JAFP-04-0172, Core Operating Limits Report, Revision 15 (Cycle 17 Update)
| ML043070346 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/26/2004 |
| From: | Ted Sullivan Entergy Nuclear Northeast |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-04-0172 | |
| Download: ML043070346 (34) | |
Text
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. Fitzpatrick NPP as Entergy RO. Box 110 Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 T.A. Sullivan October 26, 2004 Site Vice President - JAF JAFP-04-0172 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Core Operating Limits Report Revision 15 (Cycle 17 update)
Dear Sir; Attached is Revision 15 to the James A. FitzPatrick (JAF) Core Operating Limits Report (COLR). This report is submitted in accordance with Technical Specifications (TS) 5.6.5.
Revision 15 of the COLR incorporates changes as a result of reload analysis completed by Global Nuclear Fuel (GNF) for Cycle 17 operations. The stability portion of the analysis is acceptable up to 6000 MWD/ST, and per TS Section 5.6.5.d, another revision to the COLR will be submitted when GNF completes the analysis for the remainder of the cycle. Also, JAF has upgraded core monitoring to the PANAC 11 analytical model in accordance with NRC approved NEDE-24011-P-A 'GESTAR II' (Amendment 26).
In addition, editorial corrections and administrative changes are included in revision 15 that do not alter its 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 you S, TAS:GB:las Attachment as stated cc: next page
-A,) )
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. Patrick D. Milano, 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 15 REVIEWED BY: ONSITE SAFETY REVIEW COMMITTEE MEETING NO.04-014 DATE: 10/15/04 APPROVED BY: William Drews .J&- DATE: 10/15/04 REACTOR ENGINEERING SUPERINTENDENT APPROVED BY: Kevin Mulligan GENERAL MANAGER - PLANT OPERATIONS
CORE OPERATING LIMITS REPORT CYCLE 17
,. I 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 Lirmit MCPR .6 7.2 Average Planar Linear Heat Generation Rate (APLHGR) . 8 7.3 Linear Heat Generation Rate (LGR) .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. 15 Page 2 of 32
CORE OPERATING LIMITS REPORT CYCLE 17 1.0 PURPOSE This report provides the cycle-specific operating limits for Cycle 17 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) e 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 exceeded, 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 Design Change Package ER-JF-03-0155, Cycle 17 Core Reload 3.4 RAP-7.3.17, Core Monitoring Software and Database Changes.
3.5 Plant Operation Up To 100% Power With One Steam Line Isolated, JAF-SE-96-035.
3.6 James A. FitzPatrick Nuclear Power Plant Kf Curve Update, GE-NE-J11-03426-00-01, September 1998.
3.7 General Electric Standard Application for Reload Fuel, NEDE-24011-P-A-14 3.8 GNF Report, Supplemental Reload Licensing Report forJames A. FitzPatrick Reload 16 Cyclel7, 0000-0026-1984SRLR, Rev.0, Class I, September, 2004.
3.9 JAF-SE-00-032, Rev.0, Extended Loadline Limit Analysis (ELLLA) Implementation.
Rev. No. 15 Page 3 of 32
CORE OPERATING LIMITS REPORT CYCLE 17 3.10 JAF-RPT-MISC-04054, Rev.0, Operation under Extended Loadline Limit Analysis (ELLLA) and Power Uprate 3.11 GE Letter, FitzPatrick APRM Flow Biased Rod Block and Scram Setpoints, NSA01-273, July 3, 2001 3.12 GE Letter, R. Kingston to P. Lemberg, Scram Time Versus Notch Positions for Option B, REK-E: 02-009, May 28, 2002 3.13 GE Report, James A. FitzPatrick Nuclear Power Plant Final Feedwater Temperature Reduction NEDC-33077, September 2002.
3.14 JD-02-122, Final Feedwater Temperature Reduction Implementation.
3.15 GE Report, GE14 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.
3.16 GNF Report, GNF Report, Fuel Bundle Information Report for James A. FitzPatrick Reload 16 Cycle 17, 0000-0026-1984FBIR, Revision 0, September 2004.
3.17 GNF Report, Supplemental Reload Licensing Report forJames A. FitzPatrick Reload 15 Cyclel 6, 0003-9220SRLR, Rev.0, Class 1,August, 2002.
3.18 GNF Report, Validation of FitzPatrick Cycle 16 Exclusion and Buffer Region Application for Cycle 17 Operation Up to 6000 MWD/ST Exposure, GE-NE-0000-0033-3112-RO, October 8,2004 4.0 DEFINITIONS 4.1 Average Planar Linear Heat Generation Rate (APIHGR):
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 RatealHGR):
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 lniting 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.
Rev. No. 15 Page 4 of 32
CORE OPERATING LIMITS REPORT CYCLE 17 4.5 Minimum critical powver ratio (MCPR):
The MCPR shall be the smiallest 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 3.4) 6.0 SPECIAL INSTRUCTIONS/REQUIREMENTS Not Applicable Rev. No. 15 Page 5 of 32
CORE OPERATING LIMITS REPORT CYCLE 17 7.0 PROCEDURE 7.1 Operating Limit MCPR During operation, with thermal power > 25% of 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:
TA VE TB 7.1.2.2. The average scram time to notch position 36 is determined as follows:
n TAVE n E N.
,=,
WHERE:
n Number of surveillance tests performed to date in the cycle, Ni = Number of active rods measured in the surveillance i hi = Average scram time to notch position 36 of all rods measured in surveillance test i.
Rev. No. 15 Page 6 of 32
CORE OPERATING LIMITS REPORT CYCLE 17 7.1.2.3. The adjusted analysis mean scram time is calculated as follows:
1/2
-B(sec)-=I+1.6 5U N, i=1 WHERE:
= Mean of the distribution for the average scram insertion time to the drpout of notch position 36 = 0.830 sec.
ca = 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 of t) are given in Figure 8.1, Figure 8.1.A, Figure 8.1.B or Figure 8.1.C as applicable.
(TAVE - TB)
(TA - TB WHERE:
T AVE = The average scram time to notch position 36 as defined in 7.1.2.2.
'8= 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. 15 Page 7 of 32
CORE OPERATING LIMITS REPORT CYCLE 17 NOTE: IF the operating limit MCPR obtained from these figures is determined to be less than thiee perating 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 shall be within the limits given in Tables 8.3 and 8.3.A (Figures 8.3 and 8.3.A) for the appropriate fuel type.
7.2.3 During single loop operation, the APLHGR for each fuel type shall not exceed the values given in 7.2.2 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 rod as a function of axial location and exposure shall be within limits based on applicable LHGR limit values given in Tables 8.2 and 8.2.A for appropriate fuel and rod type.
7.3.3 During single loop operation, the LHGR for each fuel type shall not exceed the values given in 7.3.2 above multiplied by the appropriate value (0.78 for GE12 and GE14 fuel).
Rev. No. 15 Page 8 of 32
CORE OPERATING LIMITS REPORT . ' ,
CYCLE 17 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 < 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 3.11 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 = Maximurm 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. 15 Page 9 of 32
CORE OPERATING LIMITS REPORT C YCLE 17 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 = Any intercept value may be used because the RBM intercept value does not effect the MCPR Operating Limit 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. 15 Page 10 of 32
CORE OPERATING LIMITS REPORT CYCLE 17
- -1 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 3.6)
Kf = MAX [1.0, A - SLOPE
- WT]
WHERE:
WT = CoreFlowas%ofRated,30% <-WT < 100%
SLOPE = (AF/100/OLMCPR ) * (SLMCPR /SLMCPR generic)
A = (B, /OLMCPR ) * (SLMCPR /SLMCPR 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, 8.1.B 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.
AF, BF = Coefficients for the Kf curve listed below:
Scoop Tube Setpoint % Ar l Bs, 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 i'
Rev. No. 15 Page 11 of 32
. 7--
CORE OPERATING LIMITS REPORT CYCLE 17 8.0 FIGURES Al 4D TABLES 8.1 FIGURES Figure 8.1. MCPR Operating Limit Versus T for GE12 and GE14.
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 GE14.
Figure 8.1.B MCPR Operating Limit Versus X for Operation with Turbine Bypass Valves Out of Service Figure 8.1.C MCPR Operating Limit Versus X for Operation with Final Feedwater Temperature Reduction Figure 8.2 Kf Factor Figure 8.3 Exposure Dependent APLHGR Limit for GE14 Fuel Figure 8.3.A Exposure Dependent APLHGR Limit for GE12 Fuel Figure 8.4 Stability Option 1D Exclusion Region Figure 8.5 Exposure Dependent LHGR Limit for GE14 Fuel.
Figure 8.5.A Exposure Dependent LHGR Limit for GE12 Fuel.
Figure 8.6. Cycle 17 Loading Pattern, Full Core by Bundle Design Figure 8.7 Users Guide F.
Rev. No. 15 Page 12 of 32
CORE OPERATING LIMITS REPORT CYCLE 17 8.2 TABLES Table 8.1 MCPR Operating Limit for Incremental Cycle Core Average Exposure Table 8.1.A MCPR Operating Limit for Incremnental Cycle Core Average Exposure for Operation above 75% of Rated Thermal Power with Three Steam Lines in Service Table 8.11.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 Table 8.2 Maximum LHGR - GE14 Table 8.2.A Maximum LHGR - GE12 Table 8.3 APLHGR Limits for GE14 Fuel Table 8.3 A APLHGR Limits for GE12 Fuel 9.0 EXHIBITS NONE i
Rev. No. Page 13 of 32
CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.1 MCPR Operating Limit For Incremental Cycle Core Average Exposure Cycle 17 Exposure Range l ' All Fuel Types BOC to <EOC-2.7 GWD/ST 1.41 EOC-2.7 GWD/ST 1.45 to BOG 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 any value of K, see Step 7.5.2 I
.1 Rev. No. 15 Page 14 of 32
CORE OPERATING LIMITS REPORT CYCLE 17 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 16 Exposure Range All Fuel Types BOC to <EOC-2.7 GWD/ST 1.43 EOC - 2.7 GWD/ST 1.47 to EOC 14 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 any value of K, see Step 7.5.2 I
A Rev. No. 15 Page 15 of 32
CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.1.B MCPR Operating Limit for Operation with Turbine Bypass Valves Out of Service Cycle 17 Exposure Range All Fuel Types ALL 1.49 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 any value of K, see Step 7.5.2 I
Rev. No. 15 Page 16 of 32
If.
CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.1.C MCPR Operating Limit for Operation with Final Feedwater Temperature Reduction Cycle 16 Exposure Range All Fuel Types At EOC only (see below) 1.45 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 trto assure adjustment per Step 7.1.4
- 2. Applicable for any value of K, see Step 7.5.2 MCPR Operating Limits in this table apply when at reduced feedwater temperature near end-of-cycle, secJD-02-122 (Reference 3.14) for further information.
Rev. No. 15 Page 17 of 32
CORE OPERATING LIMITS REPORT CYCLE 17
- G;.
TABLE 8.2 Maximum LHGR -GE14 Peak Pellet Exposure U0 2 LHGR Limit GWd/ST kW/ft 0.00 13.40 14.51 13.40 57.61 8.00 63.50 5.00 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWd/ST kW/ft 0.00 12.26 12.28 12.26 55.00 7.32 60.84 4.57 Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)
Design features of the fuel assemblies in the Cycle 17 core are provided in References 3.3, 3.16 For single loop operation these LHGR values shall be multiplied by 0.78 Linearly interpolate for LHGR at intermediate exposure Rev. No. 15 Page 18 of 3L2 C
CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.2.A Maximum LHGR - GE12 Peak Pellet Exposure U0 2 LHGR Limit GWd/ST kW/ft 0.00 11.80 13.24 11.80 63.50 6.39 Peak Pellet Exposure Most Limiting Gadolinia LHGR Limit GWd/ST kW/ft 0.00 11.35 11.69 11.35 63.50 6.20 Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)
Design features of the fuel assemblies in the Cycle 17 core are provided in References 3.3, 3.16 For single loop operation these LHGR values shall be multiplied by 0.78 Linearly interpolate for LHGR at intermediate exposure Rev. No. 15 Page 19 of 32
CORE OPERATING LIMITS REPORT CYCLE 17 TABLE 8.3 Exposure Dependent APLHGR Limit for GE14 Fuel Average Planar APLHGR Limit Exposure GWd/ST kW/ft 0.00 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 A 5.00 TABLE 8.3.A Exposure Dependent APLHGR Limit for GE12 Fuel Average Planar APLHGR Limit Exposure GWd/ST kW/ft 0.00 10.62 13.24 10.62 24.20 10.62 63.50 6.39 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 Linearly interpolate for APLHGR at intermediate exposure Rev. No. 15 Page 20 of 32
CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.1 MCPR Operating Limit Versus ¶ For All Fuel Types
.62 c
._ -I -I 2C .52 2
0 0 0.1 0.2 0.3 0.4 0.5 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 17).
I Rev. No. 15 Page 21 of 32 I
CORE OPERATING LIMITS REPORT . CYCLE 16 FIGURE 8.1.A MCPR Operating Limit Versus X For Operating Above 75% of Rated Thermal Power with Three Steam Lines in Service For all Fuel Types 1.70 1.64
.1 C.
E
.0
>1.54 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I T 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 17).
I I
Rev. No. 15 Page 22 of 32
I -I :
CORE OPERATING LIMITS REPORT CYCLE 16 FIGURE 8.1.B MCPR Operating Limit Versus X for Operation with Turbine Bypass Valves Out of Service 1.7 0 1.66 M
-J ca 0
3-a) 0o 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 17).
I Rev. No. 15 Page 23 of 32
CORE OPERATING LIMITS REPORT CYCLE 16 FIGURE 8.1.C MCPR Operating Limit Versus 'r for Operation with Final Feedwater Temperature Reduction 1.65
- 1.62 C'
0 1.6-2 I
- 1.5 X t-4.
1.45_
0 1.4 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 I Tt Technical Specification LCO 3.2.2, Minimum Critical Powver 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 17).
Rev . No. 15 Page 24 of 32
CORE OPERATING LIMITS REPORT , CYCLE 16 FIGURE 8.2 Kf Factor Cycle 17 Kf Curve for Scoop Tube Stops at 112%
Considers Two Loop and Single Loop Operation, MOC and EOC MCPR Limits 1.15* -- MOC+SLO O EOC+SLO t MOC+TLO X EOC+TLO-1.14 __ _ _=-__ --
1.13 ___The combination of MOC MCPR limit and 610 produces the most limiting K, curve. This set of data determines the 4curovused in the 3D-MONICORE daetbank May be changed when EOC MCPR limits apply. Choice of Single 1.12 - _ _ _ _ _ - Loop K values b for ese of SLO. Two loop limitsare not signitantly different _
1.1 1 SLMCPR 1.0Og(TLO). 1.1O (SLO)
___ \OLMCPRrTLO)
\ K,may be adjusted as needed to provide protection against the SLO Pump 1.09- ; - Sekzursevent. ForGE14.the0LMCPRbtlowtheSLOcoreflowllmltof58% _
_ must be greater than 1.43[SLMCPR11.12), or 1.404. In Cycle 17 the OLMCPR 1.08 __ at MOC+GLO Is1.42 for GE14, so no K,adjustment Is required.
References:
h1.07 1.K,CURVEUPDATE,GE-NE-JN11.03426-t01. 1011 6198
- 2. GE14Fue DesignCycle-IndependentAnalysesforJAFNPP.
1.06 5- .ENE-N0004002-1752401P.September 2002 1.05--_\ Equation of Cycle 17 KVairve:
1_ MAX( 10, 1.2648 -0.4358 (% Core FIow/100))
1.03 _ _ _ _ ___ _ __
1.02 -- _ _ _--- _
1.00, 1.01 0.99
_ _ _ _1_
_ _7 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. 15 Page 25 of 32
CORE OPERATING LIMITS REPORT CYCLE 16 FIGURE 8.3 Exposure Dependent APLHGR Limit for GE14 Fuel 14 ---
13 I- I~-~X 12 -
11 . _ ____ _ _ .
9 __
8-6- ___ _ _ _ _ ___ _ \_
5 4 --_ ---- __ _.__ _ _ _ \--
2 -__
2 =- - --
=_ _ _
-. ^
- - _ _-~
0 5 10 15 20 25 30 35 40 45 50 55 60 65 Planar Exposure, GWDIST 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. 15 Page 26 of 32
CORE OPERATING LIMITS REPORT CYCLE 16 FIGURE 8.3.A Exposure Dependent APLHGR Limit for GE12 Fuel 13 -i _ __ - __ __ __
12 10 - ___
9- - _ _ _ __ __ __ __
8 -_
4- __ __ __ __> \
2 -- ___ ___ __ - - ___ __ -- A I - __ ___ -~__ -- : - -
0 5 10 15 2025 303540 4550 5560 65 Planar Exposure, GW DIST 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 5 Page 27 of 32
CORE OPERATING LIMITS REPORT CYCLE 17 FIGURE 8.4 Stability Option 1-D Exclusion Region THE EXCLUSION REGION SHOWN BELOW IS APPLICABLE TO A CYCLE 17 EXPOSURE OF 6000 MWD/ST (see CR-JAF-2004-04360) 20 25 30 35 40 45 50 55 60 65 70
% rated Flow Technical Specification LCO 3.4.1, Recirculation Loops Operating References 3.17, 3.18 I Rev. No. 15 Page 28 of 32
CORE OPERATING LIMITS REPORT CYCLE 16 FIGURE 8.5 Exposure Depcndent LHGR Limit for GE14 Fuel 13 - - - - -- --
9-8 _ _ _____ ____
6- ___ __
5- ______._. ___
2- __- __. __ __ _ -----
1- -__ ___. -- _ ___ - .-- __ -__ _. .
0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 PELLET EXPOSURE GWDIST Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)
This curve represents the limiting exposure dependent LHGR values per Reference 3.16 Design features of the fuel assemblies in the Cycle 17 core are provided in Reference 3.3 Rev. No. 15 Page 29 of 32
CORE OPERATING LIMITS REPORT CYCLE 16 FIGURE 8.5.A Exposure Dependent LHGR Limit for GE12 Fuel 14 -
- 13. __ __
12-85 -_ __ __.___ _ _ __
10 --
7- __ ._ l_ __ __ __
21 = = = _ =_ _-- _. = _ =_ __,_ _
0 5 10 15 20 25 30 35 40 45 50 55 60 65 PELLET EXPOSURE GWDIST Technical Specification LCO 3.2.3, Linear Heat Generation Rate (LHGR)
This curve represents the limiting exposure dependent LHGR values per Reference 3.16 Design features of the fuel assemblies in the Cycle 17 core are provided in Reference 3.3 Rev. No. 15 Page 30 of 32
CORE OPERATING LIMITS REPORT CYCLE 16 FIGURE 8.6 Cycle I17 Loading Pattern by Bundle Design 52 DM [ [ [ [ELf 50 [lmmm[3[E [m El North 48 [ 30m 01 MIE] 1 1[ 1 46 [EA [E1m [E]A0El EA [EA[EN BBDEFI ED[EF F1 [El[Elm 44 F[II[ [0_E] 01[ 1Dff(( MG E]
[ l g11ff]Lg[
42 2IDfE[FED l OE] E~l JIElm F1 MEEi] E AlE] A10 A[3 FEWE 40 nD[ [F] M E[D nW[E EJE] E]J[D E] [Lo n~E l D D[ [l 38 F F [EA TIE]n1 E7[ BE] E1 E]I[D [0fli EASA A F 32 34 m[DI( [3IEI S[GA CE] E]IE] [DE]
AB[ D [D [D 1[3] CTI ATIEA)[E] E1D AIE A1 E]lm FT[ A31 AIj[D ASEMAE] 0E Ejl[D TDO 32 30 fFi 88~ I[ J1m [E AT AD A ADI ATE Ag[ CUIEBE [GD BE D 28 F [F D Ba [AE]ID FDE [F3A E] AI E A E L EA1[ E]
2e IMS[ED MItE] FLOM [TigE-TIE- DIE] [01[3 ETISTE ETIFOTD F1[3 ETilo10 01mEET[
24 22 [D(D[DJD il E EA] [D[
El[
E[DE] E0[ [B1{EEI ll An E1E m[Dj[ 11[E] W1[E]
22 C[E [OFEI GIE] [El1El GEA Com AEl FID Amn EC In FT0 Aim EGA[E [I7IM 20 [10[-El11D E21 E [DIE ETG 1D E1ET r ml[
[D[DED EA10El An E[W ElDX 18 [1Eto[ EIRE] -IEIl]lE P miIE MINE] [l F10e E 15 im [LEl ETID ETIST ETID[01 402 18 FEAE]E] E EAG nl AEFEAE EGAEll[D @ EI A EGA[FD O 14 FID ADEl1AE] mI-E7In E 10 ElIE] I J[l E AG[ F0lo 12 12 E]J[D [EIEI[ EA] An E]TID [DI[D rIIE[ [DIE E RIA EA]TIDEA] [EI] ff]J[
10 GAE GBE][~ GA GAD
'°ES[ETSTE ETE ST1 ETE S[E T[EETE[3[EHPF1[E]
8 m [E] [1D nIl[DE] [E]T[E]l[E]J[D DE [E1]l11[
2 4 m [l0000000000[ET1 EgEN 1 m [D ET# m[07 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 Fuel Type A=GE14-PIlODNAB405-16GZ-l OOT-150-T6(Cycle 17) E=GE1 2-PIODSB407-14G6.0-l OOT-150-T6 (Cycle 15)
B=GE14-P IODNAB405-15SG6.0-l OOT-150-T6 (Cyclel17) F=GE14-P IODNAB405-16GZ-I OOT-150-T6 (Cycle 16)
C=GE12-PI ODSB405-16GZ-lIOOT-150-T6 (Cycle 15) G=GE,14-PI ODNAB405-16GZ-I OOT-150-T6 (Cycle 16)
D=GE12-PIODSB405-17GZ-IOOT-150-T6 (Cycle 15)
Rev. No. 15 Page 31 of 32
- I
-~ -4 CORE OPERATING LIMITS REPORT CYCLE 16 i 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 < EOC17 - 2.7 GWD/ST
- r= 0 I
- 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.
Change in Operating State Change in Limits Procedure Reference Cycle Exposure = See Table 8.1(8.1 A f6r 3SL) or Figure 8.1 None EOC17 - 2.7 GWD/ST for ** 0(8.1.A for 3SL) for change in OLMCPR changes to EOC values MCPR.
at cycle exposure of 12.0 GWD/ST Kr limit may be changed in recognition of higher OLMCPR.
Scram Time Test Results such that X* 0 Use new T and see Figure 8.1 or 8.1.A for Option B limits for OLMCPR must 3SL Kr limit may be fhanged in RAP-7.4.1 be interpolated with Option A limits recognition of higher.OLMCPR.
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. Kf ST-SE, therefore OLMCPR limits increase does not change. RAP-7.3.25 by 0.01. MFLPD and MAPLHGR Verify that 3D-Monicre has recognized are reduced by a multiplier in SLO. the idle recirculation loop and is applying the SLO MFLPD and MAPLHGR multiplier of 0.78.
Three Steam Line Operation (3SL) Increase OLMCPR according to Table OLMCPR values increase by 0.02 8.1 A or Figure be changed 8.1.A(r
- 0).
in recognition of Kr limit ma higher None when operating on 3SL OLMCPR.
Operation with Turbine Bypass Increase OLMCPR according to Table Valves Out-of-Service 8.1.B or Figure 8.1.B(r
- 0). Kr limit may 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(
- 0). Kr limit may None OLMCPR values increase, no be changed in recognition of higher LHGR change required OLMCPR.
f Rev. No. 15 Page 32 of 32