JAFP-02-0200, Core Operating Limits Report Revision 14 (Cycle 16)
| ML022980058 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/14/2002 |
| From: | Ted Sullivan Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-02-0200 | |
| Download: ML022980058 (37) | |
Text
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc James A Fitzpatrick NPP P0 Box 110 "E-- Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 T.A. Sullivan Vice President, Operations-JAF October 14, 2002 JAFP-02-0200 United States Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop O-PI-17 Washington, DC 20555-0001
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Core Operating Limits Report Revision 14 (Cycle 16)
Dear Sir; Attached is Revision 14 to the James A. FitzPatrick Core Operating Limits Report (COLR). This report is submitted in accordance with Technical Specifications 5.6.5.
Revision 14 of the COLR incorporates changes as a result of implementation of Cycle 16 requirements including the GE 14 fuel design. In addition, editorial corrections and administrative changes are included that do not alter the intent.
There are no commitments contained in this report.
Questions concerning this report may be addressed to Mr. William Drews (315) 349-6562.
Very truly yours, T..
TAS:GB:Ias Attachment as stated cc: next page
cc: Regional Administrator U.S. Nuclear Regulato& Commission 475 Allendale Road King of Prussia, PA 19406 Office of the Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, New York 13093 Mr. Guy Vissing, Project Manager Project Directorate I Division of Licensing Project Management U.S. Nuclear Regulatory Commission Mail Stop 8C2 Washington, DC 20555
Entergy NuclearNortheast ENTERGY NUCLEAR OPERATIONS, INC.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT REPORT CORE OPERATING LIMITS REPORT REVISION 14 REVIEWED BY: PLANT OPERATING REVIEW COMMITTEE MEETING NO. DATE: /011 o-APPROVED BY: WiRliam Drews A-, DATE:
REACTOR ENGINEERING SUPERINTENDENT DATE:
APPROVED BY: Brian O'Grady GENERAL MANAGER - PLANT OP(TIONS
CORE OPERATING LIMITS REPORT CYCLE 16 TABLE OF CONTENTS SECTION PAGE 1.0 PU RPO SE ............................................................................................................... 3 2.0 APPLICABILITY ................................................................................................... 3
3.0 REFERENCES
...................................................................................................... 3 4.0 DEFINITIONS ...................................................................................................... 4 5.0 RESPONSIBILITIES ............................................................................................ 5 6.0 SPECIAL INSTRUCTIONS/REQUIREMENTS .......................................... 5 7.0 PROCEDURE ................................................................................................... 6 7.1 Operating Limit MCPR ....................................................................... 6 7.2 Average Planar Linear Heat Generation Rate (APLHGR) .................. 8 7.3 Linear Heat Generation Rate (LHGR) ................................................. 8 7.4 APRM Trip Settings ............................................................................. 9 7.5 RBM Upscale Rod Block Trip Setting ............................................... 10 7.6 Stability Option 1-D Exclusion Region and Buffer Zone ................... 10 7.7 Kf - Flow Dependent MCPR Limit .................................................... 11 8.0 FIGURES AND TABLES ................................... .... 12 9.0 EXHIBITS ....................................................................................................... 13 Rev. No. 14 Page- _of 35
CORE OPERATING LIMITS REPORT CYCLE 16 1.0 PURPOSE This report provides the cycle-specific operating limits for Cycle 16 of the James A.
FitzPatrick Nuclear Power Plant. The following limits are addressed:
"* Operating Limit Minimum Critical Power Ratio (MCPR)
"* Flow Dependent MCPR Limits
"* Average Planar Linear Heat Generation Rate (APLHGR)
"* Linear Heat Generation Rate (LHGR)
"* Flow-Biased Average Power Range Monitor (APRM) and Rod Block Monitor (RBM)
Settings
"* Stability Option ID Exclusion Region 2.0 APPLICABILITY The plant shall be operated within the limits specified in this report. If any of these limits are violated, the corrective actions specified in the Technical Specifications shall be taken.
3.0 REFERENCES
3.1 JAFNPP Administrative Procedure 12.05, Control of Core Operating Limits Report.
3.2 JAFNPP Technical Specifications.
3.3 FitzPatrick Cycle 16 Core Reload Safety Evaluation, JAF-SE-02-11.
3.4 GE Report, Supplemental Reload Licensing Report for James A. FitzPatrick Reload 13 Cyclel 4, J1 1-03359SRL, Rev.1, October 1998 3.5 GE Report, Supplemental Reload Licensing Report for James A. FitzPatrick Reload 12 Cyclel 3, J 11-02914SRL Rev.0, August 1996.
3.6 Design Change Package JD-01-102, Cycle 16 Core Reload 3.7 RAP-7.3.17, Core Monitoring Software and Database Changes.
3.8 Plant Operation Up To 100% Power With One Steam Line Isolated, JAF-SE-96-035.
3.9 James A. FitzPatrick Nuclear Power Plant Kf Curve Update, GE-NE-J11-03426-00-01, September 1998.
3.10 General Electric Standard Application for Reload Fuel, NEDE-24011-P-A-14 Rev. No. 1_4 Page 3 of 3_5
CORE OPERATING LIMITS REPORT CYCLE 16 3.11 GE Nuclear Energy, L.P. Harding, "Fuel-Rod Thermal-Mechanical Performance Limits for GE12", DB-0012.01, Rev 1, Sept. 2000.
3.12 GE Lattice Dependent MAPLHGR Report for James A. FitzPatrick, Reload 12 Cyclel3, J1 1-02914MAP, Rev. 0, August 1996.
3.13 GE Lattice Dependent MAPLHGR Report forJames A. FitzPatrick, Reload 13, Cycle14, J11-03359MAPL, Rev. 0, October 1998.
3.14 GNF Report, Supplemental Reload Licensing Report for James A. FitzPatrick Reload 15 Cycle16, 0003-9220SRLR, Rev.0, Class I, August, 2002.
3.15 JAF-SE-00-032, Rev.0, Extended Loadline Limit Analysis (ELLLA) Implementation.
3.16 JAF-RPT-MISC-04054, Rev.0, Operation under Extended Loadline Limit Analysis (ELLLA) and Power Uprate 3.17 GNF Report, Supplemental Reload Licensing Report for James A. FitzPatrick Reload 14 Cycle15, J11-037579SRL, Rev.0, Class I, August, 2000.
3.18 GNF Report, Lattice Dependent MAPLHGR Report for James A. FitzPatrick, Reload 14, Cyclel5, J11-03757MAPL, Rev. 0, Class III, August, 2000.
3.19 GE Letter, FitzPatrick APRM Flow Biased Rod Block and Scram Setpoints, NSA01-273, July 3, 2001 3.20 GE Letter, R. Kingston to P. Lemberg, Scram Time Versus Notch Positions for Option B, REK-E: 02-009, May 28,2002 3.21 GE Report, James A. FitzPatrick Nuclear Power Plant Final Feedwater Temperature Reduction NEDC-33077, September 2002.
3.22 JD-02-122, Final Feedwater Temperature Reduction Implementation.
3.23 GE Report, GEl4 Fuel Design Cycle-Independent Analyses for J. A. Fitzpatrick Nuclear Power Plant, GE-NE-0000-0002-1752-01P, Rev. 0, DRF 0000-0002-1752, September 2002.
3.24 GNF Report, Lattice Dependent MAPLHGR: Report for James A. FitzPatrick, Reload 15, Cyclel6, 0003z9220MAPL, Rev. 0, Class III, August, 2002.
3.25 GE Nuclear Energy, M. T. Kiernan, "Fuel-Rod Thermal-Mechanical Performance Limits for GE14C", DB-0012.03, Rev 0, May 2000.
4.0 DEFINITIONS 4.1 Average Planar Linear Heat Generation Rate (APLHGR):
Rev. No. 1..4.. Page 4 of 35
CORE OPERATING LIMITS REPORT CYCLE 16 The APLHGR shall be applicable to a specific planar height and is equal to the sum of the heat generation rate per unit length of fuel rod for all the fuel rods in the specified assembly at the specified height divided by the number of fuel rods in the fuel assembly at the height.
4.2 Fraction of Limiting Power Density:
The ratio of the linear heat generation rate (LHGR) existing at a given location to the design LHGR. The design LHGR is given in Table 8.2.
4.3 Linear Heat Generation Rate(LHGL):
The LHGR shall be the heat generation rate per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
4.4 Maximum Fraction of Limiting Power Density (MFLPD):
The MFLPD shall be the largest value of the fraction of limiting power density in the core.
The fraction of limiting power density shall be the LHGR existing at a given location divided by the specified LHGR limit for that bundle type.
4.5 Minimum critical power ratio (MCPRW:
The MCPR shall be the smallest critical power ratio (CPR) that exists in the core for each type of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
4.6 Rated Recirculation Flow:
That drive flow which produces a core flow of 77.0 x 106 lb/hr.
5.0 RESPONSIBILITIES NOTE: See AP-12.05 (Reference 3.1).
5.1 Shift Manager.
Assure that the reactor is operated within the'limits described herein. -
5.2 Reactor Engineering Superintendent:
Assure that the limits described herein are properly installed in the 3D-Monicore databank used for thermal limit surveillance (Reference 3.6) 6.0 SPECIAL INSTRUCTIONS/REQUIREMENTS Not Applicable Rev. No. 14 Page 5 of 35
CORE OPERATING LIMITS REPORT CYCLE 16 7.0 PROCEDURE 7.1 Operating Limit MCPR During operation, with thermal power ->25% rated thermal power, the Operating Limit MCPR shall be equal to or greater than the limits given below.
7.1.1 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR) 7.1.2 The Operating Limit MCPR shall be determined based on the following requirement:
7.1.2.1. The average scram time to notch position 36 shall be:
"IAVE < TEB 7.1.2.2. The average scram time to notch position 36 is determined as follows:
T AVE n ZNI WHERE:
n = Number of surveillance tests performed to date in the cycle, Ni = Number of active rods measured in the surveillance i T = Average scram time to notch position 36 of all rods measured in surveillance test i.
Rev. No. 1_.4 Page _L of 35
4 CORE OPERATING LIMITS REPORT CYCLE 16 CORE OPERATING LIMITS REPORT CYCLE 16 7.1.2.3. The adjusted analysis mean scram time is calculated as follows:
1/2
+ 1.65 " N, VB(sec)
=il WHERE:
= Mean of the distribution for the average scram insertion time to the dropout of notch position 36 = 0.830 sec.
C = Standard deviation of the distribution for average scram insertion time to the dropout of notch position 36 = 0.019 sec.
N1 = The total number of active rods measured in Technical Specification SR 3.1.4.4.
The number of rods to be scram tested and the test intervals are given in Technical Specification LCO 3.1.4, Control Rod Scram Times 7.1.3 When requirement of 7.1.2.1 is met, the Operating Limit MCPR shall not be less than that specified in Table 8.1, Table 8.1.A, Table 8.1.B or Table 8.1.C as applicable.
7.1.4 WHEN the requirement 7.1.2.1 isnot met (i.e. TB < 'AVE), THEN the Operating Limit MCPR values (as a function of -) are given in Figure 8.1, Figure 8.1.A, Figure 8.1.B or Figure 8.1.C as applicable.
(CAVE - TBO (TrA - TrB)
WHERE:
- AVE = The average scram time to notch position-36 as defined in 7.1.2.2.
TB = "The adjusted analysis mean scram time as defined in 7.1.2.3.
TA = the scram time to notch position 36 as defined in Technical Specification Table 3.1.4-1.
Rev. No. 1_b4 Page 7 of 35
CORE OPERATING LIMITS REPORT CYCLE 16 NOTE: IF the operating limit MCPR obtained from these figures is determined to be less than the operating limit MCPR found in 7.1.3, THEN 7.1.3 shall apply.
7.1.5 During single-loop operation, the Operating Limit MCPR shall be increased by 0.01.
7.1.6 During reactor power operation with core flow less than 100 percent of rated, the Operating Limit MCPR shall be multiplied by the appropriate Kf specified in Figure 8.2.
7.2 Average Planar Linear Heat Generation Rate (APLHGR) 7.2.1 Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR) 7.2.2 During operation, with thermal power > 25% rated thermal power, the APLHGR for each fuel type as a function of axial location and average planar exposure shall be within limits based on applicable APLHGR limit values which have been approved for the respective fuel and lattice types.
7.2.3 When hand calculations are required, the APLHGR for each type of fuel as a function of average planar exposure shall not exceed the limiting value for the most limiting lattice shown in Figures 8.3.A through G.
7.2.4 During single loop operation, the APLHGR for each fuel type shall not exceed the values given in 7.2.2 or 7.2.3 above multiplied by the appropriate value (0.78 for GE12 and GE14 fuel).
7.3 Linear Heat Generation Rate (LHGR) 7.3.1 Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR) 7.3.2 During operation, with thermal power > 25% rated thermal power, the LHGR for each fuel type as a function of axial location and average planar exposure shall be within limits based on applicable LHGR limit values which have been approved for the respective fuel and lattice types.
7.3.3 When hand calculations are required, the LHGR for each type of fuel shall not exceed the limiting value-for the most limiting lattice as sppecified in Table 8.2 and shown in Figures 8.5A and 8.5B.
Rev. No. 14 Page _8 of 35.
CORE OPERATING LIMITS REPORT CYCLE 16 7.4 APRM Trip Settings 7.4.1 APRM Flow Referenced Flux Scram Trip Setting (Run Mode) 7.4.1.1. Technical Specifications:
LCO 3.2.4, Average Power Range Monitor (APRM) Gain and Setpoint LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation 7.4.1.2. When operating in Mode 1, the APRM Neutron Flux-High (Flow Biased)
Trip setting shall be:
S < 0.58W + 66% for two loop operation; S 5 0.58W + 66% - 0.58 AW for single loop operation; WHERE:
S = Setting in percent of rated thermal power; W = Recirculation flow in percent of rated; AW = Difference between two loop and single-loop effective drive flow at the same core flow.
NOTE: Concerning APRM Neutron Flux-High (Flow Biased) Rod Block and Scram Trip settings: Reference 3.19 establishes Equivalent Analytical Limits for these settings. The nominal trip setpoint S :< 0.58W + 62%
(with clamp at 117%) for the Scram. Compliance with the "Allowed Region of Operation" on the Power-Flow Map, Figure 3.7-1 of the FSAR is defined by the equation 0.58W + 50% and is individually controlled and assures boundaries are not exceeded during normal operation.
7.4.1.3. In the event of operation with a Maximum Fraction of Limiting Power Density (MFLPD) greater than the Fraction of Rated Power (FRP), the setting shall be modified as follows:
S < (0.58W + 66%)(FRP/MFLPD) for two loop operation; S 5 (0.58W + 66% - 0.58-AW)(FRP/MFLPD) for single-loop operation; WHERE:
FRP = Fraction of Rated Power, MFLPD = Maximum Fraction Of Limiting Power Density, see Definition 4.4.
The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the design value of 1.0, in which case the actual operating value will be used.
Rev,. No. 1__4 Page 9 of 35
CYCLE 16 CORE OPERATING LIMITS REPORT 7.4.2 APRM Neutron Flux-High (Flow Biased) Rod Block Trip Setting (Relocated to the Technical Requirements Manual) 7.5 RBM Upscale Rod Block Trip Setting 7.5.1 Technical Specification LCO 3.3.2.1, Control Rod Block Instrumentation 7.5.2 The RBM upscale rod block trip setting shall be:
S < 0.66W + K for two loop operation; S < 0.66W + K - 0.66 AW for single loop operation; WHERE:
S = rod block setting in percent of initial; W = Loop flow in percent of rated K = Intercept values of 39%, 40%, 41%, 42%, 43%, and 44% can be used with the appropriate MCPR Operating Limit from Table 8.1 (note for Cycle 16 I the RBM intercept value does not effect the MCPR Operating Limit for K values < 44%)
AW = Difference between two loop and single loop effective drive flow at the same core flow.
7.6 Stability Option 1-D Exclusion Region and Buffer Zone.
7.6.1 Technical Specification LCO 3.4.1, Recirculation Loops Operating 7.6.2 The reactor shall not be intentionally operated within the Exclusion Region given in Figure 8.4 when the SOLOMON Code is operable.
7.6.3 The reactor shall not be intentionally operated within the Buffer Zone given in Figure 8.4 when the SOLOMON Code is inoperable.
Rev. No. 1_4_ Page -0 of 35
CORE OPERATING LIMITS REPORT CYCLE 16 CORE OPERATING LIMITS REPORT CYCLE 16 7.7 K* - Flow Dependent MCPR Limit Figure 8.2 is the Kf limit. Values of Kf are obtained using the following equation (see Reference 3.9):
Kf = MAX [1.0, A - SLOPE
- WT]
WHERE:
WT = Core Flow as % of Rated, 30% < WT :5 100%
SLOPE = (AF/100/OLMCPR) * (SLMCPR /SLMCPR generic)
A = (BJ/OLMCPR) * (SIMCPR /ST MCPR generic)
SLMCPR generic = 1.07 SLMCPR = Technical Specification LCO 2.1.1, Reactor Core SLs OLMCPR= The lowest value obtained from Figures 8.1, 8.1.A and 8.1.C as per 7.1.4, or, if the note in 7.1.4 applies, then 7.1.3 requirement must be met.
At, BF = Coefficients for the Kf curve listed below:
Scoop Tube Setpoint % Ar Br 102.5 0.571 1.655 107.0 0.586 1.697 112.0 0.602 1.747 117.0 0.632 1.809 All coefficients apply to Manual Flow Control Mode Rev. No. 1_4 Page 11 of 35
CORE OPERATING LIMITS REPORT CYCLE 16 8.0 FIGURES AND TABLES 8.1 FIGURES Figure 8.1. MCPR Operating Limit Versus T for GE12 and GEl4.
Figure 8.1 A. MCPR Operating Limit Versus t for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service for GE12 and GEI4. I Figure 8.1.B MCPR Operating Limit Versus -r for Operation with Turbine Bypass Valves Out of Service Figure 8.1.C MCPR Operating Limit Versus -r for Operation with Final Feedwater Temperatuic Reduction Figure 8.2 Kf Factor Figure 8.3A APLHGR versus Planar Average Exposure GE12-P1ODSB405-16GZ-10OT-150-T-2396.
Figure 8.3.B APLHGR versus Planar Average Exposure GE12-P1ODSB405-17GZ-10OT-150-T-2395.
Figure 8.3.C APLHGR versus Planar Average Exposure GE12-P1ODSB412-17GZ-10OT-150-T Figure 8.3.D APLHGR versus Planar Average Exposure GE12-P10DSB407-14G6.0-1OOT-150-T Figure 8.3.E APLHGR versus Planar Average Exposure GE12-P1ODSB407-17GZ-10OT-150-4 Figure 8.3.F APLHGR versus Planar Average Exposure GEI4-P1ODNAB405-16GZ-10OT-150-T-2551 (GEI4C)
Figure 8.3.G APLHGR versus Planar Average Exposure GEl4-PIODNAB405-16GZ-100T-150-T-2552 (GE14C)
Figure 8.4 Stability Option 1D Exclusion Region Figure 8.5A Exposure Dependent LIGR Limit for GEI2 fuel.
Figure 8.5.B Exposure Dependent LHGR Limit for GE14 fuel.
Figure 8.6. Cycle 16 Loading Pattern, Full Core by Bundle Design Figure 8.7 Users Guide Rev. No. 1__4 Page 12 of 35
CORE OPERATING LIMITS REPORT CYCLE 16 8.2 TABLES Table 8.1 MCPR Operating Limit for Incremental Cycle Core Average Exposure Table 8.1.A MCPR Operating Limit for Incremental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service Table 8.1.B MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service MCPR Operating Limit for Operation with Final Feedwater Temperature Table 8.1.C Reduction I Table 8.2 Maximum LHGR 9.0 EXHIBITS NONE Rev. No. 14 Page 13 of 3.5.
CORE OPERATING LIMITS REPORT CYCLE 16 TABLE 8.1 MCPR Operating Limit For Incremental Cycle Core Average Exposure Cycle 16 Exposure Range GE12 GE14 BOC to <EOC - 0.7 GWD/ST 1.37 1.40 EOC - 0.7 GWD/ST 1.38 1.44 to EOC Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
For single loop operation, these limits shall be increased by 0.01.
NOTE: 1. When entering a new Exposure Range, check the current value oft to assure adjustment per Step 7.1.4
- 2. Applicable for values of K < 44%, see Step 7.5.2 Rev. No. 1_4 Page of 3_5
CYCLE 16 CORE OPERATING LIMITS REPORT TABLE 8.1A MCPR Operating Limit for Incremental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service Cycle 16 Exposure Range GE12 GE14 BOC to <EOC - 0.7 GWD/ST 1.39 1.42 EOC - 0.7 GWD/ST 1.40 1.46 to EOC Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
For single loop operation, these limits shall be increased by 0.01.
NOTE: 1. When entering a new Exposure Range, check the current value oft to assure adjustment per Step 7.1.4
- 2. Applicable for values of K < 44%, see Step 7.5.2 Rev. No. 14 Page 15 of 35
CYCLE 16 CORE OPERATING LIMITS REPORT TABLE 8.1.B MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service Cycle 16 Exposure Range GEl2 GE14 ALL 1.42 1.48 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
Technical Specification LCO 3.7.6, Main Turbine Bypass System For single loop operation, these limits shall be increased by 0.01.
NOTE: 1. When entering a new Exposure Range, check the current value of t to assure adjustment per Step 7.1.4
- 2. Applicable for values ofK < 44%, see Step 7.5.2 Rev. No. 1__4 Page _.6 of 35
CORE OPERATING LIMITS REPORT CYCLE 16 CORE OPERATING LIMITS REPORT CYCLE 16 TABLE 8.1.C MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction Cycle 16 Exposure Range GE12 GE14 At EOC only (see below) 1.38 1.43 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
For single loop operation, these limits shall be increased by 0.01.
NOTE: 1. When entering a new Exposure Range, check the current value of r to assure adjustment per Step 7.1.4
- 2. Applicable for values of K < 44%, see Step 7.5.2 MCPR Operating Limits in this table apply when at reduced feedwater temperature near end-of-cycle, see JD-02-122 (Reference 3.22) for further information.
Rev. No. 1__4 Page 17 of 35
CYCLE 16 CORE OPERATING LIMITS REPORT TABLE 8.2 Maximum LHGR (kW/ft)
Fuel Bundle Design GE12 See Figure 8.5.A GE14 See Figure 8.5.B Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)
Design features of the fuel assemblies in the Cycle 16 core are provided in References 3.6 and 3.24, 3.25.
I NOTE: Exposure Dependent Limits will be used in the 3D-MONICORE software.
Rev. No. 1__4 Page 18 of 35
CYCLE 16 CORE OPERATING LIMITS REPORT FIGURE 8.1 MCPR Operating Limit Versus t For All Fuel Types
.61 CC E
.51 CL 0.
0 0.1 0.2 03 0.4 05 0.6 0.7 0.8 0.9 1 T
Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
For single loop operation, these limits shall be increased by 0.01.
NOTE: Should the operating limit MCPR obtained from this figure be less than the operating limit MCPR found in 7.1.3 for the applicable RBM Upscale Rod Block trip level setting then 7.1.3 shall apply (Not applicable in Cycle 16).
I Rev. No. 14- Page 1L._9 of 35
CORE OPERATING LIMITS REPORT CYCLE 16 FIGURE 8.1A MCPR Operating Limit Versus r For Operating Above 75% of Rated Thermal Power with Three Steam Lines in Service For all Fuel Types 1.63 CC
-1.53
-i E
CL 0) 0 01 0.2 0.3 04 0.5 06 0.7 08 0.9 1
,r Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
For single loop operation, these limits shall be increased by 0.01.
NOTE: Should the operating limit MCPR obtained from this figure be less than the operating limit MCPR found in 7.1.3 for the applicable RBM Upscale Rod Block trip level setting then 7.1.3 shall apply (Not applicable in Cycle 16).
I Rev. No. 1.44 Page 2.._ of 35
CORE OPERATING LIMITS REPORT CYCLE 16 FIGURE 8.1.B MCPR Operating Limit Versus T for Operation with Turbine Bypass Valves Out of Service 1.7 S- - BOd16B- to 6 CF-TBVOOS MC1
- n. 1.65 1.65 S1.6 E
.-j 3 1.55 1.48 i 0 " 1.5 1 45 r 1IL _ -i 0 01 02 0.3 04 0.5 06 0.7 0.8 0.9 1 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
For single loop operation, these limits shall be increased by 0.01.
NOTE:Should the operating limit MCPR obtained from this figure be less than the operating limit MCPR found in 7.1.3 for the applicable RBM Upscale Rod Block trip level setting then 7.1.3 shall apply (Not applicable in Cycle 16).
I Rev. No. 1._4 Page 21 of 3.5*
CORE OPERATING LIMITS REPORT CYCLE 16 FIGURE 8.1.C MCPR Operating Limit Versus T for Operation with Final Feedwater Temperature Reduction 1.65 CC O. 1.6 .6 S1.55 E
a, C'1.45 1.4 0 0.1 0.2 03 04 0.5 0.6 0.7 08 0.9 1 Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
For single loop operation, these limits shall be increased by 0.01.
NOTE:Should the operating limit MCPR obtained from this figure be less than the operating limit MCPR found in 7.1.3 for the applicable RBM Upscale Rod Block trip level setting then 7.1.3 shall apply (Not applicable in Cycle 16).
I Rev. No. 1..4 Page 22 of 35
CYCLE 16 CORE OPERATING LIMITS REPORT FIGURE 8.2 Kf Factor Cycle 16 K Curve for Scoop Tube Stops at 107%
Considers Two Loop and Single Loop Operation, MOC and EOC a MOC÷TLO x EOC+TLO KfCurve
"Thecombination of MOC MCPR limit and SLO for GE12 fuel produces the 1.143 most limiting Kf curve GE14 MCPR limits are higher and produce a lower Kf curve This set of data determines the Kf curve used In the 3D-MONICORE 1 .13 databank May be changed when EOC MCPR limits apply Choice of Single Loop Kf values Is for ease of SLO Two loop limits are not significantly different 1.12' 111 SLMCPR - 1.09 (TLO), 1 10 6t1*OtR(TLO) = 1 37 (BOC to MOC), 1 38 (MOC to EOC)
OLMCPR(SLO) - 1 38 (BOC to MOC). 1 39 (MOC to EOC) 1.10 1 09 Kf may be adjusted as needed to provide protection against the SLO Pump Seizure event For GE14, the OLMCPR below the SLO core flow limit of 58%
1 08 must be greater than 1 43"(SLMCPRII 12). or 1 404 In Cycle 16 the OLMCPR at MOC+SLO Is 141 for GEl4, so no Kf adjustment is required 1.07 References' 1.06 1. Kf CURVE UPDATE, GE-NE-Ji 1-03426-00-01, 1.05 2l Ot4 ruel Design Cycle-Independent Analyses for JAFNPP, GE-NE-0000-0002-1752-01 P. September 2002 1 04 Equation of Cycle 16 Kf curve 1.03 Kf = MAX( 1 0. 1.2642 - 0 4366*(% Core Flow/100))
1.02 101 h
1.00 0 99 10 75 eu e 30 35 40 45 50 55 60 65 70 75 so 85 90 Core Flow, % rated Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
See Section 7.7 NOTE: K- for Single Loop Operation is slightly greater than for Dual Loop Operation limits.
Therefore, Kf calculated for Single Loop Operation is more conservative and will be applied to Dual Loop Operation as well.
Rev. No. 14 Page 2_3 of _35
CORE OPERATING LIMITS REPORT CYCLE 16 FIGURE 8.3.A APLHGR versus Planar Average Exposure:
GE12-P1ODSB405-16GZ-10OT-150-T-2396 12 10 8
(.4
.IL
<2 0.
0 10 20 30 40 50 60 Planar Average Exposure (GWDIST)
This curve represents the limiting exposure dependent APLHGR values per Reference 3.17 and 3.18.
Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)
For single loop operation these APLHGR values shall be multiplied by 0.78.
Rev. No. 14 Page 24 of 3.5_
CYCLE 16 CORE OPERATING LIMITS REPORT FIGURE 8.3.B APLHGR versus Planar Average Exposure:
2 GE12-P1ODSB405-17GZ-10OT-150-T- 395 12 7 I
10 1I C 4 i
-J
.J 2 -I 0I 60 0 10 20 30 40 50
^cnvirn M.W IATI This curve represents the limiting exposure dependent APLHGR values per Reference 3.17 and 3.18.
Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Ratff (APLHGR)
For single loop bperation these APLHGR values shall be multiplied by 0.78.
Rev. No. 14 Page 25 of 35
CYCLE 16 CORE OPERATING LIMITS REPORT FIGURE 8.3.C APLHGR versus Planar Average Exposure:
GE12-P1ODSB412-17GZ-100T-150-T 121 101 j 8--1 4 1< 2 10 20 30 40 50 60 0
Planar Average Exposure (GWDIST)
This curve represents the limiting exposure dependent APLHGR values per Reference 3.5 and 3.11.
Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)
Reference:
24A5167 Rev. 0 For single loop operation these APLHGR valueg shall be multiplied by 0.78.
'D r.*, I A Page 2._6 of 35
CYCLE 16 CORE OPERATING LIMITS REPORT FIGURE 8.3.D APLHGR versus Planar Average Exposure:
GE12-P1ODSB407-14G6.0-10OT-150-T 12
=
IL 0.
60 0 10 20 30 40 50 Planar Average Exposure (GWDIST)
This curve represents the limiting exposure dependent APLHGR values per Reference 3.4 and 3.13.
Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)
For single loop operation these APLHGR values shall be multiplied by 0.78.
Page -27 of 35 Rev. No. 14
CYCLE 16 CORE OPERATING LIMITS REPORT FIGURE 8.3.E APLHGR versus Planar Average Exposure:
GE12-P1ODSB407-17GZ-10OT-150-T 0
6i 0 60 0 10 20 30 40 50 Planar Average Exposure (GWDIST)
This curve represents the limiting exposure dependent APLHGR values per Reference 3.4 and 3.13.
Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)
For single loop operation these APLHGR values shall be multiplied by 0.78.
Rev. No. 14 Page 2_8 of 35
I CYCLE 16 CORE OPERATING LIMITS REPORT FIGURE 8.3.F APLHGR versus Planar Average Exposure:
GE14-P1ODNAB405-16GZ-1OOT-150-T-2551(GE14C)
I 12 10 8
6 0
I
-J 0 4 2
0 40 50 60 70 0 10 20 30 Av. Planar Exposure GWd/St I
9 This curve represents the limiting exposure dependent APLHGR values per Reference 3.24 and 3.14.
Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)
Reference:
23A7114 Rev 1 For single loop operation these APLHGR values shall be multiplied by 0.78.
Rev. No. 1_4 Page 2_9 of 35
CORE OPERATING LIMITS REPORT CYCLE 16 FIGURE 8.3.G APLHGR versus Planar Average Exposure:
GE14-P1ODNAB405-16GZ-100T-150-T-2552(GE14C) 12 10 8
6
=,
- a. 4 2
0 0 10 20 30 40 50 60 70 Av. Planar Exposure GWd/St 1k
\
This curve represents the limiting exposure dependent APLHGR values per Reference 3.24 and 3.14.
Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)
Reference:
23A7114 Rev 1 For single loop operation these APLHGR values shall be multiplied by 0.78.
Rev. No. 1_4. Page 3.0 of 35
CORE OPERATING LIMITS REPORT CYCLE 16 CORE OPERATING LIMITS REPORT CYCLE 16 FIGURE 8.4 Stability Option 1-D Exclusion Region 100 90 80 70 C) 60 50 40 30 20 20 25 30 35 40 45 50 55 60 65 70
% rated Flow Technical Specification LCO 3.4.1, Recirculation Loops Operating Reference 3.14 Rev. No. 1_4 Page 31 of 35
CORE OPERATING LIMITS REPORT CYCLE 16 GORE OPERATING LIMITS REPORT CYCLE 16 FIGURE 8.5.A Exposure Dependent LHGR Limit for GE12 Fuel Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)
This curve represents the limiting exposure dependent LHGR values per Reference 3.11.
Design features of the fuel assemblies in the Cycle 16 core are provided in Reference 3.6 NOTE: Exposure Dependent Limits will be used in the 3D-MONICORE software.
Rev. No. 1_A4 Page 32 of 35
CORE OPERATING LIMITS REPORT CYCLE 16 CORE OPERATING LIMITS REPORT CYCLE 16 FIGURE 8.5.B Exposure Dependent LHGR Limit for GE14 Fuel 16 14 12 10 kW
/ft 8 6
4 2
0 0 10 20 30 40 50 60 70 PELLET EXPOSURE GWd/St Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)
This curve represents the limiting exposure dependent LHGR values per Reference 3.25 Design features of the fuel assemblies in the Cycle 16 core are provided in Reference 3.6 NOTE: Exposure Dependent Limits will be used in the 3D-MONICORE software.
Rev. No. 1_.4 Page 33 of 35
CORE OPERATING LIMITS REPORT CYCLE 16 FIGURE 8.6 Cycle 16 Loading Pattern by Bundle Design 52 [B] f[B] [B]I_[1B] [B] [E]i [f North 4 48 [BE] (B]_ [fl fB[] [8[B] (flB*[B]_*DB [B)) [B] [B]_D [B] [B))E D
46 E*' [EI ME F [ I -DFIlialEFII[]R I*- EMi[ EI '-FI 01L 448 [] E] BI[
EA [ A] [lE [] [] [] E]EA Di[E][ [1B ] [AB E [
32 40 [][] (B] [A] [BE A] (E]DLf [E]*D IDZ [fl] [89 I.D m-!rID l-E]D ES] [B]
EA]_*
18* DE][*LE[] Nt['DNIx-LP Efi;_* EL- FN]_*
p.[fl--]
IN F[D[i -19E_LD E-II Ea-17 1_LE EMN-L*EII NI
__D 3 [E](B(]A]A] [D__ DL_[D DO_ ICES]EA_(A]
[A]_D BE [A] [E]D [fjD [B]_LA*DA](B[fl (B 18[ AE ] AE]A]
B] E]
A A A]1]
B ]A] AB [A] I A B [I 122 28 [DB][][E[A[B 1] [A][OD [8fi[B] [B]D fID ll[A]E][] [B]l 10 [BEfB [E A[BE EABE EA] [1B]A ] EA]BE](AJI[B [AA] [A] FB] EAB] I EB 14 A BA
= A AlA B A aB B2 18 E ~l[IE -1 DE f r -F]EL]M IE F]EI 16 E]BE [BE BD BD BA BDE B[ [BE [B] BA B] BA [B] BA BD]MS 13 D 5 D 7 911 l 1351719212325229313335373414345M; 95 8 ][B OD[ E][A A ]GEA] AD[B [B]=GAE1 [A A S1][B][][
Rev. No. 1_.4 Page 3.4. of 35
CORE OPERATING LIMITS REPORT CYCLE 16 FIGURE 8.7 USERS GUIDE The COLR defines thermal limits for the various operating conditions expected during the cycle. At the start of the cycle the 3D-Monicore databank contains limits for;
- Cycle exposure range of BOC to < EOC16 - 0.7 GWD/ST c= 0I
- Dual recirculation pump operation
- Four steam line operation, and
- Operation with Turbine Bypass Valves Out-of-Service
- Final Feedwater Temperature Reduction The following is a table that offers a check to assure the correct limits are applied when operating states or conditions change.
Cnange in Operating State Change in Limits Procedure Reference Cycle Exposure = See Table 8.1(8.1.A for 3SL) or Figure 8.1 None EOC16 - 0.7 GWD/ST for #* 0(8.1.A for 3SL) for change in OLMCPR changes to EOC values MCpR.
at cycle exposure of 14.0 GWD/ST Kr limit may be changed in recognition of higher OLMCPRI Scram Time Test Results such that T S0 Use newt and see Figure 8.1 or 8.1.A for 3SL Kf limit ma be changed in RAP-7.4.1 Option B limits for OLMCPR must recognition of higher OLMCPR.
be interpolated with Option A limits Single Loop Operation Increase MCPR Limits by 0.01, or change RAP-7.4.2, The SLMCPR increases by 0.01 and acceptance criterion in ST-5E to 0.99. Kr ST-5E, therefore OLMCPR limits increase does not change. RAP-7.3.25 by 0.01. MAPLHGR is reduced by Verify that 3D-Monicore has recognized a multiplier in SLO. the idle recirculation loop and is applying the SLO MAPLHGR multiplier of 0.78.
Three Steam Line Operation (3SL) Increase OLMCPR according to Table
- 8. 1A or Figure 8.1.A(r # 0). K limit may None OLMCPR when opeatusing s by 0.02 valuesonincrease 02 be changed in recognition of higher when operating on 3SL OLMCPi.
Operation with Turbine Bypass Increase OLMCPR according to Table Valves Out-of-Service 8.1.B or Figure 8.13B(r
- 0). Kf limit ml- None OLMCPR values increase, no be changed in recognition of higher LHGR change required OLMCPR.
Operation under Final Feedwater Increase OLMCPR according to Table Temperature Reduction 8.1.C or Figure 8.1.C(t #0). Kr limit may None OLMCPR values increase, no be changed in recognition of higher LHGR change required OLMCPRt Rev. No. 1_4. Page 35 of 35