ML071360197

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Core Operating Limits Report, Revision 26 (Cycle 17)
ML071360197
Person / Time
Site: Pilgrim
Issue date: 05/09/2007
From: Bryan Ford
Entergy Nuclear Operations
To:
Document Control Desk, NRC/NRR/ADRO
References
2.07.048
Download: ML071360197 (46)
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{{#Wiki_filter:`r-1-Entergy Nuclear Operations, Inc.Pilgrim Station 600 Rocky Hill Road Plymouth, MA 02360 May 9, 2007 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 26 (Cycle 17)LETTER NUMBER: 2.07.048

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

26 provides cycle-specific limits for operating Pilgrim during Cycle 17.This letter contains no new commitments. Should you require further information concerning COLR, Revision 26, please contact me at (508) 830-8403.Sincerely, Bryan S. Ford Licensing Manager MJG/dI

Enclosure:

PNPS Core Operating Limits Report, cc: Regional Administrator, Region 1 U.S. Nuclear Regulator Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Revision 26 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 207048 740,' PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 (CYCLE 17)APPROVED: APPROVED: APPROVED: Gar James,,e ctor Engineering Superintendent lDate Gayaes eco Egnern uernedetDt Bric Sullivan, Nuclear EngineeU Director Onsite Safety Review mittee OSRC Meeting#:

  • 0 -c3d)Date 4/A/APPROVED: APPROVED: APPROVED: D. Noyes, Operations WAdnager.5v 1'a7-/,Date Robert G. SmithG al Manager Plant Operations Date K. Bronsofi, Site Vice President Date REVISION 26 COLR PAGE 1 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 TABLE OF CONTENTS Page TITLE/SIGNATURE PAGE ......................................................................

1 TABLE OF CONTENTS ........................................................................... 2 RECORD OF REVISIONS ...................................................................... 3 LIST OF TABLES .................................................................................... 4 LIST OF FIGURES .................................................................................. 4

1.0 INTRODUCTION

........................................................................... 5 2.0 INSTRUMENTATION TRIP SETTINGS ........................................ 6 2.1 APRM Flux Scram Trip Setting (Run Mode) ...................... 6 2.2 APRM Rod Block Trip Setting (Run Mode) ........................ 11 2.3 Rod Block Monitor Trip Setting ........................................... 11 3.0 CORE OPERATING LIMITS ......................................................... 16 3.1 Average Planar Linear Heat Generation Rate (APLHGR) ................................................................. 16 3.2 Linear Heat Generation Rate (LHGR) .................................. 31 3.3 Minimum Critical Power Ratio (MCPR) ............................... 35 3.4 Power/Flow Relationship ................................................... 40 4.0 REACTOR VESSEL CORE DESIGN ............................................. 43

5.0 REFERENCES

............................................................................. 45 REVISION 26 COLR PAGE 2 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 RECORD OF REVISIONS Revision Effective Date 8A Effective date based on issuance of license amendment by NRC 9A Effective date based on issuance of license amendment by NRC for ARTS and SAFER/GESTR 1 OA Effective date based on initial startup of Cycle 10 11A Effective date based on initial startup of Cycle 11 11 B Effective upon final approval 11C 11D 12A 12B 12C 12D 13A 14A 15A 15B 16A 16B 25 26 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 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 solution 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 GEl 4 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 REVISION 26 COLR PAGE 3 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 LIST OF TABLES Number Title Paae 2.1-1 Formulae for APRM Flux Scram Trip Settings in Figure 2.1-1 7 2.1-2 Formulae for APRM Flux Scram Trip Settings in Figure 2.1-2 8 2.2-1 Formulae for APRM Rod Block Trip Settings in Figure 2.2-1 12 2.2-2 Formulae for APRM Rod Block Trip Settings in Figure 2.2-2 13 3.1-1 MAPLHGR Limits For GE14 Fuel 17 At Rated Power and Rated Flow 3.3-1 MCPR Operating Limits- GE14 Fuel At Rated Power and Rated 36 Flow LIST OF FIGURES Number Title Paae 2.1-1 Allowable APRM Flux Scram Trip Settings, Two Loop Operation 9 (Normal Feed water Temperature) 2.1-2 Allowable APRM Flux Scram Trip Settings, Single Loop 10 Operation (Normal Feed water Temperature) 2.2-1 Allowable APRM Rod Block Trip Settings, Two Loop Operation 14 (Normal Feed water Temperature) 2.2-2 Allowable APRM Rod Block Trip Settings, , Single Loop 15 Operation (Normal Feed water Temperature) 3.1-1 Most Limiting Maximum Average Planar Linear Heat Generation 28 Rate (MAPLHGR) for GE14 Fuel (Normal Feedwater Temperature) 3.1-2 Flow-Dependent MAPLHGR Factor (MAPFACF) for GEl4 Fuel 29 3.1-3 Power-Dependent MAPHLGR Factor (MAPFACp) for GE14 30 Fuel 3.2-1 Maximum Linear Heat Generation 32 Rate (MLHGR) for GEl 4 Fuel 3.2-2 Flow-Dependent LHGR Factor (LHGRFACF) for GE14 Fuel 33 3.2-3 Power-Dependent LHGR Factor (LHGRFACp) for GE14 Fuel 34 3.3-1 Flow-Dependent MCPR Limits (MCPRF) for GE14 Fuel 37 3.3-2 Power-Dependent MCPR Limits (MCPRp) for GE14 Fuel, 38 Turbine Bypass Assumed Operable 3.3-3 Power-Dependent MCPR Limits (MCPRp) for GE14 Fuel, 39 Turbine Bypass Out Of Service 3.4-1 Power/Flow Operating Map, Two Loop Operation, Normal 41 Feedwater Temperature 3.4-2 Power/Flow Operating Map, Single Loop Operation 42 3.4-3 Power/Flow Operating Map, Two Loop Operation, Reduced Feedwater Temperature 4.0-1 Reactor Vessel Core Loading Pattern 44 REVISION 26 COLR PAGE 4 OF 45 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 17. In this report, Cycle 17 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)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 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.REVISION 26 COLR PAGE 5 OF 45 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 point (ATSP) for TLO is shown on Figure 2.1-1 and is clamped at 120% of rated core thermal power. Formulae used to develop Figure 2.1-1 are listed in Table 2.1-1.ATSP for SLO is shown on Figure 2.1-2 and is clamped 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.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 26 COLR PAGE 6 OF 45 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 D C D % Rated SLOPE INTERCEPT 0.20 71.5 0 < WD __ 22.5 0.71 60.0 22.5 < 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 1.a lists the values of constants listed in this Table.REVISION 26 COLR PAGE 7 OF 45 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 < 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: 4. ATSP=C*%WD+D, ATSP isin% Power 5. Figure 2.1-2 shows the plot of ATSP vs. WD.6. Reference 5.6, Table 1 .b lists the values of constants listed in this Table.REVISION 26 COLR PAGE 8 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.1-1 Allowable APRM Flux Scram Trip Settings-TLO (Normal Feed water Temperature) 130.0 120.0 110.0 a. 100.0 E 2 90.0 CL 80.0 70.0 60.0 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 WD, Drive Flow, %REVISION 26 COLR PAGE 9 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.1-2 Allowable APRM Flux Scram Trip Settings-SLO (Normal Feed water Temperature) 125.0 120.0 115.0 110.0 105.0 0 I, 100.0 2 95.0 U) 90.0 8.< 85.0 80.0-75.0-70.0 -m 65.0-0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 WD, Drive Flow, %REVISION 26 COLR PAGE 10 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 2.2 APRM Rod Block Trig Setting (Run Mode)Reference Technical Specifications: Table 3.2.C-2, 3.1..B.1 When the mode switch is in the RUN position, the average power range monitor (APRM) rod block Allowable Trip setting (ATSPRB) as a function of drive flow for Two Loop Operation shall be as given by Figure 2.2-1. 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.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. ATSPRB is clamped at 115% of rated core thermal power. Formulae that form the basis of the Figure 2.2-2 are listed in Table 2.2-2.2.3 Rod Block Monitor Trip Setting

References:

Technical Specification Table 3.2.C-2, Ref. 5.15, Ref. 5.1 Table 4.5 (b)Allowable values for the power-dependent Rod Block Monitor trip set points shall be: Reactor Power, P (% of Rated)P _ 25.9 25.9 < P < 62.0 62.0 < P < 82.0 82.0 < P Trip Set point (% of Reference Level)Not applicable (All RBM Trips Bypassed)120 115 110 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).REVISION 26REVISION 26 COLR PAGE 11 OF 45 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)o 0 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. 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 lists the values of constants listed in this Table.REVISION 26 COLR PAGE 12 OF 45 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 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 6 5.9 < WD !5 89.1 0 115.0 89.1 <WD _125 Notes: 4. ATSP=C*%WD+D , ATSP is in % Power 5. Figure 2.1-1 shows the plot of ATSP vs. WD.6. Reference 5.6, Table 1.b lists the values of constants listed in this Table.REVISION 26 COLR PAGE 13 OF 45 .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 Feed water Temperature) 120.0 110.0 100.0 0.0 90.0 0 a. 80.0 70.0 60.0 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 WD, Drive Flow, %REVISION 26 COLR PAGE 14 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Figure 2.2-2 Allowable APRM Flux Rod Block Trip Settings-SLO (Normal Feed water Temperature) RTYPE: G4.02.2 M 0 120.0 115.0 110.0 105.0 100.0 95.0 90.0 85.0 80.0 75.0 70.0 65.0 60.0 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 WD, Drive Flow, %80.0 90.0 100.0 110.0 120.0 REVISION 26 COLR PAGE 15 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.0 CORE OPERATING LIMITS 3.1 Maximum Averaae Planar Linear Heat Generation Rate (MAPLHGR)Reference Technical Specification: 3.1 1.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. 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 MAPLHGR for rated power and flow conditions for the most limiting lattice in each fuel type (excluding natural uranium lattices) are presented in Figures 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 Table 3.1-1, 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 Figures 3.1-1 and 3.1-2.When in Single Loop Operation, an SLO Multiplier of 0.8 applies to the Rated MAPLHGR limit. At off rated conditions, MAPLHGR limit is the lower of 0.8 times the rated MAPLHGR limit, the MAPLHGRp or MAPLHGRF.REVISION 26 COLR PAGE 16 OF 45 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-P1ODNAB399-10G6.0/3G5.0/1G2.0-100T-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 9.31 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 ....REVISION 26 COLRI PAGE 17 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 Continued: Bundle Type: GE14-P1ODNAB398-8G6.0/5G5.0/2G4.0-100T-145-T6-2829 (GE14C)Average Planar MAPLHGR Limit (kW/ft)Rvfnaurp GWd/MT (GWd/ST) Lattice Lattice Lattice Lattice Lattice Lattice 6Ud9- 699n "451 "47 6g8S 69S4A 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 -- --REVISION 26 COLRI PAGE 18 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Table 3.1-1 Continued: Bundle Type: GE14-P1ODNAB412-16GZ-100T-145-T6-3901 RTYPE: G4.02 Average Planar Exposure MAPLHGR Limit (kW/ft)GWd/MT (GWd/ST) Lat. Lat. Lat. Lat. Lat. Lat. Lat.4820 4827 4828 4829 4830 4825 4831 0.00 (0.00) 9.80 8.78 8.57 8.72 8.62 10.21 10.98 0.22 (0.20) 9.71 8.81 8.61 8.76 8.70 10.16 10.95 1.10(1.00) 9.50 8.87 8.68 8.85 8.79 10.01 10.86 2.20 (2.00) 9.44 8.97 8.80 8.98 8.93 9.98 10.84 3.31 (3.00) 9.45 9.08 8.92 9.12 9.07 10.01 10.86 4.41 (4.00) 9.49 9.20 9.05 9.24 9.19 10.05 10.88 5.51 (5.00) 9.53 9.32 9.17 9.36 9.31 10.10 10.91 6.61 (6.00) 9.57 9.42 9.28 9.48 9.44 10.14 10.94 7.72 (7.00) 9.61 9.52 9.39 9.60 9.58 10.18 10.96 8.82 (8.00) 9.64 9.62 9.51 9.73 9.72 10.21 10.98 9.92 (9.00) 9.66 9.72 9.62 9.87 9.87 10.24 10.99 11.02 (10.00) 9.68 9.82 9.74 10.01 10.02 10.25 11.00 12.13 (11.00) 9.69 9.92 9.86 10.16 10.18 10.26 11.00 13.23 (12.00) 9.67 9.99 9.93 10.25 10.28 10.27 11.00 14.33 (13.00) 9.64 10.04 10.00 10.32 10.34 10.23 11.00 15.43 (14.00) 9.60 10.08 10.05 10.35 10.37 10.19 10.96 15.99 (14.51) 9.58 10.09 10.07 10.36 10.38 10.17 10.94 16.53 (15.00) 9.56 10.10 10.08 10.37 10.38 10.15 10.92 18.74 (17.00) 9.48 10.11 10.11 10.37 10.38 10.07 10.83 22.05 (20.00) 9.35 10.11 10.12 10.36 10.37 9.94 10.70 23.01 (20.87) 9.28 10.09 10.10 10.35 10.35 9.89 10.66 27.56 (25.00) 8.95 10.01 10.00 10.28 10.25 9.66 10.49 32.19 (29.20) 8.40 9.65 9.65 9.92 9.94 9.11 10.04 33.07 (30.00) 8.30 9.58 9.58 9.85 9.87 9.01 9.95 38.58 (35.00) 7.65 9.15 9.15 9.42 9.40 8.36 9.31 44.09 (40.00) 7.02 8.70 8.70, 8.97 8.92 7.73 8.68 49.60 (45.00) 6.38 8.22 8.21 8.49 8.46 7.09 8.05 54.78 (49.70) 3.98 -- -- -- -- --55.12 (50.00) -- 7.68 7.63 7.95 7.98 5.63 7.42 58.14 (52.75) -- -- -- -- 4.21 --60.63 (55.00) 5.21 5.16 5.89 5.96 -- 5.46 61.32 (55.63) -- 4.84 -- -- --61.44 (55.74) 4.84 ...-- --62.67 (56.86) .-- -- 4.51 62.81 (56.98) ...... 4.90 .-- --62.91 (57.07) -- ...-- 4.92 ....REVISION 26 COLR PAGE 19 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 Continued: Bundle Type: GE14-P1ODNAB397-IOG6.0/3G5.0-I00T-145-T6-2613 Average Planar MAPLHGR Limit (kW/ft)GWd/MT (GWd/ST) Lattice Lattice Lattice Lattice Lattice Lattice 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) -- 4.94 ---REVISION 26 COLR PAGE 20 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 able 3.1-1 Continued: Bundle Type: GE14-P1ODNAB397-14GZ-t00T-145-T6-2621 Average Planar Exposure MAPLHGR Limit (kW/ft)GWd/MT (GWd/ST) Lat. Lat. Lat. Lat. Lat. Lat. Lat.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 ....REVISION 26 COLR PAGE 21 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 Continued: Bundle Type: GE14-P1ODNAB398-8G6.0/5G5.0/1G2.0-1OOT-145-T6-2614 Average Planar Exposure MAPLHGR Limit (kW/ft)GWd/MT (GWd/ST) Lattice Lattice Lattice Lattice Lattice Lattice 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 10.88 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 ....REVISION 26 COLRI PAGE 22 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Table 3.1.-i Continued Bundle Type: GE14-PIODNAB399-I5GZ-I00T-145-T6-2957 (GE14C)RTYPE: G4.02 Average Planar MAPLHGR Limit (kW/ft)FviXnfUrA___ Lattice Lattice Lattice Lattice Lattice Lattice GWdIMT (GWdIST) 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 --REVISION 26 COLRI PAGE 23 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 Continued: Bundle Type: GE14-P1ODNAB398-5G6.0/lOG5.0-1OOT-145-T6-2958 (GEl4C)Average Planar MAPLHGR Limit (kW/ft)Exposure Lattice Lattice Lattice Lattice Lattice Lattice GWdIMT (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 ......REVISION 26 COLRI PAGE 24 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 Continued: Bundle Type: GE14-P1ODNAB400-13GZ-lOOT-145-T6-2959 (GE14C)Average Planar MAPLHGR Limit (kW/ft)Iirp GWd/MT (GWd/ST) Lattice Lattice Lattice Lattice Lattice Lattice 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 -- -- --REVISION 26 COLRI PAGE 25 OF 45 1 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 Continued: Bundle Type: GE14-PIODNAB404-5G6.0/1OG5.0-1OOT-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 9.15 923 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 ......REVISION 26 COLRI PAGE 26 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE Table Continued: Bundle Tvwe: GE14-P10DNAR400-12G6 0/3G5. 0-100T-I45-T6-2961 (GEI4C): G4.02 Average Planar MAPLHGR Limit (kW/ft)Lattice Lattice Lattice Lattice Lattice Lattice GWdIMT (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 ..---.REVISION 26 COLR I PAGE 27 OF 451 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.1-1 Most limiting MAPLHGR For GE14 Fuel...............4-II 11i I I I III 101_I 19:E I I I I I I I -I W -r -]I 11 II FWFTFFT~fAZ~r7]~.JFVFT4141F"I.I I .I I I .! I j ! i i i i i i i i -1 H I! 1 1 1 1 1 1 1 1 1 1 1 1 1 1 I I X 8 7 6 5 4 MAPLHGR limits used by 3D Monicore are lattice specific and -63 are listed in Section 16.3 in the Supplemental reload Licensing --IT 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. 4.21..--II-t i 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 GWD/ST 40.0 45.0 50.0 55.0 REVISION 26 COLR PAGE 28 OF 451 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.1-2 Flow Dependent MAPLHGR Factor (MAPFACF)1.100 1.000 0.900 U.C 0.800 CJ 0.0.700 0.600 0.500 4--30.00 40.00 50.00 60.00 70.00 80.00 90.00 Core Flow %100.00 REVISION 26 COLR PAGE 29 OF 451 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Figure 3.1-3 Power Dependent MAPLHGR Factors for GE14 Fuel Note: These MAPFACp factors are valid for Turbine bypass In or out of service and for Normal Feedwater heating RTYPE: G4.02 1 0.95 0.9 0.85 0.8 0.75 4 .4 4 -I -I MAPFACp for P > Pbypass, For P, % power > Pbypass and 32.5% < Pbypass < 45%MAPFACp=0.00191(P-90) + 0.94, When 32.5 % < P <-90%MAPFACp = 0.006(P-100) t 1.0, when 90 % < P < 100 %0.C, 0.7____ I 0.65 MAPFACp = 0.557+for Core Flow <32.5% < Pbypass <0.00535(P-45) 50%, P < Pbypass, where 45%0.6-0.55 0.5 0.45 0.4 0.35 I I F F I I II I-' i JMAPFACp =0.5371+ 0.00785(P-45) 0 fr Core Flow >..50%, P <~ Pbypass, 32.5% < Pbypass <~ 45%0000 40 _ _ _ _ _ _ _ _25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100% Power REVISION 26 COLR PAGE 30 OF 45 1 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 During reactor power operation, the LHGR of any rod in any fuel assembly at any axial location shall not exceed the rated power and rated core flow limits represented by Figure 3.2-1, with the detailed values presented 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 LHGRo. 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. Gd containing fuel rods have different LHGR limits that are also exposure dependent. Reference 5.17 documents the detailed proprietary curves and values.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.REVISION 26 COLR PAGE 31 OF 45 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 I10 9.e 8.im W 7 6 5 4 0 10 20 30 40 50 60.70 Exposure, GWD/ST REVISION 26 COLRI PAGE 32 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.2-2 Flow Dependent LHGR Factor (LHGRFACF) 1.100 1.000 0.900 0.800 x 0.700 0.600 0.500 4-30.00 40.00 50.00 60.00 70.00 80.00 90.00 Core Flow %100.00 REVISION 26 COLR PAGE 33 OF 45 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 CL 4 0.7 0.65 0.6 0.55 0.5 0.45 0.4 0.35{LHGRFACp for P > Pbypass, For P. % power > Pbypass and 32.5% < Pbypass < 45%LHGRFACp=0.00191(P-90) + 0.94, When 32.5 % < P < 90%LHGRFACp = 0.006(P-100) + 1.0, when 90 % < P < 100 %LHGRFACp 0.557+ 0.00535(P-45) for Core Flow < 50%, P < Pbypass, 32.5% <~ Pbypass < 45%a LHGRFACp =0.537 + 0.00785(P-45) 0 for Core Flow > 50%, P < Pbypass, 32.5% < Pbypass 45%__ _ _ _ __ _ _ _ _ __ _ _ _ _ _ _ _ 1 _ _ _ _ __ _ _ _ _25 30 35 40 45 50 55 60 65 70 75 80 85 90 95% Power 100 REVISION 26 COLRI PAGE 34 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.3 Minimum Critical Power Ratio (MCPR)/Reference Technical Soecification: 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 PQas, MCPRp is the product of the rated power and flow MCPR operating limit presented ihTabIle 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 T.Both Figures 3.3-2 and 3.2-3 include normal and reduced feed water temperature operating modes. For SLO MCPRp and MCPRF are raised by 0.02 compared to TLO values shown in Figures 3.3-2 and 3.2-3.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%.REVISION 26 COLR PAGE 35 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.3-1 MCPR Operatinq Limits At Rated Power and Rated Flow The MCPR Operating Limit for Two Loop Operation (OLMCPRTLO) is a function of fuel type, exposure and r, derived from scram timing measurements I BOC to (EOR-1.9) (EOR-1.9) to EOC GWD/ST GWD/ST 0.0 1.44 1.49 0.0 0.1 1.45 1.51 0.1 0.2 1.46 1.52 0.2 0.3 1.47 1.54 0.3 0.4 1.48 1.56 0.4 0.5 1.50 1.58 0.5 0.6 1.51 1.59 0.6 0.7 1.52 1.61 0.7 0.8 1.53 1.63 0.8 0.9 1.54 1.64 0.9 1.0 1.55 1.66 BOC = Beginning Of Cycle EOC = End Of Cycle EOR = End Of Rated Power Operation At Rated Flow Note: Rated OLMCPR Limits for Turbine Bypass Valve OOS and Final Feedwater Temperature Reduction are the same as those for normal Feed water Temperature and Turbine bypass Valves in service, as OLMCPR is limited by the inadvertent HPCI injection event that is conservatively assumed to cause a Turbine Trip. Off rated MCPR limits are affected by TBVOOS condition and are shown in the off-rated limit curves in Figures 3.3-1, 3.3-2 and 3.3-3 and the Supplemental Reload Licensing Report (Reference 5.15).Sinale Loon Oneration.... * -11 ..... r -r ........OLMCPR SLO = 0.02 + OLMCPR TLO , where OLMCPR TLO is selected from the Table above.REVISION 26 COLR PAGE 36 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Figure 3.3-1 Flow Dependent MCPR Limits (MCPR F) for GE14 fuels Flow Dependent MCPR Limits RTYPE: G4.02 0 t 1.a.1.700 1.600 1.500 1.400 1.300 1.200 1.100.....-0-i 102.5% max flow I I AL .J0 L *Cr ' ' ~.I.... .MCPRF = Max[ 1.2, SLMCPR* (Af *WT/100 + Bf) / 1.07 1---L _A-- L. -112% max flow T ' m" flow Max Core Flow Af Bf117% max flow-1 1102.5 % -0.571 1.655 , ' 1 -40 1 , 10 % max flow T 7 107.0 % -0.586 1.697 110.0 % -0.596 1.727 L 1 LL J-:-L 112.0 % -0.602 1.747 I I- T I F T -1 F 117.0 % -0.632 1.809.L rI, -l 01 -I.--'_1 7II I I I

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  • I I I
  • I I ii.* I I lhi i .l I I i I T I I I L i T ""T -- -3, = I --i T -I -i -F 7T- i i -.-I- + ' : ' 4 -1 1-' 4: -1 + ' -1 8 ' 4' '30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 Core Flow, % Of Rated For SLO MCPRF is raised by 0.02 compared to TLO values shown in the Figure above.REVISION 26 COLR PAGE 37 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.3-2 Power Dependent MCPR Limits (MCPRp) for GE14 fuel Turbine Bypass Is Assumed Operable and Normal and Reduced Feed Water Temperature 3.50 3.00 2.50 0 2.00 1.50 1.00 OLMCPRp = 2.53+0.0335(45%

-P)when 25% i P < P byass and Core flow >50%P= % Power and 45 % Z Pbypass > 32.5%OLMCPRp =1.97+0.021(45-F) when 25% <j, S P bypass and Core flow <50%F=- % Power and 45% > Pbypass > 32.5%i Kp 1.0 + 0.00375(100% P ) for P Z Pbypass P=% Power and 45% Z Pbypass 2,32.5%25 35 45 55 65 75 85 95% Power When P < Pbypassaand in SLO, OLMCPRp is raised by 0.02 compared to TLO values shown in the Figure above.When P > Pbypass and in SLO, Rated OLMCPR is raised by 0.02 before multiplying by Kp to calculate OLMCPRp REVISION 26 COLR PAGE 38 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.3-3 Power Dependent MCPR Limits (MCPRp) for GE14 fuel Turbine Bypass Is Assumed out of service and Normal Feed Water Temperature 4.00 OLMCPRp = 2.5 + 0.08(45- P) forl 3.90 -Core flow > 50%, P= % Power and 3.80 I 25% < P _ Pbypass, 45 % > Pbypass >.32.5%3.70 3.60 3.500 3,40 OLMCPRp = 2.01 -0.0455(45 -P)3.30 Core flow < 50% and P= % Power 3.20 -25% < P < Pbypass, 45 % > Pbypass >32.5%3.10 3.00 2.90 i 2.70 2.00 , , .2.30 2.20,,, 2.00,,.1.90' ---- -- , 1.70 Kp = 1.0 +0.0041(100 -P) for P > 80%1.60 Kp = 1.082 + 0.036(80 -P)for 80% > P > Pbypass P= % Power and ,.50 45 %__> Pbypass >32.5%140.30 1.20 1 .oo a " 25 30 35 40 45 so 55 s0 66 70 75 60 63 90 95 100% Power When P < Pbypass and in SLO, OLMCPRp is raised by 0.02 compared to TLO values shown in the Figure above.When P > Pbypass and in SLO, Rated OLMCPR is raised by 0.02 before multiplying by Kp to calculate OLMCPRp REVISION 26 COLR PAGE 39 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT 3.4 Power/Flow Relationship Duringq Power Operation RTYPE: G4.02 Reference Technical Specification: 3.11..D The power/flow relationship shall not exceed the limiting values shown on the Power/Flow Operating Map in Figure 3.4-1 when in Two Loop Operation and Figure 3.4-2 when in Single Loop Operation. Cycle 17 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.Cycle 17 Stability analysis, the exclusion and the buffer regions shown in Figure 3.4-1 and Figure 3.4-2 are based on Stability Solution I-D (references 5.5, 5.12, 5.15 and 5.18) APRM trip set points are based on Drive flow rather than core flow. Scram and Rod Block Allowable trip set points as a function of drive flow are shown in Figures 2.1-1 for Two Loop Operation and 2.1-2 for Single Loop Operation. Scram and Rod Block Allowable trip set points as a function of drive flow are shown in Figures 2.2-1 for Two Loop Operation and 2.2-2 for Single Loop Operation. 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).Equations for various lines on the Power to flow map are described in Ref. 5.14.REVISION 26 COLRI PAGE 40 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIGURE 3.4-1 PILGRIM POWER / FLOW MAP- TWO LOOP OPERATION Scram and Rod Block Data based on Allowable Values CORE FLOW, MLB/HR 0 5 10 15 20 25 30 35 40 45 50 55 60 a I-4 0-LA'0 IL-J 4.uJ I-0 LU 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 65 70 75 80 2535 WMP AT 120% -2434'K CAPAI152332 SOPERATION-2129 PROHIBITED 2028 1927-1825 1724-1622.. .ICF -- 1521 CORE FLOW 1 , ,REGION -1420.....1318 1115 t I i 1 1014 913 OPERATION 710 PROHIBITED 608 507--406*1 304 1: jl:[17 f1 -7 7 203 7" ., , 101 i.--,j 0 0.,J 4 I-uJ r0 C.MIN PUMP SPEED (26%)0 5 10 15 20 25 30 35 40 45 CORE FLOW, MLB/HR 50 55 60 65 70 75 80 COLR PAGE 41 OF 45 REVISION 26 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIGURE 3.4-2 PILGRIM POWER / FLOW MAP -Single Loop Operation Scram and Rod Block Data based on Allowable Value Setpoints CORE 0 5 10 15 20 25 30 35 FLOW, MLB/H 40 45 R 50 55 60 0 I-OR 0 n-I-W 0 C 65 70 75 80... 4 ,1 2535 RM SCRAM CLAMP AT 120%0 22434)D BLOCK CLAMP AT 115% 2231 2129 2028'. 1927 1825--1724 1622 1521 1420 1318 1217 1014 913 811 710 608 507-406.203 101 0 LU 0 a.-j l--0 C., 0 5 10 15 20 25 30 35 40 45 CORE FLOW, MLB/HR 50 55 60 65 70 75 80 COLR PAGE 42 OF 45 REVISION 26 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.FuelType Cycle Number Loaded Irradiated: GEl 4-P1ODNAB412-16GZ-10OT-145-T6-3901 (GEl 4C) 14 97 GEl 4-P1 ODNAB397-1 0G6.0/3G5.0-1 0OT-1 45-T6-2613 (GEl 4C) 15 35 GEl 4-P1ODNAB397-14GZ-10OT-145-T6-2621 (GEl 4C) 15 88 GEl 4-P1 ODNAB398-8G6.0/5G5.0/1 G2.0-1 OOT-1 45-T6-2614 (GEl 4C) 15 40 GEl 4-P1i DNAB399-1 0G6.0/3G5.0/1 G2.0-1 DOT-1 45-T6-2828 (GE1 4C) 16 104 GEl 4-P1 ODNAB398-8G6.0/5G5.0/2G4.0-1 DOT-1 45-T6-2829 (GEl 4C) 16 56 New: GEl 4-P1ODNAB400-12G6.0/3G5.0-10OT-145-T6-2961 (GEl 4C) 17 32 GEl 4-P1 ODNAB398-5G6.0/1 0G5.0-1 0OT-1 45-T6-2958 (GE1 4C) 17 32 GEl 4-P1 ODNAB399-15GZ-1 0OT-1 45-T6-2957 (GEl 4C) 17 32 GEl 4-P1 ODNAB400-13GZ-1 0OT-1 45-T6-2959 (GEl 4C) 17 24 GEl 4-P10 DNAB404-5G6.0/1 0G5.0-1 DOT-1 45-T6-2960 (GE1 4C) 17 40 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.REVISION 26 COLR PAGE 43 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIGURE 4.0-1 Reactor Vessel Core Loading Pattern 42 emIMmJN mISI m N D C H 1 38 I~fl ~1 rB rCA 34 rII~ CI~ Cr E~32DE DDFl[]EDE[E]F]A EJ][ C L [[HHE]IEF] ]E]E 26 EF E K ]E ED ][A:]C K][HA K KAC]EA K C MKK]E 22 rL7+ C1J~I Hý BC rI,~J~I 3420 +B 2c D[-[-16 E lE 01 9 EIE- PILELRE1E E DE lE12 -I-14B]C]L H] A E L K AK 12 EF]I[0 KE 1 C cI E EDE 1 ID B lE01 10 L E ITEI N9E EI LEREI N EIW N E 0EIIID2AF -T 1P 28K]E]G+ K 6 E[DE]E]E][DE]E fi ] fiA E]E]E] +]C " 1 ~ ~ ~ ~ F 3K 5FH 11 1 71 1 23 25 27 29 31 333D73 14 54 95 Fuel Type A=GE14-PIODNAB404-5G6.0/10G5.0-1OOT-145-T6-2960 (Cycle 17)B--GEl 4-P1ODNAB398-5G6.0/10G5.0-I00T-145-T6-2958 (Cycle 17)C--GE14-P1ODNAB399-10G6.0/3G5.0/1G2.0-IOOT-145-T6-2828 (Cycle 16)D=GE14-PlODNAB400-13GZ-1OOT- 145-T6-2959 (Cycle 17)E=GE14-PIODNAB399-15GZ-OOT- 145-T6-2957 (Cycle 17)F=GE14-P1ODNAB412-16GZ-100T-145-T6-3901 (Cycle 14)G=GE14-P1ODNAB397-10G6.0/3G5.0-10OT-145-T6-2613 (Cycle 15)H=GE14-P1ODNAB398-8G6.0/5G5.0/2G4.0-100T-145-T6-2829 (Cycle 16)1--GE14-PlODNAB398-5G6.0/I0G5.0-1OOT-145-T6-2958 (Cycle 17)J--GE 14-P1 ODNAB400-12G6.0/3G5.0-LOOT- 145-T6-2961 (Cycle 17)K=GE14-PIODNAB397-14GZ-1OOT- 145-T6-2621 (Cycle 15)L=GE14-PIODNAB400-12G6.0/3G5.0-IOOT-145-T6-2961 (Cycle 17)M--GE 14-P 1ODNAB398-8G6.0/5G5.0/1G2.0-100T-145-T6-2614 (Cycle 15).5.REVISION 26 COLR REVISION 26 COLRF PAGE 44 OF 45 PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02

5.0 REFERENCES

5.1. NEDE-2401 1-P-A-15 and NEDE-2401 1-P-A-1 5-US, "General Electric Standard Application for Reactor Fuel", September 2005.5.2. ER05120685, Cycle 17 Reload Core Design.5.3. NEDC-31852-P, rev. 3, "Pilgrim Nuclear Power Station SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis for GEl 1 and GEl 4 Fuels", February 2005.5.4. NEDC-33155P, Rev.0, Application of Stability Long-Term Solution Option I-D To Pilgrim Nuclear Power Station, October 2004.5.5. GE-NE-0000-0056-2695-RO, Option I-D Stability Eclusion Region Analysis for Pilgrim Cycle 17, February 2007.5.6. 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-1 86, Stability AWD calculation. 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. C17DIVOM, Pilgrim C17 Stability Detect and Suppress Confirmation with Plant-Specific DIVOM, GE-NE-0000-0066-0823-RO, 3/21/2007. 5.13. ER 03110960, Stability I-D implementation. 5.14. PNPS-RPT-03-00001, Rev. 3, "Pilgrim Power To Flow Map Report." 5.15. 0000-0056-6173SRLR, "Supplemental Reload Licensing Report, Reload 16, Cycle 17." February 2007.5.16. Calculation S&SA-194, Cycle 17 OPL-3, transient Analysis Inputs.5.17. 0000-0056-6173FBIR, Rev.0, February 2007, Fuel Bundle Information Report, Cycle 17.5.18. SUDDS/RF 02-86, GNF SER issued by NRC approving elimination of Upper Bound PCT limit requirement. 5.19. Calculation S&SA-1 58, OPL 4 & 5, Accident Analysis Inputs.5.20. NEDO-32465A, Licensing Topical report "Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Application, August 1996.REVISION 26 COLR PAGE 45 OF 45}}

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