9.21 9.61 45000 8.8 8.9 8.98 8.94 8.97 8.40 8.92 50000 6.3 6.3 6.50 6.45 6.49 5.93 6.43 Note: For two recirculation loop operation. For single loop operation, multiply these values by 0.85.
Linear Heat Generation Rate Table 2 LHGR for Each FuelType (tW/ft)
NBD NBD HXB324-HXB324-HXB324-DXB333-DXB324-312A 313A 10GZ 11GZ 10GZ1 10GZ 11GZ 14.4 14.4 14.4 14.4 14.4 14.4 14.4 Reference Technical Specification Section: 3.11.B.
Page 3 of 8
Figu re 1 Monticello Cycle 17 Power Dependent MAPLHGR Limits 1.0 i
s
=
i c.
O,g
[....
+.
...._._. 4 p
i CORE FLOW s 50%
o_<b FOR P < 25% NO THERMAL LIMITS REQUIRED 2
O.6 NO LIMITS SPECIFIED Q
CCRE FLOW > 50%
o u.
FOR 45% > P > 25%
T i
LJ MAPFACp = 0.766 + 0.00695 (P - 45) 0.4 l
i-FOR CORE FLOW s 50%
+
o_
j MAPFAC = 0.643 + 0.00495 (P - 45) g p
l FOR CORE FLOW > 50%
d FOR P > 45%
0.2 i.
2 MAPFACp = 1.0 + 0.003727 (P - 100) j P = POWER (% RATED) 0.0 20 30 40 50 60 70 80 90 100 POWER (% RATED)
E
- ~ - - - - - - - - - - - - - -
Figure 2 Monticello Cycle 17 Flow Dependent MAPLHGR Limits 1.0 i
~~^.-'
100% Power MAX FLOW = 107%
0.94
.F.__...........-
P FW - 1 m
% 0.9
-+
-+-
O i
MAPFAC = MINIMUM (MFRPD. MAPMULT )
{
7 F
F Q.
h MAPMULT ' = 1.0 FOR FLOW > 80%
7
= 0.94 FOR FLOW s 80%
v 0.8
--4 g
MFRPD = MINIMUM (1.0, nF + b)
O F = CORE FLOW (% RATED) h
(
AND n. b ARE CONSTANTS GB/EN BELOW:
g 3
0.7 MAxMUu 1
j
+
+
b-CORE FLOW
[
(% RATED) n b
To Ig 107.0 0.006758 0.4574 0.6
- MAPMULT = 0.94 BETWEEN 80% AND 90%
7 CORE FLOW IF RATED MCPR UMIT (MCPR(100)) < 1.28 i
0.5 30 40 50 60 70 80 90 100 110 CORE FLOW (% RATED)
~
Figure 3 Monticello Cycle 17 Power Dependent MCPR Limits 2.6 FOR P < 25% NO THERMAL LIMITS MONITORING 2.4 4
REQUIRED - NO LIMITS SPECIFIED CORE FLOW > 50%
2.2 i-i-
i b
-1 FOR 45% lt P 2 25%
(E i
MCPRp = 1.63 + 0.0165 (45 - P)
O_
i 2.0 j-j FoR CORE FLOW s 50%
g 5
i MCPRp = 2.03 + 0.0195 (45 - P)
~~
j i.
FOR CORE FLOW > 50%
2 e
! CORE FLOW s 50%
P = POWER (% RATED) 1.6 e-o cm FOR 100% > P > 45%
)4 l
p 1.0 + 0.00418 (100 - P)
K
=
[
P = POWER (% RATED)
CL l
M N
1.2 j
N i
N I
N 1.0 20 30 40 45 50 60 70 80 90 100 POWER (% RATED)
4 Figure 4 Monticello Cycle 17 Flow Dependent MCPR Limits g
1.7 j
FOR Wc (% RATED CORE FLOW) 2 43%
MCPR = MAX (1.20 A W /100 + B )
7 7 C F
FOR WC (% RATED CORE FLOW) < 43%
MCPRF " (A W /100 + B) rc r
N
- [1 + 0.0025 (43 - W ))
c g
MAX FLOW A
B r
7 1.4
+
3 107.0%
-0.454 1.586 100% Power MAX FLOW =
7%
45% Power MAX FLOW = 112%
I 1.3 j
1.2
+
1.1 20 30 40 50 60 70 80 90 100 110 CORE FLOW (% RATED)
Figure 5 i.
l Monticello Nuclear Generating Pignt Power-Flow Operating Map for Cy'cle 17
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Operation NOT j
'q, allowed in the 3
shoded areas.
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1500
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SCRAM REGION:
J.
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r _- 10'8 7. Ro d Lin e o
3 e'., f, SCRAM required 0 1000-// '
in the IdV' -'
o CD O-double-ha tc hed -
fn rut ith k
"9" OE
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',', n a t u ral h.i [j XCLUSION REGION:
1 E Naturoi circulo' ion O
750-~
' circu!ation.
. jj
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O 20x eu,,, sp..a _
[
ji-f required in the 9 3 0 *. Pu m p3. e d
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dotted area.
O iOOx Pump _ sp.ed I
500-F X 3P_R_M,R_od Block lin e "70T. Rod Line
- /
7 10 0E Ro_d.V..
I i
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+ eoxnoetin.
O 12ix noe un. __
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250 -
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O Minimurn Power
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e 1.cn so.c 2.i.e timii p,e j _,
/j' 8 her.as.a cor. rio.
0_
0 10 20 30 40 50 60 Total Core now (MLb/Hr)
Rated IIOW r
. - - -