JAFP-24-0044, Core Operating Limits Report Cycle 27
| ML24260A031 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/16/2024 |
| From: | Mark Hawes Constellation Energy Generation |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| JAFP-24-0044 | |
| Download: ML24260A031 (1) | |
Text
James A. FitzPatrick NPP Constellation P.O. Box 110 Lycoming, NY 13093
Mark R. Hawes Regulatory Assurance
JAFP-24-0044 September 16, 2024
United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333
Subject:
Core Operating Limits Report Cycle 27
Dear Sir or Madam,
Enclosed is the James A. FitzPatrick Nuclear Power Plant (JAF) Core Operating Limits Report (COLA). This revision incorporates changes resulting from a reload analysis completed by Global Nuclear Fuel (GNF) for Cycle 27 operations. This report is submitted in accordance with JAF Technical Specifications (TS) 5.6.5.
There are no new regulatory commitments contained in this letter. Questions concerning this report may be addressed to Mr. Andrew Ross, (315) 349 - 6444.
Very truly yours,
- t0.~
Mark R. Hawes Regulatory Assurance
MRH
Enclosure:
Core Operating Limits Report for James A. FitzPatrick Nuclear Power Plant Unit 1 Reload 26 Cycle 27
cc: (w/ enclosure)
NRC Regional Administrator, NRC Region 1 NRC Project Manager NRC Resident Inspector NYSERDA NYSPSC JAFP-24-0044
ENCLOSURE
Core Operating Limits Report for James A. FitzPatrick Nuclear Power Plant Unit 1 Reload 26 Cycle 27
(22 Pages)
Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
CORE OPERA TING LIMITS REPORT
FOR
JAMES A. FITZPATRICK NUCLEAR POWER PLANT
UNIT 1 RELOAD 26 CYCLE 27
Hackett, Digitally signed by Hackett,
Alexandra A I exa n d ra Date: 2024.09.13 05:29:45 -05'00' Date: ____ _
Prepared By: --------------
A. Hackett Cycle Manager
~ rvtcCl.w.L Mcclure, Kelly Reviewed By : ---~__....,,___ ____ 2_0_2_4._09_.13 ~\\Q7:37 -04'00' K. McClure Independent Reviewer
0191tally s igned by O' Neil.
O'Neil Christopher Christopher Reviewed By: ' oate : 2024.o9.1Jo6 :00:0J -0 4*oo
- Date: ____ _
C. O'Neil Reactor Engineering
Digitally signed by Norman,
Reviewed By:~ ~Timothy Date: 2024.09.1308:4B:13 Date: ____ _
T.r~~
EnQineerinQ Safety Analysis Ir. _ Digitally signed by
~ ~~ Mccoskey, Kristin Date: 2024.09.14 11 :12:24 Approved By: -05'00' Date: ____ _
K. Mccoskey Sr. Manager - BWR Cycle Management Ross, Andrew ~~g~~:~ ~gned by Ross, Station Qualified M Date: 2024.09.1412:23:24 Review By: -04*00* Date: ____ _
A. Ross Station Qualified Reviewer
Page 1of22 Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
Table of Contents
Page
Revision History 3
List of Tables 4
List of Figures 5
1.0 Terms and Definitions 5 2.0 General Information 7
3.0 MAPLHGR Limits 8
4.0 MCPR Limits 10
5.0 LHGR Limits 14
6.0 APRM Allowable Values 17
7.0 RBM Allowable Values 18
8.0 Power/Flow Exclusion Region and Buffer Zone 19
9.0 Modes of Operation 21
10.0 Methodology 22
11.0 References 22
Page 2 of 22 Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
Revision History
Revision Description
Revision 4 First issuance for Cycle 27
Page 3 of 22 Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
List of Tables Page
Table 3-1 MAPLHGR Versus Average Planar Exposure, GNF2 Fuel 8
Table 3-2 MAPLHGR Versus Average Planar Exposure, GNF3 Fuel 8
Table 3-3 MAPLHGR Single Loop Operation (SLO) Multiplier, All Fuel Types 9
Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR), All Fuel Types 11
Table 4-2 Power Dependent MCPR Limits and Multipliers, MCPRP and KP, All Fuel Types 12
Table 4-3 Flow Dependent MCPR Limits, MCPRF, GNF2 Fuel 12
Table 4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits, MCPRF, 12 GNF2 Fuel
Table 4-5 Flow Dependent MCPR Limits, MCPRF, GNF3 Fuel 13
Table 4-6 Single Loop Operation (SLO) Flow Dependent MCPR Limits, MCPRF, 13 GNF3 Fuel
Table 4-7 Cycle-Specific SLMCPR (MCPR99.9%), All Fuel Types 13
Table 5-1 Linear Heat Generation Rate Limits - U02 Rods 14
Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods 14
Table 5-3 LHGR Single Loop Operation (SLO) Multiplier 14
Table 5-4 Power Dependent LHGR Multiplier, LHGRFACP, GNF2 Fuel 15
Table 5-5 Power Dependent LHGR Multiplier, LHGRFACP, GNF3 Fuel 15
Table 5-6 Flow Dependent LHGR MuUiplier, LHGRFACF, GNF2 Fuel 16
Table 5-7 Flow Dependent LHGR Multiplier, LHGRFACF, GNF3 Fuel 16
Table 6-1 APRM Allowable Values 17
Table 7-1 Rod Block Monitor Setpoints 18
Table 9-1 Modes of Operation 21
Table 9-2 "BASE" EOOS Option - Included Conditions 21
Table 9-3 Power Level Restrictions 21
Page 4 of 22 Constellation Energy Generation -Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
List of Figures
Figure 8-1 Exclusion and Buffer Region Illustration - Normal Feedwater 19 Temperature Operation
Figure 8-2 Exclusion and Buffer Region Illustration - Reduced Feedwater 20 Temperature Operation
1.0 Terms and Definitions
APLHGR Average Planar Linear Heat Generation Rate
APRM Average Power Range Monitor
BASE This condition is defined by a group of individual operating conditions that are applicable to all Modes of Operation discussed in Section 9. The "BASE" condition includes the EOOS conditions provided in Table 9-2, concurrent with FWHOOS/FFWTR.
CPR Critical Power Ratio
DLO Dual Loop Operation
EOG End of Cycle
EOOS Equipment Out of Service
EOR End of Rated ; the cycle exposure at which reactor power is equal to rated thermal power with recirculation system flow equal to 100%, all control rods fully withdrawn, nominal feedwater temperature, and equilibrium xenon.
FFWTR Final Feedwater Temperature Reduction
FWHOOS Feedwater Heater(s) Out of Service
FWTR Feedwater Temperature Reduction
ICF Increased Core Flow
Off-rated power dependent OLMCPR multiplier
LHGR Linear Heat Generation Rate
LHGRFACF Off-rated flow dependent LHGR multiplier
LHGRFACp Off-rated power dependent LHGR multiplier
MAPFACF Off-rated flow dependent MAPLHGR multiplier
. Page 5 of 22 Constellation Energy Generation -Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
MAPFACp Off-rated power dependent MAPLHGR multiplier
MAPLHGR Maximum Average Planar Linear Heat Generation Rate
MCPR Minimum Critical Power Ratio
MCPR99.9% Limiting MCPR value such that 99.9 percent of the fuel in the core is not susceptible to boiling transition
Off-rated flow dependent OLMCPR
Off-rated power dependent OLMCPR
MOC Defined in the licensing as the exposure corresponding to EOR -5006 MWd/ST for Cycle 27 (Reference 2)
MSIVOOS Main Steam Isolation Valve Out of Service
NRC Nuclear Regulatory Commission
OLM CPR Operating Limit Minimum Critical Power Ratio
P-bypass Reactor power level below which the TSV position and the TCV fast closure scrams are bypassed
PROOS Pressure Regulator Out of Service
RBM Rod Block Monitor
RTP Rated Thermal Power
RWE Rod Withdrawal Error
SLM CPR Safety Limit Minimum Critical Power Ratio
SLO Single Loop Operation
SRVOOS Safety/Relief Valve(s) Out of Service
TB SOOS Turbine Bypass System Out of Service
TBVOOS Turbine Bypass Valve(s) Out of Service
TRM Technical Requirements Manual w Loop drive flow in percent of rated
Page 6 of 22 Constellation Energy Generation -Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
2.0 General Information
This report provides the following cycle-specific parameter limits for James A. FitzPatrick Unit 1 Cycle 27:
- Average Planar Linear Heat Generation Rate (APLHGR)
- Minimum Critical Power Ratio (MCPR) and MCPR99.9%
- Linear Heat Generation Rate (LHGR)
- Flow-Biased Average Power Range Monitor (APRM) Allowable Values
- Rod Block Monitor (RSM) Upscale Function Allowable Values
- Power/Flow Exclusion Region
This report is prepared in accordance with Technical Specification 5.6.5 of Reference 1. Preparation of this report was performed in accordance with Constellation Energy Generation, Nuclear Fuels T&RM NF-AB-120-3600.
The data presented in this report is valid for all licensed operating domains on the operating map, including (Reference 2) :
- Maximum Extended Load Line Limit down to the minimum licensed core flow (i.e., 79.8%
of rated) during full power operation (2536 MWth)
- Rated core flow of 77.0 Mlb/hr
- Increased Core Flow (ICF) up to 105% of rated core flow
- Final Feedwater Temperature Reduction (FFWTR) up to B0°F limited to the load line corresponding to 95% rated core flow at rated power during cycle extension operation
- Feedwater Heater Out of Service (FWHOOS) feedwater temperature reduction up to 80°F limited to the load line corresponding to 95% rated core flow at rated power during normal operation
- End-of-Cycle coastdown to minimum power level of 40%
Further information on the cycle-specific analyses for FitzPatrick Unit 1 Cycle 27 and the associated operating domains discussed above is available in Reference 2.
Per Technical Specification 5.6.5, these values have been determined using NRG-approved methodology and are established such that all applicable limits of the plant safety analysis are met.
A variation of 2% in core flow or 10 psi in dome pressure or 10°F in feedwater temperature has a negligible effect on the calculated llCPR or peak vessel pressure (Reference 2).
Page 7 of 22 Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
3.0 MAPLHGR Limits
3.1 Technical Specification Sections 3.2.1 and 3.4.1
3.2 Description
The MAPLHGR limits for the most limiting lattice for GNF2 fuel, as a function of average planar exposure, are given in Table 3-1. The MAPLHGR limits for the most limiting lattice for GNF3 fuel, as a function of average planar exposure, are given in Table 3-2. For single loop operation, a multiplier is used, which is shown in Table 3-3 for GNF2 and GNF3 fuel.
The power and flow dependent multipliers for MAPLHGR have been removed and replaced with LHGRFACP and LHGRFACF; therefore, MAPFACp and MAPFACF are equal to 1.0 for all power and flow conditions (Reference 2). LHGRFACp and LHGRFACF are addressed in Section 5.0.
Table 3-1 MAPLHGR Versus Average Planar Exposure GNF2 Fuel (Reference 2)
Average Planar Exposure MAPLHGR Limit (GWd/STl (kW/ft) 0.00 13.78 17.52 13.78 60.78 7.50 63.50 6.69
Table 3-2 MAPLHGR Versus Average Planar Exposure GNF3 Fuel (Reference 2)
Average Planar Exposure MAPLHGR Limit (GWd/STl (kW/ft) 0.00 14.36 21.22 13.01 40.82 10.75 57.60 8.00 63.50 6.00
Page 8 of 22 Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
Table 3-3 MAPLHGR Single Loop Operation (SLO) Multiplier All Fuel Types (Reference 2)
GNF2 SLO Multiplier 0.85
Page 9 of 22 Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
4.0 MCPR Limits
4.1 Technical Specification Sections 3.2.2, 3.4.1, and 3.7.6
4.2 Description
The Operating Limit MCPR (OLMCPR) is provided in Table 4 - 1 and is applicable to GNF2 and GNF3 fuel, as specified, and is valid for all Cycle 27 operating domains.
These values are determined by the cycle-specific reload analyses in References 2 and
- 9. Note : the RWE-related OLMCPR results in Reference 2, the SRLR, are superseded by those found in Reference 9, the RWE Re-Evaluation. Table 4-1 includes OLMCPR values for all conditions listed in Section 9.0, Modes of Operation. For single loop operation, the MCPR operating limit is 0.02 greater than the analyzed dual loop value.
A minimum value of 1.43 is required for GNF2 fuel and a minimum value of 1.54 is required for GNF3 fuel for the SLO OLMCPR as set by the Single Loop Operation Recirculation Pump Seizure Event (Reference 2).
Control rod scram time verification is required per Technical Specification 3.1.4, "Control Rod Scram Times". Tau (r), a measure of scram time performance to notch position 36 throughout the cycle, is determined based on cumulative scram time test results (Reference 7). The calculation of Tau shall be performed in accordance with site procedures. Linear interpolation shall be used to calculate the OLMCPR value if Tau is between 0.0 (Tau Option B) and 1.0 (Tau Option A).
The power dependent MCPR limits for GNF2 and GNF3 fuel are presented in Table 4-2.
Below P-bypass, the MCPRP limits in Table 4-2 are applied directly; at or above P-bypass, the KP multiplier is applied to the OLMCPR from Table 4-1. The appropriate MCPRP or KP value may be determined by linear interpolation for points not explicitly listed. The flow dependent MCPR limits for each fuel type and recirc loop combination are provided in Tables 4-3, 4-4, 4-5, and 4-6.
The cycle specific SLMCPR, known as MCPR99.9%, can be found in Table 4-7 for dual loop and single loop operating conditions for GNF2 and GNF3 fuel. The values in Table 4-7 or conservative values were used to calculate the rated and off-rated MCPR limits.
The OLMCPR is determined for a given power and flow condition by evaluating the power and flow dependent MCPR values for the given fuel type and equipment combination and selecting the greater of the two.
Page 10 of 22 Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)
All Fuel Types (References 2 and 9)
EOOS Fuel SCRAM Cycle Exposure 1 Combination Type Time Option BOC to 4600 MWd/ST 7350 MWd/ST 7700 MWd/ST MOCtoEOC 4600 MWd/ST to 7350 MWd/ST to 7700 MWd/ST to MOC BASE All A 1.47 1.45 1.46 1.46 1.49 B 1.47 1.39 1.40 1.33 1.35
BASE SLO GNF2 A 1.49 1.47 1.48 1.48 1.51 B 1.49 1.43 1.43 1.43 1.43
BASE SLO GNF3 A 1.54 1.54 1.54 1.54 1.54 B 1.54 1.54 1.54 1.54 1.54
TBSOOS All A 1.50 1.50 1.51 1.51 1.51 B 1.47 1.45 1.46 1.39 1.39
TBSOOS SLO GNF2 A 1.52 1.52 1.53 1.53 1.53 B 1.49 1.47 1.48 1.43 1.43
TBSOOS SLO GNF3 A 1.54 1.54 1.54 1.54 1.54 B 1.54 1.54 1.54 1.54 1.54
PROOS All A 1.47 1.45 1.46 1.46 1.49 B 1.47 1.39 1.40 1.33 1.35
PROOS SLO GNF2 A 1.49 1.47 1.48 1.48 1.51 B 1.49 1.43 1.43 1.43 1.43
PROOS SLO GNF3 A 1.54 1.54 1.54 1.54 1.54 B 1.54 1.54 1.54 1.54 1.54
1 At breakpoint exposures, the more conservative OLMCPR value (i.e., the larger value) of both exposure ranges should be applied.
Page 11of22 Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
Table 4-2 Power Dependent MCPR Limits and Multipliers, MCPRP and KP All Fuel Types (Reference 2)
Core Core Thermal Power (% of Rated)
EOOS Flow 0 25 s 29 > 29 40 60 s 85 >85 100 Combination (%of Operating Limit Operating Limit MCPR Multiplier, KP rated) MCPR, MCPRP BASE < 60 2.18 2.18 2.11 1.327 1.225 1.150 1.067 1.067 1.000
- 60 2.22 2.22 2.19 BASE SLO < 60 2.20 2.20 2.13 1.327 1.225 1.150 1.067 1.067 1.000
- 60 2.24 2.24 2.21 TBSOOS < 60 2.32 2.32 2.15 1.327 1.225 1.150 1.067 1.067 1.000
- 60 2.69 2.69 2.57 TB SOOS < 60 2.34 2.34 2.17 1.327 1.225 1. 150 1.067 1.067 1.000 SLO ;
- : 60 2.71 2.71 2.59 PROOS < 60 2.18 2.18 2.11 1.362 1.258 1.221 1. 172 1.067 1.000
- 60 2.22 2.22 2.19 PROOS SLO < 60 2.20 2.20 2.13 1.362 1.258 1.221 1.172 1.067 1.000
- 60 2.24 2.24 2.21
Table 4-3 Flow Dependent MCPR Limits, MCPRF GNF2 Fuel (Reference 2)
Flow MCPRF1
(% rated) 0.0 1.76 30.0 1.58 89.4 1.22 112.0 1.22
Table 4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits, MCPRF GNF2 Fuel (Reference 2)
Flow MCPRF
(%rated) 0.0 1.78 30.0 1.60 89.4 1.24 112.0 1.24
1 Values are applicable up to a Maximum Runout Flow of 112% of rated.
Page 12 of 22 Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
Table 4-5 Flow Dependent MCPR Limits, MCPRF GNF3 Fuel (Reference 2)
Flow MCPRF 1
(% rated) 0.0 1.76 30.0 1.58 92.6 1.20 100.0 1.20
Table 4-6 Single Loop Operation (SLO) Flow Dependent MCPR Limits, MCPRF GNF3 Fuel (Reference 2)
Flow MCPRF
(% rated) 0.0 1.78 30.0 1.60 92.6 1.22 100.0 1.22
Table 4-7 Cycle-Specific SLMCPR (MCPR99.9%)
All Fuel Types (Reference 2)
Exposure Loop MCPR99.9%
Range Operation Limit BOC to DLO 1.07 7350 MWd/ST SLO 1.09 7350 MWd/ST DLO 1.08 to EOG SLO 1.10
1 Values are applicable up to a Maximum Runout Flow of 112% of rated.
Page 13 of 22 Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
5.0 LHGR Limits
5.1 Technical Specification Sections 3.2.3 and 3.7.6
5.2 Description
The LHGR limits for all fuel types is the product of the applicable exposure dependent LHGR limit (from Table 5-1 for U02fuel rods and Table 5-2 for Gadolinia fuel rods) and the minimum of the applicable power dependent LHGR factor, LHGRFACp, and the applicable flow dependent LHGR factor, LHGRFACF. The LHGRFACP multipliers are determined from Tables 5-4 and 5-5. The LHGRFACF multipliers are determined from Tables 5-6 and 5-7 and are applicable up to a Maximum Runout Flow of 112% of rated.
The single loop operation multipliers are shown in Table 5-3 and applied in Tables 5-6 and 5-7.
Linear interpolation should be used for points not explicitly listed, or as directed in References 6 and 8 for Tables 5-1 and 5-2.
Table 5-1 Linear Heat Generation Rate Limits - U02 Rods (References 4, 6, and 8)
Fuel Type LHGR GNF2 See Table B-1 of Reference 6 GNF3 See Table A-1 of Reference 8
Table 5-2 Linear Heat Generation Rate Limits - Gadolinia Rods (References 4, 6, and 8)
Fuel Type LHGR GNF2 See Table B-2 of Reference 6 GNF3 See Table A-2 of Reference 8
Table 5-3 LHGR Single Loop Operation (SLO) Multiplier (Reference 2)
GNF2 SLO Multiplier 0.85
Page 14 of 22 Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cyc le 27
Table 5-4 Power Dependent LHGR Multiplier, LHGRFACp GNF2 Fuel (Reference 2)
Core Core Thermal Power (% of Rated)
EOOS Flow 0 25 s 29 > 29 40 60 85 100 Combination (%of LHGRFACp Multiplier rated)
BASE < 60 0.513 0.513 0.524 0.625 0.683 0.789 0.921 1.000
~ 60 0.513 0.513 0.524 BASE SLO < 60 0.513 0.513 0.524 0.625 0.683 0.7 89 0.921 1.000
<?: 60 0.513 0.513 0.524 TBSOOS < 60 0.415 0.415 0.470 0.625 0.683 0.789 0.921 1.000
~ 60 0.408 0.408 0.410 TBSOOS SLO < 60 0.415 0.415 0.470 0.625 0.683 0.789 0.921 1.000
<?: 60 0.408 0.408 0.410 PROOS < 60 0.513 0.513 0.524 0.625 0.683 0.789 0.921 1.000
~ 60 0.513 0.513 0.5 24 PROOS SLO < 60 0.513 0.513 0.524 0.625 0.683 0.789 0.921 1.000
~ 60 0.513 0.513 0.524
Table 5-5 Power Dependent LHGR Multiplier, LHGRFACp GNF3 Fuel (Reference 2)
Core Core Thermal Power (% of Rated)
EOOS Flow 0 25 s 29 > 29 40 60 85 100 Combination (%of LHGRFACp Multiplier rated)
BASE < 60 0.512 0.512 0.515 0.625 0.720 1.000 1.000 1.000
~ 60 0.512 0.512 0.515 BASE S LO < 60 0.512 0.512 0.515 0.625 0.720 1.000 1.000 1.000
~ 60 0.512 0.512 0.515 TBSOOS < 60 0.512 0.512 0.515 0.625 0.720 0.965 0.967 1.000
~ 60 0.425 0.425 0.452 TBSOOS SLO < 60 0.512 0.512 0.515 0.625 0.720 0.965 0.967 1.000
~ 60 0.425 0.425 0.4 5 2 PROOS < 60 0.512 0.512 0.515 0.625 0.720 0.900 0.980 1.000
~ 60 0.512 0.512 0.515 PROOS SLO < 60 0.512 0.512 0.515 0.625 0.720 0.900 0.980 1.000
<:: 60 0.512 0.512 0.515
Page 15 of 22 Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
Table 5-6 Flow Dependent LHGR Multiplier, LHGRFACF GNF2 Fuel (Reference 2)
Core Flow (% of rated)
EOOS Combination 0 30 62.94 85 110 LHGRFACF Multiplier Dual Loop Operation 0.422 0.626 1.000 1.000 Single Loop Operation 0.422 0.626 0.850 0.850
Table 5-7 Flow Dependent LHGR Multiplier, LHGRFACF GNF3 Fuel (Reference 2)
Core Flow (% of rated)
EOOS Combination 0 30 50 60 70.29 85 112 LHGRFACF Multiplier Dual Loop Operation 0.429 0.562 0.651 0.830 1.000 1.000 Single Loop Operation 0.429 0.562 0.651 0.830 0.900 0.900
Page 16 of 22 Constellation Energy Generation -Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
6.0 APRM Allowable Values
6.1 Technical Specification Sections 3.3. 1. 1 and 3.4.1
6.2 Description
When operating in MODE 1, the APRM Neutron Flux-High (Flow Biased) Allowable Values shall be set as provided in Table 6-1. APRM Neutron Flux-High (Flow Biased)
Rod Block Allowable Values are found in TRM 3.3.B, Control Rod Block Instrumentation.
Table 6-1 APRM Allowable Values (Reference 3)
APRM Neutron Flux-High Allowable Value (% RTP) Applicable Drive Flow (Flow Biased) Function Range
0.38W + 61.0% O<WS24.7%
1.15W + 42.0% 24.7 < w s 47.0%
Dual Loop Operation 0.63W + 73.7% 47.0 < w s 68.7%
117.0% (clamp) W> 68.7%
0.38W + 57.9% 0 < ws 32.7%
1.15W+ 32.8% 32.7 < w s 50.1%
Single Loop Operation 0.58W + 61.3% 50.1 < w s 95.9%
117.0% (clamp) W> 95.9%
Page 17 of 22 Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
7.0 RBM Allowable Values
7.1 Technical Specification Sections 3.3.2. 1 and 3.4.1
7.2 Description
The Rod Block Monitor Upscale Allowable Values are determined from the relationships shown in Table 7-1. The setpoint is set at maximum equipment adjustability limits and complies with the RWE analysis because RWE is analyzed unblocked (Reference 2).
The allowable value is clamped with a maximum value not to exceed 120.9% power at 100% recirculation flow (W) per Reference 5.
Table 7-1 Rod Block Monitor Setpoints (Reference 5)
Rod Block Monitor Upscale Trip Allowable Value (%RTP)
Function
Dual Loop and Single Loop Operation s 0.66W + 54.9%
Page 18 of 22 Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
8.0 Power/Flow Exclusion Region and Buffer Zone
8.1 Technical Specification Section 3.4.1
8.2 Description
The FitzPatrick Unit 1 Cycle 27 power/flow relationship for the Stability Option 1-D Exclusion and Buffer Region is shown in Figure 8-1 for Normal Feedwater Temperature Operation and in Figure 8-2 for Reduced Feedwater Temperature Operation.
Figure 8-1 Exclusion and Buffer Region Illustration - Normal Feedwater Temperature Operation (Reference 2)
110 -.--- ~ -.. E -xc ~lu ~s ~io ~n ~R -eg ~1o~ n-- o -u -nd ~a -~ -....-.-......-.......-.-,.-,....-......-,-.--. __,....,.-,--.. __,....,.. -.--,. ~-.-.-...-.--.-.-........-~..-.-.
--+- - Buffer Region Bounda~
100
90
80
I I
-~ 70, I I 0
I
-.... I Cl) I I
~ 60 I 0 I I D.. I I ns 50 I I I
E /
.... I Cl) I
.J:. I I
..... 40 '
' I
30 - - - - - - -* - -* - - - - - -I - - - - - - - - - - -* -* - -_I_ - - - - - - - -_1_ - - - -_I_ - - -* -* - - - - - --- - -
- _ *** * - ** _ _ _ _ _ _ _ _ ** _ ** __ **** *. *.1 *** _ __ I_ **** _._ ** __ I_ ** - ** - ** _______ _
20 I t I I I
__ L __________ l I I I I
- _ ** ___ L ___
- __ 1 ______ I ______ 1 ________________ _
10 I I I I 0
0 10 20 30 40 50 60 70 80 90 100 11 0 120 Core Flow (%)
Page 19 of 22 Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
Figure 8-2 Exclusion and Buffer Region Illustration - Reduced Feedwater Temperature Operation (Reference 2)
110 -+- xc us1on Region Boundary
--+- - Buffer Region Boundary 100
90
80 - - - - - - - - - - - - - - - --1-' - - - - - - - - - - - - - -
I I t I '
- 70 - - - - - - - - - - - - - - - --1-' - - - - - - - - -------------------------------------------
'#. I
-.. I
- I t l ' I
- 60 - - - - - '- - - - - -.- - - - - -
- - - - - -,- - --1'-- -. - - -:- - - - - -:- - - - - -:- - - - - -:- - - - - - - - - - - - - - - - -
Q,,, 0 / I ' '
I
' /I I I I I E "' 50 -----------------,- - - _ ' ' 1 I I l. - - - - - - - - - -'- - -.. -_1_ - - - --*-J - - - --*-I - - --- - - - - - - - - - - -
.. 11 Cl)
.c 40 //
t- ', I
30
20
10 - _ 1_ - - - - - - - - - - - - - - - - -'- - - - -_,_ - - - --*-- - - - _,_ - - - - - - - - - - - - - - - -
I I I t I 0
0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow (%)
Page 20 of22 Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
9.0 Modes of Operation
The following conditions are supported by the FitzPatrick Unit 1 Cycle 27 licensing analyses; operation in a condition (or conditions) is controlled by station procedures. If a combination of options is not listed, it is not supported. Table 9-1 provides allowed modes of operation with thermal limit sets in this COLR. Table 9-2 provides allowed modes of operation that do not contain explicit thermal limit sets in this COLR. Table 9-3 provides power level restrictions that support specific operating conditions.
Table 9-1 Modes of Operation (Reference 2)
EOOS Options Supported Scram Speed Supported Recirculation Option Loops
BASE 1 Aor B DLO or SLO TB SOOS Aor B DLO or SLO PROOS Aor B DLO or SLO
Table 9-2 "BASE" EOOS Option - Included Conditions (Reference 2)
Condition 2 SRVOOS 1 TBVOOS 1 MSIVOOS
Table 9-3 Power Level Restrictions (Reference 2)
Condition Power Level Restrictions (% rated) 1 MSIVOOS s 75
1 The 'BASE ' condition also includes operation with o r w ithout FWHOOS/FFWTR. Operating with FWTR is limited to the 95% load line.
Page 21 of 22 Constellation Energy Generation -Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27
10.0 Methodology
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRG, specifically those described in the following document:
- 1. "General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-31, November 2020 and U.S. Supplement NEDE-24011-P-A-31-US, November 2020.
11.0 References
- 1. "James A. FitzPatrick Nuclear Power Plant Renewed Fac ility Operating License", Docket No. 50-333, Renewed License No. DPR-59.
- 2. "Supplemental Reload Licensing Report for FitzPatrick Reload 26 Cycle 27", Global Nuclear Fuel Document No. 007N6705, Revision 0, July 2024.
3. "Setpoint Calculation for APRM A through F", FitzPatrick Calculation Doc No. JAF-CALC NMS-00758, Revision 12, March 2019.
4. "Fuel Bundle Information Report for FitzPatrick Reload 26 Cycle 27", Global Nuclear Fuel Document No. 007N6706, Revision 0, June 2024.
- 5. "Setpoint Calculation for the Rod Block Monitor (07RBM-82A, B)", FitzPatrick Calculation Doc. No. JAF-CALC-NMS-00759, Revision 8D, October 2018.
6. "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)," Global Nuclear Fuel Document No. NEDC-33270P, Revision 11, August 2020.
- 7. "Scram Times Versus Notch Positions for Option B", Global Nuclear Fuel Letter REK E:02-009, May 28, 2002.
8. "GNF3 Generic Compliance with NEDE-24011-P-A (GESTAR II)," Global Nuclear Fuel Document No. NEDC-33879P, Revision 4, August 2020.
9. "FitzPatrick Cycle 27 RWE Re-Evaluation for Minimum Energy Impacts," Global Nuclear Fuel Document No. 008N9262, Revision 0, September 2024.
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