ML062690471

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Core Operating Limits Report, Revision 25
ML062690471
Person / Time
Site: Pilgrim
(DPR-035)
Issue date: 09/14/2006
From: Ford B
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2.06.088
Download: ML062690471 (45)
v • d • e


Text

" Entergy Entergy Nuclear Operations, Inc.

Pilgrim Station 600 Rocky Hill Road Plymouth, MA 02360 September 14, 2006 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station Docket No.: 50-293 License No.: DPR-35 Core Operating Limits Report, Revision 25 LETTER NUMBER:

2.06.088

Dear Sir or Madam:

Enclosed please find Revision 25 to Pilgrim Nuclear Power Station's Core Operating Umits Report (COLR). COLR Revision 25 replaces Revision 16B and was issued to address Single Recirculation Loop Operating requirements. The COLR (Rev 25) and Technical Specification Revisions (Rev 272) were previously issued via controlled copy distribution to the NRC when License Amendment 219 was implemented on August 2, 2006. Transmittal of this letter documents compliance with Pilgrim's Technical Specification 5.6.5.d. for providing the NRC with mid-cycle revisions to the COLR.

This letter contains no new commitments.

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

Sincerely, Bryan S. Ford Licensing Manager FM/dm

Enclosure:

PNPS Core Operating Limits Report, Revision 25 cc:

Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. James Shea, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission 1 White Flint North 0-8C2 11555 Rockville Pike Rockville, MD 20852 Senior Resident Inspector Pilgrim Station A ool 206088

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 (CYCLE 16)

APPROVED:

APPROVED:

APPROVED:

Robert Smith, Nuclear Engineering Director Onsite Safety Review Corn mittee OSRC Meeting #: ZOO*- 0 07 a te APPROVED:

7 APPROVED:

APPROVED:

E. Olson, Operatfios Manager Date K. 1ronson, -iant Operations General Manager Date M. Balduzzi, Senior Vicel:Yesident - Operations Date REVISION A6 COLR PAGE 1 OF 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4,02 TABLE OF CONTENTS Paae TITLE/SIGNATURE PAGE......................................................................

I 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).................................

29 3.3 Minimum Critical Power Ratio (MCPR)................................

34 3.4 Power/Flow Relationship....................................................

39 4.0 REACTOR VESSEL CORE DESIGN.............................................

42

5.0 REFERENCES

44 REVISION 25 COLR PAGE 2 OF 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 RECORD OF REVISIONS Revision 8A 9A 10A 11A 11B 11C 11D 12A 12B 12C 12D 13A 14A 15A 15B 16A 16B 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 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 #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 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.

REVISION 25 COLR PAGE 3 OF 44

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 GEl I Fuel 17 At Rated Power and Rated Flow 3.1-2 MAPLHGR Limits For GE14 Fuel 19 At Rated Power and Rated Flow 3.3-1 MCPR Operating Limits-GEl I and GEl4 Fuels At Rated 35 Power and Rated 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 25 Rate (MAPLHGR) for GEl1 I Fuel 3.1-2 Most Limiting Maximum Average Planar Linear Heat Generation 26 Rate (MAPLHGR) for GE14 Fuel 3.1-3 Flow-Dependent MAPLHGR Factor (MAPFACF) for GEl 1 and 27 GE14 Fuels 3.1-4 Power-Dependent MAPHLGR Factor (MAPFACp) for GEl I and 28 GE14 Fuels 3.2-1 Maximum Linear Heat Generation 30 Rate (MLHGR) for GEl I Fuel 3.2-2 Maximum Linear Heat Generation 31 Rate (MLHGR) for GE14 Fuel 3.2-3 Flow-Dependent LHGR Factor (LHGRFACF) for GEl 1 and 32 GE14 Fuels 3.2-4 Power-Dependent LHGR Factor (LHGRFACp) for GEl1 and 33 GE14 Fuels 3.3-1 Flow-Dependent MCPR Limits (MCPRF) for GEl1 and GE14 36 Fuels 3.3-2 Power-Dependent MCPR Limits (MCPRp) for GEl I and GE14 37 Fuels, Turbine Bypass Assumed Operable 3.3-3 Power-Dependent MCPR Limits (MCPRp) for GEl 1 and GE14 38 Fuels, Turbine Bypass Out Of Service 3.4-1 Power/Flow Operating Map, Two Loop Operation 40 3.4-2 Power/Flow Operating Map, Single Loop Operation 41 4.0-1 Reactor Vessel Core Loading Pattern 43 REVISION 25 COLR PAGE 4 OF 44

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 16. In this report, Cycle 16 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 25 COLR PAGE 5 OF 44

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#Ihr.

Source: Reference 5.6, sec. 2.1 REVISION 25 COLR PAGE 6 OF 44

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) o 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.

2.

3.

ATSP = C - % WD + D, ATSP is in % Power Figure 2.1-1 shows the plot of ATSP vs. WD.

Reference 5.6, Table l.a lists the values of constants listed in this Table.

REVISION 25 COLR PAGE 7 OF 44

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

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:

4. ATSP = C * % WD + D, ATSP is in % 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 25 COLR PAGE 8 OF 44

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 el E0 E

U (0

a-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, Dive Flow, %

REVISION 25 COLR PAGE 9 OF 44

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) 4'.

a.0 125.0 120.0 115.0 110.0 105.0 100.0 95.0 90.0 85.0 80.0 75.0 70.0 65.0 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 W[D Drive Flow, %

REVISION 25 COLR PAGE 10 OF 44

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 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 Trig 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)

P5 _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 25 COLR PAGE 11 OF 44

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 Trp Set Drive Flow Range Point (ATSPRB)

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+

,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 25 COLR PAGE 12 OF 44

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 65.9 < WD -< 89.1 0

115.0 89.1 <WD _<125 Notes:

4. ATSP=C*%WD+D,ATSPisin% Power
5. Figure 2.1-1 shows the plot of ATSP vs. WD,.
6. Reference 5.6, Table I.b lists the values of constants listed in this Table.

REVISION 25 COLR PAGE 13 OF 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 120.0 110.0 100.0 0

S90.0 0

S80.0 Figure 2.2-1 Allowable APRM Flux Rod Block Trip Settings - TLO (Normal Feed water Temperature)

OF,

-hill m

l hhhh 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 25 COLR PAGE 14 OF 44

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 0

")

V 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 25 COLR PAGE 15 OF 44

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 MAPLHGR The flow-dependent MAPLHGR limit, MAPLHGRF, is the product of the MAPLMIGR flow factor, MAPFACF, shown in Figure 3.1-3 for both GEl 1 and GE14 fuels and the MAPLHGR for rated power and flow conditions, given in Tables 3.1-1 for GE11 fuel or Table 3.1-2 for GE14 fuel. The power-dependent MAPLHGR limit, MAPLHGRp, is the product of the MAPLHGR power factor, MAPFACp, (shown in Figure 3.1-4 for both GEl I and GE14 fuels) and the MAPLHGR limit for rated power and flow conditions, given in Tables 3.1-1 for GEl1 fuel or Table 3.1-2 for GE14 fuel.

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 and 3.1-2.

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 for GEl 1 fuel and Table 3.1-2 for GE14 fuel, 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 25 COLR PAGE 16 OF 44

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 GEl I fuel Bundle Type: GE11-P9DUB407-14GZ-100T-141-T6 Average Planar MAPLHGR Limit (kW/ft)

Exposure GWd/MT (GWd/ST)

Lattice 4338 Lattice 4339 Lattice 4340 Lattice 4341 0.00(0.00) 11.43 10.37 10.28 12.14 0.22(0.20) 11.37 10.43 10.33 12.11 1.10( 1.00) 11.20 10.48 10.44 12.02 2.20(2.00) 11.16 10.60 10.59 12.02 3.31(3.00) 11.19 10.72 10.74 12.06 4.41 (4.00) 11.24 10.83 10.88 12.11 5.51 (5.00) 11.30 10.94 11.02 12.16 6.61(6.00) 11.35 11.06 11.16 12.20 7.72(7.00) 11.39 11.18 11.31 12.24 8.82(8.00) 11.42 11.30 11.47 12.27 9.92(9.00) 11.45 11.42 11.63 12.29 11.02 (10.00) 11.46 11.54 11.80 12.30 12.13 (11.00) 11.47 11.64 11.96 12.31 13.23 (12.00) 11.42 11.72 12.07 12.30 14.33 (13.00) 11.38 11.79 12.16 12.25 14.59 (13.24) 11.36 11.81 12.17 12.23 15.43 (14.00) 11.32 11.86 12.21 12.19 16.53 (15.00) 11.27 11.92 12.23 12.14 18.74 (17.00) 11.15 11.98 12.22 12.02 22.05 (20.00) 10.98 1.96 12.18 11.84 27.56 (25.00) 10.69 11.91 12.10 11.56 33.07 (30.00) 10.16 11.67 11.83 11.26 36.76 (33.35) 9.63 11.24 11.46 10.73 38.58 (35.00) 9.37 11.02 11.28 10.47 44.09 (40.00) 8.59 10.29 10.52 9.69 49.60 (45.00) 7.81 9.57 9.80 8.91 55.12 (50.00) 6.29 8.85 9.10 8.14 57.76 (52A0) 5.36 60.63 (55.00) 7.63 8.07 6.31 62.25 (56.47) 5.74 62.50 (56.70) 7.00 7.42 64.88 (58.86) 6.20 65.74 (59.63) 6.31 REVISION 25 COLR Page 17 of 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 Continued: Bundle Type: GE11-P9DUB408-6G5.0/7G4.0-100T-141-T6 Average Planar MAPLHGR Limit (kW/ft)

Exposure GWd/MT (GWd/ST)

Lattice 4324 Lattice 4325 Lattice 4326 Lattice 4327 0.00 (0.00) 11.43 10.59 10.57 12.01 0.22(0.20) 11.37 10.64 10.61 11.98 1.10(1.00) 11.20 10.73 10.70 11.88 2.20(2.00) 11.16 10.83 10.82 11.88 3.31(3.00) 11.19 10.94 10.95 11.92 4.41 (4.00) 11.24 11.06 11.08 11.97 5.51(5.00) 11.30 11.17 11.22 12.03 6.61 (6.00) 11.35 11.29 11.36 12.07 7.72(7.00) 11.39 11.41 11.51 12.11 8.82(8.00) 11.42 11.53 11.66 12.14 9.92(9.00) 11.45 11.65 11.83 12.16 11.02 (10.00) 11.46 11.77 11.99 12.18 12.13 (11.00) 11.47 11.88 12.13 12.19 13.23 (12.00) 11.42 11.94 12.21 12.17 14.33 (13.00) 11.38 11.98 12.25 12.12 14.59 (13.24) 11.36 11.99 12.26 12.11 15.43 (14.00) 11.32 12.01 12.27 12.07 16.53 (15.00) 11.27 12.03 12.27 12.01 18.74 (17.00) 11.15 12.02 12.19 11.89 22.05 (20.00) 10.98 11.98 12.02 11.71 27.56 (25.00) 10.69 11.92 11.76 11.43 33.07 (30.00) 10.16 11.71 11.56 11.09 36.76 (33.35) 9.63 11.28 11.33 10.56 38.58 (35.00) 9.37 11.07 11.22 10.30 44.09 (40.00) 8.59 10.33 10.56 9.52 49.60 (45.00) 7.81 9.60 9.83 8.75 55.12 (50.00) 6.29 8.88 9.13 7.94 57.76 (52.40) 5.36 60.63 (55.00) 7.67 8.09 6.01 61.57 (55.85) 5.68 62.50 (56.70) 7.04 7.46 65.09 (59.05) 6.16 65.90 (59.78) 6.31 REVISION 25 COLR Page 18 of 44

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 GE14 fuel Bundle Type: GE14-P1ODNAB399-10G6.0/3G5.O/IG2.0-100T-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) 1 4.94 REVISION 25 COLR Page 19 of 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 Continued: Bundle Type: GEI4-PIODNAB398-SG6.0/5G5.0/2G4.0-IOOT-145-T6-2829 (GE14C)

Average Planar MAPLHGR Limit (kW/ft)

Exposure GWd/MT (GWd/ST)

Lattice Lattice Lattice Lattice Lattice Lattice 6849 6850 6851 6852 6853 6854 0.00 (0.00) 9.80 8.69 8.67 8.63 10.21 10.94 0.22 (0.20) 9.71 8.75 8.74 8.71 10.16 10.92 1.10(1.00) 9.50 8.86 8.86 8.83 10.01 10.84 2.20 (2.00) 9.44 9.00 9.04 9.01 9.98 10.83 3.31 (3.00) 9.45 9.08 9.21 9.19 10.01 10.86 4.41 (4.00) 9.49 9.17 9.33 9.36 10.05 10.90 5.51 (5.00) 9.53 9.25 9.42 9.45 10.10 10.93 6.61 (6.00) 9.57 9.34 9.51 9.55 10.15 10.96 7.72 (7.00) 9.61 9.43 9.61 9.64 10.18 10.99 8.82(8.00) 9.64 9.51 9.71 9.74 10.21 11.01 9.92 (9.00) 9.66 9.60 9.82 9.86 10.24 11.03 11.02 (10.00) 9.68 9.70 9.94 9.99 10.25 11.04 12.13 (11.00) 9.69 9.81 10.08 10.13 10.27 11.05 13.23 (12.00) 9.67 9.89 10.19 10.25 10.27 11.05 14.33 (13.00) 9.64 9.96 10.28 10.35 10.24 11.05 15.43 (14.00) 9.60 10.04 10.36 10.43 10.20 11.02 15.99 (14.51) 9.58 10.07 10.39 10.46 10.18 11.00 16.53 (15.00) 9.56 10.10 10.42 10.49 10.16 10.97 18.74 (17.00) 9.48 10.19 10.49 10.55 10.07 10.89 22.05 (20.00) 9.35 10.27 10.54 10.59 9.94 10.76 23.01 (20.87) 9.28 10.26 10.55 10.59 9.89 10.72 27.56 (25.00) 8.95 10.24 10.56 10.62 9.66 10.55 32.19 (29.20) 8.40 9.93 10.26 10.30 9.11 10.11 33.07 (30.00) 8.30 9.87 10.20 10.24 9.01 10.02 38.58 (35.00) 7.65 9.47 9.71 9.71 8.37 9.38 44.09 (40.00) 7.02 9.02 9.18 9.19 7.73 8.75 49.60 (45.00) 6.38 8.51 8.65 8.66 7.10 8.12 54.79 (49.71) 3.98 55.12 (50.00) 7.93 8.11 8.13 5.64 7.49 58.16 (52.77) 4.21 60.63 (55.00) 5.75 6.57 6.75 5.64 62.52 (56.72) 4.88 63.01 (57.16) 4.54 63.50 (57.61) 5.24 5.41 64.17 (58.22) 4.93 64.51 (58.52) 4.95 REVISION 25 COLR Page 20 of 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 Continued:

Bundle Type: GEI4-PIODNAB412-16GZ-100T-145-T6-3901 Average Planar Exposure MAPLHGR Limit (kW/ft)

GWd/MTr (GWd/ST)

Lat.

Lat.

Lat.

Lat.

Lat.

Lit.

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 92.0 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 1037 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 25 COLR Page 21 of 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 Continued: Bundle Type: GE14-P1ODNAB397-10G6.0/3G5.0-100T-145-T6-2613 Average Planar MAPLHGR Limit (kW/ft)

Exposure 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 25 COLR Page 22 of 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE Table 3.1-2 Continued: Bundle Tvxe: GE14-PIODNAB397-14GZ-100T-145-T6-2621 G4.02 Average Planar Exposure

_MAPLHGR Limit (kW/ft)

GWd/MT (GWd/ST)

Lint.

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 25 COLR Page 23 of 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Table 3.1-2 Continued:

Bundle Type: GE14-PIODNAB398-8G6.0/5G5.0/1IG2.0-100T-145-T6-2614 RTYPE: G4.02 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 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) 935 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) 3.9S 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 25 COLR Page 24 of 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.1-1 Most Limiting MAPLHGR For Fuel Type GElI 12 11 10 9

a 7

6 5

0 10 20 30 40 50 60 GWDIST REVISION 25 COLR PAGE 25 OF 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT Figure 3.1-2 Most limiting MAPLHGR For GE14 Fuel RTYPE: G4.02 I1

-10.08 0 - '

9.6 9

7 1

I E

iI i

ili Fi 57 I

I I

I 8~8 36 777 Note:

MAPLHGR limits used by 3D Monicore are lattice specific and are listed in Table 3.1-2 in the Supplemental reload Ucensing report. Most Limiting MAPLHGR limit in any lattice is shown in 6this figure as a function of average planar exposure. Natural Uranium lattices are excluded from this figure. Use tables for accurate calculations if necessary.

5-4 I

I 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 GWDIST 40.0 45.0 50.0 55.0 REVISION 25 COLR PAGE 26 OF 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.1-3 Flow Dependent MAPLHGR Factor (MAPFACF) for both GEl1 and GE14 fuels 1.100-1.000-0.900 0.800-,

0.700 0.600 0.500 -

30.0 40.0 50.0 60.0 70.0 80.0 90.0 Core Flow %

100.0 REVISION 25 COLR PAGE 27 OF 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figire.1-4 Power Dependent MAPLIMR Factors for 0E11 and 0614 Fuel Noft: Thefe MAPFACp factors am valid for Turbine bypn In or out of service and for Normal & Reduce Feefwatr hesang II

-- A n~R 4-4

+

p -.

~-

-~-

+ -

+ AA 0.51 l.APPAf-ftfArEWf.

0.75 C0.7 O.65 0.65 0.5 0.45 0.4 A 4 For P,. %-rpo~r - Pirypene sld32.5% sfbvpfst45%A MAPFACP-OMO191 (P40) +.OAKl Whn 3251% 4 P 9 90%

MAPFACps 0DO (P400)

  • IA0 when 90%0 P 9 IX1%

J I"

I I

I I

I MAPACp O.57 e.o0535 p-45) 4f%.. OW V,

00 P........

32ZI,,

PbJpo g e 1

ý.-ý p ". -,

I I

I I

I I

1.............A I

I -

]-

SMAPFAepa -6.537 +,0.00785 (P.45) torCom Fl, jo 50%. P s Pbytp..,32A.% s Pbyps s 45% I t ~

I I

I IF 1 1

1 I

J I

J I I I I -T I 25 30 35 40 45 60 65 60 65 70 75 80 a5 90 95 100

% Power REVISION 25 COLR PAGE 28 OF 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.2 Linear Heat Generation Rage (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 Figures 3.2-1 and 3.2-2, 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 LHGR. The flow-dependent LHGR limit, LHGRF, is the product of the LHGR flow factor, LHGRFACF, shown in Figure 3.2-3 and the LHGR for rated power and flow conditions in Reference 5.17. The power ependent LHGR limit, LHGRp, is the product of the LHGR power factor, LHGRFACp, shown in Figure 3.2-4 and the LHGR for rated power and flow conditions in Reference 5.17.

LHGR Curves in Figures 3.2-1 and 3.2-2 are representative curves for U02 fuel rods and Gd containing rods in GEl1 I and GE14 fuel bundles. 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 25 COLR PAGE 29 OF 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.2-1 Most Limiting LHGR Limit for GEl1 I Fuel At Rated Power and rated Core Flow 15 14 13 12 VE 11 E 10 59 8-7.

6 5

0 10 20 30 40 50 60 Exposure, GWDIST REVISION 25 COLR PAGE 30 OF 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.2-2 Most Limiting LHGR for GE14 Fuel At Rated Power and rated Core Flow 14 13 12 11 9

8 8 E

IX 7

.1 6

5 4

0 10 20 30 40 50 60 Exposure, GWDIST 70 REVISION 25 COLR PAGE 31 OF 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.2-3 Flow Dependent LHGR Factor (LHGRFACF) for both GE1I and GE14 fuels 1.100 1.000o-0.900-0.800-(

=,

0.700 0.600 0.500 30.0 40.0 50.0 60.0 70.0 80.0 90.0 Core Flow %

100.0 REVISION 25 COLR PAGE 32 OF 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FigUre3.2-4 PowerDependentLHtGRFaCtors for (E11 and0E14 Fue No~The" LIORFACP footorm w* dd for Turimk bype" in or out of seivice and lor Norma & Roduce Fsedwete howIng 25 30 35 40 45 50 55 4s0 05 70 75 s0 05 90 95 100 REVISION 25 COLR PAGE 33 OF 44

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 core thermal powers less than or equal to PBypass, the power-dependent MCPR operating limit, MCPRp, is provided in Figure 3.3-2. For 'ower level less than Pbyrss, 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 P MCPR p is the product of the rated power and flow MCPR operating limit presented ihTable 3.3-1, and the Kp factor presented in Figure 3.3-2, when Turbine Bypass is in service and Feed water Temperature is normal. The rated power and flow MCPR operating limits presented in Tables 3.3-1 are functions of r for both GEl I and GE14 fuels.

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, as follows:

Tave-T 1.252 - ra Where:

T

= Average scram time to drop out of

,Nf Notch 34 n

X, B

=

Adjusted analysis mean

,u + 1.65a scram time 1I-i n

= Number of surveillance tests performed to date in the present cycle N1

= Total number of active control rods Ni

= Number of active control rods measured in the ith surveillance test

= Average scram time to drop put of Notch 34 position of all rods measured in the ith surveillance test

[t

-= Mean of the distribution for average scram insertion time to drop out of Notch 34

= 0.937 sec O"

= Standard deviation of the distribution for average scram insertion time to dropout of Notch 34

= 0.021 sec REVISION 25 COLR PAGE 34 OF 44

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

Table 3.3-1 MCPR Operating 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 GEl1 GE14 T

from 0.0 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 to 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 BOC to (EOR-21 GWD/ST 1.39 1.40 1.42 1.43 1.44 1.45 1.46 1.47 1.48 1.49 1.50 (EOR-21 to EOC GWD/ST 1.41 1.43 1.44 1.45 1.46 1.47 1.48 1.49 1.50 1.51 1.52 BOC to (EOR-2)

GWDIST 1.44 1.45 1.46 1.47 1.48 1.49 1.51 1.52 1.53 1.54 1.55 (EOR-2) to EOC GWD/ST 1.49 1.51 1.53 1.54 1.56 1.58 1.59 1.61 1.63 1.65 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).

Single Loop Operation OLMCPR SLO = 0.02 + OLMCPRno, where OLMCPR TLO is selected from the Table above.

REVISION 25 COLR PAGE 35 OF 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 1.700 1.600 1.500 j

1.400 CL 1.300 1.200 1.100 Figure 3.3-1 Flow Dependent MCPR Limits (MCPR F) for both GEl1 and GE14 fuels Flow Dependent MCPR Limits J.. I..

.4J..L.

+

'1102.5%

max flow/...

=Max[ 1.2 SLM R

(f

  • W 0

+

f) 1.071 T -,n-r~

n-,-,r:-0*Ib 107 % max flow 1

1JJ

-'-L '

0-e 112%t Max flow IL T -j -,-r U1 r

- -49,,-117% max flow Max Core Flow Af of-

.-A

.L.A.....

102.5 %

- 0.571 1.655 107.0%

-0.586 1.697 110.0%

-0.596 1.727 112.0%

-0.602 1.747 T

I F T -i-rT

,r-r 117.0%

-0.632 1.809 J -Ir.-

L r,

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1 -3.

Li M -i ri r

T T--

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,,,.I.LS....4..LL~

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"-1 11,-r l-1-,-,-

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L. L -1 A.-L L A A --I-

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I.,J L

J4

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-J 1-L A

L A L J

I_*

4 -1_I..,-Z I

Z**1I

-r I

r r i

r i

n r T i-r I A.. - 1 A....

L..

4

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L

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41~l 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 Core Flow, % Of Rated 100.0

[For SLO MCPRF is raised by 0.02 compared to TLO values shown in the Figure above.

REVISION 25 COLR PAGE 36 OF 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 F46M S-%-

Poer Devendmnt UCPR Lknf (MCPRP) for both GEll and GEI4u.Ia Twrbin Sypaas k Asaiemd Overabl and Katmal and Rerbied Foed Wate lesPeamum 3.50 Is 25 35 65 i

  • 75 8

% pama When P < Pbypass and in SLO, OLMCPRp is raised in the Figure above.

by 0.02 compared to TLO values shown When P > Pbypass and in SLO, Rated OLMCPR is raised by 0.02 before multiplying by Kp to calculate OLMCPRp REVISION 25 COLR PAGE 37 OF 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.3-3 Power Dependent MCPR Limits (MCPRp) for both GEl1 & GE14 fuels Turbine Bypass Out of service & Reduced Feed Water Temperature 4.10 4.00 3.90 3.80 3.70 3.60 3.60 3.40 3.30 3.20 3.10 3.00 2.90

. 2.80 2.70 2.60 0 2.60 85 2At0 2.30 2.20 2.10 2.00 1.90 1.80 1.70 1.60 1.40 1A40 1.30 1.20 1.10 1.00

-- OLMCPRp = 2.6 + 0.08 (45-P) for; Core flow.> 60%, P= % Powerand

_26%

< P S Pbypass, 45 % k Pbypass OLMCPRp = 2,01 - 0.0456 146 - P)

Core flow <60% and P= % Power 26% ZP 0 5Pbypass, 46 %

Pbypass Kp A

1.0 +.0041 (100 -0) for P 2:100A Kp u 1.082 q- 0.Q36 (80- P) for 80% > P Z P1ypass P= % Power and 45% : Pbypass k32.6%

I -

I~Ii-ziiz 26 30 36 40 45 60 65 00 65 70 76 80 86 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 25 COLR PAGE 38 OF 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT 3.4 Power/Flow Relationship During 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 16 operation is not fully analyzed for reduced feedwater temperature for issues other than thermal limii'. This report contains only the thermal limit analysis results for reduced feed water temperature mode.

Cycle 16 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 (reference 5.13 and 5.22). 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 25 COLR PAGE 39 OF 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 FIGURE 3.4-1 PILGRIM POWER I FLOW MAP Scram and Rod Block Data based on Allowable Values 0

5 125 120 V

115 110 105 0 100 U

95 S85 80! X 75 7 0 85 60 55

H_ ORA OX 50 5

48 40 LOWERBI 35 NATCBC 0

30 25 20 7

MAT 10 LIN 0

CORE FLOW, MLB/HR 10 18 20 25 30 35 40 45 50 55 60 65 70 75 80 2535 APRM SCRAM CLAMP AT 120%

2434 APR4 OO BLOCK CLAMP AT 116%

2332 2231 2028 1927 1820 0124 1622 Z :7 1521-3 COR FOW 14200 1318 1217

.........1014 U

T-71.4913 OERAION 710 0

PRO~trI'ED 608 607 MIMMUM POWER 406 MINPM PE (26%)

2034 1-01 mlmmmlm 0

5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 CORE FLOW, MLB/HR COLR REVISION 25 PAGE 40 OF 44

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIGURE 3.4-2 PILGRIM POWER I FLOW MAP - Single Loop Operation Scram and Rod Block Data based on Allowable Value Setpoints CORE FLOW, MLBIHR 0

5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 w

0 0.

0 o

T i

80 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

80 0

75 0

5 10 15 20 25 30 35 40 45 CORE FLOW, MLBIHR 50 55 60 65 70 COLR PAGE 41 OF 44 REVISION 25

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 Cycle Loaded Irradiated GE 11-P9DUB407-14GZ-1 OOT-141-T6 GEl 1-P9DUB408-6G5.0/7G4.0-1OOT-141-T6 GE14-Pl ODNAB412-16GZ-1OOT-145-T6-3901 13 13 14 15 15 15 Number 89 24 144 35 88 40 GE14-P1ODNAB397-14GZ-10OT-145-T6-2621 GE14-Pl 0DNAB398-8G6.0/5G5.0/1 G2.0-10OT-145-T6-2614 New GE14-PIODNAB398-8G6.0/5G5.012G4.0-10OT-145-T6-2829 (GE14C)

GE14-P1 ODNAB399-1 0G6.0/3G5.0/1 G2.0-1 OOT-145-T6-2828 (GE14C) 16 16 56 104 Total 580 The reactor vessel core contains 145 cruciform-shaped control rods. The control materials used are either boron carbide powder (B4C) compacted to approximately 70%

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

During RFO15, Fuel Bundle JLG621 was found to be leaking and was discharged and Bundle YJS293, originally selected for discharge, was retained in the core. Reference 5.22 documents the GESTAR Assessment by GNF concluding that the analytical limits based on the original reference loading pattern for Cycle 16 remain applicable to the changed core loading as described above.

REVISION 25 COLR PAGE 42 OF 44

PILGRIM NUCLEAR POWVER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIGURE 4.0-1 Reactor Vessel Core Loading Pattern 52 EAC A13c] E]

.- I*,* j Lifff [el Fp

] 1]fjA qE 48 EA*[ EAE Hi F[] I IEEfll[]EDH

[K]

I:Nj

'B 8

M..

EI fEEEfI

+

[e tiE 461-4 Ifl

[]

IL 44 I-EIIEMIO[]G

![EEEE]Mj1 E E 1[flEEDA1[

1!

offff ITSI E

1E[

f] 1--[f]

38 D+% 0ED IEE EE E[f JE-N

[lE 36t ff]

F PD2 E E I E Fý N i c--

L EIE EIE Elc-LF-]

EEIL E

il E [K 1~~~~~~~~~~~~~~

3 11 51 92 32 7293 33 73 14 54 95 Fuel Type A=GEI I-P9DUB408-6G5.0/7G4.0-100T-141-T6 (Cycle 13)

B=GE14-PIODNAB399-10G6.0/3G5.0/1G2.0-100T-145-T6-2828 (Cycle 16)

C=GEI I-P9DUB407-14GZ-10OT-141-T6 (Cycle 13)

D=GEI4-P1ODNAB412-16GZ-IOOT-145-T6-3901 (Cyclel4)

E=GE14-PIODNAB397-1OG6.0/3G5.0-100T-145-T6-2613 (Cycle 15)

F=GE14-PIODNAB398-SG6.0/5G5.0/2G4.0-IOOT-145-T6-2829 (Cycle 16)

G=GE14-PIODNAB397-14GZ-IOOT-145-T6-2621 (Cycle 15)

H=GE14-P1ODNAB398-SG6.0/5G5.011G2.0-IOOT-145-T6-2614 (Cycle 15)

REVISION 25 COLR PAGE 43 OF 44

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

5.0 REFERENCES

5.1.

SUDDS/RF 00-73, NEDE-24011-P-A-14 and NEDE-24011-P-A-14-US, "General Electric Standard Application for Reactor Fuel", June 2000 (includes Amendments through #26) 5.2.

ER03118299, Cycle 16 Reload Core Design.

5.3.

NEDC-31852-P, rev. 3, "Pilgrim Nuclear Power Station SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis for GEl I and GE14 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-0000-0035-9029-RO, Option I-D Reload Stability Analysis for Pilgrim Cycle 16.

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. OG01-0228-001, Determination Of Figure Of Merit for Stability DIVOM curve applicability, July 2004.

5.13. ER 03110960, Stability I-D implementation 5.14. PNPS-RPT-03-00001, Rev. 2, "Pilgrim Power To Flow Map Report."

5.15. 0000-0030-7302SRLR, "Supplemental Reload Licensing Report, Reload 15, Cycle 16."

February 2005 5.16. Calculation S&SA-188, Cycle 16 OPL-3, transient Analysis Inputs 5.17. 0000-0030-7302FBIR, Rev.0, February 2005, Fuel Bundle Information Report, Cycle 16 5.18. DRF 0000-0030-7286, Cycle 16 SLMCPR 5.19. SUDDS/RF 02-86, GNF SER issued by NRC approving elimination of Upper Bound PCT limit requirement.

5.20. Calculation S&SA-1 58, OPL 4 & 5, Cycle 15 Accident Analysis Inputs (unchanged for Cycle`16) 5.21.

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

5.22. 0000-0039-2731, Pilgrim Cycle 16 GESTAR II Section 3.4.3 Assessment 5.23. License Amendment No. 219 REVISION 25 COLR PAGE 44 OF 44

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