JAFP-22-0046, Core Operating Limits Report Cycle 26
| ML22290A145 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/17/2022 |
| From: | Mark Hawes Constellation Energy Generation |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-22-0046 | |
| Download: ML22290A145 (24) | |
Text
Constellation ~
JAFP-22-0046 October 17, 2022 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 26 James A. FitzPatrick NPP P.O Box 110 Lycoming, NY 13093 Mark R. Hawes Regulatory Assurance Manager - Acting Enclosed is the James A. FitzPatrick Nuclear Power Plant (JAF) Core Operating Limits Report (COLR). This revision incorporates changes resulting from a reload analysis completed by Global Nuclear Fuel (GNF) for Cycle 26 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) 349-2562.
Very truly yours, Mark R. Hawes Regulatory Assurance Manager (Acting)
MRH
Enclosure:
Core Operating Limits Report for James A. FitzPatrick Nuclear Power Plant Unit 1 Reload 25 Cycle 26 cc: (w/ enclosure)
NRC Regional Administrator, NRC Region 1 NRC Project Manager NRC Resident Inspector NYSE RDA NYSPSC
JAFP-22-0046 ENCLOSURE Core Operating Limits Report for James A. FitzPatrick Nuclear Power Plant Unit 1 Reload 25 Cycle 26 (22 Pages)
Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 Prepared By:
CORE OPERA TING LIMITS REPORT FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT UNIT 1 RELOAD 25 CYCLE 26 V. Riso Cycle Manager 2022.09.22 13:49:35 -04'00' Date: -----
Digitally signed by Bracke, Adam J Date: 2022.09.22 14: 16:44 -04'00' Reviewed By: --------------
Date: ____
A Bracke Independent Reviewer Lar.lmore Brett Dylan Digitally signed by Larimore, Brett Dylan 1
Date: 2022.09.22 14:20:48-04'00' Reviewed By:
Date: ____
B. Larimore Reactor Engineering
- ~~
2022.09.22 14:25:10 Reviewed By:
1Jlljl
-04'00' Date:
Approved By:
N. Todorova Engineering Safety Analysis M. Heverly 2022.09.22 14:42:57 -04'00' Date: ____
Sr. Manager - BWR Cycle Management Ross Andrew M DigitallysignedbyRoss,AndrewM Station Qualified
/
Date: 2022.09.24 08:03:51 -04'00' Review By:
Date: ____
A Ross Station Qualified Reviewer Page 1of22
Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 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 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 Revision History Revision Description Revision 3 First issuance for Cycle 26 Page 3 of 22
Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 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 11 Table4-3 Flow Dependent MCPR Limits, MCPRF, GNF2 Fuel 12 Table4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits, MCPRF, 12 GNF2 Fuel Table 4-5 Flow Dependent MCPR Limits, MCPRF, GNF3 Fuel 12 Table 4-6 Single Loop Operation (SLO) Flow Dependent MCPR Limits, MCPRF, 13 GNF3 Fuel Table4-7 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 Multiplier, 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 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 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 DLO EOC EOOS EOR FFWfR FWHOOS FWfR ICF LHGR LHGRFACF LHGRFACp MAPFACF MAPFACp MAPLHGR MCPR 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/FFWfR.
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 Off-rated power dependent MAPLHGR multiplier Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio Page 5 of 22
Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 MCPR99.9%
MCPRF MCPRP MOC MSIVOOS OLM CPR P-bypass PROOS 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 OLM CPR Defined in the licensing as the exposure corresponding to EOR - 4152 MWd/ST for Cycle 26 (Reference 2)
Main Steam Isolation Valve Out of Service 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 Rated recirculation Required drive flow to achieve rated core flow flow RBM RTP RWE SLMCPR SLO SRVOOS TBSOOS TBVOOS TRM w
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 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 2.0 General Information This report provides the following cycle-specific parameter limits for James A. FitzPatrick Unit 1 Cycle 26:
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 (RBM) 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 80"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 26 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 LiCPR or peak vessel pressure (Reference 2).
Page 7 of 22
Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 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 MAPLHG R 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 MAPLHGRVersus Average Planar Exposure GNF2 Fuel (Reference 2)
Average Planar Exposure MAPLHGR Limit (GWd/ST)
(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/ST)
(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 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 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 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 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. These values are determined by the cycle-specific reload analyses in Reference 2 and are valid for all Cycle 26 operating domains. Table 4-1 includes OLM CPR values for all conditions listed in Section 9.0, Modes of Operation.
For single loop operation, the MCPR operating limit is 0.03 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.
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 8) 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 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 selecting the greater of the two.
Page 10 of 22
Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 EOOS Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)
All Fuel Types (Reference 2)
SCRAM Cycle Exposure Combination Fuel Type Time BOC to 3480 3480 MWd/ST MOC to EOC Option MWd/ST to MOC A
1.47 1.47 BASE All B
1.43 1.35 BASE SLO GNF2 A
1.50 1.50 B
1.54 1.54 B
1.54 1.54 A
1.52 1.52 TBSOOS All B
1.48 1.39 TBSOOS SLO GNF2 A
1.55 1.55 B
1.55 1.55 B
1.54 1.54 PROOS All A
1.47 1.47 B
1.43 1.35 PROOS SLO GNF2 A
1.50 1.50 B
1.54 1.54 B
1.54 1.54 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 1.48 1.35 1.51 1.43 1.54 1.54 1.52 1.39 1.55 1.43 1.55 1.54 1.48 1.35 1.51 1.43 1.54 1.54
>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 2.21 2.21 2.14 1.327 1.225 1.150 1.067 1.067 1.000
~60 2.25 2.25 2.22 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 TBSOOS
< 60 2.35 2.35 2.18 1.327 1.225 1.150 1.067 1.067 1.000 SLO
~ 60 2.72 2.72 2.60 PRO OS
< 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 2.21 2.21 2.14 1.362 1.258 1.221 1.172 1.067 1.000
~ 60 2.25 2.25 2.22 Page 11of22
Constellation Energy Generation - Nuclear Fuels Core Operating Limits Report for FitzPatrick 1 Cycle 26 Table 4-3 Flow Dependent MCPR Limits, MCPRF GNF2 Fuel (Reference 2)
Flow MCPRF 1
(%rated) 0.0 1.76 30.0 1.58 89.4 1.22 112.0 1.22 Table 4-4 COLR FitzPatrick 1, Revision 3 Single Loop Operation (SLO) Flow Dependent MCPR Limits, MCPRF GNF2 Fuel (Reference 2)
Flow MCPRF
(% rated) 0.0 1.79 30.0 1.61 89.4 1.25 112.0 1.25 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 1.20 112.0 1.20 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 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 Table4-6 Single Loop Operation (SLO) Flow Dependent MCPR Limits, MCPRF GNF3 Fuel (Reference 2)
Flow MCPRF
(%rated) 0.0 1.79 30.0 1.61 92.6 1.23 112.0 1.23 Table 4-7 Cycle-Specific SLMCPR (MCPR99.9%)
All Fuel Types (Reference 2)
Loop MCPR99.9%
Operation Limit DLO 1.08 SLO 1.10 Page 13 of 22
Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 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 8-1 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 8-2 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 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 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 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 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 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 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%
a.saw+ 61.3%
117.0% (clamp)
Page 17 of 22 Applicable Drive Flow Range 0 < ws 24.7%
24.7 < w s 47.0%
47.0 < w s 68.7%
W>68.7%
0 < ws 32.7%
32.7 < ws 50.1%
50.1 <WS95.9%
W> 95.9%
Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 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 still 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%, the allowable value for recirculation loop drive flow (W) of 100% 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 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 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 26 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.
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Page 19 of 22
Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 Figure 8-2 Exclusion and Buffer Region Illustration - Reduced Feedwater Temperature Operation (Reference 2) 110
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Page 20 of 22
Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 9.0 Modes of Operation The following conditions are supported by the FitzPatrick Unit 1 Cycle 26 licensing analysis; 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 TBSOOS PROOS A or B A or 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 orSLO DLO orSLO DLO or SLO Condition Power Level Restrictions (% rated) 1 MSIVOOS
~ 75 1 The "BASE" condition includes operation with or without FWHOOS/FFWTR.
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Constellation Energy Generation - Nuclear Fuels COLR FitzPatrick 1, Revision 3 Core Operating Limits Report for FitzPatrick 1 Cycle 26 10.0 Methodology The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, 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 25 Cycle 26", Global Nuclear Fuel Document No. 006N2045, Revision 1, September 2022.
- 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 25 Cycle 26", Global Nuclear Fuel Document No. 006N2046, Revision 0, June 2022.
- 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 11)," Global Nuclear Fuel Document No. NEDC-33270P, Revision 11, August 2020.
- 7.
"Scram Times Versus Notch Positions for Option B", GNF 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.
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