JAFP-02-0193, Core Operating Limits Report Revision 13 (Cycle 15 Update)
| ML022820691 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/24/2002 |
| From: | Ted Sullivan Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-02-0193 | |
| Download: ML022820691 (38) | |
Text
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A Fitzpatrick NPP P0 Box 110 Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 T.A. Sullivan Vice President, Operations-JAF September 24, 2002 JAFP-02-0193 United States Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop O-Pl-17 Washington, DC 20555-0001
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Core Operating Limits Report Revision 13 (Cycle 15 update)
Dear Sir; Attached is Revision 13 to the James A. FitzPatrick Core Operating Limits Report (COLR). This report is submitted in accordance with Technical Specifications 5.6.5.
Revision 13 of the COLR incorporates changes as a result of implementation of Final Feedwater Temperature Reduction (FFTR) during the end of Cycle 15 operations. 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.
TAS:GB:Ias Attachment as stated cc: next page
cc: Regional Administrator U.S. Nuclear Regulatory 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
I-Entergy NuclearNortheast ENTERGY NUCLEAR OPERATIONS, INC.
JAMES A. FITZPATRICK NUCLEAR POWER PLANT REPORT CORE OPERATING LIMITS REPORT REVISION 13 REVIEWED BY: PLANT OPERATING REVIEW COMMITTEE MEETING NO. 02 o DATE: q il. -,o DATE:
APPROVED BY: William Drews -VV-&
REACTOR ENGINEERING SUPERINTENDENT DATE:
APPROVED BY: Bran O'Grady GENERAL MANAGER - PLANT 0 TIONS
CYCLE 15 CORE OPERATING LIMITS REPORT TABLE OF CONTENTS PAGE SECTION 1.0 PURPO SE ............................................................................................................... 3 2.0 APPLICABILITY ................................................................................................... 3 3.0 REFEREN CES ...................................................................................................... 3 4.0 D EFIN ITION S ...................................................................................................... 4 5.0 RESPON SIBILITIES ........................................................................................ 5 6.0 SPECIAL INSTRUCTIONS/REQUIREMENTS .......................................... 5 7.0 PRO CEDURE ................................................................................................... 6 7.1 Operating Limit M CPR ....................................................................... 6 7.2 Average Planar Linear Heat Generation Rate (APLHGR) .................. 8 7.3 Linear H eat Generation Rate (LH GR)................................................. 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 M CPR Limit .................................................... 11 8.0 FIGURES AND TABLES .................................................................................... 12 9.0 EXH IBITS ............................................................................................................ 13 Rev. No. 13 Page! 2of 36
CORE OPERATING LIMITS REPORT CYCLE 15 1.0 PURPOSE This report provides the cycle-specific operating limits for Cycle 15 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 15 Core Reload Safety Evaluation, JAF-SE-00-045.
3.4 GE Report, Supplemental Reload Licensing Report forJames A. FitzPatrick Reload 13 Cycle14, J11-03359SRL, Rev.1, October 1998 3.5 GE Report, Supplemental Reload Licensing Report for James A. FitzPatrick Reload 12 Cyclel3, J11-02914SRL Rev.0, August 1996.
3.6 Design Change Package JD-99-091, Cycle 15 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-J1 1-03426-00-01, September 1998.
3.10 General Electric Standard Application for Reload Fuel, NEDE-24011-P-A-14 Rev. No. 13 Page 3 of 36
CORE OPERATING LIMITS REPORT CYCLE 15 3.11 GE Letter, J. Baumgartner to P. Lemberg, Exposure Dependent LHGR Limit Curves, JAB-N8076, November 5, 1998.
3.12 GE Lattice Dependent MAPLHGR Report for James A. FitzPatrick, Reload 12 Cyclel3, J11-02914MAP, 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 GE Letter, A. Alzaben to P. Lemberg, Revised FitzPatrick Cycle 14 Exclusion Region, AFA-00-N005, February 7, 2000.
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 Cyclel5, 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 4.0 DEFINITIONS 4.1 Average Planar Linear Heat Generation Rate (APLHGR):
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.
Rev. No. 1._3_ Page 4 of 36
CORE OPERATING LIMITS REPORT CYCLE 15 4.3 Linear Heat Generation Rate(LHGR):
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 (MCPR):
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 3.7) 6.0 SPECIAL INSTRUCTIONS/REQUIREMENTS Not Applicable Rev. No. 13 Page .5 of 36
CYCLE 15 CORE OPERATING LIMITS REPORT 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:
"IA VE : r<-
B 7.1.2.2. The average scram time to notch position 36 is determined as follows:
n T AVE n Nil WHERE:
n = Number of surveillance tests performed to date in the cycle, Ni = Number of active rods measured in the surveillance i
=
=ci Average scram time to notch position 36 of all rods measured in surveillance test i.
Rev. No. 13 Pagek of 36
CORE OPERATING LIMITS REPORT CYCLE 15 7.1.2.3. The adjusted analysis mean scram tlme is calculated as follows:
-1/2 6 N vB(sec) =/t+ 1. 5 o EN, t=1 WHERE:
= Mean of the distribution for the average scram insertion time to the dropout of notch position 36 = 0.830 sec.
cy = Standard deviation of the distribution for average scram insertion time to the dropout of notch position 36 = 0.019 sec.
N, = 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 is not met (i.e. TB < TAVE), THEN the Operating Limit MCPR values (as a function oft) are given in Figure 8.1, Figure 8.1.A, Figure 8.1.B or Figure 8.1.C as applicable.
(TAVE - trB)
(TA - TB)
WHERE:
'TAVE = 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_3 Page 7 of 36
CYCLE 15 CORE OPERATING LIMITS REPORT 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 Plknar 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 F.
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 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 as a function of average planar exposure shall not exceed the limiting value for the most limiting lattice as specified in Table 8.2 and shown in Figure 8.5.
Rev. No. 13 Page 8 of 36
CORE OPERATING LIMITS REPORT CYCLE 15 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 _50.58W + 66% for two loop operation; S <_ 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 _<(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. 13 Page _2_of 36
CYCLE 15 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 15 the RBM intercept value does not effect the MCPR Operating Limit -forK 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_3_ Page 1_0 of 3.6
CYCLE 15 CORE OPERATING LIMITS REPORT 7.7 Kf - 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 _* 100%
SLOPE = (AF/100/OLMCPR ) * (SLMCPR /SLMCPR generic)
A = (BF/OLMCPR ) * (SLMCPR /SLMCPR generic)
SLMCPR generic = 1.07 SLMCPR = Technical Specification LCO 2.1.1, Reactor Core SLs OLMCPR = The highest value obtained from Figures 8.1, and 8.1.A as per 7.1.4, or, if the note in 7.1.4 applies, then 7.1.3 requirement must be met AF, BF = Coefficients for the Kf curve listed below:
Scoop Tube Setpoint % A, 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. 13 Page 1__lof 36
CORE OPERATING LIMITS REPORT CYCLE 15 CORE OPERATING LIMITS REPORT CYCLE 15 8.0 FIGURES AND TABLES 8.1 FIGURES Figure 8.1. MCPR Operating Limit Versus r for All Fuel Types Figure 8.1.A. MCPR Operating Limit Versus r for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service for All Fuel Types Figure 8.1.B MCPR Operating Limit Versus T for Operation with Turbine Bypass Valves Out of Service Figure 8.1.C MCPR Operating Limit Versus T for Operation with Final Feedwater Temperature Reduction I Figure 8.2 Kf Factor Figure 8.3:A APLHGR versus Planar Average Exposure GE12-P10DSB405-16GZ-100T-150-T-2396.
Figure 8.3.B APLHGR versus Planar Average Exposure GE12-P10DSB405-17GZ-100T-150-T-2395.
Figure 8.3.C APLHGR versus Planar Average Exposure GE12-P1ODSB417-15GZ-10OT-150-T Figure 8.3.D APLHGR versus Planar Average Exposure GE12-P1ODSB412-17GZ-100T-150-T Figure 8.3.E APLHGR versus Planar Average Exposure GE12-P1ODSB407-14G6.0-10OT-150-T Figure 8.3.F APLHGR versus Planar Average Exposure GE12-P1ODSB407-17GZ-100T-150-T Figure 8.4 Stability Option 1D Exclusion Region Figure 8.5 Exposure Dependent LHGR Limit for GEI2 fuel.
Figure 8.6.A Cycle 15 Loading Pattern, Upper Left Quadrant, Bundle Design Figure 8.6.B Cycle 15 Loading Pattern, Upper Right Quadrant, Bundle Design Figure 8.6.C Cycle 15 Loading Pattern, Lower Right Quadrant, Bundle Design Figure 8.6.D Cycle 15 Loading Pattern, Lower Left Quadrant, Bundle Design Figure 8.7 Users Guide Page 1.2 of 36 Rev. No. 13
CORE OPERATING LIMITS REPORT CYCLE 15 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 Table 8.1.C MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction I
Table 8.2 Maximum LHGR 9.0 EXHIBITS NONE Rev. No. 1._3 Page 13 of 36
CYCLE 15 CORE OPERATING LIMITS REPORT TABLE 8.1 MCPR Operating Limit For Incremental Cycle Core Average Exposure 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. 13 Page _14 of 36
CYCLE 15 CORE OPERATING LIMITS REPORT 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 Cycle 15 Exposure Range ALL Fuel Types BOC to <EOC -- 1.0 GWD/ST 1.38 EOC - 1.0 GWD/ST 1.40 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 of t to assure adjustment per Step 7.1.4
- 2. Applicable for values of K < 44%, see Step 7.5.2 Rev. No. 1_3_ Page 15 of 36
CORE OPERATING LIMITS REPORT CYCLE 15 CORE OPERATING LIMITS REPORT CYCLE 15 TABLE 8.1.B MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service Cycle 15 Exposure Range ALL Fuel Types AlL 1.41 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 of K _ 44%, see Step 7.5.2 Rev. No. 1_3_ Page 16 of 36
CORE OPERATING LIMITS REPORT CYCLE 15 TABLE 8.1.C MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction Cycle 15 Exposure Range ALL Fuel Types At EOC only (see below) 1.40 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 for further information.
Rev. No. 13 Page 17 of 36
CYCLE 15 CORE OPERATING LIMITS REPORT TABLE 8.2 Maximum LHGR Maximum LHGR Fuel Type Fuel Bundle Design (kW/ft)
ALL GE12 See Figure 8.5 Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)
Design features of the fuel assemblies in the Cycle 15 core are provided in Reference 3.6 NOTE: Exposure Dependent Limits will be used in the 3D-MONICORE software.
Rev. No. 1_3. Page _L8 of 36
CYCLE 15 CORE OPERATING LIMITS REPORT FIGURE 8.1 MCPR Operating Limit Versus T For All Fuel Types 1.48 I i I I ! , 1
-*-BOC to < EOC-I .0 GWD/ST ,
1.46- -1
- U- EC-1.0 GWD/ST to EOC r-- I. - A11.46 i I 1.44 1-.-- -_6_
0 C.,
4 1.42
-J 1.41 1.4 0
4 (U
L.
0 0.
1.38
_ _ _ _ _-__ __ I _ _ _
1.36 1.34 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I 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 15).
Rev. No. 1._3 Page 1_99of 36
CORE OPERATING LIMITS REPORT CYCLE 15 FIGURE 8.1.A MCPR Operating Limit Versus'r For Operating Above 75% of Rated Thermal Power with Three Steam Lines in Service For all Fuel Types 1.5
- BOC to < EOC-1.0 GWD/ST 1.48 -J -U- EOC-1.0 GWD/ST to EOC 1.48 1.46 E 1.44 4
1.40." 1.43
.J 1.42 0
1.4 1.38 1.38 1.36 0 0.2 0.4 0.6 0.8 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 15).
Rev. No. 13 Page 2_00of 3_6
CYCLE 15 CORE OPERATING LIMITS REPORT FIGURE 8.1.B MCPR Operating Limit Versus'r for Operation with Turbine Bypass Valves Out of Service 1.50 1.49 1.49 1.48 0~
C., 1.47 1.46 E
-j 1.45 a,E 1.44 1.43 00.
1.42 1.41 1.40 1.40 0.4 0.5 0.6 0.7 0.8 0.9 1 0 0.1 02 03 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 15).
Rev. No. 13 Page 2_1 of 3__6
CYCLE 15 CORE OPERATING LIMITS REPORT FIGURE 8.1.C MCPR Operating Limit Versus ¶ for Operation with Final Feedwater Temperature Reduction 1.49 1.48 1.48 1.A7 1.46 1.45 E
1.44
'-j t
1.43 1.42 0 1.41 1.40 1.39 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 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 15).
Page _2-2 of 3_6 Rev. No. 13
CORE OPERATING LIMITS REPORT CYCLE 15 FIGURE 8.2 Kf Factor Cycle 15 K¢ Curve for Scoop Tube Stops at 1070/0 Considers Two Loop and Single Loop Operation, MVOO anld E MCPR imits 1.15 ITXcontination of MOC MCPR linit and SLO produces the 1.14 t limiting K1curve. This set of data detenrines the Kf 1.13 cur ye used in the 3D-MONICCRE databank. May be 1.12 dtv Snoed when EOC MCPR nlits apply. Choice of Sngle p Kf values is for ease of SLO. Two loop linits are not 1.11 ificantly clifferent 1.10 Sig CPR = 1.09 (TLO), 1.10 (SLO) 1.09
.MCPR(TLQ) = 1.36 (BOC to MOC), 1.38 (MOC; to EOC) 1.08 MCPR(SLO) = 1.37 (130 to MOC), 1.39 (lACOC to EOC)
ý- 1.07 Do ference: K(CURVE UPDATE, dated 10/16/98 1.06 CLcurrent No. G-NE-J1 1-03426-00-01 1.05 1.04 uatond Cye 15 K cuve:
=MAX( 1.0, 1.2734 - 0.4397*(% Core RoWa100))
1.03 1.02 1.01 1.00 0.99 1 3 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Core Flow, %rated Technical Specification LCO 3.2.2, Minimum Critical Power Ratio (MCPR)
See Section 7.7 NOTE: Kf 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. 13 Page 2_3 of 3.6
CORE OPERATING LIMITS REPORT CYCLE 15 FIGURE 8.3.A APLHGR versus Planar Average Exposure:
GE12-P1ODSB405-16GZ-100T-150-T-2396 12 10 Y..
0 10 20 30 40 50 60 Planar Average Exposure (GWD/ST)
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. 1_3 Page 24 of 3.6_
CYCLE 15 CORE OPERATING LIMITS REPORT FIGURE 8.3.B APLHGR versus Planar Average Exposure:
GE12-P1ODSB405-17GZ-10OT-150-T-2395 12 10 8
6 r-
-I CL 4
-J a-,
2 4 1-0 .1 I 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. 1_33 Page 25 of 36
CORE OPERATING LIMITS REPORT CYCLE 15 FIGURE 8.3.C APLHGR versus Planar Average Exposure:
GE12-P1ODSB417-15GZ-100T-150-T
/1 12 10 8
1-6 i t
4
-(
0:L 2 T 0
0 10 20 30 40 50 60 Planar Average Exposure (GWDIST) 2' This curve represents the limiting exposure dependent APLHGR values per Reference 3.5 and 3.12.
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. 13 Page 26 of 3_6_
CORE OPERATING LIMITS REPORT CYCLE 15 FIGURE 8.3.D APLHGR versus Planar Average Exposure:
GE12-P1ODSB412-17GZ-100T-150-T 120 10' 8
'4 2
0 0 10 20 30 40 50 60 Planar Average Exposure (GWDIST)
This curve represents the limiting exposure dependent APLHGR values per Reference 3.5 and 3.12.
Technical Specification LCO 3.2.1, Average Planar Linear Heat Generation Rate (APLHGR)
Reference:
24A5167 Rev. 0 For single loop operation these APLHGR values shall be multiplied by 0.78.
Page 2_7 of 36 Rev. No. 13
CORE OPERATING LIMITS REPORT CYCLE 15 FIGURE 8.3.E APLHGR versus Planar Average Exposure:
GE12-P10DSB407-14G6.0-10OT-150-T 12 10 6
,4 2
0 0 10 20 30 40 50 60 Planar Average Exposure (GWDIST)
This curve represents the limiting exposure dependent APLHGR values per Reference 3.4 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. 1__3 Page 28 of 3_6
CORE OPERATING LIMITS REPORT CYCLE 15 CORE OPERATING LIMITS REPORT CYCLE 15 FIGURE 8.3.F APLHGR versus Planar Average Exposure:
GE12-P1ODSB407-17GZ-10OT-150-T 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. 1_3_ Page 29 of 36
CORE OPERATING LIMITS REPORT CYCLE 15 FIGURE 8.4 Stability Option 1-D Exclusion Region 100 90 80 70 60 50 V
0.
12 40 30 20 10 0
25 30 35 40 45 50 55 20 Rated Core Flow, %
Technical Specification LCO 3.4.1, Recirculation Loops Operating Reference 3.14 Rev. No. 13 Page 30 of 36
CORE OPERATING LIMITS REPORT CYCLE 15 FIGURE 8.5 Exposure Dependent LHGR Limit for GE12 Fuel 16 14 10 8
6 60 0 10 20 30 40 50 GWD/ST Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)
This curve represents the limiting exposure dependent LHGR values per Reference 3.11 Design features of the fuel assemblies in the Cycle 15 core are provided in Reference 3.6 NOTE: Exposure Dependent Limits will be used in the 3D-MONICORE software.
Page 31 of 3_6 Rev. No. 13
CORE OPERATING LIMITS REPORT CYCLE 15 FIGURE 8.5.A Cycle 15 Loading Pattern, Upper Left Quadrant, Bundle Design
'-.7.
N$ B B B B B 52 1--I.-
from above 50 B B B B B B the core B B B B B B 48 B B B B B B B B B B B B 46 B
B B B B B B B B B B B 44 B B B B B B B B B 42 B B B B B B B B B 40 B B B B B B B B B B B 38 B B B B
36 B B B B B B B B B B B B B B B B B B B B B B B B B 34 B B B B B B B B B B B B B 32 B B B B B B B B B B B B B 30 B B B B B B B B B B B B B 28 1 3 5 7 9 11 13 15 17 19 21 23 25 B = GE12 Rev. No. 13 Page 3_2. of 3-6
CORE OPERATING LIMITS REPORT CYCLE 15 FIGURE 8.6.B Cycle 15 Loading Pattern, Upper Right Quadrant, Bundle Design B B B B B Ný 4 52 from above B B B B B B the core 50 A
B B B B B B B B B 48 B B B B B B B B B 46 B
B B B B BB B B B B B B 44
-B B B - B B 42 B B B B B B B B B B B 40 B B B B B B B B B B B B 38 B B B B B B B B B 36 B B B B B B B B B B B B B B B B B 34 B B B B B B B B B B B B B 32 B B B B B B B B B B B B B 30 B B B B B B B B B B B B B 28 37 39 41 43 45 47 49 51 27 29 31 33 35 B = GE12 Page 3_3 of 36 Rev. No. 13
CYCLE 15 CORE OPERATING LIMITS REPORT FIGURE 8.6.C Cycle 15 Loading Pattern, Lower Right Quadrant, Bundle Design B B B B B B B B B B B B B 26 B B B B B B B B B B B B B 24 B B B B B B B B B B B B B 22 B B B B B B B B B B B B B 20 B B B B B B B B B B B B B 18 B B B B B B B B B B B B 16 B B B B B B B B B 14 B B B B B B B B 12 B B B B B B B B 10 B B B B B B B B B B B B B 8 B B B B B B B B B 6 B B B B B B B B B B N$ 4 from above B B B B B the core 2 27 29 31 33 35 37 39 41 43 45 47 49 51 B = GE12 Page 34 of 3_6 Rev. No. 13
CORE OPERATING LIMITS REPORT CYCLE 15 FIGURE 8.6.D Cycle 15 Loading Pattern, Lower Left Quadrant, Bundle Design B B B B B B B B B B B B B 26 B B B B B B B B B B B B B 24 B B B B B B B B B B B B B 22 B B B B B B B B B B B B B 20 B B B B B B B B B B B B B 18 B B B B B B B B B B B B 16
-I-I B B B B B B B B B B B 14 B B B B B B B B B B B 12 B B B B B B B B B B B 10 B B B B B B B B B B 8 B B B B B B B B B 6 t-i-t-B B B B B B 4 Nýf from above B B B B B 2 the core
- &- £- a- a. -
1 3 5 7 9 11 13 15 17 19 21 23 25 B = GE12 Rev. No. 1...3. Page 35 of 36
CORE OPERATING LIMITS REPORT CYCLE 15 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;
- [= 0
- Dual recirculation pump operation
- Four steam line operation, and
- Operation with Turbine Bypass Valves Out-of-Service
- Final Feedwater Temperature Reduction I The following is a table that offers a check to assure the correct limits are applied when operating states or conditions change.
Change in Operating State Change in Limits Procedure Reference Cycle Exposure = See Table 8.1(8.1.A for 3SL) or Figure 8.1 EOC - 1.0 GWD/ST for #* 0(8.1.A for 3SL) for change in MCPR. None OLMCPR changes to EOC values at cycle exposure of 13.447 Kr limit may be changed in recognition of GWD/ST higher OLMCPtR Scram Time Test Results such that I:
S0 Use new t and see Figure 8.1 or 8.1.A for 3SL Kr 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 The SLMCPR increases by 0.01 and acceptance criterion in ST-5E to 0.99. Kr therefore OLMCPR limits increase does not change. RAP-7.4.2, by 0.01. MAPLHGR is reduced by Verify that 3D-Monicore has recognized ST-5E, a multiplier in SLO. the idle recirculation loop and is applying RAP-7.3.25 the GE12 SLO MAPLHGR multiplier of 0.78.
Three Steam Line Operation (3SL) Increase OLMCPR according to Table limit may None OLMCPR when opealuting s by 0.02 valuesonincrease 00 8.1.A or Figure be changed in recognition ofKr 8.1.A(r # 0). higher when operating on 3SL OLMCPtL Operation with Turbine Bypass Increase OLMCPR according to Table None Valves Out-of-Service 8.1.B or Figure 8.1.B(T # 0). Kr limit 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