JAFP-20-0075, Core Operating Limits Report Cycle 25
| ML20280A611 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/06/2020 |
| From: | Sullivan R Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-20-0075 | |
| Download: ML20280A611 (21) | |
Text
Exelon Generation,,.
JAFP-20-0075 October 6, 2020 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 Richard M. Sullivan Regulatory Assurance Manager James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRG Docket No. 50-333
Subject:
Core Operating Limits Report Cycle 25
Dear Sir or Madam,
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 25 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. John Darweesh, (315) 349-7444.
Richard M. Sullivan Regulatory Assurance Manager RMS/mh
Enclosure:
Core Operating Limits Report for James A. FitzPatrick Nuclear Power Plant Unit 1 Reload 24 Cycle 25 cc: (w/ enclosure)
NRG Regional Administrator, NRG Region 1 NRG Project Manager NRG Resident Inspector NYSERDA NYSPSC
JAFP-20-0075 ENCLOSURE Core Operating Limits Report for James A. FitzPatrick Nuclear Power Plant Unit 1 Reload 24 Cycle 25 (19 Pages)
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 1 of 19 CORE OPERATING LIMITS REPORT FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT UNIT 1 RELOAD 24 CYCLE 25 Prepared By:
Date:
J. Schaefer / V. Riso Cycle Manager Reviewed By:
Date:
K. McClure Independent Reviewer Reviewed By:
Date:
K. Leaveck Reactor Engineering Reviewed By:
Date:
D. S. Knepper Engineering Safety Analysis Approved By:
Date:
A. Kovacs Sr. Manager BWR Cycle Management Station Qualified Review By:
Date:
K. Leaveck Station Qualified Reviewer FWTR (if applicable) and FFWTR cannot be used until station engineering change is fully implemented to address power-flow map stability regions that are bounding per 006N1761 Rev 0.
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 2 of 19 Table of Contents Page Revision History 3 List of Tables 4 List of Figures 4 1.0 Terms and Definitions 5
2.0 General Information 7
3.0 MAPLHGR Limits 8
4.0 MCPR Limits 9
5.0 LHGR Limits 12 6.0 APRM Allowable Values 14 7.0 RBM Allowable Values 15 8.0 Power/Flow Exclusion Region and Buffer Zone 16 9.0 Modes of Operation 18 10.0 Methodology 19 11.0 References 19
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 3 of 19 Revision History Revision Description Revision 1 First issuance for Cycle 25
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 4 of 19 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure 8
Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier 8
Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) 10 Table 4-2 Power Dependent MCPR Limits and Multipliers, MCPRP and KP 10 Table 4-3 Flow Dependent MCPR Limits, MCPRF 11 Table 4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits, MCPRF 11 Table 4-5 Cycle-Specific SLMCPR (MCPR99.9%)
11 Table 5-1 Linear Heat Generation Rate Limits UO2 Rods 12 Table 5-2 Linear Heat Generation Rate Limits Gadolinia Rods 12 Table 5-3 LHGR Single Loop Operation (SLO) Multiplier 12 Table 5-4 Power Dependent LHGR Multiplier, LHGRFACP 13 Table 5-5 Flow Dependent LHGR Multiplier, LHGRFACF 13 Table 6-1 APRM Allowable Values 14 Table 7-1 Rod Block Monitor Setpoints 15 Table 9-1 Modes of Operation 18 Table 9-2 Included Conditions 18 Table 9-3 Power Level Restrictions 18 List of Figures Figure 8-1 Exclusion and Buffer Region Illustration Normal Feedwater Temperature Operation 16 Figure 8-2 Exclusion and Buffer Region Illustration Reduced Feedwater Temperature Operation 17
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 5 of 19 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 condition includes the EOOS conditions provided in Table 9-2, concurrent with FFWTR during cycle extension operation.
DLO Dual Loop Operation 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 FWTR Feedwater Temperature Reduction ICF Increased Core Flow KP 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 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 MCPRF Off-rated flow dependent OLMCPR MCPRP Off-rated power dependent OLMCPR MELLL Maximum Extended Load Line Limit MSIVOOS Main Steam Isolation Valve Out of Service OLMCPR Operating Limit Minimum Critical Power Ratio
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 6 of 19 P-bypass Reactor power level below which the TSV position and the TCV fast closure scrams are bypassed PROOS Pressure Regulator Out of Service Rated recirculation Required drive flow to achieve rated core flow flow RBM Rod Block Monitor RTP Rated Thermal Power RWE Rod Withdrawal Error SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation SRVOOS Safety/Relief Valve(s) Out of Service TBVOOS Turbine Bypass Valve(s) Out of Service TRM Technical Requirements Manual W
Loop drive flow in percent of rated
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 7 of 19 2.0 General Information This report provides the following cycle-specific parameter limits for James A. FitzPatrick Unit 1 Cycle 25:
Average Planar Linear Heat Generation Rate (APLHGR)
Minimum Critical Power Ratio (MCPR) and MCPR(99.9%)
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 Exelon Nuclear, 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:
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 during cycle extension operation (and Feedwater Temperature Reduction (FWTR) during normal operation, if applicable) at or below the 103% rod line.
End-of-Cycle coastdown to minimum power level of 40%
Further information on the cycle-specific analyses for FitzPatrick Unit 1 Cycle 25 and the associated operating domains discussed above is available in Reference 2.
Per Technical Specification 5.6.5, these values have been determined using NRC-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
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 8 of 19 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, is given in Table 3-1. For single loop operation, a multiplier is used, which is shown in Table 3-2. 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 (Reference 2)
Average Planar Exposure (GWd/ST)
MAPLHGR Limit (kW/ft) 0.00 13.78 17.52 13.78 60.78 7.50 63.50 6.69 Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 2)
SLO Multiplier 0.85
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 9 of 19 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) for GNF2 fuel is provided in Table 4-1. These values are determined by the cycle-specific reload analyses in Reference 2 and are valid for all Cycle 25 operating domains. 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 0.03 greater than the analyzed dual loop value. A minimum value of 1.44 is required to obtain an OLMCPR set by the Single Loop Operation Recirculation Pump Seizure Event.
Control rod scram time verif 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 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 and 4-4.
The cycle-specific SLMCPR, known as MCPR99.9%, can be found in Table 4-5 for dual loop and single loop operating conditions. The values in Table 4-5 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 and selecting the greater of the two.
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 10 of 19 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR)
(Reference 2)
EOOS Combination SCRAM Time Option Cycle Exposure
< 3583 MWd/ST 3583 MWd/ST
& < EOR 3997 MWd/ST 3997 MWd/ST BASE A
1.45 1.45 1.50 B
1.39 1.32 1.36 BASE SLO A
1.48 1.48 1.53 B
1.44 1.44 1.44 TBVOOS A
1.54 1.54 1.54 B
1.57 1.57 1.57 B
1.44 1.44 1.44 PROOS A
1.45 1.45 1.50 B
1.39 1.32 1.36 PROOS SLO A
1.48 1.48 1.53 B
1.44 1.44 1.44 Table 4-2 Power Dependent MCPR Limits and Multipliers, MCPRP and KP (Reference 2)
EOOS Combination Core Flow
(% of rated)
Core Thermal Power (% of Rated) 0 25 29
> 29 40 60 85 100 Operating Limit MCPR, MCPRP Operating Limit MCPR Multiplier, KP BASE
< 60 2.41 2.41 2.35 1.520 1.390 1.150 1.056 1.000 60 2.74 2.74 2.63 BASE SLO
< 60 2.44 2.44 2.38 1.520 1.390 1.150 1.056 1.000 60 2.77 2.77 2.66 TBVOOS
< 60 2.53 2.53 2.35 1.520 1.390 1.150 1.056 1.000 60 2.74 2.74 2.63 TBVOOS SLO
< 60 2.56 2.56 2.38 1.520 1.390 1.150 1.056 1.000 60 2.77 2.77 2.66 PROOS
< 60 2.41 2.41 2.35 1.520 1.390 1.177 1.164 1.000 60 2.74 2.74 2.63 PROOS SLO
< 60 2.44 2.44 2.38 1.520 1.390 1.177 1.164 1.000 60 2.77 2.77 2.66
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 11 of 19 Table 4-3 Flow Dependent MCPR Limits, MCPRF (Reference 2)
Flow
(% rated)
MCPRF1 0.0 1.76 30.0 1.58 89.4 1.22 117.0 1.22 Table 4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits, MCPRF (Reference 2)
Flow
(% rated)
MCPRF 0.0 1.79 30.0 1.61 89.4 1.25 117.0 1.25 Table 4-5 Cycle-Specific SLMCPR (MCPR99.9%)
(Reference 2)
Loop Operation MCPR99.9%
Limit DLO 1.08 SLO 1.10 1 Values are applicable up to a Maximum Runout Flow of 112% of rated.
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 12 of 19 5.0 LHGR Limits 5.1 Technical Specification Sections 3.2.3 and 3.7.6 5.2 Description The LHGR limit for the GNF2 fuel type is the product of the exposure dependent LHGR limit (from Table 5-1 for UO2 fuel rods and Table 5-2 for Gadolinia fuel rods) and the minimum of the power dependent LHGR factor, LHGRFACP, and the flow dependent LHGR factor, LHGRFACF. The LHGRFACP multiplier is determined from Table 5-4. The LHGRFACF multiplier is determined from Table 5-5.
The single loop operation multiplier is shown in Table 5-3 and applied in Table 5-5.
Linear interpolation should be used for points not explicitly listed.
Table 5-1 Linear Heat Generation Rate Limits UO2 Rods (References 4 and 6)
Fuel Type LHGR GNF2 See Table B-1 of Reference 6 Table 5-2 Linear Heat Generation Rate Limits Gadolinia Rods (References 4 and 6)
Fuel Type LHGR GNF2 See Table B-2 of Reference 6 Table 5-3 LHGR Single Loop Operation (SLO) Multiplier (Reference 2)
SLO Multiplier 0.85
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 13 of 19 Table 5-4 Power Dependent LHGR Multiplier, LHGRFACP (Reference 2)
EOOS Combination Core Flow
(% of rated)
Core Thermal Power (% of Rated) 0 25 29
> 29 40 60 85 100 LHGRFACP Multiplier 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 0.789 0.921 1.000 60 0.513 0.513 0.524 TBVOOS
< 60 0.415 0.415 0.470 0.625 0.683 0.789 0.921 1.000 60 0.408 0.408 0.410 TBVOOS 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 0.524 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 Flow Dependent LHGR Multiplier, LHGRFACF (Reference 2)
EOOS Combination Core Flow (% of rated) 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
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 14 of 19 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 (Flow Biased) Function Allowable Value (% RTP)
Applicable Drive Flow Range Dual Loop Operation 0.38W + 61.0%
1.15W + 42.0%
0.63W + 73.7%
117.0% (clamp)
W > 68.7%
Single Loop Operation 0.38W + 57.9%
1.15W + 32.8%
0.58W + 61.3%
117.0% (clamp)
W > 95.9%
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 15 of 19 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 Allowable Value (%RTP)
Dual Loop and Single Loop Operation 0.66W + 54.9%
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 16 of 19 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 25 power/flow relationship for the Stability Option I-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)
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 17 of 19 Figure 8-2 Exclusion and Buffer Region Illustration Reduced Feedwater Temperature Operation (Reference 2)
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 18 of 19 9.0 Modes of Operation The following conditions are supported by the FitzPatrick Unit 1 Cycle 25 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 Option Supported Recirculation Loops BASE A or B DLO or SLO TBVOOS A or B DLO or SLO PROOS A or B DLO or SLO Table 9-2 Included Conditions (Reference 2)
Condition SRVOOS1 MSIVOOS2 Table 9-3 Power Level Restrictions (Reference 2)
Condition Power Level Restrictions (% rated) 1 MSIVOOS 1 Includes up to 2 SRVOOS.
2 Includes up to 1 MSIVOOS.
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 1 Core Operating Limits Report for FitzPatrick 1 Cycle 25 Page 19 of 19 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.
Reactor Fuel,
-24011-P-A-29, October 2019 and U.S. Supplement NEDE-24011-P-A-29-US, October 2019.
11.0 References
- 1.
James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. 50-333, Renewed License No. DPR-59.
- 2.
Reload Licensing Report for FitzPatrick Reload 24 Cycle 25 Nuclear Fuel Document No. 006N1761, Revision 0, July 2020.
- 3.
Setpoint Calculation for APRM A through F FitzPatrick Calculation Doc No. JAF-CALC-NMS-00758 Revision 12, March 2019.
- 4.
Information Report for FitzPatrick Reload 24 Cycle 25 Document No. 005N1960, Revision 0, July 2020.
- 5.
Doc. No. JAF-CALC-NMS-00759, Revision 8D, October 2018.
- 6.
ntage Generic Compliance with NEDE-24011-P-Global Nuclear Fuel Document No. NEDC-33270P, Revision 10, March 2020.
- 7.
REK-E:02-009, May 28, 2002.