ML16305A189
| ML16305A189 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/28/2016 |
| From: | Massaro M Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML16305A189 (28) | |
Text
Exelon Generation.
TS 5.6.5.d October 28, 2016 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington DC 20555-0001 Peach Bottom Atomic Power Station (PBAPS) Unit 3 Renewed Facility Operating License No. DPR-56 NRC Docket Nos. 50-278
Subject:
Issuance of the Core Operating Limits Report Mid-Cycle Revision for Unit 3 Enclosed is a copy of Revision 11 of the Core Operating Limits Report (COLR) that was recently issued for PBAPS Unit 3. Revisions 10 and 11 of the COLR were recently approved to address removal of Rod Block Monitor Analytical Limits and changes associated with Neutron Flux Analytical Limits. These changes were combined into a single issuance of Revision 11.
The COLR revision is being submitted to the NRC as required by the PBAPS, Unit 3 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: 16-96 Attachment Unit 3 Core Operating Limits Report for Reload 20, Cycle 21, 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 Unit 3 Core Operating Limits Report for Reload 20, Cycle 21, Revision 11
Eulan NvcJur -/'lqdur Fueb COLR PEACH BOTTOM 3 Rev. 11 PJC2 I Cort! Opc1111ng L""ll.! Rrport Page 1 of26 CORE OPERATING LIMITS REPORT FOR PEACH BOTTOM ATOMIC POWER STATION UNIT 3 RELOAD 20, CYCLE 21 PreparedBy: /)~ ~ Date: ( U/6//6 A. Miller Reviewed By: _ __.,,.....;~=-=1.,___ _..:.._.:__-1-- Date:
eactor Engineering n,,;,wodBy <;::t~ 1 Engineering Safety Analysis Date:.
Independent Review By: Date: W.4'//.£ M. Kosciuk Approved By: ~ '/... f'/n "~ Date:~0
(/ J.Mc !ale SoriooQwtllfiod Reviewer: #~ I , 1 N
1l0!:y Date: JO /1 j /b
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Report Page 2 of26 Table of Contents Page 1.0 Tenns and Definitions 5 2.0 General Information 6 3.0 MAPLHGR Limits 7 4.0 MCPRLimits 8 5.0 Linear Heat Generation Rate Limits 12 6.0 Rod Block Monitor Setpoints 14 7.0 Turbine Bypass Valve Parameters 15 8.0 EOC Recirculation Pump Trip (EOC-RPT) Operability 16 9.0 Stability Protection 17 10.0 Asynunetric Feedwater Temperature Operation (AFTO) 19 11.0 Modes of Operation 24 12.0 Methodology 24 13.0 References 25 Appendix A (Power/Flow Operating Map for MELLLA+) 26
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Report Page 3 of26 Revision History Revision Description Revision 9 Revised COLR for MELLLA+
Revision IO Revised to remove RBM Analytical Limits Revision 11 Revised for IR 2724444. Rev. IO was never implemented. Rev bars show revisions from Rev.
9
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Report Page 4 of26 List of Tables Page Table 3-1 MAPLHGR Versus Average Planar Exposure 7 Table 3-2 MAPLHGR Single Loop Operation (SLO) Multiplier 7 Table 4-1 Operating Limit Minimum Critical Power Ratio 9 Table 4-2 Power Dependent MCPR(P) Limit Adjustments and Multipliers 10 Table 4-3 Flow Dependent MCPR Limits MCPR(F) 11 Table 4-4 SLO Flow Dependent MCPR Limits MCPR(F) 11 Table 5-1 Linear Heat Generation Rate Limits - U02 rods 12 Table 5-2 Linear Heat Generation Rate Limits - Gad rods 12 Table 5-3 Power Dependent LHGR Multiplier LHGRFAC(P) 13 Table 5-4 Flow Dependent LHGR Multiplier LHGRF AC(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 Nonna! Feedwater Temperature 18 Table 9-3 Manual BSP Endpoints for Reduced Feedwater Temperature 18 Table 10-1 AFTO Thermal Limit Penalties 19 Table 10-2 AFTO Power Dependent LHGR Multiplier LHGRF AC(P) 20F < FWT DELTA :S 55F 20 Table 10-3 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 20F < FWT DELTA :S 55F 20 Table 10-4 AFTO Operating Limit Minimum Critical Power Ratio 20F < FWT DELTA :S 55F 21 Table 10-5 AFTO Power Dependent MCPR Limit Adjustments and Multipliers 22 MCPR(P) 20F < FWT DELTA :S 55F Table 10-6 AFTO Flow Dependent MCPR Limits MCPR(F) 20F < FWT DELTA :S 55F 22 Table 10-7 AFTO MAPLHGR Reduction Factor 23 Table 11-1 Modes of Operation 24 Table 11-2 Additional Equipment Out of Service Modes of Operation 24
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 l Core Operating Limits Report Page 5 of26 1.0 Terms and Definitions ABSP Automatic Backup Stability Protection AFTO Asymmetric Feedwater Temperature Operation AFTOLFWH Asymmetric Feedwater Temperature Operation Loss-of-Feedwater Heating APRM Average Power Range Monitor ARTS APRM and RBM Technical Specification Analysis BASE Defines two (2) loop operation with at least seven turbine bypass valves in service and the reactor recirculation pump trip system in service.
BOC Beginning Of Cycle BSP Backup Stability Protection DSS-CD Detect and Suppress Solution Confirmation Density DTSP Rod Block Monitor Downscale Trip Setpoint EOC End of Cycle EOOS Equipment Out of Service. An analyzed option that assumes certain equipment to be non-operational EOR End of Rated. The cycle exposure at which reactor power is equal to l 00% (3951 MW th) with recirculation system flow equal to l 00%, all control rods fully withdrawn, all feedwater heating in service and equilibrium Xenon.
FFWTR Final Feedwater Temperature Reduction FWHOOS Feedwater Heaters Out of Service FWT Feedwater Temperature HFCL High Flow Control Line HTSP Rod Block Monitor High Trip Setpoint ICF Increased Core Flow ITSP Rod Block Monitor Intennediate Trip Setpoint LHGR Linear Heat Generation Rate LHGRFAC(F) ARTS LHGR thennal limit flow dependent adjustments and multipliers LHGRFAC(P) ARTS LHGR thennal lim.it power dependent adjustments and multipliers LTSP Rod Block Monitor Low Trip Setpoint MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPR(F) ARTS MCPR thermal limit flow dependent adjustments and multipliers MCPR(P) ARTS MCPR thennal limit power dependent adjustments and multipliers MELL LA Maximum Extended Load Line Limit Analysis MELLLA+ Maximum Extended Load Line Limit Analysis Plus MSIVOOS Main Steam Isolation Valve Out of Service NCL Natural Circulation Line OLM CPR Operating Limit Minimum Critical Power Ratio PLUOOS Power Load Unbalance Out of Service PROOS Pressure Regulator Out of Service RDF Rated Drive Flow RPTOOS Recirculation Pump Trip Out of Service RTP Rated Thennal Power RWE Rod Withdrawal Error SLM CPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation TB SOOS Turbine Bypass Valves Out of Service TCV/TSVOOS Turbine Control Valve/Turbine Stop Valve Out of Service
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 l Core Operating Limits Report Page 6 of26 2.0 General Information This report provides the following cycle-specific parameter limits for Peach Bottom Atomic Power Station Unit 3 CYCLE 21 (RELOAD 20):
- Maximum Average Planar Linear Heat Generation Rate (MAPLHGR)
- Linear Heat Generation Rate (LHGR)
- Turbine Bypass Valve Parameters
- Stability Protection Setpoints
- Asymmetric Feedwater Temperature Operation (AFTO) thennal limit penalties These values have been detennined 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 pennitted in the MELLLA+ Region as controlled by station procedures. For the MELLLA+ Region, a specific definition ofFWHOOS is provided in Facility Operating License (FOL) Section 2.C(l6).
This report provides cycle-specific Operating Limit MCPR, LHGR, MAPLHGR them1al limits, and related information for the following conditions:
- All points in the operating region of the power/flow map including MELLLA+ Region down to 83%
of rated core flow during full power (3951 MWt) operation (Appendix A)
- Increased Core Flow (ICF}, up to 110% of rated core flow
- End-of-Cycle Power Coastdown to a minimum power level of 40%
- Final Feedwater Temperature Reduction (FFWTR) between End-of-Rated (EOR) and End-of-Cycle (EOC) to 90° F temperature reduction (4th and 5th stage FWHOOS)
- Asynunetric Feedwater Temperature Operation (AFTO)
ARTS provides for power and flow-dependent thermal limit adjustments and multipliers that allow for a more reliable administration of the MCPR and LHGR thermal limits. The OLMCPR is detennined 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 function of thermal 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 performed in accordance with Exelon Nuclear procedures. This report is provided to the NRC in accordance with Technical Specification 5.6.5 of Reference l and contains all thermal limit parameters related to the implementation of the ARTS Improvement Program and MELLLA+ for Peach Bottom Unit 3 Cycle 21.
The "BASE" thermal limit values shown in tables are for normal two loop operation with at least the minimum number of htrbine bypass valves in service per Section 7.0, the reactor recirculation pump trip system in service, the power load unbalance device in service, and both pressure regulators in service.
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Repon Page 7 of26 3.0 MAPLHGR LIMITS 3.1 Technical Specification Section 3.2. l, 3.3.4.2, 3.4. l and 3.7.6 3.2 Description 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. The MAPLHGR tables are used when hand calculations are required. 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 l 0.
TABLE 3-1 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 COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Report Page 8 of26 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 The Operating Limit MCPR (OLMCPR) for GNF2 fuel is provided in Tables 4-l 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 performance 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 OLMCPR value if Tau is between 0.0 (Tau Option B) and 1.0 (Tau Option A).
Separate OLMCPR values are presented in Table 4- l 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 In-Service (per section 8.0), PLU/PR In-Service, and maximum FFWTR of 90 °F
- TBS In-Service (per section 7.0), RPT In-Service (per section 8.0), PLU/PR Out-of-Service, and maximum FFWTR of90°F
- TBS In-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 reduction 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 symmetric feedwater temperature operation and Table 4-4 is valid for single loop operating conditions with symmetric feedwater temperature operation. The impact of AFTO on MCPR is addressed in Section l 0. 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 COLR PEACH BOTTOM 3 Rev. 11 P3C2 l Core Operating Limits Report Page 9 of26 TABLE4-1 Operating Limit Minimum Critical Power Ratio (Reference 2)
SCRAM Cycle Exposure Time < EOR-2523 _::: EOR-2523 EOOS Combination Option'll MWd/ST MWd/ST B 1.38 1.41 BASE A l.45 l.49 B l.43 l.43 BASE SL0<2 i A l.45 l.49 B 1.42 1.46 RPTOOS A l.59 l.63 B l.43 l.46 RPTOOS SL0<21 A 1.59 1.63 B 1.38 1.41 PR/PLUOOS A 1.45 1.49 B 1.43 1.43 PR/PLUOOS SL0< 2> A 1.45 1.49 B 1.42 1.43 TB SOOS A 1.49 1.52 B l.43 l.43 TB SOOS SLO <2> A 1.49 1.52 (1) When Tau does not equal O or 1, use linear interpolation.
(2) For single-loop operation, the MCPR operating limit is the same as the analyzed limiting two loop value. However a minimum value of 1.43 is required to obtain an OLMCPR limit set by the Single Loop Operation Recirculation Pump Seizure Event (Reference 2).
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Report Page 10 of26 TABLE 4-2 Power Dependent MCPR(P) Limit Adjustments and Multipliers (Symmetric Feedwater Heating)
(Reference 2)
Core Core Thermal Power (% of rated)
Flow EOOS Combination 0 23 <26.7 ~26.7 40 55 65 85 100
(% 01 rated Operating Limit MCPR Operating Limit MCPR Multiplier, Kp S60 2.67 2.67 2.60 Base 1.352 1.352 1.317 1.131 1.082 1.000
> 60 2.99 2.99 2.83 S60 2.67 2.67 2.60 Base SLO 1.352 1.352 1.317 1.131 1.082 1.000
> 60 2.99 2.99 2.83
.::: 60 2.67 2.67 2.60 RPTOOS 1.352 1.352 1.317 1.131 1.082 1.000
> 60 2.99 2.99 2.83
.::: 60 2.67 2.67 2.60 RPTOOS SLO 1.352 1.352 1.317 1.131 1.082 1.000
> 60 2.99 2.99 2.83
~ 60 2.67 2.67 2.60 PR/PLUOOS 1.392 1.352 1.317 1.210 1.147 1.000
> 60 2.99 2.99 2.83
.::: 60 2.67 2.67 2.60 PR/PLUOOSSLO 1.392 1.352 1.317 1.210 1.147 1.000
> 60 2.99 2.99 2.83
~ 60 3.64 3.64 3.25 TB SOOS 1.659 1.479 1.373 1.155 1.082 1.000
> 60 4.15 4.15 3.78 S 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 COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Report Page 11 of26 TABLE4-3 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)
(Reference 2) re Flow MCPR(F) rated) Limit 0.0 1.75 30.0 1.57 79.0 1.28 110.0 1.28
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Report Page 12 of26 5.0 LINEAR HEAT GENERATION RA TE 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 of recirculation loops in operation. The SLO 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 I 0. For PR/PLUOOS + TBSOOS and PR/PLUOOS + RPTOOS conditions, the limits are listed in Section I 0, 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.
TABLE 5-1 Linear Heat Generation Rate Limits - U02 rods (References 4 and 11)
Fuel Type LHGRLimit GNF2 See Appendix B of Reference 4 TABLE 5-2 Linear Heat Generation Rate Limits - Gad rods (References 4 and 11)
Fuel Type LHGR Limit GNF2 See Appendix B of Reference 4
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Report Page 13 of26 TABLE 5-3 Power Dependent LHGR Multiplier LHGRFAC(P)
(Symmetric Feedwater Heating)
(Reference 2)
Core Thermal Power (% of rated)
Core Flow EOOS Combination 0 23 <26.7 ~26.7 40 55 65 85 100
(%of rated)
LHGRFAC(P) Multiplier
- 60 0.508 0.508 0.522 Base 0.748 0.756 0.771 0.817 0.959 1.000
> 60 0.508 0.508 0.522
- 60 0.508 0.508 0.522 Base SLO 0.748 0.756 0.771 0.817 0.959 1.000
> 60 0.508 0.508 0.522
- 60 0.508 0.508 0.522 RPTOOS 0.748 0.756 0.771 0.817 0.959 1.000
> 60 0.508 0.508 0.522
- 560 0.508 0.508 0.522 RPTOOS SLO 0.748 0.756 0.771 0.817 0.959 1.000
> 60 0.508 0.508 0.522
- 560 0.508 0.508 0.522 PR/PLUOOS 0.620 0.696 0.751 0.817 0.959 1.000
> 60 0.508 0.508 0.522
- 60 0.508 0.508 0.522 PR/PLUOOS SLO 0.620 0.696 0.751 0.817 0.959 1.000
> 60 0.508 0.508 0.522
- 60 0.397 0.397 0.442 TB SOOS 0.635 0.655 0.714 0.817 0.930 1.000
> 60 0.397 0.397 0.417
- 60 0.397 0.397 0.442 TBSOOS SLO 0.635 0.655 0.714 0.817 0.930 1.000
> 60 0.397 0.397 0.417 TABLE 5-4 Flow Dependent LHGR Multiplier LHGRFAC(F)
(Symmetric Feedwater Heating)
(Reference 2)
Core Flow (% of rated)
EOOS Combination 0 30 33 .6 70 80 I IO LHGRFAC(F) Multiplier Dual Loop 0.506 0.706 0.730 0.973 1.000 1.000 Single Loop 0.506 0.706 0.730 0.730 0.730 0.730
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Report 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. The values correspond to the OLMCPR values provide in Table 4-1.
TABLE 6-1 Rod Block Monitor Setpoints (References 2 and 9)
Power Level Allowable Value<1l MCPRLimit LTSP 118.2% < 1.70 ( l )
< 1.40 t3)
ITSP 113.4% < l.7o m
< 1.40 t3l HTSP 108.4% < l.7o m
< 1.40 ( J)
INOP NIA < 1.70 ( ~}
< 1.40 (J)
(1) These setpoints (with RBM filter time c o nst a nt between 0.1 seconds and 0.55 sec o nds) 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 CO LR 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 MCPR 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 COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Repon 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 (TBSOOS) must be used. Additionally, the OLMCPR for TBSOOS must be applied. Table 7-1 includes the Turbine Bypass Valve response time parameters. The minimum number of bypass 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< '> 0.10 sec Maximum time after initial turbine inlet valve movement<'> for bypass valve position to reach 80% of full flow (includes the 0.30 sec above delay time)
(I) First movement of any TSV Qr any TCV Qr generation of the turbine bypass valve flow signal (whichever occurs first)
TABLE 7-2 Minimum Required Bypass Valves To Maintain System Operability (Reference 14)
Reactor Power No. of Valves in Service P2'.23% 7
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Report 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 EOC 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 EOC Recirculation Pump Trip Out Of Service (RPTOOS) must be used.
Additionally, the OLMCPR for RPTOOS must be applied. Table 8-1 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 fi"om when the turbine valves (turbine control valve or 0.175 sec turbine stop valve) start to close until complete arc suppression ofthe EOC-RPT circuit breakers as described in Reference 7.
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Report Page 17 of26 9.0 ST ABILITY PROTECTION 9.1 Technical Specification Section 3.3.1.1, Table 3.3.1.1-1Function2 .f, Section 5.6.5 9.2 Description Per Reference 2, the Cycle 21 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 Normal Feedwater Temperature and Reduced Feedwater Temperature are provided in Tables 9-2 and Table 9-3 .
TABLE 9-1 Automatic BSP Setpoints for the Scram Region (Reference 2)
Parameter Symbol Value Slope of ABSP APRM flow-111Trip 1.39 biased trip linear segment.
ABSP APRM flow-biased trip setpoint power intercept.
Constant Power Line for Trip Pesr-Trir 39.9 %RTP from zero Drive Flow to Flow Breakpoint value.
ABSP APRM flow-biased trip setpoint drive flow intercept. Wesr-Trip 46.5 %RDF Constant Flow Line for Trip.
Flow Breakpoint value Wesr-Brcok 20.0 %RDF
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Report Page 18 of26 TABLE 9-2°>
Manual BSP Endpoints for Normal Feedwater Temperature (Reference 2)
Endpoint Power(%) Flow(%) Definition Al 76.7 52.2 Scram Region Boundary, MELLLA+ Extension Bl 39 .9 31.0 Scram Region Boundary, NCL A2 64.5 50.0 Controlled Entry Region Boundary, HFCL B2 28. 1 30.1 Controlled Entry Region Boundary, NCL Nole: 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 65.7 51.5 Scram Region Boundary, HFCL Bl 34.9 30.7 Scram Region Boundary, NCL A2 67.3 53 .5 Controlled Entry Region Boundary, HFCL B2 28 .l 30.l Controlled Entry Region Boundary, NCL Note: The BSP Boundary for Normal and Reduced Feedwater Temperature is defined by the MELLLA boundary line, per Reference 2.
(1) Station may elect to place additional administrative margin on the endpoints provided in Table 9-2 and Table 9-3 .
Exelon Nuclear - Nuclear fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 l Core Operating Limits Report Page 19 of26 10.0 ASYMMETRIC FEEDWATER TEMPERATURE OPERATION (AFTO)
Asymmetric feedwater 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. Thermal limit values for all conditions and events are impacted by these errors excluding SLO conditions. The P3C2 I COLR Rev. 8 was the first COLR to no longer require implementation of SLO AFTO penalty files for this unit. 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 I 0-1 will be implemented when the threshold asymmetry temperature (temperature above which a penalty is required) is exceeded. This will minimize the number of AFTO thennal limit tables in the COLR and core monitoring system.
TABLE 10-1 AFTO Thermal Limit Penalties (Asymmetric Feedwater Heating)
(Reference 10)
MF LC PR MFLPD/MAPRAT 40F < FWT DELTA~ 55F 3% 4%
30F < FWT DELTA~ 40F 2% 3%
20F < FWT DELTA~ 30F 2% 2%
OF < FWT DELTA ~ 20F No Penalty No Penalty LHGRLIMITS 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 PRIPLUOOS + RPTOOS values were obtained by taking the most limiting OLMCPR 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 I 0-1 are applied to the thermal limits. Additionally, no LHGR penalties are required for asymmetric feedwater temperature option while in SLO as previously discussed.
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 l Core Operating Limits Report Page 20 of26 TABLE 10-2 AFTO Power Dependent LHGR Multiplier LHGRFAC(P) 20F < FWT DELTA :S 55F (Asymmetric Feedwater Heating)
(References 2 and 10)
Core Core Thermal Power (% of rated)
Flow 0 23 <26.7 2::26.7 40 55 65 85 100 EOOS Combination
(%of rated) LHGRFAC(P) Multiplier
- 60 0.488 0.488 0.501 Base 0.718 0.726 0.740 0.784 0.921 0.960
> 60 0.488 0.488 0.501
- 60 0.488 0.488 0.501 RPTOOS 0.718 0.726 0.740 0.784 0.921 0.960
> 60 0.488 0.488 0.501
- 60 0.488 0.488 0.501 PR/PLUOOS 0.595 0.668 0.721 0.784 0.921 0.960
>60 0.488 0.488 0.501
- 60 0.381 0.381 0.424 TB SOOS 0.610 0.629 0.685 0.784 0.893 0.960
> 60 0.381 0.381 0.400
- 60 0.381 0.381 0.424 PR/PLUOOS + TBSOOS 0.595 0.629 0.685 0.784 0.893 0.960
> 60 0.381 0.381 0.400
- 60 0.488 0.488 0.501 PR/PLUOOS + RPTOOS 0.595 0.668 0.721 0.784 0.921 0.960
> 60 0.488 0.488 0.501 TABLE 10-3 AFTO Flow Dependent LHGR Multiplier LHGRFAC(F) 20F < FWT DELTA :S 55F (Asymmetric Feedwater Heating)
(References 2 and 10)
Core Flow (% of rated)
EOOS Combination 0 I 30 I 33 .60 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
Exelon Nuclear - Nuclear fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Report Page 21 of26 MCPRLIMITS 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 MCPR limits for use during AFTO conditions are provided in Table I 0-5 . The flow-dependent MCPR limits for AFTO are provided in Table I 0-6. The power and flow-dependent OLMCPR curves were obtained from Reference 2 and were adjusted with a 3% penalty for feedwater temperature difference greater than 20 °F as displayed in Table 10-1 as per Reference 10. PR/PLUOOS + TBSOOS and PR/PLUOOS + RPTOOS values were obtained by taking the most limiting OLMCPR values of the two EOOS 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.
TABLE 10-4 AFTO Operating Limit Minimum Critical Power Ratio 20F < FWT DELTA :5 55F (Asymmetric Feedwater Heating)
(References 2 and 10)
SCRAM Cycle Exposure Time < EOR-2523 ~ EOR-2523 EOOS Combination Option MWdlST MWdlST B 1.42 1.45 BASE A 1.49 1.53 B 1.46 1.50 RPTOOS A 1.64 1.68 B 1.42 1.45 PRIPLUOOS A 1.49 1.53 B 1.46 1.47 TB SOOS A 1.53 1.57 B 1.46 1.47 PR/PLUOOS + TBSOOS A NIA NIA B 1.46 1.50 PR/PLUOOS + RPTOOS A NIA NIA (1) When Tau does not equal O or 1, use linear interpolation.
Exelon Nuclear- Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Report Page 22 of26 TABLE 10-5 AFTO Power Dependent MCPR Limit Adjustments And Multipliers MCPR(P) 20F < FWT DELTA 5 55F (Asymmetric Feedwater Heating)
(References 2 and 10)
Core Core Thermal Power (% of rated)
Flow 0 23 <26.7 2::26.7 40 55 65 85 100 EOOS Combination
(%of rated) Operating Limit MCPR Operating Limit MCPR Multiplier, Kp
~ 60 2.75 2.75 2.68 Base 1.352 1.352 1.317 1.131 1.082 1.000
> 60 3.08 3.08 2.91
~ 60 2.75 2.75 2.68 RPTOOS 1.352 1.352 l.317 1.131 1.082 1.000
> 60 3.08 3.08 2.91
~ 60 2.75 2.75 2.68 PR/PLUOOS 1.392 1.352 1.317 1.210 1.147 1.000
> 60 3.08 3.08 2.91
~ 60 3.75 3.75 3.35 TB SOOS 1.659 1.479 1.373 1.155 1.082 1.000
> 60 4.27 4.27 3.89
~ 60 3.75 3.75 3.35 PR/PLUOOS + TBSOOS 1.659 1.479 1.373 1.210 1.147 1.000
> 60 4.27 4.27 3.89
~ 60 2.75 2.75 2.68 PR/PLUOOS + RPTOOS 1.392 1.352 1.317 1.210 1.147 1.000
> 60 3.08 3.08 2.91 TABLE 10-6 AFTO Flow Dependent MCPR Limits MCPR(F) 20F < FWT DELTA$ 55F (BOC to EOC)(Asymmetric Feedwater Heating)
(References 2 and 10)
Flow MCPR(F)
(%rated) Limit 0.0 1.80 30.0 1.62 79.0 1.32 110.0 1.32
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 l Core Operating Limits Report Page 23 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 I 0-1 as per Reference I 0. No
'MAPLHGR penalties are required for asymmetric feedwater temperature option while in SLO as previously discussed.
TABLE 10-7 AFTO MAPLHGR Reduction Factor (Asymmetric Feedwater Heating)
(References 2 and 10)
AFTO Reduction Factor 20F<FWTDELTA :S 55F I 0.960
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Report Page 24 of26 11.0 MODES OF OPERATION TABLE 11-1 Modes of Operation (Reference 2)
Supported Operating EOOS Options 1 Ree:ion 2 Base, Option A or B Yes Base SLO, Option A or B Yes 3 TBSOOS, Option A or B Yes TBSOOS SLO, Option A or B Yes 3 RPTOOS, Option A or B Yes RPTOOS SLO, Option A or B Yes 3 PLUOOS, Option A or B Yes PLUOOS SLO, Option A or B Yes 3 PROOS, Option A or B Yes PROOS SLO, Option A or B Yes 3 PR/PLUOOS and TBSOOS, Option B Yes PR/PLUOOS and RPTOOS, Option B Yes TBSOOS and RPTOOS, Option A or B No TBSOOS and RPTOOS SLO, Option A or B No TABLE 11-2 Additional Equipment Out of Service Modes of Operation EOOS TCV/TSVOOS (controlled via station procedures)
MSIVOOS (controlled via station procedures)
AFTO LFWH (controlled via station procedures) 12.0 METHODOLOGY The analytical methods used in detem1ining the core operating limits have been previously reviewed and approved by the NRC, specifically those described in the following documents :
I. "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.
Modes of operation with thermal limit sets in the COLR
' Operating Region refers to operation on the Power to Flow map with or without FFWTR or AFTO.
Operation not permited in the MELLLA+ Region for Reduced Feedwater Temperature conditions as
~ontrolled by station procedures.
Operation in SLO not permitted in the MELLLA+ Region as controlled by station procedures.
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 I Core Operating Limits Report Page 25 of26
13.0 REFERENCES
- 1. "Technical Specifications for Peach Bottom Atomic Power Station Unit 3," Docket No. 50-278, Appendix A to License No. DPR-56.
- 2. Global Nuclear Fuel Document "Supplemental Reload Licensing Report for Peach Bottom Unit 3, Reload 20, Cycle 21 Extended Power Uprate (EPU)/Maximum Extended Load Line Limit Analysis Plus (MELLLA+)," GNF Document No. 001N3881, Revision 0, July 2015.
- 3. Global Nuclear Fuel Document "General Electric Standard Application for Reactor Fuel," NEDE-24011-P-A-22, November 2015 and U.S. Supplement NEDE-240 l l-P-A-22-US, November 2015.
- 4. Global Nuclear Fuel Document NEDC-33270P Rev. 5, "GNF2 Advantage Generic Compliance with NEDE-24011-P-A (GEST AR II)," May 2013.
- 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. OOA."
- 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. I dated 12/22/98.
- 8. Not Used.
- 9. PECO Calculation PE-0251, Revision 3, "PRNMS Setpoint Calculation".
- 10. General Electric Hitachi Document 00 IN6733-R l , "Final Evaluation Report Exelon Nuclear Generating Company LLC, Peach Bottom Units 2 & 3, MELLLA , Asymmetric Feedwater Temperature Operation for EPU/MELLLA+," Revision I, September 2014. This document is searchable in Exelon EDMS under document number "PEAM-EPU-68 Rev. I."
11 . Global Nuclear Fuel Document 002N8938, Revision 0, "Fuel Bundle Infonnation Report for Peach Bottom Unit 3 Reload 20 Cycle 21 Extended Power Uprate (EPU)/Maximum Extended Load Line Limit Analysis Plus (MELLLA+) and Extended Power Uprate (EPU)/Maximum Extended Load Line Limit Analysis (MELLLA)," July 2015.
- 12. Not Used 13 . Not Used
- 14. Exelon TODI ENSAF ID# ES150000l, Rev. 0, "Final Resolved OPL-3 Parameters for Peach Bottom Unit 3 Cycle 21 : EPU/MELLLA+," February 17, 2015 .
Exelon Nuclear - Nuclear Fuels COLR PEACH BOTTOM 3 Rev. 11 P3C2 l Core Operating Limits Report Page 26 of26 APPENDIX A Power/Flow Operating Map for MELLLA+
(Reference 6)
Core Flow (Mlb/hr) 0 10 20 30 -10 50 60 70 so 90 100 110 120 l'.!O -H 1-~---'Poln '-=""ts"-"'of;..;I;;;t n;;.:erest
l't. Core F1nw <,;, Fower'% 100'.; Core Flow = 102 5 Mbthr 110 !CF lllcreaoed Core Flow Recion I-13-16 A Natural Circulation B 30,o Minimum Pum S eed [ ] ] [ ] ] ((]
100 c 38.o I 54.9 90 -
0 E
99.0 100.0 lCO.O 1~0.Q IMELLL:..+ Boundary I t""3556 W"7~-
F HO 0 100.Q G 110.0 21.3 H 100.0 21.3 r6!
80 37.4 UJ~
21-3 83.0 ICO.O 55 0 78.8
? 70 55.0 68.~ T66
.. ~ ~
t.
61) l '.!j70
~
"i
- i::
50 11975 t.
-10 cbI 11580 30 11185 w 1790
,;ITJ lcavitaUon Tflterlo6 I m 10 395 0
0 10 20
~.
30 -10 50 60 0 so 90 100 110 l~O 0
Core flow(%)