ML091390257

Submittal of Core Operating Limits Report, Revision 29 (Cycle 18)

ML091390257
Person / Time
Site:	Pilgrim
Issue date:	05/15/2009
From:	Lynch J R Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2.09.033
Download: ML091390257 (60)

Text

En tergy Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 May 15, 2009 U.S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D.C. 20555-0001

SUBJECT:

Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power Station Docket 50-293 License No. DPR-35 Core Operating Limits Report, Revision 29 (Cycle 18)LETTER NUMBER: 2.09.033

Dear Sir or Madam:

The enclosed revision of Pilgrim Nuclear Power Station's (PNPS) Core Operating Limits Report (COLR) is submitted in accordance with the requirements of Pilgrim's Technical Specification 5.6.5.Revision 29 provides cycle-specific limits for operating Pilgrim during Cycle 18.This letter contains no new commitments.

Should you require further information concerning this COLR revision please contact me at (508) 830-8403.Sincerely, Joseph R ~yc Manager, Licensing WGL/wl

Enclosure:

PNPS Core Operating Limits Report, Revision 29 cc: Regional Administrator, Region 1 U.S. Nuclear Regulator Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Pilgrim Nuclear Power Station Mr. James S. Kim, Project Manager Plant Licensing Branch I-1 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North O-8C2 11555 Rockville Pike Rockville, MD 20852 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING UMITS REPORT RTYPE: G4.02 (CYCLE 18)4/16/2009 PREPARED: Shivaram Paranjape, BWR Fuels Date VERIFIED:Ro e. BWR FU3 APPROVED.-, nae F uels & Analysis APPROVED:

-1 Gary Jam , Rsactor Engineering Supervisor

/Date APPROVED:

, Oran Sullivan, uW dear Engineerng Drector r/ Dot-APPROVED:

O DO9 osRc meeting #: 2- 10'1 oGIR APPROVED APPROVED APPROVED:): D. Noyes, operationsMapwger Date'Robedrt G. Sini Gene Plant Operations ( /Date K. Brons~on, Site V DPre ntate 9 Revision 29 Cycle 18 COLR Page 1 of 59

'PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 TABLE OF CONTENTS PaEae T IT L E & C O V E R P A G E .............................................................................................................

1 T A B LE O F C O N T E N T S ............................................

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

2 R EC O R D O F R EV IS IO N S ..................................................................................................

3 LIST OF TABLES ........................................................

4 L IS T O F F IG U R E S .....................................................................................................................

5

1.0 INTRODUCTION

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

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) ..............................................................

16 2.3 Rod Block M onitor Trip Setting .................................................................................

16 3.0 CO R E O PERATING LIM ITS .....................

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

25 3.1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)

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25 3.2 Linear Heat Generation Rate (LHGR) .....................................................................

42 3.3 Minimum Critical Power Ratio (MCPR) ................

.........

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46 3.4 Power/Flow Relationship During Power Operation

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51 4.0 REACTOR VESSEL CORE DESIGN ....................................

57 5 .0 R E F E R E N C E S ..............................................................................................................

5 9 Cycle 18 COLR Revision 29 Page 2 of 59 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT* RECORD OF REVISIONS RTYPE: G4.02 Revision 8A 9A 10A 11A 11B 11C 11D 12A 12B 12C Effective Date Effective date based on issuance of license amendment by NRC Effective date based on issuance of license amendment by NRC for ARTS and SAFER/GESTR Effective date based on initial startup of Cycle 10 Effective date based on initial startup of Cycle 11 Effective upon final approval Effective upon final approval Effective upon final approval Effective date based on issuance of license amendment by NRC for SLMCPR of 1.08 Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval Effective upon final approval 12D 13A 14A 15A 15B 16A 16B Description Applicable for use during Cycle 8 Operation Applicable for use during Cycle 9 operation Applicable for use during Cycle 10 Operation Applicable for use during Cycle 11 Operation Applicable for use during Cycle 11 Operation Applicable for use during Cycle 11 Operation Applicable for use during Cycle 11 Operation Applicable for use during Cycle 12 Operation Renumbered Table 3.3-2 to 3.3-1, Sh. 2 of 2 and Table 3.3-1 to 3.3-1,Sh.

1 of 2 Changed Tech Spec section numbers referenced due to Tech Amendment

1. 177.Pages affected:

6, 24 Incorporated stability log-term solutioh option I-A.Applicable for use during Cycle 13 Operation Applicable for use during Cycle 14 Operation Applicable for use during Cycle 15 Operation Changed MAPLHGR Limits for GE14 fuel in response to an input error GE corrected.

Applicable for use during Cycle 15 Operation Applicable for use during Cycle 16 Operation Core Loading Change to replace leaking fuel bundle JLG621. Clarified P-F Map graphic on P.36. Applicable for use during Cycle 16 Operation Limits for Single Loop Operation were incorporated.

Rev number scheme changed to.Merlin Convention Applicable for use during Cycle 17 Operation Corrected typographical errors on p. 30, 34,38,39 per CR-PNP-2008-256 and 285 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 Applicable for use during Cycle 18 Operation Cycle 18 COLR Page 3 of 59 25 26 27 28 29 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 LIST OF TABLES Number 2.1-1 2.1-2 2.1-3 2.1-4 2.2-1 2.2-2 2.2-3 2.2-4 3.1-1 3.1-2 3.3-1 Title Formulae for APRM Flux Scram Trip Settings in Figure 2.1-1 Formulae for APRM Flux Scram Trip Settings in Figure 2.1-2 Formulae for APRM Flux Scram Trip Settings in Figure 2.1-3 Formulae for APRM Flux Scram Trip Settings in Figure 2.1-4 Formulae for APRM Rod Block Trip Settings in Figure 2.2-1 Formulae for APRM Rod Block Trip Settings in Figure 2.2-2 Formulae for APRM Rod Block Trip Settings in Figure 2.2-3 Formulae for APRM Rod Block Trip Settings in Figure 2.2-4 MAPLHGR Limits for Rated Power and Rated Flow for GE14 Fuel MAPLHGR Limits for Rated Power and Rated Flow for GNF2 Fuel MCPR Operating Limits At Rated Power and Rated Flow Page 8 9 10 11 17 18 19 20 26 36 47 Revision 29 Cycle 18 COLR Page 4 of 59 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 LIST OF FIGURES Number Title Paae 2.1-1 Allowable APRM Flux Scram Trip Settings -TLO with Flow Clamp 12 (Normal Feed water Temperature) 2.1-2 Allowable APRM Flux Scram Trip Settings -SLO with Flow Clamp 13 (Normal Feed water Temperature) 2.1-3 Allowable APRM Flux Scram Trip Settings -TLO without Flow Clamp 14 (Normal Feed water Temperature) 2.1-4 Allowable APRM Flux Scram Trip Settings -SLO without Flow Clamp 15 (Normal Feed water Temperature) 2.2-1 Allowable APRM Rod Block Trip Settings -TLO with Flow Clamp 21 (Normal Feed water Temperature) 2.2-2 Allowable APRM Rod Block Trip Settings -SLO with Flow Clamp 22 (Normal Feed water Temperature) 2.2-3 Allowable APRM Rod Block Trip Settings -TLO without Flow Clamp 23 (Normal Feed water Temperature) 2.2-4 Allowable APRM Rod Block Trip Settings -SLO without Flow Clamp 24 (Normal Feed water Temperature) 3.1-1 Most Limiting MAPLHGR 39 3.1-2 Flow-Dependent MAPLHGR Factor (MAPFACF) 40 3.1-3 Power-Dependent MAPHLGR Factors 41 3.2-1 Most Limiting LHGR for GE14 Fuel at Rated Power and Rated Core 43 Flow 3.2-2 Flow-Dependent LHGR Factor (LHGRFACF) 44 3.2-3 Power-Dependent LHGR Factors 45 3.3-1 Flow-Dependent MCPR Limits (MCPRF) 48 3.3-2 Power-Dependent MCPR Limits (MCPRp), Turbine Bypass Assumed 49 Operable and Normal and Reduced Feedwater Temperature 3.3-3 Power-Dependent MCPR Limits (MCPRp), Turbine Bypass Assumed 50 Out Of Service and Normal and Reduced Feedwater Temperature 3.4-1 Power/Flow Operating Map, Applicable to 0 to 2000 MWD/ST 52 Exposure Range Scram and Rod Block Data Based on AVs -TLO;with Flow Clamp; ATWS/MELLA Boundary 3.4-2 Power/Flow Operating Map, Applicable to 2000 to 5000 MWD/ST 53 Exposure Range Scram and Rod Block Data Based on AVs -TLO; No Flow Clamp; ATWS/MELLA Boundary 3.4-3 Power/Flow Operating Map, Applicable to 5000 MWD/ST to EOC 54 Exposure Range Scram and Rod Block Data Based on Allowable Values -TLO; No Flow Clamp 3.4-4 Power/Flow Operating Map, Applicable to 0 to 2000 MWD/ST 55 Exposure Range Scram and Rod Block Data Based on Allowable Values -SLO; with Flow Clamp 3.4-5 Power/Flow Operating Map, Applicable to 2000 MWD/ST to EOC 56 Exposure Range Scram and Rod Block Data Based on Allowable Values -SLO; No Flow Clamp 4.0-1 Reactor Vessel Core Loading Pattern 58 Cycle 18 COLR Revision 29 Page 5 of 59 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 18. In this report, Cycle 18 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 theapplicable values of the following fuel-related parameters:

Reference Technical Specification APRM Flux Scram Trip Setting (Run Mode)APRM Rod Block Trip Setting (Run Mode)Rod Block Monitor Trip Setting Average Planar Linear Heat Generation Rate Linear Heat Generation Rate (LHGR)Minimum Critical Power Ratio (MCPR)Power/Flow Relationship Reactor Vessel Core Design Table 3.1.1 Table 3.2.C-2 Table 3.2.C-2 3.11.A 3.11.B 3.11.C 3.11.D 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 1-D Exclusion Region and Buffer Zone.The reactor shall not be intentionally operated within the Exclusion Region given in Figures 3.4-1, 3.4-2, and 3.4-3 for Two Loop Operation (TLO) and Figures 3.4-4 and 3.4-5 for Single Loop Operation (SLO), as applicable.

Immediate exit is required for inadvertent entry into the exclusion region.The reactor shall not be intentionally operated within the Buffer Zone given in Figures 3.4-1, 3.4-2, and 3.4-3 for TLO and Figures 3.4-4 and 3.4-5, as applicable, 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 18 COLR Revision 29 Page 6 of 59 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 The Cycle 18 stability analysis credited the flow clamp feature of the FCTR cards from BOC to 2,000 MWD/ST to ensure the dominance of Core Wide Oscillations.

APRM Flux scram and Rod Block curves including the flow clamp have been developed for Cycle 18. These curves may be replaced with those that do not include the flow clamp after reaching a cycle exposure of 2,000 MWD/ST.APRM flux scram Allowable Trip Set points (ATSP) for TLO with and without the flow clamp are shown on Figures 2.1-1 and 2.1-3, respectively.

Both curves clamp power at 120% of rated core thermal power. Formulae used to develop Figures 2.1-1 and 2.1-3 are listed in Tables 2.1-1 and 2.1-3, respectively.

APRM flux scram Allowable Trip Set points (ATSP) for SLO with and without the flow clamp are shown on Figures 2.1-2 and 2.1-4, respectively.

Both curves clamp power at 120% of rated core thermal power. Formulae used to develop Figures 2.1-2 and 2.1-4 nre listed in Tables 2.1-2 and 2.1-4, respectively.

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.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 Revision 29 Cycle 18 COLR Page 7 of 59 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 with Flow Clamp Allowable Trip Set Point D o (ATSP)Drive Flow Range (ATSP)C D SLOPE INTERCEPT

% Rated 0.21 50.0 0 < WD< 25.3 0.79 50.0 25.3 < WD < 55.9 0.65 70.6 55.9 < WD 76 0 120.0 76 < WD < 125 Notes: 1. ATSP = C * % WD + D, ATSP is in % Power 2. Figure 2.1-1 shows the plot of ATSP vs. WD.3. Reference 5.6, Table 2.a is the basis for the values of constants listed in this Table.Revision 29 Cycle 18 COLR Page 8 of 59 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 with Flow Clamp Allowable Trip Set Point (ATSP)Drive Flow Range (ATSP)C D C D % Rated SLOPE INTERCEPT 0.21 47.9 0 < WD < 35.3 0.79 42.1 35.3 < WD < 65.9 0.65 64.1 65.9 < WD < 86 0 120.0 86 < WD 5 125 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 2.b is the basis for the values of constants listed in this Table.Cycle 18 COLR Page 9 of 59 1 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 2.1-3 Formulae For Allowable APRM Flux Scram Settings in Figure 2.1-3 Two Loop Operation without Flow Clamp Allowable Trip Set Point Drive Flow Range (ATSP)C D C D % Rated SLOPE INTERCEPT 0.20 71.5 0 < WD < 22.5 0.71 60.0 22.5 <WD 5 55.9 0.65 70.6 55.9 < WD < 76 0 120.0 76 < WD 5 125 Notes: 1. ATSP = C * % WD + D, ATSP is in %Power 2. Figure 2.1-3 shows the plot of ATSP vs. WD.3. Reference 5.6, Table 1.a is the basis for the values of constants listed in this Table.Cycle 18 COLR Page 10of59 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 2.1-4 Formulae For Allowable APRM Flux Scram Settings in Figure 2.1-4 Single Loop Operation without Flow Clamp Allowable Trip Set Point Drive Flow Range (ATSP)C D C D % Rated SLOPE INTERCEPT 0.20 69.5 0 -< WD < 32.5 0.71 52.9 32.5 < WD < 65.9 0.65 64.1 65.9 < WD < 86 0 120.0 86 < WD < 125 Notes: 1. ATSP=C*%WD+

D,ATSPisin

% Power 2. Figure 2.1-4 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 18 COLR Page 11 of 59 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.1-1 Allowable APRM Flux Scram Trip Settings -TLO with Flow Clamp (Normal Feedwater Temperature)

Cn E6-Cn I..130.0 120.0 110.0 100.0 90.0 80.0 70.0 60.0 50.0 40.0 0 10 20 30 40 50 60 70 80 90 100 110 120 WD, Drive Flow, %Cycle 18 COLR Page 12. of 59 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.1-2 Allowable APRM Flux Scram Trip Settings -SLO with Flow Clamp (Normal Feedwater Temperature) 0 co-E c-M.130.0 120.0 110.0 100.0 90.0 80.0 70.0 60.0 50.0-40.0 I.1 0 10 20 30 40 50 60 70 80 90 100 110 120 WD, Drive Flow, %Cycle 18 COLR Page 13 of 59 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.1-3 Allowable APRM Flux Scram Trip Settings -TLO without Flow Clamp (Normal Feedwater Temperature) 130.0 --i_ -- ------S120.0 -.0 110.0 -C-100.0 E 90.0 u) 80.0 ---i 7 0 .0 ...............

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

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

60.0 0 10 20 30 40 50 60 70 80 90 100 110 120 WD, Drive Flow, %Cycle 18 COLR Page 14 of 59 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.1-4 Allowable APRM Flux Scram Trip Settings -SLO without Flow Clamp (Normal Feedwater Temperature) 130.0 77120.0 110.0 .. ..2 70.0-. .2-...60.0 --0 10 20 -30 40 50 60 70 80 90 100 110 120 WD, Drive Flow, %Cycle 18 COLR Page 15 of 59 Revision 29 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.B.1 The Cycle 18 stability analysis credited the flow clamp feature of the FCTR cards from BOC to 2,000 MWD/ST to ensure the dominance of Core Wide Oscillations.

APRM Flux scram and Rod Block curves including the flow clamp have been developed Cycle 18. These curves may be replaced with those that do not include the flow clamp after reaching a cycle exposure of 2,000 MWD/ST.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 with and without the flow clamp shall be as given by Figures2.2-1 and 2.2-3, respectivley.

The ATSPRB is clamped at 115% of rated core thermal power for both curves. Formulae that form the basis of the Figures 2.2-1 and 2.2-3 are listed in Tables 2.2-1 and 2.2-3, respectively.

When the mode switch is in the RUN position, the average power range monitor (APRM) roda'block Allowable Trip setting (ATSPRB) as a function of drive flow for Single Loop Operation with and without the flow clamp shall be as given by Figures 2.2-2 and 2.2-4, respectively.

The ATSPRB is clamped at 115% of rated core thermal power for both curves. Formulae that form the basis of the Figures 2.2-2 and 2.2-4 are listed in Tables 2.2-2 and 2.2-4, respectively.

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 (% of Rated) (% of Reference Level)P < 25.9 Not applicable (All RBM Trips Bypassed)25.9 < P _ 62.0 120 62.0 < P < 82.0 115 82.0 < P 110 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 _ 25.9%of rated (Technical Specification Table 3.2.C-1, Note 5).Cycle 18 COLR Revision 29 Page 16 of 59 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Table 2.2-1 Formulae For Allowable APRM Rod Block Settings in Figure 2.2-1 Two Loop Operation with Flow Clamp APRM Rod Block Allowable Trip Set Poin (ATPRB)Drive Flow Range Point (ATSPRB)C D C D % Rated SLOPE INTERCEPT 0.21 45.0 0 <- WD -< 30.3 0.79 45.0 30.3 < WD -55.9 0.65 63.6 55.9 < WD -79.1 0 115.0 79.1 < WD -125 RTYPE: G4.02 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 2.a is the basis for the values of constants listed in this Table.Cycle 18 COLR Page 17 of 59 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Table 2.2-2 Formulae For Allowable APRM Rod Block Settings in Figure 2.2-2 Single Loop Operation with Flow Clamp APRM Rod Block Allowable Trip Set Drive Flow Range Point (ATSPRB)C 0 C D % Rated SLOPE INTERCEPT 0.21 42.9 0 -< WD -< 40.3 0.79 37.1 40.3 < WD -65.9 0.65 57.1 65.9 < WD -89.1 0 115.0 89.1 < WD -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 2.b is the basis for the values of constants listed in this Table.RTYPE: G4.02 Cycle 18 COLR Page 18 of 59 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Table 2.2-3 Formulae For Allowable APRM Rod Block Settings in Figure 2.2-3 RTYPE: G4.02 Two Loop Operation without Flow Clamp APRM Rod Block Allowable Trip Set Drive Flow Range Point (ATSPRB)C D C D % Rated SLOPE INTERCEPT 0.20 .66.5 0 < WD < 22.5 0.71 55.0 22.5 < WD 55.9 0.65 63.6 55.9 < WD < 79.1 0 115.0 79.1 < WD -125 Notes: 1. ATSPRB = C * % WD + D, ATSPRB is in % Power 2. Figure 2.2-3 shows the plot of ATSPRB vs. WD.3. Reference 5.6, Table 1.a is the basis for the values of constants listed in this Table.Revision 29 Cycle 18 COLR Page 19 of 59 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 2.2-4 Formulae For Allowable APRM Rod Block Settings in Figure 2.2-4 Sinqle Loop Operation without Flow Clamp V m m m APRM Rod Block Allowable Trip Set Drive Flow Range Point (ATSPRB)C D C D % Rated SLOPE INTERCEPT 0.20. 64.5 0 < WD 32.5 0.71- 47.9 32.5 < WD -65.9 0.65 57.1 65.9 < .WD 89.1 0 115.0 89.1 < WD -125 Notes: 1. ATSPRB = C * % WD + D, ATSPRB is in % Power 2. Figure 2.2-4 shows the plot of ATSPRB vs. WD.3. Reference 5.6, Table 1.b is the basis-or the Values of constants listed in this Table.Cycle 18 COLR Page 20 of 59 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.2-1 Allowable APRM Flux Rod BlockSettings

-TLO with Flow Clamp (Normal Feedwater Temperature) 0 11Z Cn 0 0 0L 120.0 110.0 100.0 90.0 80.0 70.0 60.0 50.0 40.0 0 10 20 30 40 50 60 70 80 90 100 110 120 WD, Drive Flow, %Revision 29 Cycle 18 COLR Page 21 of 59 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.2-2 Allowable APRM Flux Rod Block Settings -SLO with Flow Clamp (Normal Feedwater Temperature) 12 0 .0 ..V.Z.....

.....100.0l I _11 0.0 110.00 13 100.0 ao.o 100.0 r 40.0 , , 1 IL 0 10 20 30 40 50 60 70 80 90 100 110 120 WD, Drive Flow, %Cycle 18 COLR Page 22 of 59 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.2-3 Allowable APRM Flux Rod Block Trip Settings -T.1- without Flow Clamp (Normal Feedwater Temperature)

C~0 C.2 0 120.0 110.0 100.0 90.0 80.0 70.0 60.0 0 10 20 30 40 50 60 70 80 90 100 110 120 WD, Drive Flow, %Revision 29 Cycle 18 COLR Page 23 of 59 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.2-4 Allowable.

APRM Flux Rod Block Trip Settings -SLO without Flow Clamp (Normal Feedwater Temperature) 120.0 ...--i iK j 110.0 _a. 100.0 1-1-j __0 90. 0 A -o 980.0 F'---- I --0 70.0 .-60.10_ ...i a. 0 10 20 30 40 50 60 70 80 90 10010 120 WD, Drive Flow, %Revision 29 Cycle 18 COLR Page 24 of 59 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 ,3.0 CORE OPERATING LIMITS 3.1 Maximum Average 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).Pbypass 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 on which Tables 3.1-1 and 3.1-2 are based, indicate that no specific calculation of MAPLHGR limit was done at that point. Additionally, the limit value -given for last exposure statepoint 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 18 COLR Revision 29 Page 25 of 59 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 Bundle Type: GE14-P1ODNAB399-10G6.0/3G5.O/1 G2.0-10OT-145-T6-2828 (GE14C)Average Planar MAPLHGR Limit (kW/ft)Exposure Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT (GWd/ST) 6843 6844 6845 6846 6847 6848 0.00 (0.00) 9.80 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 1.10(1.00) 9.50 8.96 8.96 8.95 10.01 10.78 2.20(2.00) 9.44 9.10 9.13 9.12 9.98 10.77 3.31 (3.00) 9.45 9.23 9.31 9.31F 10.01 10.80 4.41 (4.00) 9.49 9.31 9.50 9.50 10.05 10.84 5.51 (5.00) 9.53 9.40 9.60 9.64 10.10 10.89 6.61 (6.00) 9.57 9:48 9.70 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 11.00 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 10.40 10.24 11.01 15.43 (14.00) 9.60 10.08 10.40 10.47 10.20 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 10.50 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 10.60 9.89 10.68 27.56 (25.00) 8.95 10.25 10.58 10.63 9.66 10.51 32.19 (29.20) 8.40 9.94 10.26 10.32 9.11 10.05 33.07 (30.00) 8.30 9.88 10.20 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 9.20 7.73 8.69 49.60 (45.00) 6.38 8.51 8.66 8.67 7.10 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 -- 5.50 62.70 (56.88) -- 4.87 -- -- --62.74 (56.91) -- -- --.. 4.52 63.50 (57.61) .... 5.32 5.49 ....64.36 (58.38) .... 4.92 --....64.70 (58.69) -- -- -- 4.94 -- --70.00 (63.50) 3.98 4.87 4.92 4.94 4.21 4.52'Revision 29 Cycle 18 COLR Page 26 of 59 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.)Bundle Type: GE14-P1ODNAB398-8G6.015G5.0/2G4.0-10OT-145-T6-2829 (GE14C)Average Planar MAPLHGR Limit (kW/ft)Exposure Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT (GWd/ST) 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 Revision 29.Cycle 18 COLR Page 27 of 59 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.)Bundle Type: GE1 4-P1ODNAB397-10G6.0/3G5.0-10OT-145-T6-2613 (GE14C)Average Planar MAPLHGR Limit (kW/ft)Exposure Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT (GWd/ST) 5841 5848 5849 5850 5846 5851 0.00(0.00) 9.80 8.75 8.72 8.71 10.21 10.87 0.22 (0.20) 9.71 8.81 8.79 8.78 10.16 10.84 1.10(1.00) 9.50 8.91 8.91 8.91 10.01 10.74 2.20 (2.00) 9.44 9.05 9.07 9.07 9.98 10.71 3.31 (3.00) 9.45 9.20 9.24 9.25 10.01 10.73 4.41 (4.00) 9.49 9.30 9.42 9.44 10.05 10.76 5.51 (5.00) 9.53 9.38 9.56 9.61 10.10 10.79 6.61 (6.00) 9.57 9.45 9.65 9.70 10.14 10.82 7.72(7.00) 9.61 9.54 9.74 9.80 10.18 '10.85 8.82 (8.00) 9.64 9.62 9.83 9.89 10.21 10.87 9.92 (9.00) 9.66 9.70 9.92 9.98 10.24 10.88 11.02 (10.00) 9.68 9.78 10.01 10.07 10.25 10.89 12.13 (11.00) 9.69 9.87 10.11 10.18 10.26 10.90 13.23 (12.00) 9.67 9.93 10.21 10.28 10.27 10.90 14.33 (13.00) 9.64 9.99 10.29 10.36 10.23 10.89 15.43 (14.00) 9.60 10.05 10.35 10.43 10.19 10.85 15.99 (14.51) 9.58 10.07 10.37 10.45 10.17 10.83 16.53 (15.00) 9.56 10.10 10.40 10.47 10.15 10.81 18.74 (17.00) 9.48 10.18 10.45 10.51 10.07 10.72 22.05 (20.00) 9.35 10.24 10.49 10.55 9.94 10.59 23.01 (20.87) 9.28 10.24 10.50 10.56 9.89 10.55 27.56 (25.00) 8.95 10.22 10.52 10.60 9.66 10.38 32.19 (29.20) 8.40 9.92 10.22 10.29 9.11 9.91 33.07 (30.00) 8.30 9.86 10.16 10.23 9.01 9.82 38.58 (35.00) 7.65 9.46 9.69 9.70 8.36 9.18 44.09 (40.00) 7.02 9.01 9.17 9.18 7.73 8.54'49.60 (45.00) 6.38 8.50 8.64 8.65 7.09 7.91 54.78 (49.70) 3.98 -- --.....55.12 (50.00) -- 7.92 8.10 8.12 5.63 7.28 58.14 (52.75) -- -- -- 4.21 --60.63 (55.00) 5.76 6.51 6.74 -- 5.12 62.02 (56.27) -- -- -- 4.47 62.56 (56.75) 4.87 -- --,....63.50 (57.61) -- 5.18 5.41 64.09 (58.14) 4.91 --64.53 (58.54) .... 7- 4.94 -- --70.00 (63.50) 3.98 4.87 4.91 4.94 4.21 4.47 Revision 29 Cycle 18 COLR Page 28 of 59 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.)Bundle Type: GE14-P1ODNAB397-14GZ-1OOT-145-T6-2621 (GE14C)Average Planar MAPLHGR Limit (kW/ft)GWd/MT (GWd/ST) Lattice Lattice Lattice Lattice Lattice Lattice Lattice 5841 5842 5843 5844 5845 5846 5847 0.00 (0.00) 9.80 8.66 8.76 -8.73 8.72 10.21 10.94 0.22 (0.20) 9.71 8.73 8.82 8.80 8.79 10.16 10.91 1.10(1.00) 9.50 8.84 8.93 8.92 8.92 10.01 10.81 2.20 (2.00) 9.44 8.99 9.07 9.09 9.09 9.98 10.79 3.31 (3.00) 9.45 9.14 9.20 9.26 9.27 10.01 10.81 4.41 (4.00) 9.49 9.24 9.27 9.43 9.46 10.05 10.83 5.51 (5.00) 9.53 9.33 9.34 9.51 9.56 10.10 10.87 6.61 (6.00) 9.57 9.41 9.41 9.59 9.64 10.14 10.89 7.72 (7.00) 9.61 9.50 9.49 9.67 9.72 10.18 10.92 8.82 (8.00) 9.64 9.58 9.57 9.75 9.80 10.21 10.94 9.92 (9.00) 9.66 9.67 9.65 9.85 9.90 10.24 10.95 11.02 (10.00) 9.68 9.75 9.73 9.97 10.02 10.25 10.96 12.13 (11.00) 9.69 9.84 9.83 10.10 10.16 10.26 10.96 13.23 (12.00) 9.67 9.90 9.91 10.21 10.28 10.27 10.96 14.33 (13.00) 9.64 9.97 9.99 10.30 10.37 10.23 10.96 15.43 (14.00) 9.60 10.03 10.05 10.36 10.44 10.19 10.92 15.99 (14.51) 9.58 10.06 10.08 10.39 10.46 10.17 10.90 16.53 (15.00) 9.56 10.09 10.11 10.41 10.48 10.15 10.88 18.74 (17.00) 9.48 10.18 10.19 10.46 10.53 10.07 10.79 22.05 (20.00) 9.35 10.25 10.25 10.50 10.57 9.94 10.66 23.01 (20.87) 9.28 10.24 10.25 10.51 10.57 9.89 10.62 27.56 (25.00) 8.95 10.22 10.23 10.53 10.61 9.66 10.45 32.19 (29.20) 8.40 9.91 9.92 10.23 10.29 9.11 9.99 33.07 (30.00) 8.30 9.86 9.86 10.17 10.23 9.01 9.90 38.58 (35.00) 7.65 9.46 9.46 9.70 9.70 8.36 9.26 44.09 (40.00) 7.02 9.01 9.01 9.17 9.18 7.73 8.63 49.60 (45.00) 6.38 8.50 8.50 8.64 8.65 7.09 7.99 54.78 (49.70) 3.98 -- --- -- -- --55.12 (50.00) -- 7.92 7.92 8.10 8.12 5.63 7.36 58.14 (52.75) -- -- -- -- 4.21 --60.63 (55.00) 5.74 5.75 6.50 6.73 -- 5.34 62.43 (56.64) -- -- -- -- 4.50 62.52 (56.72) -- 4.87 ...-- --62.53 (56.73) ..-- 4.87 -- --.63.50 (57.61) ..-- 5.17 5.40 --64.06 (58.11) -- 4.91 -- --64.49 (58.51) -- -. -- 4.94 -- --70.00 (63.50) 3.98 4.87 4.87 4.91 4.94 4.21 4.50 Revision 29 Cycle 18 COLR Page 29 of 59 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.)Bundle Type: GE14-P1ODNAB398-8G6.0/5G5.O/1 G2.0-10OT-145-T6-2614 (GE14C)Average Planar MAPLHGR Limit (kW/ft)Exposure Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT (GWd/ST) 5841 5852 5853 5854 5846 5855 0.00(0.00) 9.80 8.77 8.75 8.73 10.21 10.93 0.22 (0.20) 9.71 8.83 8.81 8.80 10.16 10.90 1.10(1.00) 9.50 8.94 8.94 8.94 10.01 10.80 2.20(2.00) 9.44 9.08 9.12 9.12 9.98 10.78 3.31 (3.00) 9.45 9.16 9.30 9.31 10.01 10.79 4.41 (4.00) 9.49 9.25 9.42 9.47 10.05 10.82 5.51 (5.00) 9.53 9:34 9.51 9.57 10.10 10.85 6.61 (6.00) 9.57 9.42 9.61 9.66 10.14 i0.88 7.72 (7.00) 9.61 9.51 9.70 9.76 10.18 10.91 8.82 (8.00) 9.64 9.59 9.79 9.85 10.21 10.93 9.92 (9.00) 9.66 9.68 9.89 9.95 10.24- 10.94 11.02 (10.00) 9.68 9.77 10.01 10.07 10.25 10.95 12.13 (11.00) 9.69 9.87 10.13 10.19 10.26 10.95 13.23 (12.00) 9.67 9.94 10.23 10.30 10.27 10.95 14.33 (13.00) 9.64 10.01 10.31 10.38 10.23 10.95 15.43 (14.00) 9.60 10.07 10.37 .10.45 10.19 10.91 15.99 (14.51) 9.58 10.10 10.39 10.47 10.17 10.89 16.53 (15.00) 9.56 10.12 10.42 10.49 10.15 10.87 18.74 (17.00) 9.48 10.20 10.47 10.54 10.07 10.78 22.05 (20.00) 9.35 10.26 10.51 10.58 9.94 10.65 23.01 (20.87) 9.28 10.26 10.52 10.58 9.89 10.61 27.56 (25.00) 8.95 10.24 10.54 10.62 9.66 10.44 32.19 (29.20) 8.40 9.93 10.24 10.30 9.11 9.98 33.07 (30.00) 8.30 9.87 10.18 10.24 9.01 9.89 38.58 (35.00) 7.65 9.47 9.71 9.71 8.36 9.25 44.09 (40.00) 7.02 9.02 9.18 9.19 7.73 8.61 49.60 (45.00) 6.38 8.51 8.66 8.67 7.09 7.98 54.78 (49.70) 3.98 --- -- -- --55.12 (50.00) -- 7.93 8.11 8.13 5.63 7.35 58.14 (52.75) -- -- -- 4.21 --60.63 (55.00) 5.77 6.53 6.77 -- 5.30 62.37 (56.58) .-- --. 4.49 62.58 (56.77) 4.88 -- --63.50 (57.61) -- 5.20 5.43 64.13 (58.17) 4.91 --64.56 (58.57) -- -- -- 4.94 -- --70.00 (63.50) 3.98 4.88 4.91 4.94 4.21 4.49 Revision 29 Cycle 18 COLR Page 30 of 59 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.)Bundle Type: GE14-P1ODNAB399-15GZ-1OOT-145-T6-2957 (GE14C)Average Planar MAPLHGR Limit (kW/ft)Exposure.

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 t10.05 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 (i0.00) 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 Revision 29 Cycle 18 COLR Page 31 of 59 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.)Bundle Type: GE 14-PI ODNAB398-5G6.0/10G5.0-100T-145-T6-2958 (GE14C)Average Planar MAPLHGR Limit (kW/ft)Exposure 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 16.21 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 18 COLR Page 32 of 59 Revision 29 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 GEl4 Fuel (cont.)Bundle Type: GE14-PIODNAB400-13GZ-1OOT-145-T6-2959 (GE14C)Average Planar MAPLHGR Limit (kW/ft)Exposure Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT (GWd/ST) 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 1.0.16 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 Revision 29 Cycle 18 COLR Page 33 of 59 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.)Bundle Type: GE14-P1ODNAB404-5G6.0/10G5.0-1OOT-145-T6-2960 (GE14C)Average Planar MAPLHGR Limit (kW/ft)Exposure Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT (GWd/ST) 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 Revision 29 Cycle 18 COLR Page 34 of 59 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.)Bundle Type: GE14-P1ODNAB400-12G6.0/3G5.0-10OT-145-T6-2961 (GE14C)Average Planar MAPLHGR Limit (kW/ft)Exposure Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT (GWd/ST) 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 1,0.94 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 Revision 29 Cycle 18 COLR Page 35 of 59 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 Bundle Type: GNF2-P10DG2B389-6G6.0/8G5.0-100T2-145-T6-3141 (GNF2)Average Planar MAPLHGR Limit (kW/ft)Exposure Lattice Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT (GWd/ST) 8661 8668 8669 8670 8671 8672 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 8.7 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 9.6 9.72 9.2 8.92 10.16 3.31 (3.00) 9.39 9.52 9.7 9.83 9.32 9.06 10.17 4.41 (4.00) 9.42 9.62 9.81 9.94 9.45 9.2 10.19 5.51 (5.00) 9.46 9.73 9.92 10.05 9.58 9.34 10.22 6.61 (6.00) 9.5 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 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) 9.6 10.24 10.48 10.39 10.29 10.1 10.32 12.13 (11.00) 9.54 10.31 10.58 10.42 10.19 10.16 10.33 1-3.23 (12.00) 9.45 10.31 10.61 10.23 10.09 10.16 10.24 14.33 (13.00) 9.36 10.31 10.6 10.17 10.07 10.14 10.14 15.43 (14.00) 9.26 10.3 10.49 10.09 10 10.07 10.04 16.53 (15.00) 9.16 10.28 10.38 10.02 9.93 10 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 10.2 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 9.5 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 9.4 9.32 9.36 9.22 25.35 (23.00) 8.35 9.7 9.53 9.31 9.23 9.27 9.11 26.46 (24.00) 8.24 9.6 9.43 9.22 9.14 9.18 9.01 27.56 (25.00) 8.14 9.5 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 8.4 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 18 COLR Page 36 of 59 Revision 29 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.)Bundle Type: GNF2-P10DG2B389-6G6.0/2G5.0/6G4.0-100T2-145-T6-3142 (GNF2)Average Planar MAPLHGR Limit (kW/ft)Exposure Lattice Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT (GWd/ST) 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 9.3 9.5 9.65 9.13 8.83 10.22 2.20 (2.00) 9.39 9.4 9.61 9.76 9.26 8.98 10.16 3.3.1 (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) 9.5 9.79 10.08 10.25 9.83 9.54 10.25 7.72 (7.00) 9.53 9.9 10.21 10.38 9.98 9.70 10.27 8.82 (8.00) 9.56 10.01 10.34 10.49. 10.1"4 9.86 10.29 9.92 (9.00) 9.58 10.13 10.47 10.5 10.29 10.02 10.31 11.02 (10.00) 9.6 10.25 10.6 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 9.6 9.65 9.53 22.05 (20.00) 8.65 10.01 9.84 9.59 9.5 9.55 9.42 23.15 (21.00) 8.55 9.92 9.74 9.5 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 9.6 9.44 9.22 9.14 9.18 9.01 27.56 (25.00)" 8.14 9.5 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 8.4 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 ........70.00 (63.50) 5.25 6.48 6.03 6.08 6.13 6.42 5.61 Revision 29 Cycle 18 COLR Page 37 of 59 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.)Bundle Type: GNF2-P10DG2B388-6G6.0/7G5.0-100T2-145-T6-3143 (GN F2)Average Planar MAPLHGR Limit (kW/ft)Exposure Lattice Lattice Lattice Lattice Lattice Lattice Lattice 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 9.2 9.44 9.6 9.47 9.13 10.17 4.41 (4.00) 9.42 9.36 9.62 9.78 9.6 9.27 10.19 5.51 (5.00) 9.46 9.52 9.8 9.94 9.74 9.42 10.22 6.61 (6.00) 9.5 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 10.2 10.29 10.17 9.88 10.29 9.92 (9.00) 9.58 '10 10.31 10.33 10.3 10.02 .10.31 11.02 (10.00) 9.6 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 10.2 10.33 13.23 (12.00) 9.45 10.1 10.47 10.4 10.48 10.2 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 10.4 .10.14 10.04 16.53 (15.00) 9.16 10.05 10.41 10.3 10.34 10.1 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 10.1 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. 9.7 9.32 24.25(22.00) 8.45 9.7 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 9.5 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 8.4 38.58 (35.00) 7.14 8.84 8.77 8.6 8.6 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 8.2 8.19 7.42 49.60 (45.00) 6.16 8.06 7.88 7.75 7.8 7.75 6.93 54.42 (49.37) 5.25 ...-- -- --55.12 (50.00) -- 7.66 7.46 7.34 7.4 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 -- -- --70.00 (63.50) 5.25 6.48 6.46 6.41 6.42 6.42 5.61 Cycle 18 COLR Page 38 of 59 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Figure 3.1-1 Most limiting MAPLHGR RTYPE: G4.02 ElIIZZL J7IrjjI j{P 100 H 0W09I1 10.0 III I 9.93 1,9.66 9.34-II 9J---GE14 --GNF2 H lI1", l i l l l i l m l l l i l I I 't I m l l i e I i i i llll-4 I II I I I I 9.5 --910$ IIIF .1I1 1,24 1 1. ............4 I i i i m i .........9.08 8.66 , 9.25 1 J 9.05-%II III 8.62-8.36 ,T 8.0 7.0 6.0 5.0--------------. ..8.21 -7 83 1111111 7. 441I T7.73 ` I III 7 05 7.05 F Note: h MAPLHGR limits used by 3D Monicore are lattice specific and are listed in Section 16.3 in the Supplemental Reload Licensing Report. Most Limiting MAPLHGR limit in any lattice is shown in this figure as a function of average planar exposure.

Natural Uranium lattices are excluded from this figure. Use tables for accurate calculations if necessary., 6-i 1-.13 6.03 6.03 i i i i i i I I I I I I 1 ! II .I ! I I l t l l1 1 1 ! I I I I I I 1 1 1 1 1 I 1 1 1 1 1 1 1 1 1 1 I I N I \ 1 1 II I 11111111 1111111 11111 111111 I :, III II 111111111 III I IL II IIIlil 4.0 1! i I I4.ll21llllLiL LL,!1il -IJ.-L.L1L iL.4 -i .0.0 5.0 10.0 15.0 20.0 25.0. 30.0 35.0 40.0 45.0 50.0 55.0 tT 60.0 Average Planar Exposure (GWd/ST)Cycle 18 COLR Page 39 of 59 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Figure 3.1-2 Flow Dependent MAPLHGR Factor (MAPFACF)RTYPE: G4.02 1.1 1.0 0.9 LA.0.0.8 0.7 0.6 0.5 30 40 50 60 70 80 90 100 110 Core Flow %Cycle 18 COLR Page 40 of 59 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.1-3 Power Dependent MAPLHGR Factors Note: These MAPFACp 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 -0.75 0.7 -0.65-0.6_______ -I 4 4- 4 1- + V 100, 1.0 94--------I -----90, 0.372.5, 0 1.873 P > Pbypass, For P, % power > Pbypass and 32.5% < Pbypass < 45%I I I 4 0.C.)4 U-0~4 Core Flow < 50%, P < Pbypass, where 32.5%:- Pbypass < 45%45, 0.557 325,,0.537 25,0.451 4 I' .o I* .. --- Core I F T 1 0.55 -0.5 0.45 0.4 Flow > 50%, P < Pbypass, where%:5 Pbypass < 45%32.5, 0.439 132.5c I I I I 1 1L V 4 -.---------

+/--------------

4 i. -~A ~ I-K'-I I25, 0.38L JJ, 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100% Power Cycle 18 COLR Page 41 of 59 Revision 29 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. In addition, due to a restriction placed in GNF2 generic fuel licensing (Reference 5.23), the Peak Pellet exposure for GNF2 is limited to 45 GWD/MT.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 18 COLR Revision 29. Page 42 of 59 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 12 11'0 E C,=-J 9 8 7 6 5 4 0 10 20 30 40 50 60 Exposure, GWD/ST 70 Cycle 18 COLR Page 43 of 59 Revision 29 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< 0.8 U-0J .I 0.6 0.5 30 40 50 60 70 80 90 100 110 Core Flow %Revision 29 Cycle 18 COLR Page 44 of 59 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 0.75 100, 1.0 I _____ +/- _____ 4 4 +/- _______ _4 ___ '___790, ý94 I I -" 1 r325. P > Pbypass,* .[ For P, % power > Pbypass and 32.5% 5 Pbypass < 45%0.C., LL CD z-J 0.7 -0.65 0.6 0.55 0.5 0.451 Core Flow < 50%, P < Pbypass, where 32.5% 5 Pbypass <45%.Il-, , * , 32.5, 0.49 25, 0.45 -__-45, 0.557 i I 10 45, 0.537 I -~ I- I I- -I I- 4--32.5, 0.439 Core Flow > 50%, P < Pbypass, where 32.5% < Pbypass < 45% .A1A1* + r- 1 F 0.35---.- -A .-4 4. .4 *25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100% Powe r Revision 29 Cycle 18 COLR Page 45 of 59 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 PBypa s, MCPRp is the product of the rated power and flow MCPR operating limit presented in Yable 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 '".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 oft 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 t.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 18 COLR Revision 29 Page 46 of 59 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Table 3.3-1 RTYPE: G4.02 MCPR Oroeratina Limits At Rated Power and Rated Flow The MCPR Operating Limit for Two Loop Operation (OLMCPRTLO) is a function of fuel type, exposure, and c, which is derived from scram timing measurements.

GNF2 GE14 t BOCto MOC MOCto EOC BOC to MOC MOC to EOC 0.0 1.49 1.54 1.46 1.51 0.0 0.1 1.50 1.55 1.48 1.53 0.1 0.2 1.51 1.56 1.49 1.55 0.2 0.3 1.52 1.57 1.50 1.57 0.3 0.4 1.53 1.58 1.51 1.58 0.4 0.5 1.54 1.59 1.52 1.60 0.5 0.6 1.55 1.60 1.53 1.62 0.6 0.7 1.56 1.61 1.54 1.63 0.7 0.8 1.57 1.62 1.55 1T.65 0.8 0.9 1.58 1.63 1.56 1.67 0.9 1.0 1.59 1.64 1.57 1.68 MOC = Middle of Cycle = End BOC = Beginning Of Cycle Of Rated Power Operation At Rated Flow (EOR) -1.323 GWd/ST EOC = End Of Cycle Note: The rated OLMCPR Limits qiven 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).Sinqle Loop Operation OLMCPR SLO = 0.03 + OLMCPR TLO , where OLMCPR TLO is selected from the Table above.Cycle 18 COLR Revision 29 Page 47 of 59 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.3-1 Flow Dependent MCPR Limits (MCPR F)1.7 1.6 I if tL.W (-0.0 (.)1.5 1.4 1.3 I 11 I.1.2 1.1 30 35 40 45 50 55 60 65 70 75 80 85 90 95- 100 105 110 115 Core Flow, % Of Rated Revision 29 Cycle 18 COLR Page 48 of 59 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 3.00 2.50 a.-.)--I 0 2.00 1.50 1.00 25 35 45 55 65 Power (%)75 85 95 Revision 29 Cycle 18 COLR Page 49 of 59 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 4.00 3.50 3.00 0 Q.5 C.)-J 2.00 1.50 1.00 25 35 45 55 65 Power(%)75 85 95 Revision 29 Cycle 18 COLR Page 50 of 59 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.4 Power/Flow Relationship Durinc Power Operation Reference Technical Specification:

3.11.D The Cycle 18 stability analysis credited the flow clamp feature of the FCTR cards from BOC to 2,000 MWD/ST to ensure the dominance of Core Wide Oscillations.

APRM Flux scram and Rod Block curves including the flow clamp have been developed for Cycle 18. Additionally, the Cycle 18 ATWS analysis requires a change to the power/flow map from BOC to 5,000 MWD/ST to ensure that the ATWS peak pressure remains below the 1500 psig acceptance criteria.

The curves may be changed consistent with the exposure ranges provided on Figures 3.4-1 through 3.4-5: however, curves that apply to earlier cycle exposure ranges are conservative for the remainder of the cycle and may remain in place if desired.The power/flow relationship shall not exceed the limiting values shown on the Power/Flow Operating Maps in Figures 3.4-1 through 3.4-3 when in Two Loop Operation for the given exposure ranges. The power/flow relationship shall not exceed the limiting values shown on the Power/Flow Operating Maps in Figures 3.4-4 and 3.4-5 when in Single Loop Operation.

Cycle 18 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.For the Cycle 18 Stability analysis, the exclusion and the buffer regions shown in Figures 3.4-1 through 3.4-5 are based on Stability Solution I-D (references 5.4, 5.12, 5.15 and 5.20)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 18 COLR Page 51 of 59 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIGURE 3.4-1: PILGRIM POWER / FLOW MAP (Applicable to 0 to 2000 MWD/ST Exposure Range)Scram and Rod Block Data based on AVs -TLO; With Flow Clamp; ATWS/MELLLA Boundary CORE FLOW, MLB/HR 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 a U.0~IL w 0 U.125 120 115 110 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5 0----------------------------------, ý -1 ý f9j-" ,-!--.fla fl nnI SI II~4~FU r-,-AT 11506 00iýTION 4.~i Yrm77~T~7~T71~I~I~I-IT7iI I ~ I '*IT~1Inoruon-=n

~..u ~w I I I r~v"un v :i...Z ~~~~i .........

.................. OPER......

......ARH B tED .....- 4. ..... .....................

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

......--,.....t. -......., ..... ..t. ----- -......... ..... ... ..._ ... .. ... ..MINIMUM~~~~~

.. PU P.PED(6%..............

..,.... .......i 2535 2434 2332 2231 2129 2028 1927 1825 1724 1622 1521 1420 1318 1217 1115 1014 913 811 710 608 507 406 304 203 101 0 i-:-0 0t.-J uJ IL I-iuJ 0.,, 0 5 10 15 20 25 30 35 40 45 CORE FLOW, MLB/HR 50 55 60 65 70 75 80 Cycle 18 COLR Page 52 of 59 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 0 0 a.-J W I-U O 0 U.125 120 115 110 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5 0 FIGURE 3.4-2: PILGRIM POWER / FLOW MAP (Applicable to 2000 to 5000 MWDIST Exposure Range)Scram and Rod Block Data based on AVs-TLO; No Flow Clamp; ATWSIMELLLA Boundary CORE FLOW, MLB/HR 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80........ .... -AT 0--/-

-2535.. .... .....ý APRM SCRAM CLAMP AT4340-2332 APRM R0D BLOCK CLAMP AT 11t5% 23 fH 2231~OPERSTION.PROHIBITED 2129 2028 1825 17241622 C142 CORE FLOW 20 REGION 1318 LOWER BOUND _ z 811 NOPERATION 710 PROHIBITED 608 NAT MINIMUM POWER INTERLOCK 30 LINE MIN PUMP SPEED (2%)203 101 0 I-.0-J I-LU 0 0 0 5 10 15 20 25 30 35 40 45 CORE FLOW, MLB/HR 50 55 60 65 70 75 80 Cycle 18 COLR Page 53 of 59 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIGURE 3.4-3: PILGRIM POWER / FLOW MAP (Applicable to 5000 MWD/ST to EOC Exposure Range)Scram and Rod Block Data based on Allowable Values -TLO; No Flow Clamp CORE FLOW, MLB/HR 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 a w 0 IL 0 0...J"I-I--UJ 125 120 115 110 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10'5...... 0A ... APRM SCRAM CLAMP AT 120%_27=- -2AFRM ROD BLOCK CLAMP ATAT5115-------- OPERAION-PROHIBITE

...... .r ' ._ __.:VL22&v.;.t.2S...VV LiI~>L9 ~=1,~010ýCOI CRE FLOW_:7 ... ...REGION OPERATION

......PROHIBITED LOWER BOUND....----

NAT CIRC LINE OPERATION OE NELC NA CT- E 2 % -.--.-= =! t = ---, , ... -= --___, 2535 2434 2332 2231 2129 2028 1927 1825 1724 1622 1521 1420 1318 1217 1115 1014 913 811 710 608 507 406 304 203 101 0 I-0 0.IL LU I-0 0, 0 5 10 15 20 25 30 35 40 45 CORE FLOW, MLB/HR 50 55 60 65 70 75 80 Revision 29 Cycle 18 COLR Page 54 of 59 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE." G4.02 FIGURE 3.4-4: PILGRIM POWER / FLOW MAP (Applicable to 0 to 2000 MWD/ST Exposure Range)Scram and Rod Block Data based on Allowable Values -SLO; With Flow Clamp CORE FLOW, MLB/HR 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 a UJI 3-1 0 a.-.1 W-0 U 125 120 115 110 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5 0.........

.... ... .........~ ~ ~ ~ ~ ._ ...=17 4 =l 14 -lAPRM SCRAM CLAMP AT 120%ROD BLOCK CLAMP AT 115%BOUNDARY OPERATION+-----

.........PROHIBITED

--:'- .PROHIBITED

ýJ T: .ýLOW ER ..... ---2--'...... ..... MI I U POW ER. INTE LOC ..... .....N A ....... ...... ....LINE 17 "L e t I PUMP SPEED 7.: .--.......-.

2535 2434 2332 2231 2129 2028 1927 1825 1724 1622 1521 1420 1318 1217 1115 1014.913 811 710 608 507 406 304 203 101 0 O-LU 0 C--J LU W-L)0 C.)0 5 10 15 .20 25 30 35 40 45 CORE FLOW, MLB/HR 50 55 60 65 70 75 80 Cycle 18 COLR Page 55 of 59 Revision 29 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIGURE 3.4-5: PILGRIM POWER I FLOW MAP (Applicable to 2000 MWD/STto EOC Exposure Range)Scram and Rod Block Data based on Allowable Values -SLO; No Flow Clamp CORE FLOW, MLBIHR 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 125 120 115 110 105 100 95 85 80-75 41....... ..- -..... .-------*

.:..::t " ..-.

ANALYSIS -----1 0 -

i!:l:i~it~ii::Affl-.M SCRAMh.. CLM A....AM!i w 0~I-0 Q 70 65 60 55 50 45 40 35 30 25 20 15 10 5 0 2535 2434 2332 2231 2129 2028 1927 1825 1724 1622 1521 1420 1318 1217 1115 1014 913 811 710 608 507 406 304 203 101 0 LU 0 a-I-0 U.... ....................

...... ....Z-]OPERATION

[==F4-PROHIBITES

-.--. -.. ...4 ,=-1 -.-LOWER BOUND .... .NAT AULh ISLO (est) MIN PUMP SPEED (26%)[-4 MINIMUM POWER.1 .I ...--t..... ... ... .. ....T.-0 5 10 15 20 25 30 35 40 45 CORE FLOW, MLB/HR 50 55 60 65 70 75 80 Cycle 18 COLR Page 56 of 59 I Revision 29 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 for each type of fuel is shown for the present cycle in Figure 4.0-1.Fuel Type LoadedNumber Irradiated:

GE14-P1ODNAB397-10G6.0/3G5.0-10OT-145-T6-2613 (GE14C) 15 17 GE 14-Pi ODNAB398-8G6.0/5G5.0/1 G2.0-10OT-145-T6-2614 (GEl 4C) 15 24 GE14-PiODNAB397-14GZ-10OT-145-T6-2621 (GE14C) 15 63'GE 14-P1ODNAB399-10G6.0/3G5.0/lG2.0-1GOT-145-T6-2828 (GE14C) '16 104 GEl 4-P1ODNAB398-8G6.0/5G5.0/2G4.0-10OT-145-T6-2829 (GEl4C 16 56 GE14-P1ODNAB404-5G6.0/10G5.0-10OT-145-T6-2960 (GE14C) 17 40 GE14-P1ODNAB398-5G6.0/10G5.0-10OT-145-T6-2958 (GE14C) 17 32 GEl 4-P1ODNAB400-13GZ-10OT-145-T6-2959 (GEl 4C) 17 24 GE 14-P10DNAB399-15GZ-10OT-145-T6-2957 (GEi4C) 17 32 GE14-P10DNAB400-12G6.0/3G5.0-10OT-145-T6-2961 (GE14C) 17 32 New: GNF2-P10DG2B389-6G6.0/2G5.0/6G4.0-10OT2-145-T6-3142 (GNF2) 18 104 GNF2-P 10DG2B389-6G6.0/8G5.0-10OT2-145-T6-3141 (GNF2) 18 16 GNF2-P10DG2B388-6G6.0/7G5.0-100T2-145-T6-3143 (GNF2) 18 36 Total: 580 The reactor vessel core contains 145 cruciform-shaped control rods. The control materials used are either boron carbide powder/ (B 4 C) compacted to approximately 70%of the theoretical density or a combination of boron carbide powder and solid hafnium.Cycle 18 COLR Revision 29 Page 57 of 59 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIGURE 4.0-1 Reactor Vessel Core Loading Pattern 52EDEEMII o m m 50 0 OWa.lT--ri Ffl"lf--I-i -al--I l~zi". Wo, Wm 46 0I[- 0 l- UMl ElVIMMMEMME., E C4 D L I 44 EDl'E 3 lI E DlDE I-F1 D'l El- l l EIE-Q lI 30 JOi A+ E+M M~ MI H [+ K 28 Kfa FM A ] A 0M +M CE+ M 0f: a MEE 0 A]E ]E 22 + I WI 1WriIr.i-18 JOB HlMME D[1E EE ED 10ID lE E El HDE Ez 14 K" aK +1-F I -E+-0 W WWII MWM'1 l-OW 2+E IM FW [WlE] AIMM+ MIA 12 Kl ED [K K HI F K] ED 2 ED ED El M'B l E3l " M D M E r -El F]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~Fuel Type A = GEl 4-P 1EDNAB404-2G6.0/1 0G.0-0l OOT-l 45-T6-2960 B = GE 14-Fl 0DNAB398-5G6.0/l10G5.O-100OT-l145-T6-2958 C = GEl 4-P 1DNAB397-1 0G6.0/3G5.0-WOMT-1 45-T6-261 3 D = GEl 4-Fl E DNAB399-l 0G6.E/3G5./Dl G2.0- 100T-l 45-T6-2828 E = GNF2-P1 0DG2B388-6G6.0/7G5.0-1 00T2-l145-T6-31 43 K = GE 14-l ODNAB398-8 GZ- G5GT-l T6-26 4 I L = GE 14-Fl10DNAB400-l G.13GZ-100-1 Tl45-T6-2969 M = GN F2-PE 0DG2B389-6G6.0[2G5.0T6G4.0-E00T2-1 45-T6-31 42 Cycle 18 COLR 1ision 29 Page 58 of 59 Re\

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

5.0 REFERENCES

5.1. NEDE-24011-P-A-16 and NEDE-24011-P-A-16-US, "General Electric Standard Application for Reactor Fuel", October 2007.5.2. EC9221, Cycle 18 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. 5, "Pilgrim Power To Flow Map Report." 5.15. C18SRLR, 0000-0083-7478SRLR, "Supplemental Reload Licensing Report, Reload 17, Cycle 18." February 2009.5.16. EC7953 documents Cycle 18 OPL-3, Transient Analysis Inputs.5.17. C18FBIR, 0000-0083-7478FBIR, Rev.0, Fuel Bundle Information Report, Cycle 18, February 2009.5.18. 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 1, August 2008 (This reference is also known as Amendment 22 report for GNF2).Cycle 18 COLR Revision 29 Page 59 of 59