ML051320351

Core Operating Limits Report, Revision 16B

ML051320351
Person / Time
Site:	Pilgrim
Issue date:	05/05/2005
From:	Ford B Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2.05.036
Download: ML051320351 (40)

Text

Entergy Nuclear Operations, Inc.

"'En terIy Pilgrim Station 600 Rocky Hill Road Plymouth, MA 02360 May 5, 2005 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

SUBJECT:

Entergy Nuclear Operations, Inc.

Docket No.: 50-293 License No.: DPR-35 Core Operating Limits Report, Revision 16B LETTER NUMBER: 2.05.036

Dear Sir or Madam:

The enclosed revision of Pilgrim's Core Operating Limits Report (COLR) is submitted in accordance with the requirements of Pilgrim's Technical Specification 5.6.5. Revision 16B provides cycle-specific limits for operating Pilgrim during cycle 16 and replaces the previously submitted Revision 16A.

This letter contains no new commitments.

Should you require further information concerning COLR, Revision 16B, please contact me at (508) 830-8403.

Sincerely, Bryan S. Ford Licensing Manager WGULdm

Enclosure:

PNPS Core Operating Limits Report, Revision 16B cc: U.S. Nuclear Regulatory Commission Mr. John Boska, 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 Rockville, MD 20852 Senior Resident Inspector trAc 205036

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

APPROVED: /,- 67.,>- At..  :,E C-/9/

Gary James, Reactor Engineerirg;uperintendent Date APPROVED:

Rob'ert Smith, Nuc ear Engineering Director Dbte APPROVED:

Operations Review Comnrtee Date ORC Meeting # L0O5 -C69 APPROVED:

APPROVED:

APPROVED: V M. Balduzzi, Senia ice President - Operations Date REVISION 16B COLR PAGE 1 OF 39

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) ........................... 25 3.3 Minimum Critical Power Ratio (MCPR) ........................... 30 3.4 Power/Flow Relationship ........................... 35 4.0 REACTOR VESSEL CORE DESIGN . .37

5.0 REFERENCES

. .39 REVISION 16B COLR PAGE 2 OF 39

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 RECORD OF REVISIONS Revision Effective Date Description 8A Effective date based on issuance Applicable for use during Cycle 8 of license amendment by NRC Operation 9A Effective date based on issuance Applicable for use during Cycle 9 of license amendment by NRC for operation ARTS and SAFER/GESTR 10A Effective date based on initial Applicable for use during Cycle 10 startup of Cycle 10 Operation 11A Effective date based on initial Applicable for use during Cycle 11 startup of Cycle 11 Operation 11B Effective upon final approval Applicable for use during Cycle 11 Operation 11C Effective upon final approval Applicable for use during Cycle 11 Operation 11D Effective upon final approval Applicable for use during Cycle 11 Operation 12A Effective date based on Applicable for use during Cycle 12 issuance of license Operation amendment by NRC for SLMCPR of 1.08 12B Effective upon final Renumbered Table 3.3-2 approval to 3.3-1, Sh. 2of2and Table 3.3-1 to 3.3-1, Sh. 1 of 2 12C Effective upon final Changed Tech Spec section numbers approval referenced due to Tech Amendment

1. 177.

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

13A Effective upon final Applicable for use during Cycle 13 approval Operation 14A Effective upon final Applicable for use during Cycle 14 approval Operation 15A Effective upon final Applicable for use during Cycle 15 approval Operation 15B Effective upon final Changed MAPLHGR Limits for GE14 approval fuel in response to an input error GE corrected. Applicable for use during Cycle 15 Operation 16A Effective upon final Applicable for use during Cycle 16 approval Operation 16B Effective upon final Core Loading Change to replace leaking approval fuel bundle JLG621. Clarified P-F Map graphic on P. 36. Applicable for use during Cycle 16 Operation REVISION 16B COLR PAGE 3 OF 39

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 LIST OF TABLES Number Title Page 2.1-1 Formulae for APRM Flux Scram Trip Settings in Figure 2.1-1 7 2.2-1 Formulae for APRM Rod Block Trip Settings in Figure 2.2-1 10 3.1-1 MAPLHGR Limits For GE11 Fuel 13 At Rated Power and Rated Flow 3.1-2 MAPLHGR Limits For GE14 Fuel 15 At Rated Power and Rated Flow 3.3-1 MCPR Operating Limits- GE11 and GE14 Fuels At Rated 31 Power and Rated Flow LIST OF FIGURES Number Title Page 2.1-1 Nominal & Allowable APRM Flux Scram Trip Settings (Normal 8 Feed water Temperature) 2.2-1 Nominal & Allowable APRM Rod Block Trip Settings (Normal 11 Feed water Temperature) 3.1-1 Most Limiting Maximum Average Planar Linear Heat Generation 21 Rate (MAPLHGR) for GE1l1 Fuel 3.1-2 Most Limiting Maximum Average Planar Linear Heat Generation 22 Rate (MAPLHGR) for GE14 Fuel 3.1-3 Flow-Dependent MAPLHGR Factor (MAPFACF) for GE1l1 and 23 GE14 Fuels 3.1-4 Power-Dependent MAPHLGR Factor (MAPFACp) for GE11 and 24 GE14 Fuels 3.2-1 Maximum Linear Heat Generation 26 Rate (MLHGR) for GE1l1 Fuel 3.2-2 Maximum Linear Heat Generation 27 Rate (MLHGR) for GE14 Fuel 3.2-3 Flow-Dependent LHGR Factor (LHGRFACF) for GE1l1 and 28 GE14 Fuels 3.2-4 Power-Dependent LHGR Factor (LHGRFACp) for GE1l1 and 29 GE14 Fuels 3.3-1 Flow-Dependent MCPR Limits (MCPRF) for GE11 and GE14 32 Fuels 3.3-2 Power-Dependent MCPR Limits (MCPRp) for GE11 and GE14 32 Fuels, Turbine Bypass Assumed Operable 3.3-3 Power-Dependent MCPR Limits (MCPRp) for GE1l1 and GE14 . 34 Fuels, Turbine Bypass Out Of Service 3.4-1 Power/Flow Operating Map 36 4.0-1 Reactor Vessel Core Loading Pattern 38 REVISION 16B COLR PAGE 4 OF 39

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) 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) 3.1 1.C Power/Flow Relationship 3.11.D Reactor Vessel Core Design 4.2 If any of the core operating limits in this report is exceeded, actions will be taken as defined in the referenced Technical Specification.

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

1.1 Stability Option 1-D Exclusion Region and Buffer Zone.

The reactor shall not be intentionally operated within the Exclusion Region given in Figure 3.4-1. 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 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 16B COLR PAGE 5 OF 39

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) 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.

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.

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 corresponds to 100% Rated Core Flow of 69 M#/hr.

Source: Reference 5.6, sec. 2.1 REVISION 16B COLR PAGE 6 OF 39

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

C D0 ae SLOPE INTERCEPT  % Rated 0.20 71.5 0 < WD < 22.5 0.71 60.0 22.5 < WD

• 55.9 0.65 70.6 55.9 <W0 76 0120.0 76 < WD < 125 Notes:

1. ATSP=C*%WD+D, ATSP is in % Power

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

3. Reference 5.6, Table 1.a lists the values of constants listed in this Table.

REVISION 16B COLR PAGE 7 OF 39

C C PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIgure 2.1-1 Allowable APRMV Flux Scram Trip Settings 125.0 -------------------------- ----- I--- 1---1 --- I---I --- I---

IALLOWABLEVAL

---

---I---t2-- -r-120.0 -- - - - - - -- - -- - -- -

115.0 110.0 --- - --- - -- -- - -- --

5S 105.0

-, 100.0 ----------------

I-3.95.0 a - - -- - - - - - - -- -- - - --

o 90.0 85.0 --- ------ ------------- ---

-.--:::--j- TL0-AV-SCRA ----------- ----------

80.0 75.0 70.0 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

% Drive Flaw REVISION 166 COLR PAGE 8 OF 39

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, 3.11.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 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.

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

2.3 Rod Block Monitor Trip Setting

References:

Technical Specification Table 3.2.C-2, Ref. 5.15, Ref. 5.1 Table 4.5 (b)

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

Reactor Power, P Trip Set point

(% of Rated) (% of Reference Level)

P*25.9 Not applicable (All RBM Trips Bypassed) 25.9 < P < 62.0 120 62.0 < P < 82.0 115 82.0 < P 110 The allowable value for the RBM downscale trip set point shall be

• 94.0% of the reference level. The RBM downscale trip is bypassed for reactor power < 25.9%

of rated (Technical Specification Table 3.2.C-1, Note 5).

REVISION 16B COLR PAGE 9 OF 39

c C PILGRIM NUCLEAR POWER STATION C

PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 2.2-1 Formulae For Allowable APRM Rod Block Settings (Two Loop Operation)

APRM Rod Block Allowable Trip Set Drive Flow Range Point (ATSPRB)

C D Rae SLOPE INTERCEPT  % Rated 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 o 115.0 79.1 <BWD *125 Notes:

1. ATSP=C*%WD+D, ATSP is in % Power

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

3. Reference 5.6, Table 2.a lists the values of constants listed in this Table.

REVISION 16B COLR PAGE 10 OF 39

C C PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.2-1 Allowable APRM Flux Rod Block Trip Settings 120.0 0 _ _

110.0 - _ I_ - _

100.0 0

(U 10 0

90.0 0.

0 L-0 80.0-60.0 LI 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

% Drive Flow REVISION 16B COLR PAGE 11 OF 39

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 MAPLI'GR flow factor, MAPFACF, shown in Figure 3.1-3 for both GE1l1 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 GE11 and GE14 fuels) and the MAPLHGR limit for rated power and flow conditions, given in Tables 3.1-1 for GE1I 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 GE1l1 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.

REVISION 16B COLR PAGE 12 OF 39

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: GEll-P9DUB407-14GZ-100T-141-T6 Average Planar MAPLHGR Limit (kNV/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 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 16B COLR Page 13 of 39

I '- !e'. . - .I PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 Continued: Bundle Type: GE11-P9DUB408-6G5.0/7G4.0-10OT-141-T6 Average Planar i MAPLHGR Limit (kNV/ft)

Exposure GWd/MT (G\Vd/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) . 11A6 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 i1.43 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 16B COLR Page 14 of 39

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 MAPLHGR Lirnits for Rated Power and Rated Flow for GEI4'fuel Bundle Type: GE14-P I ODNAB399- 1OG6.0/3G5.0/1G2.0-1OOT-145-T6-2828 (GE 14C)

Average Planar MAPLHGR Limit (kV/ft)

Exposure Lattice Lattice Lattice Lattice Lattice Lattice GWd/MIT (GWd/ST) 6843 6844 6845 6846 6847 6848 0.00 ( 0.00) 9.80 8.79 8.76 8.74 10.21 10.89 0.22 (0.20) 9.71 8.86 8.84 8.82 10.16 10.86 1.10 ( 1.00) 9.50 8.96 8.96 8.95 10.01 10.78 2.20 (2.00) 9.44 9.10 9.13 9.12 9.98 10.77 3.31 (3.00) 9.45 9.23 9.31 9.31 10.01 10.80 4.41 (4.00) 9.49 9.31 9.50 9.50 10.05 10.84 5.51 (5.00) 9.53 9.40 9.60 9.64 10.10 10.89 6.61 (6.00) 9.57 9.48 9.70 9.74 10.15 10.92 7.72 (7.00) 9.61 9.57 9.79 9.84 10.18 10.95 8.82 (8.00) 9.64 9.65 9.89 9.94 10.21 10.97 9.92 (9.00) 9.66 9.74 9.98 10.03 10.24 10.99 11.02 (10.00) 9.68 9.82 10.07 10.12 10.25 11.00 12.13 (11.00) 9.69 9.91 10.17 10.22 10.27 11.01 13.23 (12.00) 9.67 9.97 10.26 10.32 10.27 11.01 14.33 (13.00) 9.64 10.02 10.34 10.40 10.24 11.01 15.43 (14.00) 9.60 10.08 10.40 10.47 10.20 10.97 15.99 (14.51) 9.58 10.11 10.43 10.49 10.18 10.95 16.53 (15.00) 9.56 10.14 10.45 10.51 10.16 10.93 18.74 (17.00) 9.48 10.21 10.50 10.56 10.07 10.84 22.05 (20.00) 9.35 10.27 10.54 10.59 9.94 10.71 23.01 (20.87) 9.28 10.27 10.55 10.60 9.89 10.68 27.56 (25.00) 8.95 10.25 10.58 10.63 9.66 10.51 32.19 (29.20) 8.40 9.94 10.26 10.32 9.11 10.05 33.07 (30.00) 8.30 9.88 10.20 10.26 9.01 9.97 38.58 (35.00) 7.65 9.48 9.72 9.72 8.37 9.33 44.09 (40.00) 7.02 9.03 9.19 9.20 7.73 8.69 49.60 (45.00) 6.38 8.51 8.66 8.67 7.10 8.06 54.79 (49.71) 3.98 - - - - --

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

60.63 (55.00) - 5.83 6.65 6.82 - 5.50 62.70 (56.88) - 4.87 - -- - -

62.74 (56.91) - - - - - 4.52 63.50 (57.61) _ 5.32 5.49 - -

64.36 (58.38) _ _ 4.92 - - _

64.70 (58.69) _ _ - 4.94 REVISION 16B COLR Page 15 of 39

• i. '. t PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 Continued: Bundle Type: GE14-PIODNAB398-8G6.0/5G5.0/2G4.0-10OT-145-T6-2829 (GE14C)

Average Planar MAPLHGR Limit (kW/ft)

Exposure _

GWd/ilT (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 -

- t REVISION 16B

- t COLR Page 16 of 39

. p.-.

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 Continued: Bundle Type: GE14-PIODNAB412-16GZ-1OOT-145-T6-3901 Average Planar Exposure MAPLI]GR Limit (kW/ft)

GWd/MT (GWdIST) Lat. Lat. Lat. Lat. Lat. Lat. Lat.

4820 4827 4828 4829 4830 4825 4831 0.00 (0.00) 9.80 8.78 8.57 8.72 8.62 10.21 10.98 0.22 (0.20) 9.71 8.81 8.61 8.76 8.70 10.16 10.95 1.10 (1.00) 9.50 8.87 8.68 8.85 8.79 10.01 10.86 2.20 (2.00) 9.44 8.97 8.80 8.98 8.93 9.98 10.84 3.31 (3;00) 9.45 9.08 8.92 9.12 9.07 10.01 10.86 4.41 (4.00) 9.49 9.20 9.05 9.24 9.19 10.05 10.88 5.51 (5.00) 9.53 9.32 9.17 9.36 9.31 10.10 10.91 6.61 (6.00) 9.57 9.42 9.28 9.48 9.44 10.14 10.94 7.72 (7.00) 9.61 9.52 9.39 9.60 9.58 10.18 10.96 8.82 (8.00) 9.64 9.62 9.51 9.73 9.72 10.21 10.98 9.92 (9.00) 9.66 9.72 9.62 9.87 9.87 10.24 10.99 11.02 (10.00) 9.68 9.82 9.74 10.01 10.02 10.25 11.00 12.13 (11.00) 9.69 9.92 9.86 10.16 10.18 10.26 11.00 13.23 (12.00) 9.67 9.99 9.93 10.25 10.28 10.27 11.00 14.33 (13.00) 9.64 10.04 10.00 10.32 10.34 10.23 11.00 15.43 (14.00) 9.60 10.08 10.05 10.35 10.37 10.19 10.96 15.99 (14.51) 9.58 10.09 10.07 10.36 10.38 10.17 10.94 16.53 (15.00) 9.56 10.10 10.08 10.37 10.38 10.15 10.92 18.74 (17.00) 9.48 10.11 10.11 10.37 10.38 10.07 10.83 22.05 (20.00) 9.35 10.11 10.12 10.36 10.37 9.94 10.70 23.01 (20.87) 9.28 10.09 10.10 10.35 10.35 9.89 10.66 27.56 (25.00) 8.95 10.01 10.00 10.28 10.25 9.66 10.49 32.19 (29.20) 8.40 9.65 9.65 9.92 9.94 9.11 10.04 33.07 (30.00) 8.30 9.58 9.58 9.85 9.87 9.01 9.95 38.58 (35.00) 7.65 9.15 9.15 9.42 9.40 8.36 9.31 44.09 (40.00) 7.02 8.70 8.70 8.97 8.92 7.73 8.68 49.60 (45.00) 6.38 8.22 8.21 8.49 8.46 7.09 8.05 54.78 (49.70) 3.98 - - _ _

55.12 (50.00) - 7.68 7.63 7.95 7.98 5.63 7.42 58.14 (52.75) _- - - - 4.21 --

60.63 (55.00) _ 5.21 5.16 5.89 5.96 - 5.46 61.32 (55.63) _ - 4.84 - - _ _

61.44 (55.74) - 4.84 _- -

62.67 (56.86) _- _ _ 4.51 62.81 (56.98) _ _ _ 4.90 --

62.91 (57.07) - 4.92 _ _

REVISION 16B COLR Page 17 of 39

- 1.' - -- -

i PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 Continued; Bundle Type: GE14-PlODNAB397-IOG6.0/3G5.0-10OT-145-T6-2613 Average Planar .IAPLHGR Limit (kW/ft)

Exposure GWd/MT (GU'd/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 _ _

I MEVISION Rib COLR Page 18 of 39

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 Continued: Bundle Type: GE14-PIODNAB397-14GZ-IOOT-145-T6-2621 Average Planar Exposure MAPLHGR Limit (kWlft)

GWd/MT (GWd/ST) Lat. Lat. Lat. Lat. Lat. Lat. Lat.

5841 5842 5843 5844 5845 5846 5847 0.00 (0.00) 9.80 8.66 8.76 8.73 8.72 10.21 10.94 0.22 ( 0.20) 9.71 8.73 8.82 8.80 8.79 10.16 10.91 1.10 (1.00) 9.50 8.84 8.93 8.92 8.92 10.01 10.81 2.20 (2.00) 9.44 8.99 9.07 9.09 9.09 9.98 10.79 3.31 (3.00) 9.45 9.14 9.20 9.26 9.27 10.01 10.81 4.41 (4.00) 9.49 9.24 9.27 9.43 9.46 10.05 10.83 5.51 (5.00) 9.53 9.33 9.34 9.51 9.56 10.10 10.87 6.61 (6.00) 9.57 9.41 9.41 9.59 9.64 10.14 10.89 7.72 (7.00) 9.61 9.50 9.49 9.67 9.72 10.18 10.92 8.82 ( 8.00) 9.64 9.58 9.57 9.75 9.80 10.21 10.94 9.92 (9.00) 9.66 9.67 9.65 9.85 9.90 10.24 10.95 11.02 (10.00) 9.68 9.75 9.73 9.97 10.02 10.25 10.96 12.13 (11.00) 9.69 9.84 9.83 10.10 10.16 10.26 10.96 13.23 (12.00) 9.67 9.90 9.91 10.21 10.28 10.27 10.96 14.33 (13.00) 9.64 9.97 9.99 10.30 10.37 10.23 10.96 15.43 (14.00) 9.60 10.03 10.05 10.36 10.44 10.19 10.92 15.99 (14.51) 9.58 10.06 10.08 10.39 10.46 10.17 10.90 16.53 (15.00) 9.56 10.09 10.11 10.41 10.48 10.15 10.88 18.74 (17.00) 9.48 10.18 10.19 10.46 10.53 10.07 10.79 22.05 (20.00) 9.35 10.25 10.25 10.50 10.57 9.94 10.66 23.01 (20.87) 9.28 10.24 10.25 10.51 10.57 9.89 10.62 27.56 (25.00) 8.95 10.22 10.23 10.53 10.61 9.66 10.45 32.19 (29.20) 8.40 9.91 9.92 10.23 10.29 9.11 9.99 33.07 (30.00) 8.30 9.86 9.86 10.17 10.23 9.01 9.90 38.58 (35.00) 7.65 9.46 9.46 9.70 9.70 8.36 9.26 44.09 (40.00) 7.02 9.01 9.01 9.17 9.18 7.73 8.63 49.60 (45.00) 6.38 8.50 8.50 8.64 8.65 7.09 7.99 54.78 (49.70) 3.98 - - -- - -

55.12 (50.00) - 7.92 7.92 8.10 8.12 5.63 7.36 58.14 (52.75) - - -- - - 4.21 _

60.63 (55.00) - 5.74 5.75 6.50 6.73 - 5.34 62.43 (56.64) - - - - - _ 4.50 62.52 (56.72) - 4.87 - _ _ _

62.53 (56.73) _ - 4.87 - - _

63.50 (57.61) _ _ - 5.17 5.40 64.06(58.11) _ _ _ 4.91 --

64.49 (58.51) _ _ _ 4.94 . -

REVISION 16B COLR Page 19 of 39

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/1G2.0-100T-145-T6-2614 Average Planar MAPLHGR Limit (kW/ft)

Exposure Lattice Lattice Lattice Lattice Lattice Lattice GWd/NIT (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 16B COLR Page 20 of 39

C C PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.1-1 Most Limiting MAPLHGR For Fuel Type GE11 12 l_ l l = = =_ - Note:

11.46 MAPLHGR limits used by 3D Monicore are

_____ ___- lattice specific and are listed in the Supplemental reload Licensing report. Most 11 ______ _______ B e - Limiting MAPLHGR limit in any lattice is shown _

in this figure as a function of lattice exposure.

10 9

8

===== = X7.81

7

, ==-nd<==A\5.

6 5

0 10 20 30 40 50 60 GWD/ST REVISION 16B COLR PAGE 21 OF 39

C C PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.1-2 Most limiting MAPLHGR For GE14 Fuel 10 t~mA 1 X~m-m.7 8

CD

-J 7 a.

_____MAPLHGR limits used by 3D Monicore are lattice specific and _________t~

_____are listed in Table 3.1-2 in the Supplemental reload Licensing __________,,v r eport. Most Limiting MAPLHGR limit in any lattice is shown in __________t l 6

_LI t his figure as a function of average planar exposure. Natural _- 1 lil_I I ,5.6111

,-Uranium lattices are excluded from this figure. Use tables for t ~ l-lll l l accurate calculations if necessary. lllh 1-1-11 l[ll 1 5

--- H - I , l lllll*

4 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35.0 40.0 45.0 50.0 55.0 GWDIST REVISION 16B COLR PAGE 22 OF 39

C C PILGRIM NUCLEAR POWER STATION C

PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.1-3 Flow Dependent MAPLHGR Factor (MAPFACF) for both GE1I and GE14 fuels 1.100 1.000 0.900 I*.

o 0.800

-j IL 0.700 0.600 0.500 4-30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 Core Flow %

REVISION 16B COLR PAGE 23 OF 39

c C PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.14 Power Dependent MAPLHGR Factors for GE11 and GE14 Fuel Note: These MAPFACp factors are valid for Turbine bypass In or out of service and for Normal & Reduced Faodwater heating 109 0.95 0.9 0.85 -

0.8 - . _

___ _ MAPFACpfor P Pbypass, For P. % power > Pbypass and 32.5% S Pbypass S 45%

0.75 - - - - -- - - -MAPFACp0.00191(P-90)*0.94,When32.5%4cPS90%

MAPFACp = 0.006 (P.100) + 1.0, when 90 % < P s 100 %

. 0.7 U 0.7 It 0.65-0.6 MAPFACp 0.557+ 0.00535 (P45) 0.6 - for Core Flow s 50%,YP S Pbypass, 32.5% S Pbypass s 45% _ _ = =

0.55 0.5 = # @ I I I_ =__=

MAPFACp = 0.537 + 0.00785 (P.45)

-4 I l for Core Flow > 50%. P s Pbypass. 32.5% S Pbyposs s 45%

0.45 I - 1 -

0.4 I . . I I I 1 - I l An q U.JJ I I I I I 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100

% Power REVISION 16B COLR PAGE 24 OF 39

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-dependent LHGR limit, LHGRR 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 GE11 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 16B COLR PAGE 25 OF 39

c C PILGRIM NUCLEAR POWER STATION

(

PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.2-1 Most Limiting LHGR Limit for GE1I Fuel At Rated Power and rated Core Flow 15 14 13 12

_ -_ _> < = or U02 Fuel Rods==

.11

• 10 a:

C, 8 . _ ~For Gadolinia \

_rods _

7

_ \

6 5

0 10 20 30 40 50 60 Exposure, GWD/ST REVISION 16B COLR PAGE 26 OF 39

c c PILGRIM NUCLEAR POWER STATION C

PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 REVISION 16B COLR PAGE 27 OF 39

C C 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 1.000 0.900 t 0.800 0

0.700 0.600 0.500 1-30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 Core Flow %

REVISION 16B COLR PAGE 28 OF 39

C C PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.2.4 Power Dependent LHGR Factors for GEll and GE14 FueI Note: These LIGRFACp factors are valid for Turbine bypass In or out of service and for Normal & Reduced Feedwater heating I r T I 7 7 -

0.95 4--I 4 t t 0.9 -I- 4- 4 I I--I- I--*--I I I 0.85 -* 4.I -- I t.-i _ II 0.8 LHGRFACp for P - Pbypass, For P. % power > Pbypass and 32.5% s Pbypass s 45%

0.75 LHGRFACp-0.00191 (P-90) + 0.94. When 32.5 % < P s 90%

0.

C.e 0.7 I T_1 I I I LHGRFACp n 0.006 (P-100) + 1.0. when 90 % c P5 100 %

I I 0 0.65

-j LHGRFACp -0.5574 0.00535 (P.45) 0.6 _ o Core

_ Flow s 50%. P sPbypass, 32.6% s Pbypass s 45%

0.55

r.- llez ==-__

0.5 I LHGRFACp - 0.537 + 0.00785 (P-45)

I_."

_ ' r

• 1 t Coro Flow > 50%, P:s Pbypass. 32.5% s Pbypass 545%

for 0.45 0.4 0.35 I__ ____ ____ _ _____

25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100

% Power REVISION 16B COLR PAGE 29 OF 39

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 PBypassl the power-dependent MCPR operating limit, MCPRp, is provided in Figure 3.3-2. For power level less than Pb ass 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 PBynass MCPRp 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 T for both GE11 and GE14 fuels.

Both Figures 3.3-2 and 3.2-3 include normal and reduced feed water temperature operating modes.

The value of Xin 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:

rave - To T =

1.252 -

Where:

ave = Average scram time to drop out of Nr Notch 34 n i-l TB = Adjusted analysis mean =+ 1.65a n scram time N.

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 Ti = Average scram time to drop out of Notch 34 position of all rods measured in the ith surveillance test pl = Mean of the distribution for average scram insertion time to drop out of Notch 34

= 0.937sec 6 = Standard deviation of the distribution for average scram insertion time to dropout of Notch 34

= 0.021 sec REVISION 16B COLR PAGE 30 OF 39

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

.. I 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 (OLMCPR) is a function of fuel type, exposure and t, derived from scram timing measurements GE11 GE14

-C BOC to (EOR-2)

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

GWD/ST (EOR-2) to EOC GWD/ST from to 0.0 0.0 1.39 1.41 1.44 1.49 0.0 0.1 1.40 1.43 1.45 1.51 0.1 0.2 1.42 1.44 1.46 1.53 0.2 0.3 1.43 1.45 1.47 1.54 0.3 0.4 1.44 1.46 1.48 1.56 0.4 0.5 1.45 1.47 1.49 1.58 0.5 0.6 1.46 1.48 1.51 1.59 0.6 0.7 1.47 1.49 1.52 1.61 0.7 0.8 1.48 1.50 1.53 1.63 0.8 0.9 1.49 1.51 1.54 1.65 0.9 1.0 1.50 1.52 1.55 1.66 BOC = Beginning Of Cycle EOC = End Of Cycle EOR = End Of Rated Power Operation At Rated Flow Note: Rated OLMCPR Limits for Turbine Bypass Valve OOS and Final Feedwater Temperature Reduction are the same as those for normal Feed water Temperature and Turbine bypass Valves in service, as OLMCPR is limited by the inadvertent HPCI injection event that is conservatively assumed to cause a Turbine Trip. Off rated MCPR limits are affected by TBVOOS condition and are shown in the off-rated limit curves in Figures 3.3-1, 3.3-2 and 3.3-3 and the Supplemental Reload Licensing Report (Reference 5.15).

REVISION 16B COLR PAGE 31 OF 39

C PILGRIM NUCLEAR POWER STATION c (.'

PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.3-1 Flow Dependent MCPR Limits (MCPR F)for both GE1l1 and GE14 fuels Flow Dependent MCPR Limits 1.700 1 02.5% max flo T-1-:4: ~i025mxlw MCPRF =Max ( 1.2, SLMCPR* (Af WTIIOO0 + Bf) /1.071 T-i -rII

-IL I -1 1% max flow

.IJ I-) Li %axlo  : Max Core Flow Af Bf 1.600 IILIIL: L'1~axlw-102.5 % -0.571 1.655

!T 107.0 % '-0.586 1.697 I-0  : .:::::I: 110.0 % -0.596 1.727 U 112.0 % -0.602 1.747 (U

IL 1.500 17.0 % -0621.809 a.

it Ca.

U 0

20 1.400 ~T l , 4  ; l r - - r1- -, r -~--r . r, - . , s  ? --- l.,r ,,r,1 CL 0

0 1.300 J. -4.4..L ~ 4 .l LA. . I-. L . -I- . . I- .. .. L8.. * .. .I..4. .. I 4.-1. I t- .4 .. 1L. LI-A J.. II . I.I4 I ..

I4.~ L... 4.4I.

U 4

4.44-I- . II .1 1 *4 4 .4 . 4 414 4,1- 4. 1 4 4 14 1 . 1 r r - r- - -r--- -'r- r r1 1 ,

1.200 1.100-30.0 35.0 40.0 45.0 50.0 55.0 60.0 65.0 70.0 75.0 80.0 85.0 90.0 95.0 100.0 Core Flow, % Of Rated REVISION 16B COLR PAGE 32 OF 39

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure .3.2 Power Dependent MCPR Lhnks (MCPRp) for both GE11 and GE14 fuels Turbine Bypass IsAssumed Operable and Normal and Reduced Feed Water Temperature C.

cc a.

25 35 45 55 65 75 es 95

% Powu REVISION 16B COLR PAGE 33 OF 39

I; .:  ;

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.3-3 Power Dependent MCPR Limits (MCPRp) for both GE11 & GE14 fuels Turbine Bypass Out of service & Reduced Feed Water Temperature 4.10 4.00 3.90 3.80 3.70 OLMCPRp = 2.5 + 0.08 (45- P) for; 3.60 Core flow > 50%, P= % Power and 3.50 25% S P S Pbypass,45 % 2 Pbypass 3.40 3.30 3.20 3.10

_ _ I TI S 3.00 OLMCPRp 2.01 - 0.0455 (45 - P) 2.90 _

-- Core flow < 50% and P= % Power a2 2.80 25% S P S Pbypass,45 % Pbypass 0- 2.70 5 2.60 o 2.50 o 2.40

'& 2.30 2.20

- - ZTZZZZZi= _

2.10 2.00 1.90 1.80 1.70 Kp = 1.0 +0.0041 (100 - P) for P > 80%

1.60 Kp = 1.082 + 0.036 (80 - P) for 80% > P 2 Pbypass 1.50 P= % Power and 45 % 2 Pbypass 232.5%

1.40 1.30 1.20 1.10 1.00 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100

% Power REVISION 16B COLR PAGE 34 OF 39

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 Two Loop Operation with either normal or reduced feed water temperature. Cycle 16 operation is not fully analyzed for reduced feedwater temperature for issues other than thermal limits. This report contains only the thermal limit analysis results for reduced feed water temperature mode. Cycle 16 is currently limited to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of operation while in Single Loop due to License condition 3.E.

Cycle 16 Stability analysis, the exclusion and the buffer regions shown in Figure 3.4-1 are based on Stability Solution l-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 Figure 2.1-1 and Figure 2.2 -1.

Figure 3.4-1 shows APRM Scram and Rod Block lines using Allowable values as a function of Core Flow. Equations for various lines on the Power to flow map are described in Ref. 5.14.

REVISION 16B COLR PAGE 35 OF 39

C- C PILGRIM NUCLEAR POWER STATION

(

PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.4-1 PILGRIM POWER / FLOW MAP Scram and Rod Block Data based on Allowable Values CORE FLOW, MLBfHR.

0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 ,75 80 125 1-I4-I *- ~- I:i+14 I.... ~ - -~-4A17 ~34 ,L 1:-!-I '.APMSR CL PAI 2434 120 - - - ' 41 -

4-FFF- V>4*-- MR-T -

115 2332

i. t-I -,71i lr m - I ~- -- ,Ii'~ft  :. -:-= ' nI........ ...

KI_-"

2231 110 105 2129 100 2028 u'.- 95 1927

• 90 1825 de -4 85 .1724 w

80 .1622 75 4- tt 44-+/-=:r P4 zl -2.I i 4 4-4-+/- ~ -~-- 4-4-#4- 4-4,4- 14.

• 1521.

70 - ~-~4-

-- 4.4-- 4~+/-4-, 4zt. ~4--CORE FLOW- 1420 4

0 .65 -"MP- 4~ 4~A~.-j-2 4 L 1318 ZI- *60 1217 0 W

Or 55 1115 8 I-

• 50 1014.

0 .45 w' 913

• 40 811 U.

ce 35 1--

I- -t --- _ I- -! i 710 a:.

0o 30 MINIMMRPOWRU-D 608 25 NTCIRC LINE 507 20 406 15 304 10 LINE MIN ~~~~~PUMP SPEED (2% z; z~:~:~~ -~--~ 203

.5

. I - TEBI- - ~  :+/-p~ i+/-t4-101 0 0 0 5 10 . 15 20 25 30'. 35 40 45  : 50 55 60 65 70 75 80 CORE FLOW, MLB/HR REVISION 16B COLR PAGE 36 OF 39

PILGRIM NUCLEAR PONER 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 Tyne Cycle Number Loaded Irradiated GE1 1-P9DUB407-14GZ-10OT-141-T6 13 89 GE11 -P9DUB408-6G5.0/7G4.0-10OT-141 -T6 13 24 GE14-Pl ODNAB412-16GZ-1 DOT-1 45-T6-3901 14 144 GE1 4-P1 ODNAB397-1 0G6.0/3G5.0-1 DOT-145-T6-2613 15 35 GEI 4-P1 ODNAB397-14GZ-1 DOT-1 45-T6-2621 15 88 GE1 4-P1 ODNAB398-8G6.0/5G5.0/1 G2.0-1 OOT-145-T6-2614 15 40 New GE1 4-P1 ODNAB398-8G6.0/5G5.0/2G4.0-1 DOT-145-T6-2829 16 56 (GE14C)

GE1 4-P1 ODNAB399-1 OG6.0/3G5.0/1 G2.0-1 DOT-1 45-T6-2828 (GE14C) 16 104 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.

During RF015, 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 16B COLR PAGE 37 OF 39

PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 52 Elm LL 50 mr mE[ff<mlm mMHE Mm m 48 - E EAff fDIE 1 EGMID E

[GE[]I_0! [Dfl [HEt DMfj ME 46 EE ENEE g[ 1 A 11 M

44 [-!C1j1E1 [G 1M E E[IE DM[f E M[f E1 [LEIE[HE1 1[f1E[Do [AI 42 ERim [am~

1IgE Fif 'PL gm E N mt~l m E1 mlm 40 Fcg [E f [EEFt If I[ ElE [ E1E E[BE 1 1GEEEE1ffg 38ImESE~lE0[El 400 ffll15E ElE El[EI F E IIE M~

36 ml u~ME! -Fl fLN PI ilm mEIE m- 1IERNI m1tioi [gum MES 34 m LRE _Lm Fl El I-EtG lL 30 [GE[

C ME E13DIlm Elm [G fB [IEl[ fl EH mE I f I[E [TG E fflEMtg1E 28 36 ff!

+1;[ E1 m [E MHE1 ,1 EMI El[ E Iffl

L M1E DI [BE [

26 NH 24 H1fD [lE [1f flIM(E1[E IEIM [1U3[ MII ff1E Mt SlG f Z~~~~[F M&m [flEin [ESH1 IoE TI~uE11

[eE M1 'eM M1M!1 20 -q [EI M [Ell E[E D [E DI [ MI ElE 18 mlE ![lE- mlE [FE lEM MME MIIul nflE MERTM IflS l m 16 CM fI f lEF EF D [flE I [B] [ELE F] fE flE ffJ E ELE M E EjIM I7C 14 ANEW mn-& M~f m&1 {mI:

• of~jC [Efl [HE! [fll [El fIE I-E11E f ffGE RE1 LEt [El [EIflC 1E 2 § 0 !1111 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 Typc A=GEllI-P9DUB408-6G5.0/7G4.0-l OOT-141-T6 (Cycle 13)

B=GE14-PlODNAB399-lOG6.0/3G5.0/lG2.0-l OOT-145-T6-2828 (Cycle 16)

C=GElII-P9DUB407-14GZ-I OOT-141-T6 (Cycle 13)

D=GE14-P IODNAB4 12-1 6GZ-IOOT-145-T6-3901 (Cycle 14)

E=GE14-PI ODNAB397-lOG6.0/3GS.O-I OOT-145-T6-2613 (Cycle 15)

F=GE 14-P 1ODNAB398-8G6.0/SGS.O/2G4.0- 1OOT-145-T6-2829 (Cycle 16)

G=GE14-PI ODNAB397- 14GZ-I OOT-145-T6-262 1 (Cycle 15)

H=GE14-P 1ODNAB398-8G6.0/SGS.O/1 G2.0-l OOT-145-T6-2614 (Cycle 5)

REVISION I16B COLR PAGE 38 OF 39

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 GE11 and GE14 Fuels", February 2005 5.4. NEDC-33155P, Rev.0, Application of Stability Long-Term Solution Option l-D To Pilgrim Nuclear Power Station, October 2004 5.5. GE-NE-0000-0035-9029-RO, Option l-D Reload Stability Analysis for Pilgrim Cycle 16 5.6. GE-NE-GENE-0000-0033-6871-01, Rev. 0, Pilgrim Option l-D APRM Flow Biased Set points, October 2004 5.7. GE-NE-0000-0027-5301, Pilgrim Nuclear Power Station Single Loop Operation, July 2004 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 l-D implementation 5.14. PNPS-RPT-03-00001, Rev.1, '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-1 88, 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 REVISION 16B COLR PAGE 39 OF 39