JAFP-18-0097, Submittal of Core Operating Limits Report Cycle 24
| ML18285A113 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/12/2018 |
| From: | Drews W Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-18-0097 | |
| Download: ML18285A113 (20) | |
Text
Exelon Generation JAFP-18-0097 October 12, 2018 United States Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 James A. FitzPatrick NPP P.O. Box 110 Lycoming, NY 13093 William C. Drews 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 24
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 24 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. Steven J. DeFillippo, (315) 349-6455.
Very truly yours, William C. Drews Regulatory Assurance Manager WD/mh
Enclosure:
Core Operating Limits Report for James A. FitzPatrick Nuclear Power Plant Unit 1 Reload 23 Cycle 24 cc: (w/ enclosure)
NRG Regional Administrator, NRG Region 1 NRG Project Manager NRG Resident Inspector NYSE RDA NYSPSC
JAFP-18-0097 ENCLOSURE Core Operating Limits Report for James A. FitzPatrick Nuclear Power Plant Unit 1 Reload 23 Cycle 24
(18 Pages)
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 1 of 18 CORE OPERATING LIMITS REPORT FORJAMES A. FITZPATRICK NUCLEAR POWER PLANT UNIT 1 RELOAD 23 CYCLE 24 Prepared By: Date: K.PfingstenCycleManagerReviewed By: Date: R.PotterIndependent ReviewerReviewed By: Date: S.DeFillippoReactor EngineeringReviewed By: Date: D. S. Knepper Engineering Safety Analysis Approved By: Date: A.R.JohnsonSr.Manager
- BWR Cycle Management Station Qualified Review By: Date: T. Tuttle StationQualified Reviewer9/20/201809/20/2018 S D D D D D eF eF eF F eF eF F eF F F F F eF eF F F F eF F F eF F F e F e e e eF e e e e e e e e e e e e e e eilli pp o D.S.KnepperEngineeringSafetyAnalysisAll PROOS Operating Limits for MFLCPR and MFLPD (including rated and off-rated)cannot be used until station EC-DCR 625122 is fully implemented.
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 2 of 18 Table of Contents Page Revision History 3 List of Tables 4List of Figures 41.0 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 17 10.0 Methodology 18 11.0 References 18 Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 3 of 18 Revision History Revision Description Revision 0First issuance for Cycle 24 Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 4 of 18 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, MCPR P and K P 10 Table 4-3 Flow Dependent MCPR Limits, MCPR F 11 Table 4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits, MCPR F 11 Table 5-1 Linear Heat Generation Rate Limits
- UO 2 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, LHGRFAC P 13 Table 5-5 Flow Dependent LHGR Multiplier, LHGRFAC F 13 Table 6-1 APRM Allowable Values 14 Table 7-1 Rod Block Monitor Setpoints 15 Table 9-1 Modes of Operation 17 Table 9-2 "BASE" EOOS Option - Included Conditions 17 List of Figures Figure 8-1 Exclusion and Buffer Region Illustration 16 Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 5 of 18 1.0 Terms and Definitions ADSOOS Automatic Depressurization System Out of Service APLHGR Average Planar Linear Heat Generation Rate APRM Average Power Range Monitor ARTS APRM, Rod Block, and Technical Specification Improvement Program 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 FFWTR during cycle extension operation. DLO Dual Loop Operation EOC 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 ICF Increased Core Flow K P Off-rated power dependent OLMCPR multiplier K F Off-rated flow dependent OLMCPR multiplier LHGR Linear Heat Generation Rate LHGRFAC F Off-rated flow dependent LHGR multiplier LHGRFAC P Off-rated power dependent LHGR multiplier MAPFAC F Off-rated flow dependent MAPLHGR multiplier MAPFAC P Off-rated power dependent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR F Off-rated flow dependent OLMCPR MCPR P Off-rated power dependent OLMCPR MELLLA Maximum Extended Load Line Limit Analysis MSIVOOS Main Steam Isolation Valve Out of Service Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 6 of 18 OLMCPR 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 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 Recirculation flow in percent of rated
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 7 of 18 2.0 General Information This report provides the following cycle-specific parameter limits for James A. FitzPatrick Unit 1 Cycle 24: Average Planar Linear Heat Generation Rate (APLHGR) Minimum Critical Power Ratio (MCPR) 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 80F during cycle extension operation at core flow down to 95% rated core flow at rated core power End-of-Cycle coastdown to minimum power level of 40% Further information on the cycle-specific analyses for FitzPatrick Unit 1 Cycle 24 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.
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 8 of 18 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 LHGRFAC P and LHGRFAC F; therefore, MAPFAC P and MAPFAC F are equal to 1.0 for all power and flow conditions (Reference 2). LHGRFAC Pand LHGRFAC F 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 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 9 of 18 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 24 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 1.43 is required to obtain an OLMCPR 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 (), 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 fuel are presented in Table 4-2. Below P-bypass, the MCPR P limits in Table 4-2 are applied directly; at or above P-bypass, the K Pmultiplier is applied to the OLMCPR from Table 4-1. The appropriate MCPR P or K P 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 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 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 10 of 18 Table 4-1 Operating Limit Minimum Critical Power Ratio (OLMCPR) (Reference 2) EOOS Combination SCRAM Time OptionCycle Exposure < EOR - 2587 MWd/ST EOR - 2587 MWd/ST BASE A1.48 1.50 B1.40 1.40 BASE SLO A1.51 1.53 B1.43 1.43 TBVOOS A1.55 1.55 B1.41 1.41 TBVOOS SLO A1.58 1.58 B1.44 1.44 PROOS A1.48 1.50 B1.40 1.40 PROOS SLO A1.51 1.53 B1.43 1.43 Table 4-2 Power Dependent MCPR Limits and Multipliers, MCPR P and K P(Reference 2) EOOS Combination CoreFlow (% of rated)Core Thermal Power (% of Rated)025< 29 29 4060 85100Operating Limit MCPR, MCPR POperating Limit MCPR Multiplier, K PBASE 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 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 11 of 18 Table 4-3 Flow Dependent MCPR Limits, MCPR F (Reference 2) Flow (% rated) MCPR F 10.0 1.75 30.0 1.57 87.5 1.22 117.0 1.22 Table 4-4 Single Loop Operation (SLO) Flow Dependent MCPR Limits, MCPR F (Reference 2) Flow (% rated) MCPR F0.0 1.78 30.0 1.60 87.5 1.25 117.0 1.25 1 Values are applicable up to a Maximum Runout Flow of 112% of rated.
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 12 of 18 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 UO 2fuel rods and Table 5-2 for Gadolinia fuel rods) and the minimum of the power dependent LHGR factor, LHGRFAC P, and the flow dependent LHGR factor, LHGRFAC F. The LHGRFAC P multiplier is determined from Table 5-4. The LHGRFAC Fmultiplier 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
- UO 2 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 GNF2See 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 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 13 of 18 Table 5-4 Power Dependent LHGR Multiplier, LHGRFAC P(Reference 2) EOOS Combination CoreFlow (% of rated)Core Thermal Power (% of Rated)025< 29 29 4060 85100LHGRFAC P 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, LHGRFAC F(Reference 2) EOOS CombinationCore Flow (% of rated)030 62.94 85 110 LHGRFAC FMultiplierDual Loop Operation 0.422 0.626 1.000 1.000 Single Loop Operation 0.422 0.626 0.85 0.85 Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 14 of 18 6.0 APRM Allowable Values 6.1 Technical Specification Section 3.3.1.1 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 Operation0.38W + 61.0% 0 < W 24.7%1.15W + 42.0% 24.7 < W 47.0%0.63W + 73.7% 47.0 < W 68.7%117.0% (clamp) W > 68.7% Single Loop Operation 0.38W + 57.9% 0 < W 32.7%1.15W + 32.8% 32.7 < W 50.1%0.58W + 61.3% 50.1 < W 95.9%117.0% (clamp) W > 95.9%
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 15 of 18 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 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 16 of 18 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 24 power/flow relationship for the Stability Option I-D Exclusion and Buffer Region is shown in Figure 8-1. Figure 8-1 Exclusion and Buffer Region Illustration (Reference 2)
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 17 of 18 9.0 Modes of Operation The following conditions are supported by the FitzPatrick Unit 1 Cycle 24 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 9-1 Modes of Operation (Reference 2) EOOS Options Supported Scram Speed Option Supported Recirculation LoopsBASE A or BDLO or SLO TBVOOS A or BDLO or SLOPROOS A or BDLO or SLO Table 9-2 "BASE" EOOS Option - Included Conditions (Reference 2) Condition SRVOOS MSIVOOS 1 1 MSIVOOS is valid only at power levels allowed per station procedure.
Exelon Nuclear - Nuclear Fuels COLR FitzPatrick 1, Revision 0 Core Operating Limits Report for FitzPatrick 1 Cycle 24 Page 18 of 18 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-26, January 2018 and U.S. Supplement NEDE-24011-P-A-26-US, January 2018. 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 23 Cycle 24", Global Nuclear Fuel Document No. 004N2209, Revision 0, July 2018.
3."Setpoint Calculation for APRM A through F", FitzPatrick Calculation Doc No. JAF-CALC-NMS-00758 Revision 11, January 2006.
4."Fuel Bundle Information Report for FitzPatrick Reload 23 Cycle 24", Global Nuclear Fuel Document No. 004N2210, Revision 0, July 2018.
5."Setpoint Calculation for the Rod Block Monitor (07RBM
-82A, B)", FitzPatrick Calculation Doc. No. JAF-CALC-NMS-00759, Revision 8, September 2018.
6."GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GESTAR II)," Global Nuclear Fuel Document No. NEDC-33270P, Revision 9, December 2017.
7."Scram Times Versus Notch Positions for Option B", GNF Letter REK-E:02-009, May 28, 2002.