ML11172A292

Submittal of Fuel Cycle 19, Core Operating Limits Report, Revision 31

ML11172A292
Person / Time
Site:	Pilgrim
Issue date:	06/08/2011
From:	Jeffery Lynch Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML11172A292 (52)

Text

Entergy Nuclear Operations, Inc.

SEntergy Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 June 8, 2011 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

SUBJECT:

Entergy Nuclear Operations, Inc.

Docket No.: 50-293 License No.: DPR-35 Pilgrim Fuel Cycle 19, Core Operating Limits Report, Revision 31 LETTER NUMBER: 2.11.039

Dear Sir or Madam:

The enclosed revision of Pilgrim's Core Operating Limits Report (COLR) is submitted in accordance with the requirements of Pilgrim's Technical Specification 5.6.5. Revision 31 provides cycle-specific limits for operating Pilgrim during cycle 19.

This letter contains no new commitments.

Should you require further information concerning COLR, Revision 31, please contact me at (508) 830-8403.

Sincerely, JosepRLy Licensing Manager WGL/dm

Enclosure:

PNPS Core Operating Limits Report, Revision 31(51 pages) cc: U.S. Nuclear Regulatory Commission Mr. Richard Guzman, Project Manager Region I Plant Licensing Branch I-1 475 Allendale Road Office of Nuclear Reactor Regulation King of Prussia, PA 19406 U.S. Nuclear Regulatory Commission One White Flint North, O-8C2 11555 Rockville Pike Rockville, MD 20852 Senior Resident Inspector 4o0(

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 (CYCLE 19)

LBDCR2011-00 Documents Approvals Cycle 19 COLR Revision 31 Page 1 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 TABLE OF CONTENTS Page T IT LE & C O V E R PA G E ........................................................................................................ 1 TABLE OF CONTENTS ..................................................................................................... 2 R EC O R D O F R EV IS IO NS .................................................................................................... 3 LIST O F T A BLE S ....................................................................................................................... 4 LIST O F F IG UR E S ..................................................................................................................... 5 1.0 INTR O D UC T IO N ..................................................................................................... 6 1.1 Stability Option 1-D Exclusion Region and Buffer Zone ............................................ 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) .............................................................. 12 2.3 Rod Block Monitor Trip Setting ................................................................................ 12 3.0 CORE OPERATING LIMITS ..................................................................................... 17 3.1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) .................... 17 3.2 Linear Heat Generation Rate (LHGR) .................................................................... 37 3.3 Minimum Critical Power Ratio (MCPR) .................................................................... 41 3.4 Power/Flow Relationship During Power Operation ................................................... 46 4.0 REACTOR VESSEL CORE DESIGN ....................................................................... 49 5 .0 R E F E R E N C E S .............................................................................................................. 51 Cycle 19 COLR Revision 31 Page 2 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 RECORD OF REVISIONS Revision Effective Date Description 8A Effective date based on issuance of Applicable for use during Cycle 8 Operation license amendment by NRC 9A Effective date based on issuance of Applicable for use during Cycle 9 operation license amendment by NRC for ARTS and SAFER/GESTR 10A Effective date based on initial startup Applicable for use during Cycle 10 Operation of Cycle 10 11A Effective date based on initial startup Applicable for use during Cycle 11 Operation of Cycle 11 11B Effective upon final approval Applicable for use during Cycle 11 Operation 11C Effective upon final approval Applicable for use during Cycle 11 Operation 11D Effective upon final approval Applicable for use during Cycle 11 Operation 12A Effective date based on issuance of Applicable for use during Cycle 12 Operation license amendment by NRC for SLMCPR of 1.08 12B Effective upon final approval Renumbered Table 3.3-2 to 3.3-1, Sh. 2 of 2 and Table 3.3-1 to 3.3-1,Sh. I of 2 12C Effective upon final approval Changed Tech Spec section numbers referenced due to Tech Amendment #177.

Pages affected: 6, 24 12D Effective upon final approval Incorporated stability log-term solution option I-A.

13A Effective upon final approval Applicable for use during Cycle 13 Operation 14A Effective upon final approval Applicable for use during Cycle 14 Operation 15A Effective upon final approval Applicable for use during Cycle 15 Operation 15B Effective upon final approval Changed MAPLHGR Limits for GE14 fuel in response to an input error GE corrected.

Applicable for use during Cycle 15 Operation 16A Effective upon final approval Applicable for use during Cycle 16 Operation 16B Effective upon final approval Core Loading Change to replace leaking fuel bundle JLG621. Clarified P-F Map graphic on P.

36. Applicable for use during Cycle 16 Operation 25 Effective upon final approval Limits for Single Loop Operation were incorporated. Rev number scheme changed to Merlin Convention 26 Effective upon final approval Applicable for use during Cycle 17 Operation 27 Effective upon final approval Corrected typographical errors on p. 30, 34,38,39 per CR-PNP-2008-256 and 285 28 Effective upon final approval Extended Tables 3.1-1 to 63.5 GWD/ST (70 GWD/MT), updated Fig. 3.1-1, section 3.1 &

references, addressed CR-PNP-2009-01066 29 Effective upon final approval Applicable for use during Cycle 18 Operation 30 Effective upon final approval Applicable for use during Cycle 19 Operation 31 Effective upon final approval Corrected typographical error on fig.3.4-1 Cycle 19 COLR Revision 31 Page 3 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 LIST OF TABLES Number Title Page 2.1-1 Formulae for APRM Flux Scram Trip Settings in Figure 2.1-1 8 2.1-2 Formulae for APRM Flux Scram Trip Settings in Figure 2.1-2 9 2.2-1 Formulae for APRM Rod Block Trip Settings in Figure 2.2-1 13 2.2-2 Formulae for APRM Rod Block Trip Settings in Figure 2.2-2 14 3.1-1 MAPLHGR Limits for Rated Power and Rated Flow for GE14 Fuel 18 3.1-2 MAPLHGR Limits for Rated Power and Rated Flow for GNF2 Fuel 25 3.3-1 MCPR Operating Limits At Rated Power and Rated Flow 42 Cycle 19 COLR Revision 31 Page 4 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 LIST OF FIGURES Number Title Page 2.1-1 Allowable APRM Flux Scram Trip Settings - TLO 10 2.1-2 Allowable APRM Flux Scram Trip Settings - SLO 11 2.2-1 Allowable APRM Rod Block Trip Settings - TLO 15 (Normal Feed water Temperature) 2.2-2 Allowable APRM Rod Block Trip Settings - SLO 16 (Normal Feed water Temperature) 3.1-1 Most Limiting MAPLHGR 34 3.1-2 Flow-Dependent MAPLHGR Factor (MAPFACF) 35 3.1-3 Power-Dependent MAPHLGR Factors 36 3.2-1 Most Limiting LHGR for GE14 Fuel at Rated Power and Rated Core 38 Flow 3.2-2 Flow-Dependent LHGR Factor (LHGRFACF) 39 3.2-3 Power-Dependent LHGR Factors 40 3.3-1 Flow-Dependent MCPR Limits (MCPRF) 43 3.3-2 Power-Dependent MCPR Limits (MCPRp), Turbine Bypass Assumed 44 Operable and Normal and Reduced Feedwater Temperature 3.3-3 Power-Dependent MCPR Limits (MCPRp), Turbine Bypass Assumed 45 Out Of Service and Normal and Reduced Feedwater Temperature 3.4-1 Power/Flow Operating Map, Scram and Rod Block Data Based on 47 Allowable Values - TLO 3.4-2 Power/Flow Operating Map, Scram and Rod Block Data Based on 48 Allowable Values - SLO 4.0-1 Reactor Vessel Core Loading Pattern 50 Cycle 19 COLR Revision 31 Page 5 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02

1.0 INTRODUCTION

This report provides the cycle-specific limits for operation of the Pilgrim Nuclear Power Station (PNPS) during Cycle 19. In this report, Cycle 19 will be referred to as the present cycle.

Although this report is not a part of the PNPS Technical Specifications, the Technical Specifications refer to this report for the applicable values of the following fuel-related parameters:

Reference Technical Specification 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) 3.11.C Power/Flow Relationship 3.11.D Reactor Vessel Core Design 4.2 If any of the core operating limits in this report is 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 in Technical Specification 5.6.5. These limits are established such that the applicable limits of the plant safety analysis are met.

1.1 Stability Option I -D Exclusion Region and Buffer Zone.

The reactor shall not be intentionally operated within the Exclusion Region given in Figure 3.4-1, for Two Loop Operation (TLO) and Figure 3.4-2 for Single Loop Operation (SLO). Immediate exit is required for inadvertent entry into the exclusion region.

The reactor shall not be intentionally operated within the Buffer Zone given in Figure 3.4-1 for TLO and Figure 3.4-2, for SLO when the on-line Stability Monitor is inoperable.

Allowable values for APRM Scram and Rod Block trip set points are defined in Section 2.

Cycle 19 COLR Revision 31 Page 6 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 2.0 INSTRUMENTATION TRIP SETTINGS:

2.1 APRM Flux Scram Trip Setting (Run Mode)

Ref. Technical Specifications: Table 3.1.1 APRM flux scram Allowable Trip Set points (ATSP) for TLO are shown on Figure 2.1-1. The scram set point curve clamps power at 120% of rated core thermal power. Formulae used to develop Figure 2.1-1 are listed in Table 2.1-1.

APRM flux scram Allowable Trip Set points (ATSP) for SLO are shown on Figure 2.1-2, respectively. The scram set point curve clamps power at 120% of rated core thermal power.

Formulae used to develop Figure 2.1-2 are listed in Table 2.1-2.

In accordance with Technical Specification Table 3.1.1, Note 15, for no combination of loop recirculation flow rate and core thermal power shall the APRM flux scram trip setting be allowed to exceed 120% of rated thermal power. Flow clamp feature is not used in Cycle 19.

Drive Flow to Core Flow relationship:

APRM Trip settings use Drive flow to determine the power trip setting for both scrams and rod blocks, as the drive flow is a more reliable flow indication than core flow. The analysis calculates the stability based trip settings based on Core Flow.

Drive Flow (WD) normalization with core flow shall be done such that 100% Drive Flow with Two Loops corresponds to 100% Rated Core Flow of 69 M#/hr.

Source: Reference 5.6, sec. 2.1 Cycle 19 COLR Revision 31 Page 7 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 2.1-1 Formulae For Allowable APRM Flux Scram Settings in Figure 2.1-1 Two Loop Operation Allowable Trip Set Point Drive Flow Range (ATSP)

C C D D  % Rated SLOPE INTERCEPT 0.20 71.5 0 :5 WD "5 22.5 0.71 60.0 22.5 < WD ! 55.9 0.65 70.6 55.9 < Wo ! 76 0 120.0 76 < WD < 125 Notes:

1. ATSP=C*%WD+D,ATSPisin%Power

2. Figure 2.1-1 shows the plot of ATSP vs. WD.

3. Reference 5.6, Table l.a is the basis for the values of constants listed in this Table.

Cycle 19 COLR Revision 31 Page 8 of 51 1

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 2.1-2 Formulae For Allowable APRM Flux Scram Settings in Figure 2.1-2 Single Loop Operation Allowable Trip Set Point Drive Flow Range (ATSP)

C D SLOPE INTERCEPT  % Rated 0.20 69.5 0 !5 WD < 32.5 0.71 52.9 32.5 < WD 5 65.9 0.65 64.1 65.9 < WD 5 86 0 120.0 86 < WD ; 125 Notes:

1. ATSP=C*%WD+D,ATSPisin%Power

2. Figure 2.1-2 shows the plot of ATSP vs. WD.

3. Reference 5.6, Table 1.b is the basis the values of constants listed in this Table.

Cycle 19 COLR Revision 31 Page 9 of 51 I

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.1-1 Allowable APRM Flux Scram Trip Settings - TLO (Normal Feedwater Temperature) 130.0.......................~..

a*.120.0 i ...........................I

..

...I

-.-.---.... i ........ *.............

--.--..-. ---:l2OOJI' ,  : ! 7......

............

...

...

0110.0 -.-.

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.

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.i/ . ..

...................

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.... . ........ .. ... ........... ..... ...

..... -.............

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. ........ .................

.. .........

i.. . ....,...

a. 70*0.0'I,-:: ............

..

. . . . . ......... - I. .. .......

.....

. ....... ... ...

................ .................

0 10 20 30 40 50 60 70 80 90 100 110 120 WD, Drive Flow, %

Cycle 19 COLR Revision 31 Page 10 of 51 1

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.1-2 Allowable APRM Flux Scram Trip Settings - SLO (Normal Feedwater Temperature) 13 0 .0 .... .. ........"....

......

12 0 .0 j . .......... ............

........ .. ............

.... .

..........

0 110.0 1....................i .............. . . . i ... . . . ................

.....

.......

• .....

a. .I I . ......-..

..

0.0 . .............

u0 . . .... . ....... ...------...

.........

. ..........

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.1. - ..

..-.............

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8 0 .0 .............

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......... K............

i.......... .........

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!..........

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0 10 20 30 40 50 60 70 80 90 100 110 120 WD, Drive Flow, %

Cycle 19 COLR Revision 31 Page 11 of 51 I

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 2.2 APRM Rod Block Trip Setting (Run Mode)

Reference Technical Specifications: Table 3.2.C-2, 3.1.1B.1 When the mode switch is in the RUN position, the Average Power Range Monitor (APRM) rod block Allowable Trip setting (ATSPRB) as a function of drive flow for Two Loop Operation shall be as given by Figure 2.2-1. The ATSPRB is clamped at 115% of rated core thermal power. Formulae that form the basis of the Figure 2.2-1 are listed in Table 2.2-1. The flow clamp feature is not used in Cycle 19.

When the mode switch is in the RUN position, the Average Power Range Monitor (APRM) rod block Allowable Trip setting (ATSPRB) as a function of drive flow for Single Loop Operation shall be as given by Figure 2.2-2. The ATSPRB is clamped at 115% of rated core thermal power. Formulae that form the basis of the Figures 2.2-2 are listed in Table 2.2-2. The flow clamp feature is not used in Cycle 19.

2.3 Rod Block Monitor Trip Setting

References:

Technical Specification Table 3.2.C-2, Ref. 5.15, Ref. 5.10 Table 4.5 (b)

Allowable values for the power-dependent Rod Block Monitor trip set points shall be:

Reactor Power, P Trip Set point (Allowable Value)

(% of Rated) (% of Reference Level)

P < 25.9 Not applicable (All RBM Trips Bypassed) 25.9 < P _ 62.0 122 62.0 < P < 82.0 118 82.0 < P 113 The allowable value for the RBM downscale trip set point shall be _ 94.0% of the reference level. The RBM downscale trip is bypassed for reactor power !525.9% of rated (Technical Specification Table 3.2.C-1, Note 5). Analytical Value of Rod Block set point of 117% is justified as the Rod Withdrawal Error is expected to reduce MCPR by 0.28 if this set point is used. Since the minimum OLMCPR value is 1.49, a reduction of 0.28 in MCPR, starting with operation at OLMCPR, is expected to lower MCPR to 1.21. This is substantially above the Safety Limit MCPR of 1.08. Allowable value of the HTSP is set at 113 % to provide additional conservatism to account for uncertainties. Table 4-5(b) of Reference 5.10 with a more restrictive OLMCPR of 1.35 was used to determine the RBM set points with margin.

Cycle 19 COLR Revision 31 Page 12 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 2.2-1 Formulae For Allowable APRM Rod Block Settings in Figure 2.2-1 Two Loop Operation APRM Rod Block Allowable Trip Set Drive Flow Range Point (ATSPRB)

C D SLOPE INTERCEPT %Rated 0.20 66.5 0 < WD < 22.5 0.71 55.0 22.5 < WD 5 55.9 0.65 63.6 55.9 < WD s 79.1 0 115.0 79.1 < WD < 125 Notes:

1. ATSPRB= C %WD + D, ATSPRB is in %Power

2. Figure 2.2-1 shows the plot of ATSPRB vs. WD.

3. Reference 5.6, Table l.a is the basis for the values of constants listed in this Table.

Cycle 19 COLR Revision 31 Page 13 of 51 1

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 2.2-2 Formulae For Allowable APRM Rod Block Settings in Figure 2.2-2 Single Loop Operation APRM Rod Block Allowable Trip Set Drive Flow Range Point (ATSPRB)

C D  % Rated SLOPE INTERCEPT 0.20 64.5 0 5 WD < 32.5 0.71 47.9 32.5 < Wo : 65.9 0.65 57.1 65.9 < WD :5 89.1 0 115.0 89.1 < Wo !5 125 Notes:

1. ATSPRB=C % WD + D, ATSPRB is in % Power

2. Figure 2.2-2 shows the plot of ATSPRB vs. WD.

3. Reference 5.6, Table 1.b is the basis for the values of constants listed in this Table.

Cycle 19 COLR Revision 31 Page 14 of 51 1

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.2-1 Allowable APRM Flux Rod Block Trip Settings - TLO (Normal Feedwater Temperature) 120.0

-110.0 a.

4"100.0 4/)

u 90.0 o 80.0 r 70.0.

60.0 0 10 20 30 40 50 60 70 80 90 100 110 120 WD, Drive Flow, %

Cycle 19 COLR Revision 31 Page 15 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.2-2 Allowable APRM Flux Rod Block Trip Settings - SLO (Normal Feedwater Temperature) 120.0

4. 110.0 (L

., 100.0 0

u 90.0 O

o 80.0

, 70.0 60.0 0 10 20 30 40 50 60 70 80 90 100 110 120 WD, Drive Flow, %

51 19 COLR Cycle Page 16 of Revision 31

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.0 CORE OPERATING LIMITS 3.1 Maximum Averaqe Planar Linear Heat Generation Rate (MAPLHGR)

Reference Technical Specification: 3.11 .A During power operation, MAPLHGR 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-dependent and power-dependent MAPLHGR limits, MAPLHGRF and MAPLHGRp. The flow-dependent MAPLHGR limit, MAPLHGRF, is the product of the MAPLHGR flow factor, MAPFACF, shown in Figure 3.1-2 and the MAPLHGR for rated power and flow conditions, given in Tables 3.1-1 and 3.1-2 for GE14 and GNF2, respectively. The power-dependent MAPLHGR limit, MAPLHGRp, is the product of the MAPLHGR power factor, MAPFACp in Figure 3.1-3 and the MAPLHGR limit for rated power and flow conditions, given in Tables 3.1-1 and 3.1-2.

MAPLHGR for rated power and flow conditions for the most limiting lattice in each fuel type (excluding natural uranium lattices) are presented in Figure 3.1-1.

MAPLHGR limits are based on ECCS-LOCA considerations. For each lattice type, the MAPLHGR values for rated power and flow conditions are listed in Tables 3.1-1 and 3.1-2, which are obtained from the Supplemental Reload Licensing Report (Ref. 5.15).

Pbywass is the power level below which more restrictive thermal limits are applied, as the Turbine Stop Valve closure and Turbine Control Valve fast closure scrams are assumed to be bypassed. It can be set anywhere in the range from 32.5% power to 45% power. Pbypass is currently set at 32.5% power. If this setting is changed in the future, then the appropriate thermal limits can be determined using Tables 3.1-1 and 3.1-2 with Figure 3.1-3.

When in Single Loop Operation, an SLO Multiplier of 0.8 for GE14 fuel and 0.89 for GNF2 fuel applies to the Rated MAPLHGR limit. At off rated conditions, MAPLHGR limit is the lower of the SLO Multiplier times the rated MAPLHGR limit, the MAPLHGRP or MAPLHGRF.

Per the GNF letter in Reference 5.22, the dashes on the MAPLHGR Tables in the SRLR indicate that no specific calculation of MAPLHGR limit was done at that point.

Additionally, the limit value given for last exposure state point listed is applicable for higher exposures up to 63.5 GWD/ST (70 GWD/MT). This is consistent with LOCA analysis reports (References 5.3 and 5.21). As in previous cycle, 3D monicore is designed to apply the MAPLHGR limits consistent with this explanation.

Cycle 19 COLR Revision 31 Page 17 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 MAPLHGR Limits for Rated Power and Rated Flow for GE14 Fuel Average Bundle Type: GE14-PIODNAB399-10G6.0/3G5.01 G2.0-10OT-145-T6-2828 (GE14C)

Planar Exposure MAPLHGR Limit (kW/ft)

Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT GWd/ST 6843 6844 6845 6846 6847 6848 0 0.00 9.8 8.79 8.76 8.74 10.21 10.89 0.22 0.20 9.71 8.86 8.84 8.82 10.16 10.86 1.1 1.00 9.5 8.96 8.96 8.95 10.01 10.78 2.2 2.00 9.44 9.1 9.13 9.12 9.98 10.77 3.31 3.00 9.45 9.23 9.31 9.31 10.01 10.8 4.41 4.00 9.49 9.31 9.5 9.5 10.05 10.84 5.51 5.00 9.53 9.4 9.6 9.64 10.1 10.89 6.61 6.00 9.57 9.48 9.7 9.74 10.15 10.92 7.72 7.00 9.61 9.57 9.79 9.84 10.18 10.95 8.82 8.00 9.64 9.65 9.89 9.94 10.21 10.97 9.92 9.00 9.66 9.74 9.98 10.03 10.24 10.99 11.02 10.00 9.68 9.82 10.07 10.12 10.25 11 12.13 11.00 9.69 9.91 10.17 10.22 10.27 11.01 13.23 12.00 9.67 9.97 10.26 10.32 10.27 11.01 14,33 13.00 9.64 10.02 10.34 10.4 10.24 11.01 15.43 14.00 9.6 10.08 10.4 10.47 10.2 10.97 15.99 14.51 9.58 10.11 10.43 10.49 10.18 10.95 16.53 15.00 9.56 10.14 10.45 10.51 10.16 10.93 18.74 17.00 9.48 10.21 10.5 10.56 10.07 10.84 22.05 20.00 9.35 10.27 10.54 10.59 9.94 10.71 23.01 20.87 9.28 10.27 10.55 10.6 9.89 10.68 27.56 25.00 8.95 10.25 10.58 10.63 9.66 10.51 32.19 29.20 8.4 9.94 10.26 10.32 9.11 10.05 33.07 30.00 8.3 9.88 10.2 10.26 9.01 9.97 38.58 35.00 7.65 9.48 9.72 9.72 8.37 9.33 44.09 40.00 7.02 9.03 9.19 9.2 7.73 8.69 49.6 45.00 6.38 8.51 8.66 8.67 7.1 8.06 54.79 49.71 3.98 -- -- - -- --

55.12 50.00 -- 7.94 8.12 8.13 5.64 7.43 58.16 52.77 -- -- -- 4.21 --

60.63 55.00 -- 5.83 6.65 6.82 -- 5.5 62.7 56.88 -- 4.87 -- -- --

62.74 56.91 -- --..-- 4.52 63.5 57.61 .... 5.32 5.49 ..--

64.36 58.38 .... 4.92 -- -- --

64.7 58.69 ...... 4.94 I .--

70 63.50 3.98 4.87 4.92 4.94 4.21 4.52 Cycle 19 COLR Revision 31 Page 18 of 51 1

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 MAPLHGR Limits for Rated Power and Rated Flow for GE14 Fuel (cont.)

Average Planar Bundle Type: GE14-PIODNAB398-8G6.0/5G5.0/2G4.0-1OOT-145-T6-2829 Exposure (GE14C)

MAPLHGR Limit (kW/ft)

GWd/MT GWdIST Lattice Lattice Lattice Lattice Lattice Lattice 6849 6850 6851 6852 6853 6854 0.00 0.00 9.80 8.69 8.67 8.63 10.21 10.94 0.22 0.20 9.71 8.75 8.74 8.71 10.16 10.92 1.10 1.00 9.50 8.86 8.86 8.83 10.01 10.84 2.20 2.00 9.44 9.00 9.04 9.01 9.98 10.83 3.31 3.00 9.45 9.08 9.21 9.19 10.01 10.86 4.41 4.00 9.49 9.17 9.33 9.36 10.05 10.90 5.51 5.00 9.53 9.25 9.42 9.45 10.10 10.93 6.61 6.00 9.57 9.34 9.51 9.55 10.15 10.96 7.72 7.00 9.61 9.43 9.61 9.64 10.18 10.99 8.82 8.00 9.64 9.51 9.71 9.74 10.21 11.01 9.92 9.00 9.66 9.60 9.82 9.86 10.24 11.03 11.02 10.00 9.68 9.70 9.94 9.99 10.25 11.04 12.13 11.00 9.69 9.81 10.08 10.13 10.27 11.05 13.23 12.00 9.67 9.89 10.19 10.25 10.27 11.05 14.33 13.00 9.64 9.96 10.28 10.35 10.24 11.05 15.43 14.00 9.60 10.04 10.36 10.43 10.20 11.02 15.99 14.51 9.58 10.07 10.39 10.46 10.18 11.00 16.53 15.00 9.56 10.10 10.42 10.49 10.16 10.97 18.74 17.00 9.48 10.19 10.49 10.55 10.07 10.89 22.05 20.00 9.35 10.27 10.54 10.59 9.94 10.76 23.01 20.87 9.28 10.26 10.55 10.59 9.89 10.72 27.56 25.00 8.95 10.24 10.56 10.62 9.66 10.55 32.19 29.20 8.40 9.93 10.26 10.30 9.11 10.11 33.07 30.00 8.30 9.87 10.20 10.24 9.01 10.02 38.58 35.00 7.65 9.47 9.71 9.71 8.37 9.38 44.09 40.00 7.02 9.02 9.18 9.19 7.73 8.75 49.60 45.00 6.38 8.51 8.65 8.66 7.10 8.12 54.79 49.71 3.98 -- -- -- -- --

55.12 50.00 -- 7.93 8.11 8.13 5.64 7.49 58.16 52.77 -- -- -- 4.21 --

60.63 55.00 - 5.75 6.57 6.75 -- 5.64 62.52 56.72 _. 4.88 -- -- --

63.01 57.16 -..-- --. 4.54 63.50 57.61 .... 5.24 5.41 ..--

64.17 58.22 - -- 4.93 --...

64.51 58.52 --.-- 4.95 -- --

70.00 63.50 3.98 4.88 4.93 4.95 4.21 4.54 Cycle 19 COLR Revision 31 Page 19 of 51 1

w PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 MAPLHGR Limits for Rated Power and Rated Flow for GE14 Fuel (cont.)

Average Bundle Type: GE14-PiODNAB399-15GZ-10OT-145-T6-2957 (GE14C)

Planar Exposure MAPLHGR Limit (kW/ft)

Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT GWd/ST 7492 7493 7494 7495 7496 7497 0.00 0.00 9.80 8.73 8.56 8.54 10.21 10.97 0.22 0.20 9.71 8.80 8.65 8.63 10.16 10.94 1.10 1.00 9.50 8.91 8.78 8.77 10.01 10.86 2.20 2.00 9.44 9.05 8.97 8.95 9.98 10.85 3.31 3.00 9.45 9.21 9.16 9.15 10.01 10.87 4.41 4.00 9.49 9.35 9.37 9.37 10.05 10.90 5.51 5.00 9.53 9.48 9.59 9.59 10.10 10.94 6.61 6.00 9.57 9.62 9.81 9.78 10.15 10.97 7.72 7.00 9.61 9.73 9.94 9.89 10.18 11.00 8.82 8.00 9.64 9.84 10.05 10.02 10.21 11.02 9.92 9.00 9.66 9.96 10.17 10.15 10.24 11.04 11.02 10.00 9.68 10.08 10.30 10.30 10.25 11.05 12.13 11.00 9.69 10.20 10.44 10.45 10.27 11.06 13.23 12.00 9.67 10.30 10.56 10.58 10.27 11.06 14.33 13.00 9.64 10.37 10.64 10.66 10.24 11.06 15.43 14.00 9.60 10.43 10.70 10.72 10.20 11.02 15.99 14.51 9.58 10.45 10.72 10.74 10.18 11.00 16.53 15.00 9.56 10.48 10.74 10.76 10.16 10.98 18.74 17.00 9.48 10.53 10.79 10.80 10.07 10.90 22.05 20.00 9.35 10.57 10.81 10.78 9.94 10.77 23.01 20.87 9.28 10.57 10.80 10.75 9.89 10.73 27.56 25.00 8.95 10.56 10.72 10.66 9.66 10.56 32.19 29.20 8.40 10.19 10.35 10.33 9.11 10.12 33.07 30.00 8.30 10.12 10.28 10.27 9.01 10.03 38.58 35.00 7.65 9.62 9.73 9.73 8.37 9.39 44.09 40.00 7.02 9.09 9.20 9.21 7.73 8.76 49.60 45.00 6.38 8.55 8.67 8.68 7.10 8.13 54.79 49.71 3.98 -- -- -- -- --

55.12 50.00 -- 8.00 8.12 8.14 5.64 7.50 58.16 52.77 -- -- -- 4.21 --

60.63 55.00 -- 6.34 6.90 6.89 -- 5.67 63.05 57.20 -- -- --.. 4.54 63.50 57.61 -- 5.02 5.60 5.59 ..--

63.77 57.85 -- 4.89 -- --...

65.06 59.02 --.-- 4.89 ....

65.11 59.06 ..-- 4.88 --...

70.00 63.50 3.98 4.89 4.88 4.89 4.21 4.54 Cycle 19 COLR Revision 31 Page 20 of 51 1

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 MAPLHGR Limits for Rated Power and Rated Flow for GEI4 Fuel (cont.)

Average Planar Bundle Type: GE14-PIODNAB398-5G6.0110G5.0-1OOT-145-T6-2958 (GE14C)

Exposure MAPLHGR Limit kW/ft)

Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT GWd/ST 7492 7498 7499 7500 7501 7502 0.00 0.00 9.80 8.73 8.69 8.66 10.21 10.97 0.22 0.20 9.71 8.80 8.76 8.74 10.16 10.94 1.10 1.00 9.50 8.91 8.89 8.87 10.01 10.86 2.20 2.00 9.44 9.06 9.07 9.06 9.98 10.85 3.31 3.00 9.45 9.21 9.26 9.25 10.01 10.87 4.41 4.00 9.49 9.34 9.46 9.44 10.05 10.90 5.51 5.00 9.53 9.47 9.62 9.56 10.10 10.94 6.61 6.00 9.57 9.61 9.74 9.69 10.15 10.97 7.72 7.00 9.61 9.72 9.86 9.82 10.18 11.00 8.82 8.00 9.64 9.83 9.99 9.96 10.21 11.02 9.92 9.00 9.66 9.94 10.13 10.11 10.24 11.04 11.02 10.00 9.68 10.06 10.28 10.28 10.25 11.05 12.13 11.00 9.69 10.18 10.43 10.44 10.27 11.06 13.23 12.00 9.67 10.28 10.56 10.58 10.27 11.06 14.33 13.00 9.64 10.36 10.65 10.67 10.24 11.06 15.43 14.00 9.60 10.42 10.71 10.73 10.20 11.02 15.99 14.51 9.58 10.45 10.73 10.75 10.18 11.00 16.53 15.00 9.56 10.47 10.75 10.77 10.16 10.98 18.74 17.00 9.48 10.53 10.80 10.81 10.07 10.90 22.05 20.00 9.35 10.57 10.82 10.78 9.94 10.77 23.01 20.87 9.28 10.57 10.80 10.76 9.89 10.73 27.56 25.00 8.95 10.55 10.73 10.66 9.66 10.56 32.19 29.20 8.40 10.19 10.34 10.33 9.11 10.12 33.07 30.00 8.30 10.12 10.27 10.26 9.01 10.03 38.58 35.00 7.65 9.62 9.73 9.73 8.37 9.39 44.09 40.00 7.02 9.08 9.19 9.20 7.73 8.76 49.60 45.00 6.38 8.55 8.66 8.67 7.10 8.13 54.79 49.71 3.98 -- -- -- --

55.12 50.00 -- 8.00 8.12 8.13 5.64 7.50 58.16 52.77 -- -- -- 4.21 --

60.63 55.00 -- 6.32 6.86 6.85 -- 5.67 63.05 57.20 -- -- --.. 4.54 63.50 57.61 -- 5.00 5.56 5.55 ..--

63.75 57.83 -- 4.89 ..-- --.

64.96 58.93 --.-- 4.89 ....

65.01 58.98 - -- 4.88 -- -- --

70.00 63.50 3.98 4.89 4.88 4.89 4.21 4.54 Cycle 19 COLR Revision 31 Page 21 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 MAPLHGR Limits for Rated Power and Rated Flow for GE14 Fuel (cont.)

Average Bundle Type: GE14-P1ODNAB400-13GZ-1OOT-145-T6-2959 Planar (GE14C)

Exposure MAPLHGR Limit (kW/ft)

Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT GWdIST 7492 7503 7504 7505 7506 7507 0.00 0.00 9.80 8.88 8.88 8.86 10.21 10.81 0.22 0.20 9.71 8.94 8.95 8.94 10.16 10.78 1.10 1.00 9.50 9.03 9.06 9.05 10.01 10.69 2.20 2.00 9.44 9.17 9.23 9.22 9.98 10.69 3.31 3.00 9.45 9.30 9.40 9.39 10.01 10.72 4.41 4.00 9.49 9.42 9.58 9.58 10.05 10.76 5.51 5.00 9.53 9.54 9.74 9.71 10.10 10.80 6.61 6.00 9.57 9.66 9.88 9.82 10.15 10.84 7.72 7.00 9.61 9.78 9.98 9.94 10.18 10.88 8.82 8.00 9.64 9.90 10.10 10.06 10.21 10.90 9.92 9.00 9.66 10.00 10.22 10.20 10.24 10.92 11.02 10.00 9.68 10.10 10.35 10.34 10.25 10.94 12.13 11.00 9.69 10.20 10.49 10.49 10.27 10.95 13.23 12.00 9.67 10.30 10.61 10.63 10.27 10.95 14.33 13.00 9.64 10.37 10.70 10.72 10.24 10.95 15.43 14.00 9.60 10.44 10.76 10.78 10.20 10.91 15.99 14.51 9.58 10.47 10.78 10.80 10.18 10.89 16.53 15.00 9.56 10.50 10.80 10.81 10.16 10.87 18.74 17.00 9.48 10.56 10.82 10.83 10.07 10.78 22.05 20.00 9.35 10.58 10.82 10.78 9.94 10.65 23.01 20.87 9.28 10.58 10.80 10.75 9.89 10.61 27.56 25.00 8.95 10.56 10.72 10.62 9.66 10.44 32.19 29.20 8.40 10.20 10.36 10.33 9.11 9.97 33.07 30.00 8.30 10.13 10.29 10.28 9.01 9.89 38.58 35.00 7.65 9.63 9.74 9.74 8.37 9.25 44.09 40.00 7.02 9.10 9.21 9.22 7.73 8.61 49.60 45.00 6.38 8.56 8.68 8.69 7.10 7.98 54.79 49.71 3.98 -- -- -- -- --

55.12 50.00 -- 8.01 8.14 8.15 5.64 7.35 58.16 52.77 -- -- -- 4.21 --

60.63 55.00 -- 6.39 6.97 6.96 -- 5.29 62.34 56.55 ..-- - - 4.49 63.50 57.61 -- 5.07 5.67 5.66 ..--

63.89 57.96 -- 4.89 -- --...

65.20 59.15 --.-- 4.89 ....

65.25 59.19 ..-- 4.88 -- --

70.00 63.50 3.98 4.89 4.88 4.89 4.21 4.49 Cycle 19 COLR Revision 31 Page 22 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 MAPLHGR Limits for Rated Power and Rated Flow for GE14 Fuel (cont.)

Average Bundle Type: GE14-PIODNAB404-5G6.0O10G5.0-1OOT-145-T6-2960 (GE14C)

Planar Exposure MAPLHGR Limit (kWlft _

Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT GWdIST 7492 7508 7509 7510 7511 7512 0.00 0.00 9.80 8.76 8.72 8.70 10.21 10.97 0.22 0.20 9.71 8.83 8.80 8.78 10.16 10.94 1.10 1.00 9.50 8.94 8.93 8.91 10.01 10.86 2.20 2.00 9.44 9.09 9.11 9.10 9.98 10.85 3.31 3.00 9.45 9.24 9.30 9.29 10.01 10.87 4.41 4.00 9.49 9.38 9.50 9.48 10.05 10.90 5.51 5.00 9.53 9.51 9.66 9.60 10.10 10.94 6.61 6.00 9.57 9.64 9.78 9.73 10.15 10.97 7.72 7.00 9.61 9.75 9.90 9.86 10.18 11.00 8.82 8.00 9.64 9.86 10.03 10.00 10.21 11.02 9.92 9.00 9.66 9.97 10.16 10.15 10.24 11.04 11.02 10.00 9.68 10.08 10.31 10.31 10.25 11.05 12.13 11.00 9.69 10.20 10.46 10.47 10.27 11.06 13.23 12.00 9.67 10.31 10.59 10.61 10.27 11.06 14.33 13.00 9.64 10.38 10.68 10.70 10.24 11.06 15.43 14.00 9.60 10.45 10.75 10.77 10.20 11.02 15.99 14.51 9.58 10.47 10.77 10.79 10.18 11.00 16.53 15.00 9.56 10.50 10.79 10.81 10.16 10.98 18.74 17.00 9.48 10.56 10.85 10.86 10.07 10.90 22.05 20.00 9.35 10.61 10.87 10.85 9.94 10.77 23.01 20.87 9.28 10.61 10.84 10.82 9.89 10.73 27.56 25.00 8.95 10.60 10.70 10.67 9.66 10.56 32.19 29.20 8.40 10.24 10.42 10.41 9.11 10.12 33.07 30.00 8.30 10.17 10.36 10.36 9.01 10.03 38.58 35.00 7.65 9.69 9.81 9.77 8.37 9.39 44.09 40.00 7.02 9.15 9.23 9.17 7.73 8.76 49.60 45.00 6.38 8.61 8.65 8.60 7.10 8.13 54.79 49.71 3.98 -- -- -- -- --

55.12 50.00 - 8.06 8.11 8.06 5.64 7.50 58.16 52.77 -- -- - 4.21 --

60.63 55.00 6.46 7.08 7.07 -- 5.67 63.05 57.20 -- -- -- 4.54 63.50 57.61 5.14 5.78 5.77 --

64.01 58.07 4.91 -- -

65.41 59.34 -- -- 4.91 65.45 59.37 ..-- 4.90 -- -- --

70.00 63.50 3.98 4.91 4.90 4.91 4.21 4.54 Cycle 19 COLR Revision 31 Page 23 of 51 1

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 MAPLHGR Limits for Rated Power and Rated Flow for GE14 Fuel (cont.)

Average Planar Bundle Type: GE14-PIODNAB400-12G6.013G5.0-10OT-145-T6-2961 (GE14C)

Exposure MAPLHGR Limit (kWft)

Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT GWdIST 7492 7513 7514 7515 7516 7517 0.00 0.00 9.80 8.71 8.67 8.65 10.21 10.97 0.22 0.20 9.71 8.78 8.74 8.72 10.16 10.94 1.10 1.00 9.50 8.88 8.86 8.84 10.01 10.86 2.20 2.00 9.44 9.02 9.03 9.01 9.98 10.85 3.31 3.00 9.45 9.16 9.20 9.19 10.01 10.87 4.41 4.00 9.49 9.31 9.39 9.38 10.05 10.90 5.51 5.00 9.53 9.43 9.58 9.52 10.10 10.94 6.61 6.00 9.57 9.56 9.70 9.64 10.15 10.97 7.72 7.00 9.61 9.67 9.81 9.76 10.18 11.00 8.82 8.00 9.64 9.78 9.93 9.89 10.21 11.02 9.92 9.00 9.66 9.88 10.05 10.03 10.24 11.04 11.02 10.00 9.68 9.99 10.19 10.18 10.25 11.05 12.13 11.00 9.69 10.11 10.34 10.34 10.27 11.06 13.23 12.00 9.67 10.21 10.47 10.48 10.27 11.06 14.33 13.00 9.64 10.29 10.57 10.59 10.24 11.06 15.43 14.00 9.60 10.37 10.66 10.68 10.20 11.02 15.99 14.51 9.58 10.40 10.69 10.72 10.18 11.00 16.53 15.00 9.56 10.43 10.73 10.75 10.16 10.98 18.74 17.00 9.48 10.52 10.81 10.83 10.07 10.90

.22.05 20.00 9.35 10.59 10.84 10.80 9.94 10.77 23.01 20.87 9.28 10.59 10.82 10.77 9.89 10.73 27.56 25.00 8.95 10.57 10.73 10.64 9.66 10.56 32.19 29.20 8.40 10.21 10.35 10.33 9.11 10.12 33.07 30.00 8.30 10.14 10.28 10.27 9.01 10.03 38.58 35.00 7.65 9.63 9.74 9.74 8.37 9.39 44.09 40.00 7.02 9.09 9.21 9.21 7.73 8.76 49.60 45.00 6.38 8.56 8.67 8.68 7.10 8.13 54.79 49.71 3.98 - -- - -- --

55.12 50.00 - 8.01 8.13 8.14 5.64 7.50 58.16 52.77 - -- -- -- 4.21 --

60.63 55.00 - 6.35 6.92 6.91 -- 5.67 63.05 57.20 - -- -- - 4.54 63.50 57.61 -- 5.03 5.62 5.61 ..--

63.79 57.87 - 4.90 - --..

65.09 59.05 ..--. 4.89 ....

65.15 59.10 - -- 4.88 -....

70.00 63.50 3.98 4.90 4.88 4.89 4.21 4.54 Cycle 19 COLR Revision 31 Page 24 of 51 1

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 MAPLHGR Limits for Rated Power and Rated Flow for GNF2 Fuel Average Bundle Type: GNF2-P10DG2B389-6G6.018G5.0-100T2-145-T6-3141 Planar (GNF2)

Exposure MAPLHGR Limit (kW/ft_

Lat. Lattice Lattice Lattice Lattice Lattice Lat.

GWd/MT I GWdIST 8661 8668 I 8669 1 8670 1 8671 I 8672 I 8667 0.00 0.00 9.76 9.24 9.37 9.49 8.96 8.66 10.44 0.22 0.20 9.67 9.26 9.41 9.54 8.99 8.70 10.38 1.10 1.00 9.45 9.33 9.49 9.62 9.08 8.79 10.22 2.20 2.00 9.39 9.42 9.60 9.72 9.20 8.92 10.16 3.31 3.00 9.39 9.52 9.70 9.83 9.32 9.06 10.17 4.41 4.00 9.42 9.62 9.81 9.94 9.45 9.20 10.19 5.51 5.00 9.46 9.73 9.92 10.05 9.58 9.34 10.22 6.61 6.00 9.50 9.83 10.02 10.16 9.72 9.49 10.25 7.72 7.00 9.53 9.94 10.13 10.27 9.86 9.64 10.27 8.82 8.00 9.56 10.04 10.25 10.38 10.00 9.79 10.29 9.92 9.00 9.58 10.14 10.36 10.38 10.14 9.95 10.31 11.02 10.00 9.60 10.24 10.48 10.39 10.29 10.10 10.32 12.13 11.00 9.54 10.31 10.58 10.42 10.19 10.16 10.33 13.23 12.00 9.45 10.31 10.61 10.23 10.09 10.16 10.24 14.33 13.00 9.36 10.31 10.60 10.17 10.07 10.14 10.14 15.43 14.00 9.26 10.30 10.49 10.09 10.00 10.07 10.04 16.53 15.00 9.16 10.28 10.38 10.02 9.93 10.00 9.94 17.64 16.00 9.06 10.25 10.25 9.94 9.86 9.92 9.84 18.74 17.00 8.96 10.20 10.14 9.86 9.77 9.83 9.74 19.84 18.00 8.86 10.14 10.04 9.77 9.68 9.74 9.63 20.94 19.00 8.76 10.08 9.94 9.68 9.59 9.64 9.53 22.05 20.00 8.65 10.01 9.83 9.59 9.50 9.55 9.42 23.15 21.00 8.55 9.91 9.73 9.49 9.41 9.45 9.32 24.25 22.00 8.45 9.81 9.63 9.40 9.32 9.36 9.22 25.35 23.00 8.35 9.70 9.53 9.31 9.23 9.27 9.11 26.46 24.00 8.24 9.60 9.43 9.22 9.14 9.18 9.01 27.56 25.00 8.14 9.50 9.33 9.13 9.05 9.08 8.91 33.07 30.00 7.64 8.99 8.84 8.68 8.62 8.64 8.40 38.58 35.00 7.14 8.51 8.37 8.26 8.21 8.23 7.91 41.22 37.39 6.91 8.29 8.16 8.06 8.03 8.04 7.67 44.09 40.00 6.65 8.05 7.93 7.84 7.83 7.84 7.42 49.60 45.00 6.16 7.63 7.52 7.44 7.44 7.44 6.93 54.42 49.37 5.25 -- -- -- - --

55.12 50.00 -- 7.22 7.12 7.05 7.07 7.08 6.45 58.61 53.17 -- -- -- - 5.61 60.63 55.00 _ 6.83 6.74 6.55 6.54 6.59 --

62.27 56.49 -- -- -- 6.13 62.31 56.52 ...-- -- 6.42 62.50 56.70 ...--. 6.09 --

63.44 57.55 -- 6.48 -- --.

63.78 57.86 -- -- 6.03 -- -- --

70.00 63.50 5.25 6.48 6.03 6.09 6.13 6.42 5.61 Cycle 19 COLR Revision 31 Page 25 of 51 1

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 MAPLHGR Limits for Rated Power and Rated Flow for GNF2 Fuel (cont.)

Average Planar Bundle Type: GNF2-P10DG2B389-6G6.012G5.0/6G4.0-100T2-145-T6-3142 (GNF2)

Exposure MAPLHGR Limit (kW/ft )

GWd/MT GWdlST Lat. Lat. Lat. Lat. Lat. Lat. Lat.

8661 8662 8663 8664 8665 8666 8667 0.00 0.00 9.76 9.22 9.41 9.53 9.00 8.70 10.44 0.22 0.20 9.67 9.24 9.43 9.57 9.03 8.73 10.38 1.10 1.00 9.45 9.30 9.50 9.65 9.13 8.83 10.22 2.20 2.00 9.39 9.40 9.61 9.76 9.26 8.98 10.16 3.31 3.00 9.39 9.49 9.72 9.87 9.39 9.11 10.17 4.41 4.00 9.42 9.59 9.83 9.99 9.53 9.25 10.19 5.51 5.00 9.46 9.69 9.95 10.12 9.68 9.39 10.22 6.61 6.00 9.50 9.79 10.08 10.25 9.83 9.54 10.25 7.72 7.00 9.53 9.90 10.21 10.38 9.98 9.70 10.27 8.82 8.00 9.56 10.01 10.34 10.49 10.14 9.86 10.29 9.92 9.00 9.58 10.13 10.47 10.50 10.29 10.02 10.31 11.02 10.00 9.60 10.25 10.60 10.51 10.43 10.18 10.32 12.13 11.00 9.54 10.33 10.72 10.54 10.33 10.24 10.33 13.23 12.00 9.45 10.35 10.73 10.35 10.20 10.25 10.24 14.33 13.00 9.36 10.36 10.69 10.26 10.15 10.22 10.14 15.43 14.00 9.26 10.35 10.57 10.15 10.05 10.12 10.04 16.53 15.00 9.16 10.32 10.42 10.06 9.96 10.03 9.94 17.64 16.00 9.06 10.27 10.27 9.97 9.87 9.93 9.84 18.74 17.00 8.96 10.21 10.16 9.87 9.78 9.84 9.74 19.84 18.00 8.86 10.15 10.05 9.78 9.69 9.74 9.63 20.94 19.00 8.76 10.09 9.94 9.69 9.60 9.65 9.53 22.05 20.00 8.65 10.01 9.84 9.59 9.50 9.55 9.42 23.15 21.00 8.55 9.92 9.74 9.50 9.41 9.46 9.32 24.25 22.00 8.45 9.81 9.64 9.41 9.32 9.36 9.22 25.35 23.00 8.35 9.71 9.54 9.31 9.23 9.27 9.11 26.46 24.00 8.24 9.60 9.44 9.22 9.14 9.18 9.01 27.56 25.00 8.14 9.50 9.34 9.13 9.05 9.09 8.91 33.07 30.00 7.64 8.99 8.84 8.69 8.62 8.64 8.40 38.58 35.00 7.14 8.51 8.37 8.26 8.21 8.23 7.91 41.22 37.39 6.91 8.29 8.16 8.06 8.03 8.04 7.67 44.09 40.00 6.65 8.06 7.93 7.84 7.83 7.84 7.42 49.60 45.00 6.16 7.63 7.52 7.44 7.44 7.44 6.93 54.42 49.37 5.25 -- -- -- -- -- --

55.12 50.00 - 7.22 7.12 7.05 7.07 7.08 6.45 58.61 53.17 -- -- -- -- -- 5.61 60.63 55.00 __ 6.83 6.74 6.57 6.56 6.61 --

62.34 56.55 -- -- - 6.13 6.42 -

62.56 56.76 ...--. 6.08 -- --.

63.48 57.59 _. 6.48 -- --.....

63.83 57.91 ..-- 6.03 I.-- .- --

70.00 63.50 5.25 6.48 6.03 6.08 6.13 6.42 5.61 Cycle 19 COLR Revision 31 Page 26 of 51 1

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 MAPLHGR Limits for Rated Power and Rated Flow for GNF2 Fuel (cont.)

Average Planar Bundle Type: GNF2-P1 0DG2B388-6G6.0/7G5.0-1 00T2-145-T6-3143 (GNF2)

Exposure MAPLHGR Limit (kW/ft)

Lat. Lattice Lattice Lattice Lattice Lattice Lat.

GWd/MT GWd/ST 8661 8655 8656 8657 8658 8659 8667 0.00 0.00 9.76 8.73 8.94 9.08 9.09 8.73 10.44 0.22 0.20 9.67 8.78 8.99 9.13 9.13 8.77 10.38 1.10 1.00 9.45 8.89 9.11 9.26 9.22 8.86 10.22 2.20 2.00 9.39 9.04 9.27 9.42 9.34 8.99 10.16 3.31 3.00 9.39 9.20 9.44 9.60 9.47 9.13 10.17 4.41 4.00 9.42 9.36 9.62 9.78 9.60 9.27 10.19 5.51 5.00 9.46 9.52 9.80 9.94 9.74 9.42 10.22 6.61 6.00 9.50 9.69 9.94 10.09 9.89 9.57 10.25 7.72 7.00 9.53 9.81 10.08 10.23 10.04 9.73 10.27 8.82 8.00 9.56 9.91 10.20 10.29 10.17 9.88 10.29 9.92 9.00 9.58 10.00 10.31 10.33 10.30 10.02 10.31 11.02 10.00 9.60 10.09 10.41 10.38 10.42 10.16 10.32 12.13 11.00 9.54 10.11 10.48 10.43 10.49 10.20 10.33 13.23 12.00 9.45 10.10 10.47 10.40. 10.48 10.20 10.24 14.33 13.00 9.36 10.09 10.46 10.37 10.45 10.18 10.14 15.43 14.00 9.26 10.07 10.44 10.34 10.40 10.14 10.04 16.53 15.00 9.16 10.05 10.41 10.30 10.34 10.10 9.94 17.64 16.00 9.06 10.01 10.37 10.24 10.28 10.04 9.84 18.74 17.00 8.96 9.97 10.31 10.17 10.19 9.98 9.74 19.84 18.00 8.86 9.92 10.25 10.10 10.11 9.91 9.63 20.94 19.00 8.76 9.87 10.19 10.02 10.01 9.84 9.53 22.05 20.00 8.65 9.82 10.12 9.94 9.92 9.77 9.42 23.15 21.00 8.55 9.76 10.06 9.86 9.83 9.70 9.32 24.25 22.00 8.45 9.70 9.99 9.77 9.74 9.64 9.22 25.35 23.00 8.35 9.65 9.93 9.67 9.65 9.57 9.11 26.46 24.00 8.24 9.59 9.84 9.58 9.56 9.50 9.01 27.56 25.00 8.14 9.53 9.74 9.49 9.47 9.43 8.91 33.07 30.00 7.64 9.22 9.24 9.03 9.03 9.06 8.40 38.58 35.00 7.14 8.84 8.77 8.60 8.60 8.63 7.91 41.22 37.39 6.91 8.66 8.55 8.39 8.41 8.42 7.67 44.09 40.00 6.65 8.46 8.32 8.17 8.20 8.19 7.42 49.60 45.00 6.16 8.06 7.88 7.75 7.80 7.75 6.93 54.42 49.37 5.25 -- -- -- -- --

55.12 50.00 -- 7.66 7.46 7.34 7.40 7.33 6.45 58.61 53.17 .--. -- - -- 5.61 60.63 55.00 -- 7.22 7.04 6.93 6.99 6.89 --

62.39 56.60 -- -- -- -- 6.42 --

63.22 57.35 ......-- 6.42 --

63.28 57.41 ...--. 6.41 --..

63.44 57.55 -- 6.48 -- -- --

64.62 58.62 -- -- 6.46 [.-- I 70.00 63.50 5.25 6.48 6.46 6.41 6.42 6.42 5.61 Cycle 19 COLR Revision 31 Page 27 of 51 1

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3., -2 MAPLHGR Limits for Rated Power and Rated Flow for GNF2 Fuel(cont.)

Average Planar Bundle Type: GNF2-P1ODG2B401-6G6.0/8G5.O/1G4.0-100T2-145-T6-3421 (GNF2)

Exposure MAPLHGR Limit (kW/ftL Lat. Lat. Lat. Lat. Lat. Lat. Lat.

GWd/MT GWdIST 9676 9677 9678 9679 9680 9681 9682 0.00 0.00 9.76 9.01 9.15 9.25 8.68 8.39 10.44 0.22 0.20 9.67 9.05 9.19 9.29 8.71 8.42 10.38 1.10 1.00 9.45 9.12 9.27 9.38 8.79 8.51 10.21 2.20 2.00 9.38 9.21 9.36 9.49 8.91 8.63 10.16 3.31 3.00 9.39 9.30 9.46 9.59 9.02 8.76 10.16 4.41 4.00 9.42 9.39 9.56 9.69 9.14 8.89 10.19 5.51 5.00 9.46 9.48 9.66 9.79 9.27 9.03 10.22 6.61 6.00 9.49 9.57 9.76 9.90 9.40 9.17 10.25 7.72 7.00 9.53 9.66 9.86 10.00 9.53 9.32 10.27 8.82 8.00 9.56 9.75 9.96 10.11 9.66 9.46 10.29 9.92 9.00 9.58 9.85 10.07 10.21 9.80 9.61 10.31 11.02 10.00 9.60 9.94 10.18 10.32 9.94 9.74 10.32 12.13 11.00 9.53 9.97 10.24 10.40 9.98 9.79 10.32 13.23 12.00 9.44 9.97 10.25 10.41 10.02 9.84 10.24 14.33 13.00 9.35 9.97 10.25 10.41 10.04 9.87 10.14 15.43 14.00 9.25 9.96 10.25 10.40 10.05 9.89 10.04 16.53 15.00 9.16 9.95 10.24 10.31 10.05 9.89 9.94 17.64 16.00 9.06 9.93 10.21 10.23 10.02 9.88 9.83 18.74 17.00 8.95 9.90 10.17 10.14 9.99 9.85 9.73 19.84 18.00 8.85 9.86 10.13 10.05 9.94 9.82 9.62 20.94 19.00 8.75 9.81 10.07 9.95 9.84 9.78 9.52 22.05 20.00 8.65 9.77 10.02 9.85 9.75 9.74 9.42 23.15 21.00 8.54 9.72 9.96 9.76 9.65 9.70 9.31 24.25 22.00 8.44 9.67 9.88 9.66 9.56 9.60 9.21 25.35 23.00 8.34 9.61 9.78 9.56 9.46 9.51 9.10 26.46 24.00 8.23 9.56 9.67 9.47 9.37 9.41 9.00 27.56 25.00 8.13 9.51 9.57 9.37 9.27 9.31 8.90 33.07 30.00 7.63 9.19 9.06 8.90 8.82 8.84 8.39 38.58 35.00 7.13 8.69 8.56 8.45 8.38 8.40 7.90 41.22 37.39 6.89 8.46 8.34 8.23 8.19 8.20 7.66 44.09 40.00 6.64 8.21 8.10 8.00 7.97 7.98 7.41 49.60 45.00 6.15 7.76 7.66 7.57 7.56 7.57 6.92 54.38 49.33 5.24 -- -- -- -- -- --

55.12 50.00 -- 7.33 7.24 7.16 7.17 7.18 6.44 58.58 53.14 -- -- -- -- -- 5.61 60.63 55.00 6.92 6.84 6.77 6.79 6.80 --

63.11 57.25 -- -- -- 6.45 63.39 57.51 6.57 -- --

63.44 57.55 -- -- 6.14 63.75 57.84 -- 6.09 --

64.60 58.60 .... 6.26 -- . -- --

70.00 63.50 5.24 6.57 6.26 6.09 6.14 6.45 5.61

.... I Cycle 19 COLR Revision 31 Page 28 of 51 1

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 MAPLHGR Limits for Rated Power and Rated Flow for GNF2 Fuel(cont.)

Average Planar Bundle Type: GNF2-PI0DG2B395-6G6.0/9G5.0-100T2-145-T6-3422 (GNF2)

Exposure MAPLHGR Limit (kW/ft)

GWd/MT GWd/ST Lat. 9676 Lat. 9683 Lat. 9684 Lat. 9685 Lat. 9686 Lat. 9687 Lat. 9682 0.00 0.00 9.76 9.09 9.23 9.33 8.81 8.52 10.44 0.22 0.20 9.67 9.13 9.28 9.39 8.85 8.57 10.38 1.10 1.00 9.45 9.21 9.38 9.49 8.96 8.68 10.21 2.20 2.00 9.38 9.33 9.52 9.64 9.12 8.85 10.16 3.31 3.00 9.39 9.45 9.67 9.79 9.29 9.00 10.16 4.41 4.00 9.42 9.57 9.81 9.94 9.46 9.15 10.19 5.51 5.00 9.46 9.70 9.95 10.1t 9.63 9.31 10.22 6.61 6.00 9.49 9.83 10.11 10.28 9.79 9.47 10.25 7.72 7.00 9.53 9.97 10.24 10.42 9.95 9.65 10.27 8.82 8.00 9.56 9.87 10.18 10.41 10.11 9.82 10.29 9.92 9.00 9.58 9.65 9.93 10.11 10.26 9.99 10.31 11.02 10.00 9.60 9.68 9.94 10.11 10.37 10.14 10.32 12.13 11.00 9.53 9.78 10.05 10.21 10.48 10.20 10.32 13.23 12.00 9.44 9.86 10.18 10.34 10.33 10.22 10.24 14.33 13.00 9.35 9.88 10.20 10.38 10.29 10.22 10.14 15.43 14.00 9.25 9.89 10.21 10.28 10.21 10.20 10.04 16.53 15.00 9.16 9.89 10.21 10.20 10.13 10.15 9.94 17.64 16.00 9.06 9.88 10.18 10.12 10.05 10.10 9.83 18.74 17.00 8.95 9.85 10.15 10.03 9.96 10.02 9.73 19.84 18.00 8.85 9.81 10.10 9.94 9.87 9.92 9.62 20.94 19.00 8.75 9.77 10.05 9.84 9.77 9.82 9.52 22.05 20.00 8.65 9.73 9.97 9.75 9.67 9.73 9.42 23.15 21.00 8.54 9.69 9.86 9.65 9.58 9.63 9.31 24.25 22.00 8.44 9.64 9.76 9.55 9.48 9.53 9.21 25.35 23.00 8.34 9.60 9.66 9.46 9.39 9.43 9.10 26.46 24.00 8.23 9.55 9.55 9.36 9.30 9.34 9.00 27.56 25.00 8.13 9.51 9.45 9.27 9.20 9.24 8.90 33.07 30.00 7.63 9.09 8.95 8.80 8.75 8.78 8.39 38.58 35.00 7.13 8.59 8.47 8.36 8.32 8.34 7.90 41.22 37.39 6.89 8.37 8.25 8.15 8.13 8.14 7.66 44.09 40.00 6.64 8.13 8.01 7.92 7.91 7.92 7.41 49.60 45.00 6.15 7.69 7.59 7.50 7.51 7.51 6.92 54.38 49.33 5.24 -- -- -- -- -- --

55.12 50.00 -- 7.27 7.18 7.10 7.12 7.13 6.44 58.58 53.14 - -- -- -- -- 5.61 60.63 55.00 -- 6.87 6.79 6.71 6.72 6.76 --

62.67 56.86 -- -- -- -- 6.44 --

63.01 57.16 ......-- 6.13 --..

63.18 57.32 ...... 6.08 --....

63.72 57.81 -- 6.49 ...--...

64.32 58.35 -- -- 6.03 --......

70.00 63.50 5.24 6.49 6.03 6.08 6.13 6.44 5.61 Cycle 19 COLR Revision 31 Page 29 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 MAPLHGR Limits for Rated Power and Rated Flow for GNF2 Fuel(cont.)

Average Planar Bundle Type: GNF2-P10DG2B375-6G6.0/7G5.0-100T2-145-T6-3434 (GNF2)

Exposure MAPLHGR Limit (kW/ftL Lat. Lat. Lat. Lat. Lat. Lat. Lat.

GWd/MT GWdIST 9676 9688 9689 9690 9691 9692 9682 0.00 0.00 9.76 9.01 9.21 9.30 8.77 8.42 10.44 0.22 0.20 9.67 9.03 9.24 9.35 8.81 8.46 10.38 1.10 1.00 9.45 9.12 9.34 9.46 8.91 8.57 10.21 2.20 2.00 9.38 9.24 9.47 9.59 9.05 8.71 10.16 3.31 3.00 9.39 9.37 9.61 9.72 9.18 8.85 10.16 4.41 4.00 9.42 9.50 9.75 9.85 9.33 9.00 10.19 5.51 5.00 9.46 9.63 9.88 9.95 9.47 9.16 10.22 6.61 6.00 9.49 9.77 10.01 10.00 9.63 9.32 10.25 7.72 7.00 9.53 9.38 9.65 9.87 9.78 9.49 10.27 8.82 8.00 9.56 9.06 9.29 9.46 9.71 9.65 10.29 9.92 9.00 9.58 9.06 9.27 9.42 9.66 9.74 10.31 11.02 10.00 9.60 9.17 9.39 9.53 9.78 9.85 10.32 12.13 11.00 9.53 9.29 9.53 9.67 9.93 9.94 10.32 13.23 12.00 9.44 9.32 9.59 9.74 10.04 9.94 10.24 14.33 13.00 9.35 9.35 9.62 9.77 10.07 9.92 10.14 15.43 14.00 9.25 9.37 9.65 9.79 10.08 9.89 10.04 16.53 15.00 9.16 9.38 9.65 9.79 10.06 9.84 9.94 17.64 16.00 9.06 9.38 9.64 9.78 10.02 9.79 9.83 18.74 17.00 8.95 9.37 9.62 9.75 9.95 9.73 9.73 19.84 18.00 8.85 9.36 9.60 9.72 9.87 9.66 9.62 20.94 19.00 8.75 9.34 9.57 9.69 9.78 9.60 9.52 22.05 20.00 8.65 9.32 9.54 9.65 9.69 9.54 9.42 23.15 21.00 8.54 9.29 9.51 9.61 9.60 9.47 9.31 24.25 22.00 8.44 9.27 9.48 9.52 9.51 9.41 9.21 25.35 23.00 8.34 9.25 9.45 9.43 9.42 9.35 9.10 26.46 24.00 8.23 9.22 9.42 9.34 9.33 9.28 9.00 27.56 25.00 8.13 9.19 9.39 9.25 9.25 9.22 8.90 33.07 30.00 7.63 9.04 9.02 8.82 8.82 8.85 8.39 38.58 35.00 7.13 8.68 8.57 8.40 8.42 8.44 7.90 41.22 37.39 6.89 8.50 8.36 8.21 8.23 8.24 7.66 44.09 40.00 6.64 8.32 8.14 8.00 8.03 8.02 7.41 49.60 45.00 6.15 7.94 7.73 7.61 7.65 7.60 6.92 54.38 49.33 5.24 -- -- -- -- -- --

55.12 50.00 -- 7.55 7.33 7.21 7.27 7.20 6.44 58.58 53.14 -- -- -- -- -- 5.61 60.63 55.00 6.92 6.93 6.80 6.79 6.57 --

61.27 55.59 _ -- -- -- -- 6.40 62.10 56.33 -- 6.40 --

62.24 56.46 -- 6.38 --

62.37 56.58 6.47 -- --

63.46 57.57 .... 6.49 -- -- -- --

70.00 63.50 5.24 6.47 6.49 6.38 6.40 6.40 5.61

.... I Cycle 19 COLR Revision 31 Page 30 of 51 1

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 MAPLHGR Limits for Rated Power and Rated Flow for GNF2 Fuel(cont.)

Average Bundle Type: GNF2-PIODG2B401-6G6.012G5.016G4.0-100T2-145-T6-3640 (GNF2)

Planar MAPLHGR Limit (kW/ft)

Exposure GWd/MT GWd/ST Lat. Lat. Lat. Lat. Lat. Lat. Lat.

9676 9693 9694 9695 9696 9697 9682 0.00 0.00 9.76 9.04 9.17 9.30 8.72 8.43 10.44 0.22 0.20 9.67 9.08 9.22 9.34 8.75 8.47 10.38 1.10 1.00 9.45 9.15 9.30 9.42 8.84 8.56 10.21 2.20 2.00 9.38 9.25 9.40 9.53 8.96 8.69 10.16 3.31 3.00 9.39 9.34 9.51 9.64 9.09 8.82 10.16 4.41 4.00 9.42 9.43 9.61 9.74 9.22 8.97 10.19 5.51 5.00 9.46 9.53 9.72 9.85 9.35 9.11 10.22 6.61 6.00 9.49 9.63 9.83 9.97 9.49 9.26 10.25 7.72 7.00 9.53 9.72 9.94 10.08 9.63 9.42 10.27 8.82 8.00 9.56 9.82 10.05 10.20 9.78 9.58 10.29 9.92 9.00 9.58 9.92 10.17 10.32 9.92 9.74 10.31 11.02 10.00 9.60 10.03 10.28 10.43 10.06 9.87 10.32 12.13 11.00 9.53 10.06 10.35 10.52 10.10 9.91 10.32 13.23 12.00 9.44 10.06 10.35 10.52 10.11 9.93 10.24 14.33 13.00 9.35 10.05 10.35 10.50 10.12 9.95 10.14 15.43 14.00 9.25 10.03 10.32 10.46 10.10 9.94 10.04 16.53 15.00 9.16 10.01 10.29 10.35 10.08 9.92 9.94 17.64 16.00 9.06 9.97 10.24 10.25 10.04 9.89 9.83 18.74 17.00 8.95 9.93 10.19 10.16 9.99 9.86 9.73 19.84 18.00 8.85 9.88 10.14 10.06 9.95 9.82 9.62 20.94 19.00 8.75 9.83 10.08 9.96 9.85 9.78 9.52 22.05 20.00 8.65 9.78 10.02 9.86 9.76 9.74 9.42 23.15 21.00 8.54 9.72 9.97 9.77 9.66 9.71 9.31 24.25 22.00 8.44 9.67 9.89 9.67 9.56 9.61 9.21 25.35 23.00 8.34 9.62 9.78 9.57 9.47 9.51 9.10 26.46 24.00 8.23 9.57 9.68 9.48 9.38 9.42 9.00 27.56 25.00 8.13 9.51 9.57 9.38 9.28 9.32 8.90 33.07 30.00 7.63 9.20 9.06 8.91 8.82 8.85 8.39 38.58 35.00 7.13 8.69 8.57 8.45 8.39 8.41 7.90 41.22 37.39 6.89 8.46 8.34 8.24 8.19 8.21 7.66 44.09 40.00 6.64 8.21 8.10 8.00 7.98 7.99 7.41 49.60 45.00 6.15 7.76 7.66 7.57 7.56 7.57 6.92 54.38 49.33 5.24 -- -- -. -- --

55.12 50.00 -- 7.34 7.24 7.17 7.17 7.18 6.44 58.58 53.14 - -- -- -- -- 5.61 60.63 55.00 6.93 6.84 6.77 6.79 6.80 --

63.19 57.32 ...-- -- 6.45 63.45 57.56 6.57 -- --

63.45 57.56 .--. 6.14 63.76 57.84 -- 6.10 --

64.65 58.65 . -- 6.25 -- -- -.

70.00 63.50 5.24 6.57 6.25 6.10 6.14 6.45 5.61 Cycle 19 COLR Revision 31 Page 31 of 51l

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 MAPLHGR Limits for Rated Power and Rated Flow for GNF2 Fuel(cont.)

Average Planar Bundle Type: GNF2-PI0DG2B406-6G6.0/6G5.0/2G4.0-100T2-145-T6-3641 (GNF2)

Exposure MAPLHGR Limit (kWft )

GWd/MT GWdIST Lat. 9676 Lat. 9698 Lat. 9699 Lat. 9700 Lat. 9701 Lat. 9702 Lat. 9682 0.00 0.00 9.76 9.00 9.15 9.25 8.67 8.39 10.44 0.22 0.20 9.67 9.05 9.20 9.30 8.71 8.43 10.38 1.10 1.00 9.45 9.12 9.28 9.39 8.80 8.53 10.21 2.20 2.00 9.38 9.22 9.40 9.50 8.93 8.67 10.16 3.31 3.00 9.39 9.33 9.51 9.62 9.06 8.81 10.16 4.41 4.00 9.42 9.43 9.63 9.75 9.21 8.96 10.19 5.51 5.00 9.46 9.54 9.75 9.87 9.36 9.12 10.22 6.61 6.00 9.49 9.62 9.86 10.00 9.51 9.28 10.25 7.72 7.00 9.53 9.70 9.96 10.10 9.64 9.42 10.27 8.82 8.00 9.56 9.78 10.07 10.21 9.77 9.57 10.29 9.92 9.00 9.58 9.86 10.17 10.31 9.91 9.72 10.31 11.02 10.00 9.60 9.94 10.27 10.42 10.04 9.86 10.32 12.13 11.00 9.53 9.96 10.35 10.51 10.10 9.90 10.32 13.23 12.00 9.44 9.95 10.35 10.52 10.13 9.95 10.24 14.33 13.00 9.35 9.93 10.35 10.52 10.15 9.98 10.14 15.43 14.00 9.25 9.91 10.33 10.49 10.16 9.99 10.04 16.53 15.00 9.16 9.88 10.29 10.40 10.14 9.99 9.94 17.64 16.00 9.06 9.85 10.23 10.31 10.11 9.96 9.83 18.74 17.00 8.95 9.80 10.17 10.22 10.07 9.93 9.73 19.84 18.00 8.85 9.75 10.11 10.12 10.03 9.90 9.62 20.94 19.00 8.75 9.69 10.04 10.03 9.93 9.86 9.52 22.05 20.00 8.65 9.63 9.97 9.93 9.83 9.82 9.42 23.15 21.00 8.54 9.56 9.90 9.83 9.74 9.78 9.31 24.25 22.00 8.44. 9.50 9.83 9.73 9.64 9.69 9.21 25.35 23.00 8.34 9.44 9.76 9.64 9.54 9.59 9.10 26.46 24.00 8.23 9.37 9.69 9.54 9.45 9.49 9.00 27.56 25.00 8.13 9.31 9.62 9.44 9.35 9.39 8.90 33.07 30.00 7.63 8.99 9.13 8.97 8.89 8.92 8.39 38.58 35.00 7.13 8.67 8.63 8.51 8.45 8.47 7.90 41.22 37.39 6.89 8.48 8.40 8.29 8.25 8.27 7.66 44.09 40.00 6.64 8.27 8.16 8.06 8.03 8.05 7.41 49.60 45.00 6.15 7.81 7.71 7.62 7.61 7.62 6.92 54.38 49.33 5.24 -- -- -- -- --

55.12 50.00 -- 7.37 7.28 7.20 7.21 7.22 6.44 58.58 53.14 -- -- -- -- -- 5.61 60.63 55.00 -- 6.93 6.88 6.80 6.83 6.84 --

62.21 56.44 -- 6.51 -- -- -- --

63.60 57.69 .....-- -- 6.44 --

63.78 57.86 .....--. 6.15 --..

63.79 57.87 .... 6.55 -- --...

64.04 58.10 -- -- -- 6.10 -- -- --

70.00 63.50 5.24 6.51 6.55 6.10 6.15 6.44 5.61 Cycle 19 COLR Revision 31 Page 32 of 51 I

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 MAPLHGR Limits for Rated Power and Rated Flow for GNF2 Fuel(cont.)

Average Planar Bundle Type: GNF2-P10DG2B407-6G6.0/2G5.016G4.0-100T2-145-T6-3642 (GNF2)

Exposure MAPLHGR Limit (kWlft_

Lat. Lat. Lat. Lat. Lat. Lat. Lat.

GWd/MT GWd/ST 9676 9703 9704 9705 9706 9707 9682 0.00 0.00 9.76 8.79 8.91 9.00 8.69 8.42 10.44 0.22 0.20 9.67 8.84 8.95 9.04 8.74 8.46 10.38 1.10 1.00 9.45 8.91 9.03 9.12 8.83 8.56 10.21 2.20 2.00 9.38 9.00 9.13 9.23 8.97. 8.70 10.16 3.31 3.00 9.39 9.10 9.23 9.33 9.11 8.85 10.16 4.41 4.00 9.42 9.19 9.34 9.44 9.26 9.01 10.19 5.51 5.00 9.46 9.29 9.44 9.55 9.42 9.18 10.22 6.61 6.00 9.49 9.39 9.55 9.66 9.58 9.36 10.25 7.72 7.00 9.53 9.49 9.66 9.78 9.73 9.52 10.27 8.82 8.00 9.56 9.59 9.78 9.89 9.88 9.67 10.29 9.92 9.00 9.58 9.69 9.89 10.01 10.02 9.83 10.31 11.02 10.00 9.60 9.79 10.01 10.13 10.15 9.97 10.32 12.13 11.00 9.53 9.80 10.05 10.18 10.20 10.01 10.32 13.23 12.00 9.44 9.80 10.05 10.19 10.22 10.03 10.24 14.33 13.00 9.35 9.79 10.05 10.18 10.22 10.04 10.14 15.43 14.00 9.25 9.77 10.02 10.15 10.20 10.03 10.04 16.53 15.00 9.16 9.74 9.98 10.10 10.17 10.01 9.94 17.64 16.00 9.06 9.69 9.93 10.05 10.13 9.98 9.83 18.74 17.00 8.95 9.64 9.87 9.98 10.09 9.95 9.73 19.84 18.00 8.85 9.58 9.81 9.92 10.04 9.91 9.62 20.94 19.00 8.75 9.52 9.74 9.85 9.94 9.87 9.52 22.05 20.00 8.65 9.46 9.68 9.78 9.85 9.83 9.42 23.15 21.00 8.54 9.40 9.61 9.71 9.75 9.79 9.31 24.25 22.00 8.44 9.34 9.55 9.65 9.65 9.70 9.21 25.35 23.00 8.34 9.28 9.48 9.58 9.56 9.60 9.10 26.46 24.00 8.23 9.22 9.42 9.51 9.46 9.50 9.00 27.56 25.00 8.13 9.16 9.36 9.45 9.37 9.41 8.90 33.07 30.00 7.63 8.86 9.04 9.00 8.90 8.93 8.39 38.58 35.00 7.13 8.56 8.65 8.53 8.46 8.48 7.90 41.22 37.39 6.89 8.40 8.43 8.32 8.26 8.27 7.66 44.09 40.00 6.64 8.24 8.18 8.08 8.04 8.05 7.41 49.60 45.00 6.15 7.82 7.72 7.64 7.62 7.62 6.92 54.38 49.33 5.24 -- -- -- -- -- --

55.12 50.00 -- 7.39 7.30 7.22 7.22 7.22 6.44 58.58 53.14 -- -- -- -- -- 5.61 60.63 55.00 6.67 6.89 6.81 6.83 6.84 --

61.35 55.66 6.48 -- -- -- --

62.41 56.62 -- 6.51 --

62.90 57.06 -- 6.53 --

63.63 57.73 ..-- 6.44 63.86 57.93 ........ 6.15 ....

70.00 63.50 5.24 6.48 6.51 6.53 6.15 6.44 5.61 Cycle 19 COLR Revision 31 Page 33 of 51 I

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.1-1 Most limiting MAPLHGR 10.0

"--*-GE14 -*GF 9.0 8.0 NoteI 7.0 MAPLHGR limits used by 3D Monicore are lattice specific

a. and are listed in Section 16.3 in the Supplemental Reload 9 lattice is shown in this figure as a function of average 1-planar exposure. Natural Uranium lattices are excluded -----

6.0

-from this figure. Use tables for accurate calculations if exposure in the the highest up for exposures Tables, applies value Thefor higher to 70 GWV/MT.

Inecessary.

5.0 I III I I II I IIIIIII I II I IIII 11 II 1 I II I A n

'-Ip.V 0.0

. ii

.I. .I.ii 5.0 I II I I 10.0 15.0 20.0 lii I

25.0 I

30.0 I

35.0 m l !ill 111 40.0 II 1i 45.0 50.0 TIH

' 1~=-0f1*1--I-55.0

1. --

60.0 A4a Average Planar Exposure (GWd/ST)

Cycle 19 COLR Revision 31 Page 34 of 51 1

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.1-2 Flow Dependent MAPLHGR Factor (MAPFACF) 1.1 THT -W~ I tH~85L1.0 4-k-It t 1.0 I 1-J.-

IF H

0-

[.47

..

..

....

C) 4

0. 0.8 I~~ . .....

...

.1.

0.7 0.6 30.0.62 1 T!.-

F--

11-' Lr

-

I--if 30!

A1. H 11H-1VH +/-H F+4- H 30 40 50 60 70 80 90 100 110 Core Flow %

Cycle 19 COLR Revision 31 Page 35 of 51 1

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Cycle 19 COLR Revision 31 Page 36 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.2 Linear Heat Generation Rate (LHGR)

Reference Technical Specification: 3.11 .B When reactor power is greater than 25%, the LHGR of any rod in any fuel assembly at any axial location shall not exceed the rated power and rated core flow limits presented in Reference 5.17. Figure 3.2-1 represents LHGR curves for GE14 fuel. Proprietary detailed values for both GE14 and GNF2 fuels are in Reference 5.17. At other than rated power and rated flow conditions, the applicable limiting LHGR value for each fuel type is the smaller of the flow- and power-dependent LHGR limits, LHGRF and LHGRp. The flow-dependent LHGR limit, LHGRF, is the product of the LHGR flow factor, LHGRFACF, shown in Figure 3.2-2 and the LHGR for rated power and flow conditions in Reference 5.17. The power-dependent LHGR limit, LHGRp, is the product of the LHGR power factor, LHGRFACp, shown in Figure 3.2-3 and the LHGR for rated power and flow conditions in Reference 5.17.

LHGR Curves in Figure 3.2-1 are representative curves for U02 fuel rods and Gd containing rods for GE14 Fuel. A Figure comparable to Figure 3.2-1 for GNF2 is not included because GNF has requested Entergy to protect this proprietary information. Gd containing fuel rods have different LHGR limits that are also exposure dependent. Reference 5.17 documents the detailed proprietary curves and values for both GE14 and GNF2 fuels. Reference 5.23 documents the GESTAR II compliance of GNF2 fuel, as amended. Amendment 33 to GESTAR II incorporated Prime T-M methods. Cycle 19 LHGR limits are based on using PRIME for U02 fuel rods and GESTR-M for Gd rods, as GESTR-M limits for Gd rods are more conservative.

Pbypass is the power level below which more restrictive thermal limits are applied, as Turbine Stop Valve closure and Turbine Control Valve Fast Closure scrams are assumed to be bypassed. Pbypass can be set in anywhere in the range 32.5 to 45% core thermal power.

Pbypass is currently set at 32.5% power.

Cycle 19 COLR Revision 31 Page 37 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.2-1 Most Limiting LHGR for GE14 Fuel At Rated Power and rated Core Flow 14 13 T

12 11 10

-9

.7

-J 5

4 0 10 20 30 40 50 60 70 Exposure, GWDIST Cycle 19 COLR Revision 31 Page 38 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.2-2 Flow Dependent LHGR Factor (LHGRFACF) 1.1 1.0 0.9 C,

LL 0.8 C,

0.7

-J 0.6 0.5 30 40 50 60 70 80 90 100 110 Core Flow %

Cycle 19 COLR Revision 31 Page 39 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.2-3 Power Dependent LHGR Factors Note: These LHGRFACp factors are valid for Turbine bypass in or out of service and for Normal Feedwater heating 1

0.95 0.9 0.85

. ... .. ....

0.8 325 0.83! 4- _

0.75 P > Pbypass.

For P, % power > Pbypass and 32.5% .; Pbypass <45%

0.7 Core Flowq 50%, Ps Pbypass, where .i - -

C) 0.65

(. 32.5% 5 Pbypass S 45%

0.6 - ,_ ~~~45,0.557 i _ __

0.55 2 _ 4 [4 5. ... ........

0.5 . ...~~ ~ ..._.~.. ~ ... ~ ~ ....

....................... ~ ...

~ .._.

....

....

..........

........

...... ........ ....

... .......... ...............

... .............

..................... ........

. ....

............

.......

....

... .......

... . ........ ......

0.45 -0. __7

_ .3:2.5,0439' _____ Core Flow> 50%, P:5 Pbypass, where 0.4 i 32.5% r Pbypass <45%

0.3

'2, 0.3..

. - I I 0.3 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 10,

% Power Cycle 19 COLR Revision 31 Page 40 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.3 Minimum Critical Power Ratio (MCPR)

Reference Technical Specification: 3.11 .C During power operation, the MCPR shall be greater than or equal to the Operating Limit MCPR (OLMCPR). The operating limit MCPR is the greater of the flow- and power-dependent MCPR operating limits, MCPRF and MCPRp. The flow-dependent MCPR operating limit, MCPRF, is provided in Figure 3.3-1. For power level less than Pbypass, the MCPRp is independent of the fuel type and can be directly read from Figure 3.3-2, when Turbine Bypass is operable and from Figure 3.3-3, when Turbine Bypass is out of service.

Above PB MCPRp is the product of the rated power and flow MCPR operating limit presented i Table 3.3-1, and the Kp factor presented in Figure 3.3-2, when Turbine Bypass is in service and from Figure 3.3-3, when Turbine Bypass is out of service . The rated power and flow MCPR operating limits presented in Tables 3.3-1 are functions of 'U.

Both Figures 3.3-2 and 3.3-3 include normal and reduced feed water temperature operating modes. For SLO MCPRp and MCPRF are raised by 0.03 compared to TLO values shown in Figures 3.3-2 and 3.3-3.

The value of t 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. TS 4.11.C defines -.

Pbypass is the power level below which more restrictive thermal limits are applied, as Turbine Stop Valve Closure and Turbine Control Valve Fast Closure scrams are assumed to be bypassed. Pbypass can be set anywhere in the range 32.5% to 45% core thermal power.

Pbypass is currently set at 32.5%.

Cycle 19 COLR Revision 31 Page 41 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.3-1 MCPR ODeratina Limits At Rated Power and Rated Flow The MCPR Operating Limit for Two Loop Operation (OLMCPRTLO) is a function of fuel type, exposure, and t, which is derived from scram timing measurements.

GNF2 GE14 Tau CBO to MOC MOC to EOC BOC to MOC MOC to EOC From To 0.0 1.50 1.55 1.46 1.51 0.0 0.1 1.51 1.56 1.48 1.53 0.1 0.2 1.52 1.57 1.49 1.55 0.2 0.3 1.53 1.58 1.50 1.57 0.3 0.4 1.54 1.59 1.51 1.58 0.4 0.5 1.55 1.60 1.52 1.60 0.5 0.6 1.56 1.61 1.53 1.62 0.6 0.7 1.57 1.62 1.54 1.63 0.7 0.8 1.58 1.63 1.55 1.65 0.8 0.9 1.59 1.64 1.56 1.67 0.9 1.0 1.60 1.65 1.57 1.68 BOC = Beginning Of Cycle MOC = Middle of Cycle = End Of Rated Power Operation At Rated Flow (EOR) - 1.455 GWd/ST EOC = End Of Cycle Note: The rated OLMCPR Limits given above apply to both normal and reduced Feedwater Temperature as well as Turbine Bypass Valve OOS and Turbine bypass Valves in service. Off rated MCPR limits are given in Figures 3.3-1, 3.3-2 and 3.3-3 as taken from the Supplemental Reload Licensing Report (Reference 5.15).

Single Loop Operation OLMCPR SLO = 0.03 + OLMCPR TLO , where OLMCPR TLO is selected from the Table above.

Cycle 19 COLR Revision 31 Page 42 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.3-1 Flow Dependent MCPR Limits (MCPR F)

U.

Q.

0 2

60 65 70 75 80 85 Core Flow, % Of Rated Cycle 19 COLR Revision 31 Page 43 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.3-2 Power Dependent MCPR Limits (MCPRp)

Turbine Bypass is Assumed Operable and Normal and Reduced Feedwater Temperature 3.50 32.5, 3.01 3.00 ,

% SOLMCPR for 25%.-5 P:5 Pbypass and Core Flow >

50%

\~ ~ S S

S

-S S

S 45, 2.58 A

. 2.0

. . .. ...... ..

2.50 ~2~244j C- OLMCPR for 25% <9P <- Pbypass and Core Flow ,

S S

S 50%

S S

-- S

~ S F.5 _ :~ .. . ........ . . . . .. :.... .

02.00 C. When P < Pbypass and in SLO, OLMCPRp is raised by 0.03 compared to TLO values. When P >

Pbypass and in SLO, the rated OLMCPR is raised by 0.03 before multiplying by Kp to calculate OLMCPRp.

1.50 Kp for P > Pbypass P = % Power and 45% > Pbypass >

25 2 J.... 145, 1.206 60,1 9.........19 85,1.066 101-00 1.00 1.00 25 45 65 85 Power (%)

Cycle 19 COLR Revision 31 Page 44 of 51 1

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.3-3 Power Dependent MCPR Limits (MCPRp)

Turbine Bypass is Assumed Out of Service and Normal and Reduced Feedwater Temperature t25.,4.49 4.50 A When P < Pbypass and in SLO, OLMCPRp is raised by 0.03 compared to TLO values. When P > Pbypass and in SLO, the rated OLMCPR is raised by 0.03 before multiplying by Kp to 4.00 calculate OLMCPRp.

........

.7

......

.

3.50

.4,,,..,

C.

a-3.00 25 2.98 .4

.4

.4

.4 .... ......

..

.4

.4 0 .. ..... . .

..

I-.

0 * . OLMCPR for 25% S P : Pbypass and Core Flow < 50%

02.50 P = % Power and 45% > Pbypass > 32.5%

... ....

. . .. ...........

46.2.2 2.00

....~~ ... .... .........

~~ . .. ;J= Kpfor %PPower

... > Pbypass and 45% >Pbypass >32.5% ... i 1.50 325..25 F =!v~ 60. 196

..... . ..

......... .. ........... ....

1.00 25 35 45 55 65 75 85 95 Power (%)

Cycle 19 COLR Revision 31 Page 45 of 51 1

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.4 Power/Flow Relationship During Power Operation Reference Technical Specification: 3.11.D The Cycle 19 stability analysis does not credit the flow clamp feature of the FCTR cards. The dominance of Core Wide Oscillations was demonstrated without the use of the flow clamp. APRM Flux scram and Rod Block curves without the flow clamp are therefore applicable to Cycle 19.

The power/flow relationship shall not exceed the limiting values shown on the Power/Flow Operating Maps in Figures 3.4-1 when in Two Loop Operation and 3.4-2 when in Single Loop Operation.

Cycle 19 operation is not fully analyzed for reduced feedwater temperature for issues other than thermal limits. This report contains only the thermal limit analysis results for reduced feed water temperature mode.

The exclusion and the buffer regions shown in Figures 3.4-1 and 3.4-2 are based on Stability Solution I-D (references 5.4, 5.12, 5.15 and 5.2OCycle 19 Stability Analysis utilizes Reference 5.24 ODYSY LTR that removed the decay ratio adder of 0.15.Figures 3.4-1 and 3.4-2 show APRM Scram and Rod Block lines using Allowable values as a function of Core Flow.

Single Loop Analysis limits maximum Core Flow to 52% of Rated Core Flow and maximum Power to 65% of Rated due to SLO vessel internal vibration (Ref. 5.7, p. 1-2).

Various lines on the Power to flow map are described in Ref. 5.14.

Cycle 19 COLR Revision 31 Page 46 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIGURE 3.4-1 PILGRIM POWER I FLOW MAP - Two Loop Operation Scram and Rod Block Data based on Allowable Values CORE FLOW, MLB/HR 0 5 10 I6 20 25 30 34 Ah A& R

~lA~ttftCDJfl~a--Iwso 2835 128 120 2434 118 110 2332 2231 105 2129 100 *2028 1927 U

90 Ing?

0 w 80 75 1822 1621 70.

1420 6O 1315 1217 1115 1014 rU. 45 40 35 511 710 30 25 507 20 408 10 304 10 203 0- 101 0v 0 a 10 15 20 26 30 35 40 4 50 G so SS 70 78 so CORE FLOW, MLIM4R Cycle 19 COLR Revision 31 Page 47 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIGURE 3.4-2 PILGRIM POWER I FLOW MAP - Single Loop Operation Scram and Rod Block Data based on Allowable Value Setpolnt CORE FLOW, MLB/HR 0 5 10 15 20 25 30 35 40 46 65 70 75 80 125 2535 120 ,2434 115 . . ... . ..... . :. I . . . . . .. . . . . . . . . . .. . . 2332 110 2231 105 100

-*.--tSOUN * :-** ........ *V÷* .i**........* ...............  !** *  ! 2129

. . . . . . . . .P. . . -..

0..

. . ...  %., 2028 a

Lu 95 1927 90

......*LO*:[:-

,* ....

A.

'-..*-*.,--*

.....................

........ ..

.........  !.'s :nON! ... . . .... 1825 as 80 OPERATION! *: 1724 1622 75 1521

0. 70 . .. H B...T.E S". . . , . . .. 1420 66 INMU OWRINE LOCK CLM T14 1318 60 1217 55 60 1116 1014 0

n.) 45 913 40 811 o.

35 710 0 30 608 25 507 20 "::' "i ,",:":*: ... .::.:*i'.;': I)':"' MIN MUM POWER NTERLO K "*!:' :;,**.:

408 L.-INE*::.*.* ... *.* .*,::.-:.*.  :-.:* .S *. ...

16 304 0 PUM .ý[ ..'PE.".

."t 1"26%).*:.:.:K  : :L'*.,*,* ,. .: * . .*:.

10 203 5- 101 0 5 10 15 20 25 30 35 40 a 45 50 56 60 65 70 76 80 CORE FLOW, MLBIHR Cycle 19 COLR Revision 31 Page 48 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 4.0 REACTOR VESSEL CORE DESIGN Reference Technical Specification: 4.2 The reactor vessel core for the present cycle consists of 580 fuel assemblies of the types listed below. The core loading pattern (Ref. 5.15) for each type of fuel is shown for the present cycle in Figure 4.0-1.

Fuel Type Cycle Number Load Irradiated:

GE14-P1ODNAB399-10G6.0/3G5.0/1G2.0-10OT-145-T6-2828 16 67 GE14-P1ODNAB398-8G6.0/5G5.0/2G4.0-10OT-145-T6-2829 (GE14C) 16 45 GE14-P10DNAB399-15GZ-100T-145-T6-2957 (GE14C) 17 32 GE14-P1ODNAB398-5G6.0/10G5.0-100T-145-T6-2958 (GE14C) 17 32 GE14-P1ODNAB400-13GZ-100T-145-T6-2959 (GE14C) 17 24 GE14-P10DNAB404-5G6.0/10G5.0-100T-145-T6-2960 (GE14C) 17 40 GE14-P1oDNAB400-12G6.0/3G5.0-10OT-145-T6-2961 (GE14C) 17 32 GNF2-P 10DG2B389-6G6.0/8G5.0-100T2-145-T6-3141 (GNF2) 18 16 GNF2-PI DG2B389-6G6.0/2G5.0/6G4.0-100T2-145-T6-3142 (GNF2) 18 104 GNF2-P 10DG2B388-6G6.0/7G5.0-100T2-145-T6-3143 (GNF2) 18 36 New:

GNF2-P 1ODG2B401-6G6.0/8G5.0/1G4.0-100T2-145-T6-3421 (GNF2) 19 24 GNF2-P10DG2B395-6G6.0/9G5.0-100T2-145-T6-3422 (GNF2) 19 16 GNF2-P10DG2B375-6G6.0/7G5.0-100T2-145-T6-3434 (GNF2) 19 16 GNF2-P 1ODG2B401-6G6.0/2G5.0/6G4.0-100T2-145-T6-3640 (GNF2) 19 36 GNF2-P10DG2B406-6G6.0/6G5.0/2G4.0-100T2-145-T6-3641 (GNF2) 19 16 GNF2-P10DG2B407-6G6.0/2G5.0/6G4.0-100T2-145-T6-3642 (GNF2) 19 44 Total: 580 The reactor vessel core contains 145 cruciform-shaped control rods. The control materials used are either boron carbide powder (B4 C) compacted to approximately 70%

of the theoretical density or a combination of boron carbide powder and solid hafnium.

Cycle 19 COLR Revision 31 Page 49 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIGURE 4.0-1 Reactor Vessel Core Loading Pattern 3MO mm 00 m143 22 21 E4-10ABO-5 EO1O.O100T-145-T6-296 (CycleE17

. 3 ý I J 1I 1 I S 111 [ ? 21 ,*3 "5 27 .

1 1 33 ., j*5

?J ý9 41 43 4- 47 4D t,l A=GE14-PlODNAB404-5G6.0/10GS.0-100T-145-T6-2960 (Cycle 17)

S--GE14-PIODNA8398-5G6.0/10G5.0-10OT-145-T6-2958 (Cycle 17)

C=GE14-Pt0DNAB399-1OG6.0/3GS.0/1G2.0-100T-145-T6-2828 (Cycle 16)

D=GNF2-P10DG2B388-6G6.0/7GS.0-10OT2-145-T6-3143 (Cycle 18)

E=GNF2-P10DG2B395-6G&O/gG5.0-100T2-145-T6-3422 (Cycle 19)

F=GNF2-P1CDG2B401-6G&o/SGS.O/1G4.0-1o0T2-145-T6-3421 (Cycle 19)

G=GE14-P10DNAB400-13GZ-100r-14S-T6-2959 (Cycle 17)

H--GE14-P10DNA8399-15GZ-100T-145-T6-2957 (Cycle 17)

---

GNF2-PlOOG2B389-6G6.0/SGS.O-lOCT2-145-T6-3141 (Cycle 18)

J--=NF2-PlOcG2B407-6G6.0/2G5.0/6G4.0-100T2-145-T6-3642 (Cycle 19)

K=GE14-P1ODNAB398-8G6.0/SG5.0/2G4.0-10OT-145oT6-2829 (Cycle 16)

L=GNF2-P1ODG2B406-6G&O/6GS.0/2G4.0-1OOT2-145-T6-3641 (Cycle 19)

M=GE14-P1ODNAB4OC-12G6.0/3GS.O-1fOT-145-Th-2961 (Cycle 17)

N=GNF2-P1ODGZB389-6G6.0/2GS.0/6G4.0-1c0T2-145-T6-3142 (Cycle 18)

O=GNF2-P1OOG2B37S-6G6,0/7GS.O.-1OaT2-145-T6-3434 (Cycle 19)

P=GNF2-PIODG2B401-6G6.0/2GS.O/6G4.0-100"F2-145-T6-3640 (Cycle 19)

Cycle 19 COLR Revision 31 Page 50 of 51

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02

5.0 REFERENCES

5.1. NEDE-24011-P-A-17 and NEDE-24011-P-A-17-US, "General Electric Standard Application for Reactor Fuel", September 2010, eB record: RA-ENO-GEN-10-147.

5.2. EC17226, Cycle 19 Reload Core Design.

5.3. NEDC-31852-P, rev. 4, "Pilgrim Nuclear Power Station SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis for PNPS", January 2008.

5.4. NEDC-33155P, Rev.0, Application of Stability Long-Term Solution Option I-D To Pilgrim Nuclear Power Station, October 2004.

5.5. Letter 1.09.015, Letter from the NRC approving TS Amendment 232 for Cycle 18 SLMCPR.

5.6. GE-NE-GENE-0000-0033-6871-01, Rev. 0, Pilgrim Option I-D APRM Flow Biased Set points, October 2004.

5.7. GE-NE-0000-0027-5301, Rev 2, Pilgrim Nuclear Power Station Single Loop Operation, April 2006.

5.8. S&SA-186, % AWD for use with Stability Option I-D for Pilgrim (applicable to SLO).

5.9. SUDDS/RF 94-42, NEDC-32306P, "Maximum Extended Load Line Limit Analyses",

March 1994.

5.10. SUDDS/RF 88-160, NEDC-31312-P, "ARTS Improvement Program Analysis for Pilgrim Nuclear Power Station", September 4, 1987.

5.11. A22-00109-00 MAPLHGR set down process explanation for Pilgrim, November 2001.

5.12. GNF2NFI, GEH-0000-0085-9069-RO, GNF2 Fuel Design Cycle Independent Analyses for Entergy PNPS, February 2009.

5.13. ER 03110960, Stability I-D implementation.

5.14. PNPS-RPT-03-00001, Rev. 6, "Pilgrim Power To Flow Map Report."(EC27443) 5.15. ECH-NE-11-00013, 0000-0119-4309-SRLR, "Supplemental Reload Licensing Report, Reload 18, Cycle 19." January 2010 and GESTAR Assessments.

5.16. PNPS-NE-10-00006, EC23405, Cycle 19 OPL-3, Transient Analyses Inputs.

5.17. ECH-NE-1 1-00014, 0000-0119-4309-FBIR, Rev.0, Fuel Bundle Information Report, Cycle 19, January 2011 (EC27442).

5.18. SUDDS/RF 02-86, GNF SER issued by NRC approving elimination of Upper Bound PCT limit requirement.

5.19. EC7933 documents OPL-4 & 5 LOCA Inputs.

5.20. NEDO-32465A, Licensing Topical report "Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Application, August 1996.

5.21. GNF2LOCA, 0000-0095-4071-RO, PNPS GNF2 ECCS-LOCA Evaluation, February 2009.

5.22. RA-ENO-HK1-09-027, Pilgrim Cycle 17 MAPLHGR Extension, March 24, 2009 5.23. NEDE-33270P, GNF2 Advantage Generic Compliance with GESTAR II), Revision 3, March 2010 (This reference is also known as Amendment 22 report for GNF2). (record in eB: RA-ENO-GEN-10-040) 5.24. NEDE-33213, ODYSY Application for Stability Licensing Calculations Including Option I-D and II Long Term Solutions, April 2009 Cycle 19 COLR Revision 31 Page 51 of 51