ML091110049
| ML091110049 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 04/09/2009 |
| From: | Jeffery Lynch Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2.09.025 | |
| Download: ML091110049 (47) | |
Text
{{#Wiki_filter:" Entergy Entergy Nuclear Operations, Inc. Pilgrim Station 600 Rocky Hill Road Plymouth, MA 02360 April 9, 2009 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
SUBJECT:
Entergy Nuclear Operations, Inc. Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35 Core Operating Limits Report, Revision 28 (Cycle 17) LETTER NUMBER: 2.09.025
Dear Sir or Madam:
The enclosed revision of Pilgrim's Core Operating Limits Report (COLR) is submitted in accordance with Pilgrim Technical Specification 5.6.5. Revision 28 provides revised Table 3.1-1 and Figure 3.1-1 clarifying MAPLHGR limits in Section 3.1 of the Report. This letter contains no commitments. Should you have questions or require additional information relative to this COLR revision, please contact me at (508) 830-8403. Sincerely, Joseph R. Lynch Licensing Manager WGL/wl
Attachment:
Core Operating Limits Report, Revision 28, dated March 26, 2009 (45 pages) cc: Regional Administrator, Region 1 Mr. James S. Kim, Project Manager U.S. Nuclear Regulatory Commission Plant Licensing Branch I-1 475 Allendale Road Division of Operator Reactor Licensing King of Prussia, PA 19406 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North 0-8C2 Senior Resident Inspector 11555 Rockville Pike Pilgrim Nuclear Power Station Rockville, MD 20852
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ATTACHMENT PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT REVISION 28, DATED MARCH 26, 2009 (45 PAGES)
(CYCLE 17) 3/26/2009 PRFPARI*fl 3/26/2009 Shivaram Paranjape, Senior Staff Engineer Date REVIEWED: Sco St nc Id Fuels Supervisor Date APPROVED:7/ 312 ,* Fre6 Smith, Manager, Fuels & Analysis Date APPROVED: 3ýý- T Gary Ja actor Engineering Superintendent Date APPROVED: m Brian S ivan, Nucear Engineering Director Da APPROVED: 3-Dz-ate Date Onsite Safety Review Comr ittee OSRC Meeting #: ___-0C-APPROVED: __ V _ _& _ D. Noyes, O-perations KA1nager Date APPROVED: IW1 9 Robert' t mith, Gp al Manager Plant Operations /Date APPROVED: I K. gr-onson, Sit-e-Iice President Date-
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 TABLE OF CONTENTS P.1e TITLE/SIGNATURE PAGE....................................1.... TABLE O F CO NTENTS . .................................. .................................... 2 R EC OR D O F R EV ISIO N S........................................................................... 3 LIST OF TABLES....................................... ........................... 4 LIS T O F F IG UR E S .................................................................................. ..4 1.0 IN T R O D UC T IO N ........................................................................... 5 2.0 INSTRUMENTATION TRIP SETTINGS ........................................ 6 2.1 APRM Flux Scram Trip Setting (Run Mode) ...................... 6 2.2 APRM Rod Block Trip Setting (Run Mode) ......................... 11 2.3 Rod Block Monitor Trip Setting ............................................ 11 3.0 CO RE O PERATING LIM ITS ......................................................... 16 3.1 Average Planar Linear Heat Generation R ate (A P LH G R ) .................................................................. 16 3.2 Linear Heat Generation Rate (LHGR) .................................. 31 3.3 Minimum Critical Power Ratio (MCPR) ................. 35 3.4 Power/Flow Relationship ........................... 40. 4.0 REACTOR VESSEL CORE DESIGN ............................................. 43 5.0 R E F E R E NC E S ............................................................................... 45 REVISION 28 Page 2 of 45
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 of Applicable for use during Cycle 8 Operation license amendment by NRC 9A Effective date based on issuance of Applicable for use during Cycle 9 operation license amendment by NRC for ARTS and SAFER/GESTR 10A Effective date based on initial startup of Applicable for use during Cycle 10 Operation Cycle 10 11A Effective date based on initial startup of Applicable for use during Cycle 11 Operation Cycle 11 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 issuance of Applicable for use during Cycle 12 Operation license amendment by NRC for SLMCPR of 1.08 12B Effective upon final approval Renumbered Table 3.3-2 to 3.3-1, Sh. 2 of 2 and Table 3.3-1 to 3.3-1,Sh. 1 of 2 12C Effective upon final approval Changed Tech Spec section numbers referenced due to Tech Amendment #177. Pages affected: 6, 24 12D Effective upon final approval Incorporated stability log-term solution option I-A. 13A Effective upon final approval Applicable for use during Cycle 13 Operation 14A Effective upon final approval Applicable for use during Cycle 14 Operation 15A Effective upon final approval Applicable for use during Cycle 15 Operation 15B Effective upon final approval Changed MAPLHGR Limits for GE14 fuel in response to an input error GE corrected. Applicable for use during Cycle 15 Operation 16A Effective upon final approval Applicable for use during Cycle 16 Operation 16B Effective upon final approval Core Loading Change to replace leaking fuel bundle JLG621. Clarified P-F Map graphic on P. 36. Applicable for use during Cycle 16 Operation 25 Effective upon final approval Limits for Single Loop Operation were incorporated. Rev number scheme changed to Merlin Convention 26 Effective upon final approval Applicable for use during Cycle 17 Operation 27 Effective upon final approval Corrected typographical errors on p. 30, 34,38,39 per CR-PNP-2008-256 and 285 Editorial and format changes on p. 1,4, 11,12,13,16,28,29,31,33,35,36,37,40,41,45 28 Effective upon final Extended Tables 3.1-1 to 63.5 GWD/ST (70 Approval GWD/MT), updated Fig. 3.1-1, section 3.1 & references REVISION 28 Page 3 of 45
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 2.1-2 Formulae for APRM Flux Scram Trip Settings in Figure 2.1-2 8 2.2-1 Formulae for APRM Rod Block Trip Settings in Figure 2.2-1 12 2.2-2 Formulae for APRM Rod Block Trip Settings in Figure 2.2-2 13 3.1-1 MAPLHGR Limits For GE14 Fuel 17 At Rated Power and Rated Flow 3.3-1 MCPR Operating Limits-- GE14 Fuel At Rated Power and Rated 36 Flow LIST OF FIGURES Number Title Page 2.1-1 Allowable APRM Flux Scram Trip Settings, Two Loop Operation 9 (Normal Feed water Temperature) 2.1-2 Allowable APRM Flux Scram Trip Settings, Single Loop 10 Operation (Normal Feed water Temperature) 2.2-1 Allowable APRM Rod Block Trip Settings, Two LoopOperation 14 (Normal Feed water Temperature) 2.2-2 Allowable APRM Rod Block Trip Settings, , Single Loop 15 Operation (Normal Feed water Temperature) 3.1-1 Most Limiting Maximum Average Planar Linear Heat Generation 28 Rate (MAPLHGR) for GE14 Fuel (Normal Feedwater Temperature) 3.1-2 Flow-Dependent MAPLHGR Factor (MAPFACF) for GE14 Fuel 29 3.1-3 Power-Dependent MAPHLGR Factor (MAPFACp) for GE14 Fuel 30 3.2-1 Maximum Linear Heat Generation 32 Rate (MLHGR) for GE14 Fuel 3.2-2 Flow-Dependent LHGR Factor (LHGRFACF) for GE14 Fuel 33 3.2-3 Power-Dependent LHGR Factor (LHGRFACp) for GE14 Fuel 34 3.3-1 Flow-Dependent MCPR Limits (MCPRF) for GE14 Fuel 37 3.3-2 Power-Dependent MCPR Limits (MCPRp) for GE14 Fuel, 38 Turbine Bypass Assumed Operable 3.3-3 Power-Dependent MCPR Limits (MCPRp) for GE14 Fuel, 39 Turbine Bypass Out Of Service 3.4-1 Power/Flow Operating Map, Two Loop Operation, Normal 41 Feedwater Temperature 3.4-2 Power/Flow Operating Map, Single Loop Operation 42 4.0-1 Reactor Vessel Core Loading Pattern 44 REVISION 28 Page 4 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02
1.0 INTRODUCTION
This report provides the cycle-specific limits for operation of the Pilgrim Nuclear Power Station (PNPS) during Cycle 17. In this report, Cycle 17 will be referred to as the present cycle. Although this report is not a part of the PNPS Technical Specifications, the Technical Specifications refer to this report for the applicable values of the following fuel-related parameters:, Reference Technical Specification APRM Flux Scram Trip Setting (Run Mode) 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 3.1 1.A Linear Heat Generation Rate (LHGR) 3.11..B Minimum Critical Power.Ratio (MCPR) 3.11.C Power/Flow Relationship 3.11. D Reactor Vessel Core Design 4.2 If any of the core operating limits in this report is exceeded, actions will be taken as defined in the referenced Technical Specification. The core operating limits in this report have been established for the present cycle using the NRC-approved methodology provided in the documents listed in Technical Specification 5.6.5. These limits are established such that the applicable limits of the plant safety analysis are met. 1.1 Stability Option 1-D Exclusion Region and Buffer Zone. The reactor shall not be intentionally operated within the Exclusion Region given in Figure 3.4-1 for Two Loop Operation (TLO) and Figure 3.4-2 for Single Loop Operation (SLO). Immediate exit is required for inadvertent entry into the exclusion region. The reactor shall not be intentionally operated within the Buffer Zone given in Figure 3.4-1 for TLO and Figure 3.4-2 for SLO when the on-line Stability Monitor is inoperable. Allowable values for APRM Scram and Rod Block trip set points are defined in Section 2. REVISION 28 Page 5 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 2.0 INSTRUMENTATION TRIP SETTINGS: 2.1 APRM Flux Scram Trip Setting (Run Mode) Ref. Technical Specifications: Table 3.1.1 APRM flux scram Allowable Trip Set point (ATSP) for TLO is shown on Figure 2.1-1 and is clamped at 120% of rated core thermal power. Formulae used to develop Figure 2.1-1 are listed in Table 2.1-1. ATSP for SLO is shown on Figure 2.1-2 and is clamped at 120% of rated core thermal power. Formulae used to develop Figure 2.1-2 are listed in Table 2.1-2. In accordance with Technical Specification Table 3.1.1, Note 15, for no combination of loop recirculation flow rate and core thermal power shall the APRM flux scram trip setting be allowed to exceed 120% of rated thermal power. Drive Flow to Core Flow relationship: APRM Trip settings use Drive flow to determine the power trip setting for both scrams and rod blocks, as the drive flow is a more reliable flow indication than core flow. The analysis calculates the stability based trip settings based on Core Flow. Drive Flow (WD) normalization with core flow shall be done such that 100% Drive Flow with Two Loops corresponds to 100% Rated Core Flow of 69 M#/hr. Source: Reference 5.6, sec. 2.1 REVISION 28 Page 6 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Table 2.1-1 Formulae For Allowable APRM Flux Scram Settings in Figure 2.1-1 Two Loop Operation Allowable Trip Set Point Drive Flow Range (ATSP) C C D D % Rated SLOPE INTERCEPT 0.20 71.5 0 *WD *<22.5 0.71 60.0 22.5 < WD < 55.9 0.65 70.6 55.9 < WD < 76 0 120.0 76 < WDO <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 28 Page 7 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Table 2.1-2 Formulae For Allowable APRM Flux Scram Settings in Figure 2.1-2 Single Loop Operation Allowable Trip Set Point Drive Flow Range (ATSP) C D SLOPE INTERCEPT % Rated 0 <WD <_<32.5 0.20 69.5 0.71 52.9 32.5 < WD _< 65.9 0.65 64.1 65.9 < WD < 86 0 120.0 86 < Wo -<125 Notes:
- 1. ATSP = C * % WD + D, ATSP is in % Power
- 2. Figure 2.1-2 shows the plot of ATSP vs. WD.
- 3. Reference 5.6, Table 1.b lists the values of constants listed in this Table.
REVISION 28 Page 8 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Figure 2.1-1 Allowable APRM Flux Scram Trip Settings-TLO (Normal Feed water Temperature) 130.0 120.0 110.0 S I. 100.0 U, E 0n 90.0 80.0 ___ 70.0 60.0 - - 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 WD, Drive Flow, % REVISION 28 Page 9 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Figure 2.1-2 Allowable APRM Flux Scram Trip Settings-SLO (Normal Feed water Temperature) 125.0 - 120.0 - 115.0 110.0 105.0 a-0 100.0 - U, 95.0 (0 90.0 I- 85.0 80.0 75.0 70.0 _ 65.0 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 WD, Drive Flow, % REVISION 28 Page 10 of 45
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 When the mode switch is in the RUN position, the average power range monitor (APRM) rod block Allowable Trip setting (ATSPRB) as a function of drive flow for Two Loop Operation shall be as given by Figure 2.2-1. ATSPRB is clamped at 115% of rated core thermal power. Formulae that form the basis of the Figure 2.2-1 are listed in Table 2.2-1. When the mode switch is in the RUN position, the average power range monitor (APRM) rod block Allowable Trip setting (ATSPRB) as a function of drive flow for Single Loop Operation shall be as given by Figure 2.2-2. ATSPRB is clamped at 115% of rated core thermal power. Formulae that form the basis of the Figure 2.2-2 are listed in Table 2.2-2. 2.3 Rod Block Monitor Trip Setting
References:
Technical Specification Table 3.2.C-2, Ref. 5.10 Table 4.5 (a) & (b), Ref. 5.21 p.4 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). Allowable values for Reactor Power intermediate ranges are more conservative than Ref. 5.21. REVISION 28 Page 11 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Table 2.2-1 Formulae For Allowable APRM Rod Block Settings in Figure 2.2-1 (Two Loop Operation) APRM Rod Block Allowable Trip Set Drive Flow Range Point (ATSPRB) C D D C % Rated SLOPE INTERCEPT 0.20 66.5 0 _<WD -<22.5 0.71 55.0 22.5 < WD < 55.9 0.65 63.6 55.9 < WD - 79.1 0 115.0 79.1 <WD *125 Notes:
- 1. ATSPRB = C * %WD + D, ATSPRBis in % Power
- 2. Figure 2.2-1 shows the plot of ATSPRB VS. WD.
- 3. Reference 5.6, Table 1.a lists the values of constants listed in this Table.
REVISION 28 Page 12 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Table 2.2-2 Formulae For Allowable APRM Rod Block Settings in Figure 2.2-2 (Single Loop Operation) APRM Rod Block Allowable Trip Set Drive Flow Range Point (ATSPRB) C C D D % Rated SLOPE INTERCEPT 0.20 64.5 0 *<WD *<32.5 0:71 47.9 32.5 < WD - 65.9 0.65 57.1 65.9 < WD 89.1 0 115.0 89.1 <WD *<125 Notes:
- 1. ATSPRB = C * % WD + D, ATSPRB is in % Power
- 2. Figure 2.2-2 shows the plot of ATSPRB vs. WD.
- 3. Reference 5.6, Table 1.b lists the values of constants listed in this Table.
REVISION 28 Page 13 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Figure 2.2-1 Allowable APRM Flux Rod Block Trip Settings - TLO (Normal Feed water Temperature) 120.0 110.0
- 100.0 D.
o 90.0 0 CL 80.0 70.0 60.0 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 WD, Drive Flow, % REVISION 28 Page 14 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Figure 2.2-2 Allowable APRM Flux Rod Block Trip Settings-SLO (Normal Feed water Temperature) 120.0 115.0 110.0 105.0 100.0 0 a-C,$ 95.0 0 90.0 0 85.0 0- 80.0 75.0 70.0 65.0 60.0 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 WD, Drive Flow, % REVISION 28 Page 15 of 45
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 MAPLHGRp. The flow-dependent MAPLHGR limit, MAPLHGRF, is the product of the MAPLHGR flow factor, MAPFACF, shown in Figure 3.1-2 and the MAPLHGR for rated power and flow conditions, given in Tables 3.1-1. The power-dependent MAPLHGR limit, MAPLHGRP, is the product of the MAPLHGR power factor, MAPFACP in Figure 3.1-3 and the MAPLHGR limit for rated power and flow conditions, given in Tables 3.1-1 MAPLHGR for rated power and flow conditions for the most limiting lattice in each fuel type (excluding natural uranium lattices) are presented in Figure 3.1-1. MAPLHGR limits are based on ECCS-LOCA considerations. For each lattice type, the MAPLHGR values for rated power and flow conditions are listed in Table 3.1-1, which are obtained from the Supplemental Reload Licensing Report (Ref. 5.15). Pbypass is the power level below which more restrictive thermal limits are applied, as the Turbine Stop Valve closure and Turbine Control Valve fast closure scrams are assumed to be bypassed. It can be set anywhere in the range from 32.5% power to 45% power. Pbypass is currently set at 32.5% power. If this setting is changed in the future, then the appropriate thermal limits can be determined using Figures 3.1-2 and 3.1-3. When in Single Loop Operation, an SLO Multiplier of 0.8 applies to the Rated MAPLHGR limit. At off rated conditions, MAPLHGR limit is the lower of 0.8 times the rated MAPLHGR limit, the MAPLHGRp or MAPLHGRF. Via Reference 5.22, GNF provided an explanation that the dashes in the SRLR MAPLHGR Tables only indicate that specific MAPLHGR limits for the exposure points were not computed, while MAPLHGR limits are valid up to 63.5 GWD/ST nodal exposure. Per reference 5.22, the last calculated value in the tables for each lattice remain applicable till 63.5 GWD/ST. Tables 3.1-1 and Fig. 3.1-1 have been revised using this explanation. REVISION 28 Page 16 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Table 3.1-1 MAPLHGR Limits for Rated Power and Rated Flow for GE14 fuel Bundle Type: GE14-P1ODNAB399-10G6.0/3G5.0/1G2.0-100T-145-T6-2828 (GE14C) Average Planar MAPLHGR Limit (kW/ft) Exposure Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT (GWd/ST) 6843 6844 6845 6846 6847 6848 0.00 (0.00) 9.80 8.79 8.76 8.74 10.21 10.89 0.22(0.20) 9.71 8.86 8.84 8.82 10.16 10.86 i.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 -- -- 70.00 (63.50) 3.98 4.87 4.92 4.94 4.21 4.52 REVISION 28 Page 17 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Table 3.1-1 Continued: Bundle Type: GE14-PIODNAB398-8G6.0/5G5.0/2G4.0-100T-145-T6-2829 (GE14C) Average Planar MAPLHGR Limit (kW/ft) GWd/MT (GWd/ST) Lattice Lattice Lattice Lattice Lattice Lattice 0.00(0.00) 9.80 8.69 867 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 1 1.05 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 7- -- 64.17 (58.22) 4.93 -- -- 64.51 (58.52) -- -- -- 4.95 -- -- 70.00 (63.50) 3.98, 4.88 4.93 4.95 4.21 4.54 REVISION 28 Page 18 ,of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Table 3.1-1 Continued: Bundle Type: GE14-P1ODNAB412-16GZ-100T-145-T6-3901 Average Planar Exposure MAPLHGR Limit (kW/ft) GWd/MT (GWd/ST) Lat. Lat. Lat. Lat. Lat. Lat. Lat. 4820 4827 4828 4829 4830 4825 4831 0.00 (0.00) 9.80 8.78 8.57 8.72 8.62 10.21 10.98 0.22 (0.20) 9.71 8.81 8.61 8.76 8.70 10.16 10.95 1.10(1.00) 9.50 8.87 8.68 8.85 8.79 10.01 10.86 2.20 (2.00) 9.44 8.97 8.80 8.98 8.93 9.98 10.84 3.31 (3.00) 9.45 9.08 8.92 9.12 9.07 10.01 10.86 4.41 (4.00) 9.49 9.20 9.05 9.24 9.19 10.05 10.88 5.51 (5.00) 9.53 -9.32 9.17 9.36 9.31 10.10 10.91 6.61 (6.00) 9.57 9.42 9.28 9.48 9.44 10.14 10.94 7.72 (7.00) 9.61 9.52 9.39 9.60 9.58 10.18 10.96 8.82 (8.00) 9.64 9:62 9.51 9.73 9.72 10.21 10.98 9.92 (9.00) 9.66 9.72 9.62 9.87, 9.87 10:24 10.99 11.02 (10.00) 9.68 9.82 9.74 10.01 10.02 10.25 f 1.00 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 1037 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 --.. 70.00 (63.50) 3.98 4.84 4.84 4.90 4.92 4.21 4.51 REVISION 28 Page 19 of 45
PILGRIM NUCLEAR POWER STATION' PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Table 3.1-1 Continued: Bundle Type: GE14-PlODNAB397-IOG6.0/3G5.0-100T-145-T6-2613 Average Planar MAPLHGR Limit (kW/ft) L~vnnc..rn _________________ GWd/MT (GWd/ST) Lattice Lattice Lattice Lattice Lattice Lattice 5841 5848 5849 5850 5846 5851 0.00 (0.00) 9.80 8.75 8.72 8.71 10.21 10.87 0.22 (0.20) 9.71 8.81 8.79 8.78 10.16 10.84 1.10(1.00) 9.50 8.91 8.91 8.91 10.01 10.74 2.20 (2.00) 9.44 9.05 9.07 9.07 9.98 10.71 3.31 (3.00) 9.45 9.20 9.24 9.25 10.01 10.73 4.41 (4.00) 9.49 9.30 9.42 9.44 10.05 10.76 5.51 (5.00) 9.53 9.38 9.56 9.61 10.10 10.79 6.61(6.00) 9.57 9.45 9.65 9.70 10.14 10.82 7.72 (7.00) 9.61 9.54 9.74 9.80 10.18 10.85 8.82 (8.00) 9.64 9.62 9.83 9.89 10.21 10.87 9.92 (9.00) 9.66 9.70 9.92 9.98 10.24 10.88 11.02 (10.00) 9.68 9.78 10.01 10.07 10.25 10.89 12.13 (11.00) 9.69 9.87 10.11 10.18 10.26 10.90 13.23 (12.00) 9.67 9.93 10.21 10.28 10.27 10.90 14.33 (13.00) 9.64 9.99 10.29 10.36 10.23 10.89 15.43 (14.00) 9.60 10.05 10.35 10.43 10.19 10.85 15.99 (14.51) 9.58 10.07 10.37 10.45 10.17 10.83 16.53 (15.00) 9.56 10.10 10.40 10.47 10.15 10.81 18.74 (17.00) 9.48 10.18 10.45 10.51 10.07 10.72 22.05 (20.00) 9.35 10.24 10.49 10.55 9.94 10.59 23.01 (20.87) 9.28 10.24 10.50 10.56 9.89 10.55 27.56 (25.00) 8.95 10.22 10.52 10.60 9.66 10.38 32.19 (29.20) 8.40 9.92 10.22 10.29 9.11 9.91 33.07 (30.00) 8.30 9.86 10.16 10.23 9.01 9.82 38.58 (35.00) 7.65 9.46 9.69 9.70 8.36 9.18 44.09 (40.00) 7.02 9.01 9.17 9.18 7.73 8.54 49.60 (45.00) 6.38 8.50 8.64 8.65 7.09 7.91 54.78 (49.70) 3.98 -- -- -- -- -- 55.12 (50.00) -- 7.92 8.10 8.12 5.63 7.28 58.14 (52.75) -- -- -- 4.21 -- 60.63 (55.00) 5.76 6.51 6.74 -- 5.12 62.02 (56.27) -- -- -- 4.47 62.56 (56.75) 4.87 -- --. 63.50 (57.61) -- 5.18 5.41 64.09 (58.14) .... 4.91 --.... 64.53 (58.54) -- -- -- 4.94 .... 70.00 (63.50) 3.98 4.87 4.91 4.94 4.21 4.47 REVISION 28 Page 20 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Table 3.1-1 Continued: Bundle Type: GE14-PIODNAB397-14GZ-100T-145-T6-2621 Average Planar Exposure MAPLHGR Limit (kW/ft) GWd/MT (GWd/ST) Lat. Lat. Lat. Lat. Lat. Lat. Lat. 5841 5842 5843 5844 5845 5846 5847 0.00 (0.00) 9.80 8.66 8.76 8.73 8.72 10.21 10.94 0.22 (0.20) 9.71 8.73 8.82 8.80 8.79 10.16 10.91 1.10(1.00) 9.50 8.84 8.93 8.92 8.92 10.01 10.81 2.20 (2.00) 9.44 8.99 9.07 9.09 9.09 9.98 10.79 3.31 (3.00) 9.45 9.14 9.20 9.26 9.27 10.01 10.81 4.41 (4.00) 9.49 9.24 9.27 9.43 9.46 10.05 10.83 5.51 (5.00) 9.53 . 9.33 9.34 9.51 9.56 10.10 10.87 6.61(6.00) 9.57 9.41 9.41 9.59 9.64 10.14 10.89 7.72 (7.00) 9.61 9.50 9.49 9.67 9.72 10.18 10.92 8.82 (8.00) 9.64 9.58 9.57 9.75 9.80 10.21 10.94 9.92 (9.00) 9.66 9.67 9.65 9.85 9.90 10.24 10.95 11.02 (10.00) 9.68 9.75 9.73 9.97 10.02 10.25 10.96 12.13 (11.00) 9.69 9.84 9.83 10.10 10.16 10.26 10.96 13.23 (12.00) 9.67 9.90 9.91 10.21 10.28 10.27 10.96 14.33 (13.00) 9.64 9.97 9.99 10.30 10.37 10.23 10.96 15.43 (14.00) 9.60 10.03 10.05 10.36 10.44 10.19 10.92 15.99 (14.51) 9.58 10.06 10.08 10.39 10.46 10.17 10.90 16.53 (15.00) 9.56 10.09 10.11 10.41 10.48 10.15 10.88 18.74 (17.00) 9.48 10.18 10.19 10.46 10.53 10.07 10.79 22.05 (20.00) 9.35 10.25 10.25 10.50 10.57 9.94 10.66 23.01 (20.87) 9.28 10.24 10.25 10.51 10.57 9.89 10.62 27.56 (25.00) 8.95 10.22 10.23 10.53 10.61 9.66 10.45 32.19 (29.20) 8.40 9.91 9.92 10.23 10.29 9.11 9.99 33.07 (30.00) 8.30 9.86 9.86 10.17 10.23 9.01 9.90 38.58 (35.00) 7.65' 9.46 9.46 9.70 9.70 8.36 9.26 44.09 (40.00) 7.02 9.01 9.01 9.17 9.18 7.73 8.63 49.60 (45.00) 6.38 8.50 8.50 8.64 8.65 7.09 7.99 54.78 (49.70) 3.98 -- -- -- -- -- -- 55.12 (50.00) -- 7.92 7.92 8.10 8.12 5.63 7.36 58.14 (52.75) - -- -- -- -- 4.21 -- 60.63 (55.00) -- 5.74 5.75 6.50 6.73 -- 5.34 62.43 (56.64) -- -- -- --. 4.50 62.52 (56.72) -- 4.87 .....-- -- 62.53 (56.73) ..-- 4.87 -- --... 63.50 (57.61) ....-- 5.17 5.40 .... 64.06 (58.11) ...... 4.91 --.... 64.49 (58.51) -- -- -- -- 4.94 -- -- 70.00 (63.50) 3.98 4.87 4.87 4.91 4.94 4.21 4.50 REVISION 28 Page 21 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Table 3.1-1 Continued: Bundle Type: GE14-P1ODNAB398-8G6.0/5G5.0/1G2.0-100T-145-T6-2614 Average Planar Exposure MAPLHGR Limit (kW/ft) Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT (GWd/ST) 5841 5852 5853 5854 5846 5855 0.00 (0.00) 9.80 8.77 8.75 8.73 10.21 10.93 0.22(0.20) 9.71 8.83 8.81 8.80 10.16 10.90 1.10(1.00) 9.50 8.94 8.94 8.94 10.01 10.80 2.20 (2.00) 9.44 9.08 9.12 9.12 9.98 10.78 3.31 (3.00) 9.45 9.16 9.30 9.31 10.01 10.79 4.41 (4.00) 9.49 9.25 9.42 9.47 10.05 10.82 5.51 (5.00) 9.53 9.34 9.51 9.57 10.10 10.85 6.61 (6.00) 9.57 9.42 9.61 9.66 10.14 10.88 7.72(7.00) 9.61 9.51 9.70 9.76 10.18 10.91 8.82 (8.00) 9.64 9.59 9.79 9.85 10.21 10.93 9.92 (9.00) 9.66 9.68 9.89 9.95 10.24 10.94 11.02 (10.00) 9.68 9.77 10.01 10.07 10.25 10.95 12.13 (11.00) 9.69 9.87 10.13 10.19 10.26 10.95 13.23 (12.00) 9.67 9.94 10.23 10.30 10.27 10.95 14.33 (13.00) 9.64 10.01 10.31 10.38 10.23 10.95 15.43 (14.00) 9.60 10.07 10.37 10.45 10.19 10.91 15.99 (14.51) 9.58 10.10 10.39 10.47 10.17 10.89 16.53 (15.00) 9.56 10.12 10.42 10.49 10.15 10.87 18.74 (17.00) 9.48 10.20 10.47 10.54 10.07 10.78 22.05 (20.00) 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 70.00 (63.50) 3.98 4.88 4.91 4.94 4.21 4.49 REVISION 28 Page 22 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Table 3.1.-1 Continued Bundle Type: GE 14-PI ODNAB399-15GZ- 1OOT- 145-T6-2957 (GE 14C) Average Planar MAPLHGR Limit (kW/ft) Lattice Lattice Lattice Lattice Lattice Lattice GWdIMT (GWd/ST) 7492 7493 7494 7495 7496 7497 0.00 (0.00) 9.80 8.73 8.56 8.54 10.21 10.97 0.22 (0.20) 9.71 8.80 8.65 8.63 10.16 10.94 1.10(1.00) 9.50 8.91 8.78 8.77 10.01 10.86 2.20 (2.00) 9.44 9.05 8.97 8.95 9.98 10.85 3.31 (3.00) 9.45 9.21 9.16 9.15 10.01 10.87 4.41(4.00) 9.49 9.35 9.37 9.37 10.05 10.90 5.51 (5.00) 9.53 9.48 9.59 9.59 10.10 10.94 6.61 (6.00) 9.57 9.62 9.81 9.78 10.15 10.97 7.72(7.00) 9.61 9.73 9.94 9.89 10.18 11.00 8.82(8.00) 9.64 9.84 10.05 10.02 10.21 11.02 9.92(9.00) 9.66 9.96 10.17 10.15 10.24 11.04 11.02 (10.00) 9.68 10.08 10.30 10.30 10.25 11-.05 12.13 (11.00) 9.69 10.20 10.44 10.45 10.27 11.06 13.23 (12.00) 9.67 10.30 10.56 10.58 10.27 11.06 14.33 (13.00) 9.64 10.37 10.64 1.0.66 10.24 11.06 15.43 (14.00) 9.60 10.43 10.70 10.72 10.20 11.02 15.99(14.51) 9.58 10.45 10.72 10.74 10.18 11.00 16.53 (15.00) 9.56 10.48 10.74 10.76 10.16 10.98 18.74 (17.00) 9.48 10.53 10.79 10.80 10.07 10.90 22.05 (20.00) 9.35 10.57 10.81 10.78 9.94 10.77 23.01 (20.87) 9.28 10.57 10.80 10.75 9.89 10.73 27.56 (25.00) 8.95 10.56 10.72 10.66 9.66 10.56 32.19 (29.20) 8.40 10.19 10.35 .10.33 9.11 10.12 33.07(30.00) 8.30 10.12 10.28 10.27 9.01 10.03 38.58 (35.00) 7.65 9.62 9.73 9.73 8.37 9.39 44.09 (40.00) 7.02 9.09 9.20 9.21 7.73 8.76 49.60 (45.00) 6.38 8.55 8.67 8.68 7.10 8.13 54.79 (49.71) 3.98 -- -- -- -- -- 55.12 (50.00) -- 8.00 8.12 8.14 5.64 7.50 58.16 (52.77) -- -- -- 4.21 -- 60.63 (55.00) -- 6.34 6.90 6.89 -- 5.67 63.05 (57.20) ........... 4.54 63.50 (57.61) -- 5.02 5.60 5.59 ..-- 63.77 (57.85) -- 4.89 --.. -- 65.06 (59.02) --.-- 4.89 -- 65.11 (59.06) ..-- 4.88 ...... 70.00 (63.50) 3.98 4.89 4.88 4.89 4.21 4.54 REVISION 28 Page 23 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Table 3.1-1 Continued: Bundle Type: GE14-PIODNAB398-5G6.0/1OG5.0-100T-145-T6-2958 (GE14C) Average Planar MAPLHGR Limit (kW/ft) Exposure Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT (GWd/ST) 7492 7498 7499 7500 7501 7502 0.00 (0.00) 9.80 8.73 8.69 8.66 10.21 10.97 0.22 (0.20) 9.71 8.80 8.76 8.74 10.16 10.94 1.10(1.00) 9.50 8.91 8.89 8.87 10.01. 10.86 2.20 (2.00) 9.44 9.06 9.07 9.06 9.98 10.85 3.31 (3.00) 9.45 9.21 9.26 9.25 10.01 10.87 4.41 (4.00) 9.49 9.34 9.46 9.44 10.05 10.90 5.51 (5.00) 9.53 9.47 9.62 9.56 10.10 10.94 6.61 (6.00) 9.57 9.61 9.74 9.69 10.15 10.97 7.72(7.00) 9.61 9.72 9.86 9.82 10.18 11.00 8.82(8.00) 9.64 9.83 9.99 9.96 10.21 11.02 9.92(9.00) 9.66 9.94 10.13 10.11 10.24 11.04 11.02 (10.00) 9.68 10.06 10.28 10.28 10.25 11.05 12.13 (11.00) 9.69 10.18 10.43 10.44 10.27 11.06 13.23 (12.00) 9.67 10.28 10.56 10.58 10.27 11.06 14.33 (13.00) 9.64 10.36 10.65 10.67 10.24 11.06 15.43 (14.00) 9.60 10.42 10.71 10.73 10.20 11.02 15.99 (14.51) 9.58 10.45 10.73 10.75 10.18 11.00 16.53 (15.00) 9.56 10.47 10.75 10.77 10.16 10.98 18.74 (17.00) 9.48 10.53 10.80 10.81 10.07 10.90 22.05 (20.00) 9.35 10.57 10.82 10.78 9.94 10.77 23.01 (20.87) 9.28 10.57 10.80 10.76 9.89 10.73 27.56 (25.00) 8.95 10.55 10.73 10.66 9.66 10.56 32.19 (29.20) 8.40 10.19 10.34 10.33 9.11 10.12 33.07 (30.00) 8.30 10.12 10.27 10.26 9.01 10.03 38.58 (35.00) 7.65 9.62 9.73 9.73 8.37 9.39 44.09 (40.00) 7.02 9.08 9.19 9.20 7.73 8.76 49.60 (45.00) 6.38 8.55 8.66 8.67 7.10 8.13 54.79 (49.71) 3.98 -- -- -- -- -- 55.12 (50.00) -- 8.00 8.12 8.13 5.64 7.50 58.16 (52.77) -- -- -- 4.21 -- 60.63 (55.00) -- 6.32 6.86 6.85 -- 5.67 63.05 (57.20) -- -- --.. 4.54 63.50 (57.61) -- 5.00 5.56 5.55 ..-- 63.75 (57.83) -- 4.89 -- --.... 64.96 (58.93) --.-- 4.89 .... 65.01 (58.98) .... 4.88 --.... 70.00 (63.50) 3.98 4.89 4.88 4.89 4.21 4.54 REVISION 28 Page 24 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Table 3.1-1 Continued: Bundle Type: GE14-P1ODNAB400-13GZ-100T-145-T6-2959 (GE14C) Average Planar MAPLUGR Limit (kW/ft) GWd/MT (GWd/ST) Lattice Lattice Lattice Lattice Lattice Lattice 7492 7503 7504 7505 7506 7507 0.00 (0.00) 9.80. 8.88 8.88 8.86 10.21 10.81 0.22 ( 0.20) 9.71 8.94 8.95 8.94 10.16 10.78 1.10(1.00) 9.50 9.03 9.06 9.05 10.01 10.69 2.20 (2.00) 9.44 9.17 9.23 9.22 9.98 10.69 3.31 (3.00) 9.45 9.30 9.40 9.39 10.01 10.72 4.41 (4.00) 9.49 9.42 9.58 9.58 10.05 10.76 5.51 (5.00) 9.53 9.54 9.74 9.71 10.10 10.80 6.61 (6.00) 9.57 9.66 9.88 9.82 10.15 10.84 7.72 (7.00) 9.61 9.78 9.98 9.94 10.18 10.88 8.82 (8.00) 9.64 9.90 10.10 10.06 10.21 10.90 9.92 (9.00) 9.66 10.00 10.22 10.20 10.24 10.92 11.02 (10.00) 9.68 10.10 10.35 10.34 10.25 10.94 12.13 (11.00) 9.69 10.20 10.49 10.49 10.27 10.95 13.23 (12.00) 9.67 10.30 10.61 10.63 10.27 10.95 14.33 (13.00) 9.64 10.37 10.70 10.72 10.24 10.95 15.43 (14.00) 9.60 10.44 10.76 10.78 10.20 10.91 15.99 (14.51) 9.58 10.47 10.78 10.80 10.18 10.89 16.53 (15.00) 9.56 10.50 10.80 10.81 10.16 10.87 18.74 (17.00) 9.48 10.56 10.82 10.83 10.07 10.78 22.05 (20.00) 9.35 10.58 10.82 10.78 9.94 10.65 23.01 (20.87) 9.28 10.58 10.80 10.75 9.89 10.61 27.56 (25.00) 8.95 10.56 10.72 10.62 9.66 10.44 32.19 (29.20) 8.40 10.20 10.36 10.33 9.11 9.97 33.07 (30.00) 8.30 10.13 10.29 10.28 9.01 9.89 38.58 (35.00) 7.65 9.63 9.74 9.74 8.37 9.25 44.09 (40.00) 7.02 9.10 9.21 9.22 7.73 8.61 49.60 (45.00) 6.38 8.56 8.68 8.69 7.10 7.98 54.79 (49.71) 3.98 -- -- -- -- -- 55.12 (50.00) -- 8.01 8.14 8.15 5.64 7.35 58.16 (52.77) -- -- -- 4.21 -- 60.63 (55.00) 6.39 6.97 6.96 -- 5.29 62.34 (56.55) -- -- -- 4.49 63.50 (57.61) 5.07 5.67 5.66 -- 63.89 (57.96) 4.89 -- --. 65.20 (59.15) ..-- 4.89 .... 65.25 (59.19) ..-- 4.88 -- _ ..- 70.00 (63.50) 3.98 4.89 4.88 4.89 4.21 4.49 REVISION 28 Page 25 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Table 3.1-1 Continued: Bundle Type: GE14-PIODNAB404-5G6.0/lOG5.0-iOOT-145-T6-2960 (GE14C) Average Planar MAPLHGR Limit (kW/ft) Exposure Lattice Lattice Lattice Lattice Lattice Lattice GWd/MT(GWd/ST) 7492 7508 7509 7510 7511 7512 0.00(0.00) 9.80 8.76 8.72 8.70 10.21 10.97 0.22 (0.20) 9.71 8.83 8.80 8.78 10.16 10.94 1.,10 1.00) 9.50 8.94 8.93 8.91 10.01 10.86 2.20(2.00) 9.44 9.09 9.11 9.10 9.98 10.85 3.31 (3.00) 9.45 9.24 9.30 9.29 10.01 10.87 4.41 (4.00) 9.49 9.38 9.50 9.48 10.05 10.90 5.51 (5.00) 9.53 9.51 9.66 9.60 10.10 10.94 6.61 (6.00) 9.57 9.64 9.78 9.73 10.15 10.97 7.72(7.00) 9.61 9.75 9.90 9.86 10.18 11.00 8.82(8.00) 9.64 9.86 10.03 10.00 10.21 11.02 9.92(9.00) 9.66 9.97 10.16 10.15 10.24 11.04 11.02 (10.00) 9.68 10.08 10.31 10.31 10.25 11.05 12.13 (11.00) 9.69 10.20 10.46 10.47 10.27 11.06 13.23 (12.00) 9.67 10.31 10.59 10.61 10.27 11.06 14.33 (13.00) 9.64 10.38 10.68 10.70 10.24 11.06 15.43 (14.00) 9.60 10.45 10.75 10.77 10.20 11.02 15.99 (14.51) 9.58 10.47 10.77 10.79 10.18 11.00 16.53 (15.00) 9.56 10.50 10.79 10.81 10.16 10.98 18.74 (17.00) 9.48 10.56 10.85 10.86 10.07 10.90 22.05 (20.00) 9.35 10.61 10.87 10.85 9.94 10.77 23.01 (20.87) 9.28 10.61 10.84 10.82 9:89 10.73 27.56 (25.00) 8.95 10.60 10.70 10.67 9.66 10.56 32.19 (29.20) 8.40 10.24 10.42 10.41 9.11 10.12 33.07 (30.00) 8.30 10.17 10.36 10.36 9.01 10.03 38.58 (35.00) 7.65 9.69 9.81 9.77 8.37 9.39 44.09 (40.00) 7.02 9.15 9.23 9.17 7T73 8.76 49.60 (45.00) 6.38 8.61 8.65 8.60 7.10 8.13 54.79 (49.71) 3.98 -- -- -- -- -- 55.12 (50.00). -- 8.06 8.11 8.06 5.64 7.50 58.16 (52.77) -- -- -- 4.21 L-60.63 (55.00) -- 6.46 7.08 7.07 -- 5.67 63.05 (57.20) -- -- --.. 4.54 63.50 (57.61) -- 5.14 5.78 5.77 ..-- 64.01 (58.07) -- 4.91 .. --.. 65.41 (59.34) --.-- 4.91 .... 65.45 (59.37) .... 4.90 --.... 70.00 (63.50) 3.98 4.91 4.90 4.91 4.21 4.54 REVISION 28 Page 26 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Table 3.1-1 Continued: Bundle Type: GE14-P1ODNAB400-12G6.0/3G5.0-100T-145-T6-2961 (GE14C) Average Planar MAPLHGR Limit (kW/ft) Fvnnrcu.r GWd/MT (GWd/ST) Lattice Lattice Lattice Lattice Lattice Lattice 7492 7513 7514 7515 7516 7517 0.00 (0.00) 9.80 8.71 8.67 8.65 10.21 10.97 0.22 (0.20) 9.71 8.78 8.74 8.72 10.16 10.94 1.10(1.00) 9.50 8.88 8.86 8.84 10.01 10.86 2.20 (2.00) 9.44 9.02 9.03 9.01 9.98 10.85 3.31 (3.00) 9.45 9.16 9.20 9.19 10.01 10.87 4.41(4.00) 9.49 9.31 9.39 9.38 10.05 10.90 5.51 (5.00) 9.53 9.43 9.58 9.52 10.10 10.94 6.61(6.00) 9.57 9.56 9.70 9.64 10.15 10.97 7.72(7.00) 9.61 9.67 9.81 9.76 10.18 11.00 8.82(8.00) 9.64 9.78 9.93 9.89 10.21 11.02 9.92(9.00) 9.66 9.88 10.05 10.03 10.24 11.04 11.02 (10.00) 9.68 9.99 10.19 10.18 10.25 11.05 12.13 (11.00) 9.69 10.11 .10.34 10.34 10.27 11.06 13.23 (12.00) 9.67 10.21 10.47 10.48 10.27 11.06 14.33 (13.00) 9.64 10.29 10.57 10.59 10.24 11.06 15.43 (14.00) 9.60 10.37 10.66 10.68 10.20 11.02 15.99 (14.51) 9.58 10.40 10.69 10.72 10.18 11.00 16.53 (15.00) 9.56 10.43 10.73 10.75 10.16 10.98 18.74 (17.00) 9.48 10.52 10.81 10.83 10.07 10.90 22.05 (20.00) 9.35 10.59 10.84 10.80 9.94 10.77 23.01 (20.87) 9.28 10.59 10.82 10.77 9.89 10.73 27.56 (25.00) 8.95 10.57 10.73 10.64 9.66 10.56 32.19 (29.20) 8.40 10.21 10.35 10.33 9.11 10.12 33.07 (30.00) 8.30 10.14 10.28 10.27 9.01 10.03 38.58 (35.00) 7.65 9.63 9.74 9.74 8.37 9.39 44.09 (40.00) - 7.02 9.09 9.21 9.21 7.73 8.76 49.60 (45.00) 6.38 8.56 8.67 8.68 7.10 8.13 54.79 (49.71) 3.98 -- -- -- -- -- 55.12 (50.00) -- 8.01 8.13 8.14 5.64 7.50 58.16 (52.77) -- -- -- 4.21 -- 60.63 (55.00) -- 6.35 6.92 6.91 -- 5.67 63.05 (57.20) -- -- --.. 4.54 63.50 (57.61) -- 5.03 5.62 5.61 ..-- 63.79 (57.87) -- 4.90 -- --... 65.09 (59.05) --.-- 4.89 .... 65.15 (59.10) -- -- 4.88 -- -- -- 70.00'(63.50) 3.98 4.90 4.88 4.89 4.21 4.54 REVISION 28 Page 27 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Figure 3.1-1 Most limiting MAPLHGR For GE14 Fuel 10 Of (L
-J 4 1 I I I II l 1l 1l 1l1l
]11 lI1 l l ! l I ~ l . . ., . . . W 0.0 10.0 20.0 30.0 40.0 50.0 60.0 GWDIST REVISION 28 Page 28 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Figure 3.1-2 Flow Dependent MAPLHGR Factor (MAPFACF) 1.100 1.000 0.900
"- 0.800 0.700 0.600 0.500 30.00 40.00 50.00 60.00 70.00 80.00 90.00 100.00 Core Flow %
REVISION 28 Page 29 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE*OPERATING LIMITS REPORT RTYPE G4.02 Figure 3.1-3 Power Dependent MAPLHGR Factors for GE14 Fuel Note: These MAPFACp factors are valid for Turbine bypass in or out of service and for Normal Feedwater heating 1 0.95 ,1ý, 0.9 0.85 0.8 MAPFACp for P > Pbypass, For P, % power > Pbypass and 32.5% < Pbypass < 45% 0.75 MAPFACp=0.00191(P-90) + 0.94, When 32.5 % < P < 90% C. MAPFACp = 0.006(P-1 00) + 1.0, when 90 % < P < 100 %
. 0.7 IL
< 0.65 4 1- ______ 4 MAPFACp = 0.557+ 0.00535(P-45) for Core Flow < 50%, P < Pbypass, where 0.6 32.5% < Pbypass < 45%
0.55 I I 0.5 '0-4 MAPFACp = 0.537 + 0.00785(P-45) for Core Flow > 50%, P < Pbypass, 0.45 32.5% -5Pbypass < 45% IIII I I I II 0.4 0.35 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100
% Power REVISION 28 Page 30 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 3.2 Linear Heat Generation Rate (LHGR) Reference Technical Specification: 3.11.B During reactor power operation, the LHGR of any rod in any fuel assembly at any axial location shall not exceed the rated power and rated core flow limits represented by Figure 3.2-1, with the detailed values presented in Reference 5.17. At other than rated power and rated flow conditions, the applicable limiting LHGR value for each fuel type is the smaller of the flow- and power-dependent LHGR limits, LHGRF and LHGRp. The flow-dependent LHGR limit, LHGRF, is the product of the LHGR flow factor, LHGRFAC F, shown in Figure 3.2-2 and the LHGR for rated power and flow conditions in Reference 5.17'. The power-dependent LHGR limit, LHGRp, is the product of the LHGR power factor, LHGRFACp, shown in Figure 3.2-3 and the LHGR for rated power and flow conditions in Reference 5.17. LHGR Curves in Figure 3.2-1 are representative curves for U02 fuel rods and Gd containing rods. Gd containing fuel rods have different LHGR limits that are also exposure dependent. Reference 5.17 documents the detailed proprietary curves and values. Pbypass is the power level below which more restrictive thermal limits are applied, as Turbine Stop Valve closure and Turbine Control Valve Fast Closure scrams are assumed to be bypassed. Pbypass can be set in anywhere in the range 32.5 to 45% core thermal power. Pbypass is currently set at 32.5% power. REVISION 28 Page 31 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Figure 3.2-1 Most Limiting LHGR for GE14 Fuel At Rated Power and rated Core Flow 14 13 12 11 10? S9 8 E z 7 C,
-J 6
5 4 0 10 20 30 40 50 60 70 Exposure, GWD/ST REVISION 28 Page 32 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Figure 3.2-2 Flow Dependent LHGR Factor (LHGRFACF) 1.100 1.000 0.900 C_)
- 0.800
-. I 0.700 0.600 0.500 -
30.00 40.00 50.00 60.00 70.00 80.00 90.00 100.00 Core Flow % REVISION 28 Page 33 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Figure 3.2-3 Power Dependent LHGR Factors Note: These LHGRFACp factors are valid for Turbine bypass in or out of service and for Normal Feedwater heating 1 0.95 0.9 0.85 -- -- -- + -- -- 0.8 LHGRFACp for P > Pbypass, For P, % power > Pbypass and 32.5% < Pbypass < 45% 0.75 LHGRFACp=0.00191(P-90) + 0.94, When 32.5 % < P < 90% LHGRFACp = 0.006(P-1 00) + 1.0, when 90 % < P < 100 % C, 0.
<0.7 ILL O 0.65
-r LHGRFACp = 0.557+ 0.00535(P-45) 0.6 for Core Flow < 50%, P < Pbypass, 32.5% 5 Pbypass < 45% 0.55 _____ _____ 4 4 I I
-: 4 +/- A 4
- I _____ I _____
0.5 0.45
.~~-h'~jL ____ __0 LHGRFACp = 0.537 + 0.00785(P-45) for Core Flow > 50%, P < Pbypass, 32.5% < Pbypass < 45%
0.4 L r t -~ . 0.35 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100
% Power REVISION 28 Page 34 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 3.3 Minimum Critical Power Ratio (MCPR) Reference Technical 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 power level less than Pbypass, the MCPRp 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 PBypaas, MCPRp is the product of the rated power and rated flow MCPR operating limit presen tedin Table 3.3-1, and the Kp factor presented in Figure 3.3-2, when Turbine Bypass is in service and from Figure 3.3-3, when Turbine Bypass is out of service. The rated power and flow MCPR operating limits presented in Tables 3.3-1 are functions of T. Both Figures 3.3-2 and 3.2-3 include normal and reduced feed water temperature operating modes. For SLO MCPRp and MCPRF are raised by 0.02 compared to TLO values shown in Figures 3.3-2 and 3.2-3. The value oft in Table 3.3-1 shall be equal to 1.0, unless it is calculated from the results of the surveillance testing of Technical Specification 4.3.C. TS 4.11.C defines -r. Pbypass is the power level below which more restrictive thermal limits are applied, as Turbine Stop Valve Closure and Turbine Control Valve Fast Closure scrams are assumed to be bypassed. Pbypass can be set anywhere in the range 32.5% to 45% core thermal power. Pbypass is currently set at 32.5%. REVISION 28 Page 35 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Table 3.3-1 MCPR Operatinq Limits At Rated Power and Rated Flow The MCPR Operating Limit for Two Loop Operation (OLMCPRTLO) is a function exposure and t, derived from scram timing measurements BOC to (EOR-1.9) (EOR-1.9) to EOC GWD/ST GWD/ST 0.0 1.44 1.49 0.0 0.1 1.46 1.51 0.1 0.2 1.47 1.53 0.2 0.3 1.48 1.55 0.3 0.4 1.49 1.56 0.4 0.5 1.50 1.58 0.5 0.6 1.51 1.60 0.6 0.7 1.52 1.61 0.7 0.8 1.53 1.63 0.8 0.9 1.54 1.65 0.9 1.0 1.55 1.66 BOC = Beginning Of Cycle EOC = End Of Cycle EOR = End Of Rated Power Operation At Rated Flow Note: Rated OLMCPR Limits for Turbine Bypass Valve OOS and Final Feedwater Temperature Reduction are the same as those for normal Feed water Temperature and Turbine bypass Valves in service, as OLMCPR is limited by the inadvertent HPCI injection event that is conservatively assumed to cause a Turbine Trip. Off rated MCPR limits are affected by TBVOOS condition and are shown in the off-rated limit curves in Figures 3.3-1, 3.3-2 and 3.3-3 and the Supplemental Reload Licensing Report (Reference 5.15). Sinqle Loolp Operation OLMCPR SLO = 0.02 + OLMCPR TLO, where OLMCPR TLO is selected from the Table above. REVISION 28 Page 36 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Figure 3.3-1 Flow Dependent MCPR Limits (MCPR F) for GE14 fuels 1.700 .f./.0.
. . . =Max[1.2, . . . . SLMCPR*. . . . . (Af *WT/100. ...
, .- . . . .; ,. - --- -,_m
- 1107
_ '"10, 0 2 .5%max f lo w
% m a xflow -- ' MCPRF + ) 10 S--0 112%maxflow S117%.max flow ' Max Core Flow Af Bf 1.600
,.I7ý .
IT 1100omaxflow 1 %ma flow 102.5 % -0.571 1.655 lii , L,., I I 107.0% -0.586 1.697 0
.110.0% -0.596 1.727 T -F-H-,-, 112.0% -0.602 1.747 "1.500
-H 117.0% -0.632 1.809 C.)
.... ', .. .. For SLO MCPRf is raised by 0.02 copared t 7 --I 7 -- -T I-r - -I-1 T
- 1.400 C- 1.40 .- 'L ', .. L..+ . -! , , * , ." ', '1, vaue shw in the Figue abve.
C.) ii~
.30.0 1
~
35 I- I -i L -i 0I6 r 1 45. 1i 1 ' 50 ... . 6. 700 5 0 85 i7
-i- -f -i-- - -r,
. 9.0 1 00.
iF i T i i1ii I T -1 1 1 , 1 T
*" 1.200 "I T
-------- - 7 i-,- r- i i i r, T , -!7-, T -- -- ]7 i r --- '7-- ] , i f i Core Flow, % Of Rated RE\o'ISION 26 COLR PAGE 37 OF 45 REVISION 28 Page 37 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Figure 3.3-2 Power Dependent MCPR Limits (MCPRp) for GE14 fuel Turbine Bypass Is Assumed Operable and Normal and Reduced Feed Water Temperature 3.50 OLMCPRp = 2.53+0.0335(45% - P) "
- - - when 25% < P < Pbypass and Core flow > 50%
3.00 P= % Power and 45 % > Pbypass > 32.5% 2.50 a2. OLMCPRp = 1.97+0.021(45-P) 0. __ - when 25% 5 P 5 Pbypass and Core flow 5 50% ,-J 0 P= % Power and 45% Ž Pbypass Ž 32.5% When P < Pbypass and in SLO, OLMCPRp 2.00 is raised by 0.02 compared to TLO values. -
, When P > Pbypass and in SLO, Rated OLMCPR is raised by 0.02 before multiplying by Kp to calculate OLMCPRp -
1.50 Kp = 1.0 + 0.00375(100% - P) for P > Pbypass P= % Power and 45% > Pbypass > 32.5% 1.00 25 35 45 55 65 75 85 95
% Power REVISION 28 Page 38 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 Figure 3.3-3 Power Dependent MCPR Limits (MCPRp) for GE14 fuel Turbine Bypass Is Assumed out of service and Normal Feed Water Temperature 4.10
- NCPRp =2.50 + 0.08(45- P) for; 390 Core flow > 50%, P= % Power and 380 25% < P < Pbypass, 45 % Ž Pbypass - 32.5% -
3.70 360 -- . __ 3.50 _ 3.30 OLMCPRp = 2.01 + 0.0455(45 - P) Core flow < 50% and P= % Power 25% - P -< Pbypass, 45 % Z>Pbypass ->32.5% 3.10 3.00 2.70 V When P < Pbypass and in SLO, " 2.60 OLMCPRP is raised by 0.02 compared to 0 2.50 TLO values. When P > Pbypass and in SLO, Rated 2.40 OLMCPR is raised by 0.02 before - 2.30o . - multiplying by Kp to calculate OLMCPRP - 2.20 2.10 2.00 1.90 1.80 1.70 Kp =1.0 + 0.00375(100% - P) for P > Pbypass - 1.60 . P= % Power and 45% > Pbypass - 32.5% 1.50 1.40 1.30 I 1.20 25 30 35 40 45 s0 55 60 65 70 75 80 85 90 95 100
% Power REVISION 28 Page 39 of 45
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 when in Two Loop Operation and Figure 3.4-2 when in Single Loop Operation. Cycle 17 operation is not fully analyzed for reduced feedwater temperature for issues other than thermal limits. This report contains only the thermal limit analysis results for reduced feed water temperature mode. Cycle 17 Stability analysis, the exclusion and the buffer regions shown in Figure 3.4-1 and Figure 3.4-2 are based on Stability Solution I-D (references 5.5, 5.12, 5.15 and 5.18) APRM trip set points are based on Drive flow rather than core flow. Scram Allowable trip set points as a function of drive flow are shown in Figures 2.1-1 for Two Loop Operation and 2.1-2 for Single Loop Operation. Rod Block Allowable trip set points as a function of drive flow are shown in Figures 2.2-1 for Two Loop Operation and 2.2-2 for Single Loop Operation. Figures 3.4-1 and 3.4-2 show APRM Scram and Rod Block lines using Allowable values as a function of Core Flow. Single Loop Analysis limits the maximum rod line allowed for SLO operation as the rod line with a maximum power of 65% and a core flow of 52% of rated due to SLO vessel internal vibration (Ref. 5.7, p. 1-2). Equations for various lines on the Power to flow map are described in Ref. 5.14. REVISION 28 Page 40 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 FIGURE 3.4-1 PILGRIM POWER I FLOW MAP Scram and Rod Block Data based on Allowable Values CORE FLOW, MLB/HR 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 125 2535 120 LftJ114Jilt i ft~j LI I ll- IlrIitliti i Lt1 Ii lt~i-I l.J.l-:J 1 jJi£ft% APRM SCRAM CLAMP AT12 % 0 Ir 1 1 7!*rt-IF 2434 TT-T.... AA* Tp[-M nT-1447 115 2332
.i.APRM RODBLOCKCLAMP AT 115%
110 2231 v....L...-.... .. '71i -*,*: *:.i,' OPERATION 2129 105 4T-4tv- TT - L- ' ' Y, 44"-* PROHIBITED a 100 2028 95 . 1927 171 I- l 1 J-- - t
-i- i4::111 V-]4 7F 1 t77 ,C 90 -riiI= -IT1 =Ui- F IT41 II LII +- 1 17jiT--11 1'~ T I~ f I Aiidl 1825 85 1724 I-80 mi---t-T--iv - ----
" i*"i - T I 1-m- -'-' -"- i -tRFLOW 1622 75 iL.t- i v-......... . t I t- -- 1521 70 0 0 65 l I; J - -I 4 i O L 1318 w
.0
-J 60 1217 uJ 55 1115 50 .~ .,~ -ti*Fi till: lilWt- ifP it tT -4 u REGION 1014 C., 45 IR . . . . . . . . ..
913 I.-
. . .. OIET E LU 40 811 0 0 35 710 BOWER MLNIMU 0(
0 30 608 N. 1A -t i I T -.1t I 25 f PUMP MIN .l~ fl-~ (267 '-1 4-Fli-p¶-U *.,T --* I- TFI i-- . .-- 507 20 - MINIMUM POWER__ 406 15 304 10 411LNEIIT F MIN PUMP SPEED (26/) ilIV- tF ~l li I V44 203 5 0
-TY~~ 1 T I-f v-j 101 0
0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 CORE FLOW, MLB/HR REVISION 28 Page 41 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 FIGURE 3.4-2 PILGRIM POWER I FLOW MAP - Single Loop Operation Scram and Rod Block Data based on Allowable Value Setpoints CORE FLOW, MLB/HR 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80
' ' ...... .. ' 2535 125 T-rjf [- jiIi F1-- J1f .-- *li*J . tI I tFP I-I-trF F"-APRM LT-1' ThI'I-:":-3--*fm I SCRAM CLAMP AT 120%
2<*I 2434 120 4--Tl'ii.Iifhli lTIT]-ui[V fii=-P-lu-l-ll: [-i----1 2332 115 110 TAPRM ROD BLOCK CLAMP1AT 115% 105 100 IIVI7Ilulil
........ --,----, 'lI:V*i74 1441..
.. . ... fi .. .2028Ii~~'~
95 90 At OUNAR 1. A 'I 1-- ..... 1+ 9J 85 0 80 [4 4- ---- . . ... O. -*,---1 -- RATION PlT .............
... Th 1 T4i1-+
. - 1115 1622 w 75 .
il} *:!N!; iAe f*71 0 70 NA1ICLNE 7--' "---
-- i-*..M
- - - - PROHIBITED R BiLOC CLAMP A 7- 1318 1217 aJ 0- 65 LWR BOUND AR Aýs lý 41 T1 72 60
-J 55
- A--j I M ."-- 1801 50 IX 0~ I-I--
45 n.) wl 40 I IN U ý-- PP LIN E I ---- I -nti -L~s)
-2/o
-~ 4 ~ 1
.-.- --- -T--- 42 0-i-I II f-IH IIII f-KI O+ERATION 44~ . 0 00 35 TTT~~~~~~~~ -- -j --~-~ -il-11
-i --4. -j1t 1018
-h~~~.1VK U
30 A0 25 20 1* L-NE CIRCi~
-*r-r SLO 2---{
PM SP MINIMUWM POWER INTERLOCK ....
-*-t --4*-----
-IN j :-:
406 406 15 10 5 0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 CORE FLOW, MLB/HR REVISION 28 Page 42 of 45
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. Cycle Fuel Type Loaded Number Irradiated: GE14-PIODNAB412-16GZ-100T-145-T6-3901 (GE14C) 14 97 GE14-P1ODNAB397-10G6.0/3G5.0-10OT-145-T6-2613 (GE14C) 15 35 GEl 4-P1ODNAB397-14GZ-10OT-145-T6-2621 (GEl 4C) 15 88 GE14-P1ODNAB398-8G6.0/5G5.0/1 G2.0-10OT-145-T6-2614 (GE14C) 15 40 GE 14-P1ODNAB399-10G6.0/3G5.0/1G2.0-10OT-145-T6-2828 (GE14C) 16 104 GE14-P1ODNAB398-8G6.0/5G5.0/2G4.0-1 00T-145-T6-2829 (GE14C) 16 56 New: GE14-P1ODNAB400-12G6.0/3G5.0-1OOT-145-T6-2961 (GE14C) 17 32 GE14-P1ODNAB398-5G6.0/10G5.0-10OT-145-T6-2958 (GE14C) 17 32 GE14-P1ODNAB399-15GZ*100T-145-T6-2957 (GE14C) 17 32 GE14-P1ODNAB400-13GZ-10OT-145-T6-2959 (GE14C) 17 24 GE14-P1 ODNAB404-5G6.0/10G5.0-10OT-145-T6-2960 (GEl 4C) 17. 40 Total: 580 The reactor vessel core contains 145 cruciform-shaped control rods. The control materials used are either boron carbide powder (B4 C) compacted to approximately 70% of the theoretical density or a combination of boron carbide powder and solid hafnium. REVISION 28 Page 43 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02 FIGURE 4.0-1 Reactor Vessel Core Loading Pattern 52 MF [F] E]_F]E_] []EF] EFEF] MFF] DF [] 48 [] [] E] A] EC EB] [ ] [C] A] ]A [M ] E] 46 W I 9L EL2M 44 r[.__][EF] I F..IH-] [M] . [E] C] [1]EM [A [] EGI[G]E1 [1] EC] EE][I] [H] M~MI[FE] [--] 42 F'-'--'v 'l I"* r"'-U-'" 40 EFE] [K] [..f11C_ .F [D] [E] [E] [H]EL]EC]E] [K] [K] [A]EC] [L] [HEK] [D MFI__FI_2- ] 38 L E ' F[L 36 EF[]EK]_IF[C [DD __D] [fl [H]EA] [M]K]H9E]EC ]_Z IECr]_EL*] 9HEK) ]M] [AH[I] [fl [D] [CD[~ ] 32 [F]__ll- [E[]_.I[E] [E][BE]II-EC]_I [B]B] [HEEC] [ LE*- ZF ] [H] fC[]B [H
] [D § E] [fl [K] EE] [fl [K] [F]
16 0E INME N -- 28 [F]_1_@2M[]__F MGII- FI[CE] rKf EC_1][K] [1H EA[K]I*[ [K)) _[][H))E[A ] [] [] [] [ 24 [FE]_[E_] H--EI [A] EC][A][G]_.r EL_
] [EH][L][EA] [AD_[MM [LEII
[H] OL[G] A_,2F C]JFA]E]HE] 20 F]_ HMF [E]_* [CgE] [G] [L]__flE+]__-[E] []+EH [K]_EI[+H II*] KIIII[_ZF M][][ 14 :- rH Lo Fl]El]FB 16[][F CDE][HE][E] 12 3 5 10] 7 9 11 _- [E[A[C][BE][G]AE]A[]1[]EKID[B] 131517I1921- 23 25 27 2 Ell [g((M][E]H][E]M F9l33E] [35 [3] 39_41 Fllý+C i
]rF"I[
E4344[ C[F F] 45 1 0 MF-Ir+El[ FIFIM EIRE] II ME [H D]E]-]K][E 1~~~~~~~~~~~~ 7 11 51 1 12rC 52 9 13 53c9414 54 95 Fuel Type A=GE 14-P 1ODNAB404-5G6.0/1 OG5.0- I GOT- 145-T6-2960 (Cycle H=GE 14-P 10DNAB398-8G6.0/5G5.0/2G4.0-100T- 145-T6-2829
- 17) (Cycle 16)
B=GE 14-P IODNAB398-5G6.0/I 0G5.0-IOOT- 145-T6-2958 (Cycle I=GE 14-P I ODNAB398-5G6.0/10G5.0-I0OT- 145-T6-2958
- 17) (Cycle 17)
C=GEI4-P IODNAB399-I0G6.0/3G5.0/IG2.0-10OT- 145-T6-2828 J=GE14-PIODNAB400-12G6.0/3G5.0-100T-145-T6-2961 (Cycle 16) (Cycle 17) D=GE 14-P1ODNAB400-13GZ- IGOT- 145-T6-2959 K=GE 14-P1ODNAB397-14GZ- 100T-145-T6-2621 (Cycle 17) (Cycle 15) E=GE 14-P 10DNAB399-1 5GZ- 1001- 45-T6-2957 L=GE 14-P IODNAB400-12G6.0/3G5.0-1001T-145-T6-2961 (Cycle 17) (Cycle 17) F=GE 14-P IODNAB412-16GZ- 100T-145-T6-3901 M=GE 14-PI ODNAB398-8G6.0/5G5.0/I G2.0-1001T-145-T6-2614 (Cycle 14) (Cycle 15) G=GEI4-PIODNAB397-I0G6.0/3G5.0-I001T-145-T6-2613 (Cycle 15) REVISION 28 Page 44 of 45
PILGRIM NUCLEAR POWER STATION PNPS CORE OPERATING LIMITS REPORT RTYPE G4.02
5.0 REFERENCES
5.1. NEDE-24011-P-A-15 and NEDE-24011-P-A-15-US, "General Electric Standard Application for Reactor Fuel", September 2005. 5.2. ER05120685, Cycle 17 Reload Core Design. 5.3. NEDC-31852-P, rev. 4, " SAFER/GESTR-LOCA Loss-of-Coolant Accident Analysis for Pilgrim Nuclear Power Station ", January 2008. 5.4. NEDC-33155P, Rev.0, Application of Stability Long-Term Solution Option I-D To Pilgrim Nuclear Power Station, October 2004. 5.5. GE-NE-0000-0056-2695-RO, Option I-D Stability Eclusion Region Analysis for Pilgrim Cycle 17, February 2007. 5.6. ,GE-NE-GENE-0000-0033-6871-01, Rev. 0, Pilgrim Option I-D APRM Flow Biased Set points, October 2004. 5.7. GE-NE-0000-0027-5301, Rev 2, Pilgrim Nuclear Power Station Single Loop Operation, April 2006. 5.8. S&SA-1 86, Stability AWD calculation. 5.9. SUDDS/RF 94-42, NEDC-32306P, "Maximum Extended Load Line Limit Analyses", March 1994. 5.10. SUDDS/RF 88-160, NEDC-31312-P, "ARTS Improvement Program Analysis for Pilgrim Nuclear Power Station", September 4, 1987. 5.11. A22-00109-00 MAPLHGR set down process explanation for Pilgrim, November 2001. 5.12. C17DIVOM, Pilgrim C17 Stability Detect and Suppress Confirmation with Plant-Specific DIVOM, GE-NE-0000-0066-0823-RO, 3/21/2007. 5.13. ER 03110960, Stability I-D implementation. 5.14. PNPS-RPT-03-00001, Rev. 3, "Pilgrim Power To Flow Map Report." 5.15. 0000-0056-6173SRLR, "Supplemental Reload Licensing Report, Reload 16, Cycle 17." February 2007. 5.16. -Calculation S&SA-194, Cycle 17 OPL-3, transient Analysis Inputs. 5.17. 0000-0056-6173FBIR, Rev.0, February 2007, Fuel Bundle Information Report, Cycle 17. 5.18. SUDDS/RF 02-86, GNF SER issued by NRC approving elimination of Upper Bound PCT limit requirement. 5.19. Calculation S&SA-158, OPL 4 & 5, Accident Analysis Inputs. 5.20. NEDO-32465A, Licensing Topical report "Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Application, August 1996. 5.21. EDE-49-1290, Rev. 2, DRF#C51-00082-5, GE APRM, RBM and TS Set point Calculations for BECO, Pilgrim Nuclear power Station, 6/14/1991 (Attachment to SUDDSRF91-104) 5.22. GNF Letter, EWG-ENO-HK1-09-002, "Pilgrim Cycle 17 MAPLHGR Extension", dated March 24, 2009. REVISION 28 Page 45 of 45}}