ML20133A851
| ML20133A851 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 12/04/1996 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20133A849 | List: |
| References | |
| NUDOCS 9701020134 | |
| Download: ML20133A851 (26) | |
Text
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PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 l
l (CYCLE 11) l ps ssw h
i 1
APPROVED:
I Operations Supporfpivision Manager Date i
APPROVED:
N (Le m4e st[2b[7(a Qr Engineering Shces Department Manager Date I
o(Lt. M 49 APPROVED:
OA b 96-77 l'/2C/94 OperatMs Review # Committee Date APPROVED: -
t'1Do M N-b AVb/#
nt'Dep
'ent Manager
/6 ate
(
APPROVED:
's
${cr-Station or Date 1
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l 9701020134 961223 PDR ADOCK 05000293 COLR REVISION 11D PAGE 1 OF 26
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l PILGRIM NUCLEAR POWER STATION i
PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 i
i TABLE OF CONTENTS i
P.R89 l
1 TITLE / SIGNATURE PAGE.,............
.I TABLE OF CONTENTS......................
..........................2 i
RECORD OF REVISIONS...................................
.3 i
i LIST OF TABLES.....
.4 LIST OF FIGURES..
.5 l
L
1.0 INTRODUCTION
.6 2.0 INSTRUMENTATION TRIP SETTINGS.......
.7 i
2.1 APRM Flux Scram Trip Setting (Run Mode)................ 7 2.2 APRM Rod Block Trip Setting (Run Mode)..
............7
)
1 t
i 2.3 Rod Block Monitor Trip Setting..
....8 3.0 CORE OPERATING LIMITS...
.9 i
I 3.1 Average Planar Linear Heat Generation Rate (APLHGR).....
.9 3.2 Linear Heat Generation Rate (LHGR).......
..9 3.3 Minimum Critical Power Ratio (MCPR).....
... 17 i
)
3.4 Power / Flow Relationship.........
..24 i
4.0 REACTOR VESSEL CORE DESIGN.....
.. 24
5.0 REFERENCES
. 24 i
1 COLR REVISION 11D PAGE 2 OF 26
4 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 RECORD OF REVISIONS Revision Effective Date Descriotion 8A Effective date based on Applicable for use during issuance oflicense Cycle 8 Operation amendment by NRC 9A Effective date based on Applicable for use during issuance oflicense Cycle 9 operation amendment by NRC for ARTS and SAFER /GESTR 10A Effective date based on Applicable for use during initial startup of Cycle 10 Cycle 10 Operation 11A Effective date based on Applicable for use during initial startup ofCycle 11 Cycle 11 Operation 1IB Effective upon final Applicable for use during approval Cycle 11 Operation 11C Effective upon final Applicable for use during approval Cycle 1I Operation 1ID Effective upon final Applicable for use during approval Cycle 11 Operation i
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COLR REVISION 11D PAGE 3 OF 26
PILGRIM NUCLEAR POWER STATION l
PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 i
l LIST OF TABLES l
Number Title East 3.2-l LHGR Operating Limits 10 3.3-1 MOC MCPR Operating Limits 19 3.3-2 EOC MCPR Operating Limits 20 3.3-3 EOC MCPR Operating Limits 21 with Final Feedwater Temperature Reduction f
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COLR l
REVISION 11D PAGE 4 OF 26
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 i
i LIST OF FIGURES i
Number Tjlle Pagg 3.1-1 Maximum Average Planar Linear Heat Generation 11 i
Rate (MAPLHGR) for Fuel Type BP8DRB300 i
l 3.1-2 Maximum Average Planar Linear Heat Generation 12 Rate (MAPLHGR) for Fuel Type BP8DQB323 l
3.1-3 Maximum Average Planar Linear Heat Generation 13 l
Rate (MAPLHGR) for Fuel Type BP8HXB355 l
3.1-4 Maximum Average Planar Linear Heat Generation 14 Rate (MAPLHGR) for Fuel Type BP9 HUB 378 l
3.1-5 Flow-Dependent MAPLHGR Factor (MAPFACr) 15 i
3.1-6 Power-Dependent MAPHLGR Factor (MAPFACp) 16 3.3-1 Flow-Dependent MCPR Limits (MCPRr) 22 3.3-2 Power-Dependent MCPR Limits (MCPRp) 23 3.4-1 Power / Flow Operating Map 25 I
4.0-1 Reactor Vessel Core Loading Pattern 26 l
COLR REVISION 1ID PAGE 5 OF 26
9 PILGRIM NUCLEAR POWER STATION.
PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02
(
l
1.0 INTRODUCTION
I l
This repon provides the cycle-specific limits for operation of the Pilgr..a Nuclear Power Station (PNPS) during Cycle 11. In this report, Cycle Il'will f;equently be~
referred to as the present cycle.
j 1
Although this report is not part of the PNPS Technical Specifications, the l
Technical Specifications refer to this report for the applicable values of the following fuel-related parameters-i i
i Reference
')
Technical Soecification l
APRM Flux Scram Trip Setting (Run Mode)
Table 3.1.1 APRM Rod Block Trip Setting (Run Mode)
Table 3.2.C-2 i
Rod Block Monitor Trip Setting Table 3.2.C-2 t
Average Planar Linear Heat Generation Rate 3.11. A Linear Heat Generation Rate (LHGR) 3.11.B l
Minimum Critical Power Ratio (MCPR) 3.11.C L
Power / Flow Relationship 3.11.D Reactor Vessel Core Design 5.2 l
If any of the core operating limits in this report are exceeded, actions will be taken as defined in the referenced Technical Specification.
l t
The core operating limits in this repon have been established for the present cycle usmg the NRC-approved methodology provided in the documents listed both in l
dection 5.0, References, and in Technical Specification 6.9.A.4. These limits are established such that the applicable limits of the plant safety analysis are met.
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I COLR REVISION 11D PAGE 6 OF 26
1.
l PILGRIM NUCLEAR POWER STATION l
)
PNPS CORE OPERATING LIMITS REPORT-RTYPE: G4.02 l
1 2.0 INSTRUMENTATION TRIP SETTINGS:
l 2.1 APRM Flux Scram Trio Settine (Run Model Reference Technical Specifications: Table 3.1.1,3.1.B.1 l
When the mode switch is in the run position, the average power range monitor (APRM) flux scram trip setting (S.) shall be:
S, s 0.66 W + 69%
i with a clamp at 120% of rated core thermal power and b
l l
S=
APRM flux scram trip setting in percent of rated thermal power (1998 MW).
i W=
Percent of drive flow required to produce a rated core flow I
of 69 Mlb/hr.
l
)
l The APRM flux scram trip setting is valid only for operation using two i
recirculation loops. Operation with one recirculation loop out of service is I
restricted by License Condition 3.E.
l In accordance with Technical Specification Table 3.1.1, Note 15, for no
+
combination ofloop recirculation flow rate and core thermal power shall l.
the APRM flux scram trip setting be allowed to exceed 120% of rated thermal power.
2.2 APRM Rod Block Trip Setting (Run Mode) l Reference Technical Specifications: Table 3.2.C-2, 3.1.B.1 When the mode switch is in the run position, the average power range monitor (APRM) rod block trip setting (Saa) shall be:
l Saa s 0.66 W + 62%
j with a clamp at 115% of rated core thermal power and San = APRM rod block trip setting in percent of rated thennal power (1998 MW).
i W=
Percent of drive flow required to produce a rated core flow of 69 Mlb/hr.
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COLR REVISION 11D PAGE 7 OF 26
i PILGRIM NUCLEAR POWER STATION
' ~
- PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 l
2.2 -
APRM Rod Block Trip Setting (Ru_n Mode) (Continued)
The APRM rod block trip setting is valid only for operation using two recirculation loops. Operation with one recirculation loop out of service is restricted by License Condition 3.E.
2.3 Sod Block Monitor Trio Settina Reference Technical Soecification: Table 3.2.C-2 Allowable values for the power-dependent Rod Block Monitor trip i
retpoints shall be:
Reactor Power, P Trip Setpoint
(% of Rated)
(% of Reference Level)
P s 25.9 Not applicable (All RBM Trips Bypassed) 25.9 < P s 62.0 120 62.0 < P s 82.0 115 82.0 < P 110 The allowable value for the RBM downscale trip setpoint shall be 2 94.0%
of the reference level. The RBM downscale trip is bypassed for reactor j
power s 25.9% of rated.
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COLR REVISION 11D PAGE 8 OF 26 l
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PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 l
3.0 CORE OPERATING LIMITS L
3.1 Average Planar Linear Heat Generation Rate (APLHGR)
Reference Technical Specification: 3.11.A L
During power operation, APLHGR for each fuel type as a function of axial location and average planar exposure shall not' exceed the applicable limiting value. The applicable limiting value for each fuel type is the smaller of the flow-and power-dependent APLHGR limits, MAPLHGRr and MAPLHGR,. The flow-dependent APLHGR limit, MAPLHGRr, is -
L the product of the MAPLHGR flow factor, MAPFACF, shown in Figure l
3.1-5 and the MAPLHGR for rated power and flow conditions. The power-dependent APLHGR limit, MAPLHGRe, is the product of the MAPLHGR power factor, MAPFACp, shown in Figure 3.1-6 and the MAPLHGR for rated power and flow conditions. The MAPLHGR for rated power and flow conditions for each fuel type as a function of axial location and average planar exposure are based on the approved l
methodology referenced in Section 5.0 and programmed in the plant process computer. The MAPLHGR for rated power and flow conditions for the limiting lattice in each fuel type (excluding natural uranium) are l
presented in Figures 3.1-1 through 3.1-4.
t f
The core loading pattern for each type of fuel in the reactor vessel is shown l
for the present cycle in Figure 4.0-1.
3.2 Linear Heat Generation Rage (LHGR)
B_e_ferince._T. hai.c31.Sp.e. cifical.ioA 3. I 1.B Sc i
During reactor power operation, the LHGR of any rod in any fuel assembly at any axial location shall not exceed the limits presented in Table 3.2-1.
COLR REVISION 11D PAGE 9 OF 26
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__ _. _. - _ _ =. - - -..
i PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.2-1 LHGR Operatina Limits LHGR Operating Fuel Tvoe Limit (KW/ft)
BP8DRB300 13.4 BP8DQB323 l'4.4 BP8HXB355 14.4 BP9 HUB 378 14.4 i
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COLR REVISION 11D PAGE 10 OF 26
4 E
$a O
O 12.5 12 d2.1 f%
11.5 i i.5
$4 5y 30 a
'im,
ii.o s
N
\\
10.5 y
h ia3
~
oh 5
'o
\\
gx d
9.5
\\
ge 9
s 8.5 C m
8 N
Q 0
5,000 10,000 15,000 20,000 25,000 30,000 35,000 40,000 45,000 rn4
=
PLANAR AVERAGEEXPOSURE (MWD /ST) on o
mo
-^
M9 8
FIGURE 3.1-1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for FucIType BP8DRB300
-________.____.__,_._.1.._
m
=-
s se 13.5 13.1
)%
o
%l
/
^K l
/'"
N,2.,
1.6 7
E 11.5 3 ii
\\,4 E3 s
N M
N g"
o 10.5 T.2
,g 10 m o 1000 1f 9.5 H
' f 200 9
h n
x 8.5 a
4 0
5,000 10,000 15,000 20,000 25,000 30,000 35,000 40,000 45,000 m
on Planar Average Exposure (MWD /ST)
Q 3O IS FIGURE 3.1-2 Maximum Average Planar Linear llent Generation Rate (MAPLHGR) for FucI Type BP8DQB323
13
^
s w5 12.5 12 3 3
f%q 11.s 12 g
g
1.3[,,4 i
t i.4 mO 11 no.\\s o.
y 10.5
\\
o n
\\
5E 9.5
\\x m.
V 1000 8.5 gy m$
< r g
gd 200
]
7.9 7.5
\\
7
\\
6.5 x
\\
m f
5.9b C
5.5 i
Q@
0 5,000 10,000 15,000 20,000 25,000 30,000 35,000 40,000 45,000 50,000 y$
Planar Average Exposure (MWD /ST)
FIGURE 3.1-3: Maximum Average Planar Linear IIcal Generation Rate (MAPLHGR) for Fuel Type HP8HXB355
- ~'
I3
^
s h
12.5 z
12 U
I 1.6 i 3.4 j
11.0, 11.0
[
10.5 0.2 too e
N 5$
9.5 gg 3(9.3 o :53 M
9 rm b(87 u 1000 200 m.o a
3Z 7.5 G
.7 6.5 g
j 6.4 q
6 O
I m
5.5 uog 0
5,000 10,000 15,000 20,000 25,000 30,000 35,000 40,000 45,000 50,000 55,000 60,000 yy Planar Average Exposure (MWD /ST) w FIGURE 3.1-4: Maximum Average Planar Linear IIcat Generation Rate (MAPLHGR) for Fuel Type B P9 HUB 378
. T.
O
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. r h
1.1 s
sa 07
^
me O
f f
n&
/
/
EE O
/////
$0
/j MAPLIIGRp = MAPFACp
- MAPLIIGRSTD h%
M MAPLIIGRSTD = Standard MAPLIIGR Limits O
/
/
from Figures 3.1-1 through 3.1-4 Og 4
MAPFACp = MINIMUM (1.0, Ap+Bp F) h s
/
MAPFAC for p
[
[
scoop tube setpoint ge F = Fraction of Rated Core I%w "k
calibration postioned ho A and B 0.7 7
such that Flowmax=
p p are fuel-type dependent 3Z g
7 constants given below:
N r
112.0 %
(% Rated)
Ap Bp h
Flowmax All Fuci Tynes
/
2 N
117.0 %
0.6 10U 0.4861 0.6784 7
107.0 0.4574 0.6758 t 12.0 0.4214 0.6807
,q I17.0 0.3828 0.6886 8
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0.5 9
Q8 30 50 70 90 I10
-g yQ CORE FLOW (% RATED) i FIGURE 3.1-5 Flow Dependent MAPLHGR Factor (MAPFAC )
l p
.2 a
-m
1.0 S
Q l P> 45%.
/~/
5 9
u a
08 55 2
og 6 0.7 P ss< P s45%
MAIUfGRp = MAPFACp
- MAPLilGRSTD B
,e o
k l
MAPLilGRSTU = Standan! MAPI.IIGR Limits from Figwes 3.1 1 On
( 0.6 th-ush 3.14 P = % Rated Core Thermal Power triE g
g,,, = % Rated Core Thermal Ibwer that Corresponds so the Scipoint q
yp O
I 5 0.5
! C ri -s'a* a-a F '
y for Rypass of Scram Signals Generseed by Closure of Twbine f;
S.ep vai.es o, F si ciesw. ef1., sine Cen i v.i.es g o,5 l
l
.t
/
i (Maximum thypass = 45%)
r t.j O
l Core Flow >50% Rated 8
e 9W 8
For P< 25%: No Thermal Monitoring is Required (No Limits Specified)_
dM t
0.4 y
i Q
gy g
For 25% s P s 45% : P <%va. and Core Flow s 50% Rseed:
d s
i MAPFACp = 0.55 + 0.005 (P - 45%)
O E 0.3 O Z n,
8 For 25% s P s 45% : P < pBronss and Core Flow > 50% Rase f:
N l
l MAPFACp = 0.50 + 0.006 (P - 45%)
d 113 "0
l For 25% s P s 45% en.1 P >P,33 h
.2 g
3 I
MAPFACp = 1.0 + 0.005224 (P - 100%)
m h
0.1 For P> 45% MAPFACp= 1.0 + 0.005224 (P - 100%)
4 O
l l
M E
0'0 E
@O M'" P
=
0 20 40 syrass 60 80 100 b
ME
% RATED CORE TIIERMAL POWER (P)
FIGURE 3.1-6 Power Dependent MAPLIIGR Factor (MAPFAC )
p
1 l
PILGRIM NUCLEAR POWER STATION l
PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.3 Minimum Critical Power Ratio (MCPR)
Reference Technical Soecification: 3.11.C l
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During power operation, the MCPR shall be greater than or equal to the operating limit MCPR. The operating limit MCPR is the greater of the flow-and power-dependent MCPR operating limits, MCPRr and MCPRp.
I l
The flow-dependent MCPR operating limit, MCPRr, is provided in Figure l
3.3-1. For core thermal powers less than or equal to Psyp, the power-dependent MCPR operating limit, MCPRp, is provided in Figure 3.3-2.
j Above Psyp, MCPRp is the product of the rated power and flow MCPR operating limit presented in Tables 3.3-1,3.3-2 and 3.3-3, and the Kp l
factor presented in Figure 3.3-2. Figure 3.3-2 also specifies the maximum value for Psyp. The rated power and flow MCPR operating limits presented in Tables 3.3-1 and 3.3-2 are functions of t for the indicated
)
l MOC and EOC cycle exposures. The rated power and flow MCPR operating limits presented in Table 3.3 3 are functions of t for EOC l
exposures and a final feedwater temperature reduction of up to 75 F.
l The value of t in Tables 3.3-1 and 3.3-2 shall be equal to 1.0, unless it is l
calculated from the results of the surveillance testing of Technical l
Specification 4.3.C as follows:
r.
- r, l.2 5 2 - r, l
Where:
t Average scram time to
- t.,
=
drop out ofNotch 34 N
l E N'S Z, M s.
i in Adjusted analysis mean
=
l scram time I Ni i
p + 1.65cr
=
L[.,M COLR REVISION 11D PAGE 17 OF 26
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i PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02
[
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i 3.3 Minimum Critical Power Ratio (MCPR) (Continued)
Number ofsurveillance tests performed to date in the n
=
present cycle l
l Ni Total number of active control rods
=
i N
Number of active control rods measured in the i*
i
=
i surveillance test
~
Average scram time to drop *out ofNotch 34 position-Ti
=
of all rods measured in the i surveillance test l
Mean of the distribution for average scram
=
insertion time to drop out ofNotch 34 0.937 sec i
l
=
I l
c
=
Standard deviation of the distribution for average Scram insertion time to dropout of Notch 34 l
0.021 sec
=
f f
- j r
l l
t COLR REVISION 11D PAGE 18 OF 26
=-
1 l
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.3-1 i
I The MCPR operating limits (OLMCPR) for operation from the Beginning of Cycle (BOC) l to the End of Cycle (EOC) - 5250 MWD /ST as a function ofI and core flow are:
l OLMCPR (J_)
102% Rated < Core Flow I
Core Flow s102% Rated s107.5% Rated j
i s 1.0 1.40 1.45 1
I f
a i
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1
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l l
t k
i COLR REVISION 1ID PAGE 19 OF 26
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PILGRIM NUCLEAR POWER STATION I
PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 i
Table 3.3-2 EOC MCPR Operating Limits j
The MCPR operating limits (OLMCPR) as a function of t for operation from the End of 1
Cycle (EOC) - 5250 MWD /ST to the EOC with core flow s107.5% of rated are:
l I
OLMCPR (t) t s 0.0 1.39 0.0 < t 5 0.1 1.40 0.1 < t s 0.2 1.40 O.2 < t 5 0.3 1.41 l
0.3 < T s 0.4 1.41 O.4 < t s 0.5 1.42 0.5 < t s 0.6 1.43 l
0.6 < t s 0.7 1.43 l
0.7 < t s 0.8 1.44 I
0.8 < t s 0.9 1.44 0.9 < T s 1.0 1.45 P
G t
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COLR REVISION 11D PAGE 20 OF 26
PILGRIM NUCLEAR POWER STATION f
PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.3-3 EOC MCPR Operating Limits with Feedwater Temocrature Reduction The MCPR operating limits (OLMCPR) as a function of T for operation from the End of Cycle (EOC) - 5250 MWD /ST to the EOC with core flow s107.5% of rated and a feedwater temperature reduction ofup to 75 F are:
l I
OLMCPR (t) t s 0.0 1.41 t
0.0 < t s 0.1 1.42 0.1 < t s 0.2 1.42 0.2 < T s 0.3 1.43 i
0.3 < t s 0.4 1.43 0.4 < t s 0.5 1.44 i
l 0.5 < T s 0.6 1.45 i
0.6 < t s 0.7 1.45 0.7 < t s 0.8 1.46 i
0.8 < T s 0.9 1.46
)
0.9 < t s 1.0 1.47 l
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COLR REVISION 11D PAGE 21 OF 26
O i.7 E
l l
l l
l l
l
\\
Fnr F> o.40:
y
\\
ucFay = u.x:mm (i.20. A F + B )
F p
3 i.6 For F < o 40-g ucrn
=( A F + B )(I + 032(o.40- F))
p F
F p
\\
h where:
F = Fraction of Resed Core Fiow E
\\ ('
\\,
Ap and By a Flow Dependent Constanes OZ
- u. 1.5
\\
oiven Below:
@g lE k
\\
_E k 9-A s
Flowman
^E 8
\\\\ \\ \\
h 102.5
-o37:
1.655 s>k 107.o
-o.ss6 i.697 1 1.4 F
112.0
-o.602 a.747
.O O
cf Scoop sutie setposa 117.o
. o.632 1.so9 j!
Fa _,
x y
/^
N N
6 m,
- =ch ihet h =
s N
\\ \\
k
'*io7$k /
- a.
ll #
NNNN l5 x x x
\\ \\ \\N i.2 s
E
[
o m
!3 1.1 "m
O@
(
2o 3o 4e so so 70 so 90 too tio gQ CORE FLOW (% RATED)
O 4
i FIGURE 3.3-1 Flow Dependent MCPR Limits (MCPR )
p l
"'-"-"4->M4 nm-5-mh
-"-"--""'-~-' ' ' - - ' " " " " ' ' - - - - - ' - " " - - -
- - ^ - ' -
- - - ~ - - - ~ ' - ' - - - - - - ~ ' - - - - - ' ' ' ' - - - - ~ --- - - - " - " " - - ' - ' ' " - " - ~ ' - - - ' ' - - - ~ ' - " - ' - -~ ' - " ' - - - - - - - - - - - - - - ' ' ~ - - ~ - - - ' - - ' ' ~ - - ' - - - - - ' ' - - - ' - - ~ ~ - - - - " " - - - - - - - - - ' - ' - - ' - " - - ' ' - ' - ' - - - - ~ - - " ' - ' - " ' - ' ~ " ' " - " - - - - - - - - - - ' - ' - - " - ~ - ' ' - - - ~ - " - ~ ~ ~ " - - - ~ -
~ - - ~ ' ' " - -
e g
I I
I l
3.4~
h 50 %
Operating Limit MCPRp=Kp
- OLMCPR(IOO)
?
3.2 OLMCPR(100) = Operating Limit MCPR Values for 100% Rased Core Thermal Pbwer
~
[
t fran Table 33-1 and Table 33-2 M
3.0 P = % Rased Core Thermal Pbwer
~
D e
Scram Signals Generseed by Closure of Turbme Soap Valves or Fast Closure of f'Uo PBps= % Rated Core Thermal Power thae Correspnnds to the Scepmns for Bypass of 2.8 y
I I
TierbineControlValves (Maximum Q, = 45%)
g O 2.6 Kp = Rased MCPR Muhiplier as Defined Below:
_Q 2,4 - -
for Care Plow s 50% Rased N
For P < 25%: No Thermal Monienring is Required (No Limits are Specified) h Limit MCPRp i
j For 25% s Ps 45% and P <P%,,.
@Q g 2.2 O
i N
i K
p, _ Rve + KSlo (45% - P1 2.0 g
OLMCPR(100)
~
3,3 Where Kgyp= 1.95 and Kg= 0.0125 for Core Flow s 50% Rased or Og K
= 235 and K,= 0.043 for Core Nw > 50% Rased Fm B
33 Far 25% s Ps 45% and P> %vosss : Kp = I.28 + 0.0134 (45% - P)
,.m g
-- 1.6 U
I I
I For 45% < P < 60%: Kp = 1.15 + 0.00867(60% - P)
%d N,
-- 1.5 N
i it o
i i
g i
Fer P 2 60%.
Kp = 1.0 + 0.00375 (100% - P)
O Z l
7 N
i i
l i
NI i
P orPhypass< Ps45%
j K, for P> 60% j 33 K
f N
/
4 i2
- tr
,g l K, for 45% < P< 60% j 1.1 y C
l eM b
i t
^
3,g,t, 2o 30 40 ""'hyp== 50 60 70 80 90 100 O
l
'"on o[@
% RATED CORE THERMAL POWER (P) 8 1
FIGURE 3.3-2 Power Dependent MCPR Limits (MCPR )
p i
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PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.4 Power / Flow Relationship During Power Operation Reference Technical Specification: 3. l l.D The power / flow relationship shall not exceed the limiting values shown on the Power / Flow Operating Map in Figure 3.4-1.
4.0 REACTOR VESSEL CORE DESIGN Reference Technical Specification: 5.2 i
L The reactor vessel core for the present cycle consists of 580 fuel assemblies of the types listed below. The core loading pattern for each type of fuel is shown for the present cycle in Figure 4.0-1.
l L
Fuel Tvoe Cycle Loaded Number i
i Irradiated I-BP8DRB300 8
136 l-BP8DQB323 9
168 BP8HXB355 10 140 l
New BP9 HUB 378 11 136 Total 580 L
The reactor vessel core contains 145 cruciform-shaped control rods. The control l
- materials used are either boron carbide powder (B C) compacted to approximately 70% of the theoretical density or a combination of boron carbide powder and solid hafnium.
l 5.0-REFERENCES 5.1 NEDE-24011-P-A-10 and NEDE-24011-P-A-10-US, " General Electric Standard Application for Resctor Fuel", February and March,1991.
5.2 NEDC-31852-P, " Pilgrim Nuclear Power Station SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis", September 1990.
5.3 NEDC-31312-P, " ARTS Improvement Program Analysis for Pilgrim l
Nuclear Power Station", September 4,1987.
i COLR REVISION 11D PAGE 24 OF 26
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10 15 20 25 30 35 40 45 50 55 60 65 69 75 80
$n Core Flow (MLB/IIR) 9 38 N
ax FIGURE 3.4-1 Power / Flow Operating Map 2.
3
]
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 1
BEBEBEMBEEBE i
BBBBBRHBiHBiBBBB i
HBBBBBBBBMBIBEMBEM i
~::3BBBBRM BBBBBBBiH BBBBBBBB MiEBIBBBBBBBBBBBBBEMBBBBBB
- R BiBIBBBBBBBBBBBBBRBBBBB8 i
- BBRBBBCBBBIBitiBBBBBEMBs
- 1E R H H H H BE H H H H H BB 3EBIMMMHHHBEMBEMBB i
- RBRMMMMMBBBIMBIBEBE BBM H H H BBM M M M M EMMMMMMME MHHHHHH i
1 3 5 7 9 111315171921232527293133353739414345474951 Fuel Types ( Cycle Loadad)
)'
E BP8DRB300 (Cycle 8)
E BP8HXB355 (Cycle 10) l
@ BP8DQB323 (Cycle 9)
E BP9 HUB 378 (Cycle 11) 1 1
j FIGURE 4.01 Reactor Vessel Core Loading Pattern COLR 3
REVISION 11D PAGE 26 OF 26 J
.