ML043350369

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Revised Core Operating Limits Report
ML043350369
Person / Time
Site: Pilgrim
Issue date: 11/22/2004
From: Bethay S
Entergy Nuclear Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2.04.117
Download: ML043350369 (38)
v • d • e


Text

-Entergy Entergy Nuclear Operations, Inc.

Pilgrim Station 600 Rocky Hill Road Plymouth, MA 02360 Stephen J. Bethay November 22, 2004 Director, Nuclear Assessment U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

SUBJECT:

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35 Revised Core Operating Limits Report

REFERENCES:

1. General Electric 10 CFR 50.46 Notification Letter 2004-01, dated September 24, 2004.
2. Entergy letter to U.S. NRC, 30-Day Report Required by 10 CFR 50.46(a)(3)(ii), dated October 21, 2004, LETTER NUMBER: 2.04.117

Dear Sir or Madam:

The enclosed Core Operating Limits Report, Revision 151B, is submitted in accordance with the requirements of Pilgrim Station's Technical Specification 5.6.5.

The revision provides cycle-specific limits for operating Pilgrim during fuel cycle 15. The revised core operating limits have been established using the NRC-approved methodology provided in the reference listed in COLR, Section 5.0, and in Technical Specification 5.6.5. The revision resulted from actions taken in response to Reference 1 that resulted in the submittal of Reference 2.

There are no commitments contained in this letter.

Please feel free to contact Bryan Ford, (508) 830-8403, for any questions regarding this subject.

Sincerely, Step enJ. thay SJB/dm

Enclosure:

Pilgrim Power Station Core Operating Limits Report, Revision 15B (37 pages) cc: U.S. Nuclear Regulatory Commission Mr. Robert Fretz, Project Manager Region I Office of Nuclear Reactor Regulation 475 Allendale Road Mail Stop: 0-8B-1 King of Prussia, PA 19406 U. S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Senior NRC Resident Inspector Rockville, MD 20852

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 (CYCLE 15)

APPROVED:

Reaclor nring Superintendent 7/ Bate' APPROVED: /2f//H Nuleear Eng ineering Director Date APPROVED: L-4L1x- l///e/l) -

Operoons Review Committee 7 Date ORC Meeting #: ____-_e /_

APPROVED: -

Operafions Manager Date APPROVED: -

Plant Operations General Manager Date APPROVED: -

Vice PresWzt- Operations Date REVISION 15B COLR PAGE 1 0F37

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) .9 2.3 Rod Block Monitor Trip Setting .9 3.0 CORE OPERATING LIMITS .. 12 3.1 Average Planar Linear Heat Generation Rate (APLHGR) .12 3.2 Linear Heat Generation Rate (LHGR) ........................... 24 3.3 Minimum Critical Power Ratio (MCPR) ........................... 29 3.4 Power/Flow Relationship ........................... 33 4.0 REACTOR VESSEL CORE DESIGN . .35

5.0 REFERENCES

.. 37 REVISION 15B COLR PAGE 2 OF 37

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

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

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

Applicable for use during Cycle 15 Operation REVISION 15B COLR PAGE 3 OF 37

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 LIST OF TABLES Number Title Page 2.1-1 Formulae for APRM Flux Scram Trip 7 Settings in Figure 2.1 -1 2.2-1 Formulae for APRM Rod Block Trip 10 Settings in Figure 2.2-1 3.1-1 MAPLHGR Limits For GE11 Fuel 13 At RatedPower and Rated Flow 3.1-2 MAPLHGR Limits For GE14 Fuel 16 At RatedPower and Rated Flow 3.3-1 MCPR Operating Limits- GE1 1 Fuel 30 At RatedPower and Rated Flow LIST OF FIGURES Number Title Paqe 2.1-1 Nominal & Allowable APRM Flux Scram Trip Settings (Normal 8 Feedwater Temperature) 2.2-1 Nominal & Allowable APRM Rod Block Trip Settings (Normal 11 Feedwater Temperature) 3.1-1 Most Limiting Maximum Average Planar Linear Heat Generation 20 Rate (MAPLHGR) for GE1 1 Fuel 3.1-2 Most Limiting Maximum Average Planar Linear Heat Generation 21 Rate (MAPLHGR) for GE14 Fuel 3.1-3 Flow-Dependent MAPLHGR Factor (MAPFACF) for GE1 1 and 22 GE14 Fuels 3.1-4 Power-Dependent MAPHLGR Factor (MAPFACp) for GE1 1 and 23 GE14 Fuels 3.2-1 Maximum Linear Heat Generation 25 Rate (MLHGR) for GE1 1 Fuel 3.2-2 Maximum Linear Heat Generation 26 Rate (MLHGR) for GE14 Fuel 3.2-3 Flow-Dependent LHGR Factor (LHGRFACF) for GE1 1 and 27 GE14 Fuels 3.2-4 Power-Dependent LHGR Factor (LHGRFACp) for GE1 1 and 28 GE14 Fuels 3.3-1 Flow-Dependent MCPR Limits (MCPRF) for GE1 1 and GE14 31 Fuels 3.3-2 Power-Dependent MCPR Limits (MCPRp) for GE1 1 and GE14 32 Fuels, Turbine Bypass Assumed Operable 3.4-1 Power/Flow Operating Map 34 4.0-1 Reactor Vessel Core Loading Pattern 36 REVISION 15B COLR PAGE 4 OF 37

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 15. In this report, Cycle 15 will be referred to as the present cycle.

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

Reference Technical Specification APRM Flux Scram Trip Setting (Run Mode) Table 3.1.1 APRM Rod Block Trip Setting (Run Mode) Table 3.2.C-2 Rod Block Monitor Trip Setting Table 3.2.C-2 Average Planar Linear Heat Generation Rate 3.11.A Linear Heat Generation Rate (LHGR) 3.11.B Minimum Critical Power Ratio (MCPR) 3.11.C Power/Flow Relationship 3.11.D Reactor Vessel Core Design 4.2 If any of the core operating limits in this report is exceeded, actions will be taken as defined in the referenced Technical Specification.

The core operating limits in this report have been established for the present cycle using the NRC-approved methodology provided in'the documents listed in Technical Specification 5.6.5. These limits are established such that the applicable limits of the plant safety analysis are met.

REVISION 15B COLR PAGE 5 OF 37

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

a. Normal Feedwater Heating or Low Thermal Reactor Power:

TFW > TFw(rated)-50 0 F OR P < 30%,

WhereTrw = rated equivalent Feedwater Temperature in OF; P= Core Power, % of rated.

When the mode switch is in the RUN position, the average power range monitor (APRM) flux scram trip setting (Sr), in percent of rated thermal power, as a function of aligned drive flow shall be as given by Figure 2.1-1. Ss is clamped at 120% of rated core thermal power.

Formulae used to develop Figure 2.1-1 are listed in Table 2.1-1.

The aligned drive flow to the input drive flow relationship is as follows:

WD = WDl 00 (AD40) - Wn4O (AD1 00) + AWD*WD1 AWD - AD1 00 + AD40 Where:

WD10OO = 100.319 (Ref: 5.10 Table 16)

WD40 = 34.957 (Ref: 5.10 Table 16)

AWD= WD100 - WD40 AD40 = Low flow drive flow alignment setting AD100= High flow drive flow alignment setting FCTR card input drive flow in percent of rated WDI= Aligned drive flow in percent of rated Source: Reference 5.20, Equation 5-14 The APRM flux scram trip setting is valid only for operation using two recirculation loops.

Operation with -one recirculation loop out of service is restricted by License Condition 3.E.

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. The 50 OF Feedwater Temperature reduction limit only applied to the APRM FCTR Card Settings, based on the validity range of Stability Analysis.

Drive flow alignment will be done within 7 days of reaching equilibrium xenon at 100 % Core Thermal Power after a Refueling Outage.

b. Reduced Feedwater Heating:

TFw < TFw(rated) - 501F AND P > 30%,

Cycle 15 operation is not fully analyzed for reduced feedwater temperature. Core stability has been analyzed for feedwater temperature reduction. Use of this analysis requires implementation of the appropriate settings on the Flow Control Trip Reference (FCTR) cards, changes to thermal limits and Power to Flow map.

REVISION 15B COLR PAGE 6 OF 37

PILGRIM NUCLI POWER STATION PNPS CORE torERATING LIMITS REPORT RTi, cE:

G4.02 Table 2.1-1 Formulae For Nominal and Allowable APRM Flux Scram Settings (Normal Feedwater Temperature)

Expression Ss = P,% power, where A B C D E Drive Flow Range

._  % Rated P=A 38.791 0 BaWd *18.669 41.2469 1.7257 0.3699 -6.1436 19.0656 18.669 <Wd < 34.865 C+ WD E ()+

WD' )1 P=AxB[ 0 E~~

P=A + B XWD -644.1699 20.0695 34.865 < WD C 35.817 P=A + B X WD 45.6282 0.8105 35.817 < WD *57.49 P=A + B XWD -524.2987 10.7241 57.49 < WD *58.37 P=A + B XWD 54.1885 0.8134 58.37 < WD

  • 78.447 P=A 118 .1 78.447 <WD <*109.688 Notes: I
1. Ss is the Scram Trip Setting in % Core Power and WD is the % Aligned Drive Flow as stated in section 2.1
2. Figure 2.1-1 shows the plot of Ss vs. WD-
3. Allowable setting = 2 + Nominal Ss calculated at (WD + 3)
4. Reference 5.10, Table 12.C lists the values of constants listed in this Table.

'I REVISION 15B COLR PAGE 7 OF 37

PILGRIM NUCLU POWER STATION PNPS CORE tPERATING LIMITS REPORT RTb. cE:

G4.02 Figure 2.1-1 Nominal and allowable APRM Flux Scram Trip Settings 130 120 110 lob _ _ _ _ -_ - o_ - _-__

90 0a lI 2 80 co a:

e 70 _ _ _Nominal

&Z

¢ 0 60 o 50

.-,.~~~~~~~WoleI ____ -___

40 40

. = ==

== ===== = == ===

20 10 0

0 10 20 30 40 50. 60 70 80 90 100 110 Aligned Drive Flow, (% Rated)

REVISION 15B COLR PAGE 8 OF 37

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

a. Normal Feedwater Heating or Low Thermal Reactor Power:

TFW 2 TFw(rated)-50'F OR P < 30%

Where TFw = rated equivalent Feedwater Temperature. OF & P=Core Power, % of rated When the mode switch is in the run position, the average power range monitor (APRM) rod block trip setting (SRB) as a function of aligned drive flow shall be as given by Figure 2.2-1. SF is clamped at 115% of rated core thermal power.

Formulae that form the basis of the Figure 2.2-1 are listed in Table 2.2-1.

The aligned drive flow is calculated from the input drive flow using the relationship given in section 2.1.

The APRM rod block trip setting is valid only for operation using two recirculation loops. Operation with one recirculation loop out of service is restricted by License Condition 3.E.

2.2 APRM Rod Block Trip Setting (Run Mode)

b. Reduced Feedwater Heating:

TFW, < TFw(rated) - 50'F AND P > 30%

Cycle 15 operation is not fully analyzed for reduced feedwater temperature. Core stability has been analyzed for feedwater temperature reduction. Use of this analysis requires implementation of the appropriate settings on the Flow Control Trip Reference (FCTR) cards, changes to thermal limits and Power to Flow map.

2.3 Rod Block Monitor Trip Setting Reference Technical Specification: Table 3.2.C-2 Allowable values for the power-dependent Rod Block Monitor trip setpoints shall be:

Reactor Power, P Trip Setpoint

(% of Rated) (% of Reference Level)

P < 25.9 Not applicable (All RBM Trips Bypassed) 25.9 < P < 62.0 120 62.0<P<82.0 115 82.0<P 110 The allowable value for the RBM downscale trip setpoint shall be < 94.0% of the reference level. The RBM downscale trip is bypassed for reactor power < 25.9%

of rated.

REVISION 15B COLR PAGE 9 OF 37

PILGRIM NUCL' I POWER STATION PNPS CORE --iPERATING LIMITS REPORT RT .-E:

G4.02 I. Table 2.2-1 Formulae For Nominal & Allowable APRM Rod Block Settings (Normal Feedwater Temperature)

Expression SRB = P,% power A B C D E Drive Flow Range where  % Rated P=A 29.6577 N/A N/A N/A N/A 0 <WD< 18.669 32.0 2.5918 -0.0718 -1.0956 5.6374 18.669 <WD< 34.876

+D - + -32.0 2.5918 -0.0928 -0.7999 4.9601 34.876 <WD< 51.488 PLAxB[ 100 (10 32.0 2.5918 -0.1237 0.1291 3.2741 51.488 <WD< 60.6 P=A + B XWD 47.0121 0.8133 N/A N/A N/A 60.6 <WD<81.133 P=A 113.000 N/A N/A N/A N/A 81.133<WD<l09.237 Notes: I

1. SRB is the APRM Rod Block Trip Setting ith % Core Power and WD is the % Aligned Drive Flow as stated in section 2.2
2. Figure 2.2-1 shows the plot of SRB VS. WD.
3. Allowable setting = 2 + Nominal SRB calculated at (WD + 3)
4. Reference 5.10, Table 12.C lists the values of constants listed in this Table.

(

REVISION 15B COLR PAGE 10 OF 37

PILGRIM NUCL I POWER STATION PNPS CORE -iPERATING LIMITS REPORT RI .,.E:

G4.02 Figure 2.2-1 Nominal & Allowable APRM Rod Block Trip Settings 140 T- F.

__ I ZL] _______ zliz 1 z zI1I - *i 120

--- - 2 _ _

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

I

- -t-- .*

100 __ I I 80 I1--Nominal

- -------- L-AI3wabIe 60 40 It:t 20 ii __ __ i-..-.- - - - - -- -

0 JZ. I _ _

0 20 40 60 80 100 120 Aligned Drive Flow (% Rated)

REVISION 15B COLR PAGE 11 OF 37

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 MRPLHGR flow factor, MAPFACF, shown in Figure 3.1-3 for both GE1 1 and GE14 fuels and the MAPLHGR for rated power and flow conditions, given in Tables 3.1-1 for GE1 1 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 GE1 1 and GE14 fuels) and the MAPLHGR limit for rated power and flow conditions, given in Tables 3.1-1 for GE1 1 fuel or Table 3.1-2 for GE14 fuel.

The MAPLHGR for rated power and flow conditions for each fuel type as a function of axial location and average planar exposure are based on the approved methodology referenced in Section 5.0 and programmed in the plant process computer. The MAPLHGR for rated power and flow conditions for the most limiting lattice in each fuel type (excluding natural uranium lattices) are presented in Figures 3.1-1 and 3.1-2. The MAPLHGR limits for off-rated conditions are based on the approved methodology in reference 5.3.

'MAPLHGR limits are based on ECCS-LOCA considerations. The new GNF SER issued by the NRC (Reference 5.18) documents the basis for the elimination of an Upperbound PCT limit. Cycle 15 MAPLHGR limits are based on use of this SER. Peak LHGR and peak MAPLHGR were both reduced in order to obtain a margin to the Licensing basis PCT limit of 2200 "F. Lattice and exposure dependent MAPLHGR limits were to control the peak LHGR and MAPLHGR within a node. For each lattice type, the MAPLHGR values for rated power and flow conditions are listed in Tables 3.1-1 for GE1 1 fuel which are obtained from the Supplemental Reload Licensing Report (Ref. 5.14). MAPLHGR Values for GE14 fuel reported by the SRLR were found to be in error as reported by GE in 10CFR50.46 notification 2004-01 (reference 5.22) .

Therefore, the MAPLHGR values in the SRLR (Ref. 5.14) are superceded by Reference 5.21, which reported corrected MAPLHGR limit values. The corrected values calculated using SAFER/GESTR and were design verified by GE.

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. Pbypass is currently set at 32.5% power.

REVISION 15B COLR PAGE 12 OF 37

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 GE11 fuel Bundle Type: GE11-P9DUB407-14GZ-10OT-141-T6 Average Planar Exposure MAPLHGR Limit (kWlft) for Lattice #

GWdIMT (GWd/ST) 4338 4339 4340 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 11.96 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 (52.40) 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 15B COLR Page 13 of 37

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 Continued: BundleType: GE11-P9DUB408-6G5.017G4.0-10OT-141-T6 Average Planar Exposure MAPLHGR Limit (kWlft) for Lattice #

GWd/MT (GWd/ST) 4324 4325 4326 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 15B COLR Page 14 of 37

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 Continued: Bundle Type: GEl1-P9DUB408-16GZ-100T-141-T6 Average Planar Exposure MAPLHGR Limit (kW/ft) for Lattice #

GWd/MT (GWdIST) 3651 3944 3955 3956 3957 3958 0.00 (0.00) 11.46 10.36 10.53 10.26 10.54 12.35 0.22 (0.20) 11.40 10.42 10.58 10.32 10.58 12.33 1.10 (1.00) 11.23 10.46 10.65 10.43 10.67 12.25 2.20 (2.00) 11.20 10.58 10.75 10.58 10.78 12.25 3.31 (3.00) 11.23 10.71 10.86 10.73 10.90 12.28 4.41 (4.00) 11.28 10.82 10.96 10.90 11.02 12.32 5.51 (5.00) 11.33 10.93 11.07 11.07 11.15 12.36 6.61 (6.00) 11.38 11.05 11.17 11.24 11.29 12.40 7.72 (7.00) 11.42 11.17 11.28 11.40 11.43 12.43 8.82 (8.00) 11.45 11.29 11.39 11.56 11.57 12.46 9.92 (9.00) 11.47 11.42 11.50 11.71 11.72 12.47 11.02 (10.00) 11.49 11.54 11.62 11.87 11.88 12.48 12.13 (11.00) 11.50 11.65 11.72 12.01 12.03 12.49 13.23 (12.00) 11.45 11.73 11.78 12.11 12.13 12.49 14.33 (13.00) 11.40 11.81 11.84 12.12 12.13 12.44 14.59 (13.24) 11.39 11.83 11.86 12.12 12.13 12.42 I 15.43 (14.00) 11.35 11.88 11.90 12.12 12.13 12.38 16.53 (15.00) 11.29 11.93 11.95 12.08 12.08 12.33 18.74 (17.00) 11.18 11.95 11.99 11.98 11.98 12.21 22.05 (20.00) 11.00 11.77 11.88 11.81 11.81 12.04 27.56 (25.00) 10.71 11.50 11.58 11.56 11.55 11.75 33.07 (30.00) 10.19 11.22 11.34 11.35 11.34 11.48 36.76 (33.35) 9.66 10.94 11.11 11.07 11.07 10.97 38.58 (35.00) 9.39 10.80 11.00 10.93 10.94 10.72 44.09 (40.00) 8.61 10.04 10.30 10.32 10.28 9.94 49.60 (45.00) 7.83 9.29 9.58 9.71 9.49 9.17 55.12 (50.00) 6.32 8.54 8.86 9.08 8.73 8.39 57.83 (52.46) 5.37 - -- -- -- --

60.63 (55.00) -- 7.54 7.66 8.06 7.62 6.76 62.50 (56.70) 6.95 7.03 7.42 6.99 6.11 63.29 (57.41) -- - -- -- 5.83 64.95 (58.92) 6.19 -- --

65.03 (58.99) --- 6.17 65.67 (59.57) - - 5.93 65.80 (59.70) 6.30 --

REVISION 15B COLR Page 15 of 37

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RT'YPE: G4.02 Table 3.1-2 MAPLHGR Limits for Rated Power and Rated Flow for GE14 fuel Bundle TyDe: GE14-PlODNAB412-16GZ-IOOT-145-T6-3901 Average Planar Exposure MAPLHGR Limit (kW/ft) for Lattice #

GWdIMT (GWdIST) 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 10.966 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 I -- --

62.91 (57.07) 4.92 REVISION 15B COLR Page 16 of 37

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 Continued: Bundle Type: GE14-PlODNAB397-lOG6.0/3G5.0-OOT-145-T6-2613 Average Planar MAPLHGR Limit (kW/ft) for Lattice #

Exposure GWdIMT (GWd/ST) 5841 5848 5849 5850 5846 5851 0.00 (0.00) 9.80 8.75 8.72 8.71 10.21 10.87 0.22 (0.20) 9.71 8.81 8.79 8.78 10.16 10.84 1.10( 1.00) 9.50 8.91 8.91 8.91 10.01 10.74 2.20 (2.00) 9.44 9.05 9.07 9.07 9.98 10.71 3.31 (3-00) 9.45 9.20 9.24 9.25 10.01 10.73 4.41 (4.00) 9.49 9.30 9.42 9.44 10.05 10.76 5.51 (5.00) 9.53 9.38 9.56 9.61 10.10 10.79 6.61 (6.00) 9.57 9.45 9.65 9.70 10.14 10.82 7.72 (7.00) 9.61 9.54 9.74 9.80 10.18 10.85 8.82 ( 8.00) 9.64 9.62 9.83 9.89 10.21 10.87 9.92 ( 9.00) 9.66 9.70 9.92 9.98 10.24 10.88 11.02 (10.00) 9.68 9.78 10.01 10.07 10.25 . 10.89 12.13 (11.00) 9.69 9.87 10.11 10.18 10.26 10.90 13.23 (12.00) 9.67 9.93 10.21 10.28 10.27 10.90 14.33 (13.00) 9.64 9.99 10.29 10.36 10.23 10.89 15.43 (14.00) 9.60 10.05 10.35 10.43 10.19 10.85 15.99 (14.51) 9.58 10.07 10.37 10.45 10.17 10.83 16.53 (15.00) 9.56 10.10 10.40 10.47 10.15 10.81 18.74 (17.00) 9.48 10.18 10.45 10.51 10.07 10.72 22.05 (20.00) 9.35 10.24 10.49 10.55 9.94 10.59 23.01 (20.87) 9.28 10.24 10.50 10.56 9.89 10.55 27.56 (25.00) 8.95 10.22 10.52 10.60 9.66 10.38 32.19 (29.20) 8.40 9.92 10.22 10.29 9.11 9.91 33.07 (30.00) 8.30 9.86 10.16 10.23 9.01 9.82 38.58 (35.00) 7.65 9.46 9.69 9.70 8.36 9.18 44.09 (40.00) 7.02 9.01 9.17 9.18 7.73 8.54 49.60 (45.00) 6.38 8.50 8.64 8.65 7.09 7.91 54.78 (49.70) 3.98 -- -- -- - --

55.12 (50.00) -- 7.92 8.10 8.12 5.63 7.28 58.14 (52.75) - -- -- 4.21 --

60.63 (55.00) 5.76 6.51 6.74 -- 5.12 62.02 (56.27) -- - -- 4.47 62.56 (56.75) 4.87 -- -- -

63.50 (57.61) - 5.18 5.41 _ _

64.09 (58.14) 4.91 -

64.53 (58.54) - 4.94 _

REVISION 15B COLR Page 17 of 37

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 Continued: Bundle Type: GE14-PlODNAB397-14GZ-IOOT-145-T6-2621 Average Planar Exposure MAPLHGR Limit (kW/ft) for Lattice Number GWd/MT (GWd/ST) 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 15B COLR Page 18 of 37

. PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 Continued: Bundle Type: GE14-PlODNAB398-8G6.0/5G5.O/IG2.0-10OT-145-T6-2614 Average Planar Exposure MAPLHGR Limit (kW/ft) for Lattice #

GWdIMT (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) 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 15B COLR Page 19 of 37

PILGRIM NUCL I POWER STATION PNPS CORE uPERATING LIMITS REPORT RTYPE: (u4.02 FIGURE 3.1-1 Most Limiting MAPLHGR FOR GE11 Fuel Type I II -  ! Y 13 , . .

._ . v I I , I

! -I I! ) I 4. .

I i

1. . ; ...- . 1 95 11.92I

, -- II.--119 ?j..fj 11.92 1 1-11 I I . , - I 12 __ _ 4 +

r -11.77-  ; . i. '!I 11.54 i , 11.50I

',i I

..J .1 iI 11.22  :;

1..93 .I. I. E I I

"-:'-,10.93

,/ i 1 ........ -: 11i :s:. I  :. I -  :.:...

11 I --!

.I :

1 . I . . _ l

. i I .1 I I I - I I I . -- I -10.80 1 i I

(I 10

.A 1%On :10.04::L 10 IUu. oI I

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

i I*- I I i i I% I I

! I I

i i .

I . .I I I 11 .1. i  !, I ,

.! ...- ] ...... ..... IJ, I I

9

-J 0.

$, f_ t~,T. itLI1 I

., ,I.... ,1

__ _i . +/-.j....., _ .__ j .1, .- ? -?

I ...

8- I I1i1 I - I I i I .,I

'. i Note:

MAPLHGR Limits used by 3D-Monicore are lattice specific and : l l .

are listed in Table 3.1-1 as provided in the SRLR. The most _ 1 limiting MAPLHGR of all GE1 1 fuel bundle lattices as a function of planar average exposure is shown in this figure for illustrative purposes. 1-.--.

"Ii 6-i-

Ii Il l  ; I

________ t Ir 4 ~.- I'

  • 1

- I  : 4I I q I I

  • Y I

. I 3 5 . . .. 1 0 5 10 15 20 25 30 35 40 45 50 55 60 65 Planar Average Exposure (GWD/ST)

REVISION 15B COLR PAGE 20 OF 37

PILGRIM NUCL I POWER STATION PNPS CORE %HERATING LIMITS REPORT RTYPE: *.02 lgum 3a1-2 Mods liffitingPMAUV Fbr (14 Fue

- 1Q I- 1 11 1 1 1 1 7.1 --

-j 0.

M4LHRlK iryts ed Ly3D rvteruelatI~cespecdfic a-clare listedin Telie l-2 inth-ce nawtireoad Uoensr-greport. Mod furcki d awg lplan e~pose for illu~ate pupses, N~tura Lhnim~lattices ame duzid from tls figie. Use tabes fcr aximie 5CEI~atiatns ff necessav.

-1 IL I4.21 4-- .HIIL:F o 5.0 1iQO 15.0 2D.0 25.0 3o0 5.0 40.0 45.0 . 90.0 55.0 G=Sr REVISION 15B COLR PAGE 21 OF 37

PILGRIM NUCL I POWER STATION PNPS CORE %jPERATINGLIMITS REPORT RTYPE: ,4.02 Figure 3.1-3 Flow Dependent MAPLHGR Factor (MAPFACF) for both GE11 and GE14 fuels 1.100 1 .000 0.900 0

IL m 0.800 IAPLHGRf =MAPLHGIRFACf *MAPLHGRstd a.

hi IAPLHGRstd = MAPLHGR rated power & flow MAPLHGRFAC-102.5%

= min(1.0 or 0.4861 + 0.6784 (WT/1 00 )

0.700 MAPLHG R FAC-107%

= min(1.0 or 0.4574 + 0.6758 (WT/1 00 )

0.600 MAPLHGRFAC-112%

= min(1.0 or 0.4214 + 0.6807 (WT/1 00 )

0.500 4-30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 I,

Core Flow %

REVISION 15B COLR PAGE 22 OF 37

PILGRIM NUCL  : POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: u4.02 Figure 3.1-4 Power Dependent MAPLHGR Factors for GE11 and GE1 4 Fuel i

MAPFACp for P > Pbypass, Turbine bypass is operable and Normal Feedwater Heating I __ _ _ _ _- _ __ I Z 0.95 32.5 % < P 2 70 % , MAPFACp=0.00408

  • P + 0.6364 70 % < P 590 %, MAPFACp = 0.001
  • P + 0.852 90 % < P 5 100 %, MAPFACp = 0.0058 *P + 0.42 S _ _ _ _. wX _ _

(I 0.85 0.

0.75

_X-l l_ l ff  ;

______* \_

Temperature Reduction of up to 75 °F is assumed III-:

MAPFACp for P > Pbypass, Turbine bypass inoperable and Feedwater U __ _ - _32.5 % < P 5 90 MAPFACp =09 +0.004 *(P.90) 90 % < P s100%, MAPFACp= 1.0 +0.01 *(P-100)

< 0.65 0.55 MAPLHGRFACp 0.49+ 0.00533 (P-32.5) for Core Flow r 50% and P !: Pbypass of 32.5%

I I - I I I I I I I 0.45 MAPLHGRFACp = 0.44 + 0.008 (P-32.5)

_ _for Core Flow > 50% and P < Pbypass of 32.5%

0.35 35 45 55 65 75 85 95

%Power REVISION 15B COLR PAGE 23 OF 37

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

Reference Technical Specification: 3.1 1.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 5.16. 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, LH8 RFACF, shown in Figure 3.2-3 and the LHGR for rated power and flow conditions in Reference 5.16. The power-dependent 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 5.16.

The LHGR limits for each fuel type as a function of axial location, rod power and exposure are based on the approved methodology referenced in Section 5.0 and programmed in the plant process computer. LHGR limits are based on thermal-mechanical design limits in reference 5.1. LHGR Curves in Figures 3.2-1 and 3.2-2 are representative curves for U02 fuel rods and Gd containing rods in GE1l1 and GE14 fuel bundles. Gd containing fuel rods have different LHGR limits that are also exposure dependent. Reference 5.16 documents the detailed proprietary curves and values. Limits specified in Reference 5.16 are programmed into the 3D Monicore Process Computer.

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 is currently set at 32.5% power.

REVISION 15B COLR PAGE 24 OF 37

PILGRIM N -EAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.2-1 LHGR Limit for GE11 Fuel At Rated Power and rated Core Flow 15 14 13 12 11 E~

10 0r 9

8 7

(

6 5

0 10 20 30 40 n0. 50 60 Exposure, GWD/ST REVISION 15B COLR PAGE 25 OF 37

PILGRIM Nt EAR POWER STATION PNPS CORE OPEHATING LIMITS REPORT RTYPE: ui4.02 Figure 3.2-2 LHGR for GE14 Fuel At Rated Power and rated Core Flow 14- __ TIiL[

_____ __________ ___mI 12 - - - - - - - - - - -0 I I For U02Fuel t

11 ~Rods4 E 4 -0 87~or GdRods -~

7-5-

4 0 10 20 30 40 50 60 70 Expostore, GWDIST F REVISION 15B COLR PAGE 26 OF 37

PILGRIM N. .EAR POWER STATION PNPS CORE OPEHATING LIMITS REPORT RTYPE: G4.02 REVISION 15B COLR PAGE 27 OF 37

PILGRIM I\ LEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.2-4 Power Dependent LHGR Factors for GE1 I and GE14 Fuel LHGRFACp for P > Pbypass, Turbine bypass is operable and Normal Feedwater Heating 0.95 -

32.5 % < P 5 70%, LHGRFACp=0.00408

  • P + 0.6364 _ _- _-- I I __-_ I c VI__

70 % < P 590 %, LHGRFACp = 0.001

  • P + 0.852 90 % < P 5 100 %, LHGRFACp = 0.0058 *P + 0.42

-- 1 1 1 - 1 I - T r - I , I 0.85 0.75 _ __LHGRFACp for P > Pbypass, Turbine bypass inoperable and Feedwater Temperature Reduction of up to 75 °F is assumed

_ _ 32.5 % < P 5 90% LHGRFACp = 0.9 +0.004 * (P 90) a: 90%<P5100% LHGRFACp=1.0+0.01*(P-100)

= 0.65

-J 0.55 LHGRFACp 0.49+ 0,00533 (P-32.5) l -

f.or Core Flow 5 50% and P 5 Pbypass of 32.5%

(I 0.45

_ 2 § __ =_= TmLHGRFACp = 0.44 + 0.008 (13-32.5) __

/ l l }l g l 0 l §for Core Flow > 50% and P 5Pbypass of 32.5%II 0.35 25 35 45 55 %5 75 85 95

% Power REVISION 15B COLR PAGE 28 OF 37

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 PB pa s, the power-dependent MCPR operating limit, MCPRp, is provided in Figure 3.3-2 for nolymal Feedwater Temperature. Above PBvnas, MCPRp is the product of the rated power and flow MCPR operating limit presented in iae 3.3-1, and the Kp factor presented in Figure 3.3-2, when Turbine Bypass is in service and Feedwater Temperature is normal. Figure 3.3-2 indicates MCPRp up to 45% power, which is the maximum analyzed value for Pbypass. The rated power and flow MCPR operating limits presented in Tables 3.3-1 are functions of T for both GE11 and GE14 fuels. In arriving at the MCPRp for off-rated power conditions, Kp from Figure 3.3-2 is multiplied by the rated OLMCPR from Table 3.3-1 for the appropriate fuel type, GE1 1 or GE14, when power is above Pbypass. For power level less than Pbypass, the MCPRp is independent of the fuel type and can be directly read from Figure 3.3-2.

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:

Ta ye - ri 1.252 - r, Where:

S In

-a.= Average scram time to drop out of Z N Notch 34 EN

_ iNi

= Adjusted analysis mean = + 1.65c i scram time EN 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 out of Notch 34 position of all rods measured in the ith surveillance test J.. = Mean of the distribution for average scram insertion time to drop out of Notch 34

= 0.937sec CT = Standard deviation of the distribution for average scram insertion time to dropout of Notch 34

= 0.021 sec REVISION 15B COLR PAGE 29 OF 37

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 is currently set at 32.5%.

Table 3.3-1 MCPR Operatinq Limits At Rated Power and Rated Flow The MCPR Operating Limit (OLMCPR) is a function of fuel type, exposure and t, derived from scram timing measurements GE11 Fuel GE14 Fuel from to BOC to (EOR-2) to BOC to (EOR-2)

(EOR-2) EQO (EOR-2) to EOC GWD/ST GWD/ST GWD/ST GWD/ST

<0.0 1.37 1.39 1.41 1.50 0.0 *0.1 1.38 1.40 1.42 1.52 0.1 <0.2 1.39 1.41 1.43 1.53 0.2 50.3 1.40 1.42 1.44 1.55 0.3 *0.4 1.41 1.43 1.45 1.57 0.4 *0.5 1.43 1.45 1.47 1.59 0.5 50.6 1.44 1.46 1.48 1.60 0.6 *0.7 1.45 1.47 1.49 1.62 0.7 *0.8 1.46 1.48 1.50 1.64 0.8 *0.9 1.47 1.49 1.51 1.65 0.9 51.0 1.48 1.50 1.52 1.67 BOC = Beginning Of Cycle 15 EOC = End Of Cycle 15 EOR = End Of Rated Power Operation At Rated Flow Note: Limits for other Out Of Service Conditions such as Turbine Bypass Valve OOS and Final Feedwater Temperature Reduction are in the Supplemental Reload Licensing Report (Reference 5.14)

REVISION 15B COLR PAGE 30 OF 37

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.3-1 Flow Dependent MCPR Limits (MCPR F) for both GE1 1 and GE14 fuels 1.8 For W(C) (% Rated Core Flow) x 30%/6 MCPR(P) e MAX(1.20, A(F) W(C) /100 + B(F))

Max Flow = 117.0 A(F) = -0.632 B(F) = 1.809 1.7 Max Flow = 112.0 A(F) = -0.602 B(F) = 1.747 Max Flow = 107.0 A(F) = -0.586 B(F) = 1.697 Max Flow = 102.5 A(F) = -0.571 B(F) = 1.655 1.6 N- I I MCPR(F) = (A(F)

  • W(C) /100 + B(F))

- -_ ' 2 1.5 'N C,

IL 0.

E 1.4 I

N

-- 102.5%

I N "41\

"I 107.01/6 N,

1.3 N - 112.0%

1 Nll- N, - 117.0'%

1.2 1.1 30 40 50 60 70 80 90 100 110 120 Core Flow (% Rated)

REVISION 15B COLR PAGE 31 OF 37

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.3-2 Power Dependent MCPR Limits (MCPRp) for both GEII and GE14 fuels Turbine Bypass Is Assumed Operable and Normal Feed Water Heating

- - - - OLMCPRp = 2.95 + 0.0333 (32.5% - P) when 25% 5 P5 Pbyass and Core flow >50%

3 - - - - P= %Power and Pbypass = 32.5%

OLMCPRp = 2.34 when 25% 5 P s Pbypass and Core flow S50%

P= %Power and Pbypass = 32.5% _ -

2.5 C!

C F.

2 h~~ - -__ _- _ _

1.5 Kp 1.0_0.00375(100%- P); Power> P bypass

_ I. P= %Power and Pbypass = 32.5%

25 35 45 55 65 75 85 95

%Power REVISION 15B COLR PAGE 32 OF 37

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 3.4 Power/Flow Relationship During Power Operation Reference Technical Specification: 3.11.D The power/flow relationship shall not exceed the limiting values shown on the Power/Flow Operating Map in Figure 3.4-1. The Power/Flow Map, Figure 3.4-1 is applicable to operation with Normal feedwater heating. Cycle 15 operation is not fully analyzed for reduced feedwater temperature.

Intentional operation within the Restricted Region is prohibited. The Restricted Region boundary as a function of aligned drive flow is as given in Figure 2.2 -1.

Note: The boundary of the Restricted Region is established by analysis in terms of thermal power and core flow as shown in Figure 3.4 - 1. The Restricted Region boundary is defined by the locus of APRM Rod Block setpoints as a function of the reactor recirculation flow as shown by Figure 2.2-1.

REVISION 15B COLR PAGE 33 OF 37

PILGRIM NUCL ' POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIGURE 3.4-1 PILGRIM POWERIFLOW MAP 0 5 10 15 20 25 30 35 48 *45 50 55 60 65 70 75 80 I

l , - ,.7 1-4 i t I I I ; II I . . . I I SCRAM CLAMP AT liSt 2400 2400 RI1Th- -TIBt LTh.7nl.

f1ht tt dtt tItI 4NttITrMt1tl'

[r-It.-l-IVIt.fl i ITr11 1-111l!tQI4,4-IIWIV.tti4Ti-l- DBLOCK CLAMP AT 1131lF-iŽY 2200 lt-Wtttl

+trtt it :11+/-1fV ttITtttrtfl-1- Art-rn *M-111 ~ri1:111T1It ,tt IBi [PIfT LCT-i -17C2htI

  • 2200 4It [ [i4 [llgt f Htt..t 11111 -T~~* 1 OPERATION LiHlUf ..441Tfl+/-h'-TF wIfl+4fl-i -1111+/-I1 ftf-f tW, - K-7rJ J I PR-f"IBarED I 2000 WtI ttvtMtt IV 4it +/-1 2000

-i i t-! Iit-TI Vt4t it 1 I 1 - 1 1T I Fl I F1Hf1r:H-T T I Ill II11T 1,- mB S E .l:!3.14:-F5HI

. I TTh11.fr TITi i iFR,\

-tiY.

I 1:1 ~1 4 itI I"1-l-tl.W-I Ii Er I!T 1 n11 '1.. It~t

. . t4. -_tJCI; .144

.I-I.~. I . .

___"14+1

4 Ii ImI:4t Xi4T-fM H 11Wrft'iir-'i-j-irifiT*tw atHI T fThiE AP$ I14 tIIIHT3-LWN-.m.

18w I___ + 1 I-I -F4F+ 44 J-F II-- -I-P -4 - I 44- -1 I II+S+ I I I l ii. 1 _I tfIJ I VA ---

IiI-j1 , 14 i. 1-=1-II .- - jl i --f ,- - 1800 4.t t1- wL4L '.1 F 4,r 11: I ff i 1-i ....

lil 14 "I',

t.4._

I if'L - _uii t-Iii t :tl' t! IAl111X14,11 J-r IA; g tv,

--. j,fli__

," iMD4W9AM_ 110-'WH ilb P41'J- I MM14F I .l~'HfY It ir.L ~7ij r:ir-t'3L16800 1800 1

jatII Jl AF3 Ftl +FEH I fit 1fl:4tT4i1I.19341:I41414T44 14-444-Pt 1 s1I- Ml-u

+Fi

........ t t. r ... +

1 I- -

tEf-.....

r _ _i-.

RCRAM 11. 1.8 hAsrAzA ntsimurtuu I1_

tttJ MOUT;OREO 1- A L

+F{+§-F+-l ,W-I-Ie;l.

I iP I$1t-tii --I tlM $[ .__- ftF] t; -HJ 4wtl-tt - ttl ULI o 1400 REGION 1 REGION I REGION ARY Icr CORE FLOW r r-'-

-1400 0 BOUNDARY IrI BOUNDARY M ']OUNDARY I-t REGION .. I -

a.

I t t I i fI ti i

+L4--44,

  1. -1M,1-1 FS!I-1 -rFF LMI I

tia~

N . T=-

F1 F

-},-# --utwi tmnItinsrt-n-ni ru -i +/-tt 4:j ff1tE j 1 1200 - fm -1200 C 14;4ŽPThfiT-hVHt [it 11 -IHt14 c

C u

1000 Pil t .tI-I t-yiI IL14+.1 Ti-iW-_n+'L_~~-j

? 1000w 0

U nonti ]- jj41tAM SCRAM - 800 iOif* :Lx i 4t -li^ 12fi8< i -l HAT OPERATION l IS -_ 600l 3SX,~~ ~~ -ltlR"APRAIH I PROMIBWTEN l tv

/'

600nn 1-l:S %S> -...

>.,.  ; 400 FI{--W14-VTT- ' 1441 ITT It-ITEI4Tif-i p_,4 1, ...... r, 'I P i-- ;l 2 F Rl FI i4Tfl MIN PUMP SPEED (26) 1:,l:144l :1 III 1114MT rT1474flhi-trI:

200

28. 8'k k a- F t ~q-j~+~ +- F I
Lt lIitLIIt0l -iftftiI'.Mjtf S+luT i jt[Th I .-.-J-jTfITW IfThTjfff# tF lIfl-HTh I

L44- - I. I .. I.. i I- 1l I 1Ji' 1Wl;E 1l'1-1 I l I 0 5 10 15 20 25 30 35 40 45 50 55 fi 65 70 75 80 CORE FLOW MLB11IR REVISION 15B COLR PAGE 34 OF 37

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 Tvpe Cycle Number Loaded Irradiated GE11 -P9DUB408-6G5.0/7G4.0-1 OOT-141 -T6 12 40 GE1 1-P9DUB408-16GZ-1 DOT-1 41 -T6 12 73 G E11 -P9DUB407-14GZ-1 DOT-1 41 -T6 13 119 GE 1-P9DUB408-6G5.0/7G4.0-1 DOT-1 41 -T6 13 40 GE1 4-P1 ODNAB412-1 6GZ-1 DOT-1 45-T6-3901 14 144 New b GE1 4-P 1ODNAB397- 1OG6.0/3G5.0- 1 OT-1 45-T6-2613 15 36 GE 14-P1 ODNAB397-14GZ-1 COT-1 45-T6-2621 15 88 GE1 4-P1 ODNAB398-8G6.0/5G5.0/1 G2.0-1 DOT-1 45-T6-2614 15 40 Total 580 The reactor vessel core contains 145 cruciform-shaped control rods. The control materials used are either boron carbide powder (B4 C) compacted to approximately 70% of the theoretical density or a combination of boron carbide powder and solid

. hafnium.

REVISION 15B COFR PAGE 35 OF 37

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIviTS REPORT RTYPE: G4.02 FIGURE 4.0-1 Reactor Vessel Core Loading Pattern 50 M 1E E-1l I W E m elD! Imn [EI IDM 48 Ej [ [E]IE [E] [ [E]L[ F1 [EE EC][FEJ FJ[E [E] 1EP 46 E 44OFM3p2 EEl[ O[1ln ml< 131 M0El In 42 03 Ei i51E [PO3[M E IIIEIWlE Iz MEIFIE 40 E [ [3 EgE [ E FgL[

[ID [E 1[E [f1 lB(I II E) E] JgE 38 [9I0 0IEl El [IPE]J M I0M[F ID19 rn 36 JE] [E En 21C[D [E][0 3 Eli I ElI IE 1[ ML [EE 340M ID31 19 0l B1E WE EISDI ElE E1E DEl[mi WOE 1[ § ED1 328 MJF [gff] [E]lFL[] FEJ rig MB E]IE] ED

[E [E] rEflEl EN1 D El[D] El] ED CM [IJ 24 26 EgM1 lmA I

mj1[El Lh [E FL Eul EuE EDT1 ElI Le  ;DE WIE Wo1 WEN -E1E l So te IOUPm [Elm Fl 228 rTq [TE~ TE][CDrEfl]E][ [E][E TE] [DE] [LE] TE] A LED EC] [D (LE]

DM CEI 22 18 Eg[SEl El[E

[Di[El M [0 MTE TE] TE] [LE] DM nFEMMR 3 C IE FMl~ 1 [3EJ]

3E l l I I3w l139 ElE El [El [Elm

[ElE E3 12 Mi9[i [El 3ED[3I[3P~ [D [El [EI[DD E In[CD[D MEJ (lE] [D C n

[E]E 18 4[l E m E lm m E [tl 12 [D[lEND EjEET~ ] 2]X1[ED {3AE] AE]9EGElT][CID ] Mi -F 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 Fuel Type A=GE1 l-P9DUB407-14GZ-10OT-141-T6 (Cycle 13) G=GEl 1-P9DUB408-16GZ-lOOT-141-T6 (Cycle 12)

B=GE1l-P9DUB408-6G5.O/7G4.0-IOOT-141-T6 (Cycle 13) H=GEIl-P9DUB408-6G5.0/7G4.0-lOOT-141-T6 (Cycle 12)

C=GE1 1-P9DUB407- 14GZ- lOOT-141 -T6 (Cycle 13) I=GE14-PlODNAB397-14GZ- lOOT-145-T6-2621 (Cycle 15)

D=GE11-P9DUB408-6G5.0/7G4.0-lOOT-141-T6 (Cycle 13) J=GE1 -P9DUB408-16GZ-0OOT-141-T6 (Cycle 12)

E=GE14-PI ODNAB412-16GZ- I OOT-145-T6-3901 (Cycle 14) K=GEl l-P9DUB408-6G5 .0/7G4.0-IOOT-141-T6 (Cycle 12)

F=GEI4-P lODNAB397- lOG6.0/3G5.0-IOOT-145-T6-2613 L-GE14-PIODNAB398-8G6.0/5G5.0/1 G2.0- lOOT- 145-T6-2614 (Cycle 15) (Cycle 15)

REVISION 15B COLR PAGE 36 OF 37

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. PDC 03-01, Cycle 15 Reload Core Design.

5.3. SUDDS/RF 02-61, NEDC-31852-P, rev. 2, "Pilgrim Nuclear Power Station SAFERIGESTR-LOCA Loss-of-Coolant Accident Analysis for GE1 1 and GE14 Fuels",

January 2003 5.4. SUDDS/RF 02-63, PNPS Cycle 15 Stability Region Boundary Validation Reports 5.5. SUDDS/RF 02-83 Cycle 15, Flow mapping inputs and outputs 5.6. SUDDS/RF 02-43, TPO power to flow map 5.7. SUDDS/RF 03-007 Calculation of CON1 61 constant for Cycle 15 stability Analysis 5.8. SUDDS/RF 94-42, NEDC-32306P, "Maximum Extended Load Line Limit Analyses",

March 1994.

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

5.10. SUDDS/RF 02-83, GENE-0000-0013-1555, Rev. 1, " Pilgrim Nuclear Power Station Reactor Stability Long-Term Solution Enhanced Option I-A Flow Mapping Application Output Cycle 15 Normal Feedwater Temperature Operating Range", February 2003.

5.11. SUDDS/RF 98-031, NEDO-32339-A, Revision 1, "Reactor Stability Long- Term Solution: Enhanced Option I-A," GENE, April 1998. b 5.12. SUDDS/RF 02-63, GE14 Reference Cycle for Stability Option ElA 5.13. SE-3397, Safety Evaluation for Cycle 15 Reload Core Design.

5.14. 0000-0008-6613SRLR, "Supplemental Reload Licensing Report, Reload 14, Cycle 15."

(SUDDSRF02-58) _

5.15. Calculation S&SA-174, Cycle 15 OPL-3, transient Analysis Inputs 5.16. SUDDS/RF 02-84, 0000-0008-6613FBIR, Rev.0, February 2003, Fuel Bundle Information Report, Cycle 15 5.17. SUDDS/RF 02-82, Cycle 15 SLMCPR Affidavit 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, Cycle 15 Accident Analysis Inputs 5.20. NEDO-32339-A Supplement 3, December 1996 5.21. GE-NE-0000-0033-7542-RO, "Pilgrim Cycle 15 GE14 MAPLHGRs with correction of Radiation Resistance Array error in SAFER, dated 10/-19/2004 5.22. 10 CFR 50.46 Notification letter 2004-01, dated September 24, 2004.

REVISION 15B COLR PAGE 37 OF 37

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