ML031400562
| ML031400562 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 05/13/2003 |
| From: | Riggs W Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2.03.076 | |
| Download: ML031400562 (38) | |
Text
{{#Wiki_filter:1~~~~~~'~~~~~Entergy~~~~~~~~~~~~~~~~~Pilgrim Entergy 600 Nuclear Hill RoadOperations, Station Rocky Inc. Plymouth, MA 02360 William J. Riggs Director, Nuclear Assessment May 13, 2003 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 15A LETTER NUMBER: 2.03.076
Dear Sir or Madam:
The attached 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 15A provides cycle-specific limits for operating Pilgrim during cycle 15. The core operating limits in COLR, Revision 15A, 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. Should you require further information concerning COLR, Revision 15A, please contact Bryan Ford (508) 830-8403. Sincerely, si`¢William J. Riggs
Attachment:
Pilgrim Power Station Core Operating Limits Report, Revision 15A cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Mr. Travis Tate, Project Manager Office of Nuclear Reactor Regulation Mail Stop: 0-8B-1 U. S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockville, MD 20852 Senior Resident Inspector 203076
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 (CYCLE 15) APPROVED: . j7 L L/ 2oe3 Reactor agirving Superintendent Date APPROVED: AN APPROVED: c. On-Site Safety Review Committee Date OSRC Meeting #: X 2?- APPROVED: _5 4a'< A PpeOaVions D:na APPROVED:\ APPROVED: Vice President - Operatifg Date REVISION 15A COLR PAGE 1 OF 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 TABLE OF CONTENTS Paae TITLE/SIGNATURE PAGE .................. 1 TABLE OF CONTENTS .............. . . 2 RECORD OF REVISIONS .............. . . 3 LIST OFTABLES ........... 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 Seting .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 15A COLR PAGE2 OF 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 RECORD OF REVISIONS Revision Effective Date Description BA 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 1OA 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 iC 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 REVISION 15A 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- GE11 Fuel 30 At RatedPower and Rated Flow LIST OF FIGURES Number Title Page 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 15A 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) 3.1 1.B Minimum Critical Power Ratio (MCPR) 3.1 1.C Power/Flow Relationship 3.1 1.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 15A 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 Ž TFw(rated)-50 0 F OR P < 30%, WhereTFw = rated equivalent Feedwater Temperature in F; P= Core Power, % of rated. When the mode switch is in the RUN position, the average power range monitor (APRM) flux scram trip setting (Ss), 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 = Wn1 00*(AD40) - WD40*(AD1 00) + AWD*WD1 AWD - AD1 00 + AD40 Where: WD100 = 100.319 (Ref: 5.10 Table 16) WD40 = 34.957 (Ref: 5.10 Table 16) AWD= WD1 00 - WD40 AD40 = Low flow drive flow alignment setting AD100 = High flow drive flow alignment setting WD1= FCTR card input drive flow in percent of rated WD= 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 F 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 < Tw(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. REVISION 15A COLR PAGE 6 OF 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: 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 Wd 18.669 41.2469 1.7257 0.3699 -6.1436 19.0656 18.669 <Wd < 34.865 P=A[
P=A + B XWD -644.1699 20.0695 34.865 < WD 35.817 P=A + BX 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_ 78.447 < WD 109.688 Notes:
- 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.
REVISION 15A COLR PAGE 7 OF 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.1-1 Nominal and allowable APRM Flux Scram Trip Settings 130 b~~ ~ ~ ~~~~~ -- - 120 110 100 90 0) co 80 4-70 - - - - -- RS
---- oW- - -- - - Nominal
- 0) = =-, = =Allowable 0 60 0:
0 IL 0 50 00_. 40 30 20 10 0 0 10 20 30 40 50 60 70 80 90 100 110 Aligned Drive Flow, (% Rated) REVISION 15A 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, 3.13.B.1
- a. Normal Feedwater Heating or Low Thermal Reactor Power:
TFW 2 Trw(rated)-50'F OR P < 30% Where TFW = rated equivalent Feedwater Temperature. F & 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. SRB 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 Settina 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 15A COLR PAGE 9 OF 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 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 <WDC 18.669
[ 32.0 2.5918 -0.0718 -1.0956 5.6374 18.669 <WD< 34.876 c+D WD )+WE - D)2 32.0 2.5918 -0.0928 -0.7999 4.9601 34.876 <WD< 51.488 P = AXB- 100) 100) 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<WDl109.237 Notes:
- 1. SRB iSthe APRM Rod Block Trip Setting in % 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 15A COLR PAGE 10 OF 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 2.2-1 Nominal & Allowable APRM Rod Block Trip Settings 140 120 100
* --- --- - -- -oo*t---- ---------
V co (U 80
- - -Nominal C)
- ---- - -- - - - - - Alo- a-Ible 0 0 EL 60
_________zz__ - -~-- IIIII= 0 C.) ___==_/,==_==___ 5 40 .- . 71___ zill ___ 20 0 0 20 40 60 80 100 120 Aligned Drive Flow (% Rated) REVISION 15A 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 MAPLHGR 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 GE11 fuel or Table 3.1-2 for GE14 fuel, which are obtained from the Supplemental Reload Licensing Report (Ref. 5.14). 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 15A 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 GE1 1 fuel Bundle Type: GE1 1-P9DJB407-14GZ-lOOT-141-T6 Average Planar Exposure MAPLHGR Limit (kW/ft) 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 15A COLR Page 13 of 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 Continued: Bundle Type: GE11-P9DUB408-6G5.O/7G4.0-10OT-141-T6 Average Planar Exposure MAPLHGR Limit (kW/ft) GWd/MT (GWdlST) Lattice 4324 Lattice 4325 Lattice 4326 Lattice 4327 0.00 (0.00) 11.43 10.59 10.57 12.01 0.22 (0.20) 11.37 10.64 10.61 11.98 1.10 (1.00) 11.20 10.73 10.70 11.88 2.20 (2.00) 11.16 10.83 10.82 11.88 3.31 (3.00) 11.19 10.94 10.95 11.92 4.41 (4.00) 11.24 11.06 11.08 11.97 5.51 (5.00) 11.30 11.17 11.22 12.03 6.61 (6.00) 11.35 11.29 11.36 12.07 7.72 (7.00) 11.39 11.41 11.51 12.11 8.82 ( 8.00) 11.42 11.53 11.66 12.14 9.92 (9.00) 11.45 11.65 11.83 12.16 11.02 (10.00) 11.46 11.77 11.99 12.18 12.13 (11.00) 11.47 11.88 12.13 12.19 13.23 (12.00) 11.42 11.94 12.21 12.17 14.33 (13.00) 11.38 11.98 12.25 12.12 14.59 (13.24) 11.36 11.99 12.26 12.11 15.43 (14.00) 11.32 12.01 12.27 12.07 16.53 (15.00) 11.27 12.03 12.27 12.01 18.74 (17.00) 11.15 12.02 12.19 11.89 22.05 (20.00) 10.98 11.98 12.02 11.71 27.56 (25.00) 10.69 11.92 11.76 11.43 33.07 (30.00) 10.16 11.71 11.56 11.09 36.76 (33.35) 9.63 11.28 11.33 10.56 38.58 (35.00) 9.37 11.07 11.22 10.30 44.09 (40.00) 8.59 10.33 10.56 9.52 49.60 (45.00) 7.81 9.60 9.83 8.75 55.12 (50.00) 6.29 8.88 9.13 7.94 57.76 (52.40) 5.36 - -- 60.63 (55.00) -- 7.67 8.09 6.01 61.57 (55.85) - - 5.68 62.50 (56.70) 7.04 7.46 65.09 (59.05) 6.16 -- 65.90 (59.78) 6.31 REVISION 15A COLR Page 14 of 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-1 Continued: Bundle Type: GE11-P9DUB408-16GZ-100T-141-T6 Average Planar Exposure MAPLHGR Limit (kW/ft) For Lattice Number GWd/MT (GWd/ST) 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 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 15A COLR Page 15 of 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 MAPLHGR Limits for Rated Power and Rated Flow for GE14 fuel Bundle Type: GE14-PlODNAB412-16GZ-IOOT-145-T6-3901 Average Planar Exposure MAPLHGR Limit (kNV/ft) for Lattice Number GWd/IT (GWd/ST) 4820 4827 4828 4829 4830 4825 4831 0.00 (0.00) 10.36 9.29 9.07 9.22 9.12 10.80 11.61 0.22 (0.20) 10.27 9.31 9.11 9.26 9.20 10.74 11.58 1.10 ( 1.00) 10.05 9.38 9.19 9.36 9.30 10.59 11.49 2.20 (2.00) 9.98 9.49 9.31 9.50 9.44 10.56 11.47 3.31 (3.00) 10.00 9.61 9.44 9.65 9.59 10.59 11.48 4.41 (4.00) 10.04 9.73 9.57 9.77 9.72 10.63 11.51 5.51 (5.00) 10.08 9.86 9.70 9.90 9.85 10.68 11.54 6.61 (6.00) 10.12 9.97 9.82 10.03 9.99 10.73 11.57 7.72 (7.00) 10.16 10.07 9.94 10.16 10.13 10.77 11.60 8.82 ( 8.00) 10.19 10.17 10.06 10.30 10.28 10.80 11.61 9.92 (9.00) 10.22 10.28 10.18 10.44 10.44 10.83 11.63 11.02 (10.00) 10.24 10.39 10.30 10.59 10.60 10.85 11.64 12.13 (11.00) 10.25 10.50 10.42 10.75 10.77 10.86 11.64 13.23 (12.00) 10.21 .10.54 10.48 10.83 10.85 10.86 11.64 14.33 (13.00) 10.15 10.57 10.52 10.87 10.89 10.80 11.64 15.43 (14.00) 10.08 10.58 10.55 10.88 10.89 10.73 11.57 15.99 (14.51) 10.04 10.58 10.55 10.87 10.89 10.69 11.53 16.53 (15.00) 10.01 10.57 10.56 10.86 10.88 10.66 11.49 18.74 (17.00) 9.86 10.53 10.53 10.81 10.82 10.51 11.34 22.05 (20.00) 9.61 10.43 10.43 10.71 10.72 10.28 11.12 27.44 (24.89) 8.96 10.02 10.01 10.29 10.31 9.67 10.61 27.56 (25.00) 8.95 10.01 10.00 10.28 10.30 9.66 10.60 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) l 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 15A 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-PIODNAB397-OG6.013G5.0-lOOT-145-T6-2613 Average Planar Exposure MAPLHGR Limit (kW/ft) for Lattice Number GWd/MT (GWd/ST) 5841 5848 5849 5850 5846 5851 0.00 (0.00) 10.36 9.26 9.22 9.22 10.80 11.50 0.22 (0.20) 10.27 9.32 9.29 9.29 10.74 11.46 1.10 (1.00) 10.05 9.43 9.42 9.42 10.59 11.36 2.20 (2.00) 9.98 9.58 9.60 9.60 10.56 11.33 3.31 (3.00) 10.00 9.73 9.78 9.79 10.59 11.35 4.41 (4.00) 10.04 9.84 9.97 9.98 10.63 11.38 5.51 (5.00) 10.08 9.92 10.11 10.17 10.68 11.42 6.61 (6.00) 10.12 10.00 10.20 10.27 10.73 11.45 7.72 (7.00) 10.16 10.09 10.30 10.36 10.77 11.48 8.82 (8.00) 10.19 10.17 10.39 10.46 10.80 11.50 9.92 ( 9.00) 10.22 10.26 10.49 10.56 10.83 11.51 11.02 (10.00) 10.24 10.35 10.59 10.66 10.85 11.52 12.13 (11.00) 10.25 10.44- 10.70 10.77 10.86 11.53 13.23 (12.00) 10.21 10.48 10.78 10.86 10.86 11.53 14.33 (13.00) 10.15 10.51 10.84 10.92 10.80 11.52 15.43 (14.00) 10.08 10.55 10.88 10.96 10.73 11.45 15.99 (14.51) 10.04 10.56 10.89 10.97 10.69 11.41 16.53 (15.00) 10.01 10.58 10.90 10.98 10.66 11.38 18.74 (17.00) 9.86 10.60 10.89 10.97 10.51 11.23 22.05 (20.00) 9.61 10.58 10.85 10.92 10.28 11.00 27.44 (24.89) 8.96 10.23 10.53 10.60 9.67 10.48 27.56 (25.00) 8.95 10.22 10.52 10.60 9.66 10.46 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 -- -- -- 63.49 (57.60) -- 5.18 5.42 64.09 (58.14) - 4.91 -- 64.53 (58.54) -- 4.94 _ REVISION 15A COLR Page 17 of 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Table 3.1-2 Continued: Bndle Type: GE14-PIODNAB397-14GZ-10OT-145-T6-2621 Average Planar Exposire MAPLHGR Limit (kWlft) for Lattice Number GWd/MT (GWd/ST) 5841 5842 5843 5844 5845 5846 5847 0.00 (0.00) 10.36 9.16 9.27 9.23 9.23 10.80 11.57 0.22 (0.20) 10.27 9.23 9.33 9.30 9.30 10.74 11.54 1.10 ( 1.00) 10.05 9.35 9.44 9.43 9.43 10.59 11.44 2.20 (2.00) 9.98 9.51 9.59 9.61 9.62 10.56 11.41 3.31 (3.00) 10.00 9.67 9.73 9.80 9.81 10.59 11.A3 4.41 (4.00) 10.04 9.78 9.80 9.98 10.01 10.63 11.46 5.51 (5.00) 10.08 9.87 9.88 10.06 10.12 10.68 11.49 6.61 (6.00) 10.12 9.96 9.96 10.14 10.20 10.73 11.52 7.72 (7.00) 10.16 10.05 10.04 10.23 10.28 10.77 11.55 8.82 (8.00) 10.19 10.14 10.12 10.32 10.37 10.80 11.57 9.92 (9.00) 10.22 10.23 10.20 10.42 10.47 10.83 11.58 11.02 (10.00) 10.24 10.32 10.30 10.54 10.60 10.85 11.59 12.13 (11.00) 10.25 10.41 10.40 10.68 10.75 10.86 11.60 13.23 (12.00) 10.21 10.45 10.46 10.78 10.86 10.86 11.60 14.33 (13.00) 10.15 10.49 10.51 10.85 10.93 10.80 11.59 15.43 (14.00) 10.08 10.53 10.56 10.89 10.97 10.73 11.52 15.99 (14.51) 10.04 10.55 10.57 10.90 10.98 10.69 11.49 16.53 (15.00) 10.01 10.57 10.59 10.91 10.99 10.66 11.45 18.74 (17.00) 9.86 10.60 10.61 10.91 10.98 10.51 11.30 22.05 (20.00) 9.61 10.58 10.58 10.86 10.93 10.28 11.08 27.44 (24.89) 8.96 10.23 10.24 10.54 10.61 9.67 10.56 27.56 (25.00) 8.95 10.22 10.23 10.53 10.61 9.66 10.55 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 - -- 63.49 (57.60) - 5.17 5.40 64.06 (58.11) _ 4.91 -- 64.49 (58.51) - 4.94 _ REVISION 15A 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/lG2.0O100T-145-T6-2614 Average Planar Exposure MAPLHGR Limit (kW/ft) for Lattice # GWd1MT (GWdlST) 5841 5852 5853 5854 5846 5855 0.00(0.00) 10.36 9.28 9.25 9.24 10.80 11.56 0.22 (0.20) 10.27 9.34 9.32 9.31 10.74 11.53 1.10( 1.00) 10.05 9.46 9.46 9.45 10.59 11.42 2.20 (2.00) 9.98 9.60 9.65 9.64 10.56 11.40 3.31 (3.00) 10.00 9.69 9.84 9.85 10.59 11.42 4.41 (4.00) 10.04 9.78 9.96 10.02 10.63 11.45 5.51 (5.00) 10.08 9.88 10.06 10.12 10.68 11.48 6.61 (6.00) 10.12 9.97 10.16 10.22 10.73 11.51 7.72 (7.00) 10.16 10.06 10.26 10.32 10.77 11.54 8.82 ( 8.00) 10.19 10.15 10.36 10.42 10.80 11.56 9.92 ( 9.00) 10.22 10.24 10.47 10.52 10.83 11.57 11.02 (10.00) 10.24 10.34 10.59 10.65 10.85 11.58 12.13 (11.00) 10.25 10.44 10.72 10.78 10.86 11.59 13.23 (12.00) 10.21 10.49 10.81 10.88 10.86 11.59 14.33 (13.00) 10.15 10.53 10.86 10.94 10.80 11.58 15.43 (14.00) 10.08 10.57 10.90 10.98 10.73 11.51 15.99 (14.51) 10.04 10.59 10.91 10.99 10.69 11.47 16.53 (15.00) 10.01 10.60 10.92 11.00 10.66 11.44 18.74 (17.00) 9.86 10.62 10.92 10.99 10.51 11.29 22.05 (20.00) 9.61 10.59 10.87 10.94 10.28 11.06 27.44 (24.89) 8.96 10.25 10.55 10.63 9.67 10.55 27.56 (25.00) 8.95 10.24 10.54 10.62 9.66 10.54 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 -- -- -- 63.49 (57.60) -- 5.20 5.44 _ 64.13 (58.17) 4.91 -- 64.56 (58.57) 4.94 REVISION 15A COLR Page 19 of 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIGURE 3.1-1 Most Limiting MAPLHGR FOR GE11 Fuel Type 13 -...- -. ...-I l l
- 1- -:.
t l I---.I-ti-i . t 7:
.- l.---.
I 12
.- -..I-..... .....
-__ w.._ .. -
l--t1-Ie---- I--- -- --t
- -f-t
-t--
I
.~.... I
.. I lQ
. l .vc J.1 1.95
-I - -4i
- t::-I....
-11.,
1-7 7 ,' I, I
.. ,,4-..
l.-- ---- I--- --- - -fl-i- ;
. t t: I..-.-
. . I I--. . -.
I
':: 1
- I:::t 11 H1-121-1: -
. . . . . .': I § I ' ' !
I ......
-- I...
[-I.. ....-- -I.. I __
,- 10.93 I
[__,1--- I61-,L A 3 -H
---t--1+-- 1t f--- --I---
2J- 1: I 11.22-I _- I., --
.I1-I....
I .--1 - - :: 1 ::-: -:-[ 1--F §-. -I -§-- '- -i --4 .i-..: i . I ....i i ....I I I.-i I1... 11
. __S +_ -10 .80:
4.
=t-;> -_s__.4 F]=- -
-i-+ I -- t- I -tt-t I- - -:-t -:
I I - -I "-4:...t f-t-f-t-t-t-§-t-+---- I.--
- 0 i 1:
I1 I I 1-.' I-. --
-1 0.26: 10.04-.
E 10 I-1i1 I..
- 9.291
- 1. t L,.
d: - t1----t--1-4I---1-------!---l--l--- 1- I,1-9 1j1j-G
-J 0.
t .'-..4..
- .t: .: : t :: F:::.1- -:,
= ,8 _.5 E
*~~~~~~~~
- I .. = . ll..
__.5
- .:: I-8 I I . . I . I . . I . - .- . -
_._-t_-t-i-l-:vrt----F-4-:Il L . ; . I .
-: t- -t:-: -:l.~.~j::l::VI ~-:l - I=--J:tI:tl: .- I
__.._44_+ __+/- = . t242... K ,7.4.: ~ ;.I _ _ Note: - .1 I4 I I
- MAPLHGR Limits used by 3D-Monicore are lattice specific and - . .i... ...-I ... 1 I - [- - E W X -i-..,,.". I..
7- . are listed in Table 3.1-1 as provided in the SRLR. The most
- limiting MAPLHGR of all GEI I fuel bundle lattices as a function
- t. I :::: I.:-:
...... _. : I . : .
- -::: of planar average exposure is shown in this figure for illustrative .6 1 ....: :
.- -.....- I ..-. 1 - T-- .I}-Tr-,,t_
- -' .- . ::1:::-:-::
6 - u purposes. 3-- t-i4-4 ilz:1 I f741 .--4 --,---4---I-+--4l 14 jI---i- -.. - I - I-:VI:V-c-j......-...... 1.... 1+
........ -H--l ::-
- :1' .I I.j . .
1- t
.I.; .-: t1 ii 5 Ir 1- I 1._iL, . ',
0 5 10 15 20 25 30 35 40 45 50 55 60 65 Planar Average Exposure (GWD/ST) REVISION 15A COLR PAGE 20 OF 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIGURE 3.1-2 Most Limiting MAPLHGR FOR GE14 Fuel Type 13 12 t--+
-t EF=I :.r-I-
11: ex
.zJ::z.z IU.bt 3t O :='::: I--f-:i- - A-
.I1iI I
I u.
.,,,.t 10: S -- 9F7 ) .t--
t-d- ,9.66 1-9 -1<V 9.07
=F :I-:i : ...:-.-:-..::::::
- - . .: I.... .. : : --: -:t:::. ::::::
I 8 r_ _i1-*- i L..-t=.. t- . ~tl I- --.......
- ; I il
-J w~~~~~~~~~~.v _ ..-_
I 7 _ _4-^---*---t---~ ~~ 6 Note: It ---
..-i---r ~~
.. ___ s= ._.' _ L _+_. ... .. _...._ ._... ....
MAPLHGR Limits used by 3D-Monicore are lattice specific and . ,:r._, ,_ _ ,_ = = = ._ = _I are listed in Table 3.1-2 as provided in the SRLR. The most 5 limiting MAPLHGR of all GE14 fuel bundle lattices as a function of planar average exposure is shown in this figure for illustrative purposes. 4 * . fi -t-
-- -1 71
- .. .-.. I .
f:-1.
+=.. 1..-
3 0 5 10 15 20 25 30 35 40 45 50 55 60 Planar Average Exposure (GWD/ST) REVISION 15A COLR PAGE 21 OF 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.1-3 Flow Dependent MAPLHGR Factor (MAPFACF) for both GE11 and GE14 fuels 1.100 i . I . . . . . l i. . . I I . . . . . . . . . . . . N
. . . . . . . . I . . . . . . 102.5% max I I I I I I I I I I_ core flow 1 T 1 1 1 T 1 I T 1 1 1 =
=4=
1.000
= I I I I N 107% max I I I I I I I II core flow ) I Ir rI I I- -O - 1
_ . . _ - I I - z - , I- - _._ I I . N- 0- . I I I I \1 I -ol 1 I 1 _ - I _ - .- I I. 0.900 \ I I max core flow 1..
. 1.-1;r 1~;t 41 = = I 1 = 1= It I=
0 117A=nY1 I - core flow l zz" -
- - - _ I
- I 1
t
- - -tI --
I .
-4I I
MAPLHGRf =MAPLHGRFACf *MAPLHGRstd I I I I
. I I
I . I I
+ 4-I 0.800
-- - - - - l - MAPLHGRstd = MAPLHGR rated power & flow a.
I- - MAPLHrAGRFAC-102.5%
- o =mn(1.0 mi or 0.4861 + 0.6784 (WT/100) 0.700
- - _-A - -----iIIII IMAPLHGRFAC-107%
- - 0 l I I I l l l l - - l l - =min(1.0rO.4574+0.6758 (WT/100) 0.600 I I- Iii I I I I I I II I MAPLHGRFAC-1 12%
P, l l l l l l l l l l l l- =min(1.0 or 0.4214 + 0.6807 (WT/100) l l l l l- l l l l l l l l l l- l lMAPLHGRFAC-117% l l- l l l l l l l l - - l- l - ll- min(1.0 or 0.3828 + 0.6886 (WT/100) 0.500 I I I I I I I I I I I I I I I I 1- 1'I 1- 'I '
- 30. 0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 Core Flow %
REVISION 15A COLR PAGE 22 OF 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIgure 3.1-4 Power Dependent MAPLHGR Factors for GEl Iand GE14 Fuel MAPFACp for P > Pbypass, I Turbine bypass is operable and Normal Feedwater Heating 0.95 32.5 % < P ! 70 % , MAPFACp=0.00408
- P + 0.6364 70 % < P 90 %, MAPFACp = 0.001
- P + 0.852 90 % < P 100 %, MAPFACp = 0.0058 1 + 0.42 0.85 0.75 _L i
cL
< 0.65 0.55 a
0.45 0.35 25 35 45 55 65 75 85 95
% Power REVISION 15A 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: 3.11.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 5.16. 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, LH 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 GE1 1 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 15A COLR PAGE 24 OF 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.2-1 LHGR Limit for GEll Fuel At Rated Power and rated Core Flow 15 14 13 E 11 E 10 I3 I
-J 9 8
7 6 5 0 10 20 30 40 .... 50 60 Exposure, GWD/ST REVISION 15A COLR PAGE.25 OF 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.2-2 LHGR for GE14 Fuel At Rated Power and rated Core Flow 14 13 12 111ForU02Fue T1 Rods J 10
. 9 E 8 - --- ForO dRod dRd -to 0 -
-J 7
-J 6
5 4 0 10 20 30 40 50 60 70 Exposure, GWDIST - REVISION 15A COLR PAGE 26 OF 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.2-3 Flow Dependent LHGR Factor (LHGRFACF) for both GE11 and GE14 fuels 1.100 u cc D
-j 0.500 4-30.0 40.0 50.0 60.0 70.0 60.0 90.0 100.0 Care Flow %
REVISION 15A COLR PAGE 27 OF 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 Figure 3.2-4 Power Dependent LHGR Factors for GE11 and GE1 4 Fuel LHGRFACp for P > Pbypass, Turbine bypass is operable and Normal Feedwater Heating 0.95 - 32.5 % < P c 70%, LHGRFACp=0.00408
- P + 0.6364 70 % < P 90 %, LHGRFACp = 0.001
- P + 0.852 I I I _
\ S c _ _ _ ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~. __,
4_ 90 % < P c 100 %, LHGRFACp = 0.0058 *P + 0.42 n or _ U.AU
- _.1 _ _ _ _
r> r t - l l l r- l-fl LHGRFACp for P > Pbypass, Turbine bypass inoperable and lFeedwater Temperature Reduction of up to 75 F is assumed iU- _ _ l[ % t P l < } c l 90% l LHGRFACp = 0.9 + 0.004 * (P-90)
- 32.5
_ _ 90% _ .<P_c_100% _ l l LHGRFACp l 1.0 l l l l = -t +0.01 * (P-100)
= 0.65 0.55 LHGRFACp =0.49+ 0.00533 (P-32.5) ll l - l l _
0.45 __ _ _ for Core Flow > 50%a nd P5 Pbypass of 32.5% 1111 0.35 25 35 45 55 75 85
% Power REVISION 15A 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 ass, the power-dependent MCPR operating limit, MCPRp, is provided in Figure 3.3-2 for noYa7 Feedwater Temperature. Above P vnassi MCPRp is the product of the rated power and flow MCPR operating limit presented in afe 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 GE1 1 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, GEll 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: 1.252 -r; Where:
- n
'ave = Average scram time to drop out of Notch 34 =
EN f=l TB = Adjusted analysis mean u + 1.65or Ni scram time EN, f=l 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
- p. = Mean of the distribution for average scram insertion time to drop out of Notch 34
= 0.937 sec 6 = Standard deviation of the distribution for average scram insertion time to dropout of Notch 34
= 0.021 sec REVISION 15A 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 Operating Limits At Rated Power and Rated Flow The MCPR Operating Limit (OLMCPR) is a function of fuel type, exposure and , derived from scram timing measurements GE11 Fuel GE14 Fuel from to BOC to (EOR-2) to BOC to (EOR-2) (EOR-2) EOC (EOR-2) to EOC GWD/ST GWD/ST GWD/ST GWD/ST S0.0 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 *0.3 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 *0.6 1.44 1.46 1.48 1.60 0.6 S0.7 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 <1.0 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 15A 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) > 30%/ MCPR(F) = MAX(1.20, A(F) W(C) 1100 +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 I I -- L MCPR(F) = (A(F) W(C) /100 +B(F))
- a- Nfl *- .- .r 1.5 0.
C-EL 1.4 1.3
.~~ \\ % <1 ~
\N 107.0%
~ ~ ~~~~~~~~~~~~~ . fo.
1.2 112.0%~~~~~~~~~~~~~~ 1.1 30 40 50 60 70 80 90 100 110 120 Core Flow (% Rated) REVISION 15A 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 GE11 and GE14 fuels Turbine Bypass Is Assumed Operable and Normal Feed Water Heating Kp or OL M CP Rp 25 35 45 55 65 75 85 95
%Power REVISION 15A 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 15A COLR PAGE 33 OF 37
PILGRIM NUCLEAR 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 40 45 50 55 60 65 70 75 80 2400
-------- ~ ~~ ~ ~ ~ ~ ~ LRM ROD BLOCK LM T13 2200 2000 1~~~ + ___ II ~~~~~OPERATION c20 1800 I 1600 SCRAM RE#Tin CrTED MONITORF I
O 1400 REN REGION REGION CORE FLOW 10
-i C6 z 1200 BOUNDARY BOUNDARY -BOUNDARY nGO 0
CL uJ j 1000 0 0 u APRMCRA __ ~~~~~~~~~~~~~ 800 600 OPERATION CIRC PROHIBrrED LINE 400...V 400 200 0 I I I I I I I I I I 1011h I~~0 MNPMP I SPEED (26)~II_
~ ~~ ~~~~~~~~~~~~dI'
~~~i I I I~~~~~~d I I I I I I I I I I v 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 0 CORE FLOW MLBiHR REVISION 15A 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 GE1 1-P9DUB408-6G5.0/7G4.0-100T-141-T6 12 40 GEl 1-P9DUB408-16GZ-1 OT-1 41 -T6 12 73 GE 1-P9DUB407-14GZ-10OT-141 -T6 13 119 GE1 -P9DUB408-6G5.0/7G4.0-1 OT-141 -T6 13 40 GE14-Pl ODNAB412-16GZ-1 OT-1 45-T6-3901 14 144 New GE14-P1 ODNAB397-1 OG6.0/3G5.0-1 OT-1 45-T6-2613 15 36 GE1 4-Pl ODNAB397-14GZ-1 OT-1 45-T6-2621 15 88 GE14-P1 ODNAB398-8G6.0/5G5.0/1 G2.0-1 OT-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 (B 4 C) compacted to approximately 70% of the theoretical density or a combination of boron carbide powder and solid hafnium. REVISION 15A COLR PAGE 35 OF 37
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE: G4.02 FIGURE 4.0-1 Reactor Vessel Core Loading Pattern 52 i H FHI 50 48 [J H][D[f Eff 0 [1 iE 46 44 Jn[ MID[j E1 [o FIE1 0 42 rEi A cF I Fn E M 40 1 I] Dll E0E 38 ETsB [09 FETM MET MUE eeeesSEff WERM nT mIT 36 ] ]IrF 34 MM-1 ffif -EI WMMMMC -[D-j 32 1 g l E E E l g 30 DF [M+M-D In +][EM FL [ E]E[D] I 1 EFn [gE D 28 K 26 EN nC+rC E MAS ) FI 1EL1E MM-1 M1 rLS 24 r [ I 1E 22 1 1 Er DIE em Ie eT lfI eT r j i[ 20 Emmmmfsgm WE Sm 18 El EJI Ej El F0E Z cmi jI DIDB9[[9E [LE El E 16 m] w [ [F F [ [D E] E] [DF E] 146 t1 Ejljfflg im E AElM 'Fi[ ClM [El1[L [1 El 1E El gD 12 4 ~~~~~~~~~~~~~~~lg in E D 10 A~~~L-LLL JLJL L 6 H~~~~~E KF B E KIr 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=GE lI-P9DUB407-14GZ-10OT-141-T6 (Cycle 13) -G=GE11-P9DUB408-16GZ-10OT-141-T6 (Cycle 12) B=GEI I-P9DUB408-6G5.O/7G4.0-10OT-141-T6 (Cycle 13) H=GE1 1-P9DUB408-6G5.O7G4.0-OOT-141-T6 (Cycle 12) C=GEI I-P9DUB407- 14GZ-10OT- 141-T6 (Cycle 13) I=GE14-PlODNAB397-14GZ-10OT-145-T6-2621 (Cycle 15) D=GE1 1-P9DUB408-6G5.OnG4.0-JOOT- 141-T6 (Cycle 13) J=GE1 1-P9DUB408-16GZ-100T- 141-T6 (Cycle 12) E=GE14-PIODNAB412-16GZ- lOOT-145-T6-3901 (Cycle 14) K=GEl l-P9DUB408-6G5.O/7G4.0-10OT-141-T6 (Cycle 12) F=GE14-PIODNAB397- lOG6.013G5.0- 10OT-145-T6-2613 b-GE14-PODNAB398-8G6.0/5G5.01IG2.0-1OOT- 145-T6-2614 (Cycle 15) (Cycle 15) REVISION 15A 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-2401 1-P-A-14 and NEDE-2401 1-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 SAFER/GESTR-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 CON161 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-0000-001 3-1555, 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. 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. SUDDS/RF 02-58, 0000-0008-6613SRLR Rev.1, March 2003, "Supplemental Reload Licensing Report, Reload 14, Cycle 15." 5.15. Calculation S&SA-1 74, 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 REVISION 15A COLR PAGE 37 OF 37}}