ML20197C547
| ML20197C547 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/31/1998 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20197C544 | List: |
| References | |
| NUDOCS 9809140081 | |
| Download: ML20197C547 (26) | |
Text
.-
PILGRIM NUCLEAR POWER STATION
' PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 (CYCLE 12) 9 2kf6 APPROVED: 64 0
Op6 rations Support Department Manager.
Date APPROVED:
W f
h, 7 f6!((
Nticlear Engineering Services GMup Manager D' ate APPROVED:
4 f
7 Operations Review /domr'nittee Date N
APPROVED:
i Plant Grouplianager
\\ Date 6t1%
APPROVED:
>M-31 A0C,98 Station Director Date I
9809140001 980904 t
PDR ADOCK 05000293 4 p
PDR g
COLR REVISION 12C PAGE 1 OF 26
3 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 TABLE OF CONTENTS Page TITLE / SIGNATURE PAGE..
I 9
TABLE OF CONTENTS.
.2 RECORD OF REVISIONS.
.. 3 LIST OF TABLES..
.4 LIST OF FIGURES..,.......
.5
1.0 INTRODUCTION
....6 2.0 INSTRUMENTATION TRIP SETTINGS.
.7 2.1 APRM Flux Scram Trip Setting (Run Mode).
7 2.2 APRM Rod Block Trip Setting (Run Mode)....
.7 2.3 Rod Block Monitor Trip Setting..
8 j
3.0 CORE OPERATING LIMITS..
.9
{
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).
.18 3.4 Power / Flow Relationship.....
.. 24 4.0 '
REACTOR VESSEL CORE DESIGN.
.. 24
5.0 REFERENCES
. 24 COLR REVISION 12C l
PAGE 2 OF 26
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 i
RECORD OF REVISIONS Egylti9n Efeelive Dats Dmcriptipa 8A Effective date based on Applicable for use during issuance oflicense Cycle 8 Operation amendment by NRC I
9A Effective date based on Applicable for use during t
is:;uance 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 l
initial startup of Cycle 11 Cycle 11 Operation 11B Effective upon final Applicable for use during approval Cycle 11 Operation 11C Effective upon final Applicable for use during approval Cycle 11 Operation llD Effective upon final Applicable for use during approval Cycle 11 Operation 12A Effective date based on Applicable for use during l
issuance oflicense Cycle 12 Operation L
amendment by NRC for i
SLMCPR of 1.08 12B Effective upon final Renumbered Table 3.3-2 approval to 3.3-1, Sh. 2 of 2 and Table 3.3-1 to 3.3-1, Sh.1of2 12C Effective upon final Changed Tech Spec section approval numbers referenced due to Tech Amedment #177.
j Pages affected: 6,24 i
COLR REVISION 12C PAGE 3 OF 26
l PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 i
LIST OF TABLES NMmher Ih!.9 bgg 3.2-1 LHGR Operating Limits 10 3.3-1, Sh.1 of 2 MOC MCPR Operating Limits 20 3.3-1, Sh. 2 of 2 EOC MCPR Operating Limits 21 i
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COLR REVISION 12C j
PAGE 4 OF 26
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 LIST OF FIGUREJ Number Title Page
{
a f
3,1-1 Maximum Average Planar Linear Heat Generation 11 Rate (MAPLIIGR) for Fuel Type BP8DQB323 3.1-2 Maximum Average Planar Linear Heat Generation 12 Rate (MAPLHGR) for Fuel Type BP8HXB355 3.1-3 Maximum Average Planar Linear Heat Generation 13 Rate (MAPLHGR) for Fuel Type BP9 HUB 378 3.1-4 Maximum Average Planar Linear Heat Generation 14 Rate (MAPLHGR) for Fuel Type P9 DUB 408-6G5.0/7G4.0 i
3.1-5 Maximum Average Planar Linear Heat Generation 15 I
Rate (MAPLHGR) for Fuel Type P9 DUB 408-16GZ1 3.1-6 Flow-Dependent MAPLHGR Factor (MAPFACr) 16 3.1-7 Power-Dependent MAPHLGR Factor (MAPFACp) 17 3.3-1 Flow-Dependent MCPR Limits (MCPRr) 22 3.3-2 Power-Dependent MCPR Limits (MCPRp) 23 I
3.4-1 Power / Flow Operating Map 25 4.0-1 Reactor Vessel Core Loading Pattern 26
)
1 COLR REVISION 12C PAGE 5 OF 26
_ _ _ _ ~
PILGRIM NUCLEAR POWER STATION l
PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 i
1.0 INTRODUCTION
This report provides the cycle-specific limits for operation of the Pilgrim Nuclear l
Power Station (PNPS) during Cycle 12. In this report, Cycle 12 will frequently be referred to as the present cycle.
Although this report is not part of the PNPS Technical Specifications, the Technical Specifications refer to this report for the' applicable values of the following fuel-related parameters:
Reference Tgghnical Specificati.pn APRM Flux Scram Trip Setting (Run Mode)
Table 3.1.1 APRM Rod Block Trip Setting (Run Mode)
Table 3.2.C-2
[
Rod Block Monitor Trip Setting Table 3.2.C-2 Average Planar Linear Heat Generation Rate 3.11. A Linear Heat Generation Rate (LHGR) 3.11.B Minimum Critical Power Ratio (MCPR) 3.ll.C Power / Flow Relationship 3.11.D Reactor Vessei Core Design 4.2 i
If any of the core operating limits in this report are exceeded, actions will be taken as defined in the referenced Technical Specification.
The core operating limits in this report have been established for the present cycle using the NRC-approved methodology provided in the documents listed both in Section 5.0, References, and in Technical Specification 5.6.5. These limits are established such that the applicable limits of the plant safety analysis are met.
l l
l l
l l
l COLR REVISION 12C l
PAGE 6 OF 26 I
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 l
' 2.0 INSTRUMENTATION TRIP SETTINGS:
l j
2.1 APRM Flux Scram TripJstiing_(Run Mp_de)
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%
with a clamp at 120% of rated core thermal power and 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 of 69 Mlb/hr.
The APRM flux scram trip setting is valid only for operation using two recirculation loops. Operation with one recirculation Sop out of service is restricted by License Condition 3.E.
In accordance with Technical Specification Table 3.1.1, Note 15, for no combination ofloop recirculation flow rate and core thermal power shall the APRM flux scram trip setting be allowed to exceed 120% of rated thermal power.
2.2 APRM Rod Block Trip Setting (Run Mode) j 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 (Su) shall be:
Su s 0.66 W + 62%
with a clamp at 115% of rated core thermal power and Su = APRM rod block trip setting in percent of rated thermal power (1998 MW).
i l
W=
Percent of drive flow required to produce a rated j
l core flow of 69.Mlb/hr.
)
i COLR REVISION 12C PAGE 7 OF 26
~
TILGR.lM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 APRM Rod Blo' k Trip Setting (Run Mode) (Continued)
, 2.2 c
l l
The APRM rod block trip setting is valid only for operation using two recirculation loops. Operation with one recirculation loop out of service is l-restricted by License Condition 3.E.
l 2.3 Rod Block Monitor Trip Setting T
Reference Technical Specification: Table 3.2.C-2 Allowable values for the power-dependent Rod Block Monitor trip setpoints shall be:
Reactor Power, P Trip Setpoint
(% of Rated)
(% of Reference Level) l 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 l
The allowable value for the RBM downscale trip setpoint shall be 2 94.0%
l of the reference level. The RBM downscale trip is bypassed for reactor l
power s 25.9% of rated.
l
[
l 4
i COLR l
REVISION 12C j
PAGE 8 OF 26 i
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.0 CORE OPERATING LIMITS 3.1 Average Planar Linear Heat Generation Rate (APLHGR)
Reference Tesimical Specification: 3. I I. A 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, MAPFACr, shown in Figure 3.1-6 and the MAPLHGR for rated power and flow conditions. The power-dependent APLHGR limit, MAPLHGRe, is the product of the MAPLHGR power factor, MAPFACe, shown in Figure 3.1-7 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 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 presented in Figures 3.1-1 through 3.1-5.
The core loading pattern for each type of fuel in the reactor vessel is shown for the present cycle in Figure 4.0-1.
I 3.2 Linear Heat Generation Raye (LHGR)
Reference Technical Snecification: 3.11.B 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.
I COLR REVISION 12C PAGE 9 OF 26
= _ _ _.... _ _
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.2-1 LHGR Operating Limits LHGR Operating Fuel Typs Limit (KW/fD BP8DQB323 14.4 BP8HXB355 14.4 BP9 HUB 378 14.4 BP9 DUB 408-6G5.0/7G4.0 14.4 BP9 DUB 408-16GZ1 14.4 i
COLR REVISION 12C l
PAGE 10 OF 26
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10 1000 1 f 9.5 h
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8.5 5
0 5,000 10,000 15,000 20,003 25,000 30,000 35,000 40,000 45,000 2
Planar AverageExposme (MWD /ST) on 1.
8 38 FIGURE 3.1-1 Maximum Average Planar Linear Heat Generation Rate
[
(MAPLHGR) for FuelType BP8DQB323
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- 3
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mO Planar Average Eximme (MWD /ST) w og i
r FIGURE 3.1-2: Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for Fuel Type BP8HXB355 S
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- 8 Planar Average Earmme (MWD /ST) h o
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FIGURE 3.1-3: Maximum Average Planar Linear Heat Generadon Rate (MAPLHGR) l'or Fuel Type BP9 HUB 378 j
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gg Planar AverageExposure pq FIGURE 3.1'.4: Maximum Average Planar IJnear Heat Generation i
Rate (MAPLHGR)forFhelType P9 DUB 408-6G5.0/7G4.0 i
- - ~ _ _ _ _ _. _ _ _ _ _ _
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FIGURE 3.1'-5: Maximum AveragePlanarLinearHeat Generation
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Rate (MAPLHGR)forFtnelType P9 DUB 408-16GZ1 1
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FIGURE 3.1-6 Flow Dependent MAPLHGR Factor (MAPFAC )
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MAPPACp= 1A+0.0052M @- 100%)
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% RA*IED CORETHERMALPOWER(P)
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FIGURE 3.1-7 Power Dependent MAPLHGR Factor (MAPFAC )
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PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.3 Minimum Critichl Power Rajio (MCPR)
Reference Technical Specification: 3.11.C 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.
The flow-dependent MCPR operating limit,' MCPRr, is provided in Figure 3.3-1. For core thermal powers less than or equal to Payp,,,, the power-dependent MCPR operating limit, MCPRe, is provided in Figure 3.3-2.
Above Peyp,,,, MCPRp is the product of the rated power and flow MCPR operating limit presented in Table 3.3-1, and the Kp factor presented in Figure 3.3-2. Figure 3.3-2 also specifies the maximum value for Payp,,,.
The reed power and flow MCPR operating limits presented in Tables 3.3-1 and 3.3-2 are functions of T for the indicated MOC and EOC cycle exposures.
The value ofI in Table 3.3-1 shall be equal to 1.0, unless it is calculated from the results of the surveillance testing of Technical Specification 4.3.C, as follows:
r.., - r, 1.2 5 2 - r, Where:
Average scram time to t,v.
=
drop out ofNotch 34
[Nm
- *)
=
Zu is) in Adjusted analysis mean
=
scram time Ni
+ 1.65cr
=
T[ dei M
COLR REVISION 12C l
PAGE 18 OF 26
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02
, 3.3 Minimum Critical Power Ratio (MCPR) (Continued)
Number of surveillance tests performed to date in the n
=
present cycle Ni Total number of active control rods
=
Number of active control rods measured in the i*
N;
=
surveillance test Ti Average scram time to drop out of Notch 34 position
=
of all rods measured in the i* surveillance test Mean of the distribution for average scram
=
insertion time to drop out ofNotch 34 0.937 sec
=
Standard deviation of the distribution for average o
=
scram insertion time to dropout of Notch 34 0.021 sec
=
i COLR REVISION 12C PAGE 19 OF 26
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.3-1, Sh. I of 2 MOC MCPR Onerating Limits The MCPR operating limits (OLMCPR) as a function ofI for operation from the Beginning of Cycle (BOC) to the End of Cycle (EOC) - 4361 MWD /ST with core flow s107.5% of rated are:
9 I
OLMC.PR (t)
T s 0.0 1.31 0.0 < T s 0.1 1.31 0.1 < T s 0.2 1.31 0.2 < t s 0.3 1 31 0.3 < t s 0.4 1.31 0.4 < T s 0.5 1.32 0.5 < t s 0.6 1.33 0.6 < T s 0.7 1.34 0.7 < t s 0.8 1.34 0.8 < t 5 0.9 1.35 0.9 < t s 1.0 1.36 COLR REVISION 12C g
PAGE 20 OF 26
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 a
Table 3.3-1, Sh. 2 of 2 E.Q_C MCPR OperatingLimits The MCPR operating limits (OLMCPR) as a function of T for operation from the End of Cycle (EOC) - 4361 MWD /ST to the EOC with core flow s107.5% of rated are:
I OLMCPR (t) t s 0.0 1.36 0.0 < t s 0.1 1.37 O.1 < T s 0.2 1.37 0.2 < t s 0.3 1.38 0.3 < T s 0.4 1.38 0.4 < T s 0.5 1.39 0.5 < t s 0.6 1.40 0.6 < T s 0.7 1.40 0.7 < t s 0.8 1.41 l
0.8 < T s 0.9 1.41 0.9 < t s 1.0 1.42 1
~
COLR REVISION 12C PAGE 21 OF 26
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 s
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PAGE 22 OF 26
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l ym Opwebig LhnisMCIRp.
OperatingLiniltMCPRp =Kp *0LMCPROOO) p 3d~
g forOwe hw>$0% Rated
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3.2 I
OLMCPR(Itto) = Operating Linilt MCPR Values for 100% Rased CoreThennel Power Z
l franTables 3.31 and 3.3-2 2 3.0 P= % Rated Core 1herrnsIPower l
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g= % Rased Core 1herinal Power that Comsponde no ths Seepahit for Bypass of mm Seren signals Generseed try Closure of habine soap Vehus or Past Closure of Z p:
i 2.8 hubineControlValves (Maxinruni Q = 45%)
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_l Kp = Rased MCPR Muhlpfler as Defined Below:
n O
Operating thaltMCPRp For P < 25%: No Thermal Monhoring in Required (Pto1&nbs are Speelfled) 2.4 --
forCorePhrws50%Reseg On L
Par 25% < Pf 45% and Pc %.
P m m 2.2 I
M i
K
- Kave+Kg ragg.pg g
l O
I N
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OLMCPROOO)
Q l
2.0 w
m i
I EO Where g 1.97 and Kgkr 0A126 ihr CorePlow $50% Rased er Og g,g Kg = 2.3F and Kh=0.0434 forCarePlow>50% Rased For25% cps 43% sedP>IIlvenssi K =1.2B+0A134(45%-P) p
- 1.6 HH I
Par 45% <P<60%: Kp =1.15+0.00867(605-P) h
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0
's ParP:t60%:
Kp =1.0+0.00375(100%-F) g2
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Kp ferPh<Ps45%
i K pforP>60% j A
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l 20 30 40 " M 50 60 70 80 90 100 d
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% RATED CORETHERMALPOWER(P) l 0o mO t
ER E f
i FIGURE 3.3-2 Power Pependent MCPR Limits (MCPR )
p 3
t
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02
, 3.4 Power / Flow Refationship During Power Operation Reference Technical S ecification: 3.11.D 2
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 VES.SEL CORE DESIGN Reference Technical Soccification: 4.2 I
The reactor vessel core for the present cycle consists of 580 fuel assemblies of the types listed below. The core loading pattem for each type of fuel is shown for the present cycle in Figure 4.0-1.
EusLType C_ycle Loaded Number Irradiated BP8DQB323 9
96 BP8HXB355 10 140 BP9 HUB 378 11 136 New P9 DUB 408-6G5.0/7G4.0 12 64 P9 DUB 408-16GZ1 12 144 Total 580 The reactor vessel core contains 145 cruciform-shaped control rods. The control materials used are either boron carbide powder (B4C) compacted to approximately 70% of the theoretical density or a combination of boron carbide powder and solid hafnium.
5.0 REFERENCES
5.1 NEDE-24011-P-A-13 and NEDE-24011-P-A-13-US, " General Electric Standard Application for Reactor Fuel", August,1996.
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 Nuclear Power Station", September 4,1987.
COLR REVISION 12C j
PAGE 24 OF 26
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APRMSCRAM 0.66W + 69%
0 120 l
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3 to 15 20 25 30 35 40 45 50 55 60 65 s
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.tn CoreFlow(MLB/HR) a U
oe ME B
l mC FIGURE 3A-1 Power / Flow Operating Map-l l
i PILGRIM NUCLEAR POWER STATION j
PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 i
HHHHHHH i
HHHHHHHHH l
MMMMMMME4HHH
- ME434DiBENDiBEBEHBEE4E4 l
lui4E4BBiti+ENHISBIE4BIBBBB
':-IEEEitBIBBBBBlitBBBBBEBBBB l
l HitBEECEEBIBBBBBBBBBBBBBB
- H B I M E C B E B R M B I B E R H H i+
l
': ME4E1HE1E4BBBBBEMBBBEM
- MBEECE4BIBiBlitBIBIBERGH MBBB4E4ME4HMMEGRE l
l NEGBBBBMI4BBBBBB l
MHy4HMEM 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 l
l FuelTypes (CycleInded) l E BP8DQB323 (Cycle 9)
E BP9 HUB 378 (Cycle 11) i
,@ BP8HXB355 (Cycle 10)
S P9 DUB 408-6G5.0RG4.0 (Cycle 12)
E P9 DUB 408-16GZ1 (Cycle 12)
FIGURE 4.0-1 i
Reactor Vessel Core Loading Pattern j
COLR i
4 REVISION 12c I
PAGE 26 OF 26
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