ML16327A068

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Issuance of the Core Operating Limits Report for Reload 21, Cycle 22, Revision 11
ML16327A068
Person / Time
Site: Peach Bottom Constellation icon.png
Issue date: 11/18/2016
From: Massaro M
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML16327A068 (28)
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{{#Wiki_filter:- 1 7 ~--*- Exelon Generation November 18, 2016 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington DC 20555-0001 Peach Bottom Atomic Power Station, Unit 2 Renewed Facility Operating License No. DPR-44 NRC Docket No. 50-278 TS 5.6.5.d

Subject:

Issuance of the Core Operating Limits Report for Reload 21, Cycle 22, Revision 11 Enclosed is a copy of Revision 11 of the Core Operating Limits Report (COLR) for Peach Bottom Atomic Power Station (PBAPS) Unit 2 for Reload 21, Cycle 22. Revision 11 of this report incorporates the revised cycle specific parameters resulting from the new core configuration as a result of the PBAPS Unit 2 refueling outage. This COLR is being submitted to the NRC as required by the PBAPS, Unit 2 Technical Specifications (TS) Section 5.6.5.d. If you have any questions concerning this letter, please contact Dave Foss at (717) 456-4311. Michael J. Massaro Site Vice President Peach Bottom Atomic Power Station CCN: 16-101 Attachment Unit 3 Core Operating Limits Report for Reload 21, Cycle 22, Revision 11 cc: Regional Administrator, Region I, USNRC (without attachments) USNRC Senior Resident Inspector, PBAPS (without attachments) Project Manager-PBAPS, USNRC (with attachments) R. R. Janati, Pennsylvania Bureau of Radiation Protection (without attachments) S. T. Gray, State of Maryland (without attachments)

ATTACHMENT Core Operating Limits Report for Reload 21, Cycle 22, Revision 11

E."<clon Nuclear - Nuclcur Fuels P2C22 CoreOpcraling limits Rcporl COLR PEACH BOTTOM 2 Rev. 11 Pagel of26 CORE OPERATING LIMITS REPORT.FOll PEACH ~OTTOM ATOMIC POWER STATION iJNIT 2 Prepared By: Reviewed By: Reviewed By: Independent Review By: Approved By: Station Qualified Reviewer: RELOAD 21, CYCLE 22 (This is a Complete Re-write) P. Henry Engineering Safety Analysis C. Burns J. McHale Date: 10/11/2016 Date: Date: 10/12/2016 D 10/11/2016 ate: ___ _ Date: 10/13/2016-Date:

Exelon Nuclear-Nuclear Fuels P2C22 Core Operating Limits Report Revision History Tenns and Definitions General Infonnation MAPLHGR Limits MCPRLimits Linear Heat Generation Rate Limits Rod Block Monitor Setpoints Turbine Bypass Valve Parameters Table of Contents EOC Recirculation Pump Trip (EOC-RPT) Operability Stability Protection Asymmetric Feedwater Temperature Operation (AFTO) Modes of Operation Methodology References Appendix A (Power/Flow Operating Map for MELLLA+) COLR PEACH BOTTOM 2 Rev. 11 Page 2 of26 Page 3 5 6 7 8 12 14 15 16 17 19 24 25 25 26

Exelon Nuclear-Nuclear Fuels P2C22 Core Operating Limits Repon Revision Revision 11 Revision Historv COLRPEACHBOTTOM2Rev. ll Page 3 of26 Description New Issue for Cycle 22

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 11 Page4 of26 List of Tables Table 3-1 MAPLHGR Versus Average Planar Exposure Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier Table 4-1 Operating Limit Minimum Critical Power Ratio Table 4-2 Power Dependent MCPR(P) Limit Adjustments and Multipliers Table 4-3 Flow Dependent MCPR Limits MCPR(F) Table 4-4 SLO Flow Dependent MCPR Limits MCPR(F) Table 5-1 Linear Heat Generation Rate Limits - U02 rods Table 5-2 Linear Heat Generation Rate Limits - Gad rods Page 7 7 9 10 11 11 12 12 Table 5-3 Power Dependent LHGR Multiplier LHGRF AC(P) 13 Table 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F) 13 Table 6-1 Rod Block Monitor Setpoints 14 Table 7-1 Turbine Bypass System Response Time 15 Table 7-2 Minimum Required Bypass Valves to Maintain System Operability 15 Table 8-1 Recirculation Pump Trip Response Time 16 Table 9-1 Automatic BSP Setpoints for the Scram Region 17 Table 9-2 Manual BSP Endpoints*for Normal Feedwater Temperature 18 Table 9-3 Manual BSP Endpoints for Reduced Feedwater Temperature 18 Table 10-1 AFTO Therinal Limit Penalties 19 Table 10-2 AFTO Power Dependent LHGR Multiplier LHGRF AC(P) 20F < FWT DELTA :5 55F 20 Table 10-3 AFTO Flow Dependent LHGR Multiplier LHGRF AC(F) 20F < FWT DELTA:::; 55F 20 Table 10-4 AFTO Operating Limit Minimum Critical Power Ratio 20F < FWT DELTA::::; 55F 21 Table 10-5 AFTO Power Dependent MCPR Limit Adjustments and Multipliers MCPR(P) 20F < FWT DELTA :5 55F 22 Table 10-6 AFTO Flow Dependent MCPR Limits MCPR(F) 20F < FWT DELTA :5 55F 22 Table 10-7 AFTO MAPLHGR Reduction Factor 23 Table 11-1 Modes of Operation* 24 Table 11-2 "Base" EOOS Option Included Conditions 24

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 11 Page 5 of26 1.0 Terms and Deimitions ABSP AITO AFTOLFWH APRM ARTS BASE BOC DSS-CD DTSP EOC EOOS EOR FFWT'R FWHOOS FWT HFCL HTSP !CF !TSP LHGR LHGRFAC(F) LHGRFAC{P) LTSP MAPLHGR MCPR MCPR(F) MCPR(P) MELLLA MELLLA+ MSlVOOS NCL OLMCPR PR/PLUOOS RDF RPTOOS RTP RWE SLMCPR SLO SRVOOS TBVOOS TBSOOS TCVffSVOOS Automatic Backup Stability Protection Asymmetric FeedwaterTemperature Operation Asymmetric FeedwaterTemp~"rature Operation Loss-of-Feedwater Heating Average Power Range Monitor APRM and RBM Technical Specification Analysis The "!3ASE" condition is defined by a group of individual operating conditions that are applicable lo all Modes of Operation discussed in Section 11. The "BASE" condition includes the EOOS conditions provided in Table 11-2 as well as operation with FWHOOS!FFWTR. Beginning Of Cycle Detect and Suppress Solution -Confirmation Density Rod Block Monitor Downscale Trip Sctpoint EndofCycle Equipment Out of Service. An analyzed option that assumes certain equipment to be non-operational End of Rated. Tiie cycle exposure at which reactor power is equal to I 00% (3951 MWth) with recirculation system Jlow equal to l 00%, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon. Final Feedwater Temperature Reduction Feed waler Heaters Out of Service Feed waler Temperature High Flow Control Line Rod Block Monitor High Trip Setpoint lncrL-ased Core Flow Rod Block Monitor lntennediate Trip Setpoint Linear Heat Generation Rate ARTS LHGR thennal limit flow dependent adjustments and multipliers ARTS LHGR thermal limit power dependent adjustments and multipliers Rod Block Monitor Low Trip Setpoint Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio ARTS MCPR them1nl limit flow dependent adjustments and multipliers ARTS MCPR thermal limit power dependent adjustments and multipliers Maximum ExtendL'CI Load Linc Limit Analysis Maximum fatended Load Line Limit Analysis Plus Main Steam Isolation Valve Out of Service Natural Circulation Line Operating Limit Minimum Critical Power Ratio Pressure Regulator Out ofSe1vice and/or Power Load Unbalance Ol!t of Service Rated Drive Flow Recircl!lalion Pump Trip Out of Service Rated Thermal Power Rod Withdrawal Error Safety Limit Minimum Critical Power Ratio Single Loop Operation Safety Relief Valve Out of Service Turbine Bypass Valve Out of Service Turbine Bypass Syslem Out of Service I Turbine Control Valve and/or I Turbine Stop Valve Out of Service

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report 2.0 General Information COLR PEACH BOTTOM 2 Rev. 11 Page 6 of26 This report provides the following cycle-specific parameter limits for Peach Bottom Atomic Power Station Unit 2 CYCLE 22 (RELOAD 21): Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) Single Loop Operation (SLO) MAPLHGR multipliers Operating Limit Minimum Critical Power Ratio (OLMCPR) ARTS MCPR theOJial limit adjushnents and multipliers Single Loop Operation (SLO) MCPR adjustment Linear Heat Generation Rate (LHGR) ARTS LHGR thermal limit multipliers Single Loop Operation (SLO) LHGR multipliers Rod Block Monitor (RBM) Allowable Values and MCPR Limits Turbine Bypass Valve Parameters EOC Recirculation Pump Trip (EOC-RPT) Parameters Stability Protection Setpoints Asymmetric Feedwater Temperanrre Operation (AFTO) thennal limit penalties These values have been determined using NRC-approved methodology and are established such that all applicable limits of the plant safety analysis are met. SLO, FWHOOS operation, and FFWTR operation are not permitted in the MELLLA+ Region as controlled by station procedures. For the MELLLA+ Region, a specific definition of FWHOOS is provided in Facility Operating License (FOL) Section 2.C(16). This report provides cycle-specific Operating Limit MCPR, LHGR, MAPLHGR thermal limits, and related information for the following conditions: All points in the operating region of the power/flow map including the MELLLA+ Region down to 83% of rated core flow during full power (3951 MWt) operation (Appendix A) Increased Core Flow (!CF), up to 110% of rated core flow End-of-Cycle Power Coastdown to a minimum power level of 40% Feedwater Heaters Out of Service (FWHOOS) to 55° F temperature reduction Final Feedwater Temperature Reduction (PFWTR) between End-of-Rated (EOR) and End-of-Cycle (EOC) to 90° F temperature reduction (4 111 and5th stage FFWTR) Asymmetric FeedwaterTemperature Operation (AFTO) ARTS provides for power-and flow-dependent thennal limit adjustments and multipliers that allow for a more reliable administration of the MCPR and LHGR thennal limits. The OLM CPR is determined by the cycle-specific reload analyses in Reference 2. Rated LHGR values are obtained from the bundle-specific thennal-mechanical analysis. Supporting documentation for the ARTS-based limits is provided in Reference 2. The Allowable Values documented in Reference 5 for feedwater temperature as a timction of thennal power for both FWHOOS and FFWTR are specified in the appropriate Peach Bottom procedures. Also note that the following description of MAPLHGR, LHGR and MCPR limits pertain to NON -AFTO conditions. A separate description of AFTO limits and their associated ARTS tables are located in Section 10. Preparation of this report was perfom1ed in accordance with Exelon Nuclear procedures. This report is provided to the NRC in accordance with Technical Specification 5.6.5 of Reference 1 and contains all thennal limit parameters related to the implementation of the ARTS Improvement Program and MELLLA+ for Peach Bottom Unit 2 Cycle 22.

Exelon Nuclear-Nuclear Fuels P2C22 Core Operating Limits Report 3.0 MAPLHGR LIMITS 3.1 Technical Specification Section 3.2.1, 3.3.4.2, 3.4.1and3.7.6 3.2 Description COLR PEACH BOTTOM 2 Rev.11 Page 7 of26 The MAPLHGR limits (kW/ft) obtained from the emergency core cooling system (ECCS) analysis are provided in Table 3-1. The MAPLHGR limits comprise a given fuel type as a function of average planar exposure. All MAPLHGR values for GNF2 as a function of axial location and average planar exposure shall be less than or equal to the applicable MAPLHGR limits for GNF2 fuel and lattice type. These MAPLHGR limits are specified in Reference 2 and the process computer databank. The SLO MAPLHGR multiplier is provided in Table 3-2 per Reference 2 and must be applied to the Table 3-1 limits when operating in SLO. The impact of AFTO on MAPLHGR is addressed in Section 10. TABLE3-l MAPLHGR Versus Average Planar Exposure (Reference 2) Average Planar Exposure MAPLHGR Limit (GWD/ST) (kW/ft) 0.0 13.78 17.52 13.78 60.78 7.50 63.50 6.69 TABLE3-2 MAPLHGR Single Loop Operation (SLO) Multiplier (Reference 2) SLO Multiplier 0.73

Exelon Nuclear-Nuclear Fuels P2C22 Core Operating Limits Report 4.0 MCPR LIMITS 4.1 Technical Specification Section 2.1.1.2, 3.2.2, 3.3.4.2, 3.4.1 and 3.7.6 4.2 Description COLR PEACH BOTTOM 2 Rev. 11 Page 8 of26 The Operating Limit MCPR (OLMCPR) for GNF2 fuel is provided in Tables 4-1 and 4-2. These values are detennined by the cycle-specific fuel reload analyses in Reference 2. Control rod scram time verification is required as per Technical Specification 3.1.4, "Control Rod Scram Times". Tau, a measure of scram time perfom1ance to notch position 36 throughout the cycle, is determined based on the cumulative scram time test results. The calculation of Tau shall be performed in accordance with site procedures. Linear interpolation shall be used to calculate the OLM CPR value if Tau is between 0.0 (Tau Option B) and 1.0 (Tau Option A). Separate OLMCPR values are presented in Table 4-1 for the following conditions:

  • TBS In-Service (per section 7.0), RPT In-Service (per section 8.0), PLU/PR In-Service, and maximum FFWTR of90 °F (a.k.a. "BASE")
  • TBS Out-of-Service (per section 7.0), RPT Jn-Service (per section 8.0), PLU/PR In-Service, and maximum FFWTR of 90 °F
  • TBS In-Service (per section 7.0), RPT hi-Service (per section 8.0), PLU/PR Out-of-Service, and maximum FFWTR of 90°F
  • TBS hi-Service (per section 7.0), RPT Out-of-Service (per section 8.0), PLU/PR In-Service, and maximum FFWTR of 90 °F The ARTS-based power-dependent MCPR limits are provided in Table 4-2. Table 4-2 is valid for a maximum temperature requction of90 °F for FFWTR operation (bounding for FWHOOS operation). The

'flow-dependent MCPR limits are provided in Tables 4-3 and 4-4. Table 4-3 is valid for dual loop operating conditions with Sy:Imnetric feedwate:r temperature operation and Table 4-4 is valid for single loop operating conditions with symmetric feed water temperature operation. The impact of AFTO on MCPR is addressed in Section 10. For PR/PLUOOS + TBSOOS and PR/PLUOOS + RPTOOS conditions, the limits are listed in Section 10, these values are bounding for non-AFTO conditions.

Exelon Nuclear-Nuclear Fuels P2C22 Core Operating Limits Report TABLE4-1 COLR PEACH BOTTOM 2 Rev. 11 Page 9 of26 Operating Limit Minimum Critical Power Ratio (Reference 2) SCRA.t'\\1 Cycle Exposure Time <EOR-2597 :;:EOR-2597 EOOS Combination Option<1> MWd/ST MWd/ST B 1.41 1.41 BASE A 1.49 1.49 B 1.43 1.43 BASESLO A 1.49 1.49 B 1.41 1.41 RPTOOS A 1.58 1.58 B 1.43 1.43 RPTOOSSLO A 1.58 1.58 B 1.41 1.41 PR/PLUOOS A 1.49 1.49 B 1.43 1.43 PR/PLUOOS SLO A 1.49 1.49 B 1.45 1.45 TB SOOS A 1.54 1.54 B 1.45 1.45 TBSOOS SLO A 1.54 1.54 (1) When Tau does not equal 0 or 1, use linear interpolation

Exelon Nuclear-Nuclear Fuels P2C22 Core Operating Limits Report TABLE 4-2 COLRPEACHBOTTOM2Rev. ll Page 10 of26 Power Dependent MCPR(P) Limit Adjustments And Multipliers (Symmetric Feedwater Heating) (Reference 2) Core Core Thermal Power (% of rated) EOOS Combination Flow(% 0 23 <26.7 '?..26.7 40 55 65 85 100 of rated) Operating Limit MCPR Operating Limit MCPR Multiplier, Kp Base

S60 2.67 2.67 2.60 1.352 1.131 1.082 1.000 1.392 1.317

> 60 2.99 2.99 2.83 Base SLO

S60 2.67 2.67 2.60 1.352 1.317 1.131 1.082 1.000

>60 2.99 2.99 '2.8:3,fa.~* 1.392 RPTOOS

60 2.67' 2.67
  • . 2.60 1.392 1.317 1.131 I.082 1.000 2.99 2.99 2.83 1.352

>60 RPTOOS SLO

60 2.67 2.67 2.60 1.392 1.082 1.000

>60 2.99 ,2.99 1.352 1.317 1.131 2.83 PR/PLUOOS

60 2.67 2.67 2.60 1.352 1.317 1.210 1.147 1.000

>60 2.99 2.99 2.83 1.392 PR/PLUOOSSLO

60 2.67 2.67 2.60 1.352 1.317 1.210 1.147 1.000

>60 2.99 2.99 2.83 1.392' TBSOOS

s 60 3.64 3.64 3.25 1.659 1.479 1.373 1.155 1.082 1.000

>60 4.15 4.15 3.78

60 3.64 3.64 3.25 TBSOOSSLO 1.659 1.479 1.373 1.155 1.082 1.000

>60 4.15 4.15 3.78

Exelon Nuclear -Nuclear Fuels P2C22 Core Operating Limits Report TABLE4-3 COLR PEACH BOTTOM 2 Rev. 11 Page 11 of26 Flow Dependent MCPR Limits MCPR(F) (Symmetric Feedwater Heating) (Reference 2) Core Flow MCPR(F) (%rated) Limit 0.0 1.75 30.0 1.57 79.0 1.28 110.0 1.28 TABLE4-4 SLO Flow Dependent MCPR Limits MCPR(F) (Symmetric Feedwater Heating) eference2 r.===~~ =~===; 30.0 1.57 79.0 1.28 110.0 1.28

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 11 Page 12 of26 5.0 LINEAR HEAT GENERATION RATE LIMITS 5.1 Technical Specification Section 3.2.3, 3.3.4.2, 3.4.1 and 3. 7.6 5.2 Description The LHGR values for GNF2 fuel type are provided in Tables 5-1 and 5-2. The ARTS-based LHGR power-dependent multipliers are provided in Table 5-3. Table 5-3 is valid for a maximum temperature reduction of 90° F for FFWTR operation (bounding for FWHOOS operation). The flow-dependent multipliers are provided in Table 5-4 as a function of the number ofrecirculation loops in operation. The SLQ LHGR multiplier is provided and accounted for in Table 5-4. The power-and flow-dependent LHGR multipliers were obtained from Reference 2. The impact of AFTO on LHGR is addressed in Section 10. For PR/PLUOOS + TBSOOS and PR/PLUOOS + RPTOOS conditions, the limits are listed in Section 10, these values are bounding for non-AFTO conditions. The power and flow dependent LHGR multipliers are sufficient to provide adequate protection for the off-rated conditions from an ECCS-LOCA analysis perspective. TABLES-1 Linear Beat Generation Rate Limits - U02 rods (References 4and11) Fuel Type LHGRLimit GNF2 See Appendix B of Reference 4 TABLE5-2 Linear Heat Generation Rate Limits - Gad rods (References 4 and 11) Fuel Type LHGRLimit GNF2 See Appendix B of Reference 4

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 11 Page 13 of26 TABLES-3 Power Dependent LHGR Multiplier LHGRFAC(P) (Symmetric Feedwater Heating) (Reference 2) EOOS Core Flow Core Thermal Power (% of rated) Combination Base Base SLO RPTOOS RPTOOS SLO PR/PLUOOS PR/PLUOOSSLO TB SOOS TBSOOS SLO EOOS Combination Dual Loop Single Loop (%of 0 23 <26.7 ~26.7

40.

55 rated) LHGRFAC(P) Multiplier

560

> 60

560

>60

560

>60

5 60

>60

5 60

>60

5 60

>60

5 60

>60

5 60

>60 0.508 0.508 0.522 0.620 0.696 b.508 0.508 0.522 0.508 0.508 0.522 0.508 0.508 0.522 0.620 0.696 0.508 0.508 0.522 0.508 0.508 0.522 0.620 0.696 0.508 0.508 0.522 0.620 0.508 0.508 0.522 0.696 0.508 0.508 0.522 0.620 0.696 0.508 0.508 0.522 0.508 0.508 0.522 0.620 0.696 0.508 0.508 0.522 0.397 0.397 0.442 0.620 0.655 0.397 0.397 0.417 0.397 0.397 0.442 0.620 0.655 0.397 0.397 0.417 TABLE5-4 Flow Dependent LHGR Multiplier LHGRFAC(F) (Symmetric Feedwater Heating) (Reference 2) Core Flow (% of rated) 0 30 33.6 70 LHGRFAC(F) Multiplier 0.506 0.706 0.730 0.973 0.506 0.706 0.730 0.730 0.751 0.751 0.751 0.751 0.751 0.751 0.714 0.714 80 1.000 0.730 I 6s 85 0.817 0.930 0.817 0.930 0.817 0.930 0.817 0.930 0.817 0.930 0.817 0.930 0.817 0.930 0.817 0.930 110 1.000 0.730 I 100 1.000 1.000 1.000 1.000 1.000 1.000 1.000 1.000

Exelon Nuclear-Nuclear Fuels P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 11 Page 14 of26 6.0 ROD BLOCK MONITOR SETPOINTS 6.1 Technical Specification Section 3.3.2.1 6.2 Description The RBM power-biased Allowable Values and MCPR Limits are provided in Table 6-1 with supporting documentation in References 2 and 9. These values correspond to the OLMCPR values provide in Table 4-1. Power Level LTSP ITSP HTSP INOP TABLE6-1 Rod Block Monitor Setpoints (References 2 and 9) Allowable Value<1l 118.2% 113.4% 108.4% NIA MCPRLimit < 1.70 <2J < 1.40 (JJ < 1.70 (2) < 1.40 (J) < 1.70 <2> < 1.40 (J} < 1.70 (2) < 1.40 (J} (1) These setpoints (with RBM filter time constant between O.l seconds and 0.55 seconds) are based on a cycle-specific rated RWE MCPR limit which is less than or equal to the minimum cycle OLMCPR based on other events (see COLR References 2 and.9). (2) This is the MCPR limit (given THERMAL POWER is >28.4% and< 90%) below which the RBM is required to be OPERABLE (see COLR Reference 2 and TS Table 3.3.2.1-1). (3) This is the t~CPR limit (given THERMAL POWER is > 90%) below which the RBM is required to be OPERABLE (see COLR Reference 2 and TS Table 3.3.2.1-1). -

Exelon Nuclear -Nuclear Fuels P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 11 Page 15 of26 7.0 TURBINE BYPASS VALVE PARAMETERS 7.1 Technical Specification Section 3.7.6 7.2 Description The operability requirements for the steam bypass system are governed by Technical Specification 3.7.6. If the requirements cannot be met, the appropriate power and flow dependent limits for Turbine Bypass System Out-of-Service (TB SOOS) must be used. Additionally, the OLMCPR for TB SOOS must be applied. Table 7-1 includes the Turbine Bypass Valve response time parameters. The minimum number ofbypass valves to maintain system operability is provided in Table 7-2 per Reference 14. TABLE 7-1 Turbine Bypass System Response Time (Reference 14) Maximum delay time before start of bypass valve opening following initial turbine inlet valve movement(IJ Maximum time after initial turbine inlet valve movement(IJ for bypass valve position to reach 80% of foll flow (includes the above delay time) (I) First movement of any TSV many TCV (whichever occurs first) TABLE7-2 0.10 sec 0.30 sec Minimum Required Bypass Valves To Maintain System Operability (Reference 14) Reactor Power No. of Valves in Service P~23% 7

Exelon Nuclear-Nuclear Fuels P2C22 Core Operating Limits Repon COLR PEACH BOTTOM 2 Rev. 11 Page 16 of26 8.0 EOC RECIRCULATION PUMP TRIP (EOC-RPT) OPERABILITY 8.1 Technical Specification Section 3.3.4.2 8.2 Description The operability requirements for the BOC Recirculation Pump Trip are governed by Technical Specification 3.3.4.2. If the requirements cannot be met, the appropriate power and flow dependent limits for BOC Recirculation Pump Trip Out Of Service (RPTOOS) must be used. Additionally, the OLM CPR for RPTOOS must be applied. Table 8-l includes the total RPT response time parameter. TABLE 8-1 Recirculation Pump Trip Response Time (Reference 14) Total Recirculation Pump Trip Response Time

  • The time from lvhen the turbine valves (turbine control valve or turbine stop valve) start to close until complete arc suppression of the EOC-RPT circuit breakers as described in Reference 7.

0.175 sec

Ex~lon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report 9.0 STABILITY PROTECTION 9.1 Technical Specification COLR PEACH BOTTOM 2 Rev.11 Page 17 of26 Section 3.3.l.1, Table 3.3.1.1-1 Function 2.f, Section 5.6.5 9.2 Description Per Reference 2, the Cycle 22 DSS-CD SAo Setpoint was confirmed to be 1.10 for DLO and SLO. The Automatic Backup Stability Protection (BSP) Setpoints are provided in Table 9-1. The Manual BSP Endpoints for Nonna! Feedwater Temperature and Reduced Feedwater Temperature are provided in Tables 9-2 and Table 9-3, respectively. TABLE9-1 Automatic BSP Setpoints for the Scram Region (Reference 2) Parameter Symbol Value Slope of ABSP APRM flow-IDT rip 1.65 biased trip linear segment. ABSP APRM flow-biased trip setpoint power intercept. Constant Power Line for Trip PasP-Trip 40.5 %RTP from zero Drive Flow to Flow Breakpoint value. ABSP APRM flow-biased trip setpoint drive flow intercept. WasP-Trip I 46.7%RDF Constant Flow Line for Trip. Flow Breakpoint value WasP-Break 25.0 %RDF

Exelon Nuclear -Nuclear Fuels P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 11 Page 18 of26

  • TABLE 9-2<1>

Manual BSP Endpoints for Normal Feedwater Temperature (Reference 2) Endpoint Power(%) Flow(%) Definition Al 75.8 51.0 Scram Region Boundary, HFCL Bl 40.5 31.0 Scram Region Boundary, NCL A2 64.5 50.0 Controlled Entry Region Boundary, HFCL B2 28.1 30.l

  • Controlled Entry Region Boundary, NCL Note: The BSP Boundary for Nonna! and Reduced Feedwater Temperature is defined by the MELLLA boundary line, per Reference 2.

TABLE 9_3<1> Manual BSP Endpoints for Reduced Feedwater Temperature (Reference 2) Endpoint Power(%) Flow(%) Definition Al' 63.8 49:1 Scram Region Boundary, HFCL I Bl' 34.4 30.6 Scram Region Boundary, NCL I A2' 65.9 51.7 Controlled Entry Region Boundary, HFCL B2' I 28.1 30.1 Controlled Entry Region Boundary, NCL I I Note: The BSP Boundary for Normal and Reduced Feed water Temp~rature is defined by the l'vrELLLA boundary line, per Reference 2. (l) Station may elect to place additional administrative margin on the endpoints provided in Table 9-2 and Table 9-3.

Exelon Nuclear-Nuclear Fuels P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 11 Page 19 of26 10.0 ASYMMETRIC FEEDWATER TEMPERATURE OPERATION (AFTO) Asymmetric feed water heating (resulting from removing a heater string, or individual feedwater heaters, from operation) is the result of the specific configuration of the feedwater lines at Peach Bottom. A reduction in heating in either the 'A' or the 'C' heater strings will result in a temperature mismatch between the feedwater flows entering the opposite sides of the reactor vessel. This temperature mismatch may result in errors in the thermal limit values calculated by the core monitoring system. Thenml limit values for all conditions and events are impacted by these errors excluding SLO conditions. The station no longer requires SLO AFTO files or penalties due to a 3D MONICORE upgrade required for EPU operation. Asymmetric feedwater temperature operation (AFTO) is defined as operation in a feedwater heater/string configuration that results in a specified threshold difference as described in Reference 10. To simplify the implementation of the AFTO limits, only the maximum AFTO penalties indicated in Table 10-1 will be implemented when the threshold asymmetry temperature (temperature above which a penalty is required) is exceeded. This will minimize the number of AFTO thermal limit tables in the COLR and core monitoring system. 40F < FWT DEL TA::; 55F 30F <FWT DELTA:S40F 20F < FWT DELTAS30F OF< FWT DELTA:::; 20F TABLEl0-1 AFTO Thermal Limit Penalties (Asymmetric Feedwater Heating) (Reference 10) MFLCPR 3% 2% 2% No Penalty LHGRLIMITS MFLPDIMAPRAT 4% 3% 2% No Penalty The ARTS-based LHGR power-dependent multipliers for AFTO operation are provided in Table 10-2. The flow-dependent multipliers for AFTO in DLO are provided in Table 10-3. The power-and flow-dependent LHGR multipliers were obtained from Reference 2 and were adjusted with the appropriate penalties displayed in Table 10-1 as per Reference 10. PRIPLUOOS + TBSOOS and PR/PLUOOS + RPTOOS values were obtained by taking the most limiting OLM CPR values of the two EOOS conditions, these values are bounding for non~AFTO conditions. The maximum feedwater temperature difference allowed without a thennal limit penalty is 20 °F. Once the temperature difference exceeds 20 °F the maximum penalties from Table 10-1 are applied to the theimal limits. . Additionally, no LHGR penalties are required for asymmetric feedwater temperature option while in SLO as previously discussed.

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report TABLE 10-2 COLRPEACH BOTTOM 2 Rev.11 Page 20 of26 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 20F < FWT DELTAS 55F (Asymmetric Feedwater Heating) (References 2 and 10) Core Core Thermal Power (% of rated) EOOS Combination Flow 0 23 <26.7 ?::.26.7 40 55 65 85 (%of rated) LHGRFAC(P) Multiplier S60 0.488 0.488 0.501 Base 0.595 0.668 0.721 0.784 0.893 >60 0.488 0.488 0.501

60 0.488 0.488 0.501 RPTOOS 0.595 0.668 0.721 0.784 0.893

>60 0.488 0.488 0.501

60 0.488 0.488 0.501 PR/PLUOOS 0.595 0.668 0.721 0.784 0.893

>60 0.488 0.488 0.501

60 0.381 0.381 0.424 TBSOOS 0.595 0.629 0.685 0.784 0.893

> 60 0.381 0.381 0.400

5 60 0.381 0.381 0.424 PR/PLUOOS + TBSOOS 0.595 0.629 0.685 0.784 0.893

>60 0.381 0.381 0.400

560 0.488 0.488 0.501 PR/PLUOOS + RPTOOS 0.595 0.668 0.721 0.784. 0.893

>60 0.488 0.488 0.501 TABLE 10-3 AFTO Flow Dependent LHGR Multiplier LHGRFAC{F) 20F < FWT DELTAS 55F (Asymmetric Feedwater Heating) (References 2 and 10) Core Flow (% of rated) EOOS Combination 0 I 30 I 33.6 I 70 I 80 I 110 LHGRFAC(F) Multiplier Dual Loop 0.486 I 0.678 I 0.701 I 0.934 I 0.960 I 0.960 100 0.960 0.960 0.960 0.960 0.960 0.960

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report MCPRLIMITS COLR PEACH BOTTOM 2 Rev.11 Page21 of26 The OLMCPRs during asymmetric feedwater temperature operation with a feedwater temperature difference greater than 20 ~F are provided in Table 10-:4. The ARTS-based power-dependent M<;::PR limits for use during AFTO conditions are provided in Table l 0-5. The flow-dependent MCPR limits for AFTO are provided in Table l 0-6. The

  • power and flow-dependent OLMCPR curves were obtained from Reference 2 and were adjusted with a 3% penalty for feed water temperature difference greater than 20 °F as displayed in Table 10-1 as per Reference I 0. PRIPLUOOS

+ TB SOOS and PRIPLUOOS + RPTOOS values were obtained by talcing the most limiting OLM CPR values of the two BOOS conditions, these values are bounding for non-AFTO conditions. No MCPR penalties are required for asymmetric temperature differentials less than or equal to 20 °F. Additionally, no MCPR penalties are required for asymmetric feedwater temperature option while in SLO as previously discussed. TABLEl0-4 AFTO Operating Limit Minimum Critical Power Ratio 20F < FWT DELTA~ 55F (Asymmetric Feedwater Heating) (References 2 and 10) SCRAM Cycle Exposure Time <EOR-2597 ?::EOR-2597 EOOS Combination Option<') 1 MWd/ST MWd/ST BASE B 1.45 1.45 A 1.53 1.53 RP TO OS B 1.45 1.45 A 1.63 1.63 PR/PLUOOS B 1.45 1.45 A 1.53 1.53 TBSOOS B 1.49 1.49 A 1.59 1.59 PR/PLUOOS + TBSOOS B 1.49 1.49 A NIA NIA PR/PLUOOS + RPTOOS B 1.45 1.45 A NIA NIA (1) ~Jhen Tau does not equal 0 or 1, use *linear interpolation.

Exelon Nuclear* Nuclear Fuels P2C22 Core Operating Limits Report TABLE 10-5 COLR PEACH BOTTOM 2 Rev.11 Page22 of26 AFTO Power Dependent MCPR Limit Adjustments And Multipliers MCPR(P) 20F < FWT DELTAS 55F (Asymmetric Feedwater Heating) (References 2 and 10) Core Core Thermal Power (% of rated) EOOS Combination Flow 0 23 <26.7 (%of ~6.7 40 55 65 85 100 rated) Operating Limit MCPR Operating Limit MCPR Multiplier, Kp

S60 2.75 2.75 2.68 1.392 1.317 1.131 Base 1.352

> 60 3.08 3.08 2.91 RPTOOS

S60 2.75 2.75 2.68 1.392 1.352 1.317 1.131

>60 3.08 3.08 2.91 PR/PLUOOS

60 2.75 2.75 2.68 1.392 1.352 1.317 1.210

> 60 3.08 3.08 2.91 TBSOOS

60 3.75 3.75 3.35 1.659. 1.479 1.373 1.155

>60 4.27 4.27 3.89 PRIPLUOOS + TBSOOS

S60 3.75 3.75 3.35 1.659 1.479 1.373 1.210

>60 4.27 4.27 3.89 PR/PLUOOS + RPTOOS

60 2.75 2.75

>60 3.08 3.08 2.68 2.91 1.392 1.352 1.317 1.210 TABLE 10-6 AFTO Flow Dependent MCPR Limits MCPR(F) 20F < FWT DELTA :5 55F (BOC to EOC)(Asymmetric Feedwater Heating) (References 2 and 10) Flow MCPR(F) (%rated) Limit 0.0 1.80 I 30.0 1.62 79.0 1.32 110.0 1.32 1.082 1.000 1.082 1.000 1.147 1.000 1.082 1.000 1.147 1.000 1.147 1.000

E!elon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 11 Page23 of26 MAPLHGR LIMITS An appropriate penalty must be applied to MAPLHGR limits under asymmetric feedwater temperature operation (AFTO) for varying temperature differentials as displayed in Table 10-1 as per Reference 10. No MAPLHGR penalties are required for asymmetric feedwater temperature option while in SLO as previously discussed. TABLEl0-7 AFTO MAPLHGR Reduction Factor (Asymmetric Feedwater Heating) (References 2 and 10) AFTO Reduction Factor 20F < FWT DELTA :s: 55F I 0.960

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 11 Page24 of26 11.0 MODES OF OPERATION The following conditions are supported by the Peach Bottom 2 Cycle 22 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 11-1 provides allowed modes ofoperation with thennal limit sets in the COLR. Table 11-2 provides allowed modes of operation that do not contain explicit thennal limit sets_in the COLR. EOOS Option Base2* 3' 0' 7 Base+ TBSOOS4 Base+ RPTOOS Base + PRIPLUOOS Base+ PRIPLUOOS + TBSOOS Base+ PR/PLUOOS + RPTOOS TABLE 11-1 Modes of Operation (Reference 2 and 12) Supported Scram Speed Option AorB AorB AorB AorB B B TABLE 11-2 Supported Recirc. Loops1 DLOorSLO DLO orSLO DLO orSLO DLOorSLO DLO DLO "Base" EOOS Option Included Conditions (Reference 2) Condition 2 TBVOOS 1 SRVOOS I MSNOOS6 1 TCV/TSVOOS4* 7 1 Operation in SLO not permitted in the MELLLA+ Region as co11trolled by station procedures ~The "Base" condition includes the conditions discussed in Table 11-2. Supported SFTO/AFTO SFTO or AFTO SFTOorAFTO SFTO or AFTO SFTO orAFTO AFT05 AFT05 3 The "Base" condition includes operation with FWHOOS/FFWTR. Operation not permitted in the MELLLA+ Region for reduced feedwater temperature conditions as controlled by station procedures.. 4 l TCV/TSVOOS is valid coincident with the TBSOOS condition, but only at power levels S55% rated thermal power 5 AFTO operation bounds SFTO operation for DLO 6 With 1 MSIVOOS, the "Base" condition is only valid at power levels S66.7% rated thennal power 7 With 1 TCV/TSVOOS, the "Base" condition is only valid at power levels S80% rated thermal power

Exelon Nuclear -Nuclear Fuels P2C22 Core Operating Limits Report 12.0 l\\IBTHODOLOGY COLR PEACH BOTTOM 2 Rev. 11 Page25 of26 The analytical methods used in determining the core operating limits have been previously reviewed and approved by the NRC, specifically those described in the following document: L "General Electric Standard Application for Reactor Fuel", NEDE-24011-P-A-22, November 2015 and U.S. Supplement NEDE-24011-P-A-22-US, November 2015.

13.0 REFERENCES

1. "Technical Specifications for Peach Bottom Atomic Power Station Unit 2", Docket No. 50-277, License No. DPR-44.
2. Global Nuclear Fuel Document "Supplemental Reload Licensing Report for Peach Bottom Unit 2, Reload 21, Cycle 22", GNF

. Document No. 002N6785, Revision 1, September 2016.

3. Global Nuclear Fuel Document "General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A-22, November 2015 and U.S. Supplement NEDE-24011-P-A-22-US, November 2015.
4.

Global Nuclear Fuel Document NEDC-33270P Rev. 6, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GEST AR II)," March, 2016.

5.

General Electric Hitachi Document OOIN2494-RO, "Peach Bottom EPU Evaluation of Feedwater Temperature vs. Reactor Power for Feedwater Temperature Conditions of Nominal Rated, FWHOOS (Nominal -55°F) and FFWTR (Nominal -90°F)", July 2014. This document is searchable in Exelon EDMS under document number "PEAM-EPU-1 Rev. OA."

6.

General Electric Hitachi Document NED0-33720, "Safety Analysis Report for Peach Bottom Atomic Power Station Units 2 & 3 Maximum Extended Load Line Limit Analysis Plus", Revision 0, September 2014.

7.

PECO Calculation PE-0173, "Determination of Total Time Required to Initiate the Trip Signal to the EOC-RPT Circuit Breakers Trip Coils and to Complete the Recirculation Pump Trip", Rev. 1 dated 12/22/98.

8.

General Electric Hitachi Document GEH-0000-0107-7348, "GNF2 Fuel Design Cycle-Independent Analyses For Exelon P,each Bottom Atomic Power Station Units 2 and 3, Revision 6, April 2015. This document is searchable il1 Exelon EDMS under document number "G-080-VC-399 Rev. 3."

9.

PECO Calculatio~ PE-0251, Revision 3, "Provide Allowable Values (AV) and Nominal Trip Setpoints (NTSP) for Various Setpoint Functions of the NUMAC PRNM System" dated 10/11116.

10. General Electric Hitachi Document 001N6733-Rl, "Final Evaluation Report Exelon Nuclear Generating Company LLC, Peach Bottom Units 2 & 3, MELLLA+, Asymmetric Feedwater Temperature Operation for EPU/MELLLA+", Revision 1, September 2014. This document is searchable in Exelon EDMS under document number "PEAM-EPU-68 Rev. l."
11. Global Nuclear Fuel Document 002N6786, "Fuel Bundle Information Report for Peach Bottom Unit 2 Reload 21Cycle22",

Revision 0, September 2016.

12. Ge11eral Electric Hitachi Document 002N8351-R2, "Peach Bottom Units 2 and 3 TRACG Cycle-Independent PROOS &

PLUOOS Analysis Report," dated 5/25/2016.

13. Not Used
14. Exelon TODI ENSAF ID# ES1600008, Rev. 1, "Final Resolved OPL-3 Parameters for Peach Bottom Unit 2 Cycle 22,

June 28, 2016.

Exelon Nuclear - Nuclear Fuels P2C22 Core Operating Limits Report COLR PEACH BOTTOM 2 Rev. 11 Page26 of26 0 120 110* 100 90 so

?

~ 70 3: 60 ~ 1t 50 40 30 20 10 0 0 10 20 APPENDIX A . Power/Flow Operating Map for MELLLA + (Reference 6) Core Flow (Mlb/hr) 30 40 50 60 70 80 90 I 100 110 120 i~~~I!Fiovi*--i;-~~~\\-~h,*---- I -*-*-"-----*-*----*--......... --*-***t**-***-*--l--.-......... :.. -....,, ______.!. ____ _ i-=-i=~~.,.....~==-------1 I i I m I m 1m ciJ t---=-+----';,;:-;:----""="'..,,.._.,*************r**-******:-*******---*r**---**-*--1** E 100~0 f IMELUA+Boundory Ii t----"'F-+-~1""10"".o~-t--==---1********-*-r**--****-****T-*-***-**** !--*--*--** G 110.0 21.3 i H 100.0 21.3 l 3?.4 21,3 J 83.0 100.0 K SS.O 78.8 L ss.o * , 68.4 1 - -r**-*--r-----*--r-**----**-r**--------- ---------- --- ------ 1 1 l f J I 1 ...------L*-***----*---l---**-****-j****-****-***-l---*-* ** IM8.LLA 80U1dary l*-*****+***-*-----*j--****--***+**........... **{][I ** *-------*- j I I I I i l I IITJ I i

  • ----*---r-******-****r***--***-1** -ri--*-*-**1**---*****----r*-*--*-1-**--*t**-***---r*--*-*-*------*----* ***-----*-**-*

. i I I I - -------1----I"" -------**t *---~------- 1-- -***--*r*-----------***-i-**----------1--------

r-------'. -----* ----T-l'.*------~----*-f------1*--**-*---r*---*--+***--- *-*-*- -*--**

I 11 i i i

~~t==r~-{)t~~=~=+:=1:_~::::~'.'ri==-~+=-~+~~+=

I !.. --.... *~ \\ f l t f 4741 4346 3951 3556 3161 2766 2370 1975 1580 l!S5 790 395 a 10 20 30 40 50 60 10 80 90

  • 100 110 120 Core Flow(%)

~ ~* 6..... ;: ~" ,....}}

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