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
Constellation JAFP-24-0044 September 16, 2024 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Dear Sir or Madam,
James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333 Core Operating Limits Report Cycle 27 James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Mark R. Hawes Regulatory Assurance 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' Prepared By: --------------
A. Hackett Cycle Manager Date: ____ _
~ rvtcCl.w.L Mcclure, Kelly Reviewed By: ---~__....,,___ ____
2_0_2_4._09_.13 ~\\Q7:37 -04'00' K. McClure Independent Reviewer 0191tally signed by O'Neil.
O'Neil Christopher Christopher Reviewed By:
oate: 2024.o9.1Jo6:00:0J -04*oo*
Date: ____ _
C. O'Neil Reactor Engineering Digitally signed by Norman,
~Timothy Reviewed By:~
Date: 2024.09.1308:4B:13 T.r~~
EnQineerinQ Safety Analysis Ir Digitally signed by
~
~~
Mccoskey, Kristin Date: 2024.09.14 11 :12:24
-05'00' Approved By:
K. Mccoskey Sr. Manager - BWR Cycle Management Ross, Andrew
~~g~~:~ ~gned by Ross, Date: ____ _
Date: ____ _
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 Temperature Operation 19 Figure 8-2 Exclusion and Buffer Region Illustration - Reduced Feedwater Temperature Operation 20 1.0 Terms and Definitions APLHGR APRM BASE CPR DLO EOG EOOS EOR FFWTR FWHOOS FWTR ICF LHGR LHGRFACF LHGRFACp MAPFACF Average Planar Linear Heat Generation Rate Average Power Range Monitor 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.
Critical Power Ratio Dual Loop Operation End of Cycle Equipment Out of Service 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.
Final Feedwater Temperature Reduction Feedwater Heater(s) Out of Service Feedwater Temperature Reduction Increased Core Flow Off-rated power dependent OLMCPR multiplier Linear Heat Generation Rate Off-rated flow dependent LHGR multiplier Off-rated power dependent LHGR multiplier 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 MAPLHGR MCPR MCPR99.9%
MOC MSIVOOS NRC OLM CPR P-bypass PROOS RBM RTP RWE SLM CPR SLO SRVOOS TB SOOS TBVOOS TRM w
Off-rated power dependent MAPLHGR multiplier Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio 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 Defined in the licensing as the exposure corresponding to EOR - 5006 MWd/ST for Cycle 27 (Reference 2)
Main Steam Isolation Valve Out of Service Nuclear Regulatory Commission Operating Limit Minimum Critical Power Ratio Reactor power level below which the TSV position and the TCV fast closure scrams are bypassed Pressure Regulator Out of Service Rod Block Monitor Rated Thermal Power Rod Withdrawal Error Safety Limit Minimum Critical Power Ratio Single Loop Operation Safety/Relief Valve(s) Out of Service Turbine Bypass System Out of Service Turbine Bypass Valve(s) Out of Service Technical Requirements Manual 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 GNF3 SLO Multiplier 0.90 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 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 COLR FitzPatrick 1, Revision 4 Combination Type Time BOC to 4600 MWd/ST 7350 MWd/ST 7700 MWd/ST Option 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 EOOS Table 4-2 Power Dependent MCPR Limits and Multipliers, MCPRP and KP All Fuel Types (Reference 2)
Core Core Thermal Power (% of Rated)
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
- 60 BASE SLO
< 60
- 60 TBSOOS
< 60
- 60 TB SOOS
< 60 SLO
- 60 PROOS
< 60
- 60 PROOS SLO
< 60
- 60 2.18 2.18 2.11 1.327 1.225 1.150 2.22 2.22 2.19 2.20 2.20 2.13 1.327 1.225 1.150 2.24 2.24 2.21 2.32 2.32 2.15 1.327 1.225 1.150 2.69 2.69 2.57 2.34 2.34 2.17 1.327 1.225 1.150 2.71 2.71 2.59 2.18 2.18 2.11 1.362 1.258 1.221 2.22 2.22 2.19 2.20 2.20 2.13 1.362 1.258 1.221 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 1.067 1.067 1.067 1.067 1.067 1.067 1.067 1.067 1.172 1.067 1.172 1.067 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 1.000 1.000 1.000 1.000 1.000 1.000
Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report for FitzPatrick 1 Cycle 27 Table 4-5 Flow Dependent MCPR Limits, MCPRF GNF3 Fuel (Reference 2)
Flow MCPRF1
(% rated) 0.0 1.76 30.0 1.58 92.6 1.20 100.0 1.20 Table 4-6 COLR FitzPatrick 1, Revision 4 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 GNF3 SLO Multiplier 0.90 Page 14 of 22
Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 4 Core Operating Limits Report for FitzPatrick 1 Cycle 27 Core EOOS Flow Combination
(%of rated)
BASE
< 60
~ 60 BASE SLO
< 60
<?: 60 TBSOOS
< 60
~ 60 TBSOOS SLO
< 60
<?: 60 PROOS
< 60
~ 60 PROOS SLO
< 60
~ 60 Core EOOS Flow Combination
(%of rated)
BASE
< 60
~ 60 BASE SLO
< 60
~ 60 TBSOOS
< 60
~ 60 TBSOOS SLO
< 60
~ 60 PROOS
< 60
~ 60 PROOS SLO
< 60
<:: 60 Table 5-4 Power Dependent LHGR Multiplier, LHGRFACp GNF2 Fuel (Reference 2)
Core Thermal Power (% of Rated) 0 25 s 29
> 29 40 60 LHGRFACp Multiplier 0.513 0.513 0.524 0.625 0.683 0.789 0.513 0.513 0.524 0.513 0.513 0.524 0.625 0.683 0.789 0.513 0.513 0.524 0.415 0.415 0.470 0.625 0.683 0.789 0.408 0.408 0.410 0.415 0.415 0.470 0.625 0.683 0.789 0.408 0.408 0.410 0.513 0.513 0.524 0.625 0.683 0.789 0.513 0.513 0.524 0.513 0.513 0.524 0.625 0.683 0.789 0.513 0.513 0.524 Table 5-5 Power Dependent LHGR Multiplier, LHGRFACp GNF3 Fuel (Reference 2)
Core Thermal Power (% of Rated) 0 25 s 29
> 29 40 60 LHGRFACp Multiplier 0.512 0.512 0.515 0.625 0.720 1.000 0.512 0.512 0.515 0.512 0.512 0.515 0.625 0.720 1.000 0.512 0.512 0.515 0.512 0.512 0.515 0.625 0.720 0.965 0.425 0.425 0.452 0.512 0.512 0.515 0.625 0.720 0.965 0.425 0.425 0.452 0.512 0.512 0.515 0.625 0.720 0.900 0.512 0.512 0.515 0.512 0.512 0.515 0.625 0.720 0.900 0.512 0.512 0.515 Page 15 of 22 85 100 0.921 1.000 0.921 1.000 0.921 1.000 0.921 1.000 0.921 1.000 0.921 1.000 85 100 1.000 1.000 1.000 1.000 0.967 1.000 0.967 1.000 0.980 1.000 0.980 1.000
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 LHGRFACF Multiplier Dual Loop Operation 0.422 0.626 1.000 Single Loop Operation 0.422 0.626 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 LHGRFACF Multiplier Dual Loop Operation 0.429 0.562 0.651 0.830 Single Loop Operation 0.429 0.562 0.651 0.830 0.900 Page 16 of 22 110 1.000 0.850 85 112 1.000 1.000 0.900
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.
APRM Neutron Flux-High (Flow Biased) Function Dual Loop Operation Single Loop Operation Table 6-1 APRM Allowable Values (Reference 3)
Allowable Value (% RTP) 0.38W + 61.0%
1.15W + 42.0%
0.63W + 73.7%
117.0% (clamp) 0.38W + 57.9%
1.15W+ 32.8%
0.58W + 61.3%
117.0% (clamp)
Page 17 of 22 Applicable Drive Flow Range O<WS24.7%
24.7 < w s 47.0%
47.0 < w s 68.7%
W> 68.7%
0 < ws 32.7%
32.7 < w s 50.1%
50.1 < w s 95.9%
W> 95.9%
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 Function Dual Loop and Single Loop Operation Page 18 of 22 Allowable Value (%RTP) s 0.66W + 54.9%
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)
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--+--
Buffer Region Bounda~
100 90 80 70 60 50 40 30 20 10 0
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30 40 50 60 70 80 Core Flow (%)
Page 19 of 22 90 100 11 0 120
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) 110 100 90 80
- 70
- 60 0
Q,,,
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.c 40 t-30 20 10 0
-+-
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--+-- Buffer Region Boundary 0
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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 BASE1 TB SOOS PROOS Aor B Aor B Aor B 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)
DLO or SLO DLO or SLO DLO or SLO Condition Power Level Restrictions (% rated) 1 MSIVOOS s 75 1 The 'BASE' condition also includes operation with or without 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 Facility 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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